Requirements for Expanded Definition of Byproduct Material, 55864-55937 [07-4735]
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10 CFR Parts 20, 30, 31, 32, 33, 35, 50,
61, 62, 72, 110, 150, 170, and 171
RIN 3150–AH84
Requirements for Expanded Definition
of Byproduct Material
Nuclear Regulatory
Commission.
ACTION: Final rule.
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AGENCY:
SUMMARY: The Nuclear Regulatory
Commission (NRC) is amending its
regulations to include jurisdiction over
discrete sources of radium-226,
accelerator-produced radioactive
materials, and discrete sources of
naturally occurring radioactive material,
as required by the Energy Policy Act of
2005 (EPAct), which was signed into
law on August 8, 2005. The EPAct
expanded the Atomic Energy Act of
1954 definition of Byproduct material to
include any discrete source of radium226, any material made radioactive by
use of a particle accelerator, and any
discrete source of naturally occurring
radioactive material, other than source
material, that the Commission, in
consultation with other Federal officials
named in the EPAct, determines would
pose a similar threat to the public health
and safety or the common defense and
security as a discrete source of radium226, that are extracted or converted after
extraction for use for a commercial,
medical, or research activity. In so
doing, these materials were placed
under the NRC’s regulatory authority.
The EPAct also mandated that the
Commission, after consultation with the
States and other stakeholders, issue
final regulations establishing
requirements that the Commission
determines necessary under the EPAct.
This rulemaking effort has been
undertaken in response to that mandate
and includes significant contributions
from many States that have regulated
the naturally occurring and acceleratorproduced radioactive material, the
Organization of Agreement States, Inc.,
the Conference of Radiation Control
Program Directors, Inc. (CRCPD), and
other stakeholders. In addition, this
final rule was informed and guided by
the CRCPD’s applicable Suggested State
Regulations for the Control of Radiation.
Licensees, individuals, and other
entities who are engaged in activities
involving the newly defined byproduct
material in both Agreement States and
non-Agreement States and United States
Territories will be affected by this
rulemaking.
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Effective Date: This final rule is
effective on November 30, 2007.
FOR FURTHER INFORMATION CONTACT:
Lydia Chang, Office of Federal and State
Materials and Environmental
Management Programs, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone (301) 415–
6319, e-mail lwc1@nrc.gov; or Catherine
R. Mattsen, Office of Federal and State
Materials and Environmental
Management Programs, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone (301) 415–
6264, e-mail crm@nrc.gov.
SUPPLEMENTARY INFORMATION:
DATES:
NUCLEAR REGULATORY
COMMISSION
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I. Background
II. Discussion
A. The New, Expanded Definition of
Byproduct Material
B. The NRC’s Regulatory Approach
C. Changes to Existing NRC Regulations to
Accommodate the New Byproduct
Material
D. License Application and Annual Fees
E. Implementation Strategy
III. Summary and Analysis of Public
Comments on the Proposed Rule
IV. Section-by-Section Analysis of Final
Revisions
V. Criminal Penalties
VI. Agreement State Compatibility
VII. Voluntary Consensus Standards
VIII. Environmental Assessment and Finding
of No Significant Environmental Impact:
Availability
IX. Paperwork Reduction Act Statement
X. Regulatory Analysis
XI. Regulatory Flexibility Certification
XII. Backfit Analysis
XIII. Congressional Review Act
I. Background
The Energy Policy Act of 2005
On August 8, 2005, the President
signed into law the EPAct. Among other
provisions, Section 651(e) of the EPAct
expanded the definition of Byproduct
material as defined in Section 11e. of
the Atomic Energy Act of 1954 (AEA),
placing additional byproduct material
under the NRC’s jurisdiction, and
required the Commission to provide a
regulatory framework for licensing and
regulating this additional byproduct
material.
Specifically, Section 651(e) of the
EPAct expanded the definition of
Byproduct material by: (1) Adding any
discrete source of radium-226 that is
produced, extracted, or converted after
extraction, before, on, or after the date
of enactment of the EPAct for use for a
commercial, medical, or research
activity; or any material that has been
made radioactive by use of a particle
accelerator and is produced, extracted,
or converted after extraction, before, on,
or after the date of enactment of the
EPAct for use for a commercial,
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medical, or research activity (Section
11e.(3) of the AEA); and (2) adding any
discrete source of naturally occurring
radioactive material, other than source
material, that the Commission, in
consultation with the Administrator of
the Environmental Protection Agency
(EPA), the Secretary of the Department
of Energy (DOE), the Secretary of the
Department of Homeland Security
(DHS), and the head of any other
appropriate Federal agency, determines
would pose a threat similar to the threat
posed by a discrete source of radium226 to the public health and safety or
the common defense and security; and
is extracted or converted after extraction
before, on, or after the date of enactment
of the EPAct for use in a commercial,
medical, or research activity (Section
11e.(4) of the AEA).
Although Section 651(e) of the EPAct
became effective on August 8, 2005, the
NRC did not have regulations in place
that would specifically apply to this
newly covered byproduct material
(hereafter referred to as NARM). The
EPAct also allowed the NRC to issue
waivers to States and other entities
while developing final regulations for
NARM. A waiver was issued on August
31, 2005 (70 FR 51581).
Previous Regulatory Structures for
NARM
The AEA authorizes the States to
assume regulatory control of certain
radioactive materials provided the State
has an adequate program to protect the
public health and safety and is
compatible with the NRC’s program for
regulation of these materials and enters
into an agreement with the NRC. As
authorized by Section 274b of the AEA,
34 States have assumed responsibility
for regulating certain activities related to
radioactive material by entering into
agreements with the NRC. The activities
regulated by these ‘‘Agreement States’’
include the use of byproduct material,
source material, and special nuclear
material. Each Agreement State issues
licenses to persons who use these
materials in that State except for DOE,
other Government agencies, and
Federally recognized Indian Tribes. The
NRC issues licenses to persons using
these materials in non-Agreement
States.
Before enactment of the EPAct, the
NRC did not have authority over NARM
or regulations for this type of material.
Although the NRC has not regulated
NARM in the past, all 34 Agreement
States and certain non-Agreement States
have regulatory programs for NARM.
The NRC’s regulations did require
licensees to account for dose
contributed from NARM, as well as dose
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contributed from other byproduct,
source, or special nuclear material,
because the definition of Occupational
dose encompasses both licensed
material and nonlicensed material such
as NARM sources at a licensed facility.
In addition, the NRC requires in its
radiological criteria for license
termination that licensees consider
other nondiscrete sources, including
radium, during decommissioning
activities at sites contaminated with
source material, such as rare-earth
processing facilities.
Currently, there are 16 nonAgreement States plus United States
(U.S.) Territories. Although most nonAgreement States and U.S. Territories
have some type of programs for NARM,
the regulatory structures vary greatly.
Certain non-Agreement States have
established a licensing structure for
regulating their NARM users. As such,
the regulatory structure could parallel
the NRC regulations issued in Title 10
of the Code of Federal Regulations (10
CFR) applicable to the current materials
program, or it could parallel the
Suggested State Regulations for the
Control of Radiation (SSRs) developed
by the CRCPD. Other non-Agreement
States or U.S. Territories have elected to
use registration as their regulatory
structure for managing the NARM users.
Some States register facilities; others
register both facilities and devices.
Some States use registration information
to conduct inspections; others use
registration to identify facility locations
for security purposes. In general, there
is limited regulatory oversight where
registration is used in non-Agreement
States. It was, in part, due to this lack
of national consistency, that the EPAct
placed these materials under the NRC’s
jurisdiction.
Agreement States have regulated
NARM use for many decades in a fairly
uniform and consistent manner. The
Agreement States have accomplished
this by using the same standards to
regulate NARM as those used to regulate
other byproduct, source, and special
nuclear material under the NRC’s
authority. In many respects, regulations
applicable to NARM adopted by the
Agreement States are compatible with
the NRC’s regulations for the current
materials program, or parallel the
CRCPD’s SSRs.
Although Agreement States do have
some provisions specifically for NARM,
in general, the regulatory structure used
by Agreement States does not
distinguish between NARM and other
radioactive material. NARM users in the
Agreement States are expected to
implement all aspects of standards for
their radiation protection programs with
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respect to NARM, including those
aspects relating to receipt, possession,
use, storage, transfer, transportation,
and disposal of NARM. This regulatory
structure also subjects NARM users in
the Agreement States to the same
licensing, inspection, and enforcement
policies as those using other byproduct,
source, or special nuclear materials. In
addition, this regulatory structure
allows for both specific and general
licensing of various NARM products,
the distribution of certain NARM items
to persons exempt from regulation and,
in most cases, includes provisions to
review and approve proposals for sealed
sources and devices containing NARM.
The Agreement States have regulated
a vast array of NARM produced for
medical, industrial, research and
development, commercial, and
consumer purposes. In many Agreement
States, this regulatory structure also
captures some types of nondiscrete
sources found in the oil and gas
industry or mining industry; moreover,
it captures inadvertently produced
activation products from the use of
proton beams for medical radiation
therapy. However, the regulation of
these nondiscrete sources and activation
products varies from Agreement State to
Agreement State.
Other Federal Agencies’ Regulatory
Authority Over NARM
Although the States had the primary
responsibility for regulating the use of
NARM before the passage of the EPAct,
certain Federal regulations continue to
apply under some circumstances, such
as environmental protection, workplace
safety, drug safety, transportation, and
disposal. With the passage of the EPAct,
the NRC will have primary
responsibility for radiation safety and in
regulating the use of these materials in
cooperation with the States, with the
exception of those activities that are
self-regulated by the DOE.
Other Federal agencies have
regulations or have established
programs for self-regulating certain
activities involving NARM. The
Department of Transportation (DOT)
regulates interstate transport of NARM.
In cooperation with DOT, the NRC
approves Type B packages through
regulations in 10 CFR Part 71. The EPA
has established controls for certain
NARM through several authorities,
including the Clean Air Act, the Safe
Drinking Water Act, the Toxic
Substances Control Act, the Resource
Conservation and Recovery Act, and the
Comprehensive Environmental
Response, Compensation, and Liability
Act. The Occupational Safety and
Health Administration (OSHA) of the
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Department of Labor has the oversight
for occupational health and safety for
radiation protection. It has regulations
governing radiation protection in the
workplace, including provisions
addressing the exposure of minors to
radioactive material in the workplace,
but defers to the NRC on AEA materials.
The Department of Commerce (DOC)
has controlled the export of radioactive
material. Before the enactment of the
EPAct, the DOC regulated the export of
all radium-226. With the enactment of
the EPAct, the NRC will regulate the
export of discrete sources of radium226; DOC retains jurisdiction to regulate
the export of nondiscrete sources of
radium-226. The Consumer Product
Safety Commission regulations have
addressed hazardous substances other
than byproduct, source, and special
nuclear materials currently regulated by
the NRC. The Food and Drug
Administration (FDA) regulates all
drugs (including drugs containing
radioactive materials) by requiring good
manufacturing practices to assure the
purity, potency, and consistency of
finished drugs with their labeling in
establishing the safety and effectiveness
of these drugs.
Section 651(e)(3) of the EPAct
provides that byproduct material, as
defined by Section 11e.(3) or 11e.(4) of
the AEA, may only be transferred to and
disposed of in a disposal facility that is
adequate to protect public health and
safety, and is licensed by either the NRC
or a State that has entered into an
agreement with the Commission under
Section 274b of the AEA or at a disposal
facility in accordance with any Federal
or State solid or hazardous waste law,
including the Solid Waste Disposal Act,
also known as the Resource
Conservation and Recovery Act (RCRA).
Development of the Suggested State
Regulations (SSRs)
Since enactment of the AEA in 1954,
scientists continue to develop new
technologies in producing
radionuclides, such as the use of
particle accelerators. At the beginning of
the 20th century, naturally occurring
radioactive material, including radium226, was routinely used in consumer
products and in cancer treatment.
Because there was no Federal mandate
to regulate these materials, most States
have since established regulatory
structures for both accelerator-produced
radioactive material and naturally
occurring radioactive material,
including radium-226.
In 1968, CRCPD was chartered as a
nonprofit organization to provide a
forum for enhancing communication
among States and Federal agencies
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regarding radiation regulations and to
promote a uniform radiation protection
environment for all radioactive material.
Throughout the years, CRCPD
developed policies and guidance for its
member States. In addition, CRCPD is
responsible for the development of
model regulations, known as the SSRs.
Under the SSRs’ regulatory framework,
NARM has been a regulated radioactive
material comparable to byproduct
material. Nearly all of the Agreement
States have based their regulations on
this model for NARM.
For NARM regulation only, CRCPD
also established ‘‘Licensing States’’
similar to the Agreement State Program
under Section 274 of the AEA.
Licensing States recognized by CRCPD
under criteria found in Publication 94–
8, ‘‘CRCPD Recognition of Licensing
States for the Regulation and Control of
NARM,’’ are those States that have
demonstrated an adequate and
consistent regulatory control program
for NARM. Licensing State designation
assures comparable regulatory
structures with respect to NARM, and
other States may grant reciprocal
recognition of their licenses or
acceptance of their licensees’
manufactured products.
Issuance of Waiver on August 31, 2005
Section 651(e) of the EPAct became
effective immediately upon signature by
the President on August 8, 2005. Before
enactment of the EPAct, the NRC did
not have authority over NARM or
regulations in place that would
specifically apply to this material.
Nonetheless, persons engaged in
activities involving NARM could be,
and States seeking to continue
regulation of NARM would be, in
technical violation of the AEA.
Section 651(e)(5) of the EPAct
authorized the Commission to issue a
waiver of the requirements of Section
651(e) to any entity with respect to
NARM for specified periods of time if
the Commission determined that the
waiver was in accordance with the
protection of the public health and
safety and the promotion of the common
defense and security. The Commission
determined that there was no basis to
conclude that these materials would not
continue to be used in a manner that is
protective of public health and safety
while the waiver is in effect. The
Commission also determined that it
would be in the best interest of the
public to allow continued use of NARM,
especially for medical purposes, and to
allow the States to continue to regulate
NARM until the Commission could
codify new regulations for these
materials.
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The Commission believed that
granting the waiver would allow the
States to continue with their regulatory
programs, allow persons engaged in
activities involving NARM to continue
their operations in a safe manner, and
allow continued access to medical
radiopharmaceuticals. In addition, it
would enable the Commission to work
with the States in developing
appropriate regulations for NARM and
in formulating a sound Transition Plan
for implementation of these regulations.
It would also provide an opportunity for
non-Agreement States that currently do
not have Agreement State regulatory
programs under Section 274b. of the
AEA to consider entering into an
agreement with the NRC. The
Commission determined that issuance
of the waiver would be in accordance
with the protection of public health and
safety and the promotion of the common
defense and security.
The Commission granted a waiver (70
FR 51581; August 31, 2005) from the
requirements of Section 651(e) of the
EPAct to: (1) All persons engaged in
export from or import into the U.S. of
byproduct material through August 7,
2006, unless terminated sooner if the
Commission determined that an earlier
termination was warranted; and except
with regard to the requirements of the
DOC relating to export of byproduct
material; (2) all persons acquiring,
delivering, receiving, possessing,
owning, using, or transferring byproduct
material through August 7, 2009, unless
terminated sooner if the Commission
determined that an earlier termination
was warranted; and (3) all States that
had entered into an agreement with the
Commission under Section 274b. of the
AEA, and States that had not entered
into such an Agreement, through August
7, 2009, unless terminated sooner if the
Commission determined an earlier
termination was warranted, or for an
Agreement State if the Commission
made certain determinations required
by Section 651(e)(5)(B)(ii) of the EPAct.
Stakeholder Involvement in the
Rulemaking Process
The NRC took several initiatives in an
effort to enhance stakeholder
involvement and to improve efficiency
during the rulemaking process. With
assistance from the Organization of
Agreement States (OAS) and CRCPD,
the NRC was able to obtain participation
of several State representatives in
various working groups in the
development of the proposed rule.
Principals from OAS and CRCPD,
representing interests for both
Agreement States and non-Agreement
States, also participated in the steering
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committee forming a partnership with
the NRC in making rulemaking
decisions. In an effort to keep
stakeholders informed, the NRC held a
public roundtable meeting in early
November. In addition, the NRC has met
with other Federal agencies to ensure
coordination regarding this rulemaking.
The NRC held a public meeting on
November 9, 2005, to discuss
rulemaking activities to incorporate
NARM into its regulatory framework.
The public meeting was in a
‘‘roundtable’’ format to allow
stakeholders an opportunity to discuss
concerns and to enhance interaction
among all interested parties on the
subject of the NRC regulating NARM.
Representatives from other Federal
agencies, States, and a broad spectrum
of interest groups were invited to
participate in the ‘‘roundtable’’
discussion. A transcript of this meeting
is available via the NRC’s and other
related documents are available from
(see FOR FURTHER INFORMATION CONTACT
section of this document.)
Following the public meeting, the
NRC received five written comments
from interested parties related to the
discussion at the meeting and the
rulemaking activities. These comment
letters were reviewed and considered by
the NRC staff in the development of the
proposed rule.
In addition to the public meeting, the
NRC interacted and met with FDA staff
to exchange information regarding the
NRC’s NARM rulemaking efforts and the
FDA’s regulations for acceleratorproduced drugs. The primary objective
of the FDA’s regulations is to ensure
medical safety, purity, potency, and
effectiveness of the drugs, and that of
the NRC’s regulations is to ensure
radiation safety. During the meeting,
areas of potential dual regulation were
discussed. Because the NRC and the
FDA have different missions, the
associated regulations are more
complementary than duplicative. FDA
has published a proposed rule (70 FR
55038; September 20, 2005), ‘‘Current
Good Manufacturing Practice for
Positron Emission Tomography Drugs,’’
and expects to finalize the rule soon.
The FDA’s final rule will establish
criteria for the production and process/
quality controls for the Positron
Emission Tomography (PET) drugs in
PET centers registered with the FDA.
The NRC hosted a meeting of Federal
agency representatives on November 22,
2005, to discuss the development of a
definition of Discrete source to be added
to the NRC’s regulations. Agencies
represented at this meeting were DOT,
DOE, including the National Nuclear
Security Administration, Department of
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Defense, DOC, EPA, and the U.S.
Customs and Border Protection. A draft
definition was formulated. This
definition formed the basis for the
definition in the proposed rule, with
only minor changes and text
rearrangement for clarity.
The NRC published the proposed rule
to establish the regulatory framework for
the newly defined byproduct material
on July 28, 2006 (71 FR 42952). Thirtynine comment letters were received.
The commenters included a number of
States, Federal agencies, professional
organizations, universities, medical
communities, industries, and
individuals.
II. Discussion
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A. The New, Expanded Definition of
Byproduct Material
Section 651(e) of the EPAct expanded
the definition of Byproduct material to
include: (1) Any discrete source of
radium-226 that is produced, extracted,
or converted after extraction, before, on,
or after the date of enactment of the
EPAct for use for a commercial,
medical, or research activity; (2) any
material that has been made radioactive
by use of a particle accelerator and is
produced, extracted, or converted after
extraction, before, on, or after the date
of enactment of the EPAct for use for a
commercial, medical, or research
activity; and (3) any discrete source of
naturally occurring radioactive material,
other than source material, that the
Commission, in consultation with the
Administrator of the EPA, the Secretary
of DOE, the Secretary of DHS, and the
head of any other appropriate Federal
agency, determines would pose a threat
similar to the threat posed by a discrete
source of radium-226 to the public
health and safety or the common
defense and security, and that is
extracted or converted after extraction,
before, on, or after the date of enactment
of the EPAct for use in a commercial,
medical, or research activity. The NRC
is revising the definition of Byproduct
material in 10 CFR Parts 20, 30, 50, 72,
150, 170, and 171 to be consistent with
the EPAct. The same revision to the
definition of Byproduct material was
made in a separate rulemaking for 10
CFR Part 110 (April 20, 2006; 71 FR
20336). A different definition for the
term Byproduct material is used in 10
CFR Part 40, because 10 CFR Part 40
regulations are limited to source
material and the tailings or wastes
associated with the extraction or
concentration of source material.
Therefore, 10 CFR Part 40 regulations
are not impacted by the EPAct, and the
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definition of Byproduct material in that
Part remains unchanged by this rule.
Since the publication of the proposed
rule, and after considering the
comments on the new definition of
byproduct material, the Commission has
taken a closer look at the scope of the
Commission’s jurisdiction over the
newly added byproduct material. The
EPAct covers discrete sources of
radium-226 and accelerator-produced
radioactive material that is ‘‘produced,
extracted, or converted after extraction,
before, on, or after August 8, 2005, for
use for commercial, medical, or research
activity’’ (emphasis added).
Notwithstanding that a discrete source
of radium-226 may have originated from
a commercial supplier, the Commission
has determined that discrete sources of
radium-226 still in control of the
military do not constitute ‘‘commercial
use’’ under the EPAct, and are therefore,
outside the Commission’s jurisdiction.
Defining ‘‘commercial use’’ to include
all material supplied to the military
from a commercial supplier would
result in virtually all military use of this
material to be ‘‘commercial use.’’ This
would vitiate any distinction that the
EPAct intended to make for military
use, as opposed to commercial use, by
excluding military use from its
coverage.
However, this exclusion from the
coverage of the EPAct only applies to a
certain type of military use, i.e., NARM
used for ‘‘military operations.’’ The term
‘‘military operations’’ covers what is
traditionally understood as the
military’s primary mission for national
defense, including warfare, combat, and
battlefield missions, and, of course,
training for battlefield missions. NARM
used, or available for use, for these
purposes would be excluded from the
coverage of the EPAct and from the
coverage of this rule. If the material is
intended for use in military operations,
it is excluded from the coverage of this
rule notwithstanding the fact that it was
originally produced by a commercial
supplier. In addition, ‘‘military
operational’’ material includes material
still under the control of the military,
i.e., in storage, or material that may be
subject to decontamination and
disposal.
Other use of NARM by the military
would be covered by this rule. Under
the Commission’s interpretation of the
EPAct, NARM, whether discrete sources
or accelerator material, that is produced,
extracted, or converted for use or has
been used, in medical or research
activities, or in a manner similar to a
commercial activity, e.g., military
museums, is covered by the EPAct and
this rule. Furthermore, NARM that was
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used for military operations but is no
longer under the control of the military,
has been sold, or is in the possession of
private individuals, is also within the
coverage of this rule.
The NRC intends to interact with the
Department of Defense to obtain a
common understanding of the uses of
radium-226 and accelerator-produced
radioactive material by the military to
resolve any potential issues regarding
the application of the Commission’s
interpretation of the EPAct in regard to
any specific case of military use.
Radium-226
Radium is a chemically reactive,
silvery white, radioactive, metallic
element with an atomic number of 88
and symbol of Ra. Radium-226, the most
abundant and most stable isotope of
radium, is formed by the radioactive
disintegration of thorium-230 in the
decay series starting with uranium-238.
Radium-226 can be found in all
uranium ores. The half-life of radium226 is 1599 years. Radium-226 emits
alpha particles and gamma radiation
and decays to radon gas.
Although radium was discovered in
the ore pitchblende by the chemists
Marie and Pierre Curie in 1898, no one
understood the dangers of radium until
later in the twentieth century. Based on
radium’s properties, especially its
ability to stimulate luminescence,
industries started manufacturing
hundreds of consumer products
containing radium. Radium was added
to products such as hair tonic,
toothpaste, ointments, and elixirs.
Radium paint was used in the mid1900s to paint the hands and numbers
of some clocks, watches, doorknobs, and
other objects to make them glow in the
dark. Glow-in-the-dark watch and clock
faces were particularly popular. Most of
these uses were eventually discontinued
for health and safety reasons, but its
wide use in luminescent paints
continued through World War II
because radium’s luminescent glow
made aircraft and vehicle dials, gauges,
and other instruments visible at night.
Many of these early products still
remain in the possession of museums
and individual collectors. Large
inventories of radium-226 luminescent
military and aircraft devices remain and
periodically turn up in repair shops,
and have resulted in contamination
incidents.
In more recent times, radium sources
were used in industrial radiography and
industrial smoke detectors. Currently,
radium sources are still being used in
some industrial products, such as
industrial gauges, that measure certain
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physical properties such as moisture
and density.
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Accelerator-Produced Radioactive
Material
Particle Accelerators
A particle accelerator is a device that
imparts kinetic energy to subatomic
particles by increasing their speed
through electromagnetic interactions.
Particle accelerators are used to produce
radioactive material by directing a beam
of high speed particles at a target
composed of a specifically selected
element, which is usually not
radioactive. Nuclei in the target are
struck by the high speed particles and
undergo a nuclear transformation. A
nuclide that is struck is transformed
into a different nuclide. By careful
selection of the target element, the
particles accelerated, and the operating
parameters of the accelerator (e.g., beam
energy), a resultant proton-heavy
nuclide can be produced. Usually the
nuclide produced is radioactive and is
created for the use of its radiological
properties. The process of transforming
nuclei from a stable element into a
radionuclide is called activation. In
some cases, the target is selected so that
the accelerator produces a neutron beam
that is, in turn, used to activate nuclides
that are then used for their radioactive
properties. Some particle accelerators
are not used to produce radioactive
material, but instead the high energy
beam produced by the particle
accelerator is used directly, for example,
to treat cancer patients.
The two basic designs of particle
accelerators are linear and circular, also
known as cyclotron. In either case,
charged particles are injected into the
accelerator to form a beam. The beam is
accelerated and focused onto the target.
In the circular designs, the beam must
be directed to travel in a circular shaped
path. For all accelerators, the process of
accelerating, focusing, and directing the
beam is accomplished by a combination
of electrically charged structures and
magnetic fields in the accelerator.
During operation, these internal
structures will be struck by particles
from the beam and activated
incidentally.
Particle accelerators are often
classified by the maximum energy of the
accelerated particles, expressed in
megaelectron-volts (MeV). An electronvolt is the amount of energy imparted to
an electron by an accelerating potential
of one volt. The small cyclotrons that
produce radionuclides used in PET
nuclear medicine usually operate at
energies of up to about 30 MeV. By
comparison, the accelerators used in
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basic physics research facilities reach
energies in excess of 1000 MeV.
For the purposes of this rulemaking,
the NRC divided particle accelerators
into three groupings: (1) Those that are
always operated to intentionally
produce radioactive materials in
quantities useful for their radioactive
properties for a commercial, medical, or
research activity; (2) those that are
operated to produce only particle beams
and not radioactive materials; and (3)
accelerators that are used to produce
both radioactive materials and particle
beams for other uses. Examples of
accelerators that are operated to produce
only particle beams and not radioactive
materials include linear accelerators
used for medical treatment of cancer
and other health-related conditions.
Other examples include the
experimental particle physics research
colliders used to probe the fundamental
properties of nature (as long as that is
their only use) and electron
microscopes, i.e., particle accelerators
that probe the structure of materials at
a very small dimension (high
magnification). Ion implanters are
particle accelerators used to modify the
electrical properties of materials in
semiconductor fabrication. In these
activities, no radioactive material is
intentionally created; all activation is
incidental to the intended use of the
accelerator.
The NRC will regulate the radioactive
material both intentionally and
incidentally produced by all
accelerators that are intentionally
operated to produce a radioactive
material for its radioactive properties.
The NRC will not regulate the incidental
radioactive material produced by
accelerators that are operated to produce
only particle beams and not radioactive
materials for use for a commercial,
medical, or research activity. For those
accelerators that are used to produce
both radioactive material and particle
beams, the NRC will regulate the
intentionally produced radioactive
material and all of the incidentally
produced radioactive material,
including incidental radioactive
material produced when the accelerator
is operated to produce radioactive
material, as well as incidental
radioactive material produced when it is
operated to produce only a particle
beam. The incidental radioactive
materials produced in these accelerators
are indistinguishable, so both will be
considered byproduct material. The
NRC believes very few, if any,
accelerators are operated in this way.
The EPAct does not give the NRC
authority to regulate the possession or
use of particle accelerators. The NRC
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has not adopted any rule regarding the
operation of a particle accelerator or the
qualification of any person maintaining
or operating a particle accelerator.
However, nothing in the EPAct directs
the NRC to change the policy that
radiation safety standards must consider
unregulated as well as regulated sources
of radiation. The NRC will continue to
require any person subject to the dose
limits in 10 CFR Part 20 to continue to
include the radiation dose from the
operation of a particle accelerator in
meeting the dose limitations. The NRC
is aware that the operation of a particle
accelerator may activate materials in the
structure of the building and facilities
housing the accelerator. The NRC
intends to assure the safe
decommissioning of particle accelerator
buildings and facilities, including the
removal and disposal of activated
building materials, to assure that the
dose limits to members of the public are
not exceeded. The decommissioning of
these facilities will be required to meet
the radiation dose limits in 10 CFR Part
20 Subpart E—Radiological Criteria for
License Termination.
The majority of accelerator-produced
radioactive material is now created for
use in medicine. The NRC is aware of
only two operations in the U.S. and a
few importers, mostly from Europe and
Canada, that are commercial producers
of accelerator-produced radioactive
material for use in industrial activities.
The regulatory approach for
manufacturing accelerator-produced
radioactive material for industrial
purposes is similar to the regulatory
approach for manufacturing acceleratorproduced radioactive material for
medical purposes.
Accelerator-Produced Radioactive
Material Used in Medical Activities
Medical use of radioactive material
began over 50 years ago. The medical
use of sealed and unsealed radioactive
materials continues to be an important
component of medical specialties for
both diagnosis and therapy purposes.
The use of small quantities of unsealed
radioactive materials
(radiopharmaceuticals) in nuclear
medicine is an integral part of patient
care and is extremely valuable in the
early diagnosis and treatment of medical
conditions. Radiation oncology uses
larger amounts of radioactivity in sealed
sources to deliver therapeutic or
palliative radiation doses.
Almost all reactor-produced
byproduct radionuclides for radioactive
drugs are imported into the U.S., as well
as most reactor-produced radionuclides
used in sealed sources, although some
used in radioactive drugs and sealed
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sources are also produced in an NRCregulated nonpower reactor.
Commercial manufacturers primarily
use the imported radionuclides to
produce specific sealed sources,
radioactive drugs, and biologics.
Commercial nuclear pharmacies may
use radiochemicals to prepare
radioactive drugs, as well as
commercially produced radioactive
drugs and drug sources, such as
molybdenum-99/technetium-99m
generators, to prepare unit dosages of
other radioactive drugs.
The U.S. has a limited number of
commercial radionuclide production
facilities that use accelerators to
produce radionuclides, such as
thallium-201, iodine-123, indium-111,
and gallium-67 used in radioactive
drugs. A larger number of radionuclide
production facilities (often referred to as
PET centers) use cyclotrons to produce
the PET radionuclides fluorine-18,
carbon-11, nitrogen-13, and oxygen-15
for use in PET radioactive drugs. PET
radionuclides decay by positron
emission and, because of their relatively
short half-life (minutes to hours), are
produced at locations in close proximity
to the patients (e.g., in hospitals or
academic institutions) or at nearby
locations.
Palladium-103, the most common
accelerator-produced medical use
radionuclide contained in a sealed
source, was originally produced at
reactor facilities. Other radionuclides
used in medical radiation therapy can
also be produced with either reactors or
accelerators. With the new definition of
Byproduct material, sealed sources that
can be produced from either pathway
will be uniformly regulated. At this
time, there are no teletherapy or remote
afterloader or gamma stereotactic
radiosurgery units with acceleratorproduced sources.
Because production accelerators for
medical radionuclides (e.g., PET
production facilities) and industrial
radionuclides are used to intentionally
produce radioactive material for use of
its radioactive properties for a
commercial, medical, or research
activity, the NRC will regulate both the
radionuclides produced in these
accelerators as well as the incidentally
activated radioactive material.
Other Naturally Occurring Radioactive
Material With Similar Risk as Radium226
The EPAct amended the definition of
Byproduct material to include any
discrete source of naturally occurring
radioactive material, other than source
material, that the Commission, in
consultation with the Administrator of
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the EPA, the Secretary of Energy, the
Secretary of Homeland Security, and the
head of any other appropriate Federal
agency, determines would pose a threat
similar to the threat posed by a discrete
source of radium-226 to the public
health and safety or the common
defense and security, and is extracted or
converted after extraction, before, on, or
after the date of enactment of the EPAct
for use in a commercial, medical, or
research activity.
The inclusion of discrete sources of
naturally occurring radioactive material
into the definition of Byproduct
material is contingent on the
Commission’s determination, in
consultation with other Federal
agencies, that these discrete sources
would pose a threat similar to the threat
posed by a discrete source of radium226. The NRC has not currently
identified any discrete sources of
naturally occurring radioactive material
under this provision, and the rule does
not contain criteria for making such a
determination. For comparison, the
International Atomic Energy Agency
(IAEA) has identified a list of sources
that are considered to pose a high risk
to human health and safety if not
managed safely and securely. The IAEA
Code of Conduct on the Safety and
Security of Radioactive Sources (Code of
Conduct) identified certain quantities of
26 radionuclides that pose a significant
risk to individuals, society, and the
environment. The activity of these
radionuclides at the IAEA Code of
Conduct Category 1 or 2 level could be
fatal or cause permanent injury to a
person who handled them or was
otherwise in contact with them for a
short time, if not safely managed or
securely protected. Of these 26 sources,
only two naturally occurring
radionuclides are listed: Radium-226
and polonium-210. Because this rule
addresses discrete sources of radium226, the only other naturally occurring
radioactive material similar in hazard to
radium-226 when using the IAEA
criteria is polonium-210. However,
naturally occurring polonium is scarce.
One ton of uranium ore contains only
about 100 micrograms (0.0001 grams) of
polonium. Due to its scarcity in nature,
polonium-210 used for commercial
purposes is usually produced by
bombarding bismuth-209 with neutrons
in a nuclear reactor and had been
regulated by the NRC before the EPAct.
Additionally, polonium-210 is unlikely
to be commercially used in individual
radioactive sources with activity levels
that would place them within the IAEA
Code of Conduct Category 1 or 2. Hence,
the NRC has determined that no other
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discrete sources of naturally occurring
radioactive material pose a threat
similar to the radium-226-level or IAEA
Code of Conduct Category 1 or 2
sources.
Through interaction with other
Federal agencies and States during
development of the rule, the NRC
concluded that, at this time, only
polonium-210 has the potential to pose
a threat similar to the threat posed by a
discrete source of radium-226 to the
public health and safety or the common
defense and security. The NRC had
already been regulating the use and
possession of polonium-210 because it
is produced in nuclear reactors and is
rarely extracted as naturally occurring
radioactive material. Therefore,
although this rule adds this category of
byproduct material to the definitions in
the regulations, at this time, the NRC’s
regulations will not apply to any
discrete sources of naturally occurring
radioactive material, other than radium226. The EPAct has provided a
mechanism for the Commission to
include additional discrete sources of
naturally occurring radioactive material
in the future following consultation
with other Federal agencies, if the need
arises to consider other naturally
occurring radioactive material as
byproduct material. No further revision
to the regulations will be necessary to
begin regulating a material identified
through this mechanism. However, the
NRC will provide an opportunity for
public input before applying its
regulations to other naturally occurring
radionuclides that the NRC determines
in consultation with other federal
agencies, pose a threat similar to the
threat posed by discrete source of
radium-226.
B. The NRC’s Regulatory Approach
Consideration of Suggested State
Regulations for the Control of Radiation
(SSRs)
All 34 Agreement States have
regulations for NARM. Twelve nonAgreement States and certain U.S.
Territories have some type of regulatory
structure for NARM, while four nonAgreement States have no program for
regulating NARM. The EPAct mandated
that the NRC use model State standards
to the maximum extent practicable in
issuing regulations for the expanded
definition of Byproduct material. The
NRC considered the SSRs published by
CRCPD (https://www.crcpd.org/
free_docs.asp) as the model State
standard in developing this rule. Most
Agreement States have regulated
discrete sources of radium and
accelerator-produced radioactive
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material in a manner similar to and
under the same requirements as reactorproduced radioactive material. Few
provisions in the SSRs exist solely to
address these materials. Where specific
provisions do exist in the SSRs for these
materials, they have been evaluated for
possible inclusion in the NRC’s
regulations.
For radionuclide-specific values listed
in 10 CFR part 20, Appendices B and C,
the NRC found that there are no other
radionuclides identified in the SSRs
that are not already included in 10 CFR
part 20. As discussed further in this
document under Section C., ‘‘Changes to
Existing NRC Regulations to
Accommodate the New Byproduct
Material,’’ most of the specific
provisions related to NARM
radionuclides in the SSRs have been
adopted in this rule. These include
exempt quantities in 10 CFR 30.18 and
10 CFR 30.71, an exemption for
timepieces in 10 CFR 30.15, a general
license for calibration and reference
sources in 10 CFR 31.8, a general license
for use of radioactive material for
certain in vitro clinical or laboratory
testing in 10 CFR 31.11, contamination
limits for strontium-82/rubidium-82
generators, and requirements to measure
the contamination limits in 10 CFR
35.204 with corresponding
recordkeeping requirements in 10 CFR
35.2204.
While SSRs do exist that address
other types of naturally occurring
radioactive material that are not covered
by the EPAct or these new regulations,
discrete sources of radium and
accelerator-produced radioactive
material are covered under the same
provisions of the SSRs that apply to
reactor-produced radioactive material.
There is general agreement among the
States, reflected in the SSRs, that the
new categories of byproduct material
should be regulated under the same
requirements as reactor-produced
radioactive material. This rule takes the
same regulatory approach. Most of the
requirements that will apply to users of
the newly regulated material are
preexisting NRC requirements.
Other Related Rulemakings
The NRC amended its regulations in
10 CFR Part 110 revising the definition
of Byproduct material to include
discrete sources of radium-226,
accelerator-produced radioactive
material, and discrete sources of
naturally occurring radioactive material
(71 FR 20336; April 20, 2006). In
addition, an earlier amendment (70 FR
37985; July 1, 2005) added discrete
sources of radium to 10 CFR Part 110,
Appendix P. Together, the two
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amendments satisfy the requirements of
Section 651(d) of the EPAct pertaining
to the export or import of Category 1 or
Category 2 radiation sources as defined
by the IAEA Code of Conduct. By this
final rule, the NRC is again amending is
regulations in 10 CFR Part 110 to
include a definition of Discrete source.
Section 651(d) of the EPAct also
requires the NRC to issue regulations
establishing a mandatory tracking
system for radiation sources, including
radium-226, in the U.S. The NRC issued
a final rule for national source tracking
of sealed sources (71 FR 65686;
November 8, 2006) that included
radium-226 sources.
Definition of Discrete Source
The EPAct extended the definition of
Byproduct material in the AEA to
include any discrete source of radium226 and certain other naturally
occurring radioactive material that is
produced, extracted, or converted after
extraction, before, on, or after the date
of the enactment of the EPAct, for use
for a commercial, medical, or research
activity. The term Discrete source is not
defined in the EPAct, and the EPAct
specifically mandates that the final
regulations, in establishing
requirements necessary to carry out the
amendment, shall include a definition
of the term Discrete source. The
definition of Discrete source is used for
purposes of the new definition of
Byproduct material in the case of
radium-226 and other naturally
occurring radioactive material other
than source material. The term Discrete
source is not used in conjunction with
accelerator-produced radioactive
material in the EPAct language.
Thus, the EPAct gave the NRC
authority over discrete sources of
radium-226 but not over diffuse sources
of radium-226. The EPAct did not
extend the NRC’s authority over radium226 as it occurs in nature, or over other
processes where radium-226 may be
unintentionally concentrated. The focus
was on those materials that presented a
threat to public health and safety or to
the common defense and security
similar to the threat posed by discrete
radium-226 sources. Scale from pipes
used in the fossil fuel industry, fly ash
from coal powerplants, phosphate
fertilizers, or residuals from treatment of
water to meet drinking water standards
are not considered discrete sources.
However, uranium and thorium within
these materials may become licensable
source material depending upon their
concentration.
The definition of Discrete source in
the proposed rule was ‘‘a radioactive
source with physical boundaries, which
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is separate and distinct from the
radioactivity present in nature, and in
which the radionuclide concentration
has been increased by human processes
with the intent that the concentrated
radioactive material will be used for its
radiological properties.’’ As a result of
public comments on the proposed rule,
the NRC changed the wording of the
definition of Discrete source from that
in the proposed rule. Discrete source is
defined in this final rule as ‘‘a
radionuclide that has been processed so
that its concentration within a material
has been purposely increased for use for
commercial, medical, or research
activities.’’ The changes are for
clarification purposes only and do not
change the original intent of the
proposed definition of Discrete source
or the scope of the NRC’s regulation of
radium-226 or other naturally occurring
radioactive materials identified in the
future. The intent of the revised
definition continues to be consistent
with the proposed rule in that the NRC’s
authority is not intended to extend to all
naturally occurring radioactive material,
specifically not to naturally occurring
radioactive material that is found in
nature in its original form and location,
or that which is moved or concentrated
inadvertently by some man-made
process. A discrete source will have the
same radiological characteristics (e.g.,
type of radiation, half-life) as the
radionuclide found in nature but will
have been purposefully concentrated for
use for its specific properties after it has
been removed from its original location
in nature. This definition excludes the
NRC’s jurisdiction over inadvertent
movement or concentration of naturally
occurring radioactive material such as
scale from pipes used in the fossil fuel
industry, fly ash from coal power plants,
or phosphate fertilizers. It also excludes
NRC jurisdiction over residuals from
treatment of water. While radium, in
particular, may be intentionally
concentrated in this case, it is not for
the purpose of using the radium, but to
improve water quality. Only if, and
when, this radium were further
processed for use would it be
considered a discrete source, and thus
byproduct material. Neither the changes
to the AEA as a result of the EPAct, nor
anything in this rulemaking changes the
NRC’s authority, in any manner, over
source material.
The words ‘‘a radionuclide that has
been processed so that its concentration
within a material has been purposely
increased’’ are intended to further
clarify that the extraction or processing
relates to the intent to use the
radionuclide itself, and not a material
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that happens to contain the
radionuclide, such as fertilizer. The
addition of the phrase ‘‘for use for
commercial, medical, or research
activities’’ repeats a constraint that also
appears in the definition of Byproduct
material. The NRC has repeated this
constraint in order to ensure that when
the term ‘‘discrete source’’ is used
separately from the term ‘‘byproduct
material,’’ it will not be interpreted
more broadly, but it will be clear that
only material which is intended for use
for commercial, medical, or research
activities is being referenced.
It should also be noted that in
accordance with this definition of
Discrete source, once a discrete source
meets the definition of Byproduct
material, any contamination resulting
from the use of such discrete sources of
this byproduct material will also be
considered byproduct material. This
issue is discussed further in this
document under ‘‘Summary and
Analysis of Public Comments on the
Proposed Rule.’’
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C. Changes to Existing NRC Regulations
To Accommodate the New Byproduct
Material
The Commission has authority to
issue both general and specific licenses
for the use of byproduct material and to
exempt byproduct material from
regulatory control under Section 81 of
the AEA. A general license, as provided
by regulation, grants authority to a
person for certain activities involving
byproduct material and is effective
without the filing of an application with
the Commission or the issuance of a
licensing document to a particular
person. Requirements for general
licensees appear in the regulations and
are designed to be commensurate with
the specific circumstances covered by
each general license.
In considering the expansion of the
definition of Byproduct material to
include discrete sources of radium-226
and accelerator-produced radioactive
material, the NRC has evaluated
products and materials previously
approved by the States for use under an
exemption from licensing and under a
general license. Generally, the NRC’s
intent in this rule is to accommodate
existing products and materials that
were previously regulated by the States
under similar provisions, if the potential
doses are similar to those expected from
other currently regulated products and
materials. Many of these products have
not been made for some time, so some
of the provisions in this rule are limited
to items manufactured in the past,
which may still be in use or in storage.
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The bases of these exemptions and
general licenses are primarily the SSRs
and also information in NRC’s sealed
source and device (SS&D) registry. The
SS&D registry is the NRC’s national
database of technical information on
sealed sources and devices.
Manufacturers or distributors may
submit a request to the NRC for an
evaluation of a product’s radiation
safety information and for registration of
the product. After satisfactory
completion of the evaluation, the NRC
issues a certificate of registration to the
person making the request, and this
certificate is added to the SS&D registry.
Many Agreement States have similar
registration procedures, and registration
certificates for the sources and devices
they review are added to the national
SS&D registry. The NRC also has
included SS&D certificates for NARM,
which have been issued by the States.
While this is not a complete database
with respect to NARM, it includes
detailed information about many
products containing NARM previously
evaluated by the States. In addition to
SSRs and the information in the SS&D
registry, the specific provisions of the
various States also were considered in
developing this rule.
Regulating Items Containing Radium226
Currently, items or products
containing radium-226 are unique in
that there are no new items in consumer
commerce using radium-226 byproduct
material. Although certain industrial
devices such as moisture density gauges
containing radium-226 are still in use,
most radium-226 articles have not been
produced for at least 20 years.
Beginning in the early 1900s, radium226 was used to make self-luminescent
paint and incorporated in watch and
clock dials and hands and later used to
illuminate airplane instrumentation
dials and gauges as well as markers and
signs. Beginning in the 1950s, other
radionuclides began to replace radium226 as a self-luminescent material due
to the recognition of the radiological
hazard associated with radium-226.
Currently, the radionuclides of choice
for self-luminescent applications are
promethium-147 and tritium due to the
much reduced radiological hazard vis-avis radium-226.
Based on the National Council on
Radiation Protection and Measurements
in Report 95, ‘‘Radiation Exposure of the
U.S. Population from Consumer
Products and Miscellaneous Sources,’’
radium-226 has not been used in
radioluminescent watches since 1968
and clocks since 1978. In fact, radium226 timepieces are currently kept
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55871
largely as collectors’ items and only
infrequently used by consumers as
timepieces. When originally
manufactured, the quantity of radium226 employed in watch and clock dials
and hands varied by timepiece size,
manufacturer, model, and from item to
item. While the quantity of radium-226
varied in the timepieces, there is a
general agreement for typical average
and upper bound quantities. Based
upon the spectrum of timepiece sizes,
wristwatches have the smallest quantity,
with pocket watches and clocks having
quantities several times higher than
wristwatches. The radioactivity
associated with wristwatches is
generally on the order of several
kilobecquerel (kBq) (tenths of a
microcurie (µCi)) with an average of 5.6
kBq (0.15 (µCi)). Pocket watches may
have radioactivity of about 13 kBq (0.35
µCi), and clocks are typically 18 kBq
(0.5 µCi). However, collections of pocket
watches and clocks are rare when
compared to wristwatches.
Before the discontinuation of the
manufacturing of timepieces containing
radium-226 in the 1970s, radium-226illuminated timepieces were widely
distributed throughout the country as a
common consumer product. To date, a
large number of radium-226 timepieces
are still owned by individuals as valued
heirlooms or collectors’ items or are on
display in museums. Because museums
and collectors normally collect a wide
range of timepieces, a portion of their
collection may contain radium-226
timepieces. Some businesses and a few
collectors are also engaged in repairing
and refurbishing timepieces either as a
hobby or professionally, and these
activities may occasionally involve
timepieces containing radium-226.
Because these timepieces were
manufactured before the NRC assumed
regulatory authority over radium-226,
and because these timepieces are
already in public possession, the NRC
intends to minimize regulatory impact
to individuals, museums, or other
entities in possession of these
timepieces. In finalizing the rule, the
NRC made its determination based on
no significant risk to public health and
safety and the environment.
In the proposed rule, the NRC
proposed to exempt intact timepieces
containing no more than 37 kBq (1 µCi)
of radium-226 per timepiece and repair
of no more than 10 timepieces in any
one year. In addition, the NRC proposed
to generally license no more than 50
timepiece hands and dials used or
stored at the same location at any one
time. Due to lack of sufficient health
and safety information to make a final
regulatory decision, the NRC conducted
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a scoping study for estimating potential
radiological doses to individuals
associated with use, storage, and repair
of radium-226 timepieces. The scoping
approach taken by the NRC used widely
accepted methods and employed
conservative assumptions for various
scenarios involving use, storage, and
repair of radium-226 timepieces.
Because the scoping study was designed
to be conservative and meaningful and
yet easy to perform, it is to be expected
that the actual doses would be
significantly lower than those predicted
by the scoping study.
To evaluate the potential doses
associated with the proposed exemption
of radium-226 timepieces, 37 kBq (1
µCi) of radium-226 per timepiece was
used in the scoping study instead of the
typical average activities for timepieces,
which provided for additional
conservatism. Radon-222 is a decay
product in the radium-226 decay series
and may be emitted from the timepiece
into the surrounding atmosphere and
thus result in exposure to an individual
in proximity to the timepiece. It is
believed that the radon-222 emanating
from the paint is almost totally trapped
within the watch. Because of the age of
radium-226 timepieces, and because
there is no established method for
quantifying the trapping behavior, the
scoping study conducted by the NRC
assumed that the entire inventory of
decay products instantly escaped and
became uniformly distributed into the
surrounding building volume. This
assumption is obviously very
conservative. As a result, the estimated
inhalation doses associated with radon222 are extremely conservative. The
scoping study found that the estimated
doses to a collector for repair, storage,
and use of a radium-226 timepiece range
from a fraction of 0.01 millisievert/yr
(mSv/yr) [1 millirem/yr (mrem/yr)] to a
few mSv/yr (mrem/yr) to over 1 mSv/yr
(100 mrem/yr).
At one time, there were repair
facilities refurbishing radium timepieces
on a regular basis by replacing radium226 paint with tritium paint. Scraping
off the radium-226 paint may have
resulted in significant contamination.
The NRC is not aware of any current
operations in which individuals are still
routinely handling radium watches in
such a way as to create a contamination
problem. Based upon the estimated
doses for repairs, the NRC believes that
a specific limit on the annual number of
repairs is not necessary. As long as these
repairs are taking place under a general
license, actions could always be taken if
the Commission receives information
that suggests that the public health and
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safety are not being adequately
protected.
The NRC’s intent is to minimize
regulatory impact on those private
collectors and museums as much as
possible, and to be as consistent as
possible with the regulatory approach
taken by the Agreement States, many of
whom have been regulating radium-226
for several decades. Accordingly, in
light of the public comments received,
the Agreement States’ rulemaking
involvement and the results of the
scoping study in finalizing the rule, the
NRC revised the proposed revisions
related to radium-226 timepieces.
Primarily, the change made in this final
rule is to broaden the general license
provision for the radium-226
timepieces. Specifically, the NRC has
concluded that a finite number of
annual repairs as well as a limitation on
the number of nonintact timepieces and
timepiece hands and dials is
unnecessary and not warranted based
upon the NRC’s understanding of
radium-226 timepieces either in
collections or in use. As a result of the
scoping study and in response to public
comments, the NRC has concluded that
it is appropriate to recategorize the
repair of timepieces from an activity
allowed under an exemption from
licensing to one covered by a general
license. This categorization is also more
consistent with the Agreement States’
existing exemption provision.
Although not mandated by
regulations, the NRC advises that
individual collectors or persons engaged
in repair of these devices should use
good practices such as wearing gloves
when handling radium-226 timepieces,
hands, and dials, and washing hands to
minimize potential exposure to the
radioactive material. In addition,
individual collectors should ensure that
storage areas are well ventilated to
minimize potential exposure due to
accumulation of radon-222 gas and
should avoid unnecessary exposure to
these types of timepieces.
Exemptions From Licensing
In 10 CFR Part 30, a number of
exemptions from licensing requirements
are included. These exemptions allow
for certain products and materials
containing byproduct material to be
used without any regulatory
requirements imposed on the user. The
two exemptions in 10 CFR 30.19, Selfluminous products containing tritium,
krypton-85, or promethium-147, and 10
CFR 30.20, Gas and aerosol detectors
containing byproduct material, are class
exemptions which cover a broad class of
products. Under these provisions, new
products can be approved for use
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through the licensing process if the
applicant demonstrates that the specific
product is within the class and meets
certain radiation dose criteria. This
contrasts with other exemptions for
which the level of safety is controlled
through such limits as specification of
radionuclides and quantities. Section
30.14, Exempt concentrations, and
Section 30.18, Exempt quantities, of
NRC’s regulations, are broad materials
exemptions, which allow the use of a
large number of radionuclides. The
specific radionuclide limits on these
concentrations and quantities are
contained in tables in 10 CFR 30.70 and
10 CFR 30.71, respectively. The
remaining exemptions from licensing
are product specific, for which many
assumptions can be and have been made
concerning how the product is
distributed, used, and disposed of. This
final rule adds some products and
materials containing NARM to some of
the previously existing exemptions. The
table of exempt concentrations in 10
CFR 30.70 already included all of the
radionuclides and associated limits
contained in the equivalent section of
the SSRs. Thus, the NRC is not revising
the exempt concentration table in this
final rule.
Exempt Quantities
Part C of the SSRs includes a list of
exempt quantities which are identical to
those in 10 CFR 30.71 but includes an
additional 13 radionuclides, which are
accelerator produced. This final rule
adds these 13 radionuclides and their
respective quantities, as already
included in the SSRs, to the list of
exempt quantities in 10 CFR 30.71. The
technical bases of these values are
similar to those used for the existing
values in 10 CFR 30.71.
The NRC considered whether there
were additional radionuclides in use
under comparable State exemptions that
should be accommodated under 10 CFR
30.71. It was noted that a few of the
States’ regulations for exempt quantities
include additional radionuclide-specific
values, each appearing in only one or
two States’ regulations. These
radionuclides are specifically exempted
in only one or two States; thus, they do
not represent nationally recognized
exemptions. It was also not clear as to
what approach was used to calculate
their exemption values. Therefore, the
NRC is adding only the 13 radionuclides
and values from the SSRs for which
there are adequate technical bases, and
no further additions to 10 CFR 30.71 are
included in this final rule. It is noted,
however, that for other byproduct
material, excluding alpha emitters,
which is the last item on the list in 10
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CFR 30.71, Schedule B allows for 3.7
kBq (0.1 µCi) to be used as an exempt
quantity. This will apply to acceleratorproduced radionuclides as well. Minor
changes are also being made to 10 CFR
30.18 to accommodate any materials
that may have been received before
September 25, 1971, under a general
license of a State similar to that then
provided in 10 CFR 31.4.
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Timepieces Containing Radium-226
The exemption in 10 CFR 30.15(a)(1)
is being revised to include intact
timepieces that were manufactured
before the effective date of this final rule
and containing no more than 37 kBq (1
µCi) of radium-226. This provision is
consistent with the SSRs, except that
the rule is limited to ‘‘intact’’
timepieces. In the final rule, the repair
of timepieces was moved from the
exemption to the general license to be
more consistent with the SSRs and to
broaden the general license provision.
As discussed earlier, the possession of
nonintact timepieces, hands, and dials,
and the repair of timepieces would be
covered by a new general license. This
general license provision should cover
most current practices involving
radium-226 and minimize impacts upon
individual collectors and small
businesses. A general license is
automatically granted by NRC
regulations to any person meeting the
general license criteria. No action is
required from these persons to obtain a
general license, and no license or
annual fees are applicable to persons
operating under this general license.
Self-Luminous Products
Although the SSR section similar to
10 CFR 30.19 includes an exemption for
previously acquired self-luminous
articles containing less than 3.7 kBq (0.1
µCi) of radium-226, 10 CFR 30.19 is not
being amended to include this
exemption. The basis for not including
this exemption is that, as currently
written, 10 CFR 30.19 only applies to
products manufactured and distributed
under a specific license issued under 10
CFR 32.22. The SSR exemption does not
require that these products be
previously manufactured and
distributed under a specific license, nor
do the SSRs provide for such a license
with regard to radium-226. Instead, the
possession, use, and transfer of these
items will be subject to the general
license for certain items and selfluminous products containing radium226 established in 10 CFR Part 31.
Smoke Detectors
Smoke detectors are included in the
class exemption in 10 CFR 30.20 for gas
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and aerosol detectors. This exemption is
being revised to include previously
manufactured detectors containing
radium-226. The provision for smoke
detectors is different from the SSRs in
that the SSRs contain a specific limit of
3.7 kBq (0.1 µCi) for radium-226 that
manufacturers may incorporate into the
currently manufactured detectors.
However, the SS&D registry includes
certificates for smoke detectors
categorized as exempt containing up to
74 kBq (2 µCi) of radium-226. While
some of these certificates are categorized
as ‘‘Active,’’ meaning that continued
distribution is permitted, a survey of the
States with these certificates confirmed
that the distribution of radium-226 in
smoke detectors was, in fact, a past
practice. The provision added to 10 CFR
30.20 for detectors containing radium226 is limited to detectors previously
manufactured and distributed under a
specific license issued by a State under
comparable provisions to 10 CFR 32.26.
Thus, similar standards were used in
approving distribution of these detectors
for use under an exemption from
licensing. This exemption does not
cover smoke detectors manufactured
earlier with larger quantities of radium226 and authorized for use under a
general or specific license, or smoke
detectors that may not have been
distributed under a specific license.
Distribution to Exempt Persons
The NRC retains the authority for
authorizing distribution of products and
materials where the end user is exempt
from licensing and regulatory
requirements by regulation in 10 CFR
150.15(a)(6), which states, in part, that
persons in Agreement States are not
exempt from the Commission’s
licensing and regulatory requirements
with respect to the transfer of
possession or control of any equipment,
device, commodity, or other products
containing byproduct material to
persons who are exempt from licensing
and regulatory requirements of the
Commission. The NRC does not transfer
this authority when a State enters into
an Agreement with the NRC. Therefore,
persons who initially transfer products
containing byproduct material to
persons who are exempt from licensing
must have a license from the NRC
authorizing these activities. These
distributors also need a specific license
from either an Agreement State or from
the NRC authorizing the possession and
use of the byproduct material. As a
result of the expansion of the definition
of Byproduct material, the distribution
of NARM to exempt persons, including
distribution by licensees in Agreement
States, will also be authorized only by
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the NRC. Currently, the States have only
a few licensees authorized to distribute
to persons exempt from licensing
requirements. These are for exempt
quantities of accelerator-produced
radioactive material. In finalizing this
rule, the NRC has determined that most,
if not all, of these distribution licensees
already have an NRC license under 10
CFR 32.18 authorizing the distribution
of exempt quantities of pre-EPAct
byproduct material. For these
distribution licensees, only a simple
amendment of those NRC licenses will
be required as a result of this aspect of
this final rule.
Existing General Licenses
General License for Devices in 10 CFR
31.5
Section 31.5 is the primary general
license provision in 10 CFR Part 31. It
covers a broad range of devices
‘‘designed and manufactured for the
purpose of detecting, measuring,
gauging, or controlling thickness,
density, level, interface location,
radiation, leakage, or qualitative or
quantitative chemical composition, or
for producing light or an ionized
atmosphere.’’ These devices must be
distributed under specific licenses
issued under 10 CFR 32.51 or equivalent
regulations of an Agreement State.
There are numerous SS&D certificates
for devices containing NARM that have
been approved by the States for use
under a general license. These are
almost all for devices containing cobalt57, sodium-22, or radium-226. In many
cases, models have been approved
which are authorized to contain one of
these radionuclides or one or more other
radionuclides that were byproduct
material before the EPAct. They have
been evaluated under equivalent, in
most cases, or at least comparable,
standards by the States. The rule will
accommodate generally licensed devices
meeting the restrictions of the general
license that were previously approved
by the States under comparable
provisions to 10 CFR 32.51. Active
certificates would stand with
amendments, if needed, being made to
the distributors’ licenses to cover the
new categories of byproduct material.
Any new certificates would be issued by
the NRC or the Agreement States under
the AEA encompassing the new
definition of Byproduct material.
The criteria for registration of
generally licensed devices under 10 CFR
31.5(c)(13)(i) are revised to include a
criterion for registration by general
licensees of devices containing 3.7
megabecquerels (MBq) (0.1 millicurie
(mCi)) or more of radium-226. This
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registration process is separate and quite
different from the SS&D registry. It
requires physical inventories and
certification of device information by
general licensees, allows the NRC and
Agreement States with equivalent
regulations to more fully track generally
licensed devices meeting these criteria,
and serves to remind general licensees
of their responsibilities under the
general license. SS&D certificates for
generally licensed devices that will now
come under 10 CFR 31.5 include
devices with more than 3.7 MBq (0.1
mCi) of radium-226. These devices will
be subject to the registration
requirement in 10 CFR 31.5(c)(13).
Other certificates, which include
devices with radium-226, allow only
much smaller quantities. These devices
will not be required to be registered.
This criterion for registration of radium226 was chosen because of the low
concentration levels which typically are
required for decontamination and
decommissioning involving radium-226,
as well as the relative dispersibility of
radium-226. A principal purpose of the
registration process concerns reducing
losses of devices that could significantly
contaminate a smelter, if inadvertently
melted. The NRC does not believe there
are accelerator-produced materials used
in significant quantities in these types of
generally licensed devices to warrant
registration.
Distributors of NARM have typically
also been distributors of pre-EPAct
byproduct material. Many of them have
not excluded information about
transfers of devices containing NARM
from reports of transfers made to the
NRC on generally licensed devices
transferred into the NRC jurisdiction.
Therefore, the NRC already has
information on some of these devices in
its general license tracking system. The
NRC will work with the States to
examine methods to include State
information. It is expected that the
registration process will identify
additional devices containing registrable
quantities of radium-226, as users in
many cases will already be registering
other devices with the NRC containing
other radionuclides and will need to
add devices containing radium-226
during the registration process. The
requirements in 10 CFR 32.51, 32.51a,
and 32.32 applicable to the manufacture
or initial transfer of these devices did
not need revision to accommodate
NARM.
Calibration and Reference Sources in 10
CFR 31.8
Section 31.8 provides a general
license for the use of up to 185 kBq (5
µCi) of americium-241 in calibration
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and reference sources. This final rule
adds radium-226 to 10 CFR 31.8,
consistent with the SSRs. This general
license is only applicable to specific
licensees that have calibration and
reference sources as defined in 10 CFR
31.8, and simply eliminates certain
administrative requirements to address
these sources under the specific license.
The sources are covered by
requirements applicable under the
specific license, as well as additional
requirements in 10 CFR 31.8. The
requirements in 10 CFR 32.57, 32.58,
32.59, and 32.102 applicable to licenses
to manufacture or initially transfer these
sources are also amended to include
radium-226.
General License for In Vitro Test Kits in
10 CFR 31.11
In keeping with the equivalent section
of the SSRs, cobalt-57, in units not
exceeding 370 kBq (10 µCi) each, is
added to the general license in 10 CFR
31.11 for use in certain in vitro clinical
or laboratory testing. Also, the
requirements in 10 CFR 32.71, which
provide the licensing criteria for the
manufacturer and distributor of the
products used under this general
license, are revised to apply to the
cobalt-57 products included in the
general license.
New General License for Certain Items
and Self-Luminous Products Containing
Radium-226
The Commission specifically
requested information on the types and
quantities of products containing
radium-226 and any information that
could assist the NRC in more fully
evaluating the potential impact to
public health and safety and the
environment due to activities involving
radium-226 sources. As discussed
earlier, the general license provisions
for radium-226 timepieces were
changed to remove, from the proposed
rule, a limitation on the number of
timepieces that could be possessed. In
response to public comment, the general
license provision within this section for
luminous gauges and other luminous
products containing radium-226 was
also changed with respect to the
categories of products covered and the
numbers of products allowed to be kept
at any one location. This is discussed in
this document under the section,
‘‘Summary and Analysis of Public
Comments on the Proposed Rule.’’
Because 10 CFR 31.2 delineates the
applicability of specific provisions in 10
CFR part 30 to the general licenses of 10
CFR part 31, an exemption from the
reporting and recordkeeping
requirements of 10 CFR 30.50 and 30.51
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is added to further reduce the regulatory
burden on stakeholders. Furthermore,
because many of the circumstances that
would require reporting under 10 CFR
30.50 are unlikely to occur, the NRC
believes that it is unnecessary to apply
these requirements to this general
license and that the reporting
requirements in 10 CFR 31.12 are
adequate.
The new section added to 10 CFR part
31 provides a general license to any
person for other products and discrete
sources containing radium-226 that are
not exempted, and are apparently in the
public domain, but were not otherwise
covered under a license and are not
specifically addressed in the SSRs. The
general license includes: (1) Antiquities
originally intended for use by the
general public and distributed in the
late 19th and early 20th centuries, such
as radium emanator jars, revigators,
radium water jars, radon generators,
refrigerator cards, radium bath salts, and
healing pads; (2) Nonintact luminous
timepieces and timepiece hands and
dials not contained in timepieces; (3)
Luminous gauges and other items
containing radium-226 installed in air,
marine, or land vehicles (These include
airplanes, helicopters, jeeps, trucks,
tanks, ships, landing vessels, artillery
pieces, and any other former military
use vehicle no longer in control of the
military.); (4) All other luminous
products, provided that no more than
100 are used or stored at the same
location at any one time; and (5) Small
radium sources containing no more than
37 kBq (1 µCi) of radium-226 as discrete
survey instrument calibration sources,
sources contained in radiation
measuring instruments, sources used in
educational demonstrations (such as
cloud chambers, and spinthariscopes),
electron tubes, lightning rods, ionization
sources, and static eliminators. As
discussed earlier, this general license
allows any person to acquire, receive,
possess, use, or transfer radium-226
contained in the previously mentioned
products. Persons who receive, possess,
use, or transfer the radium-226 items
under the general license are exempt
from the provisions of 10 CFR parts 19,
20, 21, and 10 CFR 30.50 and 30.51 to
the extent that the receipt, possession,
use, or transfer is within the terms of the
general license.
The general license prohibits the
manufacture, assembly, disassembly,
repair, or import of products containing
radium-226 except for the repair of
timepieces; prohibits export under the
general license; and requires that the
product only be disposed of by transfer
to a specific licensee authorized to
receive it or to a disposal facility
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authorized to dispose of the material in
accordance with any Federal or State
solid or hazardous waste law. The
general license also prohibits
abandonment of the product. The
general license requires notifying the
NRC if there is any indication of a
possible failure of, or damage to, the
product that could result in a loss of the
byproduct material and requires persons
possessing these devices under the
general license to respond to written
requests for information from the NRC.
It should be noted that 10 CFR 31.2
delineates the terms and conditions of
10 CFR part 30 which apply to general
licensees. These provisions generally
will not require general licensees to
initiate any actions.
It is the NRC’s intent, through the
general license provision, that the
Agreement States, to a large extent, will
be able to maintain the existing ‘‘status
quo’’ in regulating these categories of
discrete sources of radium-226. The
Agreement States may continue with
their programs, including requiring a
specific Agreement State license or
decommissioning plan when larger
numbers of products may be involved or
significant contamination of property
has resulted.
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Specifically Licensed Sealed Sources
and Devices
Registration of Safety Information and
Licensing of Sealed Sources and Devices
The NRC is revising 10 CFR 30.32(g)
to allow for the specific licensing of
sealed sources and devices containing
NARM that were previously regulated
by the States. Sources and devices
registered by the States may be licensed
under 10 CFR 30.32(g)(1), and the user
is only required to provide the
manufacturer and model number as
registered in the SS&D registry.
A new paragraph (3) is also being
added to 10 CFR 30.32(g) to allow for
the licensing of sealed sources and
devices containing NARM for which all
of the information otherwise required is
not available. This second provision has
been added in this final rule as a result
of public comment. Previously, if a
source or device were not registered in
the SS&D registry, the applicant who
wanted to use the source or device
would be required to submit all of the
safety information identified in 10 CFR
32.210(c), because this information had
not been submitted previously by the
manufacturer or distributor as part of
registering the source or device. For
older ‘‘legacy’’ devices for which the
manufacturer is no longer in existence,
it may be impossible to provide all of
the categories of information identified
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in 10 CFR 32.210, as required by 10 CFR
30.32(g)(2). The provision being added
as 10 CFR 30.32(g)(3) delineates
additional information that will be
required to license a source or device for
which all of the information previously
required is not available. The
information must include a description
of the source or device, a description of
radiation safety features, intended use
and associated operating experience,
and results of a recent leak test. The
NRC licensing staff will review the
submitted information to make a
licensing decision regarding possession
and use of the source and device. This
new provision is only applicable to
sources and devices containing NARM
manufactured before the effective date
of this final rule.
The information to be provided must
demonstrate that there is reasonable
assurance that the radiation safety
properties of the source or device are
adequate to protect health and minimize
danger to life and property. The amount
of detail needed to make this finding
will depend on such things as the
nature of the source or device and the
amount of information identified in 10
CFR 32.210(c) that is available.
However, generally, the source or device
description might include the
radionuclide(s), source activity,
chemical and physical form,
manufacturer’s name, distributor’s
name, model number, construction
details such as source or device
dimensions, source encapsulation, any
labeling, and a radiation profile. A
description of device radiation safety
features might include shielding, on-off
mechanisms or indicators, methods for
locking beam shutters, any safety
warning labels, type of installation
including method of attachment to its
mounting if installed in a fixed location
and means of relocation if portable, and
any automatic safety features. The
description of the intended use of the
source or device could include how the
source or device is used, the types of
users, the locations of use, the occasions
when persons will be near the device
and the frequency of these occasions,
and the likely environments to which
the source or device will be subjected
during normal use and likely accident
conditions. A description of associated
operating experience using the source or
device should describe how the device
has been used, particularly if the device
will be used in this manner in the
future, should include routine
maintenance procedures and how
frequently performed, should note any
operating problems and their resolution,
and should identify any parts that were
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repaired or replaced. A description of a
recent leak test should identify when
the swipe was taken and evaluated and
describe how the leak test swipe was
taken, the results, and who conducted
the evaluation.
Applicants are not authorized to
remove sources from a device to obtain
source details, unless qualified and
specifically authorized to perform these
activities under a license. For
‘‘uncontained’’ sources, applicants will
need to use caution and minimize
exposure time when attempting to
gather details or information directly
from the source.
Regulating the Accelerator-Produced
Radioactive Material Used in Medical
Activities
When reviewing the public
comments, it was clear that the
discussion in the proposed rule of the
NRC’s existing regulatory framework for
medical products, the distinction
between radionuclide production
licensing and radioactive drug
production licensing, and the
commercial and noncommercial
distribution provisions, as well as the
introduction of the term ‘‘consortium,’’
were confusing to commenters. In
addition to responding to individual
comments on these subjects in the
‘‘Summary and Analysis of Public
Comments on the Proposed Rule’’
section of this document, the following
discussion is provided to give a clearer
overview of the NRC’s regulatory
framework than was provided in the
proposed rule discussion, particularly
with respect to the delineation between
production of radionuclides and
radioactive drugs.
Section 651(e) of the EPAct requires
the NRC to consider the impact of its
regulations on the availability of
radioactive drugs to physicians and
patients. After consideration, the NRC
concluded that its well established
regulatory framework for the
production, distribution, and use of in
vitro test kits, radioactive drugs (which
include biologics), and SS&Ds for
medical use activities involving
byproduct material is also appropriate
in large part to similar products
containing accelerator-produced
radioactive materials. Using the existing
regulations could, with minor changes,
minimize the impact on the availability
of radioactive drugs containing
accelerator-produced radionuclides.
Therefore, this regulatory framework is
applied to the producers, distributors,
and medical users of in vitro test kits,
radionuclides, radioactive drugs, and
SS&Ds containing NARM that are
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included in the EPAct’s expanded
definition of Byproduct material.
Radionuclide Production
The preexisting regulatory framework
is directly applicable to the commercial
production and distribution of NARM
radionuclides. Longer-lived acceleratorproduced radionuclides used in
medicine may include: thallium-201,
cobalt-57, and palladium-103. The
shorter half-life PET radionuclides may
include: fluorine-18, oxygen-15, and
carbon-11. The production of
radionuclides by accelerators (including
PET radionuclides from cyclotrons), as
well as the subsequent possession and
use of these radionuclides, will be
licensed under existing requirements in
10 CFR part 30. The producer of the
accelerator-produced radionuclides
(including PET radionuclides) can
transfer these radionuclides to
manufacturers and other specific
licensees under the provisions of 10
CFR 30.41. This includes both
commercial and noncommercial
distribution of accelerator-produced
radionuclides (including PET
radionuclides) to specifically licensed
universities and research laboratories
for basic research but not for use on
human beings, which is specifically
excluded in the definition of Research
and development in 10 CFR 30.4.
These radionuclide production
facilities include commercial nuclear
pharmacies with PET centers, i.e.,
facilities with cyclotrons used to
produce PET radionuclides. The NRC
will review applications and the
associated radiation safety programs of
these radionuclide production facilities
in accordance with the criteria in 10
CFR 30.33 and other existing
requirements such as 10 CFR parts 19
and 20. In meeting the general training
and experience requirement in 10 CFR
30.33(a)(3), these applicants will need to
have individuals with training and
experience in the production of PET
radionuclides, i.e., the processes from
insertion of targets in the accelerator or
cyclotron to radiochemical isolation,
purification, and testing. Individuals,
such as radiochemists, physicists,
engineers, and others identified by the
applicant with appropriate training and
experience, will be recognized as
authorized users (AUs) under the
manufacturer’s, producer’s, or
pharmacy’s 10 CFR part 30 license for
the production of accelerator-produced
radionuclides (including PET
radionuclides) using cyclotrons or other
types of accelerators. To ensure the
continued availability of acceleratorproduced radionuclides used to
manufacture or prepare radioactive
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drugs, it is expected that individuals,
who can demonstrate that they
performed the radionuclide production
activities using an accelerator at a
radionuclide production facility under
the NRC’s waiver (70 FR 51581; August
31, 2005), will be recognized as AUs as
long as their duties and responsibilities
do not significantly change. The
applicant will be required to document
that these individuals were responsible
for the production of radionuclides
using a cyclotron or accelerator when
the waiver was in effect.
The NRC is distinguishing between
the ‘‘production of radionuclides’’ and
‘‘preparation of radioactive drugs.’’
Production of radionuclides, which
would include production of PET
radionuclides using a cyclotron (or
other accelerator), is regulated under 10
CFR part 30. Preparation of radioactive
drugs for medical use from
radionuclides, including PET
radionuclides, is regulated under 10
CFR 32.72 and 10 CFR part 35.
Preparation of radioactive drugs for
medical use may occur at locations
other than the production facility. In the
proposed rule, 10 CFR 32.72 included a
provision to authorize commercial
nuclear pharmacies that were not
registered with FDA or registered with
a State as a PET drug production facility
to produce PET radionuclides if their
radiation safety programs meet the
criteria in 10 CFR 30.33. However, the
purpose of 10 CFR 32.72 is to address
the criteria and requirements for the
production and commercial distribution
of radioactive drugs for medical use,
and not the production of radionuclides.
Therefore, the final rule does not
include this provision. Based on a
review of the requirements in 10 CFR
part 30, no revisions to the regulations
are needed to license PET radionuclide
production under 10 CFR part 30.
10 CFR Part 32 Specific Production and
Distribution Requirements.
Byproduct material may be
transferred under 10 CFR 30.41 from
one specific licensee to another person
authorized to receive the material.
However, not all transfers can be made
under this provision, and certain
transfers (or distributions) require that
the manufacturer, preparer, or
distributor meet specific provisions of
10 CFR part 32. Specifically, a
commercial radioactive drug
manufacturer or a commercial nuclear
pharmacy must obtain a distribution
license issued under 10 CFR 32.71 to
distribute certain in vitro test kits to
generally licensed medical and
veterinary clinical laboratories, and a
medical distribution (MD) license
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issued under 10 CFR 32.72 to
commercially distribute radioactive
drugs to 10 CFR part 35 (and equivalent
Agreement State) medical use licensees.
The proposed rule included revisions to
the qualifications for a licensee to obtain
a 10 CFR 32.72 MD license to more
accurately describe the FDA registration
criteria and to include licensees
registered with a State as a PET drug
production facility. These provisions are
unchanged in the final rule. No changes
are necessary for MD licenses issued to
medical SS&D manufacturers under 10
CFR 32.74. The MD licenses issued
under 10 CFR 32.72 and 10 CFR 32.74
authorize distribution for medical use
(10 CFR part 35 and equivalent State)
licensees. Under the NRC’s licensing
practice, most of the 10 CFR part 32
distribution licenses do not authorize
the possession and use of byproduct
material; rather, separate 10 CFR part 30
licenses are issued for this purpose.
PET radioactive drugs are made with
radionuclides that are usually very short
lived. In addition to the commercial
drug manufacturers and commercial
nuclear pharmacies, individual
hospitals, educational institutions, and
Federal facilities may have cyclotrons
used to produce PET radionuclides and
may also prepare PET drugs from these
PET radionuclides. Although most PET
radionuclides are very short lived,
certain PET radionuclides with longer
half-lives may be transported from the
production facility to the user’s site. The
longer-lived PET radionuclides may also
be combined with nonradioactive
chemicals and biologics to produce new
PET radioactive drugs. Hence, there are
production and commercial
distributions of some PET radioactive
drugs (e.g., fluorine-18 deoxyglucose) to
medical users (10 CFR part 35
licensees).
Consortiums and Noncommercial
Distribution
The extremely short-lived
radionuclides used for medical use have
to be made into drugs and administered
immediately after production,
essentially necessitating that the
cyclotron be located in the medical
facility or in very close proximity. Some
educational institutions, medical use
facilities, or Federal facilities may form
‘‘consortiums’’ with adjacent or nearby
hospitals to jointly own or share in the
operation and maintenance costs of the
PET radionuclide production facility.
‘‘Consortium’’ in this context means an
association of medical use licensees,
and a PET radionuclide production
facility, in the same geographical area,
that jointly own or share in the
operation and maintenance cost of the
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PET radionuclide production facility
that produces PET radionuclides, for
use in producing radioactive drugs
within the consortium, for
noncommercial distributions among its
associated members for medical use.
The PET radionuclide production
facility within the consortium must be
located at an educational institution or
a Federal facility or a medical facility.
These facilities may produce PET
radionuclides and radioactive drugs for
members of their consortium and make
these PET radionuclides and drugs
available to these associated facilities
through noncommercial distributions.
Before this rulemaking, the NRC’s
regulations did not allow for the
noncommercial distribution of
radioactive drugs to medical use
licensees. The NRC’s regulations in 10
CFR 32.72 for the manufacture,
preparation, or transfer of radioactive
drugs cover only commercial
distribution. Medical uses of drugs
under 10 CFR 35.100, 35.200, and
35.300 were previously limited to drugs
obtained from a 10 CFR 32.72 licensee,
or Agreement State equivalent, or
prepared by the medical use licensee
under specific provisions in 10 CFR part
35. Because the NRC did not allow
noncommercial distribution of
radioactive drugs, failure to address
noncommercial distribution of PET
radioactive drugs in the this final rule
would impact the availability of these
drugs to physicians and patients.
Therefore, the NRC developed a new
regulatory process based upon existing
practices to minimize impact on the
noncommercial distribution of PET
radioactive drugs to medical use
licensees within such a consortium. In
accordance with this process, a part 35
medical use facility that uses its own
cyclotron to produce PET radionuclides
for use under its own medical use
license, would not need to be licensed
for medical distribution under 10 CFR
32.72, but it would have to be
specifically authorized under 10 CFR
part 30 for the production of PET
radionuclides.
The definition of Consortium
incorporates the unique features
associated with the noncommercial
distribution of PET radioactive drugs.
For example, the consortium members
must be in the same geographical area
because of the short half-lives of PET
radionuclides, e.g., 1.8 hours for
fluorine-18, 20 minutes for carbon-11,
and 2 minutes for oxygen-15. The
location of the PET radionuclide
production facility is limited to an
educational institution or a Federal
facility or a medical facility because
these are the noncommercial facilities
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that would have cyclotrons that could
produce PET radionuclides.
The NRC will review PET
radionuclide production applications
and their radiation safety programs in
accordance with the criteria in 10 CFR
30.32 and 30.33 and other applicable
requirements. In the proposed rule, only
the noncommercial transfer of PET
radioactive drugs between 10 CFR part
35 medical use licensees was
considered. However, the NRC
recognized that the entity within the
consortium with the PET production
operation may not be a medical
licensee, but a university or Federal
facility. In addition, the radionuclide
production facility requires a specific
license under 10 CFR part 30. For this
reason, the labeling provisions in 10
CFR 35.69, which would only have
applied to medical licensees, were
relocated from 10 CFR part 35 to 10 CFR
part 30.
The new definition of Consortium and
the provisions for noncommercial
distribution are added to 10 CFR 30.4,
30.32, and 30.34 to allow for
authorization of the production of PET
radioactive drugs for noncommercial
transfer to medical use licensees within
a consortium. Thus, under these new
provisions, a medical use facility,
educational institution, or Federal
facility with a licensed PET
radionuclide production facility within
its consortium does not need a medical
distribution license under 10 CFR 32.72
if it intends to transfer PET radioactive
drugs to members of its consortium. If
it intends to commercially distribute
PET radioactive drugs or distribute to
medical licensees outside of its
consortium, then a medical distribution
license under 10 CFR 32.72 would be
required. In any event, a specific
authorization would be required to
produce the PET drugs for
noncommercial transfer to medical use
licensees within its consortium. The
requirements for authorization to
produce PET drugs for noncommercial
transfer to consortium members and the
definition of Consortium are being
added to 10 CFR 30.4. Specific
requirements applicable to this licensed
activity are added to 10 CFR 30.34(j).
These requirements parallel the
requirements for the commercial
distribution of PET radioactive drugs,
e.g., the licensee is qualified to produce
radioactive drugs, the labeling contains
consistent information, transport
containers are adequately shielded, and
radioactivity is accurately determined.
Noncommercial distribution of PET
radioactive drugs within a consortium
may occur among members that are
located in the same geographical area
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55877
even if in different jurisdictions (e.g.,
Federal facility or other NRC licensees
and Agreement State licensees). Thus,
these new provisions are being assigned
a Compatibility Category B.
Minor revisions were proposed to 10
CFR part 35 to permit medical use
facilities to receive PET radioactive
drugs by noncommercial transfer and to
permit the medical use licensee to use
activity values or activity concentration
values for these PET radioactive drugs
based on the measurements made by a
PET radioactive drug producer within
its consortium. The final rule also
includes these provisions (in 10 CFR
35.65(b)(2) and (c)(3), 35.100(a),
35.200(a), and 35.300(a)), but the
provisions are revised to clarify that the
PET radioactive drugs have been
produced by, and the measurements
made by, the licensee authorized under
10 CFR 30.32(j) to produce PET
radioactive drugs for noncommercial
transfer to members of its consortium.
Authorized Nuclear Pharmacists (ANPs)
and Authorized Users (AUs).
No regulatory changes were needed
for ANPs to use all byproduct material
(i.e., reactor-produced radionuclides,
PET radionuclides, and other
accelerator-produced radionuclides) to
prepare PET radioactive drugs and other
radioactive drugs under the practice of
pharmacy. Medical use licensees that
receive PET radionuclides that are
added to ‘‘cold kits’’ may continue to
prepare them under the same
authorization in 10 CFR 35.100(b),
35.200(b), and 35.300(b) as other
unsealed byproduct materials for
medical use. However, a minor revision
was made to each of these sections to
clarify that the ANP and the qualified
AU were not authorized under these
sections to produce radionuclides.
Further, to ensure the availability of
radioactive drugs made from
accelerator-produced radionuclides,
nuclear pharmacists responsible for the
preparation of only PET or other NARM
radioactive drugs under the NRC’s
waiver (70 FR 51581; August 31, 2005)
will be ‘‘grandfathered’’ and will not be
required to meet the new training and
experience requirements as long as their
duties and responsibilities under the
new license do not significantly change.
The ‘‘grandfathering’’ provisions are
included in the revised provisions of 10
CFR 35.57 and 10 CFR 32.72(b)(4). The
licensee is required by 10 CFR
32.72(b)(5) or 10 CFR 35.14(a) to
document that these individuals were
responsible for the preparation of only
PET or other NARM radioactive drugs
when the waiver was in effect.
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To ensure a smooth transition and
availability of radioactive drugs and
sealed sources made from acceleratorproduced radionuclides for medical use,
those individuals, i.e., physicians,
podiatrists, dentists, and radiation
safety officers (RSOs), who used only
NARM byproduct materials for medical
uses under the NRC’s waiver (70 FR
51581; August 31, 2005) will also be
‘‘grandfathered’’ in 10 CFR 35.57 as long
as their duties and responsibilities do
not change significantly. These new
grandfathering provisions are limited to
those who used only NARM during the
waiver, because any prior use of ‘‘old’’
byproduct material would have been
subject to the existing requirements for
being an AU or ANP or RSO.
These grandfathering provisions were
in the proposed rule. However, the final
rule does not include revisions to the
definition of an Authorized user or
Authorized nuclear pharmacist in 10
CFR 35.2. The NRC concluded that the
definitions did not need to be revised
because the grandfathering provisions
for the RSOs, medical physicists,
nuclear pharmacists, physicians,
dentists, and podiatrists, who used only
accelerator-produced radioactive
material, were included in 10 CFR
35.57. Language has been added to 10
CFR 35.57 to clarify that these
individuals qualify as AUs and ANPs
for purposes of the regulations in part
35. In addition, these individuals could
continue to work as AUs, Authorized
medical physicists (AMPs), or ANPs
under the notification provisions of 10
CFR 35.13 and 10 CFR 35.14.
The radiation safety knowledge
needed to safely use NARM for medical
uses or for use in the practice of
pharmacy is similar to that for other
byproduct material. Therefore,
individuals who only used NARM
radioactive drugs or sealed sources in
the practice of medicine or pharmacy
will be authorized for use of all similar
byproduct material for the same uses.
The reverse is also true that individuals
already authorized to use byproduct
material in 10 CFR part 35 for medical
use or for use in the practice of
pharmacy are authorized to use NARM.
Further, no changes were made to the
training and experience criteria in 10
CFR part 35 for any authorized
individual.
Actions Taken To Ensure Availability of
Accelerator-Produced Radioactive Drugs
In summary, to minimize the
regulatory impact on the availability of
accelerator-produced radioactive drugs,
the NRC is taking the following actions:
(1) Applying its established regulatory
framework to the commercial
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distribution of these drugs; (2)
expanding the regulations to permit
production of PET drugs by medical use
licensees, educational institution
licensees, and Federal licensees for
noncommercial distribution to members
of their consortium; (3) permitting
medical use licensees to use activity or
activity concentration values measured
by the PET radioactive drug producer in
their consortium when determining
dosages; (4) ‘‘grandfathering’’ current
medical and pharmacy users of
accelerator-produced radioactive drugs;
and (5) retaining the existing training
and experience criteria in 10 CFR part
35 for authorized individuals.
In addition, as discussed under
‘‘Implementation Strategy’’ in this
document, the NRC is revising Parts 30,
32, and 35 to authorize persons that
used accelerator-produced radioactive
material under the NRC’s waiver (70 FR
51581; August 31, 2005) to continue to
use these materials after the waiver is
terminated, provided that these persons
apply for a license or request for a
license amendment within the allotted
time frames. This regulatory provision
allows all persons, including those who
manufacture, produce, transfer, receive,
acquire, own, possess, or use these
materials, to continue with their
activities including medical activities
until the NRC makes its final licensing
decision. This provision also ensures
the availability of accelerator-produced
radionuclides, radioactive drugs, and
sealed sources and devices used for
medical uses.
Amendments and Notifications for PET
Radionuclide Production and Delivery
Lines
The NRC reviewed its regulations in
10 CFR Part 35 to determine if there
were radiation safety provisions in its
existing regulations that needed revision
to incorporate unique radiation safety
issues associated with the use of
accelerator-produced radionuclides for
medical use. The medical use of
extremely short-lived radionuclides,
e.g., oxygen-15, requires that a PET
radioactive drug containing this
radionuclide be administered in the
imaging and localization medical use
area (10 CFR 35.200) immediately after
the radionuclide is produced by the
cyclotron and processed as a radioactive
drug. This necessitates that the medical
use area be co-located with the
cyclotron or have a PET radioactive
drug delivery line from the PET
radionuclide production/PET
radioactive drug processing area. This
introduces the potential for a high
radiation area in a medical use area that
would otherwise be a low radiation
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area. This is a unique situation and was
not envisioned when the NRC
developed the requirements that
permitted licensees to make changes in
the areas where byproduct material is
used only in accordance with 10 CFR
35.100 or 10 CFR 35.200 without
submitting a license amendment. As a
result, changes have been made to the
requirements in revised 10 CFR 35.13,
‘‘License amendments,’’ 10 CFR 35.14,
‘‘Notifications,’’ and 10 CFR 35.15,
‘‘Exemptions regarding Type A specific
licenses of broad scope.’’ The final rule
provides that an amendment is required
for a limited specific medical use
licensee in the unique situation
described previously if the changes
involved movement of the cyclotron or
a PET radioactive drug delivery line
from the PET radionuclide production/
PET radioactive drug processing area.
Changes to the typical 10 CFR 35.100
and 10 CFR 35.200 medical use areas
are not affected. Section 35.15 is revised
to clarify that a licensee possessing a
Type A specific license of broad scope
would not need to meet the notification
requirements in 10 CFR 35.14(b)(5) for
any changes to the area of use identified
in its application where byproduct
material is used in accordance with 10
CFR 35.100 or 10 CFR 35.200. This
provision was revised from the
proposed rule.
Strontium/Rubidium Generators
Contamination limits for strontium82/rubidium-82 generators and related
requirements consistent with similar
provisions of the SSRs are added to 10
CFR part 35. The contamination limits
are no more than 0.02 kBq of strontium82 per MBq of rubidium-82 chloride
injection (0.02 µCi of strontium-82 per
mCi of rubidium-82 chloride), or no
more than 0.2 kBq of strontium-85 per
MBq of rubidium-82 chloride injection
(0.2 µCi of strontium-85 per mCi of
rubidium-82). These limits and
requirements to measure the
contamination for compliance with
these limits are added to 10 CFR 35.204,
with corresponding recordkeeping
requirements added to 10 CFR 35.2204.
A corresponding provision for these
tests and associated recordkeeping is
also added to 10 CFR 30.34 for
nonmedical use licensees, such as
commercial nuclear pharmacies, using
these generators.
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Appendix B to Part 20—Annual Limits
on Intake (ALIs) and Derived Air
Concentrations (DACs) of Radionuclides
for Occupational Exposure; Effluent
Concentrations; Concentrations for
Release to Sewerage
The comparable provisions in Part D
of the SSRs do not include any new
accelerator-produced radionuclides
other than the ones already in 10 CFR
part 20, Appendix B. The NRC
considered whether some other
radionuclide-specific values should be
added to 10 CFR part 20, Appendix B.
Because nitrogen-13 and oxygen-15 are
two of the accelerator-produced
radionuclides that are produced for
medical uses, the NRC performed a
preliminary calculation of values based
on dose factors published in National
Council on Radiation Protection and
Measurements (NCRP) Report No. 123
on Screening Models for Releases of
Radionuclides to Atmosphere, Surface
Water, and Ground. Certain dose
conversion factors were not readily
available. Results from these
preliminary calculations yielded a
derived air concentration (DAC) based
on the submersion scenario for both
nitrogen-13 and oxygen-15 of about 1.48
× 10¥2 becquerels per milliliter (Bq/ml)
(4 × 10¥6 µCi/ml) for occupational
exposure and a corresponding effluent
concentration of 7.4 × 10¥4 Bq/ml (2 ×
10¥8 µCi/ml) for exposure of members
of the public. These calculated values
are larger than the default values for
DAC and effluent concentration by a
factor of 40 and 20, respectively, in 10
CFR part 20, Appendix B. Because the
approach used in calculating values for
nitrogen-13 and oxygen-15 is different
from that used for other radionuclides
included in 10 CFR part 20, Appendix
B, the NRC did not include adding
specific values for these radionuclides
in the proposed rule. Because certain
medical communities had expressed the
desire of having specific DACs for these
two radionuclides, the Commission
specifically requested public comment
on the default values, and whether it
should include larger specific values for
oxygen-15 and nitrogen-13 in the final
rule. As a result of comments, these
values have been added to 10 CFR part
20, Appendix B, in the final rule. This
is discussed further in this document
under ‘‘Summary and Analysis of Public
Comments on the Proposed Rule.’’
Emergency Planning
The regulations in 10 CFR 30.32(i)(1)
require applications for specific licenses
for byproduct material in unsealed form,
on foils or plated sources, or sealed in
glass in excess of the quantities in 10
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CFR 30.72, ‘‘Schedule C—Quantities of
radioactive materials requiring
consideration of the need for an
emergency plan for responding to a
release,’’ to contain either an evaluation
showing that the maximum dose to a
person offsite, due to a release of
radioactive materials, would not exceed
0.01 sievert (Sv) (1 rem) effective dose
equivalent or 0.05 Sv (5 rems) to the
thyroid, or an emergency plan for
responding to a release of radioactive
material. Schedule C also contains a
release fraction for each radionuclide
against which aspects of the evaluation
submitted in place of an emergency plan
must be compared in accordance with
10 CFR 30.32(i)(2).
Although Part P, ‘‘Contingency
Planning for Response to Radioactive
Material Emergencies,’’ of the SSRs
addresses an emergency plan, a value
for radium-226 is not specifically listed.
The NRC staff therefore considered
NUREG–1140, ‘‘A Regulatory Analysis
on Emergency Preparedness for Fuel
Cycle and Other Radioactive Material
Licensees,’’ dated August 1991.
NUREG–1140 was used as the technical
basis in a past rulemaking effort related
to quantities of radioactive materials
requiring an emergency plan. NUREG–
1140 provided the basis for 10 CFR
30.72 Schedule C values. Schedule C
also contains a default value for alpha
emitters of 74 gigabecquerels (GBq) (2
curies (Ci)) (with release fraction 0.001),
which would apply to discrete sources
of radium-226 absent a specific value
being added to the table. However, the
quantity value for radium-226 in
NUREG–1140 is 3.7 terabecquerels
(TBq) (100 Ci) along with a release
fraction value of 0.001. This final rule
adds radium-226 with the quantity 3.7
TBq (100 Ci) and release value 0.001 to
10 CFR 30.72 Schedule C, which is
consistent with the technical basis for
the original emergency planning
requirements. It is expected that few, if
any, licensees, or applicants for a
license, would have 3.7 TBq (100 Ci) of
discrete sources of radium-226. Because
the ‘‘rule of ratios’’ applies (See
Footnote 1 to 10 CFR 30.72), licenses
authorizing other byproduct material, in
quantities approaching values that
would require emergency planning,
which are being amended to add
significant quantities of discrete sources
of radium-226, could potentially result
in authorizing total quantities of
byproduct material that would meet the
criteria for emergency plan
requirements. It is not expected that
accelerator-produced radioactive
materials are used in significant enough
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quantities to affect the applicability of
emergency plan requirements.
Low-Level Radioactive Waste and
Decommissioning
Low-Level Radioactive Waste
Section 651(e)(3) of the EPAct
mandates that the newly added
byproduct material is not considered to
be low-level radioactive waste for the
purposes of the Low-Level Radioactive
Waste Policy Amendments Act (42
U.S.C. 2021b) (LLRWPAA). The intent
of this provision is that the newly added
byproduct material is not to be impacted
by the compact process of the
LLRWPAA. This provision does not
have an impact on the NRC’s policy and
requires only a minor change to the
regulations to ensure that the term ‘‘lowlevel radioactive waste,’’ when used in
the NRC’s requirements, does not
include the newly added byproduct
material.
Although the newly added byproduct
material is not considered low-level
radioactive waste, it does pose a similar
hazard, and it does need to be disposed
of appropriately. Section 651(e)(3) of the
EPAct requires that the newly added
byproduct material must be disposed of
in a facility that: (1) Is adequate to
protect public health and safety; and (2)
is licensed by the Commission or by an
Agreement State. Even though it is not
low-level radioactive waste, this
provision clarifies that the newly added
byproduct material is to be disposed of
in a facility licensed by the NRC under
10 CFR part 61 or the Agreement State
requirements, which are compatible to
10 CFR part 61. This provision also
allows for the disposal of the newly
added byproduct material in a facility
licensed by the NRC under other parts
of the NRC’s regulations, such as
facilities licensed under 10 CFR part 40,
Appendix A.
To ensure that disposal facilities
licensed under 10 CFR part 61 continue
to be adequate to protect public health
and safety, the NRC must consider the
specific health and safety issues
associated with disposal of discrete
sources of radium. Rather than making
any changes to 10 CFR part 61 at this
time, the NRC will evaluate any specific
disposals of discrete sources of radium
at an NRC-licensed disposal facility
under 10 CFR 61.58, ‘‘Alternative
requirements for waste classification
and characteristics.’’ The NRC has not
identified any other radionuclides being
added to the definition of Byproduct
material that require any specific
evaluations to ensure the proper
disposal of waste in accordance with 10
CFR part 61.
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Notwithstanding the previously
mentioned provisions for the NRC or
Agreement State licensing of the
disposal facility for the newly added
byproduct material, Section 651(e)(3) of
the EPAct does not affect the authority
of any entity to dispose of the newly
added byproduct material at a disposal
facility in accordance with any Federal
or State solid or hazardous waste law,
including the Solid Waste Disposal Act.
This means that Federal and State solid
or hazardous waste laws can continue to
be used as an authority to permit
disposal of this newly added byproduct
material. Disposal solutions already in
place to allow disposal of the newly
added byproduct material are unaffected
by the EPAct. To implement this
provision of the EPAct, the NRC is
changing its regulations in 10 CFR Part
20 to redefine Waste to allow disposal
of the newly added byproduct material
in the NRC-regulated disposal facilities
or in a disposal facility permitted under
Federal or State solid or hazardous
waste laws.
Appendix G of 10 CFR Part 20, the
uniform manifesting requirements for
low-level radioactive waste, includes
numerous requirements containing the
words ‘‘low-level radioactive waste’’
and ‘‘waste.’’ This is potentially
confusing because the newly added
byproduct material is not low-level
radioactive waste in accordance with
the provisions of the EPAct. However,
no changes have been made to
Appendix G to 10 CFR Part 20. The text
changes made to the 10 CFR Part 20
regulations to clarify that the newly
added byproduct materials are not ‘‘lowlevel radioactive waste’’ make it clear
that the Appendix G to 10 CFR Part 20
requirements must be met if any of the
newly added byproduct material waste
is to be disposed of at a facility licensed
under 10 CFR Part 61 or an equivalent
Agreement State rule.
Decommissioning Issues
The inclusion of accelerator-produced
radioactive material that is used for a
commercial, medical, or research
activity, in the definition of Byproduct
material, requires the NRC to ensure
that decommissioning funding is
adequate at accelerator facilities to
adequately decontaminate and
decommission their facilities for license
termination. Radioactive materials
produced in accelerator facilities, that
are produced, extracted or converted
after extraction for use for commercial,
medical, or research purposes and that
are no longer residing in the accelerator,
are not a concern for decommissioning.
However, materials intentionally or
incidentally made radioactive as a result
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of the production of the radioactive
materials for use for commercial,
medical, or research purposes must be
managed safely. Any radioactive
material residing in the accelerator or
within the facility that houses the
accelerator must be adequately
considered for safe operation, and
managed appropriately at the time of
decommissioning of the acceleratorproduced radionuclide production
facility, including the accelerator, and
the NRC must ensure that adequate
financial assurances are put in place to
address the costs of decommissioning
when the radionuclide production
operation ceases, and the accelerator is
shutdown, and the license is
terminated. As with all decontamination
and decommissioning situations, shortlived radionuclides are expected to
decay to safe levels before license
termination. Therefore, only
radionuclides with a half-life of more
than 120 days, that are present in
sufficient quantities specified in 10 CFR
30.35, need to be addressed for the
purposes of establishing adequate
financial assurances for
decommissioning.
Similarly, the addition of discrete
sources of radium-226 in the definition
of Byproduct material requires the NRC
to ensure that decommissioning funding
is adequate for holders of specific
licenses for possession of discrete
sources of radium-226. Radium-226 is
already included in Appendix B of 10
CFR Part 30 to determine the required
level of financial assurance for holders
of specific licenses in accordance with
the requirements of 10 CFR 30.35.
Therefore, applicants for specific
licenses to possess discrete sources of
radium-226 will need to assure that
adequate financial assurances are
provided for the types of sources and
the total amount of radium-226
contained in the sources they will
possess. Holders of general licenses for
possession of discrete sources of
radium-226 do not need financial
assurance for decommissioning.
However, in accordance with the
approach for general and specific
licensing of discrete sources of radium226 being undertaken by the NRC in this
final rule, a general licensee may
become subject to specific licensing if
the accumulated number of discrete
sources of radium-226 exceeds the
allowable quantities of a general license.
If a general licensee becomes subject to
specific licensing, the licensee would be
required to acquire the financial
assurances required under 10 CFR
30.35.
The NRC believes that the financial
assurance requirements included in 10
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CFR 30.35 are adequate to ensure that
any person who will receive a specific
license authorizing possession and use
of byproduct material will be required
to have adequate financial assurance in
place for decommissioning the facility.
Therefore, the NRC is not changing the
regulations governing financial
assurance for decommissioning.
The NRC is cognizant of the potential
existence of facilities and sites which
may be, or have the potential to become,
contaminated with significant amounts
of radium-226 from past practices or
operations. Additionally, the potential
exists for significant quantities of
discrete sources of radium-226 to have
been previously disposed of by both
licensees and nonlicensees at their
facilities. The existing requirements for
licensing and decommissioning in 10
CFR Part 30 are sufficient to address
these situations for any facilities that
will apply for a specific license or
amendment to authorize possession of
discrete sources of radium-226 for their
current operations. The applications to
the NRC, in these cases, would include
a facility-specific decommissioning plan
that addresses the current
contamination and any previous onsite
disposals.
There are no similar assurances for
any facility that is currently
contaminated from discrete sources of
radium-226 but is not licensed. With the
inclusion of discrete sources of radium226 in the definition of Byproduct
material, the NRC acquires the
regulatory authority to address these
situations where a specific license has
not been issued (or where a potential
licensee cannot be identified). At this
time, there is not enough known about
the breadth or depth of these potential
radium-226 contamination situations to
determine if any additional
requirements may be needed to address
them. Therefore, the NRC will address
these situations on a case-by-case basis
as they are identified following the
effective date of this final rule.
D. License Application and Annual Fees
The NRC is required to recover
approximately 90 percent of its budget
authority each year under the Omnibus
Budget Reconciliation Act of 1990
(OBRA–90), as amended. Therefore, the
NRC charges licensing, inspection, and
annual fees to its applicants and
licensees. Each type of fee includes
agency and program overhead. The NRC
revises these fees each year in light of
its current fiscal year budget and other
factors, including changes in the
regulatory efforts associated with the
different classes of licensees.
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Persons applying for a license with
the NRC, or requesting an amendment to
their current licenses that may result in
the addition of a new fee category, are
required to pay a license application fee
under 10 CFR Part 170, unless exempt
under the fee exemption provisions of
10 CFR 170.11. The application fees for
materials users are ‘‘flat’’ fees that are
calculated by multiplying the average
professional staff hours needed to
process the application by the
professional staff-hour rate in 10 CFR
170.20 ($258 in the FY 2007 final fee
rule). An application fee must generally
be paid for each applicable fee category.
Additionally, all persons who hold
licenses issued by the NRC are subject
to annual fees under 10 CFR Part 171,
unless exempt under the provisions of
10 CFR 171.11. The 10 CFR Part 171 fee
categories, and the associated fees for
materials users, are provided in 10 CFR
171.16, and must generally be paid for
each applicable fee category. A licensee
may request consideration as a small
entity for the annual fees which may
result in a reduced fee, as described in
10 CFR 171.16.
The annual fees for the materials
users fee class are calculated based on
the NRC’s budgeted resources allocated
to regulating these types of licensees,
less any receipts received from this fee
class for 10 CFR Part 170 activities. The
net dollar value of budgeted resources
for this fee class is allocated to all
materials user fee categories (subclasses)
based on the average application and
inspection costs associated with each
category. This approach provides a
proxy for allocating the generic and
other regulatory resources to the diverse
categories of licensees based on how
much it costs the NRC to regulate each
fee category. The fee calculation also
considers the inspection frequency
(priority based), which is indicative of
the safety risk and resulting regulatory
costs associated with these categories of
licenses.
The license application fees schedule
is in 10 CFR 170.31. The annual fees
schedule is in 10 CFR 171.16. The fee
amounts included in the proposed rule
were based on the FY 2005 fees. The fee
amounts noted in the final rule are
based on the final FY 2007 fees. The
final 2007 fee rule was published June
6, 2007 (72 FR 31402).
The NRC believes that the majority of
the NRC’s licensees affected by this final
rulemaking will be using radioactive
material in a manner similar to their
existing authorizations, and their
existing fee categories should not
change as a result of this rule. However,
some licensees may need to amend their
licenses to add one or more new fee
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categories, if applicable, for new uses
and radioactive material now
considered byproduct material, i.e.,
accelerator-produced radioactive
material or discrete sources of radium226.
The NRC is establishing three new fee
categories for activities that were not
previously covered by its regulations.
The new fee categories apply to certain
items previously manufactured and selfluminous products containing radium226 and to the production of
accelerator-produced radioactive
material. In determining the fees for
these new categories, the NRC evaluated
existing fee categories that the NRC
believes require a similar level of
regulatory effort as these newly
regulated activities for actions such as
licensing, inspection, and event
response.
Most individuals and other entities
collecting items containing radium-226
are expected to be eligible to be exempt
from license under 10 CFR 30.15 or for
a general license under the new 10 CFR
31.12, ‘‘General license for certain items
and other self-luminous products
containing radium-226.’’ Therefore, they
would be subject to the requirements of
10 CFR 30.15 or 10 CFR 31.12 (e.g.
proper disposal of the radioactive
material). However, if a person collects
more than the number of items or limits
specified in these sections, that person
will be required to obtain a specific
license and be subject to the regulations
regarding license application and
annual fees. The NRC is establishing a
new fee category, 3.R., with a two-tiered
fee level, for those persons requiring a
specific license for items containing
radium-226. The distinction between
the two fee levels is based on the
number of items or limits specified in
10 CFR 31.12(a)(4) or (5) and the
estimate of the level of regulatory effort
between the two levels. Licensees who
currently possess radium sources in
amounts that exceed the general license
provisions of 10 CFR 31.12 would be
required to add the sources to their
specific license. This would normally
subject the licensee to the fees in this
new fee category. However, if the
radium-226 sources are used for
operational purposes that are covered
under another fee category, the licensee
will not be subject to the fees in this
new fee category. This exception will
not apply if the radium sources are
possessed for storage only.
The first new fee Category 3.R.1. is for
persons possessing quantities greater
than the number of items or limits in 10
CFR 31.12(a)(4) or (5), but less than or
equal to 10 times these quantities.
Because the estimated level of
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regulatory effort is comparable to the
level of effort for Category 8, Civil
defense, the license application and
annual fees for 3.R.1. will be $590 and
$2,100, respectively. The second new
fee Category 3.R.2. is for persons
possessing quantities greater than 10
times the number of items or limits in
10 CFR 31.12(a)(4) or (5). The license
application and annual fees for this new
category, 3.R.2., will be $1,400 and
$2,700, respectively, comparable to the
fees for Category 3.P., ‘‘All other specific
byproduct material licenses, except
those in Categories 4A through 9D.’’
Persons who wish to disassemble,
repair, or assemble products containing
radium-226 will be required to obtain a
specific license and will be subject to
the applicable license application and
annual fees. The NRC is including this
use in fee Category 3.B., ‘‘Other licenses
for possession and use of byproduct
material issued under 10 CFR Part 30 of
this chapter for processing or
manufacturing of items containing
byproduct material for commercial
distribution.’’ The license application
fee for this category will be $4,600, and
the annual fee will be $8,400.
The NRC is adding a new fee Category
3.S. for the production of acceleratorproduced radioactive materials. The
NRC is adding this new fee category
because these production activities need
to be distinguished from those activities
that only involve the use of alreadyprepared radionuclides. The regulatory
effort for the new fee Category 3.S. is
estimated to be similar to that for fee
Category 3.C. The license application
and annual fees for this new category
will be $8,000 for the application fee
and $10,900 for the annual fee. The
annual fee for category 3.S. in this final
rule is slightly less than that for category
3.C. because the category 3.S. fee does
not include a portion of the low-level
waste (LLW) surcharge, while the
category 3.C. fee does. This is because
the licensees in fee category 3.C.
directly benefit from the NRC’s LLW
activities, but the licensees in fee
category 3.S. do not. Fee amounts
included in this final rule are different
from those included in the proposed
rule because they are based on the FY
2007 Fee Schedules instead of the FY
2005 Fee Schedules.
E. Implementation Strategy
Specific provisions are included in
this rule, and several actions are
planned in conjunction with, or
following, the issuance of this final rule
covering the newly added byproduct
material, including:
(1) Issuance and publication of a
Transition Plan for the orderly
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transition of regulatory authority for the
newly added byproduct material;
(2) Termination of the waiver issued
by the NRC (70 FR 51581; August 31,
2005) for the States and users of the
newly added byproduct material; and
(3) Inclusion of specific provisions
allowing users of the newly added
byproduct material to continue with
their activities for a period of time while
coming into compliance with the newly
issued regulations.
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Transition Plan
Section 651(e) of the EPAct requires
the NRC, in issuing new regulations for
the newly added byproduct material, to
prepare and publish a Transition Plan
for the orderly transition of regulatory
authority over the newly added
byproduct material for Agreement and
non-Agreement States. The EPAct
requires that the Transition Plan
describe the conditions under which a
State (including U.S. Territories and the
District of Columbia) may exercise
authority over the newly added
byproduct material, and include a
statement of the Commission, that any
agreement between the Commission and
a State under Section 274b. of the AEA,
covering byproduct material, and
entered into before the date of
publication of the Transition Plan, be
considered to include the newly added
byproduct material. The statement of
the Commission is subject to a
certification provided by the Governor
of the State to the Commission on the
date of publication of the Transition
Plan that: (1) the State has a program for
licensing the newly covered byproduct
material that is adequate to protect the
public health and safety, as determined
by the Commission; and (2) the State
intends to continue to implement the
regulatory responsibility of the State
with respect to the byproduct material.
The NRC also will include in the
Transition Plan the process it will use
to terminate the waiver issued by the
NRC on August 31, 2005, and for the
transition of regulatory authority
following expiration or earlier
termination of the waiver.
Termination of Waiver
The waiver issued by the NRC (70 FR
51581; August 31, 2005) is effective
through August 7, 2009 (except
terminated August 7, 2006, for the
import and export of materials covered
by the waiver), unless terminated earlier
by the Commission. The waiver applies
to Agreement and non-Agreement State
regulatory programs and users of the
newly added byproduct material, and
allows persons owning, using, and
otherwise engaging in activities
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involving the material to continue with
their activities and the States to
continue to regulate this material during
the applicable waiver period. All
persons in States (including U.S.
Territories and the District of Columbia)
that do not have an agreement with the
Commission under Section 274b. of the
AEA that covers the newly added
byproduct material on or before August
7, 2009, will automatically be subject to
the NRC regulatory authority for the
material on August 8, 2009. The waiver
also may be terminated earlier than
August 7, 2009, if the Commission
determines that an earlier termination is
warranted.
For a new or existing Agreement State
that intends to implement the regulatory
program of the State with respect to the
newly added byproduct material,
Section 651(e) of the EPAct requires that
the waiver be terminated for the State
when the Commission determines that
the State has entered into an agreement
with the Commission, under Section
274b. of the AEA, that the State program
covers the newly added byproduct
material, and that the State program for
licensing the newly added byproduct
material is adequate to protect the
public health and safety. The
Commission determination and
termination of the waiver will be
noticed in the Federal Register
(Notification of Waiver Termination).
Users of the newly added byproduct
material currently licensed, or
registered, by an Agreement State that
continues to implement its regulatory
program, with respect to the newly
added byproduct material, will continue
to be subject to the Agreement State
regulatory authority.
With regard to the States that do not
have an existing agreement with the
Commission under Section 274b. of the
AEA (non-Agreement States), the waiver
period provides additional time for
those States that desire to establish such
an agreement for the newly added
byproduct materials to develop a
program. To establish this agreement
with the Commission, the Governor of
the current non-Agreement State will
need to request an agreement with the
Commission. The process of
establishing these agreements can take 3
or more years to complete. Options will
be considered, on a case-by-case basis,
to limit the impact of the transition of
authority on affected users of the new
byproduct material in the State.
Additional details on the process that
the NRC will use to terminate the
waiver for Agreement and nonAgreement States and users in these
States will be provided in the
Commission’s Transition Plan, as
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required by Section 651(e) of the EPAct.
The NRC plans to publish the Transition
Plan following publication of this final
rule and before the effective date of this
final rule.
Notification of Waiver Termination
The Commission is terminating the
waiver for Government agencies and
Federally recognized Indian Tribes on
the effective date of this final rule
because there is currently limited
regulatory oversight for the newly added
byproduct material at these facilities.
Waiver termination is necessary to
require Government agencies and
Federally recognized Indian Tribes to
comply with the new requirements and
for the NRC to ensure protection of
public health and safety for the newly
added byproduct material.
The Commission has also determined
that an earlier termination is warranted
and is therefore terminating the waiver
for persons owning, using, and
otherwise engaging in activities
involving the newly added byproduct
material in the following States on the
effective date of this final rule:
Delaware, Indiana, Wyoming, and
Montana, as well as the District of
Columbia, Puerto Rico, and the U.S.
Virgin Islands. The effective date of this
final rule is 60 days after the date of
publication in the Federal Register.
Waiver termination is necessary to
require persons owning, using, and
otherwise engaging in activities
involving the newly added byproduct
material in these States, U.S. Territories,
and the District of Columbia to comply
with the new requirements and for the
NRC to ensure protection of public
health and safety for the newly added
byproduct material.
Implementation Period
Although Government agencies,
Federally recognized Indian Tribes, and
certain persons owning, using, and
otherwise engaging in activities
involving the newly added byproduct
material in the States of Delaware,
Indiana, Wyoming, and Montana, and
the District of Columbia, Puerto Rico,
and the U.S. Virgin Islands are already
being regulated by the NRC for the AEA
11e.(1) and 11e.(2) byproduct material,
the NRC is allowing a transitional
period for them to submit a license
amendment or a new license application
for the newly added byproduct material.
This final rule allows an additional 6month period from the effective date of
the final rule to apply for a license
amendment; and an additional 12month period from the effective date of
the final rule to apply for a new license.
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In addition, the rule contains specific
provisions that gives Governmental
agencies, Federally recognized Indian
Tribes, and persons owning, using, and
otherwise engaging in activities
involving the newly added byproduct
material, in the States of Delaware,
Indiana, Wyoming, and Montana, and
the District of Columbia, Puerto Rico,
and the U.S. Virgin Islands, the
authority to continue to use the newly
added byproduct material during the
period following the waiver termination
until the date of the NRC’s final
licensing determination, provided that
either a license amendment or a license
application is submitted within the
specified time frame and while
complying with all other aspects of the
regulations (e.g., event reporting,
personnel dosimetry) upon the effective
date of this final rule.
For persons owning, using, and
otherwise engaging in activities
involving the newly added byproduct
material, compliance with the rule will
be required depending on the date of
waiver termination. For certain States
and persons, the NRC plans to terminate
the waiver earlier than the final date of
the waiver, i.e., August 7, 2009. A
decision for early termination will
depend on a number of factors,
including the status of an Agreement
State Governor’s certification of
adequate program for the newly added
byproduct material, status of a nonAgreement State’s application to
become an Agreement State, and
activities or areas under exclusive NRC
jurisdiction. Upon waiver termination,
all persons that possess the new
byproduct materials must be in
compliance with NRC regulations. It is
noted that being in compliance with the
NRC regulations includes, for example,
meeting the reporting and
recordkeeping requirements for the new
byproduct material once the waiver is
terminated. In addition, such persons
will either be required to: (1) apply for
license amendments for the new
byproduct material within 6 months
from the date the waiver is terminated,
if they hold an NRC specific byproduct
materials license; or (2) submit a license
application for the new byproduct
material within 12 months from the date
the waiver is terminated. It is noted that
authorization statements for certain
licenses are inclusive of byproduct
materials and their uses so that an
amendment may not be needed to
specifically add NARM to the license.
During the time between the
termination of the waiver and the user’s
application for an NRC license or
license amendment, users in
Government agencies, Federally
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recognized Indian Tribes, and nonAgreement States will be under the
NRC’s jurisdiction for enforcement
purposes. The NRC will handle
enforcement cases involving the use of
the newly regulated materials on a caseby-case basis. However, should the
number of cases involving these
materials be larger than anticipated, the
staff will prepare additional
enforcement guidance to ensure
consistency in handling such issues.
III. Summary and Analysis of Public
Comments on the Proposed Rule
The proposed rule on Requirements
for Expanded Definition of Byproduct
Material was published on July 28, 2006
(71 FR 42952). The comment period
ended on September 11, 2006. The NRC
received 39 comment letters on the
proposed rule. Comment letters were
submitted from the States, other Federal
agencies, professional organizations,
universities, medical communities,
industries, and individuals. On August
22, 2006, the NRC held a public meeting
in Las Vegas, Nevada, on the proposed
rule during the comment period. Copies
of the public comments and the public
meeting transcripts are available for
review in the NRC Public Document
Room, 11555 Rockville Pike, Rockville,
Maryland.
In addition to requesting public
comments on the proposed rule, the
NRC specifically requested additional
information or comments on 15 specific
items outlined in Section II.G. of the
proposed rule. A synopsis of the items
and type of comments received are as
follows:
Item 1—Technical Information to
Support Exemption of Old Radium-226
Sources. One commenter provided
information on potential pressure buildup within radium sources that could
lead to the release of radium into the
environment. Another commenter
provided a reference to an FDA
document. There were comments on the
availability of information on radium226 items and on exemption of
antiquities. The NRC appreciates the
information. A discussion of the
comments on exemption of antiquities
and associated response is included
later in this document under
‘‘Comments Related to Radium-226.’’
Item 2—Extent of Use of Accelerators.
No comments were received regarding
the extent of accelerators that are used
to intentionally produce radioactive
material and also used to generate
particle beams for basic science
research. One commenter indicated that
the commenter’s organization does not
operate any particle accelerators for the
purpose of producing radioactive
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materials and producing particle beams
for other uses. Another commenter
informed the NRC that it will be
building a new accelerator facility
where radionuclides will be produced.
Item 3—Information on
Decommissioning of Accelerator
Facilities. Several comments were
received regarding information on
decommissioning of accelerator
facilities, including accelerator
components and facility building
materials that may become activated. A
detailed discussion of the comments
and response is included later in this
document under ‘‘Comments on Waste
and Decommissioning.’’
Item 4—Inclusion of Specific ALI and
DAC Values. In response to the NRC’s
question on whether to develop specific
ALI and DAC values for oxygen-15 and
nitrogen-13 for inclusion in 10 CFR Part
20, Appendix B, several commenters
provided specific DAC values. A
discussion of the values and the
methodology used can be found later in
this document under ‘‘Comments on
Other General Requirements.’’
Item 5—Exemption of Radium-226
Timepiece Repairs. In regard to the
appropriateness of the proposed
exemptions to allow repairs of 10
radium-226 timepieces per year, one
commenter suggested increasing the
proposed limit of 10 per year to 18. The
commenter did not provide specific data
concerning how active the repair of
radium-226 timepieces may be or the
safety significance of the proposed
exemption. However, there were several
comments related to radium-226
exemptions. Detailed discussion of
these comments and the associated
responses is included later in this
document under ‘‘Comments Related to
Radium-226.’’
Item 6—Health and Safety
Information of Radium-226 Sources.
The NRC requested information on the
health and safety impact from activities
involving radium-226 sources, in
particular, information to support a
technical basis for an exemption as an
alternative to the proposed general
licensing approach. Several commenters
indicated that they believed that an
exemption would be preferable to a
general license for items containing
radium-226, but no specific health and
safety impact information was provided.
Most commenters agreed that more
information about risk is needed to
make a final decision. Discussion of
comments associated with this issue is
included later in this document under
‘‘Comments Related to Radium-226.’’
Item 7—Existing and Proposed Fee
Categories. The NRC requested
information on whether the majority of
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licensees would remain in the existing
fee categories and whether new NARM
licensees would fall under the current
fee categories or the new proposed fee
categories. No specific information on
this issue was received from the
commenters. However, several
commenters indicated that they
believed that there is no need to
establish a new fee category for the
production of accelerator-produced
radioactive material. All of the
comments related to fees are discussed
later in this document under
‘‘Comments on Licensing Fees and Fee
Categories’’.
Item 8—Licensing Boundaries for
Radium-226 Private Collectors. No
information was received on whether
private collectors of items or products
containing radium-226 would remain
within the boundaries of the proposed
general license or be required to obtain
a specific license and be charged with
the associated licensing fees. One
commenter recommended that an
‘‘exception’’ be extended to certain
organizations. A discussion of radium226 exemptions is included in
subsection ‘‘Comments Related to
Radium-226,’’ and a discussion of fees
is included later in this document under
‘‘Comments on Licensing Fees and Fee
Categories’’.
Item 9—Two-Tiered Fees for Radium226. No information was received
regarding the two-tiered license fees
proposed for possession of different
quantities of radium-226 items.
Comments received on the proposed fee
categories and amounts are discussed
later in this document under
‘‘Comments on Licensing Fees and Fee
Categories’’.
Item 10—Effective Date and
Implementation Periods. Several
comments were received on the
proposed effective date and
implementation periods of the rule. A
discussion is included later in this
document under ‘‘Comments on Waiver
Termination and Transitioning.’’
Item 11—Compatibility Category
Designations. All comments related to
the compatibility category designations
are discussed later in this document
under ‘‘Comments Related to Agreement
States and Other Government
Agencies’’.
Item 12—Environmental Assessment.
Comments received on the draft
Environmental Assessment were
considered in the final Environmental
Assessment and Finding of No
Significant Impact.
Item 13—Information Collections. No
comments were received on the
information collections aspects of the
rule.
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Item 14—Regulatory Analysis. No
comments were received on the draft
Regulatory Analysis.
Item 15—Impact to Small Business.
No comments were received on the
impacts of the rule on small businesses.
General information and editorial
suggestions received on the proposed
rule are appreciated but do not need to
be discussed in this final rulemaking.
Comments associated with nuclear
reactors and the high-level waste
repository are outside the scope of this
rulemaking; therefore, they will not be
addressed in this section. All other
comments have been grouped into broad
categories, and a detailed discussion of
the comments and the NRC’s responses
are as follows:
Comments Related to Agreement States
and Other Government Agencies
Agreement State Compatibility
Designations
Comment: The comments received on
‘‘compatibility’’ are primarily centered
around one main concern:
Implementation of the requirements for
the Compatibility Category of Health
and Safety (H&S) for several definitions.
The basic concern expressed by these
commenters was that the States should
not be required to amend their
definitions in their State statutes and
regulations. In particular, some
commenters were concerned about the
designation of H&S for the definition of
Byproduct material. These commenters
indicated that they would support an
H&S designation if the Statements of
Consideration to the final rule provided
that the NRC’s initial determination of
the adequacy of definitions would rely
on a Governor’s certification that the
State’s program was ‘‘adequate,’’ and
that if the Governor’s certification was
accepted, no changes to the State’s
definitions would be required. As an
alternative, some commenters suggested
that the Statements of Consideration
recognize that the States could use
alternative language in their definitions
including the use of the more generic
term of ‘‘radioactive material,’’ rather
than revise the definitions to conform
with the new definitions. In the absence
of implementing those suggestions,
these commenters recommended that
the Compatibility Category designation
for definitions be changed from H&S to
D.
These commenters generally
indicated that if those suggestions could
not be implemented, they would
recommend that the NRC designate the
definitions it was changing as
Compatibility D.
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NRC Response: The NRC does not
agree with the commenters’ assertion
that the designation for the definition of
Byproduct material should be changed
from H&S. The NRC also does not agree
that the Governor’s certification of the
adequacy of an Agreement State’s
program should relate to the need for
the State to revise its regulations.
However, the States may continue to use
the existing definition including
Radioactive material in State statutes
and regulations, although there may be
limited areas where a State may need to
revise its regulations to include material
now under the jurisdiction of the NRC
(e.g., exempt distribution for certain
materials).
The NRC applied the criteria in
Management Directive (MD) 5.9,
‘‘Adequacy and Compatibility of
Agreement State Programs,’’ in
evaluating the compatibility category of
the definitions, and determined that a
category of H&S is appropriate for the
definition of Byproduct material. MD
5.9 provides that an H&S designation is
appropriate for elements that are not
required for compatibility but have been
identified as having a particular health
and safety role in the regulation of
agreement material within the State. In
accordance with this designation, the
State should adopt program elements,
based on those of the NRC, that embody
the essential objectives of the NRC
program elements because of particular
health and safety considerations. A
category of H&S is appropriate for the
definition of Byproduct material
because the absence of the essential
objectives of the program element from
an Agreement State program could
create a situation that could directly
result in exposure to an individual in
excess of basic radiation protection
standards.
MD 5.9 provides that the NRC
program elements in Compatibility
Category D are those that do not meet
the criteria of Compatibility Categories
A, B, or C, and thus, do not need to be
adopted by the Agreement States for
purposes of compatibility. The NRC has
determined that a Compatibility D
designation is not appropriate for the
definition of Byproduct material
because if the definition of Byproduct
material or another term which
encompasses all of the byproduct
material regulated by the State were not
somewhere within the State program
(i.e., in statute or in regulations), it is
possible that some byproduct material
could escape regulatory oversight with a
result of exposure to an individual in
excess of the 10 CFR Part 20 limits. The
State regulatory program must include
Sections 11e.(3) and 11e.(4) byproduct
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material in its regulatory program if the
Agreement includes this material, thus,
an H&S designation (an assessment of
adequacy) is appropriate.
In implementing the Commission’s
policy on Agreement States, a
designation of H&S for the definition of
Byproduct material will require NRC
staff to continue to assure that the
essential objectives (i.e. Sections 11e.(3)
and (4) byproduct materials are
addressed in the regulatory program) are
met. The NRC staff notes that under a
designation of D, this assurance would
not be obtained because program
elements designated D are not a
required part of an Agreement State
program (they could be dropped from or
not included in the Agreement State
program, and the program could still be
found adequate and compatible).
Comment: With regard to the
definitions in 10 CFR 35.2 of Authorized
nuclear pharmacist, Authorized user,
and Positron Emission Tomography
(PET), one commenter recommended
that any Agreement State that has rule
language essentially the same as the
current CRCPD’s SSRs should be
considered to have compatible rules and
should not have to revise those rules
regardless of the level of compatibility
assigned by the NRC. The commenter
further recommended that the NRC
might include this recognition in the
Statements of Consideration.
NRC Response: The NRC has
determined that it is not necessary to
change the current definitions for an
Authorized user or Authorized nuclear
pharmacist. This rule does not change
the existing definitions or impact the
existing compatibility designation for
these definitions. The definition of
Positron Emission Tomography is not in
the SSRs, and it is identified in the final
rule as having a designation of ‘‘H&S,’’
which assures that the State’s regulatory
programs adequately address the
essential objectives of the NRC program
elements when using the term Positron
Emission Tomography.
Comment: For each of the sections
with a Compatibility B Category, it is
not clear that the NRC accepts the
language of the States that is essentially
identical to the SSRs.
NRC Response: For the definitions
and sections assigned a Compatibility B
designation, the NRC cannot
automatically accept the States’
language; the States’ regulations must be
reviewed. Agreement State regulations
will be reviewed according to Office of
Federal and State Materials and
Environmental Management Programs
(FSME) Procedure 201 (SA–201) and
should be submitted within 3 years of
publication, in accordance with the
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NRC’s 1997 Policy Statement on
Adequacy and Compatibility of
Agreement State Programs (62 FR
46517; September 3, 1997). The NRC
notes that portions of the SSRs may be
outdated and do not reflect recent
amendments (e.g., definitions of
Authorized user and Authorized nuclear
pharmacist) and so cannot be used.
Comment: Referring to 10 CFR 32.72,
a commenter recommends that the NRC
specifically recognize that an Agreement
State will not be required to amend its
comparable regulation, as long as that
comparable regulation provides for the
same control of the manufacture and
initial distribution of radium-226
sources under a general license as was
provided in the proposed regulation.
NRC Response: The NRC does not
agree with the comment. Section 32.72
in 10 CFR Part 30 authorizes specific
licensees to manufacture, prepare, and
distribute radioactive drugs to medical
use licensees. This provision does not
include generally licensed material.
Further, the NRC is unaware of any
radioactive drugs containing radium226. Agreement States have 3 years to
adopt regulatory requirements
compatible with 10 CFR 32.72 revisions.
For a specific license to allow the
manufacture or initial transfer of
calibration or reference sources
containing radium-226, under 10 CFR
32.57, for distribution to persons
generally licensed, the NRC has
included provisions in 10 CFR 31.8 to
recognize specific licenses issued for
these sources by a State with
comparable regulations.
Comment: A commenter stated that
the NRC’s deliberate use of
Compatibility B and H&S categories sets
the tone that its considerations are
preeminent. Another commenter stated
that the language of the EPAct indicates
that the burden should be on the NRC
to bring its regulations into conformance
with the Agreement State regulations.
The commenter also stated that whether
or not the NRC is making an effort to
obey the EPAct language to cooperate
with the States or use model State
standards will depend on whether the
NRC accepts the Agreement States’
regulations. The commenter believes
that the Agreement State regulations do
not need to be changed to be exactly like
the NRC’s.
NRC Response: In accordance with
AEA Section 274b, for an agreement
between the NRC and a State, a State
program must be adequate to protect
public health and safety and be
compatible with the NRC. The EPAct
gives the NRC jurisdiction over NARM
byproduct material, and does not
mandate that the NRC bring its
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regulations into conformance with the
Agreement State regulations, but only
requires that the Commission, to the
maximum extent practicable, cooperate
with the States and use model State
standards. The Commission has fulfilled
this mandate by working closely
throughout the development of this final
rule with OAS, the CRCPD, and other
stakeholders, and by considering the
model State standards. As discussed
previously, the NRC applied criteria laid
out in MD 5.9, ‘‘Adequacy and
Compatibility of Agreement State
Programs,’’ which includes criteria for
the NRC to designate compatibility and
adequacy categories to the NRC’s
regulations and coordinating
amendments for radioactive material
included in the Agreement. In
promulgating the final rule, these
criteria were applied to the definitions
and other requirements of the EPAct to
determine the appropriate compatibility
categories.
Interaction With Other Federal Agencies
Comment: A commenter asked if any
Memorandum of Understanding (MOU)
between the NRC and the DOT on
byproduct materials would be affected
by the changes in the proposed rule.
NRC Response: The roles and
responsibility between DOT and the
NRC in the regulation of the
transportation of radioactive material
are clearly described in an MOU signed
on June 8, 1979, and published in the
Federal Register (44 FR 38690; July 2,
1979). As delineated in the MOU, the
DOT is generally responsible for
regulating safety in transportation of all
hazardous material, including
radioactive material, and the NRC is
responsible for regulating safety in
receipt, possession, use, and transfer of
byproduct, source, and special nuclear
materials. The NRC is also responsible
for approval of package designs for
fissile materials and for other
radioactive materials in quantities
exceeding Type A limits. In reviewing
the language of the existing MOU, the
NRC has determined that no change is
necessary as a result of this final rule.
The MOU stated that the NRC is
authorized to regulate, among other
things, byproduct material under the
AEA of 1954, as amended, and the
Energy Reorganization Act of 1974, as
amended. Because the EPAct amends
the AEA, the expanded definition of
Byproduct material will automatically
be subject to the MOU. In addition,
there are routine interactions between
the NRC and the DOT, and the DOT is
aware of the expanded definition of
Byproduct material.
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Comment: A commenter asked if the
proposed changes in the regulations
would have any impact on accelerators
or accelerator radionuclides that are
taken to sea or out of the U.S., and if
those changes would also impact the
EPA’s responsibilities, treaty
requirements, or Status of Forces
agreements. For example, the
commenter noted that a research vessel,
military hospital, or Centers for Disease
Control vessel leaving the U.S. for
foreign ports and returning to the U.S.
may have an electron microscope or
metabolic (Na, Cl, K) studies with
accelerator-produced radionuclides on
board. The commenter asked if
activation from neutron radiography on
board these ships would be an issue.
The commenter also asked if the
proposed changes would affect
machines that the U.S. Customs uses to
radiograph containers in foreign ports
before they are placed on shipboard if
the machine is greater than 1 MeV. The
commenter also wanted to know how
replaced parts of those machines will be
handled, whether all parts would be
controlled, and whether they could be
disposed of in a foreign state.
NRC Response: The commenter
appears to be concerned, in part, about
regulatory requirements pertaining to
U.S. originated accelerator-produced
radioactive material taken outside of the
U.S., i.e., export of accelerator-produced
radioactive material. Part 110 of the
NRC’s regulations governs export and
import of radioactive material within
the NRC’s regulatory jurisdiction. On
April 20, 2006 (71 FR 20336), the NRC
issued a final rule amending 10 CFR
Part 110 to reflect the EPAct’s
augmentation of the NRC’s regulatory
jurisdiction to include acceleratorproduced radioactive material.
Specifically, the rule added
‘‘accelerator-produced radioactive
material’’ to the definition of Byproduct
material in 10 CFR 110.2 and Appendix
L to 10 CFR Part 110. Export and import
of all byproduct material, including
accelerator-produced radioactive
material, are governed by 10 CFR Part
110. There is no difference in regulatory
treatment between byproduct material
produced by an accelerator and
byproduct material produced in a
reactor.
The commenter also asks whether this
rule would affect U.S. Customs’ use of
‘‘radiograph machines.’’ The NRC does
not believe this final rule would have
any impact on the Customs and Border
Protection’s use of radiograph machines
because these machines use byproduct
material that is already regulated by the
NRC because the material is produced
in a reactor. With the revised definition
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of Byproduct material, there will be no
difference in regulatory treatment
between byproduct material produced
by an accelerator and byproduct
material produced in a reactor. If the
radiograph machine uses the
accelerator-produced radioactive
material, it would now be subject to the
same regulatory requirements as the
machine-used byproduct material
produced in a reactor. The NRC’s or any
other requirements on the use of
byproduct material in radiograph
machines would be no different from
the pre-EPAct condition for both the
domestic and export context.
Neutron radiograph machines do not
use byproduct material; they are
actually accelerators. Only neutron
beams are generated in these types of
radiograph machines for imaging
purposes. Because these types of
radiograph machines (or accelerators)
do not produce radioactive material for
use for commercial, medical, or research
activities, the NRC has no regulatory
authority over these machines or the
activation material produced incidental
to imaging operation.
Comment: A commenter
recommended that the NRC pursue an
MOU with OSHA in order for the NRC
to assume regulatory jurisdiction over
the occupational exposure to ionizing
radiation in non-Agreement States. The
commenter noted that before the
expansion of the NRC’s jurisdiction over
NARM, OSHA had jurisdiction for
occupational health and safety in nonAgreement States. The commenter noted
that OSHA published a request for
information to better understand what,
if any, changes OSHA needed to
consider in its regulation of the use of
ionizing radiation in the workplace
(See: Occupational Exposure to Ionizing
Radiation—Request for Information; 70
FR 22828; May 3, 2005). The commenter
recommended that the NRC work
actively with OSHA to streamline the
regulatory requirements and eliminate
duplication of authority over the use of
NARM in non-Agreement States.
NRC Response: The NRC has been
working, and continues to work, with
OSHA and other Federal agencies
through the Interagency Steering
Committee on Radiation Standards
(ISCORS) to coordinate issues and
activities, including the development of
Federal Guidance for Occupational
Exposure to Radiation and regulations
related to radiation protection and
safety. The NRC recognizes that the
existing MOU is now out of date with
respect to references of enabling
legislation and the respective
jurisdictions of the two agencies as a
result of the EPAct. However, the
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procedures specifying the interactions
between OSHA and the NRC and the
authority and responsibilities of each
agency remain appropriate and valid to
cover interactions in the newly enacted
jurisdictional framework. Thus, the NRC
does not believe that there is an
imminent need to reexamine and update
the MOU.
Comment: Several commenters
requested clarification on the NRC’s
jurisdiction and role regarding radium226 contaminated sites or old landfills,
especially for sites currently under
remediation by either the EPA or an
authorized State under the RCRA or the
Comprehensive Environmental
Response, Compensation, and Liability
Act (CERCLA, also known as
Superfund) programs. One commenter
asked if the NRC and EPA have
executed an MOU for Superfund sites.
Another commenter asked if the NRC/
EPA MOU on decommissioning (2002)
will be impacted by this rule. Another
commenter suggested that the NRC and
EPA should have a dialogue to discuss
a collaborative approach to address
licensing of discrete sources covered by
this rule that are already considered as
part of the Superfund efforts. The
commenter indicated that such dialogue
would complement ongoing
coordination between EPA and the NRC
under the existing MOU, ‘‘Consultation
and Finality on Decommissioning and
Decontamination of Contaminated
Sites’’.
NRC Response: Under the EPAct, the
NRC has the regulatory authority over
any discrete source of radium-226 that
is produced, extracted, or converted
after extraction, before, on, or after the
date of enactment of the act for use for
a commercial, medical, or research
activity. Hence, the NRC has the
jurisdiction over old landfills or
disposal sites contaminated with
radium-226 due to past operations or
disposal of discrete sources of radium226.
The NRC typically has regulatory
authority over sites undergoing
radiological decommissioning, even
those sites that also contain EPA
hazardous materials (CERCLA and
RCRA). The NRC and EPA have entered
into site-specific agreements via formal
letters in which the license for a site
undergoing decommissioning was put
in abeyance and regulatory authority for
decommissioning the site deferred to
the EPA. There is no MOU for these
agreements because they are rare and
very site specific. The NRC anticipates
that this site-specific process will
continue.
The current MOU ‘‘Consultation and
Finality on Decommissioning and
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Decontamination of Contaminated
Sites’’ between the NRC and EPA
defines the policy for deferral of
regulatory authority between the two
agencies for radiological
decommissioning and decontamination
of the NRC-licensed sites. The MOU
specifically provides that under certain
clearly defined criteria, EPA agrees to a
basic policy of EPA deferral to the NRC
decisionmaking in the decommissioning
of the NRC-licensed sites without the
need for consultation. If the criteria are
not met, the MOU directs the NRC to
consult with the EPA regarding the site.
The MOU does not provide for the
deferral of regulatory authority from the
NRC to the EPA.
The NRC has routine interactions
with EPA through ISCORS and through
informal communications among staff
on a multitude of subject areas.
Currently, there are seven
subcommittees in ISCORS, including
Cleanup, Federal Guidance, Mixed
Waste, Naturally Occurring Radioactive
Material, Recycle, Risk Harmonization,
and Sewage Sludge Subcommittees. The
NRC will continue to work closely with
EPA though ISCORS and other informal
mechanisms regarding
decommissioning and decontamination
of sites.
Because the NRC had been deferring
regulatory authority to the EPA on a
site-by-site basis in the past, the NRC
believes, at this time, that there may not
be a need to revise the existing MOU.
Once the NRC has gained sufficient
experience in dealing with old disposal
sites contaminated with the newly
added byproduct material and if
significant issues arise regarding shared
regulatory authority, the NRC will
cooperate with EPA in evaluating the
need to amend the existing MOU and in
determining an approach in resolving
issues in managing these old disposal
sites.
Comment: A commenter noted that
the discussions on current regulatory
structures for NARM, and on other
Federal agencies’ regulatory authority
over NARM, do not mention that some
Federal licensees, such as licensees who
hold a Master Materials License (MML),
have established self-regulation
requirements for NARM use. The
commenter recommended that the NRC
should describe the MML licensees’ role
in the regulation of NARM.
NRC Response: MML licensees are the
NRC licensees and are required to
comply with the NRC regulations. The
fact that some MML licensees have
established self-regulating requirements
for accelerator-produced radioactive
material and may have issued permits to
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their permittees for these materials is
noted.
Comment: A commenter stated that
requirements under several sections
related to a master materials license
address ‘‘a permit issued by a
Commission master material license
broad scope permittee’’ with the
implication that a broad-scope permittee
is required to issue such a permit. The
commenter stated that, in most cases,
the permittee might issue an
authorization or other type of document
for an AU. The commenter requested
that the regulatory requirement be
revised as ‘‘a permit, or other
authorization, issued by a Commission
master material license broad-scope
permittee’’.
NRC Response: The NRC does not
agree that this language is ambiguous.
The use of the phrase ‘‘a permit issued
by a Commission broad scope licensee’’
has been used by the NRC in 10 CFR
Part 35 since the 1994 ‘‘Radiopharmacy
Rule’’ (59 FR 61781; December 2, 1994)
to designate the document that the
broad-scope Radiation Safety Committee
issues to individuals to permit or
authorize them to use specific
radionuclides for licensed activities.
The same term was used in the major
revision to 10 CFR Part 35 (67 FR 20370,
April 24, 2002) for the same type of
documentation issued by the MML
broad-scope permittee to individuals at
its facility.
Comments on Defining the Byproduct
Material
Comment: A commenter, discussing
the proposed Byproduct material
definition in 10 CFR 20.1003 and 30.4,
believes the wording ‘‘produced,
extracted, or converted after extraction,
before, on, or after August 8, 2005,’’ was
confusing and ambiguous, stating that
the phrase, ‘‘before, on, or after August
8, 2005,’’ appears to be meaningless and
that it was not clear whether the phrase
referred only to material ‘‘converted
after extraction,’’ or to material
‘‘produced, extracted, or converted after
extraction’’.
NRC Response: The phrase, ‘‘before,
on, or after August 8, 2005,’’ has been
incorporated into the definition of
Byproduct material in the AEA as a
result of the language of the EPAct. It is
included in the definition in the final
rule because it is important to be clear
that materials that have been produced,
extracted, or converted after extraction
at any time, even before promulgation of
the EPAct, are included. This phrase is
intended to apply to all of these
activities, i.e., the production,
extraction, and conversion after
extraction. Not having such an explicit
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phrase in the definition may raise
questions regarding applicability of the
regulations for materials resulting from
past activities.
Definition of Discrete Source
Comment: Commenters generally
supported the stated result of the
definition as to the limits of NRC’s
authority and specifically the proposed
limitation of the definition to exclude
radium-bearing wastes generated by
many facilities, including drinking
water treatment plants and oil and gas
production facilities. One commenter
specifically agreed with the definition
stating that it captured the important
aspects of the discussions at the public
and interagency meetings, as well as the
original intent of earlier versions of
legislation incorporated into the EPAct.
However, other commenters expressed
concerns about the clarity of the
definition. Several commenters stated
that some of the provisions in the
proposed definition of discrete source,
such as the requirements that the source
have physical boundaries and that the
materials have been concentrated for
their radiological properties, were
ambiguous and could lead to uneven
regulation. The commenters
recommended that the NRC revise the
proposed definition, and two
commenters suggested alternate
definitions.
One commenter stated that the
phrases ‘‘with physical boundaries’’ and
‘‘which is separate and distinct from the
radioactivity present in nature’’ in the
proposed definition of Discrete source
could cause confusion. The commenter
stated that the requirement for physical
boundaries without further description
or statement of the purpose of the
physical boundaries is ambiguous and
leaves room for uneven regulation.
Commenters were also concerned with
the words, ‘‘which is separate and
distinct from the radioactivity present in
nature,’’ particularly with the usage of
‘‘radioactivity.’’ One commenter stated
that a workable definition is crucial to
keep unintended materials from being
captured.
Other commenters expressed concern
about the phrase, ‘‘with the intent that
the concentrated radioactive material
will be used for its radiological
properties,’’ with one commenter
recommending that it be deleted. This
commenter noted that it has
encountered situations where discrete
sources of radium-226 were deposited
over a large area of land in which there
were discrete nuggets and that there was
no way of determining whether the
discrete nuggets were produced for their
radiological properties or not.
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NRC Response: The proposed
definition of Discrete source was ‘‘a
radioactive source with physical
boundaries, which is separate and
distinct from the radioactivity present in
nature, and in which the radionuclide
concentration has been increased by
human processes with the intent that
the concentrated radioactive material
will be used for its radiological
properties.’’ It is clear from some of the
comments that the proposed definition
of Discrete source, particularly the
phrase ‘‘with physical boundaries,’’
creates confusion that would, among
other things, present problems with the
regulation of material no longer in its
original form, but which the NRC
intends to regulate.
The wording in the final rule has been
revised to clarify the ambiguities that
gave rise to these comments. The
revised definition of Discrete source is
‘‘a radionuclide that has been processed
so that its concentration within a
material has been purposely increased
for use for commercial, medical, or
research activities’’.
With the modification of the
definition of Discrete source to
eliminate the word ‘‘separate’’ and the
phrase ‘‘with physical boundaries,’’
radium contamination resulting from
the use of purposely concentrated
radium-226 falls within the definition of
Discrete source. These changes should
make it clearer that the NRC’s
jurisdiction continues through
decommissioning. The radiological
criteria for unrestricted use in 10 CFR
20.1402 refer to residual radioactivity
that is distinguishable from background.
Some commenters appeared concerned
that for purposes of decommissioning, it
would not be possible to distinguish
between the atoms of material that had
been purposely concentrated for use for
its radiological properties from atoms of
material present in nature. This concern
is not warranted because, in practice,
this is not the methodology used to
determine the need for
decontamination.
The revised definition also removes
the requirement that the purpose for
concentrating radium-226 (or other
identified naturally occurring
radioactive material) be specifically for
use of its radiological properties.
However, this change is not expected to
have any practical effect on the
regulation of radium-226, as all known
uses of radium-226 have been for its
radiological properties and not
primarily its chemical or physical
properties. The only effect of revising
the definition would be if a future use
is made of a highly radioactive naturally
occurring material involving chemical
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or physical, but not radiological,
properties. To constitute byproduct
material as it is now defined in Section
11e.(4) of the revised AEA, this material
would have to have been determined by
the Commission to meet the standard of
threat similar to that of radium-226.
The comments on the definition of
Discrete source relate mainly to
questions concerning what naturally
occurring radioactive material will be
considered byproduct material, and thus
be regulated by the NRC. In revising the
definition of Discrete source, the
Commission has also added the
condition that to be a discrete source,
the radionuclide has been processed so
that its concentration within a material
has been purposely increased ‘‘for use
for commercial, medical, or research
activities.’’ The addition of this limiting
phrase may appear redundant, as the
words ‘‘for use for a commercial,
medical, or research activity’’ are
already in the definition of Byproduct
material, and a discrete source is a
subcategory of byproduct material.
However, the addition of these words to
the definition of Discrete source ensures
an understanding that the term ‘‘discrete
source,’’ where used in the regulations
other than in the definition section of
the regulations, will be subject to this
limitation.
The Commission interprets the words
in the definition of Byproduct material,
‘‘produced, extracted, or converted after
extraction for use for a commercial,
medical, or research activity,’’ to mean
a purposeful activity whereby the
radium-226, or other specific
radionuclide, if identified in accordance
with Section 11e.(4) of the revised AEA,
is processed for the use of the radium226 (or other specific radionuclide).
This purposeful activity must relate to
the radium-226 (or other radionuclide)
and not to the overall material that
inadvertently contains radium-226, for
example, fertilizer. However, this
activity need not involve an actual
isotopic separation process specifically
separating radium-226 from radium-228.
In addition, the ‘‘new’’ byproduct
material consists of the specific
radionuclides only, and not the
associated material. For example, in a
radium salt, the atoms other than those
of radium in the salt are not part of the
byproduct material. The NRC notes that
the original definition of Discrete
source, as it had been proposed, was
written to contain strict constraints to
guard against any potential
interpretation that the NRC was
extending its jurisdiction in an
unintended or unauthorized manner.
However, the NRC has found that these
constraints were, in a large part,
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unwarranted because, as already noted,
a discrete source is a subset of the
specifically delineated byproduct
material that is being regulated and
must, therefore, be constrained by the
general definition of the new Byproduct
material. In this connection, the NRC
also removed the words ‘‘distinct from
the radioactivity present in nature’’ as
an unnecessary condition.
Comment: Some commenters had
questions concerning the regulatory
authority over the manufacture of
radiological sources and the associated
waste management. One commenter
noted that the EPAct does not assign
responsibility to the NRC for regulating
the manufacture of discrete sources,
rather, the NRC’s responsibility applies
after a discrete source is produced. The
commenter asked whether the
Agreement States would be required to
regulate the manufacturing and waste
management aspects of source
production, and also who is responsible
for radiological safety if the
manufacturing occurs in a nonAgreement State. Another commenter
asserted that the manufacture of radium
sources should be specifically licensed,
even though the radium may not yet
meet the definition of a Discrete source.
NRC Response: The EPAct gave the
NRC authority to regulate radium-226
that is produced, extracted, or converted
after extraction, before, on, or after the
date of enactment for use for a
commercial, medical, or research
activity. Therefore, the NRC does have
authority for regulating the manufacture
of sources, and the NRC’s responsibility
applies before, on, or after a source is
produced. This should be more evident
with the revised wording of the
definition of Discrete source. Radium226 is byproduct material and under the
NRC’s jurisdiction if it is purposely
concentrated and produced, extracted,
or converted after extraction, for use for
a commercial, medical, or research
activity.
Section 30.3, ‘‘Activities requiring
license,’’ states ‘‘Except as provided in
paragraphs (b)(2), (b)(3), (c)(2), and (c)(3)
of this section and for persons exempt
as provided in this part and part 150 of
this chapter, no person shall
manufacture, produce, transfer, receive,
acquire, own, possess, or use byproduct
material except as authorized in a
specific or general license issued in
accordance with the regulations in this
chapter.’’ Therefore, the NRC will
regulate the manufacture of products
involving the intentional use of discrete
sources of radium-226, as well as
resulting wastes. A specific license will
be required for the manufacture of such
radium sources.
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Comment: A commenter asked if the
proposed definition of Discrete source
would include sources that are
electroplated, i.e., where the
radioactivity is on the surface of the
source and is not encapsulated and
therefore is not separate from nature
(such as radium needles).
NRC Response: Electroplated sources
are included as the wording of the
definition in the final rule clarifies.
Comment: A commenter
recommended that the NRC add the
definition of Discrete source to 10 CFR
Part 35 in addition to 10 CFR Parts 20
and 30.
NRC Response: The NRC Part 35
licensees are required to comply with 10
CFR Parts 20 and 30. The term Discrete
source is being defined in those
regulations. Therefore, it is not
necessary to repeat the definition in Part
35.
Other Naturally Occurring Radioactive
Material
Comment: Two commenters asserted
that they believe the NRC should
consider other criteria in addition to the
International Atomic Energy Agency
Code of Conduct Categories 1 and 2 to
determine if there are any other
nuclides that would pose a threat to
public health and safety and common
defense and security similar to that
posed by a discrete source of radium226.
One commenter did not believe that
using IAEA Categories 1 and 2 to
measure the risk of other nuclides
against the risk posed by discrete
sources of radium-226 meets the EPAct
requirement to consider comparative
risk to public health and safety as well
as common defense and security. The
commenter stated that within the U.S.,
IAEA Categories 1 and 2 have been
associated with ‘‘high-risk’’ sources and
activities of concern to common defense
and security, not to health and safety.
The commenter argued that instead,
because IAEA regards uncontrolled
Categories 1, 2, and 3 sources as
potentially dangerous to human health,
Category 3 is also a threat, and the
NRC’s analysis should at least include
that Category in addition to Categories
1 and 2.
However, the commenter agreed with
the NRC that polonium-210 does not
need to be included in the definition of
Byproduct material under the category
of naturally occurring radioactive
materials posing a similar risk as radium
because the production of polonium-210
discrete sources for commercial,
medical, or research use is by activation
in a reactor, and therefore it is already
regulated as byproduct material.
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Another commenter asked if, by using
IAEA Categories 1 and 2 to measure
other nuclides’ comparative risk to
radium-226, the NRC meant to only
regulate materials that could be fatal or
cause permanent injury if they are not
safely managed or securely protected.
The commenter asked whether discrete
sources of radium-226 that do not meet
the IAEA Category 1 or 2 definitions
would not be regulated in the expanded
definition of Byproduct material. The
commenter asserted that regulations for
radioactive materials should not be
based solely on acute effects.
NRC Response: The EPAct expanded
the definition of Byproduct material to
include any discrete source of naturally
occurring radioactive material, other
than source material, that the NRC, in
consultation with the Administrator of
the EPA, the Secretary of Energy, the
Secretary of Homeland Security, and the
head of any other appropriate Federal
agency, determines would pose a threat
similar to the threat posed by a discrete
source of radium-226 to the public
health and safety or the common
defense and security. The legislation,
and the proposed rule, do not contain
criteria for making such a comparison or
determination. The NRC, in its meeting
with other Federal agencies, considered
the IAEA list of sources in its Code of
Conduct that are considered to pose a
high risk to human health and safety if
not managed safety and securely as a
point of initiation for comparison. The
NRC did not intend the Code of Conduct
listing to be the sole criterion to
measure comparative risk to public
health and safety. Currently, the NRC, in
consultation with other Federal
agencies, has not found any other
naturally occurring radioactive material
that is extracted or converted after
extraction that is used for a commercial,
medical, or research activity that poses
a threat to public health and safety, or
to common defense and security, similar
to radium-226. Discrete sources of
radium-226 much lower in activity than
discussed in the IAEA Code of Conduct
are addressed in the regulations that
will protect public health and safety.
For instance, there are no exempt
concentration or quantity levels for
radium-226 in 10 CFR Part 30. There are
Annual Limits on Intake and Derived
Air Concentration limits in Appendix B
to 10 CFR Part 20 for radium-226. The
EPAct has provided a mechanism for
the Commission to include additional
discrete sources of naturally occurring
radioactive material in the future
following consultation with other
Federal agencies, if the need arises to
consider other naturally occurring
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radioactive material for byproduct
material. The NRC, along with other
Federal agencies, will use all of these
criteria to determine if there are any
other naturally occurring radioactive
material posing a threat to public health
and safety similar to radium-226. In
addition, the NRC did not intend to
imply that it was limiting its regulatory
authority over radium-226 at quantities
which could be fatal or cause permanent
damage, or basing its regulations for
radioactive material solely on acute
effects.
Comments Related to Radium-226
Comment: A commenter, noting that
radium-226 is a naturally occurring
material present in most city water
supplies, asked how the NRC proposes
to differentiate regulated doses from
background doses, and normal levels of
radium-226 in building materials from
regulated radium-226 contamination.
The commenter also noted that because
of radium’s high excretion rate,
bioassays may need to include weekly
to monthly fecal analyses to suppress
the missed dose to a value less than a
few Roentgen Equivalent Man (Rem) per
year. The commenter asserted that it is
highly unlikely that licensees will be
able to determine if a nonoccupational
individual received less than 1 mSv
(100 mrem).
NRC Response: The NRC’s regulations
in 10 CFR 20.1502 specify the criteria
that licensees must address to show
compliance with monitoring
requirements for occupational dose
limits. The regulation requires licensees
in monitoring occupational exposure to
take into account radiation from both
licensed and unlicensed radiation
sources under the control of the
licensee. Occupational exposure does
not include doses from background
radiation. It is true that radium is
ubiquitous in nature. However, there are
methods that can be used to determine
and subtract background radiation from
dose measurements of occupational
dose, such as determining ambient
exposure by surveys or monitoring in
the absence of byproduct material, and
using this information to subtract
background component from readings
that include a total of both background
and occupational exposure.
External exposure from radium-226
sources comes from its daughter product
and gamma radiation, and occupational
exposure is usually determined by a
radiation dosimeter (badge). For internal
exposure, a licensee can measure the
concentration of radioactive material in
the air in the work area, the quantity of
radionuclide in the body, the quantity of
radionuclide excreted by the body, or a
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combination of all these measurements.
Excretion measurement is not the only
method to determine dose from internal
exposure.
Comment: A commenter asked if, for
source activity reporting and internal/
external dosimetry, owners would be
required to report any information about
the radionuclide products that come
from radium (daughter products). The
commenter asked whether the most
current International Commission on
Radiological Protection (ICRP)/National
Council on Radiation Protection and
Measurements (NCRP) internal/external
dosimetry standards will be used by the
NRC, and if the newer consensus
standards regarding actinide uptakes
would be acceptable. The commenter
also asked whether the American
National Standards Institute (ANSI)/
Health Physics Society (HPS) N43.4–
2000 Classification of Radioactive SelfLuminous Light Sources Standard is a
reference document that will be used by
the NRC.
NRC Response: If the daughter
products came from byproduct material
(i.e., the radium-226 parent was
byproduct material), the internal and
external exposure would be required to
be considered. Daughters from radium226, which are not byproduct material,
would not fall under the NRC’s
jurisdiction. However, 10 CFR 20.1502
specifies that, for occupational
exposure, licensees must take into
account radiation from both licensed
and unlicensed radiation sources under
the control of the licensee.
The current methodology used in 10
CFR Part 20 is from Federal Guidance
Report Number 11, ‘‘Limiting Values of
Radionuclide Intake and Air
Concentration and Dose Conversion
Factors for Inhalation, Submersion, and
Ingestion,’’ for internal dose
coefficients, and ICRP 26,
‘‘Recommendations of the International
Commission on Radiological Protection,
January 1977,’’ for external exposure.
Radium-226 values in Appendix B to 10
CFR Part 20 came from the Federal
Guidance Report Number 11. The
methodologies are not being changed at
this time.
The ANSI/HPS N43.4–2000 Standard,
Classification of Radioactive SelfLuminous Light Sources, was not
specifically referenced in the
regulations or in the Statements of
Consideration to the proposed rule. The
N43.4–2000 Standard classifies certain
radioactive self-luminous light sources
but does not establish design or safety
standards. It is more for the use of the
supplier or user to establish design
features by providing minimum
prototype testing requirements for these
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types of sources, and promoting
uniformity in the production of these
types of light sources.
Comment: A commenter stated that
under the proposed rulemaking (10 CFR
30.32(g)), any specific license
applications authorizing prostate
brachytherapy must identify source
manufacturers and model numbers of
Palladium-103 brachytherapy sources.
The commenter suggested that this
requirement could be avoided by
amending 10 CFR 30.32(g) to remove the
requirement for identifying
manufacturers and model numbers for
sources authorized for any medical uses
(specifically those per 10 CFR 35.400).
The commenter also believes that the
proposed rule was unclear about how
some legacy radium-226 sources that
were not eligible for a general license
could be specifically licensed per the 10
CFR 30.32(g) requirements.
NRC Response: Revision of 10 CFR
30.32(g) to remove the requirement for
identifying manufacturers and model
numbers for sources authorized for any
medical uses (specifically those per 10
CFR 35.400) is outside the scope of this
rulemaking effort. However, the NRC is
revising 10 CFR 30.32(g) to address the
issue of sealed sources to address the
information required from licensees that
have legacy sources containing the
newly defined byproduct materials that
are not in the SS&D registry.
Comment: A commenter asserted that
the radium-226 issues are likely to be
much larger and broader than believed.
The commenter also noted that there are
few consultants available with radium
experience and asked whether the NRC
has considered that it may have to act
as a resource to answer questions and
resolve problems.
NRC Response: The NRC recognizes
that there may be broad issues regarding
radium and that, although radium-226
was widely used in the past, there does
not appear to be a significant volume of
information concerning its health and
safety implications and past uses. The
NRC plans to develop a link on its
public website under Nuclear Materials
for ‘‘Frequently Asked Questions’’ to try
to help answer some of the questions
about radium as they arise.
Regulating Items Containing Radium226
Comment: In response to Question 1
in NRC’s request for additional
information on issues in the proposed
rule, technical information to support
an exemption for old radium-226
sources, several commenters discussed
the availability of data on the possession
and disposal of radium items. The
commenters stated that they do not
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believe that a consolidated source of
information on the items, their location,
or owners exists that could provide
enough safety information for the NRC
to make an informed decision on the
regulation of these items.
One commenter recommended that
the NRC conduct a systematic study to
assess the potential individual and
collective (population) radiation doses
associated with the use, possession,
transfer, and disposal of regulated
radium items, especially antiquities,
and suggested that the study could be
similar to NUREG–1717, ‘‘Systematic
Radiological Assessment of Exemptions
for Source and Byproduct Materials.’’
The commenter further recommended
that the NRC review NUREG/CP–0001,
‘‘Radioactivity in Consumer Products,’’
dated August 1978, for more
information on radium in watches,
smoke detectors, lightning rods, and
other consumer products.
NRC Response: The NRC agrees that
there does not appear to be a
consolidated source of information
concerning radium items, their location,
or who may be in possession of these
items. The NRC staff contacted several
organizations, such as the National
Association of Watch & Clock
Collectors, to alert them of the
publication of the proposed rule
because they might have an interest in
this rulemaking. In addition, these
organizations might be able to provide
further information to assist the NRC in
making regulatory decisions regarding
radium items. The NRC staff has also
secured the services of a contractor to
help it better characterize the likely
activities and potential doses to users,
initially, from the proposed exemption
for radium timepieces, and, at a later
date, other radium antiquities that will
be subject to general licensing. The NRC
staff has used NUREG/CP–0001 as part
of its evaluation and has referred the
NUREG to its contractor for use in its
review. Evaluations of previously
manufactured items would be somewhat
different than those in NUREG–1717 as
no new distribution is being allowed for
many of these items.
Comment: In response to the NRC’s
Issue for Public Comment Q.1, a
commenter noted that pre-WWII naval
warships used radium luminescent
buttons as deck edge markers. The
commenter was concerned that these
marker buttons may not meet the NRC’s
descriptions of the various radium
sources. The commenter suggested that
the NRC expand the coverage of radium226 items beyond light sources in
aircraft and medical uses. The
commenter also asked if the NRC will
bring enforcement actions against
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persons who discover previously
unknown radium-226 items, and who
would be financially responsible for
those items.
NRC Response: The NRC has become
aware that radium luminous items were
also commonly used on military
vehicles and naval ships in addition to
aircraft. The NRC believes that vehicles
with radium luminous items may be
found in military museums and owned
by private collectors. With regard to
ships, it is the NRC’s understanding that
the Navy made a concerted effort years
ago to remove and dispose of radium
luminous items. However, there may be
some of these items remaining on
‘‘mothballed’’ ships. The NRC agrees
that the general license in 10 CFR 31.12
should be expanded to include
additional military vehicles. As
restructured, the 10 CFR 31.12 general
license would automatically apply to all
possessors of antiquities originally
intended for use by the general public,
nonintact timepieces, and timepiece
hands and dials no longer installed in
timepieces; luminous items installed in
air, marine, or land vessels or ships
(This would include airplanes,
helicopters, jeeps, trucks, tanks, ships,
landing vessels, artillery pieces, and any
other former military use vehicle no
longer under the control of the military.)
See discussion under New General
License for Certain Items and SelfLuminous Products Containing Radium226, above; all other luminous products,
provided that no more than 100 items
are used or stored at the same location
at any one time; and small radium
sources containing no more than 0.037
MBq (1 µCi) of radium-226. While the
general license does not authorize the
manufacture, assembly, disassembly, or
repair of most of the listed items, the
disassembly and repair of timepieces
would be allowed. The general license
is automatically granted by NRC
regulations to persons meeting the
general license criteria. No action is
required from these persons to obtain a
general license. The NRC foresees no
issue regarding possession of these
items provided that the restrictions on
the general license are complied with.
The NRC would hold persons who
possess the items financially
responsible for the items with regard to
such things as disposal or meeting other
requirements of the general license.
The general license established in 10
CFR 31.12 is revised from the proposed
rule as follows: Paragraph (a)(2) is
revised to read, ‘‘Nonintact timepieces
and timepiece hands and dials no longer
installed in timepieces’’; paragraph
(a)(3) is revised to read, ‘‘Luminous
items installed in air, marine, or land
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vehicles’’; paragraph (a)(4) is revised to
read, ‘‘All other luminous items,
provided that no more than 100 are used
or stored at the same location at any one
time’’; and paragraph (d) is revised to
read, ‘‘The general license in paragraph
(a) of this section does not authorize the
manufacture, assembly, disassembly,
repair, or import of products containing
radium-226, except that timepieces may
be disassembled and repaired’’.
Comment: A commenter asked
whether the NRC’s reporting
requirements apply to owners of past
accelerators or radium-226 items if they
do not presently have control over the
item. For example, the commenter noted
that wrecked ships and airplanes could
contain radium dials, and luminous dial
instruments could be disposed of in a
sanitary landfill, and the original
owners of these items would not
necessarily have any knowledge of their
current location.
NRC Response: The NRC’s regulations
apply to persons who currently, or will
in the future, possess byproduct
material. The NRC would not hold
persons responsible for reporting any
previous possession, transfers, or
disposals of materials that may have
been disposed into locations such as
municipal landfills over which they
have no control. However, while the
NRC will not hold anyone accountable
for past disposals in a landfill, these
persons might be accountable under
EPA’s Superfund regulations.
Comment: In response to the NRC’s
Issue for Public Comment Q.1, a
commenter stated that the trade of
radium-dial watches has increased in
the past 10 years with most of these sold
through Internet auction sites or on
personal web sites. The commenter does
not believe that the majority of the
people buying these watches are aware
that the watches are radioactive or the
degree of their radioactivity and is
concerned about the effect of these
watches on people who are
inadvertently exposed to the watches by
their incidental close proximity to
someone wearing or carrying one. The
commenter also noted that most owners
of these watches are not aware that the
radiation is still active because the
luminous scintillating material in the
paint mixture is no longer working. In
the commenter’s opinion, the sale and
use of vintage radium dial watches is
not in keeping with the goal of ‘‘as low
as is reasonably achievable’’ (ALARA).
The commenter stated that many
people open these watches to try to
repair them, to clean their dials, and to
replace hands, that many of these
watches are bought and sold in poor
condition (e.g., open, not sealed), and
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that often a watch is sold with the
crystal (glass) missing and the radium
paint on the dial exposed to the outside
air. The commenter noted that radium
powder/dust can and does flake off of
exposed dials and broken watch cases.
The commenter indicated that the
NRC should require possessors of these
kinds of watches to follow the same
shipping requirements as businesses,
because the watches exhibit the same
types of hazards. The commenter
recommended that the NRC consider
these concerns in connection with
defining byproduct material. The
commenter does not think activity
thresholds will be useful or practical,
but that any rulemaking would have to
consider ‘‘radium dial watch’’ as an
entity.
NRC Response: To further support the
exemption and the related general
license with regard to timepieces, the
NRC conducted a scoping study to
determine the typical and maximum
radium activities used in various types
of timepieces and the potential
exposures that might result to users,
collectors, and repair technicians. The
results of this study indicate that the
doses expected to an individual user,
collector, or repair technician are
acceptably low.
As directed by the EPAct, the NRC’s
development of the proposed rule
considered the CRCPD’s applicable
SSRs. As provided in the SSRs, the NRC
has included an exemption from
licensing for persons who possess intact
timepieces that contain no more than
0.037 megabecquerel (1.0 microcurie) of
radium. The NRC regulation is more
restrictive than the SSRs in that the
exemption only applies to intact
timepieces. In the proposed rule, the
exemption would also have allowed
antique collectors and watch repair
facilities to repair up to 10 timepieces
in any year. In the final rule, however,
the allowance for repair is eliminated
from the exemption and is now
authorized under the general license
provision. As noted, the exemption only
applies to intact timepieces. Possession
of nonintact timepieces, or radium
luminous parts such as hands, dials, or
faces, and timepiece disassembly and
repair would be subject to the general
license provided in 10 CFR 31.12.
Shipment of radium timepieces are
currently and will continue to be subject
to regulations established by the DOT
and the United States Postal Service.
Such shipments will now also come
under the NRC’s regulations in 10 CFR
Part 71.
The NRC has specifically included
radium in the definition of Byproduct
material. The NRC appreciates that most
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consumers will probably not know how
much activity there may be in a
particular timepiece. However, the
NRC’s evaluation indicates that most
timepieces that were produced in the
past contained less than the 1microcurie (37 kBq) exempt limit. If a
particular intact timepiece contains
more than 1 microcurie (37 kBq), then
possession would fall under the general
license provided in 10 CFR 31.12.
Comment: In response to the NRC’s
Issue for Public Comment Q.1, a
commenter stated that it has never
found or been informed of a leak from
any of the double-encapsulated and
welded radium-226/beryllium sources
in their gauges. The commenter noted
that even in some worst-case accidents
that occurred, such as compactors
running over gauges, no source has
leaked radioactive material, and no
accident has caused the source to be
separated from its shield.
NRC Response: The NRC notes that
the commenter appears to be describing
sources used in portable moisturedensity measuring devices used in
roadbed and other construction
activities. Generally, these devices are
possessed under a specific license,
although there is a possibility some
devices may have been authorized by a
State under a specific license similar to
10 CFR 32.51 for distribution to general
licensees under requirements
comparable to 10 CFR 31.5. As noted in
response to another comment, if a
device is generally licensed, a label on
the product should indicate its generally
licensed status. In either case, the
licensing authorization would remain
the same. Periodic source leak testing is
generally required for such devices.
Exemption of Certain Radium-226 Items
Comment: One commenter
recommended that the proposed limit
for repairing timepieces containing
radium-226 be increased from 10 to 18
units per year. This commenter also
suggested that the limitation should not
be restricted by company, but by the
number of qualified timepiece repair
technicians employed. The commenter
suggested that this change is needed to
provide necessary consideration for
industry consolidation, the emergence
of specialized repair centers, and the
expansion of geographic markets
brought about by the Internet and
globalization.
NRC Response: The NRC conducted a
scoping study regarding potential risk
associated with handling timepieces
containing radium. Based on the results
of the scoping study on the potential
health and safety impacts of repairing
timepieces containing radium-226
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(including the storage of loose parts
likely to be associated with repair
facilities and not covered by the
exemption), the Commission has
decided not to limit the number of
repairs. However, the repair will be
subject to the general license in 10 CFR
31.12. There may be limited
circumstances where companies with a
number of timepiece repair technicians
specifically involved with handing
radium-226 should be specifically
licensed or may be required to conduct
cleanup activities. See additional
comment and response discussion on
General License of Certain Radium-226
Items and on Specific Licenses for
Radium-226.
Comment: A commenter disagreed
with the NRC’s proposal under 10 CFR
30.20 to exempt smoke detectors
containing up to 74 kBq (2 µCi) of
radium-226 from the licensing
requirements in 10 CFR Parts 20, 30
through 36, and 39. The commenter
stated that radiation detection
equipment at landfills and scrap
facilities are very sensitive and are often
set to thresholds less than twice the
background radiation. The commenter
noted that low activity sources, such as
smoke detectors containing up to 74 kBq
(2 µCi) of radium-226, will trigger these
detectors and cause the arriving load to
be rejected. The commenter stated that
this would increase the number of
incidents that the States would be
required to respond to, which would
result in an increased expenditure of
time, human resources, and funds. The
commenter recommended that these
sources should not be allowed to be
disposed of in the general waste stream,
and that facilities with devices
containing these levels of activity
should be generally licensed and should
be required to dispose of the sources
properly.
NRC Response: The exemption for
smoke detectors is only being expanded
to cover detectors previously distributed
in accordance with a specific license
issued by a State under comparable
provisions to 10 CFR 32.26 authorizing
distribution to persons exempt from
licensing. Smoke detectors meeting this
criteria are already exempted by most
States. Documentation of the individual
safety evaluations made to demonstrate
that these detectors meet the applicable
safety criteria is incomplete. However,
the Bureau of Radiological Health (BRH)
of the FDA, in consultation with the
States and other Federal agencies
including the NRC and its predecessor,
the Atomic Energy Commission (AEC),
developed NARM guides in the 1970’s,
to assist the States to develop more
uniform regulations for NARM. These
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guides included one for gas and aerosol
detectors, which was essentially
equivalent to the NRC’s regulations in
10 CFR 32.26, 32.27 and 32.28. By the
late 1970’s, the SSRs included
comparable provisions. The guide and
the SSRs also included a quantity limit
of 3.7 kBq (0.1 µCi) for radium-226.
Some information on potential
impacts of disposal of these detectors is
contained in the Nuclear Energy Agency
document, ‘‘Recommendations for
ionization chamber smoke detectors in
implementation of radiation protection
standards, 1977,’’ and NUREG/CR–1156,
‘‘Environmental Assessment of
Ionization Chamber Smoke Detectors
Containing Am-241,’’ November 1979.
According to these documents,
americium-241 had almost completely
replaced radium-226 in smoke detectors
being sold by the late seventies, and the
quantities of radium-226 used had
generally been reduced to no more than
3 kBq (1 µCi), typically 1.8 kBq (0.05
µCi). It is not expected that there are
large numbers of smoke detectors with
radium-226 still in existence, with the
smaller quantities being more common
among those that are. Thus, it is not
expected that large numbers of detectors
containing radium-226 would be
disposed of concurrently. The disposal
of small numbers of such detectors in a
landfill or municipal incinerator is not
expected to result in a significant
impact to public health and safety or the
environment.
The commenter was particularly
concerned with the cost related to
detectors containing radium being
detected at landfills and scrap facilities.
Exempting from the NRC’s regulations
those detectors which have been
previously exempted from regulation by
the States will not add to the number of
these incidents nor will not exempting
them be able to prevent all such
incidents. However, a significant part of
the cost is incurred after identification
of a source, if it requires a more
expensive disposal route. In many cases,
once a radioactive source has triggered
a monitor, it can still be disposed of at
the landfill if this is determined to be an
acceptable disposal option. Because the
EPAct allows for the disposal of the
newly added byproduct material in
disposal facilities permitted under
Federal or State solid or hazardous
waste laws, acceptability at landfills for
disposal of an exempted product or
material should be improved. What
happens after identification will
depend, in part, on the label, which
would have been required by the State
at the time of distribution. If intact and
legible, it would indicate whether the
product had been exempted from State
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regulations or generally licensed.
However, the NRC recognizes, as one
commenter pointed out, that some
landfill operators may not be obligated
to accept such material at their facilities.
The Commission continues to
consider the exemption of these
previously distributed detectors to be
justified. The final rule includes this
exemption in revised 10 CFR 30.20.
Comment: Two of the State
commenters stated that the NRC should
add 3.7 kilobecquerel (kBq) [0.1
microcurie (µCi)] of radium-226 to 10
CFR 30.19 for self-luminous products or
otherwise include exemption language
from the SSRs for low activity radium226 sources rather than including those
sources under a general license. One of
these commenters specifically
mentioned types of products other than
self-luminous products listed in the
proposed general license in 10 CFR
31.12 and indicated that they should
also be exempt if containing the same
low quantity of radium-226. Both of
these commenters asserted that there are
no problems known to exist with these
exempt sources so there is no sufficient
reason for the NRC to not exempt them
as the States have done for many
decades, and stated that if the NRC is
aware of some risk to public health and
safety from these very low activity
sources, then it should provide the
information.
NRC Response: There is only limited
information on these items. However,
there is some indication that the applied
radium may be subject to such concerns
as flaking off due to aging. The NARM
guides developed by BRH/FDA in the
1970’s included a guide for
radioluminous products which
contained safety criteria for approval of
a product for use under a general
license, but not for use under an
exemption. The SSRs do not include
provisions similar to those in 10 CFR
32.22, 32.23, and 32.24, for the
manufacture or initial distribution of
self-luminous products for use under an
exemption. The SSR provision similar
to 10 CFR 30.19 covers only previously
acquired products in the case of items
containing radium-226. It appears that
these products were generally not
evaluated under provisions comparable
to those in 10 CFR 32.22, 32.23, and
32.24 for self-luminous products. This
SSR provision exempts ‘‘articles’’
containing radium under the heading
‘‘Self-luminous products.’’ While the
quantity limit is less than that for
watches, the category of product is very
open-ended and could include items
where the radium is not contained.
For these reasons, the Commission
considers it prudent not to exempt this
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category of products that is covered by
an exemption in the SSRs, or other
unspecified products with no more than
3.7 kBq (0.1 µCi) of radium-226. In
addition, there are many self-luminous
products containing more than 3.7 kBq
(0.1 µCi) of radium-226 and most would
not be labeled with the quantity or
activity of the radium-226. It would be
difficult to determine which products
would fall under the exemption and
which would fall under the general
license in 10 CFR 31.12.
Comment: One commenter noted the
proposed graded approach for different
levels of radium-226 sources and also
mentioned the discussion in the
Statements of Consideration of various
approaches used by the non-Agreement
States. This commenter responded to
the NRC’s request for input on whether
a general license approach or exemption
approach would be better for some of
the devices containing radium-226, by
saying that an exemption would gather
no data, and therefore not be the desired
path except for the smallest amounts
(e.g., 1 µCi). This commenter also stated
that an exemption concentration level of
1 µCi (and an appropriate corresponding
exempt quantity limit) could be
considered with the specific/general
license approach for materials above
that de minis amount.
NRC Response: The SSRs do not
include an exempt quantity or exempt
concentration for radium-226. With the
exception of an exempt quantity of
polonium-210, these exemptions do not
include alpha emitters. Given that there
are no materials in use that have been
previously universally exempt from
licensing under State regulations, there
is no justification for adding such
exemptions now. Without a
demonstrated need, the NRC does not
consider it prudent to allow
introduction of radium-226 into
materials and products to be used by
persons exempt from licensing or to
allow the distribution of radium-226 as
exempt quantities.
The requirements for registration of
generally licensed devices only apply to
those generally licensed under 10 CFR
31.5 and then only if the device
contains a radium source of 3.7 MBq
(0.1 mCi) or greater. The new general
license in 10 CFR 31.12 will not require
registration by possessors of the items
identified in the regulation nor does the
NRC believe there is a need to impose
such a regulatory burden on the general
licensee.
Comment: A commenter
recommended that the NRC include an
exemption in the final rule for Internal
Revenue Service (IRS)-designated
501(c)(3) organizations that existed
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before the effective date of the final rule
that operate, in whole or in part, as an
accredited school of watch and/or clock
repair and/or specialty museum with a
primary focus on housing and
exhibiting timepieces and related
objects. The commenter noted that it is
important for students to have access to
examples of radium parts and watches
as part of their training, and museums
must be able to preserve and present
practices and objects through exhibits to
fulfill their educational mission. The
commenter stated that without this
exemption, the proposed inventory
process and licensing fees would create
an undue burden on these
organizations.
NRC Response: The status of an
organization as a nonprofit institution
and whether its mission is educational
are not appropriate bases for exemption
from licensing requirements.
Exemptions from licensing are based
primarily on findings with respect to
health, safety, and environmental
impacts. It should be noted, however,
that organizations categorized as small
entities in accordance with 10 CFR
2.810 are eligible for reduced annual
licensing fees in accordance with 10
CFR 171.16. Also, a licensee, such as a
nonprofit educational institution, may
be exempt from application fees under
10 CFR 170.11 and annual licensing fees
under 10 CFR 171.11, depending on the
licensed activities. Also, a museum or
school may possess watches under the
exemption in 10 CFR 30.15(a)(1)
irrespective of whether other products
or activities require these entities to be
a general or specific licensee.
General License of Certain Radium-226
Items
Comment: Several commenters
responded to the NRC’s Issue for Public
Comment Q.6 request for information on
health and safety impact from activities
involving radium-226 sources that
would support a regulatory framework
other than general licensing, such as an
exemption. In general, the commenters
agreed that an exemption would be
preferable to a general license for items
containing radium-226; however, most
of the commenters also agreed that more
information on the risks of these items
is needed before a final decision is
made.
Several of the commenters, citing a
number of reasons, recommended that
the NRC create a time-limited
exemption for antiquities containing
radium-226 until such time as sufficient
data are gathered and analyzed to
determine whether these items exhibit
high enough risk to require a license
rather than a permanent exemption.
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Two commenters noted that their
States have had to respond to scrap
metal yards, steel mills, and municipal
waste sites where radium-226 items had
caused loads to be rejected and noted
that this happens because possessors of
these items do not usually know how to
safely dispose of them.
Other commenters suggested that an
exemption for items containing radium226 is better as long as enough safety
data exist proving a low risk level for
these items to justify the exemption and
recommended that more investigation,
which might include working groups
and a public outreach effort, is needed
into the safety risks of these items. One
commenter noted that such an outreach
effort would place a burden on State
financial and human resources, and
recommended that the NRC conduct a
cost-benefit analysis to analyze these
impacts on the States.
While the commenters were in
general agreement with the NRC’s
proposed approach regarding the
specific constraints in the proposed
exemption in 10 CFR 30.15(a)(1)(viii),
one commenter asked how the NRC
proposes to regulate radiological
antiquities that are bought and sold on
the Internet.
NRC Response: The NRC notes that,
for the most part, there appears to be no
existing regulatory approach for many of
the radium items identified in the 10
CFR 31.12 general license, and that very
little information exists. Therefore, the
NRC believes it is more appropriate to
regulate the products under a general
license until the NRC has had the
opportunity to further document and
evaluate these items and practices, and
determine whether or not additional
exemptions may be appropriate. The
NRC also recognizes that many
individuals may not be aware that they
possess radium items and that
‘‘incidents’’ where these items are
identified at waste sites may continue
into the future.
Based on its initial evaluations, the
NRC has been able to find only limited
information regarding existing safety
data which show a low risk level for
these items which is necessary to justify
an exemption. The NRC currently has
plans to conduct further evaluations,
including gathering information
concerning the products, to help it
better characterize the likely activities
and potential doses to users from
radium antiquities that will be subject to
general licensing. The NRC will
consider the commenter’s suggestion
regarding a public outreach program
and the program’s impact on State and
Federal resources.
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The general license in 10 CFR 31.12
allows general licensees to transfer
possession of antiquities and other
products between general licensees, and
this includes antiquities bought and
sold over the Internet. The NRC believes
this is acceptable while the NRC
conducts evaluations and because the
limited information available does
indicate a low risk associated with these
items.
Comment: Several commenters
discussed the appropriate regulation of
the repair and disassembly of items
containing radium-226. One commenter
stated that it believes a ‘‘prohibition of
these activities under general licensure’’
is appropriate. The commenter
recommended that disassembly, repair,
and assembly work on an antique item
should be authorized by a specific
license, not a general license. Another
commenter recommended that facilities
disassembling or repairing timepieces
containing radium be generally licensed
until a study is conducted and
completed to assess the potential
individual and collective (population)
radiation doses associated with this
industry.
NRC Response: The NRC agrees that
the repair and dissassembly of certain
items containing radium-226 should
only be conducted under a specific
license and notes that 10 CFR 31.12(d)
prohibits these activities under the
general license. The NRC conducted a
scoping study on potential exposures
regarding activities involving timepieces
containing radium-226. Based on the
results of the scoping study, the NRC
will allow timepiece disassembly and
repair under the general license
provision.
Comment: Several commenters were
in support of a general license for items
containing radium. One commenter
requested clarification of the general
license requirements for radium dials,
gauges, and buttons installed in aircraft
used as static displays, in aircraft used
in museums, in aircraft that are in
storage for potential re-use as
refurbished piloted aircraft, as
unmanned drone aircraft (potentially
used as targets), or as a source for spare
parts, and in dials, gauges, buttons, and/
or painted lettering or numbering that
do not have a glass or crystal face
covering, or for which the covering is
damaged or broken. The commenter also
expressed concern that the transfer
requirements of proposed 10 CFR
31.12(c)(2) may place an undue burden
on the licensees and recommended that
the NRC should allow for easier transfer
under the general license from one
entity to another.
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One commenter stated that some
museums possess devices containing
radium-226 in gauges and other safety
devices installed in ground vehicles
(e.g., trucks, armored tanks, artillery
pieces), portable radios, and submarine
instrument panels on display and that
public access to these devices is
controlled in the same manner as
aircraft at these museums. The
commenter recommended that the NRC
expand the 10 CFR 30.12 general license
to include radium containing devices
installed on other types of vehicles and
equipment besides just aircraft.
Another commenter stated that a
common practice on World War II
aircraft was to apply radium paint over
the words and numbers engraved on
cockpit instrument panels so that they
were visible in the dark. The commenter
noted that in these cases, the painted
surfaces are not contained behind glass
as in gauges.
NRC Response: The rule allowing
possession under the general license
rule applies to all luminous items
installed in aircraft regardless of
whether the material is in an intact
gauge, a gauge missing a face plate, or
as luminous paint applied on the
outside of a gauge. The general license
also applies to all aircraft regardless if
the aircraft is routinely used or in
storage.
Paragraph (a) of 10 CFR 31.12 allows
any general licensee to transfer any
generally licensed item identified in this
section to another general licensee for
possession and use without restriction.
The provisions in 10 CFR 31.12(c)(2)
only restrict transfers to specific
licensees or as otherwise authorized by
the NRC under 10 CFR 20.2008 when
the general licensee is intending to
dispose of the item.
The NRC agrees that the general
license should be extended to include
luminous items installed in additional
large military transport vehicles no
longer under the control of the military
and has modified 10 CFR 31.12 to
include marine ships and land vehicles
in addition to aircraft. The general
license also allows for the possession of
up to 100 other luminous items,
including uninstalled aircraft safety
devices.
Specific License for Radium-226
Comment: A commenter stated that
there should be a threshold level for
possession of radium-226 luminous
items that are not contained in an intact
product beyond which a specific license
is preferable, whether or not the items
are intact. The commenter
recommended that the NRC consider
requiring a specific license for a number
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of items that is at least the exempt
quantity value times 10 to 100. The
commenter also stated that commercial
transfers of items containing radium-226
should not be treated the same as
possession and use and recommended
that the NRC require a specific license
for commercial transfers.
NRC Response: The NRC does not
agree, based on other comments and the
information currently available, that it
should impose more restrictive
requirements beyond those provided in
10 CFR 31.12. However, the NRC may
consider the commenter’s suggestions in
a future rulemaking should the results
from further evaluations, and
characterization of the likely activities
and potential doses to users from
radium antiquities, indicate a need for
additional restrictions in these areas.
Comment: With regard to proposed 10
CFR 31.8(b), which relates to the general
license for radium-226 in calibration or
reference sources, one commenter
recommended that the NRC provide a
‘‘grandfather clause for [radium-226]
items’’ that were approved for
manufacture before 10 CFR 32.57 was
adopted in its current form. The
commenter stated that the States should
be able to simply attest that the
calibration or reference sources were
manufactured to standards or criteria
that have been demonstrated through
years of use to be adequate to protect the
public health and safety and the users
of the sources. The commenter asserted
that, unless the NRC has knowledge of
problems of leaking sources of this type,
the NRC should provide clarification
that these sources are acceptable as
manufactured.
NRC Response: ‘‘The general license
in 10 CFR 31.8 contains a footnote to
include any sources labeled in
accordance with the provisions
applicable before January 19, 1975, i.e.,
with labels referring to the AEC before
the creation of the NRC. In addition to
the revision of paragraph (b) of 10 CFR
31.8, this footnote is being revised to
include a requirement that sources
containing radium-226 be labeled as
required by the authorizing State at the
time of manufacture. Therefore, the NRC
believes that there is no need for any
further grandfathering. Any calibration
and reference source (or its container)
containing radium-226, that was
manufactured or initially transferred
under requirements comparable to 10
CFR 32.57, would be labeled
accordingly. As suggested by the
commenter, the NRC expects that these
sources are acceptable as manufactured.
Comment: A commenter noted that
the proposed 10 CFR 32.59 required
testing for leakage ‘‘with a filter paper’’
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and ‘‘application of moderate finger
pressure.’’ The commenter believes this
is overly prescriptive, prohibiting the
use of other materials and requiring the
use of ‘‘the fingers.’’
NRC Response: The requirements
referred to by the commenter are the
existing requirements for distributors of
calibration and reference sources
containing americium-241 for use under
the general license in 10 CFR 31.8 and
equivalent general licenses of the
Agreement States, to which radium-226
is being added. It is consistent with the
SSRs. The commenter’s request for this
general revision is outside of the scope
of this rulemaking.
Comments Related to Accelerator and
Accelerator-Produced Radioactive
Material
Comment: One commenter believes
that the definition of Cyclotron was
unclear, noting the statement that
particles are ‘‘bent’’.
NRC Response: To address the
commenter’s concern, the NRC is
revising the definition of Cyclotron to
indicate that the charged particles travel
in an outward spiral or circular path.
Comment: A commenter stated that
the definition of Particle accelerator
should be revised. The commenter
noted that the definition currently states
that a particle accelerator is a machine
capable of ‘‘discharging the resultant
particles or other radiation into a
medium at energies in excess of 1
megaelectron volt (MeV).’’ The
commenter noted that cathode ray tube
television sets were developed from
early particle accelerators, and that
while commercial television sets
operate at 0.035 MeV, overzealous
application of the rule might include
these and other smaller particle
accelerators. The commenter also stated
that it is possible that any beta-emitting
source with energies greater than 1 MeV
in a vacuum might also be considered
an accelerator. The commenter noted
that the ‘‘NRC is now regulating exotic
particles such as muons, but that [the
commenter’s] search of 10 CFR part 20
did not find any reference to muons.’’
The commenter noted that the NRC
should also ‘‘expect to see extremity
doses approaching 50 REM per year for
the preparers of the acceleratorproduced medical isotope unit doses’’
and apparently that the NRC should
consider those health effects in its
regulation of NARM.
NRC Response: The definition of
Particle accelerator has been used by
State radiation control programs for
many years. The lower limit of 1 MeV
was chosen to avoid regulation of lower
energy accelerators. Consistent with the
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intent of the EPAct, the NRC will
regulate byproduct material as defined
in the EPAct as radioactive material
produced by use of a particle
accelerator. The NRC will not regulate
the possession or operation of any
particle accelerators that will not
produce the byproduct material that the
NRC will regulate. Also, note that the
NRC will not regulate particles such as
protons or electrons, or exotic particles
such as muons generated in these
particle accelerators that will not
produce byproduct material.
The NRC is aware that high radiation
doses are possible from handling
accelerator-produced radioactive
materials. Because licensees are
required to comply with the radiation
safety program requirements in 10 CFR
Part 20, the NRC expects that licensees
will use handling methods and
equipment as part of their radiation
safety program to prevent high radiation
doses. No change is made to the
definition.
Comment: A commenter noted that
for hadronic beams, measurements of
energy per nucleon (MeV/nucleon) may
provide more useful information
(apparently rather than the maximum
energy of the accelerated particles). The
commenter gave as an example that a 1MeV proton will have different
activation potential than a uranium-238
nucleus with (collectively) 1 MeV.
NRC Response: The commenter’s
view on energy level is noted. Because
the NRC only regulates the radioactive
material produced by using a particle
accelerator and not the radiation beam
itself, the activation potential of the
beam or particle has no direct impact in
the NRC’s determination of the
regulated material. Radioactive material
is defined as byproduct material if it is
produced for use for commercial,
medical, or research activities and is
produced by irradiation or activation in
a particle accelerator regardless of the
type or energy level of the particle.
Comment: A commenter asked if the
NRC’s jurisdiction over accelerators
includes particle beam weapons in
space, the ion drive technologies being
developed for interplanetary use, or
laser wake field accelerators; or if the
NRC’s jurisdiction would extend to such
items and materials as beam energy,
interlock requirements, minimization of
activated/spallated materials, ion
species accelerated/charge state, or
minimization of beryllium components
(neutron spallation targets). The
commenter also asked what parts of an
accelerator (e.g., magnets, power
supplies, RF cavities, beam pipe, nuts,
bolts, wire, shielding, tools) the NRC
will regulate. The commenter noted that
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these parts are transferred between the
DOE-owned/NRC-regulated accelerators
and worldwide researchers.
NRC Response: The NRC’s authority
does not include regulating accelerators
or parts of an accelerator, nor does it
include particles or particle beams. The
NRC does not regulate accelerator or
accelerator operating parameters.
However, certain Agreement and nonAgreement States may regulate
accelerators, accelerator operations, and
accelerator safety requirements within
their State’s radiation control programs.
Under the EPAct, the NRC will regulate
radioactive materials produced in an
accelerator used to intentionally
produce radioactive material for use for
commercial, medical, or research
activities. This will also include any
activated radioactive material that may
still reside within the accelerator as a
result of using the accelerator to
intentionally produce radioactive
material. The determination of the
regulated material is based on whether
a radioactive material is produced in a
particle accelerator for use for
commercial, medical, or research
activities. In addition to regulating the
accelerator-produced radioactive
material, the production facility will
also be regulated through the NRC or
Agreement State licensing process to
ensure safe handling of the material and
to ensure protection of public health
and safety and the environment.
Comment: A commenter stated that
most activation/spallation in
accelerators occurs in high loss areas.
The commenter noted that beam dumps
can become very radioactive in higher
energy machines. The commenter stated
that caution should be exercised
because the efficiency of Geiger-Mueller
(GM) photon counters for photon-only
emitting radionuclides that are common
in accelerator environments is 0.17
percent as opposed to a GM photoncounting efficiency of 30 percent for
medium energy beta emitters.
NRC Response: The NRC appreciates
the commenter’s insight. The NRC
expects licensees to be knowledgeable,
based on their qualification through
training and experience, of the response
characteristics of survey and
measurement instrumentation relative
to the radioactive material being
produced or used. Licensee RSOs are
required to show evidence of such
training and experience as part of the
licensing process.
Comment: Two commenters asked if
entities other than particle accelerator
users would be regulated by the NRC.
One commenter asked if the NRC will
license accelerator producers and
distributors. Another commenter asked
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who the NRC anticipates will regulate
the safety of accelerator facilities and
their operation in both Agreement and
non-Agreement States. The commenter
noted that many States have
implemented the SSR accelerator
regulations. However, the commenter
stated that ‘‘the regulatory responsibility
for the radiation safety of the accelerator
facility, the production of the
radionuclides (licensing of accelerator
targets), and the radioactive waste
management (specifically, accelerator
targets) is unclear in Non-Agreement
States, particularly in Federal
institutions.’’
NRC Response: The NRC has no
jurisdiction over accelerators; therefore,
the NRC will not license or regulate
producers, distributors, or users of
particle accelerators. The NRC will,
however, regulate persons that handle
radioactive material from an accelerator
that is used to intentionally produce
radioactive material for use for
commercial, medical, or research
activities. Although the NRC will not
license or otherwise regulate the sales or
distribution of particle accelerators,
certain Agreement States and nonAgreement States may have regulatory
programs for registration, licensing,
and/or safe operation of accelerators.
As provided by the EPAct, the NRC or
the Agreement States have the
regulatory authority for regulating the
accelerator-produced radioactive
material, the production of acceleratorproduced radioactive material, and the
associated waste. Once the Agreement
State certifies, and the NRC determines
that the State’s program is adequate to
protect the public health and safety for
the newly added byproduct material,
the State will have regulatory authority
over the newly added byproduct
material. If an Agreement State did not
certify or the NRC determined that the
State’s program is inadequate, the NRC
will retain its regulatory authority over
the newly added byproduct material. In
a non-Agreement State, the NRC has the
regulatory authority for all AEA
materials including the newly added
byproduct material. As for Federal
facilities, the NRC has the regulatory
authority regardless if the Federal
facility is located in an Agreement State
or in a non-Agreement State.
Comment: Two commenters agreed
with the NRC’s proposed delineation of
particle accelerators into three varieties,
especially with the one category specific
to accelerators that are operated to
produce only particle beams and not
radioactive materials. The commenters
agreed that these types of accelerators,
which include linear accelerators used
in radiation therapy, should not be
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regulated. One commenter supported
the NRC’s proposal to not include
incidental radioactive material
produced by medical linear accelerators
in the regulation.
One commenter recommended that
the NRC should, in the final rule,
include a specific exemption for
commercially available linear
accelerators used only for medical
purposes to treat patients. The
commenter recommended modifying
the definition of Particle accelerator for
such exemption and provided specific
language for the modification.
NRC Response: Under the EPAct, the
NRC only has regulatory authority over
accelerator-produced radioactive
material and not over the accelerator.
Because the NRC can only exempt
material or activity under its
jurisdiction, it would not be appropriate
for the NRC to exempt accelerators in its
regulation.
Comment: A commenter asked if the
NRC would regulate neutron generators
as accelerators. The commenter noted
that these neutron generators operate by
D,T [deuterium, tritium] reactions that
use a 4-MeV (2 MeV per nucleon)
deuteron to produce up to a 12-MeV
evaporation neutron. The commenter
stated that confusion will occur if the
NRC regulates accelerators based on
their acceleration potential. As an
example, the commenter stated that a 4MeV electron will accelerate a nucleon
to 4 MeV if only one electron is
removed from the electron shell (charge
state), but if two electrons are stripped,
then the acceleration energy will be 8
MeV (4 MeV × 2).
NRC Response: The NRC will not
regulate accelerators nor the operation
of an accelerator. The NRC will only
regulate the radioactive material
produced in an accelerator intentionally
operated to produce radioactive material
for use for commercial, medical, or
research activities. Therefore, the
acceleration potential is irrelevant to the
NRC’s regulatory program. A minimum
accelerator potential of 1 MeV is
specified in the definition of Particle
accelerator to be consistent with the
SSRs.
If a neutron generated by the
accelerator is used to produce
radioactive material via neutron
activation, and the resulting radioactive
material is used for a commercial,
medical, or research activity, the
radioactive material (and any
incidentally produced radioactive
material) would be regulated as
byproduct material under Section
11e.(3) of the AEA as amended by the
EPAct.
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Comment: A commenter
recommended that the NRC add the
definition of Particle accelerator to 10
CFR Part 35 in addition to 10 CFR Parts
20 and 30.
NRC Response: The NRC Part 35
licensees are required to comply with 10
CFR Parts 20 and 30, in which the term
Particle accelerator is defined.
Therefore, it is not necessary to repeat
this definition. In addition, including
the definition of Particle accelerator in
10 CFR Part 35 may inaccurately reflect
that Part 35 includes regulations for
particle accelerators.
Accelerator-Produced Radioactive
Material
Comment: A commenter stated that
certain materials have low nuclear
binding energy. As with neutron sources
using a ‘‘(gamma, N) reaction,’’ particle
beams can produce substantial neutron
fluxes if they strike a beryllium target.
The commenter asked whether the NRC
would consider the materials activated
by these neutrons as byproduct material
or accelerator-produced material.
NRC Response: Before the EPAct, the
NRC regulated americium/beryllium
neutron generators but not radium/
beryllium neutron generators because
americium-241 was included in the
definition of Byproduct material, and
radium-226 was not. Both generators
will now be regulated by the NRC
because they both contain byproduct
material. The NRC also considers
activation products produced by
neutron emissions from byproduct
material (e.g., californium-252) to be
byproduct material. The NRC also
regulates the tritium targets in well
logging tools and other accelerators that
produced neutron beams because
tritium is a byproduct material. The
EPAct gives the NRC regulatory
authority over discrete sources of
radium-226 and accelerator produced
radioactive materials. Therefore, the
NRC now regulates, as byproduct
material, the activation products
produced by a neutron beam
accelerator, when the activation
products are used for commercial,
medical or research and development
uses.
Comment: A commenter noted that
DOE may begin production of
radionuclides and radioactive material
accelerators [Reference: See https://
www.eh.doe.gov/nepa/eis/eis0310/
eis0310.html Volume l, Chapter 2a (see
page 7 of the first enclosure)]. The
commenter asked if this would cause
any problems.
NRC Response: As an initial matter,
the EPAct did not give the NRC
jurisdiction over the production of
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accelerators. Therefore, the production
of radioactive material accelerators
would not impact the NRC’s regulatory
authority. In addition, DOE activities are
not subject to licensing unless they fall
within the purview of certain activities
specified in Section 202 of the Energy
Reorganization Act. The production of
radionuclides would not fall within the
scope of these activities. Therefore, DOE
would not need a license to produce
radionuclides. With the exception of
restrictions in 10 CFR Part 35 for
medical use licensees and in 10 CFR
Part 30 for general licensees, there are
no restrictions on who may transfer the
radioactive materials to the NRC
licensees. If DOE were to begin to
produce radioactive material, it could
transfer radionuclides to the NRC
licensees provided the NRC licensee
was specifically authorized to receive
the radioactive material. However, if
DOE pursued production of radioactive
drugs or sealed sources for direct
distribution to medical use licensees,
the NRC may have to change its
regulations because the existing
regulations only allow medical use
licensees to obtain these products from
a 10 CFR Part 32 licensee. Similar
changes may be needed to distribute
material to general licensees or to
persons exempt from licensing.
Comment: A commenter asked if the
NRC will allow the use of the most
current ANSI/IRCP/NCRP neutron flux
to dose conversion factors because the
accelerator neutron spectrum may
exceed the maximum energy of only 400
MeV listed in 10 CFR Part 20.
NRC Response: For those cases in
which greater than 400-MeV neutrons
are encountered during a licensed
activity, the licensee can request prior
approval to use a specific ANSI/ICRP/
NCRP neutron flux to dose equivalent
conversion.
Comment: Three commenters
provided their views on the NRC’s
proposal not to regulate incidental
radioactive material produced by
accelerators that are operated only to
produce particle beams.
Two commenters agreed with the
NRC’s suggested regulatory approach of
not regulating incidental radioactive
material produced by accelerators that
are operated only to produce particle
beams. One commenter indicated
agreement with this approach because
only small amounts of the incidental
radioactive materials are produced in
the particle beam-generating process,
and those typically have a short halflife. The other commenter agreed
because it believed that the incidental
radioactive materials are
indistinguishable from the particles
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produced intentionally in particle
beams and would not be an undue
burden on licensees. A third commenter
disagreed with the NRC’s proposed
regulatory approach and recommended
that all incidentally produced
radioactive material be regulated by the
NRC regardless of the use of the
accelerator. The commenter questioned
treating incidental material that was
made radioactive from an accelerator
used only to produce particle beams
differently than incidental material
made radioactive from an accelerator
used to produce both radioactive
material and particle beams. The
commenter stated that the incidental
accelerator-produced material is
radioactive material regardless of the
purpose for which the accelerator is
being used, and that in certain
situations during disposal of the
accelerator, the activated internal
components of all accelerators will enter
the waste stream. Furthermore, the
commenter noted that in its experience,
some activation products in the
accelerator components were still
radioactive a month after removal.
NRC Response: The NRC agrees that
there is essentially no radiological
difference between incidental
radioactive material made from an
accelerator used only to produce
particle beams and an accelerator used
to produce both radioactive material
and particle beams. However, the NRC’s
authority under the EPAct does not
extend to incidentally produced
radioactive material unless the
incidentally produced radioactive
material was made during the process of
making radioactive materials for
commercial, medical, or research uses.
Comment: One commenter agreed
with the NRC’s proposed approach to
regulate intentionally and incidentally
produced radioactive materials without
regulating the actual possession or
operation of the accelerator. However,
the commenter requested clarification of
the NRC regulatory oversight of the
radioactive material produced by an
accelerator and the decommissioning of
accelerator facilities in a non-Agreement
State if the NRC does not have the
authority under the EPAct to regulate
the possession and operation of the
accelerators that produce these
materials. The commenter noted that
some States do not have licensing
requirements for operating an
accelerator or for the material an
accelerator produces.
NRC Response: Although the NRC
does not regulate the operation of the
accelerator, it will regulate the
production of byproduct material and
the byproduct material once it is
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produced. The NRC will also regulate
the use of the radioactive materials
produced by the accelerator including
operational steps that expose
individuals to radioactive materials
being produced, or the radiation from
these materials and maintenance
processes that involve handling
components of the accelerator that have
become radioactive. The NRC will issue
a specific license to any person, as
defined in 10 CFR 30.4, ‘‘Definitions,’’
that produces byproduct material with
an accelerator, provided the person
meets the requirements in 10 CFR 30.33,
‘‘General requirements for issuance of a
specific license.’’ This license will
authorize the production of radioactive
materials by the accelerator and the
incidental radioactive materials
produced during the production
process.
Under the provisions of the waiver
that the NRC issued on August 31, 2005,
a person producing byproduct material
with an accelerator may continue that
activity until the waiver is terminated.
Under the waiver, the person was not
required to have a license. When the
NRC terminates the waiver under which
the person is producing byproduct
material with an accelerator, the person
is subject to all the NRC regulations
pertaining to the production,
possession, use, transfer, and disposal of
the radionuclides produced by the
accelerator, and must apply for a license
or an amendment to continue these
activities. The person is permitted to
continue producing radionuclides with
the accelerator until the NRC takes final
licensing action provided the person
applies for an NRC license (or an
amendment to an NRC license) within
the time specified in the regulations.
Therefore, the NRC’s authority applies
to the owner and operator of the
accelerator facility in a non-Agreement
State, and a license does not have to be
in place for the transition of authority
from a non-Agreement State to the NRC.
The NRC will regulate all radioactive
materials and the disposal of
components and decommissioning of
facilities made radioactive during the
use of the accelerator if the accelerator
is used to produce byproduct material
for a commercial, medical, or research
activity. If the accelerator is never used
to produce byproduct material for such
a purpose, then the NRC will not
regulate the incidental radioactive
material produced during the operation
of the accelerator.
Regulating Accelerator-Produced
Radioactive Material
Comment: One commenter noted that
the NRC has set up a regulatory
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framework that would issue one license
for production and distribution and
another for possession and use. The
commenter recommended that the NRC
continue to allow flexibility for the
States to either follow the NRC’s
licensing approach or to streamline the
licensing process by combining both
license authorizations into a single
license. Some States use the single
license approach so facilities are not
being required to pay multiple fees for
multiple licenses or so a single facility
with a single operator has only one
radiation safety program for the State to
evaluate. The commenter concluded
that the additional authorizations
require only a few extra lines of text in
a license document, so the licensee
should not have to pay separate
licensing fees.
Another commenter requested that
the NRC clarify whether a single license
might include authorizations under both
10 CFR Part 30 and 10 CFR 32.72 or
whether separate licenses are required
by the NRC.
NRC Response: Licensing procedures
are considered as a matter of adequacy
for the Agreement States, not
compatibility. As long as the license or
licenses written by an Agreement State
are adequate to assure that the licensed
program will protect public health and
safety, the licensing procedures need
not be the same as those used by the
NRC. The NRC will continue to consider
the adequacy of Agreement State
licensing procedures for all byproduct
licenses, including those for the newly
added byproduct material, as part of the
Integrated Materials Performance
Evaluation Program (IMPEP) reviews.
The NRC fees are based on the
number of the NRC-regulated activities
conducted by the licensee. The NRC
regulations list fee categories for the
various activities. A license may include
more than one fee category, and each fee
category has a separate fee to recover the
budgeted resources associated with that
regulated activity.
The NRC intends to license the
production of radionuclides by
accelerators as a separate Part 30 license
and has developed a separate licensing
guide for this activity (i.e., NUREG–
1556, Volume 21, ‘‘Program Specific
Guidance About Possession Licenses for
Production of Radioactive Materials
Using an Accelerator’’). Commercial
distribution will continue to be licensed
under 10 CFR 32.72 for radioactive
drugs and under 10 CFR 32.74 for
medical sealed sources. This licensing
process provides a clear delineation
between radionuclide production or
radioactive drug manufacture and
commercial distribution of radioactive
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drugs or medical sealed sources to
medical use licensees.
Historically, a radioactive drug
manufacturer has to obtain a Part 30
license for possession of the licensed
material. A Part 30 license also
authorizes the transfer of byproduct
material under 10 CFR 30.41 to other
licensees, but it does not authorize
distribution of radioactive drugs to
medical use licensees. Distribution of
radioactive drugs containing byproduct
material to medical use licensees for
medical use must be authorized by a
‘‘Medical Distribution’’ (MD) license
under 10 CFR 32.72 or 10 CFR 32.74.
The NRC issues MD licenses to
commercial nuclear pharmacies for
distribution of radioactive drugs to
medical use licensees with a Part 30
authorization for possession and use.
However, the NRC does not consider
commercial nuclear pharmacies to be
drug manufacturers, i.e., registered with
FDA or a State as a drug manufacturer.
Comment: A commenter stated that
medical radionuclides can initially
produce very high doses of radiation
from the exterior of a patient after
treatment. The commenter asked
whether, because of this, there are any
patient releasability issues such as those
for the release of iodine-131 therapy
patients. The commenter also asked
whether there would be any
releasability issues for activated or
spallated patients.
NRC Response: The requirements in
10 CFR 35.75, ‘‘Release of individuals
containing unsealed byproduct material
or implants containing byproduct
material,’’ apply to all medical uses and
all medical use licensees. It is the
licensee’s responsibility for a release
determination of a patient or human
research subject to determine whether
he or she: (1) cannot be released under
10 CFR 35.75; (2) can be released with
written instructions; or (3) can be
released without written instructions.
These decisions are based on whether
the total effective dose equivalent to any
other individual is likely to exceed
certain values. These values apply to the
evaluation of all patients including
activated patients.
Comment: Several commenters
supported the ‘‘grandfathering’’ of
individuals (i.e., not requiring
individuals to meet new training and
experience requirements in order to
continue their previous
responsibilities), discussed in the
Statements of Consideration for
individuals producing acceleratorproduced radionuclides and in the
proposed rule text for ANPs, medical
use AUs, and RSOs. These commenters
wanted a grandfathering provision for
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AUs responsible for the production and
use of PET radionuclides included in 10
CFR Part 30. Some of these commenters
requested that the NRC strengthen the
language to clarify the extent of the
grandfathering authorizations. Several
commenters requested that the NRC
consider using this rulemaking to
resolve other general issues related to
grandfathering of AMPs and RSOs. The
commenters agreed that individuals
already authorized to use byproduct
materials in 10 CFR Part 35 should also
be authorized to use the newly covered
accelerator-produced materials. One
commenter wanted the NRC to clarify
that the reverse was also true, i.e.,
individuals who previously only used
NARM were now qualified to use all
byproduct material.
NRC Response: Unlike 10 CFR Part 35
medical use licensees that are required
to meet specific training and experience
requirements, 10 CFR Part 30 licensees
that use accelerators to produce
byproduct material are required to meet
general performance criteria in 10 CFR
30.33(a)(3). The training and experience
of individuals involved in the licensing
activities to produce the newly added
byproduct material are reviewed during
the licensing process to ensure that they
are qualified to perform those activities.
Because the NRC does not have specific
requirements for these individuals,
there is no need to provide a
‘‘grandfather provision’’ for them.
Applicants with accelerators used to
produce byproduct material will be
required to describe the radiation safety
training and work experience of those
individuals using materials that they are
seeking authorization to use. It is
expected that these individuals that
used the newly added byproduct
materials will be able to document that
their radiation safety training and work
experience from using these materials
are sufficient to meet the general
performance criteria and that they be
recognized as authorized individuals.
Section 35.57 was amended in the
proposed rule to provide that certain
authorized individuals who used only
the newly defined byproduct material
may be grandfathered (i.e., need not
comply with the relevant training
requirements in Part 35) for performing
the same uses. The NRC does not
believe that the language in the
provisions should be revised.
The NRC has determined that revising
the regulations to address general issues
related to the grandfathering of AMPs
and RSOs would be outside of the scope
of this rulemaking. These issues will be
addressed separately in response to a
petition for rulemaking (PRM–35–20)
filed by the American Association of
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Physicists in Medicine on September
10, 2006.
Comment: There were several
comments on the NRC’s proposal for the
noncommercial transfer of PET
radionuclides, drugs, and biologics to
other medical facilities in its consortium
by a medical use facility that uses its
own cyclotron to produce PET
radionuclides. One commenter stated
that it agreed that facilities authorized
by a State to produce PET radionuclides
for noncommercial distribution should
be allowed to do so without a medical
distribution license.
Generally, the commenters agreed that
distribution licenses should not be
required for distribution of
radionuclides from PET facilities to
medical facilities under contract to
them, but thought it was unclear which
facilities would be included in the
definition of ‘‘medical facilities in its
consortium.’’ As an example, one
commenter was not sure whether a
cyclotron producing PET radionuclides,
that is located at a facility owned by
Company A but operated under a
separate license by a different Company
B, would need a commercial
distribution license. The commenter
also asked for clarification on whether
Company B would need a medical
distribution license if it also supplied
PET radionuclides to other facilities in
its geographical area under contract.
Another commenter noted that only
noncommercial distribution to a
medical consortium was addressed, and
not the noncommercial distribution
within the consortium in support of
research and development. The
commenter asked that the NRC expand
its proposed regulatory framework to
include authorization for licensees
producing PET radionuclides, drugs,
and biologics to allow noncommercial
transfer to any licensee approved for
research and development uses of these
materials. This commenter also asked
the NRC to provide specific guidance on
what is considered commercial transfer
and noncommercial transfer in advance
of requiring license application and
amendment submissions for the
production of accelerator-produced
radionuclides. The commenter’s interest
was based on its being funded to do
research involving nonstandard
radionuclides and to make the results
available to the research community and
others. The commenter asserted that the
NRC, in the past, approved similar
efforts by universities to produce and
supply nonstandard radionuclides not
otherwise available.
NRC Response: The NRC recognizes
that the PET radionuclide production
facility may be located in a medical
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facility, educational institution, or
Federal facility that has formed a
consortium to produce PET radioactive
drugs for its members. The NRC is
adding a definition of Consortium in 10
CFR 30.4 to clarify the purpose and
members of a consortium. In general,
the members of the consortium jointly
own or share in the operation and
maintenance cost of the PET
radionuclide production facility, and
the production facility or another
member of the consortium produces
PET radioactive drugs (including
radioactive biologics) only for its
consortium member’s medical uses. The
NRC’s authorization for the
noncommercial distribution of PET
radioactive drugs within a medical use
consortium is not dependent on an
authorization by a State to produce PET
radionuclides for noncommercial
distribution. A person or a licensee that
has or receives PET radionuclides from
a PET radionuclide production facility
may request authorization for
noncommercial distribution of PET
radioactive drugs within its consortium.
The NRC will review the request along
with the description of the consortium
during the licensing review process to
ensure eligibility for noncommercial
distribution and issuance of the
authorization.
For clarification purposes, the NRC,
in the final rule, has moved the
noncommercial distribution provisions
for PET radioactive drugs to 10 CFR Part
30. For noncommercial distribution of
PET radioactive drugs, the NRC is
applying the same requirements as those
included in 10 CFR 32.72 for
commercial distribution of these drugs.
Regarding different licensing
situations, a university that has both a
10 CFR Part 30 license and a 10 CFR
Part 35 license could transfer PET
radioactive drugs to its medical facility
without a commercial distribution
license. If the PET radionuclide
production facility produces PET
radioactive drugs and is located at a
medical facility, but owned, operated,
and licensed by another entity under a
10 CFR Part 30 license, then the PET
radionuclide production facility
licensee would need a 10 CFR 32.72
license to distribute PET radioactive
drugs to the medical facility for medical
use. If a PET radionuclide production
facility produces PET radioactive drugs
and wants to distribute excess PET
radioactive drugs to other licensees
outside its consortium, a 10 CFR 32.72
commercial medical distribution license
would be required. In general, a PET
radionuclide production facility may
transfer excess PET radionuclides to
other licensees that are authorized to
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receive such PET radionuclide transfer
under 10 CFR 30.41. However, if a PET
radionuclide production facility
produces radionuclides for commercial
distribution, then a distribution
authorization would be required as well.
An applicant’s intent regarding
noncommercial distribution, transfer, or
commercial distribution will be
evaluated as part of the licensing review
process to ensure that the proper license
or authorization is issued.
A PET radionuclide production
facility is required to obtain a 10 CFR
Part 30 license for production,
possession, and use of byproduct
material. Under 10 CFR 30.41, a licensee
is allowed to transfer byproduct
material (including PET radionuclide) to
any person authorized to receive such
byproduct material. However, as
required in 10 CFR Part 35 regulations,
medical use licensees can only obtain
PET radioactive drugs for medical use
from persons meeting specific
requirements for commercial
distribution of radioactive drugs in 10
CFR 32.72. There are no such
limitations for nonmedical use.
Therefore, a specific provision would be
needed to allow medical use licensees
to obtain PET radioactive drugs through
noncommercial distribution or from
persons not covered under 10 CFR
32.72. A new provision is added in 10
CFR 30.32(j) to allow a PET
radionuclide production facility to
noncommercially distribute PET
radioactive drugs to members of its
consortium. Such a provision is not
needed for a PET radionuclide
production facility to transfer PET
radionuclides because transfer is
already allowed under 10 CFR 30.41.
Comment: A commenter requested
that the NRC clarify whether facilities
that prepare PET drugs for use in
research under Investigational New
Drug exemptions (INDs) filed with the
FDA, or used in research conducted
under approvals granted by Radioactive
Drug Research Committees (RDRCs)
operating as branches of the FDA under
21 CFR 361.1, would be considered
‘‘registered’’ by the FDA.
NRC Response: As specified in 10
CFR 30.32(j) and 10 CFR 32.72, being
registered with the FDA is only one of
the five ways that an applicant can
demonstrate that it is qualified to
produce PET radioactive drugs for
noncommercial or commercial
distribution to medical use licensees.
Because the NRC neither interprets nor
enforces FDA requirements, it is the
applicant’s responsibility to provide
documentation of the proper FDA
registration. If there is a question as to
whether a specific facility that prepares
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PET drugs under INDs or RDRCs is
‘‘registered’’ by the FDA, the applicant
should contact FDA for a determination.
It is important to note that a 10 CFR
Part 35 medical use licensee may obtain
unsealed byproduct material for uptake,
dilution, excretion, imaging, or
localization from an NRC or Agreement
State licensee that prepared the material
for research in accordance with an
RDRC-approved protocol or an IND
protocol accepted by FDA as permitted
in current provisions of 10 CFR 35.100
and 35.200. This provision is separate
from the provision that the byproduct
material must be obtained from a
commercial manufacturer or preparer
licensed under 10 CFR 32.72 or by
noncommercial distribution from a
member of its consortium under 10 CFR
30.32(j).
Comment: A commenter expressed
concern that language in the proposed
rule could place undue burden on
health care providers who use
cyclotrons for the production of
radiotracers by requiring them to meet
FDA’s Good Manufacturing Practices
(GMPs) standard that is applied to
commercial entities producing products
for sale to the public. The commenter
stated that it was inappropriate to apply
GMPs to noncommercial production of
radiotracers. The commenter stated that:
(1) the EPAct does not give the NRC the
authority to require health care
providers to follow GMPs in their
clinical practices; (2) enforcing drug
production quality standards falls under
FDA’s jurisdiction, and the NRC should
not enforce FDA requirements; (3) such
a requirement would have a detrimental
effect on exploration of new treatment
pathways; and (4) health care providers
have not been required to apply
commercial GMP standards previously.
The commenter asserted that regulation
of cyclotron byproduct material should
not include processes involving drug
production and patient care. The
commenter further indicated that the
production of radiopharmaceuticals
using a cyclotron is no different than
using a molybdenum or rubidium
generator.
NRC Response: The NRC disagrees
that its regulations would require health
care providers to follow GMPs in their
clinical practice. The NRC requires
licensees that distribute radioactive
drugs (including radioactive biologics)
to medical use licensees to be qualified
to produce radioactive drugs for medical
use. To demonstrate this qualification,
the NRC requires in 10 CFR 30.32(j) and
10 CFR 32.72 that the applicant or
licensee submit evidence that it meets at
least one of the following criteria: (1) be
registered with the FDA, (2) be
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registered or licensed with a State
agency as a drug manufacturer, (3) be
licensed as a pharmacy by a State Board
of Pharmacy, (4) be operating as a
nuclear pharmacy within a Federal
medical institution, or (5) be a PET drug
production facility registered with a
State agency. The FDA’s rule on Good
Manufacturing Practice for PET drugs
establishes criteria for the production
and process/quality controls of PET
drugs in PET centers registered with the
FDA. While the NRC recognizes the
FDA registration in the NRC’s
regulations, registration with the FDA is
only one of five different criteria that
licensees may meet to demonstrate they
are qualified to distribute radioactive
drugs to medical use licensees.
The NRC agrees that the production of
radiopharmaceuticals using
radionuclides from a cyclotron is no
different than using molybdenum or
rubidium generators. The producer of
the molybdenum generator is registered
with the FDA as a drug manufacturer
and is licensed by the NRC under both
10 CFR Part 30 and 10 CFR 32.72. The
use of the generator to prepare other
radioactive drugs is required in 10 CFR
32.72 to be done by a commercial
nuclear pharmacy or in 10 CFR 35.200
to be done at the medical use facility by
an AU meeting specific training and
experience criteria or an ANP. The NRC
has applied the same flexibility in
recognizing that certain drugs are
produced by facilities registered with
the FDA or States and that other drugs
are prepared by or under the
supervision of AUs or ANPs.
Comment: A commenter
recommended that the NRC should
include an exemption for changes that
involve the addition or relocation of
either a PET radionuclide production
area or a radionuclide delivery line from
the PET production area from license
amendment or the NRC notification
requirements for broad scope Type A
licenses under 10 CFR 35.15. The
commenter stated that this allowance is
consistent with the level of authority the
NRC has historically granted under this
list of exemptions.
NRC Response: The NRC agrees with
the commenter and revised proposed 10
CFR 35.15(f) to make it clear that a Type
A specific license of broad scope is
exempt from the notification provisions
in 10 CFR 35.14(b)(5). In this final rule,
the NRC’s licensing practice for Type A
specific licenses of broad scope is to
have the licensee describe significant
facilities, such as the PET radionuclide
production area or radionuclide
delivery tube, and provide the NRC its
criteria for reviewing and approving the
addition or relocation of these facilities.
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The broad scope licensee with a PET
radionuclide production facility will
need to submit an application to license
the production facility and, if
applicable, increase its radionuclide
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Comments on Waste and
Decommissioning
Decommissioning and Decontamination
Comment: A commenter noted that
under the proposed rule, activities
under the new definition of Byproduct
material would need to be licensed
within 6 to 12 months after the final
rule takes effect. The commenter
requested clarification as to whether
this new requirement would result in
MML licensees having to permit/license
all sites containing radium or radium
contamination due to radium paint
operations or gauge maintenance. The
commenter noted that current U.S. Air
Force (USAF) policy is to forgo
permitting sites, until intrusive
characterization of the site has been
performed. The commenter requested
that the NRC state whether this rule
would affect the current USAF policy.
NRC Response: As previously
discussed, since the publication of the
proposed rule, and after considering the
comments on the new definition of
Byproduct material, the Commission
has taken a closer look at the scope of
the Commission’s jurisdiction over the
newly added byproduct material
including discrete sources of radium226. The EPAct covers material that is
‘‘produced, extracted, or converted after
extraction, before, on, or after August 8,
2005, for use for commercial, medical,
or research activity.’’ Notwithstanding
that a discrete source of radium-226
may have originated from a commercial
supplier, the Commission has
determined that discrete sources of
radium-226 still under the control of the
military do not constitute ‘‘commercial
use’’ under the EPAct and are, therefore,
outside the Commission’s jurisdiction.
Defining ‘‘commercial use’’ to include
all material supplied to the military
from a commercial supplier would
result in virtually all military use of this
material to be ‘‘commercial use.’’ This
would vitiate any distinction that the
EPAct intended to make for military
use, as opposed to commercial use, by
excluding military use from its
coverage.
However, this exclusion from the
coverage of the EPAct only applies to a
certain type of military use, i.e., NARM
used for ‘‘military operations.’’ The term
‘‘military operations’’ covers what is
traditionally understood as the
military’s primary mission for national
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defense, including warfare, combat, and
battlefield missions, and, of course,
training for battlefield missions. NARM
used, or available for use, for these
purposes would be excluded from the
coverage of the EPAct and from the
coverage of this rule. If the material is
intended for use in military operations,
it is excluded from the coverage of this
rule notwithstanding the fact that it was
originally produced by a commercial
supplier. In addition, ‘‘military
operational’’ material includes material
still under the control of the military,
i.e., in storage, or material that may be
subject to decontamination and
disposal. Other use of NARM by the
military would be covered by this rule.
The NRC no longer authorizes specific
byproduct material use licensees to bury
licensed materials at their facility.
Although the MML licensee cannot
issue permits for new burial sites,
licensees are required under 10 CFR
30.35 to maintain documentation of
information that is necessary for
decommissioning.
Comment: A commenter stated that
Actinide/radium-226 surface
contamination levels less than 1000–
1500 dpm/100cm2 are typically not
detectable at 1–2 sigma counting
statistics. The commenter stated that
radium-226 captured in clothing/porous
materials could have much higher
counting errors and asked if the NRC
has accepted the technological shortfall
for detection of radium-226 and
proposed an alternative.
NRC Response: Licensees are required
to ‘‘demonstrate’’ to the NRC that post
remediation contamination levels meet
the release criteria for their sites.
‘‘Demonstration’’ includes specifically
addressing instrumentation used for
detecting and measuring the
contamination. If instruments can’t
detect the contamination, other means
to identify contamination levels must be
addressed in the licensee’s
Decommissioning Plan. The NRC
guidance documents NUREG–1757,
‘‘Consolidated NMSS Decommissioning
Guidance,’’ and NUREG–1575, ‘‘MultiAgency Radiological Survey and Site
Investigation Manual,’’ both address
instrumentation.
Comment: Two commenters requested
that the NRC modify its regulations in
10 CFR 30.36 to allow a longer time
frame of at least 10 years for completion
of decommissioning for accelerator
production facilities. One commenter
stated that decommissioning of a
particle accelerator and its associated
facility can range from a return of a selfshielded cyclotron unit to the
manufacturer to a major cleanup of an
older accelerator unit and its facility.
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The commenter stated that cost for
decommissioning will be significantly
impacted by the time frame allowed to
complete this action. Under the current
10 CFR 30.36 regulations, completion of
decommissioning for an accelerator
production facility could be required in
as little as 48 months following
cessation of operation. On the other
hand, under 10 CFR 50.82,
decommissioning of a power reactor is
required to be completed within 60
years following cessation of operation.
Hence, the commenter requested that
the NRC modify its regulations in 10
CFR 30.36 to allow a longer time frame
of at least 10 years for completion of
decommissioning for accelerator
production facilities.
NRC Response: The NRC’s regulations
in 10 CFR 30.36 require that the site or
any separate building or outdoor area
that has not been used for 2 years must
be promptly remediated if the
remediation activities are allowed by
the existing license. If remediation
activities are not allowed under an
existing license, the licensee must
develop a decommissioning plan and
submit a request for a license
amendment within 1 year. The
decommissioning process must be
completed within 2 years, unless an
alternative schedule for completion of
decommissioning is approved by the
Commission.
The level of effort for
decommissioning a radioactive material
production facility depends on many
factors such as the design, age, operating
condition, and usage of the accelerator
and the type of facility where the
accelerator is located. Decommissioning
activity can range from simply a return
of a self-shielded cyclotron unit to the
original manufacturer to a more
complicated cleanup of an older
accelerator unit and its facility. Because
alternative schedules for
decommissioning are allowed within
the existing regulations, there is no need
to modify 10 CFR 30.36.
Comment: In response to the NRC’s
request for comments on the
decommissioning of accelerator
facilities and accelerator components,
one commenter requested clarification
in Part 35 that the term
decommissioning does not apply to the
removal or replacement of a linear
accelerator used for medical treatment.
Another commenter recommended that
the NRC include a specific exemption
that states that ‘‘decommissioning’’ does
not include: (a) replacement of one
medical accelerator for another; (b)
upgrading of a medical accelerator; (c)
replacement of one cyclotron for
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another within the same facility; or (d)
upgrading of an existing cyclotron.
NRC Response: The EPAct gave the
NRC the authority to regulate any
material that has been made radioactive
by use of a particle accelerator and is
produced, extracted, or converted for
use for a commercial, medical, or
research activity. Under the EPAct, the
NRC only has authority over the
radioactive material and not over
accelerators including linear
accelerators used for medical treatment.
Because linear accelerators used for
medical treatment do not produce
radioactive material that is used for
commercial, medical, or research
activities, the NRC will not be regulating
the activated material that may be
produced during medical treatment.
Because medical linear accelerators
and activated material associated with
these types of accelerators are not
regulated by the NRC, no specific
exemption is needed for non-NRC
regulated material, including
replacement or upgrade of a medical
linear accelerator. Decommissioning
regulations are not applicable to
nonregulated material such as a medical
linear accelerator.
Replacement or upgrade of a
cyclotron is not typically considered a
decommissioning activity; therefore, an
exemption for such activity would not
be required. However, if the cyclotron is
used to produce radioactive material for
commercial, medical, or research
activities, and accelerator components
become activated incidental to the
production of radioactive material, both
the radioactive material and the
components would be regulated as
licensed material. The activated
components would require
decommissioning upon cessation of
licensed activity. If licensed activity
continues, the replacement or upgrade
of a cyclotron or its activated
components would be addressed in the
license. The removed cyclotron and its
activated components are considered
licensed material and would be treated
as radioactive waste.
Comment: A commenter stated that
the NRC should address volumetric
contamination of materials by
activation/spallation and recommended
that the NRC develop release criteria for
the various accelerator-produced
radionuclides.
NRC Response: For decommissioned
sites, the release criterion for
unrestricted use is 25 mrem per year
(0.25 mSv per year) as listed under 10
CFR Part 20, Subpart E, and 10 CFR
30.36, including all radionuclides and
all pathways. If an accelerator is used to
produce regulated material, and
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accelerator components become
activated incidental to the production of
the regulated material, the activated
components would be licensed and
subject to 10 CFR Part 20, Subpart E,
and 10 CFR 30.36 requirements.
Even though the NRC has, in the past,
considered exposure criteria for release
of waste and contaminated scrap, no
rule has been adopted regarding
exposure criteria. Currently, the NRC
does not plan to develop release criteria
for various accelerator-produced
radionuclides. Activated waste
produced in an accelerator will be
treated like any other radioactive waste.
Guidance regarding decommissioning
and waste disposal can be found in
NUREG–1757, ‘‘Consolidated NMSS
Decommissioning Guidance.’’
Comment: Two commenters asked
whether the NRC will be proposing
acceptable de minimus values, release
criteria, or remediation criterion for
surficial and volumetric radium
contamination on building structures
and soil that can be generally applied to
decommissioning operations. One
commenter asked if the NRC accepts 5
pCi/gram of soil as volumetric de
minimus values that EPA or States have
approved for radium-226 contamination
release value at certain remediation
sites.
NRC Response: Currently, there are no
de minimus values or release criteria for
decommissioning sites. As provided in
10 CFR 20.1402, the release criterion for
unrestricted use is 25 mrem per year
(0.25 mSv per year) for all sources and
all pathways. The NRC will only accept
a release value of 5 pCi/gram (0.185 Bq)
for radium-226 contamination in soil if
the site will also meet the NRC’s release
criterion of 25 mrem per year (0.25 mSv
per year).
The NRC does have screening values
for building surfaces and surface soil
concentrations. Screening values are
based on the 25-mrem per year (0.25mSv per year) release criterion and can
be used to simplify decommissioning
efforts where low levels of
contamination exist. Screening values
are listed in tables included in
Appendix B of NUREG–1757,
‘‘Consolidated Decommissioning
Guidance-Decommissioning Process for
Materials Licensees,’’ for each
radionuclide for building surfaces and
soil surfaces. These screening values are
not de minimus values. Unlike de
minimus values, the screening values
were developed under certain site
conditions (e.g., type of facility, depth of
soil contamination, type of surface
contamination); therefore, screening
values may only be used if a site meets
these specific conditions. For a site with
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mixed radionuclides, the ‘‘unity rule’’
(or sum of the fractions rule) applies,
and screening values would change
depending on the site’s isotopic
mixture. There are only a few sites that
can use the screening method for
decommissioning because sites are very
different from each other, and most sites
do not meet the conditions for using
screening values.
Comment: One commenter provided
some insight on a radium-226 dosimeter
calibration source breach at a facility in
the 1950s and indicated that current
survey equipment has difficulty
detecting actinide contamination under
1000–1500 dpm/100cm2. The
commenter stated that if the radium-226
breach occurred before the 1970s, it is
likely that the contamination still exists.
Because the NRC has taken authority
over all past, present, and future
radium-226 sources, the commenter
asked whether the NRC’s authority
includes authority over the
contamination resulting from a radium226 source breach.
NRC Response: Under the EPAct, the
NRC has the regulatory authority over
all past, present, and future discrete
sources of radium-226 and any
contamination associated with the
discrete sources. However, the NRC
does not intend to require nonlicensed
owners of properties that may be
contaminated with radium-226 to obtain
licenses. If contamination is discovered
at a nonlicensed person’s facility, such
as contaminated buildings or grounds,
the NRC will work with the facility
owner to perform decommissioning of
the site. If the site presents a significant
threat to the public health and safety,
the NRC may order the owner to obtain
a license and to perform
decommissioning of the site. In
addition, the NRC may seek assistance
from EPA to consider listing the site on
EPA’s National Priority List and clean
up the site under the CERCLA or
Superfund Program. Any arrangement
between the NRC and EPA regarding
regulatory authority over
decommissioning would be agreed upon
on a site-specific basis.
Comment: One commenter indicated
that a number of gaslight and luminous
production sites are abandoned, and
some are Superfund sites. The
commenter asked whether the NRC has
the financial ability to clean up these
sites.
NRC Response: The NRC does not
perform or provide funds for cleanup of
contaminated sites because the NRC
does not have authority in spending
Federal funds for conducting cleanup
activities. The NRC relies solely on
licensees or property owners to perform
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the necessary cleanup work. Unlike the
NRC, EPA has the funds under the
CERCLA or Superfund Program to
evaluate the extent of the contamination
and to conduct the cleanup efforts. EPA
also has the statutory authority to
recover the cost associated with the
cleanup activities from the potentially
responsible parties.
Comment: One commenter asked
whether there will be any requirements
for the NRC’s review of radiumcontaminated sites that have been
remediated before the effective date of
this rule.
NRC Response: The NRC does not
intend to revisit sites that have already
been remediated. If sites are discovered
to be contaminated with sufficient
quantities of radionuclides to
potentially warrant additional
decommissioning, the NRC will contact
and work with the owner of the
property to re-commence the
decommissioning process.
Comment: One commenter asked how
the NRC will review decommissioning
plans and final status surveys for sites
where AEA Section 91(b) materials may
be the predominant contaminant with
respect to AEA materials regulated by
the NRC and whether there is a limit of
the NRC’s interests in these sites.
NRC Response: Decommissioning of a
licensed facility falls under the
requirements of 10 CFR part 20, Subpart
E, and 10 CFR 30.36. The NRC will
review decommissioning plans and the
final status survey to ensure that the
licensed facility meets the release
criterion of 25 mrem per year (0.25 mSv
per year) for unrestricted use for all
radionuclides and all pathways. The
NRC will use this approach for all sites
that are contaminated by any licensed
material including sites where
unlicensed radionuclides such as
Section 91(b) material contribute to the
dose estimates in the all-pathway
analysis. The NRC has no regulatory
authority over a site that is
contaminated with only Section 91(b)
material and not licensed material.
Comment: One commenter raised a
question on whether the NRC will
subsume the predominant regulatory
role for remediation of sites that predate
the USAF MML and were established
under AEC purview.
NRC Response: The NRC has the
predominate regulatory role in the
decommissioning of sites under the
MML. Sites containing licensed material
must be decommissioned under 10 CFR
part 20, subpart E, and 10 CFR 30.36
requirements regardless of whether such
sites predate the MML or were under
the purview of AEC.
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Comment: Two commenters
expressed their concern regarding the
statement in the Statements of
Consideration for the proposed rule that
only radionuclides with a half-life of
more than 120 days, that are present in
sufficient quantities to cause a public
health and safety concern, need to be
addressed for the purpose of
establishing adequate financial
assurances for decommissioning leading
to license termination. One commenter
requested that the final rule include
specifications of which radionuclides
and the threshold amounts would be
sufficient to lead to license termination.
Another commenter recommended that
the term ‘‘sufficient quantities’’ be
defined in terms of 10 CFR part 20 dose
limits.
NRC Response: In the proposed rule,
the term ‘‘sufficient quantities’’ is
referring to quantities of radionuclides
with a half-life of more than 120 days
for the purpose of establishing adequate
financial assurance for
decommissioning leading to license
termination. The specific quantities are
established in 10 CFR 30.35. For
unsealed byproduct material in
quantities exceeding 105 times, or for
sealed sources or plated foils in
quantities exceeding 1012 times the
applicable quantities in Appendix B to
10 CFR part 30, the licensee is required
to submit a decommissioning funding
plan. For unsealed byproduct material
in quantities exceeding 103 but less than
or equal to 105 times, or for sealed
sources or plated foils in quantities
exceeding 1010 but less than or equal to
1012 times the applicable quantities in
Appendix B to 10 CFR part 30, the
licensee is required to submit either a
decommissioning funding plan or a
certification that financial assurance for
decommissioning had been provided in
the amount prescribed in 10 CFR
30.35(d). Revising the quantities
requiring financial assurance is beyond
the scope of this rule.
For license termination, the release
criterion for unrestricted use is 25 mrem
per year (0.25 mSv per year) as listed
under 10 CFR part 20, subpart E, and 10
CFR 30.36. All radionuclides, regardless
of the quantities present, must be
considered in the all-pathway analysis
in demonstrating compliance with the
release criteria.
Waste Disposal
Comment: One commenter asked
whether radioactive waste site licenses
will need to be changed to reflect the
newly regulated radioactive materials
and whether it is the waste site
licensee’s responsibility to incur the
cost of changing the license.
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NRC Response: Waste site licenses
may or may not need to be amended to
include newly regulated radionuclides.
The need for amending a license will
depend on how the existing license
identifies the licensed material (listed as
a group of radionuclides or listed by
each individual radionuclide). The cost
for a license amendment would be the
responsibility of the licensee.
Comment: One commenter asked
whether there are disposal sites that can
inexpensively dispose of consumer
products and luminous light sources. If
not, the commenter stated that
abandonment may become the only
method of disposal.
NRC Response: There are radioactive
waste disposal sites, licensed by the
Agreement States, and hazardous or
solid waste disposal sites, permitted by
the EPA or its authorized States,
available for disposal of the newly
added byproduct material. Disposal
charges are set by each of the disposal
facilities based on the type of material
and the contamination level. It is the
licensee’s responsibility to locate a
disposal facility that could accept the
waste and to negotiate disposal cost.
There are also certain manufacturers
that accept returned or spent sources
from their customers. In the past, DOE
has, in certain unique situations,
cooperated with the NRC and the
CRCPD in collecting certain orphaned
sources for storage and/or disposal at
DOE facilities due to lack of disposal
options. However, these programs are
typically limited in scope and designed
for urgent needs.
In general, consumer products are
manufactured by a specific license and
distributed to consumers as an exempt
product. These consumer products
contain very small amounts of
radioactive material in order to meet the
stringent criteria for an exempt product.
There are no disposal requirements for
exempted products based on the amount
of the radioactive material present and
the negligible impact to public health
and safety. Hence, exempt products are
allowed to be disposed of in municipal
landfills.
Comment: One commenter was
concerned regarding the disposal of
exempted smoke detectors containing
radium-226.
NRC Response: This issue is
discussed earlier in this document
under ‘‘Exemption of Certain Radium226 Items.’’
Comment: One commenter asked if
the NRC will accept decay-in-storage as
a method of disposal for acceleratorproduced medical radionuclides. The
commenter also asked whether decayin-storage could also be applied to
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accelerator components that are
volumetrically activated or spallated,
and whether the time period under
which the accelerator is turned off or in
a low energy mode could be counted as
the decay-in-storage time.
NRC Response: Decay-in-storage has
been, and will continue to be, an
accepted means for disposal of
radionuclides with short half lives,
including medical radionuclides.
Activated components either within or
removed from the accelerator will be
treated as any other radioactive source.
Therefore, activated components
contaminated with short-lived
radionuclides with half lives less than
120 days will be allowed to use decayin-storage as a disposal method.
Activated components contaminated
with radionuclides with half lives
greater than 120 days would either have
to be disposed of as radioactive waste or
have to be addressed later during
decommissioning as part of the license
termination process.
Comment: For decay-in-storage or
disposal, a commenter asked whether
accelerator-produced medical
radionuclide users will be able to ignore
short-lived radionuclides. As an
example, the commenter noted that
many ‘‘hundreds of thousands’’ of
fluorine-18 disintegrations on the skin
surface will produce only microrem
doses to the skin or deep tissue.
NRC Response: All acceleratorproduced radionuclides, including
short-lived radionuclides, will be
regulated. Licensees may not ignore
short-lived radionuclides in meeting the
NRC’s regulatory requirements.
However, licensees may use decay-instorage as a means for disposal in
accordance with the NRC criteria.
Comment: One commenter stated that
decommissioning of accelerator
facilities can result in the removal of
building materials and accelerator parts
that are activated. Recycling and
disposal of material that meet the NRC’s
materials contamination limits may still
trigger detectors at landfill and scrap
facility checkpoints. The commenter
recommended that the NRC consider
exposure criteria for release of these
materials.
NRC Response: In the past, the NRC
has considered development of
exposure criteria for release of waste
and scrap through the rulemaking
process. Due to public comments on the
rulemaking effort, the NRC decided to
defer the rulemaking to a later date, and
no rulemaking on this issue was
promulgated.
Sites released for unrestricted use
based on the 25-mrem per year (0.25mSv per year) criterion specified in 10
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CFR Part 20, Subpart E, have no
restrictions placed on the use of the site
or disposition of material located on the
site or disposal of waste or materials
from the site. If a detector is triggered at
a landfill, the operator of the landfill
should notify the State or another
regulatory authority. Typically, the NRC
would be notified of the event, but, in
most cases, no action would be taken
because the material met the NRC’s
release criteria.
If the site is discovered to be
recontaminated to levels above the
release criteria, the NRC may contact the
site owner or former licensee to begin
the decommissioning process.
Comment: A commenter concurred
with the NRC’s proposed approach
towards waste disposal to change Part
20 to redefine the definition of Waste to
allow disposal of the newly added
byproduct material in the NRCregulated disposal facilities or in a
disposal facility permitted under
Federal or State solid or hazardous
waste laws. However, the commenter
questioned whether such an approach
may be arbitrary or capricious, since
other similar low-level wastes may still
fall under the Compact jurisdiction (i.e.,
Section 11e.(1) byproduct material). The
commenter suggested that this situation
could be avoided by managing the
radium as radioactive material instead
of byproduct material.
NRC Response: The commenter
appears to be concerned that it may be
arbitrary to treat some byproduct
materials as low-level waste and some
as non-low-level waste and suggested to
manage the newly added byproduct
material as radioactive material instead
of as byproduct material. However, the
EPAct defines the newly added
byproduct material, i.e., discrete sources
of radium-226 and accelerator-produced
radioactive material, as a byproduct
material. Defining the newly added
byproduct material as radioactive
material would be inconsistent with the
statutory requirement. In addition, the
NRC only has authority to regulate AEA
material and not all radioactive
material. Because the discrete source of
radium-226 is a byproduct material, and
byproduct material is only a subset of
radioactive material, treating radium226 as radioactive material instead of
byproduct material would have the
appearance that the NRC has regulatory
authority over all radioactive material.
The EPAct provides an additional
disposal approach for the newly added
byproduct material to include disposal
at a disposal facility permitted under
Federal or State solid or hazardous
waste laws. This approach is consistent
with many existing State programs that
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regulate naturally occurring and
accelerator-produced radioactive
material as radioactive material and not
as byproduct material. In addition, this
approach would enhance proper and
timely disposal of the newly added
byproduct material. Similar to low-level
waste disposal facilities, disposal
facilities permitted under Federal or
State solid or hazardous waste laws also
need to consider all radionuclides as
source terms in conducting the
performance assessment and in
formulating the waste acceptance
criteria to ensure protection to public
health and safety and the environment.
Comment: One commenter concurred
with providing multiple options for
disposal of the newly added byproduct
material but was not sure if this is
consistent with some compacts’
definitions. The EPAct and the NRC
state that the new byproduct material is
not low-level radioactive waste (LLW)
such that it is not to be impacted by the
compact process of the Low-Level
Radioactive Waste Policy Amendments
Act (LLRWPAA). The commenter stated
that this seems ‘‘backward,’’ as the
Rocky Mountain Compact specifically
captures radium in its definitions and
traditionally has treated discrete radium
as LLW.
NRC Response: Although the newly
added byproduct material would not be
considered LLW with respect to the
compact process of the LLRWPAA, the
newly added byproduct material may
still be disposed of at an LLW disposal
site. The EPAct provides additional
options for disposal of the newly added
byproduct material and does not
prohibit the existing option of LLW
disposal.
Comment: Because the newly added
byproduct material would be allowed to
be disposed of in either the NRCregulated disposal facilities or in a
disposal facility permitted under
Federal or State solid or hazardous
waste laws, a commenter asked if waste
disposed of in a CERCLA site would
incur ‘‘potential responsible parties’’
(PRP) status should the solid or
hazardous waste facility fail.
NRC Response: Currently, disposal
sites already dispose of radium-226 and
other accelerator-produced and
naturally occurring radioactive material
as daughter products or as radioactive
waste. The EPAct allows these disposal
sites to continue with their current
practice. Therefore, nothing would
change for these disposal sites under the
new regulations. The EPA has
jurisdiction over any site that becomes
a CERCLA or a Superfund site, and the
EPA has the statutory authority to
recover cleanup cost from PRPs. Under
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the Superfund, any party who is
associated with the site, used the site,
disposed of material at the site, or
contributed to the contamination at the
site could all be considered as a PRP
and liable for the cleanup.
Comment: A commenter indicated
that any disposals in solid or hazardous
waste facilities must take into account
potential release of radium from the
discrete source and therefore radon. The
commenter suggested that discrete
sources can be further encapsulated
before burial as a treatment to reduce
the potential for radium leakage and
mitigate the potential for radon.
NRC Response: Disposal facilities
need to consider all radionuclides and
their daughter products when
conducting the performance assessment
and when developing the waste
acceptance criteria regarding the type of
radioactive waste that may be safely
disposed of at the site. Depending on
the performance assessment and the
waste acceptance criteria, certain
disposal facilities may require
additional treatment of certain wastes to
control the daughter products or
migration of certain radionuclides.
However, the NRC sees no reason to
require further encapsulation of discrete
sources before disposal because waste
forms would depend on site-specific
waste acceptance criteria for each
disposal site.
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Financial Assurance
Comment: Two commenters strongly
support an exemption for facilities with
18-MeV or less cyclotrons from the
requirements of 10 CFR 30.35 for
financial assurance for
decommissioning because they do not
believe these cyclotrons are capable of
producing activation products in the
quantity sufficient to trigger the
financial assurance requirements. One
commenter stated that this approach
should be the standard in all nonAgreement States. In addition, these
commenters stated that many
burdensome expenditures are associated
with calculating and securing financial
assurance for decommissioning,
including expensive concrete bunker
boring and analysis. These costs would
inevitably put some existing medical
and scientific accelerator facilities out of
business and would also deter
prospective hospitals and educational
institutions from obtaining onsite
cyclotrons, potentially impacting
patient access to services. In support of
an exemption, one commenter stated
that it could provide data to the NRC on
incidental activation resulting from a
16.5-MeV cyclotron running at
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maximum beam current at maximum
duty cycle.
NRC Response: Although the
commenters do not believe cyclotrons
operating at 18-MeV or less are capable
of producing activation products in the
quantity sufficient to trigger the
financial assurance requirements,
supporting data have not been provided
to the NRC. Financial assurance is
required for the cost associated with
decommissioning. Cost for
decommissioning a cyclotron depends
heavily on the complexity of
decommissioning activities, which
would be impacted by multiple factors
such as design of the cyclotron,
operating conditions, maintenance
practices, and usage period. A
standardized approach would not be
suitable for all cyclotrons with various
designs. The NRC’s financial assurance
regulations require financial assurance
for decommissioning costs based on the
type, quantity, half-life, and physical
form of the radionuclides authorized in
the license. The regulations implement
a graded approach that requires
increased financial assurance as the
authorized quantity of licensed material
increases. If the license authorizes a
quantity above a threshold amount,
financial assurance is required.
Financial assurance is required because
the cost of decommissioning should be
borne by the organization that obtains
the benefits of using the licensed
material. The need for financial
assurance increases where the
decommissioning activities are complex
or costly.
The cost of preparing a cost estimate
for decommissioning cannot be avoided
because the licensee must perform its
obligation to decommission the facility
at the end of licensed operations.
Likewise, the cost of characterizing the
extent of contamination cannot be
avoided because characterization is
necessary to prepare a decommissioning
plan.
A licensee can reduce its financial
assurance costs in several ways allowed
by the regulations. The licensee can
reduce its licensed possession limits to
a level below the threshold that requires
financial assurance, or to a level that
allows lower amounts of financial
assurance. The financial assurance
regulations permit a licensee to submit
a site-specific decommissioning funding
plan. If the prescribed amounts of
financial assurance exceed a reasonable
estimate of decommissioning costs, the
licensee may submit a site-specific
decommissioning funding plan to justify
a lower amount of financial assurance.
Information relevant to the amount of
radioactive material that must be
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55905
removed to permit license termination,
and the cost of doing so, can be
presented in the license application.
The financial assurance regulations
allow for a number of different financial
instruments to provide financial
assurance, which allows the licensee to
select the lowest cost alternative.
Consequently, the NRC does not
anticipate creating an exception from
financial assurance requirements for
cyclotron licensees.
Comment: One commenter stated that
the NRC should urge the Agreement
States to adopt their current
requirements for decommissioning
through IMPEP for Agreement States.
NRC Response: Agreement States are
required under AEA Section 274 b. to
adopt the NRC’s regulations according
to the compatibility designations within
3 years. Agreement State programs are
regularly evaluated through IMPEP
reviews. The NRC has worked, and will
continue to work, closely with the
Agreement States to ensure that State
programs are compatible with the NRC.
Comment: One commenter indicated
that there should also be surety
requirements for decommissioning of
facilities used to manufacture sealed
sources.
NRC Response: If the manufacturer of
sealed sources has possession limits that
exceed the threshold amount, it will be
required under existing NRC regulations
to provide financial assurance.
Threshold quantities are included in 10
CFR 30.35.
Comment: One commenter stated that
decommissioning funding should
account for activation products because
some activation products, such as rebar
and steel structural components from
accelerator facilities, have half lives
longer than 120 days and could pose a
disposal issue. Gamma exposure due to
activated products could be an issue in
certain scenarios. If a licensee were to
abandon its facility, the potential
certainly exists for new legacy sites that
the NRC is trying to avoid.
NRC Response: If an accelerator is
used to produce regulated material, and
accelerator components become
activated incidental to the production of
the regulated material, the activated
components would be licensed and
subject to 10 CFR Part 20, Subpart E,
and 10 CFR 30.36 requirements. In
accordance with 10 CFR 30.35, financial
assurance for decommissioning of
licensed material is required based on
the radionuclides and threshold
quantities authorized in the license.
Financial assurance provides funds for
the licensee to conduct
decommissioning activities or to hire a
third-party contractor to decommission
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a facility. These funds could be used in
the event a licensee abandoned its
facility.
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Comments on Other General
Requirements
10 CFR Part 20, Appendix B, Derived
Air Concentration (DAC)
Comment: Several commenters
recommended that the NRC should use
specific values for nitrogen-13 and
oxygen-15 in 10 CFR part 20, appendix
B. One commenter stated that the use of
default values does not allow the
licensee to use a risk-based approach for
compliance.
Most of the commenters endorsed the
DAC values for nitrogen-13 and oxygen15 calculated by Dr. Michael Stabin at
Vanderbilt University. The commenters
noted that Dr. Stabin based his
calculations on EPA Federal Guidance
Report No. 12 (FGR–12) in conjunction
with exposure limits and times used by
the NRC in other calculated values in 10
CFR part 20, Appendix B. The
commenters also noted that the dose
conversion values from FGR–12 are
used by the NRC in other applications
and for other radionuclides currently in
10 CFR part 20, appendix B.
The commenters recommended that
the DAC values for nitrogen-13 and
oxygen-15 calculated by Dr. Stabin
should be rounded to one significant
number and added to part 20, appendix
B.
NRC Response: In Section G of the
proposed rulemaking, the NRC
requested comments on a number of
specific issues, including the adequacy
of the applicable default ALIs and DACs
in 10 CFR part 20, appendix B, for
oxygen-15 and nitrogen-13, and whether
staff should develop larger specific
values for these radionuclides. All six
commenters addressing this issue
believed that specific values for DAC
should be used rather than the current
default DAC value of 10¥7 and 10¥9
microcuries per milliliter of air for
occupational and member of the public,
respectively. Reasons given that the
default values in 10 CFR part 20,
appendix B, were not appropriate
included: (1) They are unnecessarily
restrictive default values that can result
in unjustified cost for unnecessary
radiological monitoring and controls; (2)
the use of default values in general does
not allow the licensee to use a riskbased approach to compliance; (3)
values in the proposed rule would be
unreasonably low; and (4) FGR–12 dose
conversion values are endorsed and
used by the NRC in other applications,
such as dose modeling in support of the
License Termination Rule.
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One commenter submitted an analysis
and DAC values for nitrogen-13 and
oxygen-15 to be incorporated in 10 CFR
part 20, appendix B, Table 1, Column 3,
and Table 2, Column 1, for the DAC
occupational value and air effluent
concentration value. This was endorsed
by several commenters. The analysis
used dose equivalent conversion factors
for submersion in a semi-infinite cloud
from FGR–12, ‘‘External Exposure To
Radionuclides in Air, Water, and Soil,’’
along with exposure parameters used by
the NRC in other calculations in 10 CFR
part 20, appendix B.
Models describing deposition and
retention in the respiratory tract, levels
and times of absorption to blood, and
the biokinetics involved were not
available. The ICRP publications for
workers or members of the public do not
have dose coefficients for radionuclides
with half-lives less than 10 minutes.
ICRP Publication 53, Radiation Dose to
Patients from Radiopharmaceuticals
(1987), does have dose coefficients for
inhalation of these radionuclides, but
the biokinetic models generally are not
directly applicable to worker intakes or
environmental emissions. Because
information was not available for dose
conversion factors for intakes of oxygen15 and nitrogen-13 to compare with the
dose conversion factors for submersion,
the NRC arranged for a study during the
comment period. The purpose of the
study was to develop scientifically
sound inhalation dose coefficients for
occupational and public exposures to
forms of nitrogen-13 and oxygen-15, in
order to compare DAC values from
inhalation with DAC derived from
submersion in contaminated air. The
study developed biokinetic models
describing deposition and respiratory
tract retention, levels and time for
absorption into blood, and systemic
biokinetics of absorbed activity. Dose
coefficients and derived air
concentrations were developed for
inhalation of nitrogen-13 as a gas and as
ammonia, and oxygen-15 as molecular
oxygen and as water vapor. The dose
coefficients for submersion in air
contaminated with nitrogen-13 and
oxygen-15 were taken from FGR–12.
These coefficients for air submersion are
virtually identical because of their
similar photon emissions.
The study verified that the limiting
dose is from submersion in a cloud of
the radionuclide and also arrived at
limiting values for submersion that were
submitted by the commenter, above, and
that were endorsed by three other
commenters. In light of the supporting
documentation and technical basis for
providing a specific value for the DACs
for oxygen-15 and nitrogen-13 from
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submersion in a semi-infinite cloud, the
NRC is incorporating values of 4E–6
microcuries per milliliter for the
occupational value in Table 1, Column
3, and 2E–8 microcuries per milliliter
for the effluent concentration in Table 2,
Column 1, of Appendix B to 10 CFR part
20, for submersion values of both
radionuclides.
Other Comments on Exemptions and
General License
Comment: Some commenters agreed
with the NRC’s proposed delineation of
particle accelerators into three varieties.
The commenters agreed that the
category of accelerators operated to
produce only particle beams and not
radioactive material, which include
linear accelerators used in radiation
therapy, should not be regulated. One
commenter supported the NRC’s
proposal not to regulate incidental
radioactive material produced by
medical linear accelerators.
The commenters recommended that
the NRC expand the exclusion in the
final rule to include a specific
exemption for commercially available
linear accelerators used only for medical
purposes to treat patients. One of the
commenters recommended that the
following or similar language may be
appropriate: ‘‘Particle accelerator means
any machine capable of accelerating
electrons, protons, deuterons, or other
charged particles in a vacuum and of
discharging the resultant particulate or
other radiation into a medium at
energies usually in excess of 1
megaelectron volt and does not include
machines that only produce particle
beams and not radioactive materials. For
purposes of this definition, accelerator
is an equivalent term.’’
NRC Response: The NRC regulates
radioactive material produced by using
particle accelerators but does not
regulate particle accelerators, including
linear accelerators. Therefore, the NRC
cannot include in its regulations the
exemption suggested by the
commenters. The definition for particle
accelerator incorporated in the NRC
regulation is the same as the definition
found in the SSRs. The commenter
suggested adding a statement to the
definition indicating that it does not
include machines that produce particle
beams and not radioactive material. The
NRC does not believe this statement
needs to be added because the NRC does
not regulate accelerators and revising
the definition of Particle accelerator as
suggested by the commenter would
introduce unnecessary confusion and
inconsistency with State regulations.
Comment: A commenter noted a
potential case in which the use of
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byproduct material may not be covered
by the proposed regulations. The
commenter asked if a person, in an
Agreement State who received
byproduct material before September
25, 1971, for use under an Agreement
State’s general license similar to the
general license then provided in 10 CFR
31.4, could still possess the radioactive
material under 10 CFR 30.18(b). The
commenter asserted that the new 10
CFR 30.18(b) should cover the old
byproduct material as well as newly
regulated accelerator-produced
radioactive material.
NRC Response: The Commission
agrees that the proposed wording of 10
CFR 30.18 did not cover materials
distributed for use under the previous
equivalent general license of Agreement
States that may now be used within the
NRC’s jurisdiction. The wording has
been corrected in the final rule to
address this comment.
Comment: A commenter noted that in
the Section-by-Section Analysis under
Section 30.18 exempt quantities, it was
stated that Paragraph (b) would be
revised to include accelerator-produced
radioactive material that had been
received or acquired under the general
license in 10 CFR 31.4. The commenter
did not believe that 10 CFR 31.4
provided coverage of acceleratorproduced radioactive material.
NRC Response: The Commission
agrees that the Section-by-Section
Analysis on this provision did not
appropriately describe the proposed
change, and this is corrected in this
notice.
Comment: A commenter stated that
the discussion for general licenses in 10
CFR 31.5 does not address consistency
with 10 CFR 35.65, which authorizes
sealed source possession. The
commenter requested clarification of
regulatory requirements for sealed
sources under 10 CFR part 35 that are
also generally licensed under 10 CFR
31.5. A similar clarification was also
suggested with respect to the general
license in 10 CFR 31.8.
In addition, the commenter noted that
the proposed rule does not address
possible alternative licensing methods
for a generally licensed sealed source
that is subject to registration
requirements and fees but that might
also be listed as a sealed source on a
specific license and achieve the same
level of regulatory oversight and
tracking. Further, the commenter stated
that the discussion does not clearly
indicate whether the requirements in 10
CFR 31.5 are for all sealed sources or
only registered sealed sources.
NRC Response: The possession and
use of a source or device is not
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authorized by both a general and a
specific license concurrently, or by
more than one general license. The
general license in 10 CFR 31.5 only
covers sealed sources incorporated into
a device, although in some cases, a
specialized source housing may also be
considered a device. The general license
in 10 CFR 31.8 only covers americium241, and now radium-226, calibration
and reference sources with a maximum
possession limit of 5 µCi (185 kBq) at
any one time in any one place. All
devices under 10 CFR 31.5 and sources
under 10 CFR 31.8 must have a label
that identifies them as generally
licensed devices or sources.
The regulations in 10 CFR 35.65
provide specific authority for medical
use licensees to receive, possess, and
use certain specifically licensed sealed
sources and other byproduct material.
This section does not authorize the
possession of generally licensed sources
or devices. Although a 10 CFR part 35
licensee may also possess sealed sources
and devices as authorized by these
general licenses, it does so under the
general license provisions of 10 CFR
31.5 and 10 CFR 31.8.
A specific licensee may use a source
or device authorized under a general
license under the authority of its
specific license if the licensee requests
transferring the authority from the
general license to the specific license
and provides assurance that
requirements of both licenses are met.
This practice normally arises because of
the registration and fees associated with
certain devices covered by the 10 CFR
31.5 general license.
Devices being authorized for use
under 10 CFR 31.5 and equivalent
Agreement State regulations are
evaluated for registration in the SS&D
registry. In large part, SS&D certificates
for devices containing radium-226 and
accelerator-produced radioactive
material have been added to the SS&D
registry, as a means of sharing this
information amongst the States, even
though NRC did not regulate these
materials in the past. If these devices
have been authorized under State
regulations that are similar to NRC
requirements, the NRC would accept
these devices containing radium-226 or
accelerator-produced radioactive
material as generally licensed under 10
CFR 31.5, and would also expect users
to follow the requirements of 10 CFR
31.5 without regard to whether or not
the State registered the device in the
SS&D registry before the effective date
of this final rule.
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55907
Comments on Licensing Fees and Fee
Categories
Comment: One commenter felt that
the discussion in the Statements of
Consideration for the proposed rule
related to license application and
annual fees was not clear in providing
the average professional staff hours for
the licensing categories, and suggested
that to assist stakeholders in reviewing
this proposed rulemaking, the average
and total professional staff hours be
listed by categories. The commenter
suggested that the breakdown for these
categories, and any possible changes in
the annual fee for existing licenses that
might require an amendment based on
the proposed rule, be in 0.25 full time
equivalent (FTE) units. The commenter
also felt that the discussion related to
accelerator-produced radioactive
material was unclear as to whether the
discussion applied only to commercial
distribution or also applied to
noncommercial distribution.
NRC Response: The FTE breakdown
for the proposed new fee categories
could be calculated based on the hourly
rate and the time spent in reviewing
license applications or in conducting
inspections. The average license
application hours used to calculate the
license application fees (as presented in
the proposed rule), for the proposed
new fee categories 3.R.1, 3.R.2, 3.S., and
the proposed revised 3.B. fee category,
are 2.3, 5.4, 24, and 17.7, respectively.
These values could be calculated by
dividing the FY 2005 application fees by
the hourly rate of $197, as described in
the proposed rule.
As explained in the proposed rule, the
annual fees for the materials users fee
class are calculated based on the NRC’s
budgeted resources allocated to
regulating these types of licensees, less
any receipts received from this fee class
for 10 CFR part 170 activities. The net
dollar value of budgeted resources for
this fee class is allocated to all materials
users fee categories (subclasses), based
on the average application and
inspection hours associated with each
fee category. The average inspection
hours (associated with the annual fees
presented in the proposed rule) for the
proposed new fee categories 3.R.1,
3.R.2, 3.S., and revised 3.B. fee category,
are 11.2, 12.2, 21.8, and 18.6,
respectively.
The NRC’s fee calculations are
described in further detail each year in
its fee rulemakings and supporting
documentation. These rulemakings
include details on the FTE and contract
dollars allocated to the materials users
fee class, for each agency-planned
activity level. On February 2, 2007 (72
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FR 5108), the NRC published in the
Federal Register its FY 2007 proposed
fee rule. The proposed fee rule, and its
supporting documentation, presents and
explains the fee calculations for all fee
categories, including the new fee
categories included in this rule. The
final 2007 fee rule was published June
6, 2007 (72 FR 31402). Note that the
NRC does not plan to assess fees for the
new fee categories of 3.R.1, 3.R.2, and
3.S. until the effective date of this final
rule.
The new fee category 3.S. applies to
production of accelerator-produced
byproduct material, i.e., a radionuclide
production facility. Because specific
provisions for noncommercial
distribution of PET radioactive drugs
within a consortium, which includes a
PET radionuclide production facility,
have been added to 10 CFR 30.32(j),
there is no additional fee for
noncommercial distribution of PET
radioactive drugs. If an acceleratorproduced radionuclide production
facility wants to commercially distribute
radioactive drugs, then the existing fee
categories 3.C. and 3.D. would apply for
the commercial distribution portion as
well as the new fee category 3.S. for the
radionuclide production portion of the
activities.
Comment: A number of commenters
did not agree that there was a need to
establish the new fee category for the
production of accelerator-produced
radioactive materials, 3.S., in Section
II.G.(7). These commenters felt that the
existing fee categories covered
byproduct materials whose possession,
use, processing, manufacturing,
distribution, and redistribution were
similar to accelerator-produced
byproduct material. One commenter
stated further that using these existing
fee categories was consistent with the
NRC’s conclusion regarding the
‘‘grandfathering’’ of medical uses, and
that the choice of existing fee categories
should be based on the type of particle
accelerators used and the types and
quantities of radioactive materials being
produced. This commenter stated that
the establishment of a new fee category
was inconsistent with the NRC’s attempt
to minimize impact on the
noncommercial distribution of PET
radionuclides, drugs, and biologics.
While not supporting the 3.S. fee
category, another commenter requested
that, if retained, the language of the final
rule explicitly state that fee category 3.S.
would be applied per facility, not per
accelerator, and that the NRC should be
mindful that additional costs would
inevitably be passed on to the health
care system and patients.
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NRC Response: The NRC is retaining
the new fee category 3.S. because the
NRC incurs budgeted resources in
regulating the production of acceleratorproduced radioactive material, which
are in addition to the budgeted
resources the NRC incurs in regulating
the activities covered by existing fee
categories. Therefore, the NRC believes
a separate fee for this activity is
appropriate. The fee is applicable for
each licensed facility regardless of how
many accelerators reside in the facility.
Comment: One commenter
recommended that exceptions be
extended to IRS-designated 501(c)(3)
organizations operating in whole or in
part as an accredited school of watch
and/or clock repair and/or specialty
museum with a primary focus on
housing and exhibiting timepieces and
related objects.
NRC Response: Exemptions of
persons from the NRC’s regulations for
timepieces and repairs of timepieces are
discussed earlier in subsection
‘‘Comments Related to Radium-226.’’ In
10 CFR 170.11 and 171.11, the NRC lists
fee exemptions for license fees and
annual fees for certain licensees,
including those for nonprofit
educational institutions. In 10 CFR
170.3 and 171.5, a nonprofit educational
institution is defined as ‘‘a public or
nonprofit educational institution whose
primary function is education, whose
programs are accredited by a nationally
recognized accrediting agency or
association, who is legally authorized to
provide a program of organized
instruction or study, who provides an
educational program for which it
awards academic degrees, and whose
educational programs are available to
the public.’’ Historically, the NRC has
not included any fee exemptions for
museums. Because the final rule
contains exemption for intact
timepieces containing less than 37 kBq
(1 µCi) of radium-226 and general
license provisions for various items
containing radium-226, the NRC does
not expect this rule to have major
impacts on museums that would
necessitate the NRC to establish a fee
exemption in its regulations. Under 10
CFR parts 170 and 171, an applicant or
a licensee may file a fee exemption
request with the NRC, and the NRC will
evaluate each request on a case-by-case
basis. Requests for a fee exemption must
be filed with the NRC within 90 days
from the effective date of this final rule
establishing the annual fees for which
the exemption is sought. However, filing
of an exemption request does not extend
the date on which the bill is payable.
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Comments on Waiver Termination and
Transitioning
Comment: A commenter noted that
some non-Agreement States may
continue to require licenses or
registration for the production of
accelerator-produced radioactive
materials, along with their associated
fees. The commenter stated that some
States have already indicated that they
will require a NARM license regardless
of whether an NRC license is required.
The commenter stated that this situation
would expand, rather than streamline,
regulation of radioactive materials.
The commenter noted that it
understood that the States will continue
to regulate radiation-producing
accelerators because the NRC will not
have jurisdiction over the possession
and operation of these machines. The
commenter stated that the NRC should
be aware of its concern that some States
will not discontinue their current
license requirements for the resulting
accelerator-produced materials and
recommended that the NRC address this
in its Transition Plan.
NRC Response: Upon expiration of
the waiver, non-Agreement States will
no longer have authority to license the
radioactive material produced in an
accelerator for use for commercial,
medical, or research activities. The
production of the radioactive material,
however, is only one facet of the
operation of the accelerator. Because the
NRC only has regulatory authority over
the radioactive material and not the
accelerator, some non-Agreement States
may continue to license the accelerator
and its operation. It is possible that
certain producers of radioactive material
may be required to hold two licenses:
One from the State for possession and
operating the accelerator, and one from
the NRC for the possession and use of
the byproduct material produced by the
accelerator. This would not be an issue
for the Agreement States because the
Agreement State will be the only
regulatory authority for radiation
control within its State.
The NRC has worked very closely
with both Agreement States and nonAgreement States in developing the
Transition Plan. The Transition Plan
includes various scenarios and
implementation guidance to ensure a
smooth regulatory transition. On
October 25, 2006, the NRC transmitted
the proposed Transition Plan to the
States for comments. The NRC will
consider State comments in finalizing
the Transition Plan and plans to publish
the final Transition Plan subsequent to
the publication of the final rule but
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before the effective date of this final
rule.
Comment: A commenter requested
that to protect the supply chain with
regard to radiopharmaceuticals, the NRC
should work closely with OAS and the
CRCPD, as well as the States
themselves, to address any licensing or
transactional issues that may arise as a
result of the transition of authority.
NRC Response: The NRC has worked
closely with OAS and CRCPD and
involved the Agreement States and nonAgreement States throughout the
rulemaking process and the
development of the Transition Plan. The
NRC is committed to continued
cooperation with the States during the
transition process.
Comments: A number of respondents
emphasized the importance of
stakeholder education and guidance to
assure a smooth transition to the NRC’s
regulatory control. Two commenters
expressed interest in the development of
a comprehensive guidance document to
be released upon implementation of the
rule, and another commenter mentioned
assistance to stakeholders through an
outline of proposed revisions to the
existing regulatory guidelines. One
commenter also offered its
organization’s publications, websites,
and meetings to assist the NRC with
outreach to the medical user
community.
NRC Response: The NRC is
developing guidance in a separate
action parallel to this rulemaking. A
writing team was established in July
2006 to amend existing guidance and, if
necessary, to develop new guidance
within the NUREG–1556, ‘‘Consolidated
Guidance About Materials Licenses,’’
series of volumes to reflect the new
authority over discrete sources of
radium-226 and the acceleratorproduced radioactive material. The NRC
is in the process of revising Volume 9,
‘‘Consolidated Guidance About
Materials Licenses Program-Specific
Guidance About Medical Use Licenses’’
and Volume 13, ‘‘Consolidated
Guidance About Materials Licenses
Program-Specific Guidance About
Commercial Radiopharmacy Licenses.’’
The NRC is developing new guidance,
Volume 21, ‘‘Consolidated Guidance
About Materials Licenses ProgramSpecific Guidance About Possession
Licenses for Production of Radioactive
Materials Using An Accelerator.’’ The
NUREG–1556 series provides guidance
in areas of the NRC’s jurisdiction and
may be helpful to Agreement States. The
NRC made the draft final guidance
publicly available for comment after the
draft final rule was made publicly
available. The draft guidance documents
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were provided for comment to the States
and the Advisory Committee on Medical
Uses of Radioisotopes at that time. The
NRC expects to finalize the guidance
documents near the effective date of this
rule (60 days after publication). The
guidance documents are being
published for use by current or potential
NRC licensees. It is important to note
that some Agreement States may already
have similar guidance documents.
Comment: A commenter requested the
NRC to confirm that on the effective
date of the proposed rule, holders of
licenses that authorize the use of
licensed material at temporary job sites,
where the NRC maintains jurisdiction,
would be able to amend them to include
accelerator-produced radionuclides. The
commenter also requested the NRC to
confirm that once such licenses were
amended, the licensees would be able to
perform activities using acceleratorproduced materials authorized in the
licenses, at temporary locations within
non-Agreement States, upon
termination of the waiver period on
August 8, 2009.
NRC Response: On the effective date
of this final rule or on the date of waiver
termination, if that date is later, persons
who use accelerator-produced
radionuclides at temporary job sites may
continue those activities regardless of
whether they have an NRC license,
provided that: (1) The person, with an
NRC license that does not authorize use
of byproduct material at temporary job
sites where the NRC has jurisdiction,
applies for an amendment to its license
to authorize uses at these temporary job
sites on or before 6 months from the
effective date of this final rule or on the
date of waiver termination, if that date
is later; or (2) The person without an
NRC specific license applies for a
license on or before 1 year from the
effective date of this final rule or on the
date of waiver termination, whichever is
later.
If the person already has an NRC
license authorizing the use of byproduct
material at temporary job sites where
the NRC has jurisdiction, the person
may continue those activities. With the
amended definition of Byproduct
material in the NRC’s regulations, the
term ‘‘Byproduct material’’ in the
existing license will be interpreted as
including accelerator-produced
radioactive material. It is possible that
an amendment may be needed to
increase the maximum activity limits or
add specific sealed sources or devices to
the license.
If the person did not use acceleratorproduced materials at temporary job
sites before the date of waiver
termination, and its existing license
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does not authorize the use of byproduct
material at temporary job sites, the
person must apply for and receive a
license or amendment before using
these materials.
Comment: Two commenters stated
that if the NRC required the States to
change their statutes, then the effective
date for the final rule should be
extended by 5 years in order for
Agreement States to amend their State
statutes and regulations. One
commenter stated that it agreed with the
proposed effective date for the final rule
and other implementation periods only
if the NRC did not require such a change
from the States.
NRC Response: The NRC does not
believe that changes to the State statutes
would be required by this rulemaking.
The NRC will apply existing policies
and procedures to work with the
Agreement States in implementing this
rule. These existing policies and
procedures allow considerable
flexibility by the States in meeting the
compatibility requirements. The
Agreement States will have up to 3
years to adopt the compatible
requirements of this rule. The NRC will
continue to work with the States to
resolve any issues that may arise.
Comment: A commenter called
attention to the discussion in the
Statements of Consideration for the
proposed rule concerning the
termination of the waiver issued by the
NRC on August 31, 2005. The
commenter noted that the discussion
included a reference to a ‘‘special
arrangement’’ that would need to be
made between a State and the NRC if
the State had not become an Agreement
State by August 7, 2009, when the
waiver will terminate. The commenter
requested additional information on
what would constitute a ‘‘special
arrangement’’ between a State and the
NRC, and how one could be obtained.
NRC Response: The NRC has
considered this comment and has
determined that the wording referred to
by the commenter did not accurately
describe the Commission’s intent in this
regard. What the Commission intended
to convey was that it understands that
situations may arise which may delay
the completion and effective date of an
Agreement. If an Agreement cannot be
completed for a State before the waiver
expires on August 8, 2009, the staff will
determine, on a case-by-case basis,
options to limit the impact of the
transition of authority on affected users
of the new byproduct material in the
State.
The NRC has been communicating
with the non-Agreement States that the
Commission believes might be seeking
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an Agreement in order to avoid this type
of situation. The Commission will
continue to closely coordinate with
these States and monitor the process of
completing any Agreements with these
States in order to decrease the
likelihood that this type of situation will
arise.
Comment: A commenter
recommended that the NRC clarify
whether any additional actions are
needed on the part of licensees that are
currently covered by the waivers issued
to the States.
NRC Response: The waiver was
issued to all persons, including
individuals and licensees as well as
States, that acquire, deliver, receive,
possess, own, use, or transfer the newly
regulated byproduct material. No
actions are needed on the part of these
entities. Once the waiver is terminated,
these persons or licensees are required
to comply with the requirements of this
rule or the corresponding requirements
of the Agreement States.
Comment: A commenter felt that the
discussion in the Statements of
Consideration for the proposed rule
under termination of the waiver for
government agencies was not consistent
with an earlier discussion in the
Supplementary Information that
concluded that radioactive materials
would continue to be used in a manner
protective of public health and safety.
The commenter believed that the later
discussion appeared to equate
regulatory oversight with outcomes
more protective of public health and
safety. The commenter felt that the basis
for concluding the waivers to be
acceptable for a period of time, and then
requiring termination of those waivers,
should be explained.
NRC Response: The NRC does not
agree that there are inconsistencies, as
stated by the commenter, in the
discussion in the Statements of
Consideration for the proposed rule. As
explained in the discussion concerning
issuance of the waiver on August 31,
2005, the NRC was given regulatory
authority over the new byproduct
material when the EPAct became
effective. Therefore, although the NRC
did not have regulations in place that
would specifically apply to this
material, persons continuing to engage
in activities involving the newly
regulated byproduct material, and States
seeking to continue to regulate this
byproduct material would be in
technical violation of the AEA. The NRC
determined that it would be prudent to
establish a mechanism to allow these
activities to continue while the NRC
established a regulatory framework for
the new byproduct material. Section
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651e(5) of the EPAct provides that the
Commission could achieve this goal
through issuing a waiver of the
requirements of Section 651(e) if the
Commission determined that the waiver
was in accordance with the protection
of public health and safety and the
promotion of the common defense and
security. The Commission determined
that the waiver that it issued on August
31, 2005, met this requirement.
However, the EPAct also mandated that
any such waiver issued would have to
expire no more than 4 years after the
date of the enactment of the EPAct.
Therefore, the waivers must expire no
later than August 8, 2009, although
under the EPAct, the Commission may
terminate waivers at an earlier time if it
finds such termination is warranted.
As explained in the discussion
concerning the termination of the
waiver, the NRC established a
Transition Plan, as required by Section
651(e) of the EPAct, to facilitate an
orderly transition of regulatory authority
once the Commission had established a
regulatory framework for regulating the
new byproduct material. This regulatory
framework has now been established
through promulgation of this final rule.
In accordance with the provisions of the
Transition Plan, and to facilitate the
transition of regulatory authority in an
orderly manner, the waivers will be
terminated in stages for users of the new
byproduct material. As explained in the
discussion for termination of the waiver
for Government agencies and Federally
recognized Indian Tribes, the
Commission determined to terminate
the waiver for these entities on the
effective date of the final rule because
there is currently limited regulatory
oversight for the newly added
byproduct material at these facilities.
Options will be considered, on a caseby-case basis, to limit the impact of the
transition of the authority on affected
users of the new byproduct material in
the State. Terminating the waiver for
these entities at that time will provide
for regulatory oversight of the newly
added byproduct material.
Comment: A commenter stated that it
holds Agreement State licenses and
licenses from the NRC that authorize
‘‘radioactive material’’ for a broad range
of radionuclides, i.e., any byproduct
material with atomic numbers 1 through
83 or any byproduct material with
atomic numbers 84 through 102. It also
holds NRC licenses that authorize
‘‘byproduct material’’ for the same broad
range of radionuclides. The commenter
requested that the newly regulated
byproduct materials be authorized
under the current license authorizations
until the licenses are renewed or
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amended. The commenter
recommended that one way to
accomplish this would be to provide a
general license for specific licensees
containing broad scope authorizations.
As an alternate approach, the
commenter suggested that the rule could
provide that licensees authorized for
such activities as using, receiving, or
possessing radionuclides with a range of
atomic numbers are similarly authorized
with respect to the newly regulated
radionuclides. The commenter stated
that these licensees already have the
controls in place to allow for safe
handling of the new radionuclides and
that the blanket authorization will save
the licensees and the NRC paperwork
and expenses. The commenter suggested
that the NRC could request information
by letter on which licensees are
handling the newly regulated
radionuclides.
NRC Response: From the commenter’s
description of its NRC specific license
authorization, it should already be
authorized to use the newly regulated
byproduct material. With the amended
definition of Byproduct material in the
NRC regulations via this rule, the use of
Byproduct material in an existing
license will be interpreted as
authorizing all radioactive materials that
fall under the newly expanded
definition of Byproduct material. With
the broad authorization in the specific
license, a license amendment would
only be needed if the quantity possessed
for one or more particular radionuclides
exceeds the individual limits specified
in the existing license authorization. If
an amendment is needed, the
regulations provide that all licensees
have 6 months from the effective date of
this final rule or from the waiver
termination date to submit an
amendment request. In addition, the
amended regulation would allow
licensees to continue to use the newly
regulated materials until the NRC takes
final licensing action provided that the
amendment request was submitted
within the allotted time. The NRC
believes that it has already provided
adequate relief in its regulations to
assure a smooth transition once the
licensee’s waiver is terminated, and that
neither a general license nor a rule
change is necessary for this purpose.
Comment: Two commenters requested
that the NRC allow sufficient time for
users to prepare for the regulatory
change by simultaneously terminating
all waivers August 7, 2009, and not
chance the supply disruption of PET
radionuclides, drugs, and biologics. The
commenter stated that there were many
differing State regulations for NARM,
and that a step-by-step approach to
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terminating State waivers could leave
unintended voids in the regulations,
thus disrupting supplies of PET
radionuclides. Another commenter
requested that the NRC terminate all
waivers at the same time on August 7,
2009, to avoid disruption. The
commenter stated that acceleratorproduction facilities, which were
designed and built to meet less
restrictive State regulations, may require
significant time to be modified to meet
the NRC’s regulations, and older
facilities may require special approvals
from the NRC.
NRC Response: The EPAct requires
that all waivers must be terminated no
later than 4 years after the date of
enactment of the EPAct. As explained in
the discussion concerning the
termination of the waiver, the NRC
established a Transition Plan, as
required by Section 651(e) of the EPAct,
to facilitate an orderly transition of
regulatory authority once the
Commission had established a
regulatory framework for regulating the
newly added byproduct material. This
regulatory framework has now been
established through promulgation of
this final rule.
The NRC recognizes the importance of
minimizing disruption of PET
radionuclides, drugs, and biologics and
that many States have regulatory
programs for NARM. While all of the
waivers cannot be terminated in
conjunction with the August 7, 2009,
statutory deadline, the NRC is revising
the proposed rule [10 CFR 30.3(c)(2) and
(c)(3), 10 CFR 32.1(c)(2), 10 CFR
35.11(c)(2), and 10 CFR 35.13(a)(2)] to
provide for some waivers to be
terminated in conjunction with the
expiration of the waiver on August 7,
2009. One aspect of the implementation
approach in the proposed rule provided
that requests for licensing actions (e.g.,
amendments or new applications)
would need to be received by the NRC
on or before August 7, 2009, or earlier,
depending upon the date of the waiver
termination. This would essentially
mean waivers would need to be
terminated in August 2008, in order to
provide all affected persons the same
amount of time, as discussed in the draft
Transition Plan, to submit licensing
actions to the NRC. In response to the
comment, the NRC is revising the
proposed rule to provide for some
waivers to be terminated in conjunction
with the expiration of the waiver on
August 7, 2009. The NRC plans to
terminate waivers in stages starting from
the effective date of this final rule and
ending on August 7, 2009. When the
waiver is terminated for persons in a
State, all persons in that State have to
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comply with the NRC regulations for the
newly defined byproduct material,
regardless of whether a license has been
issued by the NRC. If the waiver has not
been terminated for the State, all
persons in the State are still permitted
under the waiver to continue to use the
newly defined byproduct material.
The NRC does not agree that supplies
of PET radionuclides will be disrupted.
Under the waiver, PET radionuclide
production facilities can continue to
produce PET radionuclides. Once the
waiver is terminated, a PET
radionuclide production facility may
continue to produce PET radionuclides
while its license application or
amendment request is under review,
provided that a license application is
submitted within 1 year or an
amendment request within 6 months
from the date of waiver termination.
Medical use licensees can continue to
receive PET radionuclides from these
production facilities or PET radioactive
drugs from drug manufacturers or
commercial nuclear pharmacies either
under the waiver or under the NRC’s
regulations allowing continued
operation provided that the license
application or amendment request was
submitted within the allotted time.
Comments: Two commenters stated
that the transition time created by the
waiver was critical for the nonAgreement States so that patient care
and research activities could continue
without interruption. These commenters
requested that the NRC maintain the
waiver until the local medical and
scientific communities become fully
prepared for the new licensing costs and
requirements.
NRC Response: The EPAct authorized
the NRC to grant waivers for 4 years
from the date of enactment of the Act;
it did not include any provisions that
would allow the NRC to extend the
waiver beyond the statutory deadline of
August 8, 2009. The NRC recognizes the
importance of continuing patient care
and research activities without
interruption and the need for local
medical and scientific communities to
have adequate time to become fully
prepared for the new licensing costs and
requirements.
The NRC has taken several steps to
ensure a smooth transition of the NRC’s
regulatory authority over the newly
defined byproduct material. In addition
to preparing a Transition Plan, the NRC
has, in this rulemaking, included
regulatory provisions for persons or
licensees in a non-Agreement State to
continue using the newly defined
byproduct material after the waiver is
terminated for that State provided a
license application or an amendment
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55911
request is submitted within the allotted
time frame. The NRC believes that its
transitioning approach and the
regulatory provisions will provide
adequate time for licensees to transition
to the new regulations without
interrupting patient care or research for
the following reasons: First, most
medical and scientific communities in
the non-Agreement States are already
using both the traditional byproduct
materials and the newly defined
byproduct materials in similar uses;
therefore, regulatory impact, including
licensing fees and radiation safety
programs, to these people should be
minimal to none. Second, the NRC has
made rulemaking-related documents
and draft rules publicly available to
keep stakeholders informed. Third, the
NRC has allowed time for applicants to
prepare new license applications or
amendment requests in the regulations,
during which they may continue to use
the newly regulated byproduct material
to provide for a smoother transition.
Comment: Two commenters were
concerned that a ‘‘phased-in’’ approach
for terminating the waivers issued in
August 2005 had not been structured to
allow for the transfer of PET
radionuclides, drugs, and biologics to an
NRC licensee from a radionuclide or
drug production facility using
accelerators that has not yet had the
waiver terminated. One commenter
asked for clarification of potential
impacts to the medical community due
to early termination of the waiver to
Federal facilities such as Veterans
Hospitals (i.e., could Federal facilities
still accept radioactive drugs from
companies that are still covered under
the waiver).
NRC Response: The NRC’s phased
waiver termination plan will not affect
the transfer of PET radionuclides, drugs,
and biologics to an NRC licensee from
a PET radionuclide production facility
that has not yet had the NRC waiver
terminated. For example, a Government
agency that is currently receiving PET
radionuclides or drugs under the waiver
may continue to be able to receive PET
radionuclides or drugs from a PET
radionuclide and drug producer or
distributor when its waiver is
terminated. Upon waiver termination,
the Government agency’s existing
license or MML permit may already be
authorized to receive PET drugs if the
license or MML permit is for all
Byproduct material. If the Government
agency has used PET radionuclides and
drugs under the waiver and the license
(or MML permit) needs to be amended,
the Government agency may continue to
use the PET radionuclides and drugs
while preparing the amendment and
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until the NRC (or the MML licensee)
makes its final licensing decision,
provided that an amendment request is
submitted within 6 months from the
date of waiver termination. If the
Government agency used PET
radionuclides and drugs under the
waiver and did not have an NRC license
(or MML permit), the Government
agency may still continue to use the PET
radionuclides and drugs while
preparing a new license application and
until the NRC (or the MML licensee)
makes its final licensing decision,
provided that a license application is
submitted within 1 year from the date
of waiver termination.
While all of the waivers cannot be
terminated in conjunction with the
August 7, 2009, statutory deadline, the
NRC is revising the proposed rule [10
CFR 30.3(c)(2) and (c)(3), 10 CFR
32.1(c)(2), 10 CFR 35.11(c)(2), and 10
CFR 35.13(a)(2)] to provide for some
waivers to be terminated in conjunction
with the expiration of the waiver on
August 7, 2009. The NRC plans to
terminate waivers in stages starting from
the effective date of this final rule and
ending on August 7, 2009.
These same principles would apply to
the PET radionuclide and drug
producers or distributors. After this rule
becomes effective, the PET radionuclide
and drug producers or distributors may
continue to operate until the waiver is
terminated for them. Once the waiver is
terminated, they may continue to
operate if the existing license authorizes
all ‘‘byproduct material’’ or as
authorized by this rule while preparing
a new license application or an
amendment request or while waiting for
the NRC’s final licensing decision,
provided that the license application or
amendment request is submitted within
the allotted time as stated in this rule.
IV. Section-by-Section Analysis of Final
Revisions
jlentini on PROD1PC65 with RULES2
Part 20—Standards for Protection
Against Radiation
The authority citation for this part is
revised to reflect the EPAct.
Section 20.1003—Definitions
The definition of Byproduct material
is revised to reflect the new definition
as mandated in Section 651(e) of the
EPAct.
Definitions for Accelerator-produced
radioactive material, Discrete source,
and Particle accelerator are added.
A definition of Waste is added to
clarify that, as mandated by the EPAct,
byproduct material as defined in
Sections 11e.(3) and 11e.(4) of the AEA
is not low-level radioactive waste as
defined in the LLRWPAA.
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Section 20.1009—Information
Collection Requirements: OMB
Approval
Reference to § 20.2008 is added.
Section 20.2001—General Requirements
Paragraph (a)(4) is revised to include
the new § 20.2008 which addresses
disposal of waste.
Section 20.2006—Transfer for Disposal
and Manifests
Paragraph (e) is added to require the
use of uniform manifests for disposal of
byproduct material as defined in
Sections 11e.(3) and 11e.(4) of the AEA
if intended for ultimate disposal at a
land disposal facility licensed under 10
CFR Part 61.
Section 20.2008—Disposal of Certain
Byproduct Material
This section is added to part 20 to
address disposal requirements for
byproduct material as defined in
Sections 11e.(3) and 11e.(4) of the AEA.
Appendix B to Part 20—Annual Limits
on Intake (ALIs) and Derived Air
Concentrations (DACs) of Radionuclides
for Occupational Exposure; Effluent
Concentrations; Concentrations for
Release to Sewerage
The List of Elements table is revised
to include the elements nitrogen and
oxygen that are now considered
byproduct material. Tables 1, 2, and 3
are revised to specifically include
nitrogen-13 and oxygen-15 and their
associated values.
Part 30—Rules of General Applicability
to Domestic Licensing of Byproduct
Material
The authority citation for this part is
revised to reflect the EPAct.
Section 30.3—Activities Requiring
License
This section is revised to inform
Government agencies, Federally
recognized Indian Tribes, other
licensees, and other persons who
possessed and used byproduct material
as defined in Section 11e.(3) of the AEA
under the provisions of NRC’s waiver
(70 FR 51581; August 31, 2005) which
sections of the regulations will apply to
them when their waiver is terminated
before issuance of an amendment or
new license for byproduct material. For
the Government agencies and Federally
recognized Indian Tribes, requirements
for the newly added byproduct material
will apply to them on the effective date
of the final rule.
This section is also revised to allow
for transition for Government agencies,
Federally recognized Indian Tribes,
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other persons, and other licensees, who
possessed and used byproduct material
as defined in Section 11e.(3) of the AEA
under the waiver, to continue to use
these materials while applying for and
receiving licenses or amendments to
existing licenses. This section revises
the authority and responsibilities of
persons or licensees that do not file for
the license or amendment within the
required time with respect to receipt,
use, possession, and disposal of
byproduct material and the
decommissioning of facilities.
Section 30.4—Definitions
The definition of Byproduct material
is revised to be consistent with the new
definition in the AEA, with the
exception that it does not include
byproduct material as defined in
Section 11e.(2) of the AEA.
The following definitions are added to
this section: Accelerator-produced
radioactive material, Consortium,
Cyclotron, Discrete source, and Particle
accelerator.
Section 30.15—Certain Items
Containing Byproduct Material
This section is revised to add
paragraph (a)(1)(viii) to authorize 0.037
MBq (1 µCi) of radium-226 per
timepiece in intact timepieces
manufactured before the effective date
of the final rule.
Section 30.18—Exempt Quantities
Paragraph (b) is revised to include
byproduct material received or acquired
before September 25, 1971, under a
general license provided in 10 CFR 31.4
or by a State provision similar to 10 CFR
31.4.
Section 30.20—Gas and Aerosol
Detectors Containing Byproduct
Material
Paragraph (a) is revised to apply to gas
and aerosol detectors manufactured or
distributed before the effective date of
the final rule in accordance with a
specific license issued by a State with
comparable provisions to 10 CFR 32.26.
Section 30.32—Application for Specific
Licenses
Paragraph (g) is revised to accept
information from sealed source or
device registrations with regard to
NARM issued by the States under
provisions comparable to 10 CFR 32.210
as a basis for licensing the use of
sources and devices. The paragraph is
also revised to allow a basis for
licensing sources or devices containing
NARM, that were manufactured before
the effective date of the final rule, are
not registered with the Commission
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Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules and Regulations
under 10 CFR 32.210 or with an
Agreement State, and for which all the
information identified in 10 CFR 32.210
is unavailable.
Paragraph (j) is added to this section
to inform an educational institution, a
medical facility, or a Government
facility applicant of the information
required by the NRC to authorize the
production of PET radioactive drugs
used for medical uses under 10 CFR part
35 for the noncommercial transfer to
medical facilities in its consortium.
Section 30.34—Terms and Conditions of
Licenses
Paragraph (g) is revised to require
licensees to measure strontium-82 and
strontium-85 contamination before use
of the first eluate when eluding
strontium-82/rubidium-82 generators.
Paragraph (j) is added to clarify that
nothing in the authorization under 10
CFR 30.32(j) relieves the licensee from
complying with FDA, other Federal, or
State requirements for radioactive drugs,
and to include requirements associated
with the labeling and production of PET
radioactive drugs by licensees
authorized under the provisions of 10
CFR 30.32(j) to produce PET radioactive
drugs for the noncommercial transfer to
medical use licensees in their
consortium. This section also requires
licensees to use the notification process
in 10 CFR 32.72 when permitting
qualified authorized nuclear
pharmacists to work as ANPs.
Section 30.71—Schedule B
Schedule B is revised to include 13
radionuclides that are now considered
byproduct material and their associated
exempt quantities.
Section 30.72—Schedule C—Quantities
of Radioactive Materials Requiring
Consideration of the Need for an
Emergency Plan for Responding to a
Release
The table in Schedule C is revised to
specifically include radium-226 and its
associated values.
Part 31—General Domestic Licenses
For Byproduct Material
The authority citation for this part is
revised to reflect the EPAct.
jlentini on PROD1PC65 with RULES2
Section 31.4—Information Collection
Requirements: OMB Approval
Reference to §31.12 is added.
Section 31.5—Certain Detecting,
Measuring, Gauging, or Controlling
Devices and Certain Devices for
Producing Light or an Ionized
Atmosphere
Paragraph (b)(1) is revised to add
authority under the general license for
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byproduct material contained in devices
which have been manufactured or
initially transferred and labeled in
accordance with the specifications
contained in an equivalent specific
license issued by a State with
comparable provisions to 10 CFR 32.51.
Paragraph (c)(13)(i) is revised to add
radium-226, with an activity of at least
3.7 MBq (0.1 µCi) to the criteria for
devices requiring registration.
Section 31.8—Americium-241 and
Radium-226 in the Form of Calibration
or Reference Sources
The section heading and paragraph (a)
are revised to include radium-226 in a
general license for calibration and
reference sources.
Paragraph (b) is revised to recognize
sources manufactured or initially
transferred in accordance with the
specifications contained in a specific
license issued by a State with
comparable provisions to 10 CFR 32.57.
Paragraph (c)(1) is revised to include
an activity limit of 0.185 MBq (5 µCi) of
radium-226.
Paragraph (c)(2) is revised to include
radium-226 in the labeling requirement,
with the provision added to footnote 1
that, for those sources manufactured
before the effective date of the final rule,
sources containing radium-226 shall be
labeled in accordance with the
applicable State regulations at the time
of manufacture or import.
Paragraphs (c)(4), (d), and (e) are
revised to include radium-226.
Section 31.11—General License for Use
of Byproduct Material for Certain In
Vitro Clinical or Laboratory Testing
Paragraphs (a) and (c) are revised to
include cobalt-57 in the list of
authorized byproduct material for use in
in vitro clinical or laboratory testing.
Paragraph (d) is revised to allow
receipt of prepackaged units that are
labeled in accordance with a specific
license issued by a State with
comparable provisions to 10 CFR 32.71.
Sections 31.12, 31.13, and 31.14 Are
Redesignated as §§ 31.21, 31.22, and
31.23, Respectively
Section 31.12—General License for
Certain Items and Self-luminous
Products Containing Radium-226
This section is added to the
regulations to add a general license for
certain items and self-luminous
products containing radium-226 that
were manufactured before the effective
date of the final rule. The general
license addresses radium-226 contained
in products such as antiquities;
timepieces; luminous items installed in
air, marine, or land vehicles; all other
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55913
luminous products; and small radium
sources containing no more than 0.037
MBq (1 µCi) of radium-226.
The general license exempts persons
from the provisions of 10 CFR parts 19,
20, and 21, and 10 CFR 30.50 and 10
CFR 30.51.
The general license includes
requirements for notification, reporting,
disposal, and certain prohibitions.
However, the general license allows
timepieces containing radium-226 to be
disassembled and repaired.
Part 32—Specific Domestic Licenses To
Manufacture or Transfer Certain Items
Containing Byproduct Material
The authority citation for this part is
revised to reflect the EPAct.
Section 32.1—Purpose and Scope
A new paragraph (c) is added to
inform Government agencies, Federally
recognized Indian Tribes, other
licensees, and other persons who
manufacture or initially transfer items
containing accelerator-produced
radioactive material or discrete sources
of radium-226 for sale or distribution to
persons exempted from the licensing
requirements of part 30 of this chapter,
and persons generally licensed under
part 31 or part 35 of this chapter, and
radioactive drugs and sources and
devices to medical use licensees, that
the requirements in part 32 will apply
to them when their waiver is terminated
before issuance of an amendment or
new license for such activities. The
requirements will apply to Government
agencies and Federally recognized
Indian Tribes on the effective date of the
final rule.
This paragraph allows Government
agencies, Federally recognized Indian
Tribes, other persons, and other
licensees who manufacture or initially
transfer items containing acceleratorproduced radioactive material or
discrete sources of radium-226 for sale
or distribution to persons exempted
from the licensing requirements of part
30 of this chapter, persons generally
licensed under part 31 or part 35 of this
chapter, and radioactive drugs and
sources and devices to medical use
licensees to continue to manufacture or
initially transfer these items to such
persons when their waiver is terminated
before issuance of an amendment or
new license for such activities.
Section 32.57—Calibration or Reference
Sources Containing Americium-241 or
Radium-226: Requirements for License
to Manufacture or Initially Transfer
The heading and the section are
revised to add radium-226.
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Section 35.2—Definitions
The definitions of Cyclotron and
Positron Emission Tomography (PET)
radionuclide production facility are
added.
Section 32.58—Same: Labeling of
Devices
This section is revised to include
radium-226 in the example label.
Section 32.59—Same: Leak Testing of
Each Source
This section is revised to include
radium-226.
Section 32.71—Manufacture and
Distribution of Byproduct Material for
Certain In Vitro Clinical or Laboratory
Testing Under General License
Paragraph (b)(8) is added to include
cobalt-57, in units not exceeding 0.37
MBq (10 µCi) each, to the list of
authorized byproduct material approved
for distribution.
Paragraph (c)(1) is revised to include
cobalt-57.
Section 32.72—Manufacture,
Preparation, or Transfer for Commercial
Distribution of Radioactive Drugs
Containing Byproduct Material for
Medical Use Under Part 35
Paragraph (a) is revised to ensure that
the NRC’s regulation encompasses all
drug manufacturers that are registered
with the FDA or a State agency. The
description of who is registered with the
FDA was updated to conform with FDA
regulations.
Paragraph (b) is revised to recognize
nuclear pharmacists, who prepared only
accelerator-produced radioactive drugs,
before the effective date of the final rule
and authorized nuclear pharmacists
identified on permits issued by master
material licensees or by a master
material permittee of broad scope, to
work as authorized nuclear pharmacists
at a commercial nuclear pharmacy
under the notification process in 10 CFR
32.72.
Section 32.102—Schedule C—Prototype
Tests for Calibration or Reference
Sources Containing Americium-241 or
Radium-226
The heading and section are revised
to include radium-226.
Part 33—Specific Domestic Licenses of
Broad Scope for Byproduct Material
The authority citation for this part is
revised to reflect the EPAct.
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Section 33.100—Schedule A
This table is revised to add four
additional radionuclides and their
associated values.
Part 35—Medical Use of Byproduct
Material
The authority citation for this part is
revised to reflect the EPAct.
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Section 35.10—Implementation
Paragraph (a) is added to clarify that
Government agencies and Federally
recognized Indian Tribes possessing and
using accelerator-produced radioactive
material and discrete sources of radium226 for medical use must comply with
the requirements in this part on the
effective date of the final rule. The
paragraph also informs other persons
using this material for medical use
when they must comply with the
requirements of this part.
Section 35.11—License Required
Paragraph (a) is revised, and
paragraph (c) is added to allow
Government agencies, Federally
recognized Indian Tribes, and other
persons who possessed and used
accelerator-produced radioactive
materials or discrete sources of radium226, under the provisions of the NRC’s
waiver (70 FR 51581; August 31, 2005),
to have time to apply for and receive a
new medical use license and allow them
to continue to use these materials,
provided the new license was applied
for in the time required. This section
also provides the time period for
applying for a new license.
Section 35.13—License Amendments
Paragraph (a) is modified to allow
Government agencies, Federally
recognized Indian Tribes, and other
licensees that possessed and used
accelerator-produced radioactive
materials or discrete sources of radium226, under the provisions of the NRC’s
waiver (70 FR 51581; August 31, 2005),
to continue to use this material
provided that they submit an
application to amend their licenses in
the specified time required. This section
also provides the time period for
amending licenses.
A new paragraph (b)(5) is added to
permit physicians and pharmacists who
only used accelerator-produced
radioactive materials or discrete sources
of radium-226 during the NRC’s waiver
(70 FR 51581; August 31, 2005) to use
the notification process.
Paragraph (e) is modified to require an
amendment before a licensee adds to, or
changes, areas of use identified in the
application or on the license, including
areas used in accordance with either 10
CFR 35.100 or 35.200 if the change
includes the addition or relocation of
either an area where PET radionuclides
are produced or a PET radioactive drug
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delivery line from the PET
radionuclide/PET radioactive drug
production area. Other areas of use
where byproduct material is used only
in accordance with either 10 CFR 35.100
or 10 CFR 35.200 continue to be
excluded from this requirement.
Section 35.14—Notifications
Paragraph (a) is revised to address
information needed for NRC notification
of nuclear pharmacists and physicians
who used only accelerator-produced
radioactive materials and discrete
sources of radium-226 who have not
been identified on a license or permit
during the NRC’s waiver (70 FR 51581;
August 31, 2005).
Paragraph (b) is revised to retain, in
the notification requirements, any
additions or changes in 10 CFR 35.100
or 10 CFR 35.200 areas of use, if the
changes do not involve additions or
relocations of either an area where PET
radionuclides are produced or a PET
radioactive drug delivery line from the
PET radionuclide/PET radioactive drug
production area.
Section 35.15—Exemptions Regarding
Type A Specific Licenses of Broad
Scope
Paragraph (f) is revised to clarify that
the broad scope licensee is exempted
from making the notification of addition
or changes in 10 CFR 35.100 or 10 CFR
35.200 areas of use.
Section 35.57—Training for
Experienced Radiation Safety Officer,
Teletherapy or Medical Physicist,
Authorized Medical Physicist,
Authorized User, Nuclear Pharmacist,
and Authorized Nuclear Pharmacist
A new paragraph (a)(3) is added to
grandfather RSOs, medical physicists, or
nuclear pharmacists who used only
accelerator-produced radioactive
materials or discrete sources of radium226, or both, during the NRC’s waiver
(70 FR 51581; August 31, 2005) from
training requirements and to recognize
them as RSOs, AMPs, or ANPs for those
same materials and uses.
A new paragraph (b)(3) is added to
grandfather physicians, dentists, or
podiatrists who used only acceleratorproduced radioactive materials or
discrete sources of radium-226, or both,
under the NRC’s waiver (70 FR 51581;
August 31, 2005) from training
requirements and to recognize them as
AUs for those same materials and uses.
Section 35.63—Determination of
Dosages of Unsealed Byproduct Material
for Medical Use
This section is revised to add a new
provision in paragraphs (b)(2) and (c)(3)
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Section 35.2204—Records of
Molybdenum-99, Strontium-82, and
Strontium-85 Concentrations
to include PET radioactive drug
producers licensed under 10 CFR
30.32(j) for the production of PET
radioactive drugs transferred
noncommercially to members of their
consortium.
The section heading is revised to add
strontium-82 and strontium-85, and this
section is revised to include a
Section 35.100—Use of Unsealed
recordkeeping requirement of the
Byproduct Material for Uptake, Dilution, strontium-82 and strontium-85
and Excretion Studies for Which a
concentration tests required by 10 CFR
Written Directive is Not Required
35.204(b) and (c).
Paragraph (a) is revised to permit
Part 50—Domestic Licensing of
medical use licensees to obtain PET
Production and Utilization Facilities
drugs from PET radioactive drug
The authority citation for this part is
producers licensed under 10 CFR
revised to reflect the EPAct.
30.32(j) for the production of PET
radioactive drugs transferred
Section 50.2—Definitions
noncommercially to members of their
consortium.
The definition of Byproduct material
Paragraph (b) is revised to continue to is revised to be consistent with the new
clarify that 10 CFR 35.100 licensees are
definition as mandated by the EPAct,
not allowed to produce PET
with the exception that it will not
radionuclides.
include byproduct material as defined
in Section 11e.(2) of the AEA.
Section 35.200—Use of Unsealed
Byproduct Material for Imaging and
Localization Studies for Which a
Written Directive is Not Required
Paragraph (a) is revised to permit
medical use licensees to obtain PET
drugs from PET radioactive drug
producers licensed under 10 CFR
30.32(j) for the production of PET
radioactive drugs transferred
noncommercially to members of their
consortium.
Paragraph (b) is revised to clarify that
10 CFR 35.200 licensees are not allowed
to produce PET radionuclides.
Section 35.204—Permissible
Molybdenum-99, Strontium-82, and
Strontium-85 Concentrations
The section heading is revised to add
strontium-82 and strontium-85.
Paragraph (a) is revised to address
acceptable strontium-82 and strontium85 concentrations when eluting
strontium-82/rubidium-82 generators.
Paragraph (c) is revised and
redesignated, and a new paragraph (c) is
added to address measuring
requirements for strontium-82 and
strontium-85.
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Section 35.300—Use of Unsealed
Byproduct Material for Which a Written
Directive is Required
Paragraph (a) is revised to permit
medical use licensees to obtain PET
drugs from PET radioactive drug
producers licensed under 10 CFR
30.32(j) for the production of PET
radioactive drugs transferred
noncommercially to members of their
consortium.
Paragraph (b) is revised to clarify that
10 CFR 35.300 licensees are not allowed
to produce PET radionuclides.
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Part 61—Licensing Requirements for
Land Disposal of Radioactive Waste
The authority citation for this part is
revised to reflect the EPAct.
The definition of Waste is revised to
clarify that, as mandated by the EPAct,
byproduct material, as defined in
Sections 11e.(3) and 11e.(4) of the AEA,
is not low-level radioactive waste as
defined in the LLRWPAA.
Part 62—Criteria and Procedures for
Emergency Access to Non-Federal and
Regional Low-Level Waste Disposal
Facilities
The authority citation for this part is
revised to reflect the EPAct.
Section 62.2—Definitions
The definition of Low-level
radioactive waste (LLW) is revised to
clarify that byproduct material, as
defined in Sections 11e.(3) and 11e.(4)
of the AEA, is not considered low-level
radioactive waste.
Part 72—Licensing Requirements for
the Independent Storage of Spent
Nuclear Fuel, High-Level Radioactive
Waste, and Reactor-Related Greater
Than Class C Waste
Section 72.3—Definitions
The definition of Byproduct material
is revised to be consistent with the
definition in 10 CFR 30.4. This
definition is consistent with the
definition of Byproduct material in the
EPAct, with the exception that it will
not include byproduct material as
defined in Section 11e.(2) of the AEA.
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Part 110—Export and Import of
Nuclear Equipment and Material
The authority citation for this part is
revised to reflect the EPAct.
Section 110.2—Definitions
Definitions of Accelerator-produced
radioactive material, Discrete source,
and Particle accelerator are added.
Part 150—Exemptions and Continued
Regulatory Authority in Agreement
States and in Offshore Waters Under
Section 274
The authority citation for this part is
revised to reflect the EPAct.
Section 150.3—Definitions
The definition of Byproduct material
is revised to be consistent with the
definition in the EPAct.
A definition of Discrete source is
added.
Part 170—Fees for Facilities, Materials,
Import and Export Licenses, and Other
Regulatory Services Under the Atomic
Energy Act of 1954, as Amended
The authority citation for this part is
revised to reflect the EPAct.
Section 61.2—Definitions
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Section 170.3—Definitions
The definition of Byproduct material
is revised to be consistent with the new
definition in the AEA, with the
exception that it does not include
byproduct material as defined in
Section 11e.(2) of the AEA.
Section 170.31—Schedule of Fees for
Materials Licenses and Other Regulatory
Services, Including Inspections, and
Import and Export Licenses
This section is revised to include
licenses that are not included in existing
fee categories. Fee Category 3.B. is
revised to include licenses for repair,
assembly, and disassembly of products
containing radium-226. Two new fee
categories, 3.R. with additional
subcategories and 3.S., are added to
include fees for possession of items or
products containing radium-226, which
exceed the number of items or limits
specified in 10 CFR 31.12, and for
production of accelerator-produced
radioactive material.
Part 171—Annual Fees for Reactor
Licenses and Fuel Cycle Licenses and
Materials Licenses, Including Holders
of Certificates of Compliance,
Registrations, and Quality Assurance
Program Approvals and Government
Agencies Licensed by the NRC
The authority citation for this part is
revised to reflect the EPAct.
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Section 171.5—Definitions
The definition of Byproduct material
is revised to be consistent with the new
definition in the AEA, with the
exception that it does not include
byproduct material as defined in
Section 11e.(2) of the AEA.
Section 171.16—Annual fees: Materials
Licenses, Holders of Certificates of
Compliance, Holders of Sealed Source
and Device Registrations, Holders of
Quality Assurance Program Approvals,
and Government Agencies Licensed by
the NRC
This section is revised to include
licenses that are not included in existing
fee categories. Fee Category 3.B. is
revised to include licenses for repair,
assembly, and disassembly of products
containing radium-226. Two new fee
categories, 3.R. with additional
subcategories and 3.S., are added to
include fees for possession of items or
products containing radium-226, which
exceed the number of items or limits
specified in 10 CFR 31.12, and for
production of accelerator-produced
radioactive material.
V. Criminal Penalties
For the purpose of Section 223 of the
Atomic Energy Act (AEA), the
Commission is amending 10 CFR Parts
20, 30, 31, 32, 33, 35, 50, 61, 62, 72, 110,
150, 170, and 171 under one or more of
Sections 161b, 161i, or 161o of the AEA.
Willful violations of the rule would be
subject to criminal enforcement.
VI. Agreement State Compatibility
Under the ‘‘Policy Statement on
Adequacy and Compatibility of
Agreement State Programs’’ approved by
the Commission on June 30, 1997, and
published in the Federal Register (62
FR 46517; September 3, 1997), this rule
would be a matter of compatibility
between the NRC and the Agreement
States, thereby providing consistency
among the Agreement States’ and the
NRC’s requirements. The NRC staff
analyzed the rule in accordance with
the procedure established within Part
III, ‘‘Categorization Process for NRC
Program Elements,’’ of Handbook 5.9 to
Management Directive 5.9, ‘‘Adequacy
and Compatibility of Agreement State
Programs’’ (a copy of which may be
viewed at https://www.nrc.gov/readingrm/doc-collections/managementdirectives/).
The NRC program elements
(including regulations) are placed into
four compatibility categories (See the
Compatibility Table in this section). In
addition, the NRC program elements can
also be identified as having particular
health and safety significance or as
being reserved solely to the NRC.
Compatibility Category A are those
program elements that are basic
radiation protection standards and
scientific terms and definitions that are
necessary to understand radiation
protection concepts. An Agreement
State should adopt Category A program
elements in an essentially identical
manner to provide uniformity in the
regulation of agreement material on a
nationwide basis. Compatibility
Category B are those program elements
that apply to activities that have direct
and significant effects in multiple
jurisdictions. An Agreement State
should adopt Category B program
elements in an essentially identical
manner. Compatibility Category C are
those program elements that do not
meet the criteria of Category A or B, but
the essential objectives of which an
Agreement State should adopt to avoid
conflict, duplication, gaps, or other
conditions that would jeopardize an
orderly pattern in the regulation of
agreement material on a nationwide
basis. An Agreement State should adopt
the essential objectives of the Category
C program elements. Compatibility
Category D are those program elements
that do not meet any of the criteria of
Category A, B, or C, above, and, thus, do
not need to be adopted by Agreement
States for purposes of compatibility.
Health and Safety (H&S) are program
elements that are not required for
compatibility but are identified as
having a particular health and safety
role (i.e., adequacy) in the regulation of
agreement material within the State.
Although not required for compatibility,
the State should adopt program
elements in this H&S category based on
those of the NRC that embody the
essential objectives of the NRC program
elements because of particular health
and safety considerations. Compatibility
Category NRC are those program
elements that address areas of regulation
that cannot be relinquished to
Agreement States under the AEA, as
amended, or provisions of Title 10 of
the Code of Federal Regulations. These
program elements are not adopted by
the Agreement States. The following
table lists the parts and sections that
would be revised and their
corresponding categorization under the
‘‘Policy Statement on Adequacy and
Compatibility of Agreement State
Programs.’’ A bracket around a category
means that the section may have been
adopted elsewhere, and it is not
necessary to adopt it again.
The definition of Byproduct material
in the AEA was expanded by Section
651(e) of the EPAct to incorporate
certain discrete sources of radium-226
and certain accelerator-produced
radioactive materials. The definition of
Byproduct material in 10 CFR parts 20,
30, 50, 72, 150, 170, and 171 is amended
to reflect the changes to the AEA. The
definition of Byproduct material in parts
50, 72, 170, and 171 is reserved to the
NRC. The definition of Byproduct
material in 10 CFR parts 20, 30, and 150
are categorized as H&S. This designation
is for regulatory program elements that
have particular health and safety
significance. The H&S designation
indicates that the definition is needed
for purposes of ‘‘adequacy.’’ If NARM is
included in the Agreement between the
NRC and the Agreement State, then
NARM would be a necessary program
element of the Agreement State program
to adequately ensure public health and
safety. The definition of Discrete source
has also been identified in this rule as
H&S because it is part of the definition
of Byproduct material.
COMPATIBILITY TABLE
Compatibility
Section
Change
Subject
Existing
jlentini on PROD1PC65 with RULES2
20.1003 ..............................
Amend ...............................
20.1003 ..............................
20.1003 ..............................
20.1003 ..............................
20.1009 ..............................
20.2001(a)(4) .....................
Add ....................................
Add ....................................
Add ....................................
Amend ...............................
Amend ...............................
VerDate Aug<31>2005
18:25 Sep 28, 2007
Jkt 214001
PO 00000
Definition: Byproduct Material (add 11e.(3) & 11e.(4)
material).
Definition: Discrete Source ...........................................
Definition: Particle Accelerator .....................................
Definition: Waste ..........................................................
List of OMB approved information collections .............
General requirements (add reference to new
§ 20.2008).
Frm 00054
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E:\FR\FM\01OCR2.SGM
01OCR2
New
[A] ................
[H&S]
.....................
.....................
.....................
D .................
C .................
H&S
H&S
B
D
C
55917
Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules and Regulations
COMPATIBILITY TABLE—Continued
Compatibility
Section
Change
Subject
Existing
Add ....................................
20.2008 ..............................
Add ....................................
Appendix B to Part 20 .......
30.3(a) ................................
Amend ...............................
Amend ...............................
30.3(b)(1) ...........................
Add ....................................
30.3(b)(2) ...........................
Add ....................................
30.3(b)(3) ...........................
Add ....................................
30.3(c)(1) ...........................
Add ....................................
30.3(c)(2) ...........................
Add ....................................
30.3(c)(3) ...........................
Add ....................................
30.3(d) ................................
Add ....................................
30.4 ....................................
30.4 ....................................
Add ....................................
Amend ...............................
30.4 ....................................
30.4 ....................................
30.4 ....................................
30.4 ....................................
30.15(a)(1)(viii) ...................
Add
Add
Add
Add
Add
30.18(b) ..............................
Amend ...............................
30.20(a) ..............................
Amend ...............................
30.32(g) ..............................
30.32(j) ...............................
Amend ...............................
Add ....................................
30.34(g) ..............................
Amend ...............................
30.34(j) ...............................
Add ....................................
30.71 ..................................
30.72 ..................................
Amend ...............................
Amend ...............................
31.4 ....................................
31.5(b)(1) & (c)(13) ............
Amend ...............................
Amend ...............................
31.8 ....................................
Amend ...............................
31.11 ..................................
Amend ...............................
31.12 ..................................
jlentini on PROD1PC65 with RULES2
20.2006(e) ..........................
Add ....................................
32.1(c)(1) ...........................
Add ....................................
VerDate Aug<31>2005
18:25 Sep 28, 2007
....................................
....................................
....................................
....................................
....................................
Jkt 214001
PO 00000
Transfer for disposal and manifests (add 11e.(3) and
11e.(4) byproduct material).
Disposal of 11e.(3) and 11e.(4) byproduct material
(new section).
Add limits for N–13 and O–15 ......................................
Activities requiring license (add reference to paragraph (c)).
Activities requiring license (requirements that apply to
Government agencies and Federally recognized Indian Tribes at waiver termination).
Activities requiring license (authorization for Government agencies and Federally recognized Indian
Tribes to possess and use 11e.(3) materials while
applying for a license amendment).
Activities requiring license (authorization for Government agencies and Federally recognized Indian
Tribes to possess and use 11e.(3) materials while
applying for a new license).
Activities requiring license (requirements that apply to
all other persons at waiver termination).
Activities requiring license (authorization for all other
persons to possess and use 11e.(3) materials while
applying for a license amendment).
Activities requiring license (authorization for all other
persons to possess and use 11e.(3) materials while
applying for a new license).
Activities requiring license (continuation of authority
for failure to submit amendment or license).
Definition: Accelerator-produced radioactive material ..
Definition: Byproduct material (add 11e.(3) & 11e.(4)
material).
Definition: Consortium ..................................................
Definition: Cyclotron .....................................................
Definition: Discrete source ...........................................
Definition: Particle accelerator ......................................
Certain items containing byproduct material (add radium-226 intact timepieces and limited repairs).
Exempt quantities (add 11e.(3) material) .....................
Gas and aerosol detectors containing byproduct material (grandfather 11e.(3) detectors).
Application for specific licenses ...................................
Application for specific licenses (add noncommercial
transfer of PET drugs).
Terms and conditions of licenses (add strontium-82/
rubidium-82 generators).
Terms and conditions of licenses (add noncommercial
transfer of PET drugs).
Schedule B (add 11e.(3) material) ...............................
Schedule C—Quantities of radioactive materials requiring consideration of the need for an emergency
plan for responding to a release (add radium-226).
List of OMB approved information collections .............
Certain detecting, measuring, gauging, or controlling
devices and/or an ionizing atmosphere (add devices with NARM approved by States).
Americium-241 in the form of calibration or reference
sources (add radium-226).
General license for use of byproduct material for certain in vitro clinical or laboratory testing (add cobalt57).
General license for certain items and self-luminous
products containing radium-226 (new section).
Purpose and scope (requirements that apply to Government agencies and Federally recognized Indian
Tribes at waiver termination and authorization to
manufacture and distribute items with 11e.(3) material while applying for amendment or license).
Frm 00055
Fmt 4701
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E:\FR\FM\01OCR2.SGM
01OCR2
New
.....................
B
.....................
B
A ..................
C .................
A
C
.....................
NRC
.....................
NRC
.....................
NRC
.....................
D
.....................
D
.....................
D
.....................
D
.....................
[A] ................
H&S
[H&S]
.....................
.....................
.....................
.....................
B ..................
(all § 30.15)
B ..................
(all § 30.18)
B ..................
(all § 30.20)
C ..................
.....................
C
D
H&S
H&S
B
D .................
H&S
.....................
B
B ..................
H&S .............
B
H&S
D ..................
B ..................
(all § 31.5) ...
D
B
D .................
D
D .................
D
.....................
C
.....................
NRC
B
B
C
B
55918
Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules and Regulations
COMPATIBILITY TABLE—Continued
Compatibility
Section
Change
Subject
Existing
Add ....................................
32.57 ..................................
Amend ...............................
32.58 ..................................
32.59 ..................................
32.71(b)(8) & (c)(1) ............
Amend ...............................
Amend ...............................
Add ....................................
32.72(a)(2)(i), (iii), (iv), (v),
& (b).
Amend ...............................
32.102 ................................
Amend ...............................
33.100 ................................
Amend ...............................
35.2 ....................................
35.2 ....................................
Add ....................................
Add ....................................
35.10(a) ..............................
Add ....................................
35.10(g) ..............................
35.11(a) ..............................
35.11(c)(1) .........................
Redesignated ....................
Amend ...............................
Add ....................................
35.11(c)(2) .........................
Add ....................................
35.13(a)(1) .........................
Amend ...............................
35.13(a)(2) .........................
Amend ...............................
35.13(b)(5) .........................
Add ....................................
35.13(e) ..............................
35.14(a) and (b)(5) ............
Amend ...............................
Amend ...............................
35.15(f) ...............................
Amend ...............................
35.57(a)(3) & (b)(3) ............
Add ....................................
35.63(b)(2)(ii) & (c)(3) ........
Amend ...............................
35.63(b)(2)(iii) ....................
Add ....................................
35.100(a) & (b) ..................
Amend ...............................
35.200(a) & (b) ..................
jlentini on PROD1PC65 with RULES2
32.1(c)(2) ...........................
Amend ...............................
35.204(a) ............................
Amend ...............................
35.204(c) ............................
Add ....................................
VerDate Aug<31>2005
18:25 Sep 28, 2007
Jkt 214001
PO 00000
Purpose and scope (requirements that apply to all
other persons at waiver termination and authorization to manufacture and distribute items with
11e.(3) material while applying for amendment or license).
Calibration or reference sources containing americium-241: Requirements for license to manufacture
or initially transfer (add radium-226).
Same: Labeling of devices (add radium-226) ..............
Same: Leak testing of each source (add radium-226)
Manufacture and distribution of byproduct material for
certain in vitro clinical or laboratory testing under
general license (add cobalt-57).
Manufacture, preparation, or transfer for commercial
distribution of radioactive drugs containing byproduct material for medical use under part 35 (recognize FDA and State registrations of PET facilities
and pharmacist using 11e.(3) material).
Schedule C—prototype tests for calibration or reference sources containing americium-241 (add radium-226).
Schedule A (add beryllium-7, cobalt-57, radium-226,
& sodium-22).
Definition: Cyclotron .....................................................
Definition: Positron Emission Tomography (PET)
radionuclide production facility.
Implementation (requirements that apply at waiver termination).
Implementation .............................................................
License required (reference to § 35.11(c)) ...................
License required (authorize medical use of 11e.(3)
materials by Government agencies and Federally
recognized Indian Tribes while applying for license).
License required (authorize medical use of 11e.(3)
materials by all other persons while applying for license).
License amendments (authorize medical use of
11e.(3) materials by Government agencies and
Federally recognized Indian Tribes while applying
for amendment).
License amendments (authorize medical use of
11e.(3) materials by all other licensees while applying for amendment).
License amendments (grandfather physicians and
pharmacists that used 11e.(3) material).
License amendments (clarify amendment need) .........
Notifications (using notification to allow continued operation for certain 11e.(3) material).
Exemptions regarding Type A specific licenses of
broad scope (clarify the exemption).
Training for experienced Radiation Safety Officer, teletherapy or medical physicist, authorized user, and
nuclear pharmacist (grandfather RSO, AMP, ANP,
and AU who used only 11e.(3) material).
Determination of dosages of unsealed byproduct material for medical use (recognize State licenses and
State requirements).
Determination of dosages of unsealed byproduct material for medical use (recognize State licenses of
PET facilities).
Use of unsealed byproduct material for uptake, dilution, and excretion studies for which a written directive is not required (allow use of PET radionuclides).
Use of unsealed byproduct material for imaging and
localization studies for which a written directive is
not required (allow use of PET radionuclides).
Permissible molybdenum-99 concentrations (add
strontium-82 & strontium-85).
Permissible molybdenum-99 concentrations (add
strontium-82 & strontium-85.
Frm 00056
Fmt 4701
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E:\FR\FM\01OCR2.SGM
01OCR2
New
.....................
D
B ..................
B
B ..................
B ..................
B ..................
B
B
B
B ..................
B
B ..................
B
D .................
D
.....................
.....................
D
H&S
.....................
D
.....................
C .................
.....................
D
C
NRC
.....................
D
.....................
NRC
.....................
D
D .................
D
D .................
D .................
D
D
D .................
D
.....................
D
H&S .............
H&S
.....................
H&S
H&S .............
H&S
H&S .............
H&S
H&S .............
H&S
.....................
D
55919
Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules and Regulations
COMPATIBILITY TABLE—Continued
Compatibility
Section
Change
Subject
Existing
35.204(d) ............................
35.300(a) and (b) ...............
Redesignated ....................
Amend ...............................
35.2204 ..............................
Amend ...............................
50.2 ....................................
Amend ...............................
61.2 ....................................
62.2 ....................................
Amend ...............................
Amend ...............................
72.3 ....................................
Amend ...............................
110.2
110.2
110.2
150.3
..................................
..................................
..................................
..................................
Add ....................................
Add ....................................
Add ....................................
Amend ...............................
150.3 ..................................
Add ....................................
Permissible molybdenum-99 concentrations ................
Use of unsealed byproduct material for which a written directive is required (allow use of PET radionuclides).
Records of molybdenum-99 concentrations (add
strontium-82 & strontium-85).
Definition: Byproduct material (add 11e.(3) & 11e.(4)
material).
Definition: Waste (clarify 11e.(3) & 11e.(4) material) ...
Definition: Low-level radioactive waste (clarify 11e.(3)
& 11e.(4) material).
Definition: Byproduct material (add 11e.(3) & 11e.(4)
material).
Definition: Accelerator-produced radioactive material ..
Definition: Discrete source ...........................................
Definition: Particle accelerator ......................................
Definition: Byproduct material (add 11e.(3) & 11e.(4)
material).
Definition: Discrete source ...........................................
New
D ..................
H&S .............
D
H&S
D .................
D
NRC ............
NRC
B ..................
NRC ............
B
NRC
NRC ............
NRC
.....................
.....................
.....................
A ..................
NRC
NRC
NRC
H&S
.....................
H&S
10 CFR Parts 170 and 171 address areas that generally are applicable only to the NRC’s regulatory program; therefore, no compatibility designation is assigned.
VII. Voluntary Consensus Standards
The National Technology Transfer
and Advancement Act of 1995 (Pub. L.
104–113) requires that Federal agencies
use technical standards that are
developed or adopted by voluntary
consensus standards bodies unless the
use of such a standard is inconsistent
with applicable law or otherwise
impractical. In this final rule, the NRC
is assuming regulation of certain
discrete sources of naturally occurring
radioactive material and acceleratorproduced radioactive material in
addition to those byproduct materials
already under the NRC’s jurisdiction.
This action does not constitute the
establishment of a standard that
establishes generally applicable
requirements.
The EPAct requires that the NRC use
model State standards to the maximum
extent practicable in developing and
issuing regulations for the newly
expanded definition of Byproduct
material. In developing this final rule,
the NRC has consulted with Agreement
and non-Agreement States about their
regulations. To the maximum extent
practicable, the NRC has incorporated
the CRCPD’s SSRs into this final rule.
jlentini on PROD1PC65 with RULES2
VIII. Environmental Assessment and
Finding of No Significant
Environmental Impact: Availability
The Commission has determined
under the National Environmental
Policy Act of 1969, as amended, and the
Commission’s regulations in Subpart A
of 10 CFR part 51, that this rule is not
a major Federal action significantly
VerDate Aug<31>2005
18:25 Sep 28, 2007
Jkt 214001
affecting the quality of the human
environment and therefore an
environmental impact statement is not
required. The Commission has prepared
an environmental assessment for this
final rule.
Amendments to the NRC’s regulations
incorporate new materials into the
NRC’s byproduct material regulatory
program and establish new program
elements where needed. Before the
EPAct, the regulation of NARM, other
than source material, was left primarily
to the individual States. Although
efforts were made by several States to
provide a uniform regulatory
environment, particularly for
accelerator-produced radioactive
material, there is currently no
nationwide consistency to the
regulation of NARM. The amendments
to the NRC’s regulations will provide a
uniform regulatory environment for the
acquisition, possession, use, transfer,
and disposal of NARM. This uniform
regulatory environment has been
developed in cooperation with the
States, using model State standards in
existence to the maximum extent
practicable. Because the approach for
developing the generic NRC
requirements started with the existing
generic requirements for acceleratorproduced radioactive material that had
already been developed by the States for
the SSRs, little change is expected to the
byproduct material regulatory programs
already in place for the Agreement
States. Consequently, for Agreement
States, the primary foreseeable impact of
the regulatory changes applicable to
accelerator-produced radioactive
PO 00000
Frm 00057
Fmt 4701
Sfmt 4700
material is that the regulations will be
uniformly applied by all Agreement
States. Therefore, for the regulation of
accelerator-produced radioactive
material by the Agreement States, these
amendments to the NRC’s regulations
are not expected to have any adverse
environmental impacts.
In non-Agreement States, these
amendments to the NRC’s regulations
generally impose more restrictive
requirements on the acquisition,
possession, use, transfer, and disposal of
accelerator-produced radioactive
materials. In situations where the new
NRC requirements are more restrictive
than those already imposed by
individual States’ existing regulations,
the result will likely be a positive
impact on the environment. In
situations where the NRC’s
requirements are less restrictive than the
individual State’s regulations, it is likely
that the licensee will, in large part,
continue with its current practices, and
no substantial impact on the
environment is anticipated. Therefore, it
is expected that the overall
environmental impacts of the regulation
of accelerator-produced radioactive
material in non-Agreement States will
be positive.
The effects of the amendments to the
NRC’s regulations applicable to discrete
sources of radium-226 and discrete
sources of other naturally occurring
radioactive material will be greater for
the non-Agreement States than for the
Agreement States because certain nonAgreement States do not have a
regulatory program addressing this
material. The imposition of regulations
E:\FR\FM\01OCR2.SGM
01OCR2
55920
Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules and Regulations
jlentini on PROD1PC65 with RULES2
on the acquisition, possession, use,
transfer, and disposal of these discrete
sources of naturally occurring
radioactive material will provide greater
assurance that these activities are
performed in a manner that is expected
to be less harmful to the environment
than would be assured without these
regulations. Therefore, the effect of the
NRC’s regulations applicable to discrete
sources of naturally occurring
radioactive material is anticipated to be
beneficial to the environment, and it is
expected that the overall environmental
impacts will be positive.
Therefore, the determination of the
environmental assessment is that there
will be no significant impact to the
human environment from this action.
The NRC sent a copy of the
environmental assessment and the
proposed rule to every State Liaison
Officer and requested their comments
on the environmental assessment. No
significant comments were received that
changed this conclusion.
IX. Paperwork Reduction Act
Statement
This final rule amends information
collection requirements contained in 10
CFR Parts 19, 20, 30, 31, 32, and 35 that
are subject to the Paperwork Reduction
Act of 1995 (44 U.S.C. 3501 et seq.).
These requirements were approved by
the Office of Management and Budget,
approval numbers 3150–0044, –0014,
–0017, –0016, –0001, –0010, and –0120.
The changes to 10 CFR Parts 33, 50, 61,
62, 72, 110, 150, 170, and 171 do not
contain new or amended information
collection requirements.
The burden to the public for these
information collections is estimated to
average 24 hours per response,
including the time for reviewing
instructions, searching existing data
sources, gathering and maintaining the
data needed, and completing and
reviewing the information collection.
Send comments on any aspect of these
information collections, including
suggestions for reducing the burden, to
the Records and FOIA/Privacy Services
Branch (T–5 F52), U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, or by Internet
electronic mail to
INFOCOLLECTS@NRC.GOV; and to the
Desk Officer, Office of Information and
Regulatory Affairs, NEOB–10202 (3150–
0044, –0014, –0017, –0016, –0001,
–0010, and –0120, Office of
Management and Budget, Washington,
DC 20503.
Public Protection Notification
The NRC may not conduct or sponsor,
and a person is not required to respond
VerDate Aug<31>2005
18:25 Sep 28, 2007
Jkt 214001
to, a request for information or an
information collection requirement
unless the requesting document
displays a currently valid OMB control
number.
X. Regulatory Analysis
The Commission has prepared a
regulatory analysis on this regulation.
The regulatory analysis examines the
costs and benefits of the alternatives
considered by the Commission.
The regulatory analysis is available
for inspection in the NRC Public
Document Room, 11555 Rockville Pike,
Rockville, MD, and may be downloaded
from the rule forum Web site at https://
ruleforum.llnl.gov. Single copies of the
regulatory analysis are available from
Catherine R. Mattsen, Office of Federal
and State Materials and Environmental
Management Programs, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone (301) 415–
6264, e-mail crm@nrc.gov.
XI. Regulatory Flexibility Certification
In accordance with the Regulatory
Flexibility Act of 1980 (5 U.S.C. 605(b)),
the Commission certifies that this rule
will not have a significant economic
impact on a substantial number of small
entities. The majority of companies that
own these businesses do not fall within
the scope of the definition of ‘‘small
entities’’ set forth in the Regulatory
Flexibility Act or the Small Business
Size Standards set out in regulations
issued by the Small Business
Administration at 13 CFR part 121.
Section 651(e) of the EPAct expanded
the definition of Byproduct material in
Section 11e. of the AEA to include any
discrete source of radium-226, any
material made radioactive by use of a
particle accelerator, and any discrete
source of naturally occurring radioactive
material that would pose a similar threat
to the public health and safety or the
common defense and security as a
discrete source of radium-226 that is
extracted or converted after extraction
for use in a commercial, medical, or
research activity. This rulemaking
amends the NRC’s regulations to
include this newly defined byproduct
material. This amendment will
potentially affect large numbers of
individuals, businesses, or licensees
engaged in activities involving discrete
radium-226 sources or acceleratorproduced radioactive material used for
commercial, medical, or research
activities. Many individuals, businesses,
or licensees qualify as small business
entities as defined by 10 CFR 2.810.
However, the rule is not expected to
have a significant economic impact on
these individuals, businesses, or
PO 00000
Frm 00058
Fmt 4701
Sfmt 4700
licensees because the NRC is using the
existing regulatory framework to
regulate these materials and is allowing
sufficient time for individuals,
businesses, and licensees to implement
the requirements for this radioactive
material. Based on the regulatory
analysis, the NRC believes that the
selected alternative reflected in the
amendment is protective of public
health and safety and is not overly
burdensome to accomplish the NRC’s
regulatory objective. The NRC also notes
that several Agreement States have
imposed similar requirements on their
licensees either by rule, order, or license
condition.
XII. Backfit Analysis
The NRC has determined that the
backfit rule (10 CFR 50.109, 70.76,
72.62, or 76.76) does not apply to this
rule because this amendment does not
involve any provisions that would
impose backfits as defined in 10 CFR
Chapter 1. Therefore, a backfit analysis
is not required.
XIII. Congressional Review Act
In accordance with the Congressional
Review Act of 1996, the NRC has
determined that this action is not a
major rule and has verified this
determination with the Office of
Information and Regulatory Affairs of
OMB.
List of Subjects
10 CFR Part 20
Byproduct material, Criminal
penalties, Licensed material, Nuclear
materials, Nuclear power plants and
reactors, Occupational safety and
health, Packaging and containers,
Radiation protection, Reporting and
recordkeeping requirements, Source
material, Special nuclear material,
Waste treatment and disposal.
10 CFR Part 30
Byproduct material, Criminal
penalties, Government contracts,
Intergovernmental relations, Isotopes,
Nuclear materials, Radiation protection,
Reporting and recordkeeping
requirements.
10 CFR Part 31
Byproduct material, Criminal
penalties, Labeling, Nuclear materials,
Packaging and containers, Radiation
protection, Reporting and recordkeeping
requirements, Scientific equipment.
10 CFR Part 32
Byproduct material, Criminal
penalties, Labeling, Nuclear materials,
Radiation protection, Reporting and
recordkeeping requirements.
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10 CFR Part 33
Byproduct material, Criminal
penalties, Nuclear materials, Radiation
protection, Reporting and recordkeeping
requirements.
10 CFR Part 35
Byproduct material, Criminal
penalties, Drugs, Health facilities,
Health professions, Medical devices,
Nuclear materials, Occupational safety
and health, Radiation protection,
Reporting and recordkeeping
requirements.
10 CFR Part 50
Antitrust, Classified information,
Criminal penalties, Fire protection,
Intergovernmental relations, Nuclear
power plants and reactors, Radiation
protection, Reactor siting criteria,
Reporting and recordkeeping
requirements.
10 CFR Part 61
Criminal penalties, Low-level waste,
Nuclear materials, Reporting and
recordkeeping requirements, Waste
treatment and disposal.
10 CFR Part 62
Administrative practice and
procedure, Denial of access, Emergency
access to low-level waste disposal, Lowlevel radioactive waste, Low-level
radioactive waste treatment and
disposal, Low-level waste policy
amendments act of 1985, Nuclear
materials, Reporting and recordkeeping
requirements.
10 CFR Part 72
Administrative practice and
procedure, Criminal penalties,
Manpower training programs, Nuclear
materials, Occupational safety and
health, Penalties, Radiation protection,
Reporting and recordkeeping
requirements, Security measures, Spent
fuel, Whistleblowing.
10 CFR Part 110
Administrative practice and
procedure, Classified information,
Criminal penalties, Export, Import,
Intergovernmental relations, Nuclear
materials, Nuclear power plants and
reactors, Reporting and recordkeeping
requirements, Scientific equipment.
jlentini on PROD1PC65 with RULES2
10 CFR Part 150
Criminal penalties, Hazardous
materials transportation,
Intergovernmental relations, Nuclear
materials, Reporting and recordkeeping
requirements, Security measures,
Source material, Special nuclear
material.
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10 CFR Part 170
Byproduct material, Import and
export licenses, Intergovernmental
relations, Nonpayment penalties,
Nuclear materials, Nuclear power plants
and reactors, Source material, Special
nuclear material.
10 CFR Part 171
Annual charges, Byproduct material,
Holders of certificates, registrations,
approvals, Intergovernmental relations,
Nonpayment penalties, Nuclear
materials, Nuclear power plants and
reactors, Source material, Special
nuclear material.
I For the reasons set out in the
preamble and under the authority of the
Atomic Energy Act of 1954, as amended;
the Energy Reorganization Act of 1974,
as amended; and 5 U.S.C. 552 and 553;
the NRC is adopting the following
amendments to 10 CFR parts 20, 30, 31,
32, 33, 35, 50, 61, 62, 72, 110, 150, 170,
and 171.
PART 20—STANDARDS FOR
PROTECTION AGAINST RADIATION
1. The authority citation for part 20 is
revised to read as follows:
I
Authority: Secs. 53, 63, 65, 81, 103, 104,
161, 182, 186, 68 Stat. 930, 933, 935, 936,
937, 948, 953, 955, as amended, sec. 1701,
106 Stat. 2951, 2952, 2953 (42 U.S.C. 2073,
2093, 2095, 2111, 2133, 2134, 2201, 2232,
2236, 2297f), secs. 201, as amended, 202,
206, 88 Stat. 1242, as amended, 1244, 1246
(42 U.S.C. 5841, 5842, 5846); sec. 1704, 112
Stat. 2750 (44 U.S.C. 3504 note); sec. 651(e),
Pub. L. 109–58, 119 Stat. 806–810 (42 U.S.C.
2014, 2021, 2021b, 2111).
I 2. In § 20.1003, the definition of
Byproduct material is revised, and
definitions of Accelerator-produced
radioactive material, Discrete source,
Particle accelerator, and Waste are
added alphabetically to read as follows:
§ 20.1003
Definitions.
*
*
*
*
*
Accelerator-produced radioactive
material means any material made
radioactive by a particle accelerator.
*
*
*
*
*
Byproduct material means—
(1) Any radioactive material (except
special nuclear material) yielded in, or
made radioactive by, exposure to the
radiation incident to the process of
producing or using special nuclear
material;
(2) The tailings or wastes produced by
the extraction or concentration of
uranium or thorium from ore processed
primarily for its source material content,
including discrete surface wastes
resulting from uranium solution
extraction processes. Underground ore
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55921
bodies depleted by these solution
extraction operations do not constitute
‘‘byproduct material’’ within this
definition;
(3)(i) Any discrete source of radium226 that is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; or
(ii) Any material that—
(A) Has been made radioactive by use
of a particle accelerator; and
(B) Is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; and
(4) Any discrete source of naturally
occurring radioactive material, other
than source material, that—
(i) The Commission, in consultation
with the Administrator of the
Environmental Protection Agency, the
Secretary of Energy, the Secretary of
Homeland Security, and the head of any
other appropriate Federal agency,
determines would pose a threat similar
to the threat posed by a discrete source
of radium-226 to the public health and
safety or the common defense and
security; and
(ii) Before, on, or after August 8, 2005,
is extracted or converted after extraction
for use in a commercial, medical, or
research activity.
*
*
*
*
*
Discrete source means a radionuclide
that has been processed so that its
concentration within a material has
been purposely increased for use for
commercial, medical, or research
activities.
*
*
*
*
*
Particle accelerator means any
machine capable of accelerating
electrons, protons, deuterons, or other
charged particles in a vacuum and of
discharging the resultant particulate or
other radiation into a medium at
energies usually in excess of 1
megaelectron volt. For purposes of this
definition, ‘‘accelerator’’ is an
equivalent term.
*
*
*
*
*
Waste means those low-level
radioactive wastes containing source,
special nuclear, or byproduct material
that are acceptable for disposal in a land
disposal facility. For the purposes of
this definition, low-level radioactive
waste means radioactive waste not
classified as high-level radioactive
waste, transuranic waste, spent nuclear
fuel, or byproduct material as defined in
paragraphs (2), (3), and (4) of the
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definition of Byproduct material set
forth in this section.
*
*
*
*
*
I 3. In § 20.1009, paragraph (b) is
revised to read as follows:
I 5. In § 20.2006, paragraph (e) is added
to read as follows:
§ 20.2006 Transfer for disposal and
manifests.
*
§ 20.1009 Information collection
requirements: OMB approval.
(b) The approved information
collection requirements contained in
this part appear in §§20.1003, 20.1101,
20.1202, 20.1203, 20.1204, 20.1206,
20.1208, 20.1301, 20.1302, 20.1403,
20.1404, 20.1406, 20.1501, 20.1601,
20.1703, 20.1901, 20.1904, 20.1905,
20.1906, 20.2002, 20.2004, 20.2005,
20.2006, 20.2008, 20.2102, 20.2103,
20.2104, 20.2105, 20.2106, 20.2107,
20.2108, 20.2110, 20.2201, 20.2202,
20.2203, 20.2204, 20.2205, 20.2206,
20.2207, 20.2301, and appendix G to
this part.
*
*
*
*
*
I 4. In § 20.2001, paragraph (a)(4) is
revised to read as follows:
§ 20.2001 General requirements.
(a) * * *
(4) As authorized under §§20.2002,
20.2003, 20.2004, 20.2005, or 20.2008.
*
*
*
*
*
*
*
*
*
(e) Any licensee shipping byproduct
material as defined in paragraphs (3)
and (4) of the definition of Byproduct
material set forth in § 20.1003 intended
for ultimate disposal at a land disposal
facility licensed under part 61 of this
chapter must document the information
required on the NRC’s Uniform LowLevel Radioactive Waste Manifest and
transfer this recorded manifest
information to the intended consignee
in accordance with appendix G to this
part.
I 6. Section 20.2008 is added to Subpart
K—Waste Disposal—to read as follows:
§ 20.2008
material.
Disposal of certain byproduct
(a) Licensed material as defined in
paragraphs (3) and (4) of the definition
of Byproduct material set forth in
§20.1003 may be disposed of in
accordance with part 61 of this chapter,
even though it is not defined as lowlevel radioactive waste. Therefore, any
licensed byproduct material being
disposed of at a facility, or transferred
for ultimate disposal at a facility
licensed under part 61 of this chapter,
must meet the requirements of
§20.2006.
(b) A licensee may dispose of
byproduct material, as defined in
paragraphs (3) and (4) of the definition
of Byproduct material set forth in §
20.1003, at a disposal facility authorized
to dispose of such material in
accordance with any Federal or State
solid or hazardous waste law, including
the Solid Waste Disposal Act, as
authorized under the Energy Policy Act
of 2005.
7. In Appendix B to part 20, the List
of Elements table is amended by adding
Nitrogen and Oxygen in alphabetical
order, and page 1 of Tables 1, 2, and 3
following the List of Elements is revised
to read as follows:
I
Appendix B to Part 20—Annual Limits
on Intake (ALIs) and Derived Air
Concentrations (DACs) of
Radionuclides for Occupational
Exposure; Effluent Concentrations;
Concentrations for Release to Sewerage
*
*
*
*
*
LIST OF ELEMENTS
Atomic
Name
Symbol
No.
*
*
*
Nitrogen .......................................................................................
*
*
*
N ................................................................................................
*
*
*
*
Oxygen ........................................................................................
*
*
*
O ................................................................................................
*
*
*
*
*
*
*
*
*
*
*
*
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*
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*
*
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*
*
*
Footnotes
1 ‘‘Submersion’’ means that values given
are for submersion in a hemispherical semiinfinite cloud of airborne material.
2 These radionuclides have radiological
half-lives of less than 2 hours. The total
effective dose equivalent received during
operations with these radionuclides might
include a significant contribution from
external exposure. The DAC values for all
radionuclides, other than those designated
Class ‘‘Submersion,’’ are based upon the
committed effective dose equivalent due to
the intake of the radionuclide into the body
and do not include potentially significant
contributions to dose equivalent from
external exposures. The licensee may
substitute 1E–7 µCi/ml for the listed DAC to
account for the submersion dose
prospectively, but should use individual
monitoring devices or other radiation
measuring instruments that measure external
exposure to demonstrate compliance with the
limits. (See § 20.1203.)
*
*
*
*
*
PART 30—RULES OF GENERAL
APPLICABILITY TO DOMESTIC
LICENSING OF BYPRODUCT
MATERIAL
8. The authority citation for part 30 is
revised to read as follows:
I
Authority: Secs. 81, 82, 161, 182, 183, 186,
68 Stat. 935, 948, 953, 954, 955, as amended,
sec. 234, 83 Stat. 444, as amended (42 U.S.C.
2111, 2112, 2201, 2232, 2233, 2236, 2282);
secs. 201, as amended, 202, 206, 88 Stat.
1242, as amended, 1244, 1246 (42 U.S.C.
5841, 5842, 5846); sec. 1704, 112 Stat. 2750
(44 U.S.C. 3504 note); sec. 651(e), Pub. L.
109–58, 119 Stat. 806–810 (42 U.S.C. 2014,
2021, 2021b, 2111).
Section 30.7 also issued under Pub. L. 95–
601, sec. 10, 92 Stat. 2951 as amended by
Pub. L. 102–486, sec. 2902, 106 Stat. 3123 (42
U.S.C. 5851). Section 30.34(b) also issued
under sec. 184, 68 Stat. 954, as amended (42
U.S.C. 2234). Section 30.61 also issued under
sec. 187, 68 Stat. 955 (42 U.S.C. 2237).
9. Section 30.3 is revised to read as
follows:
I
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§ 30.3
Activities requiring license.
(a) Except as provided in paragraphs
(b)(2), (b)(3), (c)(2), and (c)(3) of this
section and for persons exempt as
provided in this part and part 150 of
this chapter, no person shall
manufacture, produce, transfer, receive,
acquire, own, possess, or use byproduct
material except as authorized in a
specific or general license issued in
accordance with the regulations in this
chapter.
(b)(1) The requirements, including
provisions that are specific to licensees,
in this part and parts 19, 20, 21, and 71
of this chapter, as well as the additional
requirements for specific broad scope,
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industrial radiography, irradiator, or
well logging uses in 10 CFR parts 33, 34,
36, or 39, respectively, shall apply to
Government agencies or Federally
recognized Indian Tribes on November
30, 2007, when conducting activities
under the authority provided by
paragraphs (b)(2) and (b)(3) of this
section.
(2) A specifically licensed
Government agency or Federally
recognized Indian Tribe that possesses
and uses accelerator-produced
radioactive material or discrete sources
of radium-226 for which a license
amendment is required to authorize the
activities in paragraph (a) of this
section, may continue to use these
materials for uses permitted under this
part until the date of the NRC’s final
licensing determination, provided that
the licensee submits an amendment
application on or before June 2, 2008.
(3) A Government agency or Federally
recognized Indian Tribe that possesses
and uses accelerator-produced
radioactive material or discrete sources
of radium-226 for which a specific
license is required in paragraph (a) of
this section, may continue to use such
material for uses permitted under this
part until the date of the NRC’s final
licensing determination provided that
the agency or Indian Tribe submits an
application for a license authorizing
activities involving these materials on or
before December 1, 2008.
(c)(1) The requirements, including
provisions that are specific to licensees
in this part and parts 19, 20, 21, and 71
of this chapter, as well as the additional
requirements for specific broad scope,
industrial radiography, irradiator, or
well logging uses in 10 CFR parts 33, 34,
36, or 39, respectively, shall apply to all
persons, other than those included in
paragraph (b)(1) of this section, on
August 8, 2009, or earlier as noticed by
the NRC, when conducting activities
under the authority provided by
paragraphs (c)(2) and (c)(3) of this
section.
(2) Except as provided in paragraph
(b)(2) of this section, all other licensees,
who possess and use acceleratorproduced radioactive material or
discrete sources of radium-226 for
which a license amendment is required
to authorize the activities in paragraph
(a) of this section, may continue to use
these materials for uses permitted under
this part until the date of the NRC’s final
licensing determination, provided that
the person submits an amendment
application within 6 months from the
waiver expiration date of August 7, 2009
or within 6 months from the date of an
earlier termination of the waiver as
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noticed by the NRC, whichever date is
earlier.
(3) Except as provided in paragraph
(b)(3) of this section, all other persons,
who possess and use acceleratorproduced radioactive material or
discrete sources of radium-226 for
which a specific license is required in
paragraph (a) of this section, may
continue to use such material for uses
permitted under this part until the date
of the NRC’s final licensing
determination, provided that the person
submits a license application within 12
months from the waiver expiration date
of August 7, 2009 or within 12 months
from the date of an earlier termination
of the waiver as noticed by the NRC,
whichever date is earlier.
(d) If a person or licensee is required
to file an application for a license or
amendment in accordance with
paragraphs (b)(2), (b)(3), (c)(2), and (c)(3)
of this section, but does not file for the
license or amendment within the
required time, the authority provided by
paragraphs (b)(2), (b)(3), (c)(2), and (c)(3)
of this section to receive or use the
accelerator-produced radioactive
material or discrete sources of radium226 shall expire with respect to the
person’s or licensee’s authority to
receive and use such byproduct
material. This authority shall not expire
with respect to the responsibility of the
person or licensee regarding the
possession of such byproduct material,
the decommissioning (including
financial assurance) of facilities, or the
disposal of such byproduct material.
I 10. In § 30.4, the definition of
Byproduct material is revised, and the
definitions of Accelerator-produced
radioactive material, Consortium,
Cyclotron, Discrete source, and Particle
accelerator are added alphabetically to
read as follows:
§ 30.4
Definitions.
*
*
*
*
*
Accelerator-produced radioactive
material means any material made
radioactive by a particle accelerator.
*
*
*
*
*
Byproduct material means—
(1) Any radioactive material (except
special nuclear material) yielded in, or
made radioactive by, exposure to the
radiation incident to the process of
producing or using special nuclear
material;
(2)(i) Any discrete source of radium226 that is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; or
(ii) Any material that—
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(A) Has been made radioactive by use
of a particle accelerator; and
(B) Is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; and
(3) Any discrete source of naturally
occurring radioactive material, other
than source material, that—
(i) The Commission, in consultation
with the Administrator of the
Environmental Protection Agency, the
Secretary of Energy, the Secretary of
Homeland Security, and the head of any
other appropriate Federal agency,
determines would pose a threat similar
to the threat posed by a discrete source
of radium-226 to the public health and
safety or the common defense and
security; and
(ii) Before, on, or after August 8, 2005,
is extracted or converted after extraction
for use in a commercial, medical, or
research activity.
*
*
*
*
*
Consortium means an association of
medical use licensees and a PET
radionuclide production facility in the
same geographical area that jointly own
or share in the operation and
maintenance cost of the PET
radionuclide production facility that
produces PET radionuclides for use in
producing radioactive drugs within the
consortium for noncommercial
distributions among its associated
members for medical use. The PET
radionuclide production facility within
the consortium must be located at an
educational institution or a Federal
facility or a medical facility.
*
*
*
*
*
Cyclotron means a particle accelerator
in which the charged particles travel in
an outward spiral or circular path. A
cyclotron accelerates charged particles
at energies usually in excess of 10
megaelectron volts and is commonly
used for production of short half-life
radionuclides for medical use.
*
*
*
*
*
Discrete source means a radionuclide
that has been processed so that its
concentration within a material has
been purposely increased for use for
commercial, medical, or research
activities.
*
*
*
*
*
Particle accelerator means any
machine capable of accelerating
electrons, protons, deuterons, or other
charged particles in a vacuum and of
discharging the resultant particulate or
other radiation into a medium at
energies usually in excess of 1
megaelectron volt. For purposes of this
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definition, accelerator is an equivalent
term.
*
*
*
*
*
I 11. In § 30.15, paragraph (a)(1)(viii) is
added to read as follows:
§ 30.15 Certain items containing
byproduct material.
(a) * * *
(1) * * *
(viii) 0.037 megabecquerel (1
microcurie) of radium-226 per timepiece
in intact timepieces manufactured prior
to November 30, 2007.
*
*
*
*
*
I 12. In § 30.18, paragraph (b) is revised
to read as follows:
§ 30.18
Exempt quantities.
*
*
*
*
*
(b) Any person, who possesses
byproduct material received or acquired
before September 25, 1971, under the
general license then provided in § 31.4
of this chapter or similar general license
of a State, is exempt from the
requirements for a license set forth in
section 81 of the Act and from the
regulations in parts 30 through 34, 36
and 39 of this chapter to the extent that
this person possesses, uses, transfers, or
owns byproduct material.
*
*
*
*
*
I 13. In § 30.20, paragraph (a) is revised
to read as follows:
§ 30.20 Gas and aerosol detectors
containing byproduct material.
(a) Except for persons who
manufacture, process, produce, or
initially transfer for sale or distribution
gas and aerosol detectors containing
byproduct material, any person is
exempt from the requirements for a
license set forth in section 81 of the Act
and from the regulations in parts 19, 20,
and 30 through 36, and 39 of this
chapter to the extent that the person
receives, possesses, uses, transfers,
owns, or acquires byproduct material in
gas and aerosol detectors designed to
protect life or property from fires and
airborne hazards, and manufactured,
processed, produced, or initially
transferred in accordance with a specific
license issued under § 32.26 of this
chapter, which license authorizes the
initial transfer of the product for use
under this section. This exemption also
covers gas and aerosol detectors
manufactured or distributed before
November 30, 2007 in accordance with
a specific license issued by a State
under comparable provisions to § 32.26
of this chapter authorizing distribution
to persons exempt from regulatory
requirements.
*
*
*
*
*
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14. In § 30.32, paragraphs (g)(1) and
(g)(2) are revised and paragraphs (g)(3)
and (j) are added to read as follows:
I
§ 30.32
Application for specific licenses.
*
*
*
*
*
(g) * * *
(1) Identify the source or device by
manufacturer and model number as
registered with the Commission under
§ 32.210 of this chapter, with an
Agreement State, or for a source or a
device containing radium-226 or
accelerator-produced radioactive
material with a State under provisions
comparable to § 32.210 of this chapter;
or
(2) Contain the information identified
in § 32.210(c) of this chapter; or
(3) For sources or devices containing
naturally occurring or acceleratorproduced radioactive material
manufactured prior to November 30,
2007 that are not registered with the
Commission under § 32.210 of this
chapter or with an Agreement State, and
for which the applicant is unable to
provide all categories of information
specified in § 32.210(c) of this chapter,
the applicant must provide:
(i) All available information identified
in § 32.210(c) of this chapter concerning
the source, and, if applicable, the
device; and
(ii) Sufficient additional information
to demonstrate that there is reasonable
assurance that the radiation safety
properties of the source or device are
adequate to protect health and minimize
danger to life and property. Such
information must include a description
of the source or device, a description of
radiation safety features, the intended
use and associated operating
experience, and the results of a recent
leak test.
*
*
*
*
*
(j) An application from a medical
facility, educational institution, or
Federal facility to produce Positron
Emission Tomography (PET) radioactive
drugs for noncommercial transfer to
licensees in its consortium authorized
for medical use under part 35 of this
chapter or equivalent Agreement State
requirements shall include:
(1) A request for authorization for the
production of PET radionuclides or
evidence of an existing license issued
under part 30 of this chapter or
Agreement State requirements for a PET
radionuclide production facility within
its consortium from which it receives
PET radionuclides.
(2) Evidence that the applicant is
qualified to produce radioactive drugs
for medical use by meeting one of the
criteria in § 32.72(a)(2) of this chapter.
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(3) Identification of individual(s)
authorized to prepare the PET
radioactive drugs if the applicant is a
pharmacy, and documentation that each
individual meets the requirements of an
authorized nuclear pharmacist as
specified in § 32.72(b)(2) of this chapter.
(4) Information identified in
§ 32.72(a)(3) of this chapter on the PET
drugs to be noncommercially transferred
to members of its consortium.
I 15. In § 30.34, paragraph (g) is revised
and paragraph (j) is added to read as
follows:
§ 30.34
Terms and conditions of licenses.
jlentini on PROD1PC65 with RULES2
*
*
*
*
*
(g) Each licensee preparing
technetium-99m radiopharmaceuticals
from molybdenum-99/technetium-99m
generators or rubidium-82 from
strontium-82/rubidium-82 generators
shall test the generator eluates for
molybdenum-99 breakthrough or
strontium-82 and strontium-85
contamination, respectively, in
accordance with § 35.204 of this
chapter. The licensee shall record the
results of each test and retain each
record for 3 years after the record is
made.
*
*
*
*
*
(j)(1) Authorization under § 30.32(j) to
produce Positron Emission Tomography
(PET) radioactive drugs for
noncommercial transfer to medical use
licensees in its consortium does not
relieve the licensee from complying
with applicable FDA, other Federal, and
State requirements governing
radioactive drugs.
(2) Each licensee authorized under
§ 30.32(j) to produce PET radioactive
drugs for noncommercial transfer to
medical use licensees in its consortium
shall:
(i) Satisfy the labeling requirements in
§ 32.72(a)(4) of this chapter for each PET
radioactive drug transport radiation
shield and each syringe, vial, or other
container used to hold a PET radioactive
drug intended for noncommercial
distribution to members of its
consortium.
(ii) Possess and use instrumentation
to measure the radioactivity of the PET
radioactive drugs intended for
noncommercial distribution to members
of its consortium and meet the
procedural, radioactivity measurement,
instrument test, instrument check, and
instrument adjustment requirements in
§ 32.72(c) of this chapter.
(3) A licensee that is a pharmacy
authorized under § 30.32(j) to produce
PET radioactive drugs for
noncommercial transfer to medical use
licensees in its consortium shall require
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18:25 Sep 28, 2007
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that any individual that prepares PET
radioactive drugs shall be:
(i) an authorized nuclear pharmacist
that meets the requirements in
§ 32.72(b)(2) of this chapter, or
(ii) an individual under the
supervision of an authorized nuclear
pharmacist as specified in § 35.27 of this
chapter.
(4) A pharmacy, authorized under
§ 30.32(j) to produce PET radioactive
drugs for noncommercial transfer to
medical use licensees in its consortium
that allows an individual to work as an
authorized nuclear pharmacist, shall
meet the requirements of § 32.72(b)(5) of
this chapter.
16. Section 30.71 is amended by
adding Cesium 129 (Cs 129), Cobalt 57
(Co 57), Gallium 67 (Ga 67), Germanium
68 (Ge 68), Gold 195 (Au 195), Indium
111 (In 111), Iodine 123 (I 123), Iron 52
(Fe 52), Potassium 43 (K 43), Rubidium
81 (Rb 81), Sodium 22 (Na 22), Yttrium
87 (Y 87), and Yttrium 88 (Y 88) in
alphabetical order by element as
follows:
I
§ 30.71
Schedule B.
Byproduct material
Microcuries
*
*
*
Cesium 129 (Cs 129) ...........
*
*
100
*
*
*
Cobalt 57 (Co 57) .................
*
*
100
*
*
*
Gallium 67 (Ga 67) ...............
*
*
100
*
*
*
Germanium 68 (Ge 68) ........
*
*
*
*
*
Gold 195 (Au 195) ................
*
*
*
*
Indium 111 (In 111) ..............
*
*
*
*
Iodine 123 (I 123) .................
*
*
*
*
Iron 52 (Fe 52) .....................
*
*
*
*
Potassium 43 (K 43) .............
*
*
*
*
Rubidium 81 (Rb 81) ............
*
*
*
*
Sodium 22 (Na 22) ...............
*
*
*
*
Yttrium 87 (Y 87) ..................
Yttrium 88 (Y 88) ..................
*
PO 00000
*
*
Frm 00064
*
Fmt 4701
17. Section 30.72 is amended by
adding radium-226 in alphabetical order
to read as follows:
I
§ 30.72 Schedule C—Quantities of
radioactive materials requiring
consideration of the need for an emergency
plan for responding to a release.
Radioactive
material 1
Release
fraction
*
*
Radium-226 ......
*
*
Quantity
(curies)
*
*
100
*
*
0.001
*
*
1For
combinations of radioactive materials,
consideration of the need for an emergency
plan is required if the sum of the ratios of the
quantity of each radioactive material authorized to the quantity listed for that material in
Schedule C exceeds one.
*
*
*
*
*
PART 31—GENERAL DOMESTIC
LICENSES FOR BYPRODUCT
MATERIAL
18. The authority citation for part 31
is revised to read as follows:
I
Authority: Secs. 81, 161, 183, 68 Stat. 935,
948, 954, as amended (42 U.S.C. 2111, 2201,
2233); secs. 201, as amended, 202, 88 Stat.
1242, as amended, 1244 (42 U.S.C. 5841,
5842); sec. 1704, 112 Stat. 2750 (44 U.S.C.
3504 note); sec. 651(e), P. Law 109–58, 119
Stat. 806–810 (42 U.S.C. 2014, 2021, 2021b,
2111).
19. In § 31.4, paragraph (b) is revised
to read as follows:
I
§ 31.4 Information collection
requirements: OMB approval.
*
*
*
*
*
(b) The approved information
collection requirements contained in
*
this part appear in § § 31.5, 31.8, 31.11,
10 and 31.12.
*
*
*
*
*
*
100 I 20. In § 31.5, paragraphs (b)(1)(i),
(b)(1)(ii), and (c)(13)(i) are revised and
*
paragraph (b)(1)(iii) is added to read as
100 follows:
10
*
10
*
10
Sfmt 4700
*
*
*
*
*
(b)(1) * * *
(i) A specific license issued under
10
§ 32.51 of this chapter; or
(ii) An equivalent specific license
*
10 issued by an Agreement State; or
*
*
10
10
*
§ 31.5 Certain detecting, measuring,
gauging, or controlling devices and certain
devices for producing light or an ionized
atmosphere.2
*
2 Persons possessing byproduct material in
devices under a general license in § 31.5 before
January 15, 1975, may continue to possess, use, or
transfer that material in accordance with the
labeling requirements of § 31.5 in effect on January
14, 1975.
E:\FR\FM\01OCR2.SGM
01OCR2
Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules and Regulations
(iii) An equivalent specific license
issued by a State with provisions
comparable to § 32.51 of this chapter.
*
*
*
*
*
(c) * * *
(13)(i) Shall register, in accordance
with paragraphs (c)(13)(ii) and (iii) of
this section, devices containing at least
370 megabecquerels (10 millicuries) of
cesium-137, 3.7 megabecquerels (0.1
millicurie) of strontium-90, 37
megabecquerels (1 millicurie) of cobalt60, 3.7 megabecquerels (0.1 millicurie)
of radium-226, or 37 megabecquerels (1
millicurie) of americium-241 or any
other transuranic (i.e., element with
atomic number greater than uranium
(92)), based on the activity indicated on
the label. Each address for a location of
use, as described under paragraph
(c)(13)(iii)(D) of this section, represents
a separate general licensee and requires
a separate registration and fee.
*
*
*
*
*
I 21. Section 31.8 is revised to read as
follows:
jlentini on PROD1PC65 with RULES2
§ 31.8 Americium-241 and radium-226 in
the form of calibration or reference sources.
(a) A general license is issued to those
persons listed in this section to own,
receive, acquire, possess, use, and
transfer, in accordance with the
provisions of paragraphs (b) and (c) of
this section, americium-241 or radium226 in the form of calibration or
reference sources:
(1) Any person in a non-Agreement
State who holds a specific license
issued under this chapter which
authorizes receipt, possession, use, and
transfer of byproduct material, source
material, or special nuclear material;
and
(2) Any Government agency, as
defined in § 30.4 of this chapter, which
holds a specific license issued under
this chapter which authorizes it to
receive, possess, use, and transfer
byproduct material, source material, or
special nuclear material.
(b) The general license in paragraph
(a) of this section applies only to
calibration or reference sources which
have been manufactured or initially
transferred in accordance with the
specifications contained in a specific
license issued under § 32.57 of this
chapter or in accordance with the
specifications contained in a specific
license issued to the manufacturer by an
Agreement State which authorizes
manufacture of the sources for
distribution to persons generally
licensed by the Agreement State, or in
accordance with a specific license
issued by a State with comparable
provisions to § 32.57.
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18:25 Sep 28, 2007
Jkt 214001
(c) The general license in paragraph
(a) of this section is subject to the
provisions of § § 30.14(d), 30.34 (a) to
(e), and 30.50 to 30.63 of this chapter,
and to the provisions of parts 19, 20,
and 21, of this chapter. In addition,
persons who own, receive, acquire,
possess, use, and transfer one or more
calibration or reference sources under
this general license:
(1) Shall not possess at any one time,
at any one location of storage or use,
more than 0.185 megabecquerel (5
microcuries) of americium-241 or 0.185
megabecquerel (5 microcuries) of
radium-226 in such sources;
(2) Shall not receive, possess, use, or
transfer a source unless the source, or
the storage container, bears a label
which includes the following statement
or a substantially similar statement
which contains the information called
for in the following statement: 1
The receipt, possession, use, and
transfer of this source, Model XX, Serial
No. XX, are subject to a general license
and the regulations of the United States
Nuclear Regulatory Commission or of a
State with which the Commission has
entered into an agreement for the
exercise of regulatory authority. Do not
remove this label.
55927
containing americium-241 or radium226.
(e) This general license does not
authorize the export of calibration or
reference sources containing americium241 or radium-226.
I 22. In § 31.11, paragraph (a)(8) is
added, and paragraphs (c)(1) and (d)(1)
are revised to read as follows:
§ 31.11 General license for use of
byproduct material for certain in vitro
clinical or laboratory testing.
(a) * * *
(8) Cobalt-57, in units not exceeding
0.37 megabecquerel (10 microcuries)
each for use in in vitro clinical or
laboratory tests not involving internal or
external administration of byproduct
material, or the radiation therefrom, to
human beings or animals.
*
*
*
*
*
(c) * * *
(1) The general licensee shall not
possess at any one time, under the
general license in paragraph (a) of this
section, at any one location of storage or
use, a total amount of iodine-125,
iodine-131, selenium-75, cobalt-57 and/
or iron-59 in excess of 7.4
megabecquerels (200 microcuries).
*
*
*
*
*
(d) * * *
CAUTION—RADIOACTIVE
(1) Except as prepackaged units which
MATERIAL—THIS SOURCE
are labeled in accordance with the
CONTAINS AMERICIUM–241 [or
provisions of a specific license issued
RADIUM–226, as appropriate]. DO NOT under the provisions of § 32.71 of this
TOUCH RADIOACTIVE PORTION OF
chapter or in accordance with the
THIS SOURCE.
provisions of a specific license issued
llllllllllllllllll
l by an Agreement State, or before
November 30, 2007, and the provisions
(Name of manufacturer or initial
of a specific license issued by a State
transferor)
with comparable provisions to § 32.71
that authorize manufacture and
(3) Shall not transfer, abandon, or
dispose of a source except by transfer to distribution of iodine-125, iodine-131,
carbon-14, hydrogen-3 (tritium),
a person authorized by a license issued
selenium-75, iron-59, cobalt-57, or Mock
under this chapter or by an Agreement
Iodine-125 for distribution to persons
State to receive the source.
generally licensed by the Agreement
(4) Shall store a source, except when
State or the State with comparable
the source is being used, in a closed
provisions to § 32.71.
container adequately designed and
constructed to contain americium-241
*
*
*
*
*
or radium-226 which might otherwise
§ § 31.12, 31.13, and 31.14 [Redesignated]
escape during storage.
I 23. Sections 31.12, 31.13, and 31.14
(5) Shall not use a source for any
are redesignated as § 31.21, § 31.22, and
purpose other than the calibration of
§ 31.23, respectively, § § 31.13 through
radiation detectors or the
31.20 are reserved, and a new § 31.12 is
standardization of other sources.
added to read as follows:
(d) This general license does not
authorize the manufacture or import of
§ 31.12 General license for certain items
calibration or reference sources
1 Sources
generally licensed under this section
before January 19, 1975, may bear labels authorized
by the regulations in effect on January 1, 1975.
Sources containing radium-226 generally licensed
under this section and manufactured before
November 30, 2007 shall be labeled in accordance
with the applicable State regulations at the time of
manufacture or import.
PO 00000
Frm 00065
Fmt 4701
Sfmt 4700
and self-luminous products containing
radium-226.
(a) A general license is hereby issued
to any person to acquire, receive,
possess, use, or transfer, in accordance
with the provisions of paragraphs (b),
(c), and (d) of this section, radium-226
contained in the following products
E:\FR\FM\01OCR2.SGM
01OCR2
jlentini on PROD1PC65 with RULES2
55928
Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules and Regulations
manufactured prior to November 30,
2007.
(1) Antiquities originally intended for
use by the general public. For the
purposes of this paragraph, antiquities
mean products originally intended for
use by the general public and
distributed in the late 19th and early
20th centuries, such as radium emanator
jars, revigators, radium water jars, radon
generators, refrigerator cards, radium
bath salts, and healing pads.
(2) Intact timepieces containing
greater than 0.037 megabecquerel (1
microcurie), nonintact timepieces, and
timepiece hands and dials no longer
installed in timepieces.
(3) Luminous items installed in air,
marine, or land vehicles.
(4) All other luminous products,
provided that no more than 100 items
are used or stored at the same location
at any one time.
(5) Small radium sources containing
no more than 0.037 megabecquerel (1
microcurie) of radium-226. For the
purposes of this paragraph, ‘‘small
radium sources’’ means discrete survey
instrument check sources, sources
contained in radiation measuring
instruments, sources used in
educational demonstrations (such as
cloud chambers and spinthariscopes),
electron tubes, lightning rods, ionization
sources, static eliminators, or as
designated by the NRC.
(b) Persons who acquire, receive,
possess, use, or transfer byproduct
material under the general license
issued in paragraph (a) of this section
are exempt from the provisions of 10
CFR parts 19, 20, and 21, and § 30.50
and 30.51 of this chapter, to the extent
that the receipt, possession, use, or
transfer of byproduct material is within
the terms of the general license;
provided, however, that this exemption
shall not be deemed to apply to any
such person specifically licensed under
this chapter.
(c) Any person who acquires,
receives, possesses, uses, or transfers
byproduct material in accordance with
the general license in paragraph (a) of
this section:
(1) Shall notify the NRC should there
be any indication of possible damage to
the product so that it appears it could
result in a loss of the radioactive
material. A report containing a brief
description of the event, and the
remedial action taken, must be
furnished to the Director of the Office of
Federal and State Materials and
Environmental Management Programs,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001 within 30
days.
VerDate Aug<31>2005
18:25 Sep 28, 2007
Jkt 214001
(2) Shall not abandon products
containing radium-226. The product,
and any radioactive material from the
product, may only be disposed of
according to § 20.2008 of this chapter or
by transfer to a person authorized by a
specific license to receive the radium226 in the product or as otherwise
approved by the NRC.
(3) Shall not export products
containing radium-226 except in
accordance with part 110 of this
chapter.
(4) Shall dispose of products
containing radium-226 at a disposal
facility authorized to dispose of
radioactive material in accordance with
any Federal or State solid or hazardous
waste law, including the Solid Waste
Disposal Act, as authorized under the
Energy Policy Act of 2005, by transfer to
a person authorized to receive radium226 by a specific license issued under
part 30 of this chapter, or equivalent
regulations of an Agreement State, or as
otherwise approved by the NRC.
(5) Shall respond to written requests
from the NRC to provide information
relating to the general license within 30
calendar days of the date of the request,
or other time specified in the request. If
the general licensee cannot provide the
requested information within the
allotted time, it shall, within that same
time period, request a longer period to
supply the information by providing the
Director of the Office of Federal and
State Materials and Environmental
Management Programs, by an
appropriate method listed in § 30.6(a) of
this chapter, a written justification for
the request.
(d) The general license in paragraph
(a) of this section does not authorize the
manufacture, assembly, disassembly,
repair, or import of products containing
radium-226, except that timepieces may
be disassembled and repaired.
PART 32—SPECIFIC DOMESTIC
LICENSES TO MANUFACTURE OR
TRANSFER CERTAIN ITEMS
CONTAINING BYPRODUCT MATERIAL
24. The authority citation for part 32
is revised to read as follows:
I
Authority: Secs. 81, 161, 182, 183, 68 Stat.
935, 948, 953, 954, as amended (42 U.S.C.
2111, 2201, 2232, 2233); sec. 201, 88 Stat.
1242, as amended (42 U.S.C. 5841); sec. 1704,
112 Stat. 2750 (44 U.S.C. 3504 note); sec.
651(e), Pub. L. 109–58, 119 Stat. 806–810 (42
U.S.C. 2014, 2021, 2021b, 2111).
25. In § 32.1, paragraph (c) is added to
read as follows:
I
§ 32.1
*
PO 00000
Purpose and scope.
*
*
Frm 00066
*
Fmt 4701
(c)(1) The requirements in this part,
including provisions that are specific to
licensees, shall apply to Government
agencies and Federally recognized
Indian Tribes with respect to
accelerator-produced radioactive
material or discrete sources of radium226 on November 30, 2007 except that
the agency or tribe may continue to
manufacture or initially transfer items
containing accelerator-produced
radioactive material or discrete sources
of radium-226 for sale or distribution to
persons exempted from the licensing
requirements of part 30 of this chapter,
and to persons generally licensed under
part 31 of this chapter, and radioactive
drugs and sources and devices to
medical use licensees, until the date of
the NRC’s final licensing determination,
provided that the agency or tribe
submits a new license application for
these activities on or before December 1,
2008 or an amendment application for
these activities on or before June 2,
2008.
(2) The requirements in this part,
including provisions that are specific to
licensees, shall apply to all persons
other than those included in paragraph
(c)(1) of this section with respect to
accelerator-produced radioactive
material or discrete sources of radium226 on August 8, 2009, or earlier as
noticed by the NRC, except that these
persons may continue to manufacture or
initially transfer items containing
accelerator-produced radioactive
material or discrete sources of radium226 for sale or distribution to persons
exempted from the licensing
requirements of part 30 of this chapter,
and to persons generally licensed under
part 31 of this chapter, and to sell or
manufacture radioactive drugs and
sources and devices to medical use
licensees until the date of the NRC’s
final licensing determination, provided
that the person submits a license
application within 12 months from the
waiver expiration date of August 7, 2009
or within 12 months from the date of an
earlier termination of the waiver as
noticed by the NRC, whichever is
earlier; or that the person submits an
amendment request within 6 months
from the waiver expiration date of
August 7, 2009 or within 6 months from
the date of an earlier termination of the
waiver as noticed by the NRC,
whichever date is earlier.
26. In § 32.57, the heading and the
introductory text are revised to read as
follows:
I
*
Sfmt 4700
E:\FR\FM\01OCR2.SGM
01OCR2
Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules and Regulations
§ 32.57 Calibration or reference sources
containing americium-241 or radium-226:
Requirements for license to manufacture or
initially transfer.
An application for a specific license
to manufacture or initially transfer
calibration or reference sources
containing americium-241 or radium226, for distribution to persons
generally licensed under § 31.8 of this
chapter, will be approved if:
*
*
*
*
*
I 27. Section 32.58 is revised to read as
follows:
americium-241 or radium-226 and shall
not be transferred to a general licensee
under § 31.8 of this chapter or
equivalent regulations of an Agreement
State.
I 29. In § 32.71, paragraph (b)(8) is
added, and paragraph (c)(1) is revised to
read as follows:
§ 32.71 Manufacture and distribution of
byproduct material for certain in vitro
clinical or laboratory testing under general
license.
*
*
*
*
(b) * * *
(8) Cobalt-57 in units not exceeding
§ 32.58 Same: Labeling of devices.
0.37 megabecquerel (10 microcuries)
Each person licensed under § 32.57
each.
shall affix to each source, or storage
(c) * * *
container for the source, a label which
(1) Identifying the radioactive
shall contain sufficient information
contents as to chemical form and
relative to safe use and storage of the
radionuclide, and indicating that the
source and shall include the following
amount of radioactivity does not exceed
statement or a substantially similar
0.37 megabecquerel (10 microcuries) of
statement which contains the
iodine-131, iodine-125, selenium-75, or
information called for in the following
carbon-14; 1.85 megabecquerels (50
statement: 1
microcuries) of hydrogen-3 (tritium); or
The receipt, possession, use, and
0.74 megabecquerel (20 microcuries) of
transfer of this source, Model , Serial
iron-59; or Mock Iodine-125 in units not
No., are subject to a general license and
exceeding 1.85 kilobecquerels (0.05
the regulations of the United States
microcurie) of iodine-129 and 0.185
Nuclear Regulatory Commission or of a
kilobecquerel (0.005 microcurie) of
State with which the Commission has
americium-241 each; or cobalt-57 in
entered into an agreement for the
units not exceeding 0.37 megabecquerel
exercise of regulatory authority. Do not
(10 microcuries); and
remove this label.
*
*
*
*
CAUTION-RADIOACTIVE MATERIAL–THIS *
SOURCE CONTAINS AMERICIUM-241 (or
I 30. In § 32.72, paragraphs (a)(2)(i),
RADIUM-226). DO NOT TOUCH
(a)(2)(iii), (a)(2)(iv), (b)(2)(ii), (b)(4), and
RADIOACTIVE PORTION OF THIS SOURCE (b)(5) are revised, and a new paragraph
lllllllllllllllllllll (a)(2)(v) is added to read as follows:
(Name of manufacturer or initial transferor)
28. Section 32.59 is revised to read as
follows:
I
jlentini on PROD1PC65 with RULES2
§ 32.59
Same: Leak testing of each source.
Each person licensed under § 32.57
shall perform a dry wipe test upon each
source containing more than 3.7
kilobecquerels (0.1 microcurie) of
americium-241 or radium-226 before
transferring the source to a general
licensee under § 31.8 of this chapter.
This test shall be performed by wiping
the entire radioactive surface of the
source with a filter paper with the
application of moderate finger pressure.
The radioactivity on the paper shall be
measured by using radiation detection
instrumentation capable of detecting
0.185 kilobecquerel (0.005 microcurie)
of americium-241 or radium-226. If this
test discloses more than 0.185
kilobecquerel (0.005 microcurie) of
radioactive material, the source shall be
deemed to be leaking or losing
1 Sources licensed under § 32.57 before January
19, 1975, may bear labels authorized by the
regulations in effect on January 1, 1975.
VerDate Aug<31>2005
18:25 Sep 28, 2007
Jkt 214001
*
§ 32.72 Manufacture, preparation, or
transfer for commercial distribution of
radioactive drugs containing byproduct
material for medical use under part 35.
(a) * * *
(2) * * *
(i) Registered with the U.S. Food and
Drug Administration (FDA) as the
owner or operator of a drug
establishment that engages in the
manufacture, preparation, propagation,
compounding, or processing of a drug
under 21 CFR 207.20(a);
*
*
*
*
*
(iii) Licensed as a pharmacy by a State
Board of Pharmacy;
(iv) Operating as a nuclear pharmacy
within a Federal medical institution; or
(v) A Positron Emission Tomography
(PET) drug production facility registered
with a State agency.
*
*
*
*
*
(b) * * *
(2) * * *
(ii) This individual meets the
requirements specified in § 35.55(b) and
35.59 of this chapter, and the licensee
has received an approved license
PO 00000
Frm 00067
Fmt 4701
Sfmt 4700
55929
amendment identifying this individual
as an authorized nuclear pharmacist; or
*
*
*
*
*
(4) May designate a pharmacist (as
defined in § 35.2 of this chapter) as an
authorized nuclear pharmacist if:
(i) The individual was a nuclear
pharmacist preparing only radioactive
drugs containing accelerator-produced
radioactive material, and
(ii) The individual practiced at a
pharmacy at a Government agency or
Federally recognized Indian Tribe
before November 30, 2007 or at all other
pharmacies before August 8, 2009, or an
earlier date as noticed by the NRC.
(5) Shall provide to the Commission:
(i) A copy of each individual’s
certification by a specialty board whose
certification process has been
recognized by the Commission or an
Agreement State as specified in
§ 35.55(a) of this chapter with the
written attestation signed by a preceptor
as required by § 35.55(b)(2) of this
chapter; or
(ii) The Commission or Agreement
State license, or
(iii) Commission master materials
licensee permit, or
(iv) The permit issued by a licensee or
Commission master materials permittee
of broad scope or the authorization from
a commercial nuclear pharmacy
authorized to list its own authorized
nuclear pharmacist, or
(v) Documentation that only
accelerator-produced radioactive
materials were used in the practice of
nuclear pharmacy at a Government
agency or Federally recognized Indian
Tribe before November 30, 2007 or at all
other locations of use before August 8,
2009, or an earlier date as noticed by the
NRC; and
(vi) A copy of the State pharmacy
licensure or registration, no later than
30 days after the date that the licensee
allows, under paragraphs (b)(2)(i) and
(b)(2)(iii) of this section, the individual
to work as an authorized nuclear
pharmacist.
*
*
*
*
*
I 31. In § 32.102, the heading and the
introductory paragraph are revised to
read as follows:
§ 32.102 Schedule C—prototype tests for
calibration or reference sources containing
americium-241 or radium-226.
An applicant for a license under
§ 32.57 shall, for any type of source
which is designed to contain more than
0.185 kilobecquerel (0.005 microcurie)
of americium-241 or radium-226,
conduct prototype tests, in the order
listed, on each of five prototypes of the
source, which contains more than 0.185
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PART 33—SPECIFIC DOMESTIC
LICENSES OF BROAD SCOPE FOR
BYPRODUCT MATERIAL
112 Stat. 2750 (44 U.S.C. 3504 note); sec.
651(e), Pub. L. 109–58, 119 Stat. 806–810 (42
U.S.C. 2014, 2021, 2021b, 2111).
I
32. The authority citation for part 33
is revised to read as follows:
I
Authority: Secs. 81, 161, 182, 183, 68 Stat.
935, 948, 953, 954, as amended (42 U.S.C.
2111, 2201, 2232, 2233); sec. 201, 88 Stat.
1242, as amended (42 U.S.C. 5841); sec. 1704,
kilobecquerel (0.005 microcurie) of
americium-241 or radium-226, as
follows:
*
*
*
*
*
§ 33.100
33. Section 33.100 is amended by
adding Beryllium-7, Cobalt-57, Radium226, and Sodium-22 in alphabetical
order to read as follows:
Schedule A.
Byproduct material
Col. I curies
*
*
*
*
*
Beryllium-7 ...........................................................................................................................................................
*
*
*
*
*
*
Cobalt-57 ..............................................................................................................................................................
*
*
*
*
*
*
Radium-226 ..........................................................................................................................................................
*
*
*
*
*
*
Sodium-22 ............................................................................................................................................................
*
*
*
*
*
*
PART 35—MEDICAL USE OF
BYPRODUCT MATERIAL
34. The authority citation for part 35
is revised to read as follows:
I
Authority: Secs. 81, 161, 182, 183, 68 Stat.
935, 948, 953, 954, as amended (42 U.S.C.
2111, 2201, 2232, 2233); sec. 201, 88 Stat.
1242, as amended (42 U.S.C. 5841); sec. 1704,
112 Stat. 2750 (44 U.S.C. 3504 note); sec.
651(e), Pub. L. 109–58, 119 Stat. 806–810 (42
U.S.C. 2014, 2021, 2021b, 2111).
35. In § 35.2, new definitions for
Cyclotron and Positron Emission
Tomography (PET) radionuclide
production facility are added
alphabetically to read as follows:
I
§ 35.2
Definitions.
*
jlentini on PROD1PC65 with RULES2
Col. II curies
*
*
*
*
Cyclotron means a particle accelerator
in which the charged particles travel in
an outward spiral or circular path. A
cyclotron accelerates charged particles
at energies usually in excess of 10
megaelectron volts and is commonly
used for production of short half-life
radionuclides for medical use.
*
*
*
*
*
Positron Emission Tomography (PET)
radionuclide production facility is
defined as a facility operating a
cyclotron or accelerator for the purpose
of producing PET radionuclides.
*
*
*
*
*
I 36. In § 35.10, paragraph (a) is added
to read as follows:
§ 35.10
Implementation.
(a) A Government agency or a
Federally recognized Indian Tribe that
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possesses and uses accelerator-produced
radioactive material or discrete sources
of radium-226 for which a specific
medical use license is required by the
Atomic Energy Act of 1954, as amended,
must comply with the requirements of
this part, including provisions that are
specific to licensees, on November 30,
2007. All other persons who possess
and use accelerator-produced
radioactive material or discrete sources
of radium-226 for which a specific
medical use license is required, must
comply with the requirements of this
part, including provisions that are
specific to licensees, on August 8, 2009,
or earlier as noticed by the NRC.
*
*
*
*
*
I 37. In § 35.11, paragraph (a) is revised,
and paragraph (c) is added to read as
follows:
§ 35.11
Frm 00068
Fmt 4701
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0.1
*
10
0.1
*
0.01
0.0001
*
0.1
0.001
that the person submits a medical use
license application on or before
December 1, 2008.
(2) Except as provided in paragraph
(c)(1) of this section, all other persons,
who possess and use acceleratorproduced radioactive material or
discrete sources of radium-226 for
which a specific medical use license is
required in paragraph (a) of this section,
may continue to use this type of
material for medical uses permitted
under this part until the date of the
NRC’s final licensing determination,
provided that the person submits a
medical use license application within
12 months from the waiver expiration
date of August 7, 2009 or within 12
months from the date of an earlier
termination of the waiver as noticed by
the NRC, whichever date is earlier.
38. In § 35.13, paragraphs (a) and (e)
are revised, and paragraph (b)(5) is
added to read as follows:
I
License required.
(a) A person may manufacture,
produce, acquire, receive, possess,
prepare, use, or transfer byproduct
material for medical use only in
accordance with a specific license
issued by the Commission or an
Agreement State, or as allowed in
paragraph (b) or (c) of this section.
*
*
*
*
*
(c)(1) A Government agency or a
Federally recognized Indian Tribe, that
possesses and uses accelerator-produced
radioactive material or discrete sources
of radium-226 for which a specific
medical use license is required in
paragraph (a) of this section, may
continue to use such materials for
medical uses until the date of the NRC’s
final licensing determination, provided
PO 00000
*
10
§ 35.13
License amendments.
*
*
*
*
*
(a) Before it receives, prepares, or uses
byproduct material for a type of use that
is permitted under this part, but is not
authorized on the licensee’s current
license issued under this part; except
that—
(1) A Government agency or a
Federally recognized Indian Tribe
licensee who possesses and uses
accelerator-produced radioactive
material or discrete sources of radium226 may continue to use such material
for medical uses permitted under this
part until the date of the NRC’s final
licensing determination, provided that
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the licensee submits an amendment
application on or before June 2, 2008.
(2) Except as provided in paragraph
(a)(1) of this section, all other licensees
who possess and use acceleratorproduced radioactive material or
discrete sources of radium-226 may
continue to use those materials for
medical uses permitted under this part
until the date of the NRC’s final
licensing determination, provided that
the person submits a medical use
license amendment request within 6
months from the waiver expiration date
of August 7, 2009 or within 6 months
from the date of an earlier termination
of the waiver as noticed by the NRC,
whichever date is earlier.
(b) * * *
(5) A physician, podiatrist, or dentist
who used only accelerator-produced
radioactive materials, discrete sources of
radium-226, or both, for medical uses or
a nuclear pharmacist who used only
accelerator-produced radioactive
materials in the practice of nuclear
pharmacy at a Government agency or
Federally recognized Indian Tribe
before November 30, 2007 or at all other
locations of use before August 8, 2009,
or an earlier date as noticed by the NRC,
and for only those materials and uses
performed before these dates.
*
*
*
*
*
(e) Before it adds to or changes the
areas of use identified in the application
or on the license, including areas used
in accordance with either § 35.100 or
§ 35.200 if the change includes addition
or relocation of either an area where
PET radionuclides are produced or a
PET radioactive drug delivery line from
the PET radionuclide/PET radioactive
drug production area. Other areas of use
where byproduct material is used only
in accordance with either § 35.100 or
§ 35.200 are exempt;
*
*
*
*
*
I 39. In § 35.14, the introductory text of
paragraph (a) and paragraph (b)(5) are
revised to read as follows:
jlentini on PROD1PC65 with RULES2
§ 35.14
Notifications.
(a) A licensee shall provide the
Commission a copy of the board
certification and the written
attestation(s), signed by a preceptor, the
Commission or Agreement State license,
the permit issued by a Commission
master material licensee, the permit
issued by a Commission or Agreement
State licensee of broad scope, the permit
issued by a Commission master material
license broad scope permittee, or
documentation that only acceleratorproduced radioactive materials, discrete
sources of radium-226, or both, were
used for medical use or in the practice
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55931
of nuclear pharmacy at a Government
agency or Federally recognized Indian
Tribe before November 30, 2007 or at all
other locations of use before August 8,
2009, or an earlier date as noticed by the
NRC, and for each individual no later
than 30 days after the date that the
licensee permits the individual to work
as an authorized user, an authorized
nuclear pharmacist, or an authorized
medical physicist, under § 35.13(b). For
individuals permitted to work under
§ 35.13(b)(4), within the same 30-day
time frame, the licensee shall also
provide, as appropriate, verification of
completion of;
*
*
*
*
*
(b) * * *
(5) The licensee has added to or
changed the areas of use identified in
the application or on the license where
byproduct material is used in
accordance with either § 35.100 or
§ 35.200 if the change does not include
addition or relocation of either an area
where PET radionuclides are produced
or a PET radioactive drug delivery line
from the PET radionuclide/PET
radioactive drug production area.
*
*
*
*
*
I 40. In § 35.15, paragraph (f) is revised
to read as follows:
authorized nuclear pharmacist or an
authorized medical physicist,
respectively, for those materials and
uses performed before these dates, for
purposes of this chapter.
(b) * * *
(3) Physicians, dentists, or podiatrists
who used only accelerator-produced
radioactive materials, discrete sources of
radium-226, or both, for medical uses
performed at a Government agency or
Federally recognized Indian Tribe
before November 30, 2007 or at all other
locations of use before August 8, 2009,
or an earlier date as noticed by the NRC,
need not comply with the training
requirements of subparts D through H of
this part when performing the same
medical uses. A physician, dentist, or
podiatrist, who used only acceleratorproduced radioactive materials, discrete
sources of radium-226, or both, for
medical uses at the locations and time
period identified in this paragraph,
qualifies as an authorized user for those
materials and uses performed before
these dates, for purposes of this chapter.
I 42. In § 35.63, paragraphs (b)(2)(ii)
and (c)(3) are revised, and paragraph
(b)(2)(iii) is added to read as follows:
§ 35.15 Exemptions regarding Type A
specific licenses of broad scope.
*
*
*
*
*
*
(f) The provisions of § 35.14(b)(5).
*
*
*
*
*
I 41. In § 35.57, paragraphs (a)(3) and
(b)(3) are added to read as follows:
§ 35.57 Training for experienced Radiation
Safety Officer, teletherapy or medical
physicist, authorized medical physicist,
authorized user, nuclear pharmacist, and
authorized nuclear pharmacist.
(a) * * *
(3) A Radiation Safety Officer, a
medical physicist, or a nuclear
pharmacist, who used only acceleratorproduced radioactive materials, discrete
sources of radium-226, or both, for
medical uses or in the practice of
nuclear pharmacy at a Government
agency or Federally recognized Indian
Tribe before November 30, 2007 or at all
other locations of use before August 8,
2009, or an earlier date as noticed by the
NRC, need not comply with the training
requirements of § 35.50, § 35.51 or
§ 35.55, respectively, when performing
the same uses. A nuclear pharmacist,
who prepared only radioactive drugs
containing accelerator-produced
radioactive materials, or a medical
physicist, who used only acceleratorproduced radioactive materials, at the
locations and time period identified in
this paragraph, qualifies as an
PO 00000
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Fmt 4701
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§ 35.63 Determination of dosages of
unsealed byproduct material for medical
use.
*
*
*
*
(b) * * *
(2) * * *
(ii) An NRC or Agreement State
licensee for use in research in
accordance with a Radioactive Drug
Research Committee-approved protocol
or an Investigational New Drug (IND)
protocol accepted by FDA; or
(iii) A PET radioactive drug producer
licensed under § 30.32(j) of this chapter
or equivalent Agreement State
requirements.
(c) * * *
(3) Combination of volumetric
measurements and mathematical
calculations, based on the measurement
made by:
(i) A manufacturer or preparer
licensed under § 32.72 of this chapter or
equivalent Agreement State
requirements; or
(ii) A PET radioactive drug producer
licensed under § 30.32(j) of this chapter
or equivalent Agreement State
requirements.
*
*
*
*
*
I 43. In § 35.100, paragraph (a) and the
introductory text of paragraph (b) are
revised to read as follows:
§ 35.100 Use of unsealed byproduct
material for uptake, dilution, and excretion
studies for which a written directive is not
required.
*
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*
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*
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(a) Obtained from:
(1) A manufacturer or preparer
licensed under § 32.72 of this chapter or
equivalent Agreement State
requirements; or
(2) A PET radioactive drug producer
licensed under § 30.32(j) of this chapter
or equivalent Agreement State
requirements; or
(b) Excluding production of PET
radionuclides, prepared by:
*
*
*
*
*
I 44. In § 35.200, paragraph (a) and the
introductory text of paragraph (b) are
revised to read as follows:
§ 35.200 Use of unsealed byproduct
material for imaging and localization
studies for which a written directive is not
required.
*
*
*
*
*
(a) Obtained from:
(1) A manufacturer or preparer
licensed under § 32.72 of this chapter or
equivalent Agreement State
requirements; or
(2) A PET radioactive drug producer
licensed under § 30.32(j) of this chapter
or equivalent Agreement State
requirements; or
(b) Excluding production of PET
radionuclides, prepared by:
*
*
*
*
*
I 45. In § 35.204, the heading and
paragraph (a) are revised, paragraph (c)
is redesignated as (d) and revised, and
a new paragraph (c) is added to read as
follows:
jlentini on PROD1PC65 with RULES2
§ 35.204 Permissible molybdenum-99,
strontium-82, and strontium-85
concentrations.
(a) A licensee may not administer to
humans a radiopharmaceutical that
contains:
(1) More than 0.15 kilobecquerel of
molybdenum-99 per megabecquerel of
technetium-99m (0.15 microcurie of
molybdenum-99 per millicurie of
technetium-99m); or
(2) More than 0.02 kilobecquerel of
strontium-82 per megabecquerel of
rubidium-82 chloride injection (0.02
microcurie of strontium-82 per
millicurie of rubidium-82 chloride); or
more than 0.2 kilobecquerel of
strontium-85 per megabecquerel of
rubidium-82 chloride injection (0.2
microcurie of strontium-85 per
millicurie of rubidium-82).
*
*
*
*
*
(c) A licensee that uses a strontium82/rubidium-82 generator for preparing
a rubidium-82 radiopharmaceutical
shall, before the first patient use of the
day, measure the concentration of
radionuclides strontium-82 and
strontium-85 to demonstrate compliance
with paragraph (a) of this section.
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(d) If a licensee is required to measure
the molybdenum-99 concentration or
strontium-82 and strontium-85
concentrations, the licensee shall retain
a record of each measurement in
accordance with § 35.2204.
I 46. In § 35.300, paragraph (a) and the
introductory text of paragraph (b) are
revised to read as follows:
§ 35.300 Use of unsealed byproduct
material for which a written directive is
required.
*
*
*
*
*
(a) Obtained from:
(1) A manufacturer or preparer
licensed under § 32.72 of this chapter or
equivalent Agreement State
requirements; or
(2) A PET radioactive drug producer
licensed under § 30.32(j) of this chapter
or equivalent Agreement State
requirements; or
(b) Excluding production of PET
radionuclides, prepared by:
I 47. Section 35.2204 is revised to read
as follows:
§ 35.2204 Records of molybdenum-99,
strontium-82, and strontium-85
concentrations.
A licensee shall maintain a record of
the molybdenum-99 concentration or
strontium-82 and strontium-85
concentration tests required by
§ 35.204(b) and (c) for 3 years. The
record must include:
(a) For each measured elution of
technetium-99m, the ratio of the
measures expressed as kilobecquerel of
molybdenum-99 per megabecquerel of
technetium-99m (or microcuries of
molybdenum per millicurie of
technetium), the time and date of the
measurement, and the name of the
individual who made the measurement;
or
(b) For each measured elution of
rubidium-82, the ratio of the measures
expressed as kilobecquerel of strontium82 per megabecquerel of rubidium-82
(or microcuries of strontium-82 per
millicurie of rubidium), kilobecquerel of
strontium-85 per megabecquerel of
rubidium-82 (or microcuries of
strontium-85 per millicurie of
rubidium), the time and date of the
measurement, and the name of the
individual who made the measurement.
PART 50—DOMESTIC LICENSING OF
PRODUCTION AND UTILIZATION
FACILITIES
48. The authority citation for part 50
is revised to read as follows:
I
Authority: Secs. 102, 103, 104, 161, 182,
183, 186, 189, 68 Stat. 936, 937, 938, 948,
953, 954, 955, 956, as amended, sec. 234, 83
PO 00000
Frm 00070
Fmt 4701
Sfmt 4700
Stat. 444, as amended (42 U.S.C. 2132, 2133,
2134, 2135, 2201, 2232, 2233, 2236, 2239,
2282); secs. 201, as amended, 202, 206, 88
Stat. 1242, as amended, 1244, 1246 (42 U.S.C.
5841, 5842, 5846); sec. 1704, 112 Stat. 2750
(44 U.S.C. 3504 note); sec. 651(e), Pub. L.
109–58, 119 Stat. 806–810 (42 U.S.C. 2014,
2021, 2021b, 2111). Section 50.7 also issued
under Pub. L. 95–601, sec. 10, 92 Stat. 2951
(42 U.S.C. 5841). Section 50.10 also issued
under secs. 101, 185, 68 Stat. 955, as
amended (42 U.S.C. 2131, 2235); sec. 102,
Pub. L. 91–190, 83 Stat. 853 (42 U.S.C. 4332).
Sections 50.13, 50.54(dd), and 50.103 also
issued under sec. 108, 68 Stat. 939, as
amended (42 U.S.C. 2138).
Sections 50.23, 50.35, 50.55, and 50.56 also
issued under sec. 185, 68 Stat. 955 (42 U.S.C.
2235). Sections 50.33a, 50.55a and Appendix
Q also issued under sec. 102, Pub. L. 91–190,
83 Stat. 853 (42 U.S.C. 4332). Sections 50.34
and 50.54 also issued under sec. 204, 88 Stat.
1245 (42 U.S.C. 5844). Sections 50.58, 50.91,
and 50.92 also issued under Pub. L. 97–415,
96 Stat. 2073 (42 U.S.C. 2239). Section 50.78
also issued under sec. 122, 68 Stat. 939 (42
U.S.C. 2152). Sections 50.80–50.81 also
issued under sec. 184, 68 Stat. 954, as
amended (42 U.S.C. 2234). Appendix F also
issued under sec. 187, 68 Stat. 955 (42 U.S.C.
2237).
49. In § 50.2, the definition of
Byproduct material is revised to read as
follows:
I
§ 50.2
Definitions.
*
*
*
*
*
Byproduct material means—
(1) Any radioactive material (except
special nuclear material) yielded in, or
made radioactive by, exposure to the
radiation incident to the process of
producing or using special nuclear
material;
(2)(i) Any discrete source of radium226 that is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; or
(ii) Any material that—
(A) Has been made radioactive by use
of a particle accelerator; and
(B) Is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; and
(3) Any discrete source of naturally
occurring radioactive material, other
than source material, that—
(i) The Commission, in consultation
with the Administrator of the
Environmental Protection Agency, the
Secretary of Energy, the Secretary of
Homeland Security, and the head of any
other appropriate Federal agency,
determines would pose a threat similar
to the threat posed by a discrete source
of radium-226 to the public health and
safety or the common defense and
security; and
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(ii) Before, on, or after August 8, 2005,
is extracted or converted after extraction
for use in a commercial, medical, or
research activity.
*
*
*
*
*
PART 61—LICENSING
REQUIREMENTS FOR LAND
DISPOSAL OF RADIOACTIVE WASTE
50. The authority citation for part 61
is revised to read as follows:
I
Authority: Secs. 53, 57, 62, 63, 65, 81, 161,
182, 183, 68 Stat. 930, 932, 933, 935, 948,
953, 954, as amended (42 U.S.C. 2073, 2077,
2092, st2093, 2095, 2111, 2201, 2232, 2233);
secs. 202, 206, 88 Stat. 1244, 1246 (42 U.S.C.
5842, 5846); secs. 10 and 14, Pub. L. 95–601,
92 Stat. 2951 (42 U.S.C. 2021a and 5851) and
Pub. L. 102–486, sec. 2902, 106 Stat. 3123,
(42 U.S.C. 5851); sec. 1704, 112 Stat. 2750 (44
U.S.C. 3504 note); sec. 651(e), Pub. L. 109–
58, 119 Stat. 806–810 (42 U.S.C. 2014, 2021,
2021b, 2111).
51. In § 61.2, the definition for Waste
is revised to read as follows:
I
§ 61.2
Definitions.
*
*
*
*
*
Waste means those low-level
radioactive wastes containing source,
special nuclear, or byproduct material
that are acceptable for disposal in a land
disposal facility. For the purposes of
this definition, low-level radioactive
waste means radioactive waste not
classified as high-level radioactive
waste, transuranic waste, spent nuclear
fuel, or byproduct material as defined in
paragraphs (2), (3), and (4) of the
definition of Byproduct material set
forth in § 20.1003 of this chapter.
PART 62—CRITERIA AND
PROCEDURES FOR EMERGENCY
ACCESS TO NON-FEDERAL AND
REGIONAL LOW-LEVEL WASTE
DISPOSAL FACILITIES
52. The authority citation for part 62
is revised to read as follows:
I
jlentini on PROD1PC65 with RULES2
Authority: Secs. 81, 161, as amended, 68
Stat. 935, 948, 950, 951, as amended (42
U.S.C. 211, 2201; secs. 201, 209, as amended,
88 Stat. 1242, 1248, as amended (42 U.S.C.
5841, 5849); secs. 3, 4, 5, 6, 99 Stat. 1843,
1844, 1845, 1846, 1847, 1848, 1849, 1850,
1851, 1852, 1853, 1854, 1855, 1856, 1857 (42
U.S.C. 2021c, 2021d, 2021e, 2021f; sec. 1704,
112 Stat. 2750 (44 U.S.C. 3504 note); sec.
651(e), Pub. L. 109–58, 119 Stat. 806–810 (42
U.S.C. 2014, 2021, 2021b, 2111).
I 53. In § 62.2, the definition for Lowlevel radioactive waste (LLW) is revised
to read as follows:
§ 62.2
Definitions.
*
*
*
*
*
Low-level radioactive waste (LLW)
means radioactive material that—
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(1) Is not high-level radioactive waste,
spent nuclear fuel, or byproduct
material (as defined in paragraphs (2),
(3), and (4) of the definition of
Byproduct Material set forth in
§ 20.1003 of this chapter); and
(2) The NRC, consistent with existing
law and in accordance with paragraph
(1) of this definition, classifies as lowlevel radioactive waste.
*
*
*
*
*
PART 72—LICENSING
REQUIREMENTS FOR THE
INDEPENDENT STORAGE OF SPENT
NUCLEAR FUEL, HIGH–LEVEL
RADIOACTIVE WASTE AND
REACTOR-RELATED GREATER THAN
CLASS C WASTE
54. The authority citation for part 72
continues to read as follows:
I
Authority: Secs. 51, 53, 57, 62, 63, 65, 69,
81, 161, 182, 183, 184, 186, 187, 189, 68 Stat.
929, 930, 932, 933, 934, 935, 948, 953, 954,
955, as amended, sec. 234, 83 Stat. 444, as
amended (42 U.S.C. 2071, 2073, 2077, 2092,
2093, 2095, 2099, 2111, 2201, 2232, 2233,
2234, 2236, 2237, 2238, 2282); sec. 274, Pub.
L. 86–373, 73 Stat. 688, as amended (42
U.S.C. 2021); sec. 201, as amended, 202, 206,
88 Stat. 1242, as amended, 1244, 1246 (42
U.S.C. 5841, 5842, 5846); Pub. L. 95–601, sec.
10, 92 Stat. 2951 as amended by Pub. L. 102–
486, sec. 7902, 106 Stat. 3123 (42 U.S.C.
5851); sec. 102, Pub. L. 91–190, 83 Stat. 853
(42 U.S.C. 4332); secs. 131, 132, 133, 135,
137, 141, Pub. L. 97–425, 96 Stat. 2229, 2230,
2232, 2241, sec. 148, Pub. L. 100–203, 101
Stat. 1330–235 (42 U.S.C. 10151, 10152,
10153, 10155, 10157, 10161, 10168); sec.
1704, 112 Stat. 2750 (44 U.S.C. 3504 note);
sec. 651(e), Pub. L. 109–58, 119 Stat. 806–810
(42 U.S.C. 2014, 2021, 2021b, 2111).
Section 72.44(g) also issued under secs.
142(b) and 148(c), (d), Pub. L. 100–203, 101
Stat. 1330–232, 1330–236 (42 U.S.C.
10162(b), 10168(c), (d)). Section 72.46 also
issued under sec. 189, 68 Stat. 955 (42 U.S.C.
2239); sec. 134, Pub. L. 97–425, 96 Stat. 2230
(42 U.S.C. 10154). Section 72.96(d) also
issued under sec. 145(g), Pub. L. 100–203,
101 Stat. 1330–235 (42 U.S.C. 10165(g)).
Subpart J also issued under secs. 2(2), 2(15),
2(19), 117(a), 141(h), Pub. L. 97–425, 96 Stat.
2202, 2203, 2204, 2222, 2224 (42 U.S.C.
10101, 10137(a), 10161(h)). Subparts K and L
are also issued under sec. 133, 98 Stat. 2230
(42 U.S.C. 10153) and sec. 218(a), 96 Stat.
2252 (42 U.S.C. 10198).
55. In § 72.3, the definition for
Byproduct material is revised to read as
follows:
I
§ 72.3
Definitions.
*
*
*
*
*
Byproduct material means—
(1) Any radioactive material (except
special nuclear material) yielded in, or
made radioactive by, exposure to the
radiation incident to the process of
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55933
producing or using special nuclear
material;
(2)(i) Any discrete source of radium226 that is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; or
(ii) Any material that—
(A) Has been made radioactive by use
of a particle accelerator; and
(B) Is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; and
(3) Any discrete source of naturally
occurring radioactive material, other
than source material, that—
(i) The Commission, in consultation
with the Administrator of the
Environmental Protection Agency, the
Secretary of Energy, the Secretary of
Homeland Security, and the head of any
other appropriate Federal agency,
determines would pose a threat similar
to the threat posed by a discrete source
of radium-226 to the public health and
safety or the common defense and
security; and
(ii) Before, on, or after August 8, 2005,
is extracted or converted after extraction
for use in a commercial, medical, or
research activity.
*
*
*
*
*
PART 110—EXPORT AND IMPORT OF
NUCLEAR EQUIPMENT AND
MATERIAL
56. The authority citation for part 110
is revised to read as follows:
I
Authority: Secs. 51, 53, 54, 57, 63, 64, 65,
81, 82, 103, 104, 109, 111, 126, 127, 128, 129,
161, 181, 182, 183, 187, 189, 68 Stat. 929,
930, 931, 932, 933, 936, 937, 948, 953, 954,
955, 956, as amended (42 U.S.C. 2071, 2073,
2074, 2077, 2092–2095, 2111, 2112, 2133,
2134, 2139, 2139a, 2141, 2154–2158, 2201,
2231–2233, 2237, 2239); sec. 201, 88 Stat.
1242, as amended (42 U.S.C. 5841; sec 5,
Pub. L. 101–575, 104 Stat 2835 (42
U.S.C.2243); sec. 1704, 112 Stat. 2750 (44
U.S.C. 3504 note); Energy Policy Act of 2005;
Pub. L. 109–58, 119 Stat. 594 (2005).
Sections 110.1(b)(2) and 110.1(b)(3) also
issued under Pub. L. 96–92, 93 Stat. 710 (22
U.S.C. 2403). Section 110.11 also issued
under sec. 122, 68 Stat. 939 (42 U.S.C. 2152)
and secs. 54c and 57d., 88 Stat. 473, 475 (42
U.S.C. 2074). Section 110.27 also issued
under sec. 309(a), Pub. L. 99–440. Section
110.50(b)(3) also issued under sec. 123, 92
Stat. 142 (42 U.S.C. 2153). Section 110.51
also issued under sec. 184, 68 Stat. 954, as
amended (42 U.S.C. 2234). Section 110.52
also issued under sec. 186, 68 Stat. 955 (42
U.S.C. 2236). Sections 110.80–110.113 also
issued under 5 U.S.C. 552, 554. Sections
110.130–110.135 also issued under 5 U.S.C.
553. Sections 110.2 and 110.42 (a)(9) also
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issued under sec. 903, Pub. L. 102–496 (42
U.S.C. 2151 et seq.).
57. In § 110.2, definitions of
Accelerator-produced radioactive
material, Discrete source, and Particle
accelerator are added alphabetically to
read as follows:
I
§ 110.2
Definitions.
*
*
*
*
*
Accelerator-produced radioactive
material means any material made
radioactive by a particle accelerator.
*
*
*
*
*
Discrete source means a radionuclide
that has been processed so that its
concentration within a material has
been purposely increased for use for
commercial, medical, or research
activities.
*
*
*
*
*
Particle accelerator means any
machine capable of accelerating
electrons, protons, deuterons, or other
charged particles in a vacuum and of
discharging the resultant particulate or
other radiation into a medium at
energies usually in excess of 1
megaelectron volt. For purposes of this
definition, ‘‘accelerator’’ is an
equivalent term.
*
*
*
*
*
PART 150—EXEMPTIONS AND
CONTINUED REGULATORY
AUTHORITY IN AGREEMENT STATES
AND IN OFFSHORE WATERS UNDER
SECTION 274
58. The authority citation for part 150
is revised to read as follows:
I
Authority: Sec. 161, 68 Stat. 948, as
amended, sec. 274, 73 Stat. 688 (42 U.S.C.
2201, 2021); sec. 201, 88 Stat. 1242, as
amended (42 U.S.C. 5841); sec. 1704, 112
Stat. 2750 (44 U.S.C. 3504 note); sec. 651(e),
Pub. L. 109–58, 119 Stat. 806–810 (42 U.S.C.
2014, 2021, 2021b, 2111).
Sections 150.3, 150.15, 150.15a, 150.31,
150.32 also issued under secs. 11e(2), 81, 68
Stat. 923, 935, as amended, secs. 83, 84, 92
Stat. 3033, 3039 (42 U.S.C. 2014e(2), 2111,
2113, 2114). Section 150.14 also issued under
sec. 53, 68 Stat. 930, as amended (42 U.S.C.
2073). Section 150.15 also issued under secs.
135, 141, Pub. L. 97–425, 96 Stat. 2232, 2241
(42 U.S.C. 10155, 10161). Section 150.17a
also issued under sec. 122, 68 Stat. 939 (42
U.S.C. 2152). Section 150.30 also issued
under sec. 234, 83 Stat. 444 (42 U.S.C. 2282).
59. In § 150.3, the definition of
Byproduct material is revised, and a
definition of Discrete source is added
alphabetically to read as follows:
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I
§ 150.3
*
Definitions.
*
*
*
*
Byproduct material means—
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(1) Any radioactive material (except
special nuclear material) yielded in, or
made radioactive by, exposure to the
radiation incident to the process of
producing or using special nuclear
material;
(2) The tailings or wastes produced by
the extraction or concentration of
uranium or thorium from ore processed
primarily for its source material content,
including discrete surface wastes
resulting from uranium solution
extraction processes. Underground ore
bodies depleted by these solution
extraction operations do not constitute
‘‘byproduct material’’ within this
definition; (3)(i) Any discrete source of
radium-226 that is produced, extracted,
or converted after extraction, before, on,
or after August 8, 2005, for use for a
commercial, medical, or research
activity; or
(ii) Any material that—
(A) Has been made radioactive by use
of a particle accelerator; and
(B) Is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; and
(4) Any discrete source of naturally
occurring radioactive material, other
than source material, that—
(i) The Commission, in consultation
with the Administrator of the
Environmental Protection Agency, the
Secretary of Energy, the Secretary of
Homeland Security, and the head of any
other appropriate Federal agency,
determines would pose a threat similar
to the threat posed by a discrete source
of radium-226 to the public health and
safety or the common defense and
security; and
(ii) Before, on, or after August 8, 2005,
is extracted or converted after extraction
for use in a commercial, medical, or
research activity.
*
*
*
*
*
Discrete source means a radionuclide
that has been processed so that its
concentration within a material has
been purposely increased for use for
commercial, medical, or research
activities.
*
*
*
*
*
PART 170—FEES FOR FACILITIES,
MATERIALS, IMPORT AND EXPORT
LICENSES, AND OTHER
REGULATORY SERVICES UNDER THE
ATOMIC ENERGY ACT OF 1954, AS
AMENDED
92–314, 86 Stat. 227 (42 U.S.C. 2201w); sec.
201, Pub. L. 93–438, 88 Stat. 1242, as
amended (42 U.S.C. 5841); sec. 205a, Pub. L.
101–576, 104 Stat. 2842, as amended (31 U.S.
C. 901, 902); sec. 1704, 112 Stat. 2750 (44
U.S.C. 3504 note); sec. 623, Pub. L. 109–58,
119 Stat. 783 (42 U.S.C. 2201(w)); sec. 651(e),
Pub. L. 109–58, 119 Stat. 806–810 (42 U.S.C.
2014, 2021, 2021(b), 2111).
61. In § 170.3, the definition of
Byproduct material is revised to read as
follows:
I
§ 170.3
Definitions.
*
*
*
*
*
Byproduct material means—
(1) Any radioactive material (except
special nuclear material) yielded in, or
made radioactive by, exposure to the
radiation incident to the process of
producing or using special nuclear
material;
(2)(i) Any discrete source of radium226 that is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; or
(ii) Any material that—
(A) Has been made radioactive by use
of a particle accelerator; and
(B) Is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; and
(3) Any discrete source of naturally
occurring radioactive material, other
than source material, that—
(i) The Commission, in consultation
with the Administrator of the
Environmental Protection Agency, the
Secretary of Energy, the Secretary of
Homeland Security, and the head of any
other appropriate Federal agency,
determines would pose a threat similar
to the threat posed by a discrete source
of radium-226 to the public health and
safety or the common defense and
security; and
(ii) Before, on, or after August 8, 2005,
is extracted or converted after extraction
for use in a commercial, medical, or
research activity.
*
*
*
*
*
I 62. In § 170.31, in the table,
‘‘Schedule of Materials Fees,’’ paragraph
3.B. is revised, and new categories 3.R.
and 3.S. and corresponding fees are
added to read as follows:
60. The authority citation for part 170
is revised to read as follows:
Authority: Sec. 9701, Pub. L. 97–258, 96
Stat. 1051 (31 U.S.C. 9701); sec. 301, Pub. L.
§ 170.31 Schedule of fees for materials
licenses and other regulatory services,
including inspections, and import and
export licenses.
*
I
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Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules and Regulations
SCHEDULE OF MATERIALS FEES
Category of materials licenses and type of fees 1
*
3. Byproduct material:
*
*
*
Fee 2 3
*
*
*
*
*
*
*
*
*
B. Other licenses for possession and use of byproduct material issued under part 30 of this chapter for processing or manufacturing of items containing byproduct material for commercial distribution. This category also includes licenses for repair, assembly, and disassembly of products containing radium-226.
Application .............................................................................................................................................................................
*
*
*
*
*
*
*
R. Possession of items or products containing radium-226 identified in 10 CFR 31.12 which exceed the number of items or
limits specified in that section.6
1. Possession of quantities exceeding the number of items or limits in 10 CFR 31.12(a)(4), or (5) but less than or equal to
10 times the number of items or limits specified.
Application ......................................................................................................................................................................
2. Possession of quantities exceeding 10 times the number of items or limits specified in 10 CFR 31.12(a) (4), or (5).
Application ......................................................................................................................................................................
S. Licenses for production of accelerator-produced radionuclides.
Application .............................................................................................................................................................................
*
*
*
*
*
*
*
1 Types
$4,600
590
1,400
8,000
*
jlentini on PROD1PC65 with RULES2
of fees—Separate charges, as shown in the schedule, will be assessed for pre-application consultations and reviews; applications for
new licenses, approvals, or license terminations; possession only licenses; issuance of new licenses and approvals; certain amendments and renewals to existing licenses and approvals; safety evaluations of sealed sources and devices; generally licensed device registrations; and certain
inspections. The following guidelines apply to these charges:
(a) Application and registration fees. Applications for new materials licenses and export and import licenses; applications to reinstate expired,
terminated, or inactive licenses except those subject to fees assessed at full costs; applications filed by Agreement State licensees to register
under the general license provisions of 10 CFR 150.20; and applications for amendments to materials licenses that would place the license in a
higher fee category or add a new fee category must be accompanied by the prescribed application fee for each category.
(1) Applications for licenses covering more than one fee category of special nuclear material or source material must be accompanied by the
prescribed application fee for the highest fee category.
(2) Applications for new licenses that cover both byproduct material and special nuclear material in sealed sources for use in gauging devices
will pay the appropriate application fee for fee Category 1.C. only.
(b) Licensing fees. Fees for reviews of applications for new licenses and for renewals and amendments to existing licenses, for preapplication
consultations and for reviews of other documents submitted to the NRC for review, and project manager time for fee categories subject to full
cost fees are due upon notification by the Commission in accordance with § 170.12(b).
(c) Amendment fees. Applications for amendments to export and import licenses must be accompanied by the prescribed amendment fee for
each license affected. An application for an amendment to an export or import license or approval classified in more than one fee category must
be accompanied by the prescribed amendment fee for the category affected by the amendment unless the amendment is applicable to two or
more fee categories, in which case the amendment fee for the highest fee category will apply.
(d) Inspection fees. Inspections resulting from investigations conducted by the Office of Investigations and nonroutine inspections that result
from third-party allegations are not subject to fees. Inspection fees are due upon notification by the Commission in accordance with § 170.12(c).
(e) Generally licensed device registrations under 10 CFR 31.5. Submittals of registration information must be accompanied by the prescribed
fee.
2 Fees will not be charged for orders related to civil penalties or other civil sanctions issued by the Commission under 10 CFR 2.202 or for
amendments resulting specifically from the requirements of these orders. For orders unrelated to civil penalties or other civil sanctions, fees will
be charged for any resulting licensee-specific activities not otherwise exempted from fees under this chapter. Fees will be charged for approvals
issued under a specific exemption provision of the Commission’s regulations under Title 10 of the Code of Federal Regulations (e.g., 10 CFR
30.11, 40.14, 70.14, 73.5, and any other sections in effect now or in the future), regardless of whether the approval is in the form of a license
amendment, letter of approval, safety evaluation report, or other form. In addition to the fee shown, an applicant may be assessed an additional
fee for sealed source and device evaluations as shown in Categories 9A through 9D.
3 Full cost fees will be determined based on the professional staff time multiplied by the appropriate professional hourly rate established in
§ 170.20 in effect at the time the service is provided, and the appropriate contractual support services expended. For applications currently on file
for which review costs have reached an applicable fee ceiling established by the June 20, 1984, and July 2, 1990, rules, but are still pending
completion of the review, the cost incurred after any applicable ceiling was reached through January 29, 1989, will not be billed to the applicant.
Any professional staff-hours expended above those ceilings on or after January 30, 1989, will be assessed at the applicable rates established by
§ 170.20, as appropriate, except for topical reports whose costs exceed $50,000. Costs which exceed $50,000 for each topical report, amendment, revision, or supplement to a topical report completed or under review from January 30, 1989, through August 8, 1991, will not be billed to
the applicant. Any professional hours expended on or after August 9, 1991, will be assessed at the applicable rate established in § 70.20.
*
*
*
*
*
*
*
6 Persons who possess radium sources that are used for operational purposes in another fee category are not also subject to the fees in this
category. (This exception does not apply if the radium sources are possessed for storage only.)
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*
Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules and Regulations
*
*
*
*
64. In § 171.5, the definition of
Byproduct material is revised to read as
follows:
I
PART 171—ANNUAL FEES FOR
REACTOR LICENSES AND FUEL
CYCLE LICENSES AND MATERIALS
LICENSES, INCLUDING HOLDERS OF
CERTIFICATES OF COMPLIANCE,
REGISTRATIONS, AND QUALITY
ASSURANCE PROGRAM APPROVALS
AND GOVERNMENT AGENCIES
LICENSED BY THE NRC
63. The authority citation for part 171
is revised to read as follows:
I
Authority: Sec. 7601, Pub. L. 99-272, 100
Stat. 146, as amended by sec. 5601, Pub. L.
100–203, 101 Stat. 1330 as amended by sec.
3201, Pub. L. 101–239, 103 Stat. 2132, as
amended by sec. 6101, Pub. L. 101–508, 104
Stat. 1388, as amended by sec. 2903a, Pub.
L. 102–486, 106 Stat. 3125 (42 U.S.C. 2213,
2214); and as amended by Title IV, Pub. L.
109–103, 119 Stat. 2283 (42 U.S.C. 2214; sec.
301, Pub. L. 92–314, 86 Stat. 227 (42 U.S.C.
2201w); sec. 201, Pub. L. 93–438, 88 Stat.
1242, as amended (42 U.S.C. 5841); sec. 1704,
112 Stat. 2750 (44 U.S.C. 3504 note); sec
651(e), Pub. L. 109–58, 119 Stat. 806–810 (42
U.S.C. 2014, 2021, 2021(b), 2111).
§ 171.5
Definitions.
*
*
*
*
*
Byproduct material means–
(1) Any radioactive material (except
special nuclear material) yielded in, or
made radioactive by, exposure to the
radiation incident to the process of
producing or using special nuclear
material;
(2)(i) Any discrete source of radium–
226 that is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; or
(ii) Any material that—
(A) Has been made radioactive by use
of a particle accelerator; and
(B) Is produced, extracted, or
converted after extraction, before, on, or
after August 8, 2005, for use for a
commercial, medical, or research
activity; and
(3) Any discrete source of naturally
occurring radioactive material, other
than source material, that—
(i) The Commission, in consultation
with the Administrator of the
Environmental Protection Agency, the
Secretary of Energy, the Secretary of
Homeland Security, and the head of any
other appropriate Federal agency,
determines would pose a threat similar
to the threat posed by a discrete source
of radium–226 to the public health and
safety or the common defense and
security; and
(ii) Before, on, or after August 8, 2005,
is extracted or converted after extraction
for use in a commercial, medical, or
research activity.
*
*
*
*
*
I 65. In § 171.16, paragraph (d), in the
table, Schedule of Materials Annual
Fees and Fees for Government Agencies
Licensed by the NRC, paragraph 3.B. is
revised, and new categories 3.R. and
3.S. and corresponding fees are added to
read as follows:
§ 171.16 Annual Fees: Materials licensees,
holders of certificates of compliance,
holders of sealed source and device
registrations, holders of quality assurance
program approvals, and government
agencies licensed by the NRC.
SCHEDULE OF MATERIALS ANNUAL FEES AND FEES FOR GOVERNMENT AGENCIES LICENSED BY THE NRC
Annual
fees1 2 3
Category of materials licenses
*
3. Byproduct material:
*
*
*
*
*
*
*
*
*
*
*
*
B. Other licenses for possession and use of byproduct material issued under part 30 of this chapter for processing or manufacturing of items containing byproduct material for commercial distribution. This category also includes licenses for repair, assembly, and disassembly of products containing radium–226 .....................................................................................
*
*
*
*
*
*
*
R. Possession of items or products containing radium–226 identified in 10 CFR 31.12 which exceed the number of items or
limits specified in that section:14
1. Possession of quantities exceeding the number of items or limits in 10 CFR 31.12(a)(4), or (5) but less than or equal
to 10 times the number of items or limits specified ..........................................................................................................
2. Possession of quantities exceeding 10 times the number of items or limits specified in 10 CFR 31.12(a)(4), or (5) ....
S. Licenses for production of accelerator-produced radionuclides ..............................................................................................
*
jlentini on PROD1PC65 with RULES2
*
*
*
*
*
*
$8,400
2,100
2,700
10,800
*
1 Annual fees will be assessed based on whether a licensee held a valid license with the NRC authorizing possession and use of radioactive
material during the current fiscal year. However, the annual fee is waived for those materials licensees and holders of certificates, registrations,
and approvals who either filed for termination of their licenses or approvals or filed for possession only/storage licenses before October 1, 2004,
and permanently ceased licensed activities entirely by September 30, 2004. Annual fees for licensees who filed for termination of a license,
downgrade of a license, or for a possession only license during the fiscal year and for new licenses issued during the fiscal year will be prorated
in accordance with the provisions of § 171.17. If a person holds more than one license, certificate, registration, or approval, the annual fee(s) will
be assessed for each license, certificate, registration, or approval held by that person. For licenses that authorize more than one activity on a
single license (e.g., human use and irradiator activities), annual fees will be assessed for each category applicable to the license. Licensees paying annual fees under Category 1A(1) are not subject to the annual fees for Category 1.C. and 1.D. for sealed sources authorized in the license.
2 Payment of the prescribed annual fee does not automatically renew the license, certificate, registration, or approval for which the fee is paid.
Renewal applications must be filed in accordance with the requirements of parts 30, 40, 70, 71, 72, or 76 of this chapter.
3 Each fiscal year, fees for these materials licenses will be calculated and assessed in accordance with § 171.13 and will be published in the
Federal Register for notice and comment.
*
*
*
*
*
*
*
14 Persons who possess radium sources that are used for operational purposes in another fee category are not also subject to the fees in this
category. (This exception does not apply if the radium sources are possessed for storage only.)
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*
*
*
*
Dated at Rockville, Maryland, this 13th day
of September 2007.
*
For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. 07–4735 Filed 9–28–07; 8:45 am]
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Agencies
[Federal Register Volume 72, Number 189 (Monday, October 1, 2007)]
[Rules and Regulations]
[Pages 55864-55937]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 07-4735]
[[Page 55863]]
-----------------------------------------------------------------------
Part II
Nuclear Regulatory Commission
-----------------------------------------------------------------------
10 CFR Parts 20, 30, et al.
Requirements for Expanded Definition of Byproduct Material; Final Rule
Federal Register / Vol. 72, No. 189 / Monday, October 1, 2007 / Rules
and Regulations
[[Page 55864]]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Parts 20, 30, 31, 32, 33, 35, 50, 61, 62, 72, 110, 150, 170,
and 171
RIN 3150-AH84
Requirements for Expanded Definition of Byproduct Material
AGENCY: Nuclear Regulatory Commission.
ACTION: Final rule.
-----------------------------------------------------------------------
SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its
regulations to include jurisdiction over discrete sources of radium-
226, accelerator-produced radioactive materials, and discrete sources
of naturally occurring radioactive material, as required by the Energy
Policy Act of 2005 (EPAct), which was signed into law on August 8,
2005. The EPAct expanded the Atomic Energy Act of 1954 definition of
Byproduct material to include any discrete source of radium-226, any
material made radioactive by use of a particle accelerator, and any
discrete source of naturally occurring radioactive material, other than
source material, that the Commission, in consultation with other
Federal officials named in the EPAct, determines would pose a similar
threat to the public health and safety or the common defense and
security as a discrete source of radium-226, that are extracted or
converted after extraction for use for a commercial, medical, or
research activity. In so doing, these materials were placed under the
NRC's regulatory authority. The EPAct also mandated that the
Commission, after consultation with the States and other stakeholders,
issue final regulations establishing requirements that the Commission
determines necessary under the EPAct. This rulemaking effort has been
undertaken in response to that mandate and includes significant
contributions from many States that have regulated the naturally
occurring and accelerator-produced radioactive material, the
Organization of Agreement States, Inc., the Conference of Radiation
Control Program Directors, Inc. (CRCPD), and other stakeholders. In
addition, this final rule was informed and guided by the CRCPD's
applicable Suggested State Regulations for the Control of Radiation.
Licensees, individuals, and other entities who are engaged in
activities involving the newly defined byproduct material in both
Agreement States and non-Agreement States and United States Territories
will be affected by this rulemaking.
DATES: Effective Date: This final rule is effective on November 30,
2007.
FOR FURTHER INFORMATION CONTACT: Lydia Chang, Office of Federal and
State Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
6319, e-mail lwc1@nrc.gov; or Catherine R. Mattsen, Office of Federal
and State Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
6264, e-mail crm@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
II. Discussion
A. The New, Expanded Definition of Byproduct Material
B. The NRC's Regulatory Approach
C. Changes to Existing NRC Regulations to Accommodate the New
Byproduct Material
D. License Application and Annual Fees
E. Implementation Strategy
III. Summary and Analysis of Public Comments on the Proposed Rule
IV. Section-by-Section Analysis of Final Revisions
V. Criminal Penalties
VI. Agreement State Compatibility
VII. Voluntary Consensus Standards
VIII. Environmental Assessment and Finding of No Significant
Environmental Impact: Availability
IX. Paperwork Reduction Act Statement
X. Regulatory Analysis
XI. Regulatory Flexibility Certification
XII. Backfit Analysis
XIII. Congressional Review Act
I. Background
The Energy Policy Act of 2005
On August 8, 2005, the President signed into law the EPAct. Among
other provisions, Section 651(e) of the EPAct expanded the definition
of Byproduct material as defined in Section 11e. of the Atomic Energy
Act of 1954 (AEA), placing additional byproduct material under the
NRC's jurisdiction, and required the Commission to provide a regulatory
framework for licensing and regulating this additional byproduct
material.
Specifically, Section 651(e) of the EPAct expanded the definition
of Byproduct material by: (1) Adding any discrete source of radium-226
that is produced, extracted, or converted after extraction, before, on,
or after the date of enactment of the EPAct for use for a commercial,
medical, or research activity; or any material that has been made
radioactive by use of a particle accelerator and is produced,
extracted, or converted after extraction, before, on, or after the date
of enactment of the EPAct for use for a commercial, medical, or
research activity (Section 11e.(3) of the AEA); and (2) adding any
discrete source of naturally occurring radioactive material, other than
source material, that the Commission, in consultation with the
Administrator of the Environmental Protection Agency (EPA), the
Secretary of the Department of Energy (DOE), the Secretary of the
Department of Homeland Security (DHS), and the head of any other
appropriate Federal agency, determines would pose a threat similar to
the threat posed by a discrete source of radium-226 to the public
health and safety or the common defense and security; and is extracted
or converted after extraction before, on, or after the date of
enactment of the EPAct for use in a commercial, medical, or research
activity (Section 11e.(4) of the AEA).
Although Section 651(e) of the EPAct became effective on August 8,
2005, the NRC did not have regulations in place that would specifically
apply to this newly covered byproduct material (hereafter referred to
as NARM). The EPAct also allowed the NRC to issue waivers to States and
other entities while developing final regulations for NARM. A waiver
was issued on August 31, 2005 (70 FR 51581).
Previous Regulatory Structures for NARM
The AEA authorizes the States to assume regulatory control of
certain radioactive materials provided the State has an adequate
program to protect the public health and safety and is compatible with
the NRC's program for regulation of these materials and enters into an
agreement with the NRC. As authorized by Section 274b of the AEA, 34
States have assumed responsibility for regulating certain activities
related to radioactive material by entering into agreements with the
NRC. The activities regulated by these ``Agreement States'' include the
use of byproduct material, source material, and special nuclear
material. Each Agreement State issues licenses to persons who use these
materials in that State except for DOE, other Government agencies, and
Federally recognized Indian Tribes. The NRC issues licenses to persons
using these materials in non-Agreement States.
Before enactment of the EPAct, the NRC did not have authority over
NARM or regulations for this type of material. Although the NRC has not
regulated NARM in the past, all 34 Agreement States and certain non-
Agreement States have regulatory programs for NARM. The NRC's
regulations did require licensees to account for dose contributed from
NARM, as well as dose
[[Page 55865]]
contributed from other byproduct, source, or special nuclear material,
because the definition of Occupational dose encompasses both licensed
material and nonlicensed material such as NARM sources at a licensed
facility. In addition, the NRC requires in its radiological criteria
for license termination that licensees consider other nondiscrete
sources, including radium, during decommissioning activities at sites
contaminated with source material, such as rare-earth processing
facilities.
Currently, there are 16 non-Agreement States plus United States
(U.S.) Territories. Although most non-Agreement States and U.S.
Territories have some type of programs for NARM, the regulatory
structures vary greatly. Certain non-Agreement States have established
a licensing structure for regulating their NARM users. As such, the
regulatory structure could parallel the NRC regulations issued in Title
10 of the Code of Federal Regulations (10 CFR) applicable to the
current materials program, or it could parallel the Suggested State
Regulations for the Control of Radiation (SSRs) developed by the CRCPD.
Other non-Agreement States or U.S. Territories have elected to use
registration as their regulatory structure for managing the NARM users.
Some States register facilities; others register both facilities and
devices. Some States use registration information to conduct
inspections; others use registration to identify facility locations for
security purposes. In general, there is limited regulatory oversight
where registration is used in non-Agreement States. It was, in part,
due to this lack of national consistency, that the EPAct placed these
materials under the NRC's jurisdiction.
Agreement States have regulated NARM use for many decades in a
fairly uniform and consistent manner. The Agreement States have
accomplished this by using the same standards to regulate NARM as those
used to regulate other byproduct, source, and special nuclear material
under the NRC's authority. In many respects, regulations applicable to
NARM adopted by the Agreement States are compatible with the NRC's
regulations for the current materials program, or parallel the CRCPD's
SSRs.
Although Agreement States do have some provisions specifically for
NARM, in general, the regulatory structure used by Agreement States
does not distinguish between NARM and other radioactive material. NARM
users in the Agreement States are expected to implement all aspects of
standards for their radiation protection programs with respect to NARM,
including those aspects relating to receipt, possession, use, storage,
transfer, transportation, and disposal of NARM. This regulatory
structure also subjects NARM users in the Agreement States to the same
licensing, inspection, and enforcement policies as those using other
byproduct, source, or special nuclear materials. In addition, this
regulatory structure allows for both specific and general licensing of
various NARM products, the distribution of certain NARM items to
persons exempt from regulation and, in most cases, includes provisions
to review and approve proposals for sealed sources and devices
containing NARM.
The Agreement States have regulated a vast array of NARM produced
for medical, industrial, research and development, commercial, and
consumer purposes. In many Agreement States, this regulatory structure
also captures some types of nondiscrete sources found in the oil and
gas industry or mining industry; moreover, it captures inadvertently
produced activation products from the use of proton beams for medical
radiation therapy. However, the regulation of these nondiscrete sources
and activation products varies from Agreement State to Agreement State.
Other Federal Agencies' Regulatory Authority Over NARM
Although the States had the primary responsibility for regulating
the use of NARM before the passage of the EPAct, certain Federal
regulations continue to apply under some circumstances, such as
environmental protection, workplace safety, drug safety,
transportation, and disposal. With the passage of the EPAct, the NRC
will have primary responsibility for radiation safety and in regulating
the use of these materials in cooperation with the States, with the
exception of those activities that are self-regulated by the DOE.
Other Federal agencies have regulations or have established
programs for self-regulating certain activities involving NARM. The
Department of Transportation (DOT) regulates interstate transport of
NARM. In cooperation with DOT, the NRC approves Type B packages through
regulations in 10 CFR Part 71. The EPA has established controls for
certain NARM through several authorities, including the Clean Air Act,
the Safe Drinking Water Act, the Toxic Substances Control Act, the
Resource Conservation and Recovery Act, and the Comprehensive
Environmental Response, Compensation, and Liability Act. The
Occupational Safety and Health Administration (OSHA) of the Department
of Labor has the oversight for occupational health and safety for
radiation protection. It has regulations governing radiation protection
in the workplace, including provisions addressing the exposure of
minors to radioactive material in the workplace, but defers to the NRC
on AEA materials. The Department of Commerce (DOC) has controlled the
export of radioactive material. Before the enactment of the EPAct, the
DOC regulated the export of all radium-226. With the enactment of the
EPAct, the NRC will regulate the export of discrete sources of radium-
226; DOC retains jurisdiction to regulate the export of nondiscrete
sources of radium-226. The Consumer Product Safety Commission
regulations have addressed hazardous substances other than byproduct,
source, and special nuclear materials currently regulated by the NRC.
The Food and Drug Administration (FDA) regulates all drugs (including
drugs containing radioactive materials) by requiring good manufacturing
practices to assure the purity, potency, and consistency of finished
drugs with their labeling in establishing the safety and effectiveness
of these drugs.
Section 651(e)(3) of the EPAct provides that byproduct material, as
defined by Section 11e.(3) or 11e.(4) of the AEA, may only be
transferred to and disposed of in a disposal facility that is adequate
to protect public health and safety, and is licensed by either the NRC
or a State that has entered into an agreement with the Commission under
Section 274b of the AEA or at a disposal facility in accordance with
any Federal or State solid or hazardous waste law, including the Solid
Waste Disposal Act, also known as the Resource Conservation and
Recovery Act (RCRA).
Development of the Suggested State Regulations (SSRs)
Since enactment of the AEA in 1954, scientists continue to develop
new technologies in producing radionuclides, such as the use of
particle accelerators. At the beginning of the 20th century, naturally
occurring radioactive material, including radium-226, was routinely
used in consumer products and in cancer treatment. Because there was no
Federal mandate to regulate these materials, most States have since
established regulatory structures for both accelerator-produced
radioactive material and naturally occurring radioactive material,
including radium-226.
In 1968, CRCPD was chartered as a nonprofit organization to provide
a forum for enhancing communication among States and Federal agencies
[[Page 55866]]
regarding radiation regulations and to promote a uniform radiation
protection environment for all radioactive material. Throughout the
years, CRCPD developed policies and guidance for its member States. In
addition, CRCPD is responsible for the development of model
regulations, known as the SSRs. Under the SSRs' regulatory framework,
NARM has been a regulated radioactive material comparable to byproduct
material. Nearly all of the Agreement States have based their
regulations on this model for NARM.
For NARM regulation only, CRCPD also established ``Licensing
States'' similar to the Agreement State Program under Section 274 of
the AEA. Licensing States recognized by CRCPD under criteria found in
Publication 94-8, ``CRCPD Recognition of Licensing States for the
Regulation and Control of NARM,'' are those States that have
demonstrated an adequate and consistent regulatory control program for
NARM. Licensing State designation assures comparable regulatory
structures with respect to NARM, and other States may grant reciprocal
recognition of their licenses or acceptance of their licensees'
manufactured products.
Issuance of Waiver on August 31, 2005
Section 651(e) of the EPAct became effective immediately upon
signature by the President on August 8, 2005. Before enactment of the
EPAct, the NRC did not have authority over NARM or regulations in place
that would specifically apply to this material. Nonetheless, persons
engaged in activities involving NARM could be, and States seeking to
continue regulation of NARM would be, in technical violation of the
AEA.
Section 651(e)(5) of the EPAct authorized the Commission to issue a
waiver of the requirements of Section 651(e) to any entity with respect
to NARM for specified periods of time if the Commission determined that
the waiver was in accordance with the protection of the public health
and safety and the promotion of the common defense and security. The
Commission determined that there was no basis to conclude that these
materials would not continue to be used in a manner that is protective
of public health and safety while the waiver is in effect. The
Commission also determined that it would be in the best interest of the
public to allow continued use of NARM, especially for medical purposes,
and to allow the States to continue to regulate NARM until the
Commission could codify new regulations for these materials.
The Commission believed that granting the waiver would allow the
States to continue with their regulatory programs, allow persons
engaged in activities involving NARM to continue their operations in a
safe manner, and allow continued access to medical
radiopharmaceuticals. In addition, it would enable the Commission to
work with the States in developing appropriate regulations for NARM and
in formulating a sound Transition Plan for implementation of these
regulations. It would also provide an opportunity for non-Agreement
States that currently do not have Agreement State regulatory programs
under Section 274b. of the AEA to consider entering into an agreement
with the NRC. The Commission determined that issuance of the waiver
would be in accordance with the protection of public health and safety
and the promotion of the common defense and security.
The Commission granted a waiver (70 FR 51581; August 31, 2005) from
the requirements of Section 651(e) of the EPAct to: (1) All persons
engaged in export from or import into the U.S. of byproduct material
through August 7, 2006, unless terminated sooner if the Commission
determined that an earlier termination was warranted; and except with
regard to the requirements of the DOC relating to export of byproduct
material; (2) all persons acquiring, delivering, receiving, possessing,
owning, using, or transferring byproduct material through August 7,
2009, unless terminated sooner if the Commission determined that an
earlier termination was warranted; and (3) all States that had entered
into an agreement with the Commission under Section 274b. of the AEA,
and States that had not entered into such an Agreement, through August
7, 2009, unless terminated sooner if the Commission determined an
earlier termination was warranted, or for an Agreement State if the
Commission made certain determinations required by Section
651(e)(5)(B)(ii) of the EPAct.
Stakeholder Involvement in the Rulemaking Process
The NRC took several initiatives in an effort to enhance
stakeholder involvement and to improve efficiency during the rulemaking
process. With assistance from the Organization of Agreement States
(OAS) and CRCPD, the NRC was able to obtain participation of several
State representatives in various working groups in the development of
the proposed rule. Principals from OAS and CRCPD, representing
interests for both Agreement States and non-Agreement States, also
participated in the steering committee forming a partnership with the
NRC in making rulemaking decisions. In an effort to keep stakeholders
informed, the NRC held a public roundtable meeting in early November.
In addition, the NRC has met with other Federal agencies to ensure
coordination regarding this rulemaking.
The NRC held a public meeting on November 9, 2005, to discuss
rulemaking activities to incorporate NARM into its regulatory
framework. The public meeting was in a ``roundtable'' format to allow
stakeholders an opportunity to discuss concerns and to enhance
interaction among all interested parties on the subject of the NRC
regulating NARM. Representatives from other Federal agencies, States,
and a broad spectrum of interest groups were invited to participate in
the ``roundtable'' discussion. A transcript of this meeting is
available via the NRC's and other related documents are available from
(see FOR FURTHER INFORMATION CONTACT section of this document.)
Following the public meeting, the NRC received five written
comments from interested parties related to the discussion at the
meeting and the rulemaking activities. These comment letters were
reviewed and considered by the NRC staff in the development of the
proposed rule.
In addition to the public meeting, the NRC interacted and met with
FDA staff to exchange information regarding the NRC's NARM rulemaking
efforts and the FDA's regulations for accelerator-produced drugs. The
primary objective of the FDA's regulations is to ensure medical safety,
purity, potency, and effectiveness of the drugs, and that of the NRC's
regulations is to ensure radiation safety. During the meeting, areas of
potential dual regulation were discussed. Because the NRC and the FDA
have different missions, the associated regulations are more
complementary than duplicative. FDA has published a proposed rule (70
FR 55038; September 20, 2005), ``Current Good Manufacturing Practice
for Positron Emission Tomography Drugs,'' and expects to finalize the
rule soon. The FDA's final rule will establish criteria for the
production and process/quality controls for the Positron Emission
Tomography (PET) drugs in PET centers registered with the FDA.
The NRC hosted a meeting of Federal agency representatives on
November 22, 2005, to discuss the development of a definition of
Discrete source to be added to the NRC's regulations. Agencies
represented at this meeting were DOT, DOE, including the National
Nuclear Security Administration, Department of
[[Page 55867]]
Defense, DOC, EPA, and the U.S. Customs and Border Protection. A draft
definition was formulated. This definition formed the basis for the
definition in the proposed rule, with only minor changes and text
rearrangement for clarity.
The NRC published the proposed rule to establish the regulatory
framework for the newly defined byproduct material on July 28, 2006 (71
FR 42952). Thirty-nine comment letters were received. The commenters
included a number of States, Federal agencies, professional
organizations, universities, medical communities, industries, and
individuals.
II. Discussion
A. The New, Expanded Definition of Byproduct Material
Section 651(e) of the EPAct expanded the definition of Byproduct
material to include: (1) Any discrete source of radium-226 that is
produced, extracted, or converted after extraction, before, on, or
after the date of enactment of the EPAct for use for a commercial,
medical, or research activity; (2) any material that has been made
radioactive by use of a particle accelerator and is produced,
extracted, or converted after extraction, before, on, or after the date
of enactment of the EPAct for use for a commercial, medical, or
research activity; and (3) any discrete source of naturally occurring
radioactive material, other than source material, that the Commission,
in consultation with the Administrator of the EPA, the Secretary of
DOE, the Secretary of DHS, and the head of any other appropriate
Federal agency, determines would pose a threat similar to the threat
posed by a discrete source of radium-226 to the public health and
safety or the common defense and security, and that is extracted or
converted after extraction, before, on, or after the date of enactment
of the EPAct for use in a commercial, medical, or research activity.
The NRC is revising the definition of Byproduct material in 10 CFR
Parts 20, 30, 50, 72, 150, 170, and 171 to be consistent with the
EPAct. The same revision to the definition of Byproduct material was
made in a separate rulemaking for 10 CFR Part 110 (April 20, 2006; 71
FR 20336). A different definition for the term Byproduct material is
used in 10 CFR Part 40, because 10 CFR Part 40 regulations are limited
to source material and the tailings or wastes associated with the
extraction or concentration of source material. Therefore, 10 CFR Part
40 regulations are not impacted by the EPAct, and the definition of
Byproduct material in that Part remains unchanged by this rule.
Since the publication of the proposed rule, and after considering
the comments on the new definition of byproduct material, the
Commission has taken a closer look at the scope of the Commission's
jurisdiction over the newly added byproduct material. The EPAct covers
discrete sources of radium-226 and accelerator-produced radioactive
material that is ``produced, extracted, or converted after extraction,
before, on, or after August 8, 2005, for use for commercial, medical,
or research activity'' (emphasis added). Notwithstanding that a
discrete source of radium-226 may have originated from a commercial
supplier, the Commission has determined that discrete sources of
radium-226 still in control of the military do not constitute
``commercial use'' under the EPAct, and are therefore, outside the
Commission's jurisdiction. Defining ``commercial use'' to include all
material supplied to the military from a commercial supplier would
result in virtually all military use of this material to be
``commercial use.'' This would vitiate any distinction that the EPAct
intended to make for military use, as opposed to commercial use, by
excluding military use from its coverage.
However, this exclusion from the coverage of the EPAct only applies
to a certain type of military use, i.e., NARM used for ``military
operations.'' The term ``military operations'' covers what is
traditionally understood as the military's primary mission for national
defense, including warfare, combat, and battlefield missions, and, of
course, training for battlefield missions. NARM used, or available for
use, for these purposes would be excluded from the coverage of the
EPAct and from the coverage of this rule. If the material is intended
for use in military operations, it is excluded from the coverage of
this rule notwithstanding the fact that it was originally produced by a
commercial supplier. In addition, ``military operational'' material
includes material still under the control of the military, i.e., in
storage, or material that may be subject to decontamination and
disposal.
Other use of NARM by the military would be covered by this rule.
Under the Commission's interpretation of the EPAct, NARM, whether
discrete sources or accelerator material, that is produced, extracted,
or converted for use or has been used, in medical or research
activities, or in a manner similar to a commercial activity, e.g.,
military museums, is covered by the EPAct and this rule. Furthermore,
NARM that was used for military operations but is no longer under the
control of the military, has been sold, or is in the possession of
private individuals, is also within the coverage of this rule.
The NRC intends to interact with the Department of Defense to
obtain a common understanding of the uses of radium-226 and
accelerator-produced radioactive material by the military to resolve
any potential issues regarding the application of the Commission's
interpretation of the EPAct in regard to any specific case of military
use.
Radium-226
Radium is a chemically reactive, silvery white, radioactive,
metallic element with an atomic number of 88 and symbol of Ra. Radium-
226, the most abundant and most stable isotope of radium, is formed by
the radioactive disintegration of thorium-230 in the decay series
starting with uranium-238. Radium-226 can be found in all uranium ores.
The half-life of radium-226 is 1599 years. Radium-226 emits alpha
particles and gamma radiation and decays to radon gas.
Although radium was discovered in the ore pitchblende by the
chemists Marie and Pierre Curie in 1898, no one understood the dangers
of radium until later in the twentieth century. Based on radium's
properties, especially its ability to stimulate luminescence,
industries started manufacturing hundreds of consumer products
containing radium. Radium was added to products such as hair tonic,
toothpaste, ointments, and elixirs. Radium paint was used in the mid-
1900s to paint the hands and numbers of some clocks, watches,
doorknobs, and other objects to make them glow in the dark. Glow-in-
the-dark watch and clock faces were particularly popular. Most of these
uses were eventually discontinued for health and safety reasons, but
its wide use in luminescent paints continued through World War II
because radium's luminescent glow made aircraft and vehicle dials,
gauges, and other instruments visible at night. Many of these early
products still remain in the possession of museums and individual
collectors. Large inventories of radium-226 luminescent military and
aircraft devices remain and periodically turn up in repair shops, and
have resulted in contamination incidents.
In more recent times, radium sources were used in industrial
radiography and industrial smoke detectors. Currently, radium sources
are still being used in some industrial products, such as industrial
gauges, that measure certain
[[Page 55868]]
physical properties such as moisture and density.
Accelerator-Produced Radioactive Material
Particle Accelerators
A particle accelerator is a device that imparts kinetic energy to
subatomic particles by increasing their speed through electromagnetic
interactions. Particle accelerators are used to produce radioactive
material by directing a beam of high speed particles at a target
composed of a specifically selected element, which is usually not
radioactive. Nuclei in the target are struck by the high speed
particles and undergo a nuclear transformation. A nuclide that is
struck is transformed into a different nuclide. By careful selection of
the target element, the particles accelerated, and the operating
parameters of the accelerator (e.g., beam energy), a resultant proton-
heavy nuclide can be produced. Usually the nuclide produced is
radioactive and is created for the use of its radiological properties.
The process of transforming nuclei from a stable element into a
radionuclide is called activation. In some cases, the target is
selected so that the accelerator produces a neutron beam that is, in
turn, used to activate nuclides that are then used for their
radioactive properties. Some particle accelerators are not used to
produce radioactive material, but instead the high energy beam produced
by the particle accelerator is used directly, for example, to treat
cancer patients.
The two basic designs of particle accelerators are linear and
circular, also known as cyclotron. In either case, charged particles
are injected into the accelerator to form a beam. The beam is
accelerated and focused onto the target. In the circular designs, the
beam must be directed to travel in a circular shaped path. For all
accelerators, the process of accelerating, focusing, and directing the
beam is accomplished by a combination of electrically charged
structures and magnetic fields in the accelerator. During operation,
these internal structures will be struck by particles from the beam and
activated incidentally.
Particle accelerators are often classified by the maximum energy of
the accelerated particles, expressed in megaelectron-volts (MeV). An
electron-volt is the amount of energy imparted to an electron by an
accelerating potential of one volt. The small cyclotrons that produce
radionuclides used in PET nuclear medicine usually operate at energies
of up to about 30 MeV. By comparison, the accelerators used in basic
physics research facilities reach energies in excess of 1000 MeV.
For the purposes of this rulemaking, the NRC divided particle
accelerators into three groupings: (1) Those that are always operated
to intentionally produce radioactive materials in quantities useful for
their radioactive properties for a commercial, medical, or research
activity; (2) those that are operated to produce only particle beams
and not radioactive materials; and (3) accelerators that are used to
produce both radioactive materials and particle beams for other uses.
Examples of accelerators that are operated to produce only particle
beams and not radioactive materials include linear accelerators used
for medical treatment of cancer and other health-related conditions.
Other examples include the experimental particle physics research
colliders used to probe the fundamental properties of nature (as long
as that is their only use) and electron microscopes, i.e., particle
accelerators that probe the structure of materials at a very small
dimension (high magnification). Ion implanters are particle
accelerators used to modify the electrical properties of materials in
semiconductor fabrication. In these activities, no radioactive material
is intentionally created; all activation is incidental to the intended
use of the accelerator.
The NRC will regulate the radioactive material both intentionally
and incidentally produced by all accelerators that are intentionally
operated to produce a radioactive material for its radioactive
properties. The NRC will not regulate the incidental radioactive
material produced by accelerators that are operated to produce only
particle beams and not radioactive materials for use for a commercial,
medical, or research activity. For those accelerators that are used to
produce both radioactive material and particle beams, the NRC will
regulate the intentionally produced radioactive material and all of the
incidentally produced radioactive material, including incidental
radioactive material produced when the accelerator is operated to
produce radioactive material, as well as incidental radioactive
material produced when it is operated to produce only a particle beam.
The incidental radioactive materials produced in these accelerators are
indistinguishable, so both will be considered byproduct material. The
NRC believes very few, if any, accelerators are operated in this way.
The EPAct does not give the NRC authority to regulate the
possession or use of particle accelerators. The NRC has not adopted any
rule regarding the operation of a particle accelerator or the
qualification of any person maintaining or operating a particle
accelerator. However, nothing in the EPAct directs the NRC to change
the policy that radiation safety standards must consider unregulated as
well as regulated sources of radiation. The NRC will continue to
require any person subject to the dose limits in 10 CFR Part 20 to
continue to include the radiation dose from the operation of a particle
accelerator in meeting the dose limitations. The NRC is aware that the
operation of a particle accelerator may activate materials in the
structure of the building and facilities housing the accelerator. The
NRC intends to assure the safe decommissioning of particle accelerator
buildings and facilities, including the removal and disposal of
activated building materials, to assure that the dose limits to members
of the public are not exceeded. The decommissioning of these facilities
will be required to meet the radiation dose limits in 10 CFR Part 20
Subpart E--Radiological Criteria for License Termination.
The majority of accelerator-produced radioactive material is now
created for use in medicine. The NRC is aware of only two operations in
the U.S. and a few importers, mostly from Europe and Canada, that are
commercial producers of accelerator-produced radioactive material for
use in industrial activities. The regulatory approach for manufacturing
accelerator-produced radioactive material for industrial purposes is
similar to the regulatory approach for manufacturing accelerator-
produced radioactive material for medical purposes.
Accelerator-Produced Radioactive Material Used in Medical Activities
Medical use of radioactive material began over 50 years ago. The
medical use of sealed and unsealed radioactive materials continues to
be an important component of medical specialties for both diagnosis and
therapy purposes. The use of small quantities of unsealed radioactive
materials (radiopharmaceuticals) in nuclear medicine is an integral
part of patient care and is extremely valuable in the early diagnosis
and treatment of medical conditions. Radiation oncology uses larger
amounts of radioactivity in sealed sources to deliver therapeutic or
palliative radiation doses.
Almost all reactor-produced byproduct radionuclides for radioactive
drugs are imported into the U.S., as well as most reactor-produced
radionuclides used in sealed sources, although some used in radioactive
drugs and sealed
[[Page 55869]]
sources are also produced in an NRC-regulated nonpower reactor.
Commercial manufacturers primarily use the imported radionuclides to
produce specific sealed sources, radioactive drugs, and biologics.
Commercial nuclear pharmacies may use radiochemicals to prepare
radioactive drugs, as well as commercially produced radioactive drugs
and drug sources, such as molybdenum-99/technetium-99m generators, to
prepare unit dosages of other radioactive drugs.
The U.S. has a limited number of commercial radionuclide production
facilities that use accelerators to produce radionuclides, such as
thallium-201, iodine-123, indium-111, and gallium-67 used in
radioactive drugs. A larger number of radionuclide production
facilities (often referred to as PET centers) use cyclotrons to produce
the PET radionuclides fluorine-18, carbon-11, nitrogen-13, and oxygen-
15 for use in PET radioactive drugs. PET radionuclides decay by
positron emission and, because of their relatively short half-life
(minutes to hours), are produced at locations in close proximity to the
patients (e.g., in hospitals or academic institutions) or at nearby
locations.
Palladium-103, the most common accelerator-produced medical use
radionuclide contained in a sealed source, was originally produced at
reactor facilities. Other radionuclides used in medical radiation
therapy can also be produced with either reactors or accelerators. With
the new definition of Byproduct material, sealed sources that can be
produced from either pathway will be uniformly regulated. At this time,
there are no teletherapy or remote afterloader or gamma stereotactic
radiosurgery units with accelerator-produced sources.
Because production accelerators for medical radionuclides (e.g.,
PET production facilities) and industrial radionuclides are used to
intentionally produce radioactive material for use of its radioactive
properties for a commercial, medical, or research activity, the NRC
will regulate both the radionuclides produced in these accelerators as
well as the incidentally activated radioactive material.
Other Naturally Occurring Radioactive Material With Similar Risk as
Radium-226
The EPAct amended the definition of Byproduct material to include
any discrete source of naturally occurring radioactive material, other
than source material, that the Commission, in consultation with the
Administrator of the EPA, the Secretary of Energy, the Secretary of
Homeland Security, and the head of any other appropriate Federal
agency, determines would pose a threat similar to the threat posed by a
discrete source of radium-226 to the public health and safety or the
common defense and security, and is extracted or converted after
extraction, before, on, or after the date of enactment of the EPAct for
use in a commercial, medical, or research activity.
The inclusion of discrete sources of naturally occurring
radioactive material into the definition of Byproduct material is
contingent on the Commission's determination, in consultation with
other Federal agencies, that these discrete sources would pose a threat
similar to the threat posed by a discrete source of radium-226. The NRC
has not currently identified any discrete sources of naturally
occurring radioactive material under this provision, and the rule does
not contain criteria for making such a determination. For comparison,
the International Atomic Energy Agency (IAEA) has identified a list of
sources that are considered to pose a high risk to human health and
safety if not managed safely and securely. The IAEA Code of Conduct on
the Safety and Security of Radioactive Sources (Code of Conduct)
identified certain quantities of 26 radionuclides that pose a
significant risk to individuals, society, and the environment. The
activity of these radionuclides at the IAEA Code of Conduct Category 1
or 2 level could be fatal or cause permanent injury to a person who
handled them or was otherwise in contact with them for a short time, if
not safely managed or securely protected. Of these 26 sources, only two
naturally occurring radionuclides are listed: Radium-226 and polonium-
210. Because this rule addresses discrete sources of radium-226, the
only other naturally occurring radioactive material similar in hazard
to radium-226 when using the IAEA criteria is polonium-210. However,
naturally occurring polonium is scarce. One ton of uranium ore contains
only about 100 micrograms (0.0001 grams) of polonium. Due to its
scarcity in nature, polonium-210 used for commercial purposes is
usually produced by bombarding bismuth-209 with neutrons in a nuclear
reactor and had been regulated by the NRC before the EPAct.
Additionally, polonium-210 is unlikely to be commercially used in
individual radioactive sources with activity levels that would place
them within the IAEA Code of Conduct Category 1 or 2. Hence, the NRC
has determined that no other discrete sources of naturally occurring
radioactive material pose a threat similar to the radium-226-level or
IAEA Code of Conduct Category 1 or 2 sources.
Through interaction with other Federal agencies and States during
development of the rule, the NRC concluded that, at this time, only
polonium-210 has the potential to pose a threat similar to the threat
posed by a discrete source of radium-226 to the public health and
safety or the common defense and security. The NRC had already been
regulating the use and possession of polonium-210 because it is
produced in nuclear reactors and is rarely extracted as naturally
occurring radioactive material. Therefore, although this rule adds this
category of byproduct material to the definitions in the regulations,
at this time, the NRC's regulations will not apply to any discrete
sources of naturally occurring radioactive material, other than radium-
226. The EPAct has provided a mechanism for the Commission to include
additional discrete sources of naturally occurring radioactive material
in the future following consultation with other Federal agencies, if
the need arises to consider other naturally occurring radioactive
material as byproduct material. No further revision to the regulations
will be necessary to begin regulating a material identified through
this mechanism. However, the NRC will provide an opportunity for public
input before applying its regulations to other naturally occurring
radionuclides that the NRC determines in consultation with other
federal agencies, pose a threat similar to the threat posed by discrete
source of radium-226.
B. The NRC's Regulatory Approach
Consideration of Suggested State Regulations for the Control of
Radiation (SSRs)
All 34 Agreement States have regulations for NARM. Twelve non-
Agreement States and certain U.S. Territories have some type of
regulatory structure for NARM, while four non-Agreement States have no
program for regulating NARM. The EPAct mandated that the NRC use model
State standards to the maximum extent practicable in issuing
regulations for the expanded definition of Byproduct material. The NRC
considered the SSRs published by CRCPD (https://www.crcpd.org/free_
docs.asp) as the model State standard in developing this rule. Most
Agreement States have regulated discrete sources of radium and
accelerator-produced radioactive
[[Page 55870]]
material in a manner similar to and under the same requirements as
reactor-produced radioactive material. Few provisions in the SSRs exist
solely to address these materials. Where specific provisions do exist
in the SSRs for these materials, they have been evaluated for possible
inclusion in the NRC's regulations.
For radionuclide-specific values listed in 10 CFR part 20,
Appendices B and C, the NRC found that there are no other radionuclides
identified in the SSRs that are not already included in 10 CFR part 20.
As discussed further in this document under Section C., ``Changes to
Existing NRC Regulations to Accommodate the New Byproduct Material,''
most of the specific provisions related to NARM radionuclides in the
SSRs have been adopted in this rule. These include exempt quantities in
10 CFR 30.18 and 10 CFR 30.71, an exemption for timepieces in 10 CFR
30.15, a general license for calibration and reference sources in 10
CFR 31.8, a general license for use of radioactive material for certain
in vitro clinical or laboratory testing in 10 CFR 31.11, contamination
limits for strontium-82/rubidium-82 generators, and requirements to
measure the contamination limits in 10 CFR 35.204 with corresponding
recordkeeping requirements in 10 CFR 35.2204.
While SSRs do exist that address other types of naturally occurring
radioactive material that are not covered by the EPAct or these new
regulations, discrete sources of radium and accelerator-produced
radioactive material are covered under the same provisions of the SSRs
that apply to reactor-produced radioactive material. There is general
agreement among the States, reflected in the SSRs, that the new
categories of byproduct material should be regulated under the same
requirements as reactor-produced radioactive material. This rule takes
the same regulatory approach. Most of the requirements that will apply
to users of the newly regulated material are preexisting NRC
requirements.
Other Related Rulemakings
The NRC amended its regulations in 10 CFR Part 110 revising the
definition of Byproduct material to include discrete sources of radium-
226, accelerator-produced radioactive material, and discrete sources of
naturally occurring radioactive material (71 FR 20336; April 20, 2006).
In addition, an earlier amendment (70 FR 37985; July 1, 2005) added
discrete sources of radium to 10 CFR Part 110, Appendix P. Together,
the two amendments satisfy the requirements of Section 651(d) of the
EPAct pertaining to the export or import of Category 1 or Category 2
radiation sources as defined by the IAEA Code of Conduct. By this final
rule, the NRC is again amending is regulations in 10 CFR Part 110 to
include a definition of Discrete source.
Section 651(d) of the EPAct also requires the NRC to issue
regulations establishing a mandatory tracking system for radiation
sources, including radium-226, in the U.S. The NRC issued a final rule
for national source tracking of sealed sources (71 FR 65686; November
8, 2006) that included radium-226 sources.
Definition of Discrete Source
The EPAct extended the definition of Byproduct material in the AEA
to include any discrete source of radium-226 and certain other
naturally occurring radioactive material that is produced, extracted,
or converted after extraction, before, on, or after the date of the
enactment of the EPAct, for use for a commercial, medical, or research
activity. The term Discrete source is not defined in the EPAct, and the
EPAct specifically mandates that the final regulations, in establishing
requirements necessary to carry out the amendment, shall include a
definition of the term Discrete source. The definition of Discrete
source is used for purposes of the new definition of Byproduct material
in the case of radium-226 and other naturally occurring radioactive
material other than source material. The term Discrete source is not
used in conjunction with accelerator-produced radioactive material in
the EPAct language.
Thus, the EPAct gave the NRC authority over discrete sources of
radium-226 but not over diffuse sources of radium-226. The EPAct did
not extend the NRC's authority over radium-226 as it occurs in nature,
or over other processes where radium-226 may be unintentionally
concentrated. The focus was on those materials that presented a threat
to public health and safety or to the common defense and security
similar to the threat posed by discrete radium-226 sources. Scale from
pipes used in the fossil fuel industry, fly ash from coal powerplants,
phosphate fertilizers, or residuals from treatment of water to meet
drinking water standards are not considered discrete sources. However,
uranium and thorium within these materials may become licensable source
material depending upon their concentration.
The definition of Discrete source in the proposed rule was ``a
radioactive source with physical boundaries, which is separate and
distinct from the radioactivity present in nature, and in which the
radionuclide concentration has been increased by human processes with
the intent that the concentrated radioactive material will be used for
its radiological properties.'' As a result of public comments on the
proposed rule, the NRC changed the wording of the definition of
Discrete source from that in the proposed rule. Discrete source is
defined in this final rule as ``a radionuclide that has been processed
so that its concentration within a material has been purposely
increased for use for commercial, medical, or research activities.''
The changes are for clarification purposes only and do not change the
original intent of the proposed definition of Discrete source or the
scope of the NRC's regulation of radium-226 or other naturally
occurring radioactive materials identified in the future. The intent of
the revised definition continues to be consistent with the proposed
rule in that the NRC's authority is not intended to extend to all
naturally occurring radioactive material, specifically not to naturally
occurring radioactive material that is found in nature in its original
form and location, or that which is moved or concentrated inadvertently
by some man-made process. A discrete source will have the same
radiological characteristics (e.g., type of radiation, half-life) as
the radionuclide found in nature but will have been purposefully
concentrated for use for its specific properties after it has been
removed from its original location in nature. This definition excludes
the NRC's jurisdiction over inadvertent movement or concentration of
naturally occurring radioactive material such as scale from pipes used
in the fossil fuel industry, fly ash from coal power plants, or
phosphate fertilizers. It also excludes NRC jurisdiction over residuals
from treatment of water. While radium, in particular, may be
intentionally concentrated in this case, it is not for the purpose of
using the radium, but to improve water quality. Only if, and when, this
radium were further processed for use would it be considered a discrete
source, and thus byproduct material. Neither the changes to the AEA as
a result of the EPAct, nor anything in this rulemaking changes the
NRC's authority, in any manner, over source material.
The words ``a radionuclide that has been processed so that its
concentration within a material has been purposely increased'' are
intended to further clarify that the extraction or processing relates
to the intent to use the radionuclide itself, and not a material
[[Page 55871]]
that happens to contain the radionuclide, such as fertilizer. The
addition of the phrase ``for use for commercial, medical, or research
activities'' repeats a constraint that also appears in the definition
of Byproduct material. The NRC has repeated this constraint in order to
ensure that when the term ``discrete source'' is used separately from
the term ``byproduct material,'' it will not be interpreted more
broadly, but it will be clear that only material which is intended for
use for commercial, medical, or research activities is being
referenced.
It should also be noted that in accordance with this definition of
Discrete source, once a discrete source meets the definition of
Byproduct material, any contamination resulting from the use of such
discrete sources of this byproduct material will also be considered
byproduct material. This issue is discussed further in this document
under ``Summary and Analysis of Public Comments on the Proposed Rule.''
C. Changes to Existing NRC Regulations To Accommodate the New Byproduct
Material
The Commission has authority to issue both general and specific
licenses for the use of byproduct material and to exempt byproduct
material from regulatory control under Section 81 of the AEA. A general
license, as provided by regulation, grants authority to a person for
certain activities involving byproduct material and is effective
without the filing of an application with the Commission or the
issuance of a licensing document to a particular person. Requirements
for general licensees appear in the regulations and are designed to be
commensurate with the specific circumstances covered by each general
license.
In considering the expansion of the definition of Byproduct
material to include discrete sources of radium-226 and accelerator-
produced radioactive material, the NRC has evaluated products and
materials previously approved by the States for use under an exemption
from licensing and under a general license. Generally, the NRC's intent
in this rule is to accommodate existing products and materials that
were previously regulated by the States under similar provisions, if
the potential doses are similar to those expected from other currently
regulated products and materials. Many of these products have not been
made for some time, so some of the provisions in this rule are limited
to items manufactured in the past, which may still be in use or in
storage.
The bases of these exemptions and general licenses are primarily
the SSRs and also information in NRC's sealed source and device (SS&D)
registry. The SS&D registry is the NRC's national database of technical
information on sealed sources and devices. Manufacturers or
distributors may submit a request to the NRC for an evaluation of a
product's radiation safety information and for registration of the
product. After satisfactory completion of the evaluation, the NRC
issues a certificate of registration to the person making the request,
and this certificate is added to the SS&D registry. Many Agreement
States have similar registration procedures, and registration
certificates for the sources and devices they review are added to the
national SS&D registry. The NRC also has included SS&D certificates for
NARM, which have been issued by the States. While this is not a
complete database with respect to NARM, it includes detailed
information about many products containing NARM previously evaluated by
the States. In addition to SSRs and the information in the SS&D
registry, the specific provisions of the various States also were
considered in developing this rule.
Regulating Items Containing Radium-226
Currently, items or products containing radium-226 are unique in
that there are no new items in consumer commerce using radium-226
byproduct material. Although certain industrial devices such as
moisture density gauges containing radium-226 are still in use, most
radium-226 articles have not been produced for at least 20 years.
Beginning in the early 1900s, radium-226 was used to make self-
luminescent paint and incorporated in watch and clock dials and hands
and later used to illuminate airplane instrumentation dials and gauges
as well as markers and signs. Beginning in the 1950s, other
radionuclides began to replace radium-226 as a self-luminescent
material due to the recognition of the radiological hazard associated
with radium-226. Currently, the radionuclides of choice for self-
luminescent applications are promethium-147 and tritium due to the much
reduced radiological hazard vis-a-vis radium-226.
Based on the National Council on Radiation Protection and
Measurements in Report 95, ``Radiation Exposure of the U.S. Population
from Consumer Products and Miscellaneous Sources,'' radium-226 has not
been used in radioluminescent watches since 1968 and clocks since 1978.
In fact, radium-226 timepieces are currently kept largely as
collectors' items and only infrequently used by consumers as
timepieces. When originally manufactured, the quantity of radium-226
employed in watch and clock dials and hands varied by timepiece size,
manufacturer, model, and from item to item. While the quantity of
radium-226 varied in the timepieces, there is a general agreement for
typical average and upper bound quantities. Based upon the spectrum of
timepiece sizes, wristwatches have the smallest quantity, with pocket
watches and clocks having quantities several times higher than
wristwatches. The radioactivity associated with wristwatches is
generally on the order of several kilobecquerel (kBq) (tenths of a
microcurie ([mu]Ci)) with an average of 5.6 kBq (0.15 ([mu]Ci)). Pocket
watches may have radioactivity of about 13 kBq (0.35 [mu]Ci), and
clocks are typically 18 kBq (0.5 [mu]Ci). However, collections of
pocket watches and clocks are rare when compared to wristwatches.
Before the discontinuation of the manufacturing of timepieces
containing radium-226 in the 1970s, radium-226-illuminated timepieces
were widely distributed throughout the country as a common consumer
product. To date, a large number of radium-226 timepieces are still
owned by individuals as valued heirlooms or collectors' items or are on
display in museums. Because museums and collectors normally collect a
wide range of timepieces, a portion of their collection may contain
radium-226 timepieces. Some businesses and a few collectors are also
engaged in repairing and refurbishing timepieces either as a hobby or
professionally, and these activities may occasionally involve
timepieces containing radium-226. Because these timepieces were
manufactured before the NRC assumed regulatory authority over radium-
226, and because these timepieces are already in public possession, the
NRC intends to minimize regulatory impact to individuals, museums, or
other entities in possession of these timepieces. In finalizing the
rule, the NRC made its determination based on no significant risk to
public health and safety and the environment.
In the proposed rule, the NRC proposed to exempt intact timepieces
containing no more than 37 kBq (1 [mu]Ci) of radium-226 per timepiece
and repair of no more than 10 timepieces in any one year. In addition,
the NRC proposed to generally license no more than 50 timepiece hands
and dials used or stored at the same location at any one time. Due to
lack of sufficient health and safety information to make a final
regulatory decision, the NRC conducted
[[Page 55872]]
a scoping study for estimating potential radiological doses to
individuals associated with use, storage, and repair of radium-226
timepieces. The scoping approach taken by the NRC used widely accepted
methods and employed conservative assumptions for various scenarios
involving use, storage, and repair of radium-226 timepieces. Because
the scoping study was designed to be conservative and meaningful and
yet easy to perform, it is to be expected that the actual doses would
be significantly lower than those predicted by the scoping study.
To evaluate the potential doses associated with the proposed
exemption of radium-226 timepieces, 37 kBq (1 [mu]Ci) of radium-226 per
timepiece was used in the scoping study instead of the typical average
activities for timepieces, which provided for additional conservatism.
Radon-222 is a decay product in the radium-226 decay series and may be
emitted from the timepiece into the surrounding atmosphere and thus
result in exposure to an individual in proximity to the timepiece. It
is believed that the radon-222 emanating from the paint is almost
totally trapped within the watch. Because of the age of radium-226
timepieces, and because there is no established method for quantifying
the trapping behavior, the scoping study conducted by the NRC assumed
that the entire inventory of decay products instantly escaped and
became uniformly distributed into the surrounding building volume. This
assumption is obviously very conservative. As a result, the estimated
inhalation doses associated with radon-222 are extremely conservative.
The scoping study found that the estimated doses to a collector for
repair, storage, and use of a radium-226 timepiece range from a
fraction of 0.01 millisievert/yr (mSv/yr) [1 millirem/yr (mrem/yr)] to
a few mSv/yr (mrem/yr) to over 1 mSv/yr (100 mrem/yr).
At one time, there were repair facilities refurbishing radium
timepieces on a regular basis by replacing radium-226 paint with
tritium paint. Scraping off the radium-226 paint may have resulted in
significant contamination. The NRC is not aware of any current
operations in which individuals are still routinely handling radium
watches in such a way as to create a contamination problem. Based upon
the estimated doses for repairs, the NRC believes that a specific limit
on the annual number of repairs is not necessary. As long as these
repairs are taking place under a general license, actions could always
be taken if the Commission receives information that suggests that the
public health and safety are not being adequately protected.
The NRC's intent is to minimize regulatory impact on those private
collectors and museums as much as possible, and to be as consistent as
possible with the regulatory approach taken by the Agreement States,
many of whom have been regulating radium-226 for several decades.
Accordingly, in light of the public comments received, the Agreement
States' rulemaking involvement and the results of the scoping study in
finalizing the rule, the NRC revised the proposed revisions related to
radium-226 timepieces. Primarily, the change made in this final rule is
to broaden the general license provision for the radium-226 timepieces.
Specifically, the NRC has concluded that a finite number of annual
repairs as well as a limitation on the number of nonintact timepieces
and timepiece hands and dials is unnecessary and not warranted based
upon the NRC's understanding of radium-226 timepieces either in
collections or in use. As a result of the scoping study and in response
to public comments, the NRC has concluded that it is appropriate to
recategorize the repair of timepieces from an activity allowed under an
exemption from licensing to one covered by a general license. This
categorization is also more consistent with the Agreement States'
existing exemption provision.
Although not mandated by regulations, the NRC advises that
individual collectors or persons engaged in repair of these devices
should use good practices such as wearing gloves when handling radium-
226 timepieces, hands, and dials, and washing hands to minimize
potential exposure to the radioactive material. In addition, individual
collectors should ensure that storage areas are well ventilated to
minimize potential exposure due to accumulation of radon-222 gas and
should avoid unnecessary exposure to these types of timepieces.
Exemptions From Licensing
In 10 CFR Part 30, a number of exemptions from licens