Physical Protection of Byproduct Material, 33902-33947 [2010-13319]
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Federal Register / Vol. 75, No. 114 / Tuesday, June 15, 2010 / Proposed Rules
NUCLEAR REGULATORY
COMMISSION
10 CFR Parts 30, 32, 33, 34, 35, 36, 37,
39, 51, 71, and 73
[NRC–2008–0120]
RIN 3150–AI12
Physical Protection of Byproduct
Material
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AGENCY: U. S. Nuclear Regulatory
Commission.
ACTION: Proposed rule.
SUMMARY: The U.S. Nuclear Regulatory
Commission (NRC) is proposing to
amend its regulations to establish
security requirements for the use and
transport of category 1 and category 2
quantities of radioactive material, which
the NRC considers to be risk-significant
and therefore to warrant additional
protection. Category 1 and category 2
thresholds are based on those
established in the International Atomic
Energy Agency (IAEA) Code of Conduct
on the Safety and Security of
Radioactive Sources which NRC
endorses. The objective of this proposed
rule is to provide reasonable assurance
of preventing the theft or diversion of
category 1 and category 2 quantities of
radioactive material. The proposed
regulations would also include security
requirements for the transportation of
irradiated reactor fuel that weighs 100
grams or less in net weight of irradiated
fuel. The proposed rule would affect
any licensee that is authorized to
possess category 1 or category 2
quantities of radioactive material, any
licensee that transports these materials
using ground transportation, and any
licensee that transports small quantities
of irradiated reactor fuel.
DATES: Submit comments on the
proposed rule by October 13, 2010.
Submit comments specific to the
information collection aspects of this
proposed rule by July 15, 2010.
Comments received after the above
dates will be considered if it is practical
to do so, but the NRC is able to assure
consideration only for comments
received on or before these dates.
ADDRESSES: You may submit comments
by any one of the following methods.
Please include Docket ID NRC–2008–
0120 in the subject line of your
comments. Comments submitted in
writing or in electronic form will be
posted on the NRC Web site and on the
Federal rulemaking Web site
Regulations.gov. Because your
comments will not be edited to remove
any identifying or contact information,
the NRC cautions you against including
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any information in your submission that
you do not want to be publicly
disclosed.
The NRC requests that any party
soliciting or aggregating comments
received from other persons for
submission to the NRC inform those
persons that the NRC will not edit their
comments to remove any identifying or
contact information, and therefore, they
should not include any information in
their comments that they do not want
publicly disclosed.
Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for documents filed under Docket ID
NRC–2008–0120. Address questions
about NRC dockets to Carol Gallagher
301–492–3668; e-mail
Carol.Gallagher@nrc.gov.
Mail comments to: Secretary, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, Attn:
Rulemakings and Adjudications Staff.
E-mail comments to:
Rulemaking.Comments@nrc.gov. If you
do not receive a reply e-mail confirming
that we have received your comments,
contact us directly at 301–415–1677.
Hand-deliver comments to: 11555
Rockville Pike, Rockville, Maryland
20852, between 7:30 am and 4:15 pm
Federal workdays. (Telephone 301–415–
1677).
Fax comments to: Secretary, U.S.
Nuclear Regulatory Commission at 301–
415–1101.
You may submit comments on the
information collections by the methods
indicated in the Paperwork Reduction
Act Statement.
You can access publicly available
documents related to this proposed rule
using the following methods:
NRC’s Public Document Room (PDR):
The public may examine and have
copied for a fee publicly available
documents at the NRC’s PDR, Public
File Area O–1 F21, One White Flint
North, 11555 Rockville Pike, Rockville,
Maryland.
NRC’s Agencywide Documents Access
and Management System (ADAMS):
Publicly available documents created or
received at the NRC are available
electronically at the NRC’s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this page,
the public can gain entry into ADAMS,
which provides text and image files of
NRC’s public documents. If you do not
have access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC’s
PDR reference staff at 1–800–397–4209,
301–415–4737 or by e-mail to
pdr.resource@nrc.gov.
Federal Rulemaking Web site: Public
comments and supporting materials
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related to this proposed rule can be
found at https://www.regulations.gov by
searching on Docket ID NRC–2008–
0120.
FOR FURTHER INFORMATION CONTACT:
Merri Horn, Office of Federal and State
Materials and Environmental
Management Programs, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: (301) 415–
8126, e-mail: Merri.Horn@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
II. Discussion
A. General Applicability
B. Background Investigation and Access
Authorization Program
C. Physical Protection During Use
D. Transportation Security
III. Discussion of Proposed Amendments by
Section
IV. Criminal Penalties
V. Agreement State Compatibility
VI. Plain Language
VII. Voluntary Consensus Standards
VIII. Finding of No Significant
Environmental Impact: Availability
IX. Paperwork Reduction Act Statement
X. Regulatory Analysis
XI. Regulatory Flexibility Certification
XII. Backfit Analysis
I. Background
The NRC has long participated in
efforts to address radioactive source
protection and security. However, the
terrorist attacks of September 11, 2001,
heightened concerns about the use of
risk-significant radioactive materials in
a malevolent act. Such an attack is of
particular concern because of the
widespread use of radioactive materials
in the United States by industrial,
medical, and academic institutions. The
theft or diversion of risk-significant
quantities of radioactive materials could
lead to their use in a radiological
dispersal device (RDD) or a radiological
exposure device (RED).
The NRC’s current regulations
provide requirements for the safe use,
transit, and control of licensed material.
Any loss of control of risk-significant
radioactive material, whether
inadvertent or through a deliberate act,
could result in significant adverse
impacts that could reasonably constitute
a threat to the public health and safety
or the common defense and security of
the United States. In the changed threat
environment after the attacks of
September 11, 2001, the Commission
determined that certain licensed
material should be subject to enhanced
security requirements and safeguarded
during transport, and that individuals
with unescorted access to risksignificant quantities of radioactive
material should be subject to
background investigations.
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As part of the development of the
enhanced security measures, the NRC
performed vulnerability assessments to
identify gaps or vulnerabilities in
security and the effectiveness and costs
of certain physical protection
enhancements at various licensed
facilities. The results of the
vulnerability assessments were used in
the development of security
enhancement orders that were issued to
licensees using a graded approach based
on the relative risk and quantity of
material possessed by the licensee. The
NRC issued the first series of orders to
certain panoramic and underwater
irradiator licensees that possessed more
than 370 TBq (10,000 Ci) of radioactive
material (EA–02–249; June 6, 2003) (68
FR 35458; June 13, 2003). The next
series of orders were issued to certain
manufacturing and distribution (M&D)
licensees (EA–03–225; January 12, 2004)
(69 FR 5375; February 4, 2004). These
orders require the implementation of
additional security measures and the
protection of the licensee’s physical
protection information as Safeguards
Information—Modified Handling (SGI–
M). The original orders are not publicly
available because they contain detailed
security requirements that are
designated as SGI–M. However,
redacted versions of these orders have
been made available to the public (73
FR 33859; June 13, 2008, and 73 FR
49714; August 22, 2008). These orders
were issued to both NRC and Agreement
State licensees under the NRC’s
authority to protect the common defense
and security. Subsequently, the NRC
issued Increased Control Orders (EA–
05–090; November 14, 2005) (70 FR
72128; December 1, 2005) to other
licensees authorized to possess certain
risk-significant quantities of radioactive
material (category 1 and category 2
quantities). The Increased Control
Orders do not contain safeguards
information (SGI) or SGI–M and are
available on the NRC’s public Web site
at https://www.nrc.gov/security/
byproduct/orders.html. These orders
were issued under the NRC’s authority
to protect public health and safety, and
require licensees to implement
enhanced security measures known as
Increased Controls. To effect nationwide
implementation of the Increased Control
Orders, each Agreement State issued
legally binding requirements to put
enhanced security measures, identical
to the Increased Controls, in place for
licensees under that State’s regulatory
jurisdiction.
These security orders specifically
address the security of byproduct
material possessed in quantities greater
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than, or equal to, category 1 and
category 2 quantities. The orders
provide for enhanced security measures
for such things as license verification
before transfer, intrusion detection and
response, access control, and
coordination with local law
enforcement authorities (LLEAs). The
orders also contain requirements for the
licensee to determine the
trustworthiness and reliability of
individuals permitted unescorted access
to risk-significant radioactive materials.
The determination involves a
background investigation of the
individual. The background
investigations were originally limited to
local criminal history records checks
with law enforcement agencies,
verification of employment history,
education, personal references, and
confirmation of employment eligibility
(legal immigration status).
In 2005, Congress passed, and the
President signed, the Energy Policy Act
of 2005 (EPAct). The EPAct amended
Section 149 of the Atomic Energy Act
(AEA) to authorize the Commission to
require to be fingerprinted any
individual who is permitted unescorted
access to radioactive material or other
property subject to regulation by the
Commission that the Commission
determines to be of such significance to
the public health and safety or the
common defense and security as to
warrant fingerprinting and a Federal
Bureau of Investigation (FBI) criminal
history records check. With this new
authority, the Commission determined
that individuals who have access to
category 1 and category 2 quantities of
radioactive material warrant
fingerprinting and FBI criminal history
records checks. On October 17, 2006,
the NRC issued orders to panoramic and
underwater irradiator licensees (EA–06–
248) (71 FR 63043; October 27, 2006),
manufacturer and distributor licensees
(EA–06–250) (71 FR 63046; October 27,
2006), and licensees making shipments
of category 1 quantities of radioactive
material (EA–06–249) (71 FR 62302;
October 24, 2006) to require
fingerprinting and FBI criminal history
records checks for unescorted access to
risk-significant quantities of radioactive
material at their facilities. In issuing
these orders, NRC noted that a
malevolent act by an individual with
unescorted access to these materials
could result in significant adverse
impacts to the public health and safety
or the common defense and security
and, thus, necessitated expedited
implementation of fingerprinting
requirements. The orders were issued to
both NRC and Agreement State
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licensees under the NRC’s authority to
protect the common defense and
security. On December 5, 2007, the NRC
issued orders to all other NRC licensees
that possessed category 1 or category 2
quantities of radioactive material (EA–
07–305) (72 FR 70901; December 13,
2007) to require fingerprinting and FBI
criminal history records checks for
unescorted access to category 1 or
category 2 quantities of radioactive
material. These orders were issued
under the NRC’s authority to protect the
public health and safety and are
available on the NRC public Web site at
https://www.nrc.gov/security/byproduct/
orders.html. To effect nationwide
implementation, each Agreement State
issued legally binding requirements to
licensees under their regulatory
jurisdiction.
During the same time period, efforts
were underway to enhance
transportation security of category 1 and
category 2 quantities of radioactive
materials. The NRC issued two sets of
orders to licensees transporting
radioactive material in quantities of
concern. The first set of transportation
security orders was issued to certain
licensees that might be expected to
transport radioactive materials in
quantities of concern (category 1
quantities) (EA–05–006; July 19, 2005)
(70 FR 44407; August 2, 2005). The
orders require the implementation of
additional security measures and the
protection of the licensee’s physical
protection information as SGI–M. The
original orders are not publicly available
because they contain detailed security
requirements that are designated as
SGI–M. However, a redacted version of
the order is publicly available (73 FR
51016; August 29, 2008). These orders
were issued to both NRC and Agreement
State licensees under the NRC’s
authority to protect the common defense
and security. Subsequently, the NRC
issued orders (EA–05–090; November
14, 2005) (70 FR 72128; December 1,
2005) to other licensees authorized to
possess certain risk-significant
quantities of radioactive material
(category 2 quantities). The Increased
Control Orders mentioned earlier also
contain requirements for transporting
category 2 quantities of radioactive
material.
These security orders specifically
address the transportation security of
byproduct material transported in
quantities greater than, or equal to,
category 2. The additional security
measures contained in the orders
provide for enhanced security measures
during transportation that are beyond
the current regulations, including
enhanced security in preplanning and
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coordinating shipments, advance
notification of shipments to the NRC
and States through which the shipment
will pass, control and monitoring of
shipments that are underway,
trustworthiness and reliability of
personnel, information security
considerations, and control of mobile or
portable devices.
The requirements put in place by the
orders supplement the existing
regulatory requirements. These
additional requirements are primarily
intended to provide reasonable
assurance of preventing the theft or
diversion of this risk-significant
material. These requirements provide
the Commission with reasonable
assurance that public health and safety
and the common defense and security
continue to be adequately protected.
Although an order, like a rule, is
legally binding on the licensee receiving
the order, a rule is generally applicable
to all licensees. Further, the notice-andcomment rulemaking process allows
members of the public to provide
comments on the proposed rule. It is
Commission policy to implement
generally applicable requirements
through rulemaking.
If promulgated, this rulemaking
would adopt security requirements for
category 1 and category 2 quantities of
radioactive material into the regulations.
New requirements for background
investigations and an access
authorization program are proposed to
ensure that individuals who have access
to these materials have gone through
background investigations and are
determined to be trustworthy and
reliable. New requirements are also
proposed to establish physical
protection systems to detect, assess, and
respond to unauthorized access to
category 1 and category 2 quantities of
radioactive material. For transport of the
radioactive materials, new requirements
for recipient license verification;
preplanning and coordination of
shipments; advance notification of
shipments; notification of shipment
delays, schedule changes, and suspected
loss of a shipment; and control and
monitoring of shipments are proposed.
The proposed amendments would also
include security requirements for
shipments of irradiated reactor fuel that
weighs 100 grams (0.22 pounds (lb)) or
less in net weight of irradiated fuel,
exclusive of cladding or other structural
or packaging material, which has a total
external radiation dose rate in excess of
1 sievert (Sv) (100 rem) per hour at a
distance of 0.91 meters (m) (3 feet (ft))
from any accessible surface without
intervening shielding.
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In developing the proposed rule the
NRC considered, among other things,
the various security orders, lessonslearned during implementation of the
orders, the recommendations of the
Independent External Review Panel and
the Materials Program Working Group,
and stakeholder comments received on
the orders and the preliminary rule
language that was posted on
Regulations.gov. The Commission
chartered the Independent External
Review Panel to: (1) Identify
vulnerabilities in the NRC’s materials
licensing program with respect to
import, export, specific, and general
licenses; (2) validate the ongoing
byproduct material security efforts; and
(3) evaluate the apparent ‘‘good faith
presumption’’ that pervades the NRC
licensing process. The Panel’s March
2008 report is available in ADAMS
under accession number ML080700957.
The Materials Program Working Group
conducted a comprehensive evaluation
of the materials program to identify
short- and long-term strategies to
mitigate security vulnerabilities. The
Working Group report contains sensitive
information and is not publicly
available. However, the Group’s
comments on the Panel’s report are
publicly available in ADAMS under
accession number ML080660424.
In developing the basis for the
transportation security aspects of the
rule, NRC held three public meetings to
seek public comment on the
development of the technical basis. The
NRC published information on the
requirements being considered along
with some background information and
a notice of the three meetings (73 FR
826; January 4, 2008). In response the
NRC received more than 100 comments
from stakeholders that were used to
finalize the technical basis for the
transportation portion of this
rulemaking. The comments addressed a
number of issues and concerns.
However, most focused on clarifying
requirements, adding efficiencies, and
improving the processes that licensees
follow to comply with the additional
security measures currently enforced
under security orders.
During the development of the
proposed rule, the NRC posted
preliminary rule text for public
comment on https://www.regulations.gov
under Docket ID NRC–2008–0120. The
posting of the preliminary rule text was
noticed in the Federal Register and
included the portions of the rule that
address background investigation and
access control aspects (subpart B) (74 FR
17794; April 17, 2009), enhanced
security during use (subpart C) (74 FR
20235; May 1, 2009), and transportation
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security aspects (subpart D) (73 FR
69590; November 19, 2008). The NRC
allowed a 45-day comment period for
each subpart. In the documents
announcing the availability of the
preliminary regulatory text, the NRC
made it clear that it would not respond
to any of the comments received during
this pre-rulemaking stage. The NRC did
consider the public input on the
preliminary rule text in finalizing the
proposed rule, and areas where they
made a substantive change based on the
comments are discussed in this
Statement of Considerations. The NRC
also made some editorial changes based
on the comments; these changes are not
discussed further.
PRM–71–13
On July 16, 2008 (73 FR 40767), the
NRC published the resolution and
closure of a petition for rulemaking
(PRM) filed by Christine O. Gregoire,
Governor of the State of Washington
(PRM–71–13). The NRC indicated that
the issues raised by the petitioner would
be considered in an ongoing rulemaking
on the security requirements for the
transportation of radioactive material in
quantities of concern.
The petitioner requested that the NRC
adopt the use of global positioning
system (GPS) tracking as a national
requirement for vehicles transporting
highly radioactive mobile or portable
radioactive devices. The petitioner
stated that the Commission could
instead grant States the flexibility to
impose more stringent requirements
than those required under the current
increased controls. The petitioner
believes that GPS technology is an
effective and relatively inexpensive tool
that will help when a vehicle with
radioactive material is missing, but also
acknowledged that requiring a GPS on
these vehicles does not ensure that the
radiological source will be found.
However, the petitioner believes that
these suggestions would give law
enforcement a significant advantage.
The NRC considered the issues
identified by the petitioner and the
petitioner’s suggested approach to
address those issues in the development
of this proposed rule.
II. Discussion
The NRC believes that a new part of
the Code of Federal Regulations (CFR)
should be established for the security
requirements for use of category 1 and
category 2 quantities of radioactive
material. The concept for using a
separate part for safety and physical
protection requirements has already
been established for special nuclear
material (10 CFR part 73). The
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establishment of a new part for securityrelated requirements for byproduct
material would be more effective and
efficient compared to interspersing the
requirements with safety requirements
or placing them with the part 73
security requirements for special
nuclear material. A new part
specifically directed to byproduct
material licensees should make
applicable requirements easier for both
licensees and other stakeholders to
locate and understand.
This discussion section has been
divided into four subsections to better
present information on the proposed
rule. Each section presents information
on a different aspect of the proposed
rule. Section A provides information
that is generally applicable to all aspects
of this proposed rulemaking. Section B
provides information on background
investigations and the access
authorization program. Section C
provides information on the physical
protection of the materials during use.
Lastly, Section D provides information
on transportation security aspects.
A. General Applicability
1. What action is the NRC taking?
The NRC is proposing to amend its
regulations to impose security
requirements for the use of category 1
and category 2 quantities of radioactive
material. The proposed requirements
would establish the objectives and
minimum requirements that licensees
must meet to protect against theft or
diversion. These requirements are
intended to increase the protection of
the public against the unauthorized use
of category 1 or category 2 quantities of
radioactive material by reducing the risk
of the theft or diversion of the material.
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2. Why do the requirements need to be
revised?
Prior to September 11, 2001, NRC
requirements focused on safety and
preventing inadvertent or accidental
exposure of both workers and the public
to these materials. These requirements
also indirectly provided security for the
material. However, the events of
September 11 made the NRC take a
broader look at its requirements and
reevaluate what a terrorist might do to
attain these materials. From this effort,
the NRC identified several areas where
additional requirements should be
knife devices; self-shielded irradiator
licensees (including blood irradiators);
teletherapy unit licensees;
radiographers; well loggers; broad scope
users; radioisotope thermoelectric
generator licensees; and licensees that
ship or prepare for shipment category 1
or category 2 quantities of radioactive
material. Nearly 1,400 licensees are
implementing the various orders and are
the entities that would be impacted by
this proposed rule. In addition, some
fuel cycle and reactor licensees that
possess sources at these levels would be
impacted. Licensees whose activities are
covered under the physical protection
requirements of 10 CFR part 73 would
be exempt from the requirements of 10
CFR part 37. For example, a reactor
licensed under part 50 that also
possesses a radiography source would
not need to implement the part 37
provisions if the source is protected
under the reactor security program
required by part 73.
implemented to improve security. The
security requirements need to be placed
in the regulations so that they are
generally applicable to all licensees and
to provide an opportunity for all
stakeholders to comment on the
proposed requirements.
3. Why doesn’t the NRC just keep the
orders in effect?
The orders issued by the NRC could
stay in place indefinitely. However, the
regulations would not reflect current
Commission policy or requirements.
Imposing long-term requirements
through orders has not traditionally
been the agency’s preferred method of
regulation. Orders, unlike rules, do not
apply prospectively to applicants for
new licenses. The NRC would have to
periodically issue new orders to cover
new and amended licenses, and perhaps
reissue orders periodically to existing
licensees if requirements or
administrative practices change. In
order to make the requirements
generally applicable to all present and
future licensees, the security-related
requirements need to be placed in the
regulations.
Assured that adequate security is in
place for these materials (because of
existing regulations and orders), the
NRC is now planning to formally revise
its security requirements and gather
public and stakeholder input. The
orders would remain in place for NRC
licensees until the final rule becomes
effective. Once the final rule is effective,
the NRC will rescind the orders that
were issued to its licensees. For
Agreement State licensees that received
an NRC order, the order would remain
in place until the Agreement State
issues compatible requirements. Once
the State has issued its requirements,
the NRC would rescind the order. Each
Agreement State would follow its own
process for replacing the increased
control legally binding requirements
with the requirements contained in the
final rule.
5. What are category 1 and category 2
quantities of radioactive material?
Category 1 quantities of radioactive
material have been called radioactive
material in quantities of concern
(RAMQC). Category 1 and category 2
quantities of radioactive material have
been called risk-significant radioactive
material and refer specifically to 16
radioactive materials (14 single
radionuclides and 2 combinations).
These materials are: americium-241;
americium-241/beryllium; californium252; curium-244; cobalt-60; cesium-137;
gadolinium-153; iridium-192;
plutonium-238; plutonium-239/
beryllium; promethium-147; radium226; selenium-75; strontium-90
(yttrium-90); thulium-170; and
ytterbium-169. Irradiated fuel and
mixed oxide fuel are not included even
though they may contain category 1 or
category 2 quantities of radioactive
material; these materials are covered by
other regulations. The thresholds for
category 1 and category 2 quantities of
radioactive material are provided in the
following table. Terabecquerels is the
official value to be used for determining
whether a radioactive material is a
category 1 or category 2 quantity.
Because many licensees use curies in
their activities instead of becquerels, the
table provides the curie value at three
figures for practical usefulness.
4. Who would this action affect?
These requirements would apply to
NRC or Agreement State licensees that
are authorized to possess category 1 or
category 2 quantities of radioactive
material. This includes a wide range of
licensees, including pool-type irradiator
licensees; manufacturer and distributor
licensees; medical facilities with gamma
Category 1 Threshold
Radioactive Material
Terabecquerels
(TBq)
Americium-241 .............................................................................
Americium-241/Beryllium .............................................................
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Category 2 Threshold
Curies
(Ci)
Terabecquerels
(TBq)
1,620
1,620
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Category 1 Threshold
Radioactive Material
Terabecquerels
(TBq)
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Californium-252 ............................................................................
Curium-244 ..................................................................................
Cobalt-60 .....................................................................................
Cesium-137 ..................................................................................
Gadolinium-153 ............................................................................
Iridium-192 ...................................................................................
Plutonium-238 ..............................................................................
Plutonium-239/Beryllium ..............................................................
Promethium-147 ..........................................................................
Radium-226 .................................................................................
Selenium-75 .................................................................................
Strontium-90 (Yttrium-90) ............................................................
Thulium-170 .................................................................................
Ytterbium-169 ..............................................................................
These materials and thresholds are
based on the IAEA Code of Conduct.
The NRC and the international
community, led by the IAEA, revised
the IAEA Code of Conduct in 2003 to
establish common international
guidance for safety and security
measures for radioactive sources. The
IAEA published these results in a
document titled ‘‘Code of Conduct on
the Safety and Security of Radioactive
Sources.’’ A link to this document can
be found on the NRC Web site at https://
www.nrc.gov/security/byproduct/
enhanced-security.html. In a separate
effort, the U.S. Department of Energy
(DOE) and the NRC reviewed the
chemical, physical, and radiological
characteristics of each radioactive
material that is licensed in the United
States, for its attractiveness to a terrorist.
This effort identified 16 radioactive
materials that could pose a serious
threat to people and the environment.
This effort further identified the
different quantities or ‘‘thresholds’’ of
materials that could be useful to a
terrorist. The results of the DOE/NRC
effort closely matched the Code of
Conduct Category 2 quantities. The NRC
adopted the IAEA Code of Conduct
Category 1 and Category 2 threshold
quantities to provide consistency
between domestic and international
efforts for security of radioactive
materials that are deemed to be
attractive targets for malevolent use.
IAEA, Safety Series RS–G–1.9,
Categorization of Radioactive Sources,
provides the underlying methodology
for the development of the Code of
Conduct thresholds. Safety guide RS–G–
1.9 provides a risk-based ranking of
radioactive sources in five categories in
terms of their potential to cause severe
deterministic effects for a range of
scenarios that include both external
exposure from an unshielded source
and internal exposure following
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Curies
(Ci)
20
50
30
100
1000
80
60
60
40,000
40
200
1,000
20,000
300
6. Why are the requirements limited to
these 16 radionuclides?
The Radiation Source Protection and
Security Task Force, an interagency task
force established by the EPAct,
concluded in its 2006 report to Congress
and the President (ADAMS
ML062190349) that the appropriate
radioactive sources were being
protected and that the IAEA Code of
Conduct serves as an appropriate
framework for considering which
sources warrant additional protection.
The Task Force did note that the U.S.
Government should periodically
reevaluate the list of radionuclides that
warrant additional security and
protection. Therefore, the radionuclides
and thresholds could change in the
future and any changes would be
addressed in a future rulemaking.
7. What is the sum of fractions
methodology or unity rule?
The sum of fractions methodology,
also known as the unity rule, is used to
determine if a licensee would be
required to implement 10 CFR part 37
requirements. A licensee may need to
implement the requirements in 10 CFR
part 37 even if it does not possess any
single source or single radionuclide in
excess of the category 2 thresholds. For
combinations of materials (to include
sealed sources, unsealed sources, and
bulk material) and radionuclides, a
licensee must include multiple sources
(including bulk material) of the same
Frm 00006
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Sfmt 4702
Terabecquerels
(TBq)
540
1,350
810
2,700
27,000
2,160
1,620
1,620
1,080,000
1,080
5,400
27,000
540,000
8,100
dispersal. The categorization system
uses the ‘D’ values as normalizing
factors. The ‘D’ value is the radionuclide
specific activity of a source that, if not
under control, could cause severe
deterministic effects for a range of
scenarios that include both external
exposure from an unshielded source
and internal exposure following
dispersal of the source material.
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Category 2 Threshold
0.2
0.5
0.3
1
10.0
0.8
0.6
0.6
400
0.4
2.0
10.0
200
3
Curies
(Ci)
5.40
13.5
8.10
27.0
270
21.6
16.2
16.2
10,800
10.8
54.0
270
5,400
81.0
radionuclide and multiple sources
(including bulk material) of different
radionuclides to determine if the
requirements apply. For the purposes of
this calculation, licensees would be
required to consider all of the
radioactive material at a facility. The
following formula for the unity rule
would be used to determine if a licensee
is required to implement the Part 37
requirements: [(total amount of
radionuclide A) ÷ (category 2 threshold
of radionuclide A)] + [(total amount of
radionuclide B) ÷ (category 2 threshold
of radionuclide B)] + etc.....≥ 1. If the
sum is greater than or equal to 1, the
licensee would have at least a category
2 quantity of radioactive material, and
the 10 CFR part 37 requirements would
apply at that facility.
8. Does the NRC plan to issue guidance
on these proposed requirements?
Yes, the NRC plans to issue guidance
on the security requirements for
category 1 and category 2 quantities of
radioactive materials. The guidance will
be made available for public comment
sometime during the comment period
for this proposed rule. The NRC is
planning to host at least one public
workshop on the guidance documents.
A separate document announcing the
availability of the guidance and the
information on the workshop will be
published in the Federal Register.
9. Will all of the information considered
to be safeguards information under the
orders now be made public?
No. The orders issued to some
licensees contained detailed security
information that could be useful to an
adversary. To increase public awareness
and participation, the NRC identified
the primary security concepts behind
each security measure and included
these concepts in the proposed rule to
allow discussion of the security
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measures in a public forum. But the
specific measures that a licensee puts in
place may be considered SGI–M. The
final rule on safeguards information
became effective on February 23, 2009
(73 FR 63546; October 24, 2008), and
established as SGI–M certain physical
protection information related to
panoramic and underwater irradiators
that possess greater than 370 TBq
(10,000 Ci) of byproduct material in the
form of sealed sources; manufacturers
and distributors of items containing
source material, byproduct material, or
special nuclear material in greater than
category 2 quantities; and transportation
of source, byproduct, or special nuclear
material in greater than or equal to
category 1 quantities. Physical
protection information for other
facilities that fall under the
requirements of 10 CFR part 37 would
be considered physical protection
information under 10 CFR 2.390(d)(1).
Licensees would also be required to
protect the security plan and
implementing information from
unauthorized disclosure. The rule
provisions that address SGI–M or
include references to the SGI–M
requirements in part 73 are reserved for
the NRC and are considered
compatibility category NRC.
10. What is the authority for this
proposed rule?
As noted in the background
discussion, the NRC issued some orders
under its authority to protect the
common defense and security and some
orders under its authority to protect the
public health and safety. With respect to
whether the following regulations are
being issued under ‘‘public health and
safety’’ or ‘‘common defense and
security,’’ it should be recognized that
almost all regulations relating to the
security of materials serve both
purposes to some degree. For example,
securing radioactive materials with
multiple barriers protects the public
health and safety by preventing the
unknowing theft of radioactive
materials—such as someone stealing a
vehicle with material stored in the
vehicle but whose target is the vehicle—
which could result in the unintentional
exposure of members of the public to
the material. The barriers also protect
the common defense and security by
preventing the theft of the radioactive
material by potential terrorists or others
targeting the specific material intending
to use it to affect the common defense
and security by exposing members of
the public to the material. However, the
designation of the authority being used
for these regulations does have
significance in determining whether
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Agreement States or the NRC will be
responsible for overseeing the
implementation of these requirements
for Agreement State licensees.
Although the NRC relinquishes its
regulatory authority to Agreement States
for certain materials, under Section
274(m) of the AEA no such agreement
will affect the authority of the
Commission to take regulatory action to
protect the common defense and
security. Thus, as evidenced by orders
issued to Agreement State licensees
after the events of September 11, 2001,
the NRC always has the ability to take
necessary steps to address particular
common defense and security needs. If
these regulations were to be issued
under the NRC’s common defense and
security authority, only the NRC would
have the authority to impose these
requirements on Agreement State
licensees and the NRC would be
responsible for inspection and
enforcement of these requirements for
Agreement State licensees.
When regulations such as these
complement both the NRC’s public
health and safety and common defense
and security missions, the operative
question is whether NRC oversight is
necessary to fulfill the common defense
and security aspects of the regulations.
The NRC believes that the Agreement
States can consistently and adequately
implement the physical protection
requirements on a nationwide basis, and
as such, there will be no need for
independent NRC action to protect the
common defense and security. The NRC
has regular oversight of individual
Agreement State programs through its
Integrated Materials Performance
Evaluation Program (IMPEP). As always,
the NRC retains the authority under
Section 274(m) to take any necessary
actions for protection of the common
defense and security should individual
licensees or State programs develop
issues requiring immediate action. The
Commission also has the authority
under Section 274(j) to terminate or
suspend all or part of its agreement with
a State and reassert the Commission’s
licensing and regulatory authority when
the Commission determines that doing
so is necessary to protect the public
health and safety. The failure of an
individual Agreement State to
implement compatible and adequate
legally binding requirements to protect
radioactive materials within its
jurisdiction disrupts the entire national
scheme to protect radioactive materials
such that it might raise serious public
health and safety or common defense
and security concerns that the NRC
would have to address. As long as all
Agreement States continue to
PO 00000
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33907
implement compatible and adequate
security requirements, there appears to
be no benefit to the public health and
safety, or common defense and security,
that would justify removing oversight of
these requirements from an established
regulatory program overseeing
Agreement State licensees.
Implementing these regulations under
the NRC’s public health and safety
authority would avoid potential
complications with licensees being
subject to dual regulation for a single
activity. Thus, the NRC is proposing to
issue these regulations under its public
health and safety authority, and these
requirements will be applicable to
Agreement State licensees through the
Agreement State Program.
11. When would the rule be effective?
The NRC is recommending that the
final rule be effective 270 days after
publication in the Federal Register.
This would provide time for licensees to
put in place the necessary programs,
develop procedures, and conduct
training on the new requirements. While
most of the provisions are similar to
those contained in the orders, there are
differences. The Agreement States
would be required to issue compatible
requirements within 3 years. Licensees
in an Agreement State would continue
to operate under the orders or other
legally binding requirements until the
Agreement State issues compatible
requirements. The provisions put in
place for the inspection of licensees in
Agreement States that received the
orders issued under common defense
and security would remain in place
until the Agreement State implements
the requirements. For those States that
entered into 274i Agreements, the State
would continue inspections under the
Agreement. For those States that did not
enter into 274i Agreements, the NRC
would continue to conduct the
inspections until the State puts in place
the new requirements. The NRC would
rescind the orders as the regulatory
requirements become effective.
12. How does the NRC ensure licensees
are following these rules?
The NRC and Agreement States
conduct inspections to ensure that
licensees are following the
requirements. The NRC and Agreement
State inspectors have received training
and follow inspection procedures on
how to ascertain whether licensees are
meeting security requirements. Potential
violations that are identified will be
processed in accordance with the NRC
Enforcement Policy, and depending on
the severity of a violation, licensees
could be subject to civil or criminal
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penalties. Additionally, the NRC has
developed enforcement guidance to
ensure consistency in the enforcement
process. Agreement State licensees
would be subject to the State’s
enforcement process.
collection requirements; Section X
contains a request for comment on the
draft regulatory analysis; and Section XI
contains a request for comment on the
impact of the proposed rule on small
businesses.
13. What should I consider as I prepare
my comments to the NRC?
Tips for preparing your comments—
when submitting your comments,
remember to:
i. Identify the rulemaking (RIN 3150–
AI12, NRC–2008–0120).
ii. Explain why you agree or disagree;
suggest alternatives and substitute
language for your requested changes.
iii. Describe any assumptions and
provide any technical information and/
or data that you used.
iv. If you estimate potential costs or
burdens, explain how you arrived at
your estimate in sufficient detail to
allow for it to be reproduced.
v. Provide specific examples to
illustrate your concerns, and suggest
alternatives.
vi. Explain your views as clearly as
possible.
vii. Make sure to submit your
comments by the comment period
deadline identified.
viii. The NRC is particularly
interested in your comments concerning
the following issues in Section II: (1)
Item B5 of this document contains a
request for comment on whether the
reviewing official should be
fingerprinted as part of the
trustworthiness and reliability
determination; (2) item B8 contains a
request for comment on the elements of
the background investigation; (3) item
C6 contains a request for comment on
the protection of information; (4) item
C15 contains a request for comment on
the need to notify the LLEA before
working at a temporary jobsite; (5) item
C17 contains a request for comment on
vehicle disabling requirements for
mobile sources; (6) item C19 contains a
request for comment on the reporting
requirements; (7) item D4 contains a
request for comment on requiring
license verification before transferring
category 2 quantities of radioactive
material; and (8) item D21 contains a
request for comment on requiring an
NRC-approved monitoring plan for the
classification yard for rail shipment. In
addition, Section V of this document
contains a request for comment on the
compatibility designations for the
proposed rule; Section VI contains a
request for comment on the use of plain
language; Section VIII contains a request
for comment on the environmental
assessment; Section IX contains a
request for comment on the information
B. Background Investigations and
Access Authorization Program
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1. Who would be required to have an
access authorization program?
Any licensee that is authorized to
possess category 1 or category 2
quantities of radioactive materials at a
facility would need to determine
whether it needs to have an access
authorization program. The licensee
would be required to submit
information to the NRC concerning its
compliance with the access
authorization program requirements.
The information should include a
statement that the licensee is or is not
implementing an access authorization
program. The statement should not
include details of the licensee’s access
authorization program or implementing
procedures. Only those licensees that
permit unescorted access to category 1
or category 2 quantities of radioactive
material would be required to establish
and implement an access authorization
program. In addition, any applicant for
a license or license amendment to
possess category 1 or category 2
quantities of radioactive material at a
facility would be required to establish
an access authorization program before
obtaining the radioactive material.
2. What is the objective of the access
authorization program?
The main objective of the access
authorization program is to ensure that
individuals who have unescorted access
to category 1 or category 2 quantities of
radioactive material are trustworthy and
reliable and do not constitute an
unreasonable risk to the public health
and safety or common defense and
security.
3. Who would be subject to the
licensee’s access authorization program?
The EPAct authorizes the Commission
to require fingerprinting of any
individual who is permitted unescorted
access to ‘‘any radioactive material that
the Commission determines to be of
such significance to the public health
and safety or the common defense and
security as to warrant fingerprinting and
background checks.’’ The Commission
has determined that the threshold that
warrants fingerprinting and background
checks is category 2. Therefore,
individuals subject to a licensee’s access
authorization program would include
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Frm 00008
Fmt 4701
Sfmt 4702
anyone permitted to have unescorted
access to category 1 or category 2
quantities of radioactive material.
Unescorted access would be defined as
solitary access to category 1 or category
2 quantities of radioactive material
granted to an approved individual, and
includes solitary access to sufficient
quantities of radioactive material such
that an individual could successfully
accumulate lesser quantities of material
into a category 1 or category 2 quantity.
This would be an individual at the
licensee’s facility who has access to
various locations within the licensee’s
facility and does not address the
situation where a contractor might have
access to the facilities of several
licensees.
The access authorization program
would also include individuals that
have access to SGI–M, such as vehicle
drivers and accompanying individuals
for road shipments of category 1
quantities of radioactive material,
movement control center personnel for
shipments of category 1 quantities of
radioactive material, and any individual
whose assigned duties provide access to
shipment information on category 1
quantities of radioactive material. In
response to comments on the
preliminary rule language, the NRC
added text to clarify that ‘‘access to
shipping information’’ referred to
shipping information that was
considered to be SGI–M and not all
shipping information.
Those individuals who have
unescorted access to certain quantities
of byproduct material could pose a
threat to the public health and safety or
the common defense and security
because they could divert or steal risksignificant radioactive material, or could
aid others in the commission of such
acts. The Radiation Source Protection
and Security Task Force encouraged the
NRC to require fingerprinting and
Federal criminal history checks of any
individual with access to category 1 or
category 2 quantities of radioactive
material.
Certain categories of individuals
would be relieved from the background
investigation aspect of the access
authorization program (see Section II,
question B20 and B21). Licensees do
have the option to escort an individual
and not make a trustworthiness and
reliability determination. The escorts
would need to be approved for
unescorted access.
In response to comments on the
preliminary rule language, the NRC
removed a restriction that would
prohibit a licensee from granting
unescorted access to anyone that had
been previously denied unescorted
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access. The NRC agreed that this was
too limiting as information upon which
a denial is based could change, and the
individual could be unfairly denied
access in the future.
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4. What are the key access authorization
program requirements?
The key components of an access
authorization program would be the
reviewing official, the informed consent
of the subject individual, personal
history disclosure by the subject
individual, a background investigation,
use of procedures, and the individual’s
right to correct and complete the
information on which the decision to
grant unescorted access is based. Each
of these areas is discussed in more
detail in the following questions and
answers.
5. What is the role of the reviewing
official?
The reviewing official would be the
individual that makes the
trustworthiness and reliability
determinations for the licensee; the
reviewing official determines who could
be granted unescorted access
authorization. Note that the Increased
Control Fingerprinting Orders referred
to a trustworthiness and reliability
official or T&R official as the individual
that made determinations on an
individual’s trustworthiness and
reliability. Unlike the reviewing official
the T&R official did not have to be
fingerprinted and was not reviewed by
the regulator. Licensees would need to
nominate one or more individuals to be
a reviewing official and submit their
fingerprints to the NRC. The fingerprints
of the nominated individual(s) would
need to be taken by either a law
enforcement agency, a Federal or State
agency that provides fingerprinting
services to the public, or a commercial
fingerprinting service authorized by a
State to take fingerprints. Before sending
the nominated individual’s fingerprints
to the NRC, the licensee would need to
conduct the rest of the elements of the
background investigation. Reviewing
officials must be permitted either access
to safeguards information or unescorted
access to category 1 or category 2
quantities of radioactive material since
Section 149 of the Atomic Energy Act
only authorizes the collection of
fingerprints for the purposes of
unescorted access or access to
safeguards information. The
Commission has requested statutory
changes to the Atomic Energy Act that
would permit fingerprints of reviewing
officials without requiring access for
these purposes. The NRC would then
transmit the nominated reviewing
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official’s fingerprints to the FBI and
would review the individual’s criminal
history records and, if appropriate,
approve the reviewing official.
Reviewing officials would not be able to
make trustworthiness and reliability
determinations until approved by the
NRC. For certain licensees, the NRC
may have already approved reviewing
officials, either under the October 17,
2006, orders [(EA–06–248, 71 FR 63043;
October 27, 2006), (EA–06–250, 71 FR
53046; October 27, 2006), and (EA–06–
249; 71 FR 62303; October 24, 2006)],
under the August 21, 2006, SGI–M
orders, or under other regulatory
requirements. In those cases, the
reviewing official may continue to act in
that capacity for an expanded set of
persons. If the reviewing (or T&R)
official has not had an FBI criminal
records history check, he or she would
need to be fingerprinted and receive
NRC approval before making additional
trustworthiness and reliability
determinations. The NRC believes that it
is important that the individual who is
making the final determination on
whether an individual is trustworthy
and reliable be trustworthy and reliable
themselves and have undergone the
same background investigation as
individuals who would be granted
unescorted access, including
fingerprinting and the FBI criminal
records check. If the reviewing official
is not fingerprinted, a gap could be
created in the security program that
could potentially be exploited. The NRC
is specifically requesting comment on
this aspect of the proposed access
authorization program. In developing
comments on this issue, consider the
following questions:
(1) Does the reviewing official need to
be fingerprinted and have a FBI criminal
records check conducted?
(2) Are the other aspects of the
background investigation adequate to
determine the trustworthiness and
reliability of the reviewing official?
(3) Are there other methods that could
be used to ensure that the reviewing
official is trustworthy and reliable?
(4) Does the requirement to
fingerprint the reviewing official place
too large of a burden on the licensee?
(5) Do Agreement States have the
necessary authority to conduct reviews
of the nominated individual’s criminal
history record?
6. What is informed consent?
Informed consent is the authorization
provided by an individual that allows a
background investigation to be
conducted to determine whether the
individual is trustworthy and reliable.
The signed consent would include
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33909
authorization to share personal
information with other individuals or
organizations as necessary to complete
the background investigation. An
individual would be able to withdraw
his or her consent at any time. After the
withdrawal, the licensee would not be
able to initiate any elements of the
background investigation that were not
in process at the time of the withdrawal
of consent. The licensee would be
required to inform the individual that
withdrawal of consent for the
background investigation would be
sufficient cause for denial or
termination of unescorted access
authorization.
Licensees do not need to obtain
signed consent from individuals that
have already undergone a background
investigation that included
fingerprinting and an FBI criminal
history records check, been determined
to be trustworthy and reliable, and
permitted unescorted access to category
1 or category 2 quantities of radioactive
material under the NRC orders or the
legally binding requirements issued by
the Agreement States. A signed consent
would be needed for any
reinvestigation.
In response to comments on the
preliminary rule language, the NRC
removed provisions for retention of
background investigation information if
the individual withdraws consent. If the
individual later seeks unescorted access,
the background investigation
information collected during the
original attempt could no longer be
relied on, and the investigation would
need to be restarted. Requiring the
preservation of this information would
place an unnecessary burden on
licensees.
7. What is a personal history disclosure?
The personal history disclosure is the
personal history required to be provided
by the individual seeking unescorted
access to category 1 or category 2
quantities of radioactive material. The
information would include items such
as employment history, education,
credit history (including bankruptcies),
and any arrest record. This information
would provide the reviewing official
with a starting point for the background
investigation. Failure to provide the
information or falsification of any
information could be grounds for denial
of the individual’s request for
unescorted access authorization or
termination of access if the individual
already has access. If the individual
provides false information, it could be
an indication that he or she is not
trustworthy or reliable.
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8. What are the components of a
background investigation?
A background investigation includes
several components: Fingerprinting and
an FBI identification and criminal
history records check; verification of
true identity; employment history
evaluation; verification of education;
credit history evaluation; criminal
history review; and character and
reputation determination.
It is the licensee’s responsibility to
make a trustworthiness and reliability
determination of an employee,
contractor, or other individual who
would be granted unescorted access to
category 1 or category 2 quantities of
radioactive material or a device
containing such radioactive material. It
is expected that licensees will use their
best efforts to obtain the information
required to conduct a background
investigation to determine an
individual’s trustworthiness and
reliability.
The full credit history evaluation
reflects the Commission’s intent that all
financial information available through
credit reporting agencies is to be
obtained and evaluated as part of the
trustworthiness and reliability
evaluation. The Commission recognizes
that some countries may not have
routinely accepted credit reporting
mechanisms. Therefore, the
Commission allows reviewing officials
to use multiple sources of credit history
that could potentially provide
information about a foreign national’s
financial record and responsibility.
Fingerprinting an individual for a FBI
criminal history records check is an
important element of the background
investigation. It can provide
comprehensive information regarding
an individual’s recorded criminal
activities within the U.S. and its
territories and the individual’s known
affiliations with violent gangs or
terrorist organizations.
The background investigation is a tool
to determine whether individuals are
trustworthy and reliable and could be
permitted unescorted access to category
1 or category 2 quantities of radioactive
material. It is essential to ensure that
individuals seeking unescorted access to
radioactive material are dependable in
judgment, character, and performance,
such that unescorted access to category
1 or category 2 quantities of radioactive
material by that individual does not
constitute an unreasonable risk to the
public health and safety or common
defense and security.
The NRC is specifically inviting
comment on the elements of the
background investigation. Please
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consider the following questions in
developing comments:
(1) Is a local criminal history review
necessary in light of the requirement for
a FBI criminal history records check?
(2) Does a credit history check
provide valuable information for the
determination of trustworthiness and
reliability?
(3) Do the Agreement States have the
authority to require a credit history
check as part of the background
investigation?
(4) What are the appropriate elements
of a background investigation and why
are any suggested elements appropriate?
(5) Are the elements of the
background investigation too subjective
to be effective?
(6) How much time does a licensee
typically spend on conducting the
background investigation for an
individual?
9. Where does a licensee submit the
fingerprints for processing?
Under the EPAct, licensees are
required to submit the fingerprints to
the NRC, which forwards the
fingerprints to the FBI for processing. If
an individual comes under one of the
relief categories specified in 10 CFR
37.29, the licensee would not need to
submit the individual’s fingerprints to
the NRC.
10. What should a licensee do if an
individual or entity contacted as part of
a background investigation refuses to
respond?
If a previous employer, educational
institution, or any other entity fails to
provide information or indicates an
inability or unwillingness to provide
information in a timely manner, the
licensee would be required to document
the refusal, unwillingness, or inability
to respond in the record of
investigation. The licensee would then
need to obtain confirmation from at
least one alternate source that has not
been previously used. In response to
comments on the preliminary rule
language, the NRC revised the rule
language to provide more flexibility to
licensees as to what would be
considered a timely manner.
11. Does an individual have the right to
correct his or her criminal history
records?
Yes, an individual has the right to
correct his or her criminal history
records before any final adverse
determination is made. If the individual
believes that his or her criminal history
records are incorrect or incomplete in
any respect, he or she can initiate
challenge procedures. These procedures
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would include direct application by the
individual challenging the criminal
history records to the law enforcement
agency that contributed the questioned
information.
Before an adverse determination on a
request for unescorted access,
individuals have the right to provide
additional information.
12. Is a licensee required to have
procedures for conducting background
investigations?
Yes, licensees would be required to
develop, implement, and maintain
written procedures for conducting the
background investigations. Procedures
would address notification of
individuals denied unescorted access
authorization and would also ensure
that individuals who have been denied
unescorted access authorization are not
allowed unescorted access to category 1
or category 2 quantities of radioactive
material (these individuals could be
escorted by an approved individual.)
The NRC agreed with comments on the
preliminary rule language that the
provision prohibiting even escorted
access for those individuals denied
unescorted access was too inflexible,
licensees should be given the flexibility
to escort individuals if they so choose.
The preliminary language also
contained a provision that required a
licensee to provide an opportunity for
an independent management review if
the individual was denied unescorted
access. Several commenters noted that
the requirement was too prescriptive
and that a decision on whether and how
to conduct a review should be left up to
the licensee. The NRC agrees with the
commenters and has not included the
provision in the proposed rule.
13. What information should the
reviewing official use to determine that
an individual is trustworthy and
reliable?
The reviewing official would use all
of the information gathered during the
background investigation, including the
information received from the FBI, in
making a determination that an
individual is trustworthy and reliable.
The reviewing official may not
determine that an individual is
trustworthy and reliable and grant them
unescorted access until all of the
information for the background
investigation has been obtained and
evaluated. The reviewing official may
deny unescorted access to any
individual based on any information
obtained at any time during the
background investigation. However, as
required by Section 149.c(2)(c) of the
Atomic Energy Act, the licensee may
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not base a final determination to deny
an individual unescorted access to
category 1 or category 2 quantities of
radioactive material solely on the basis
of information received from the FBI
involving: (1) An arrest more than 1 year
old for which there is no information of
the disposition of the case; or (2) an
arrest that resulted in dismissal of the
charge or an acquittal. If there is no
record on the disposition of the case, it
may be that information on a dismissal
or acquittal was not recorded.
14. How frequently would a
reinvestigation be required?
A reinvestigation would be required
every 10 years to help maintain the
integrity of the access authorization
program. This is necessary because an
individual’s financial situation or
criminal history may change over time
in a manner that can adversely affect his
or her trustworthiness and reliability.
The reinvestigation would include the
local criminal history review and credit
history check, but would not include
identification through fingerprinting,
employment verification, or the
character and reputation determination.
would be required to verify information
such as name, date of birth, social
security number, gender, and other
physical characteristics to ensure that
the individual is the person whose file
has been transferred.
18. What records are required to be
maintained?
Licensees would be required to retain
all fingerprint and criminal history
records received from the FBI, or a copy
if the individual’s file has been
transferred, for 5 years after the
individual no longer requires
unescorted access to category 1 or
category 2 quantities of radioactive
material. Licensees would also be
required to retain the written
confirmation received from entities
concerning a security clearance or
favorably adjudicated criminal history
records check and any written
verifications received from service
providers. In response to comments on
the preliminary rule language, the NRC
revised the record retention
requirements so that the language was
consistent throughout subpart B of 10
CFR part 37.
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15. Are licensees required to protect
information obtained during a
background investigation?
Yes, licensees would be required to
protect the information obtained during
a background investigation. The
licensee would be required to establish
and maintain a system of files and
procedures for protection of the
information from unauthorized
disclosure. Licensees would only be
permitted to disclose the information to
the subject individual, the individual’s
representative, those who have a needto-know the information to perform
their assigned duties to grant or deny
unescorted access to category 1 or
category 2 quantities of material or
safeguards information, or an authorized
representative of the NRC.
19. How would a licensee determine the
effectiveness of the access authorization
control program?
16. Could a licensee transfer personal
information obtained during an
investigation to another licensee?
Yes, a licensee would be able to
transfer background information on an
individual to another licensee if the
individual makes a written request to
the licensee to transfer the information
contained in his or her file.
20. Would individuals transporting
radioactive material be subject to the
background investigation requirements?
17. If I receive background investigation
information from another licensee, can
I rely on that information?
Yes, a licensee would be able to rely
on the background investigation
information that is transferred from
another licensee. However, a licensee
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Licensees would be required to
review their program to confirm
compliance with the requirements. The
review would evaluate all program
performance objectives and
requirements, would document any
findings and corrective actions, and
would be conducted annually. Any
records would need to be maintained for
5 years. Commenters on the preliminary
rule language suggested that the review
period should be annual for consistency
with the radiation protection program
review. The NRC agrees and changed
the review frequency from 24 months to
12 months.
As part of this rulemaking, the NRC
considered what level of responsibility
to place on its licensees regarding
fingerprinting and criminal history
records checks for persons involved in
the transportation of category 1 and
category 2 quantities of radioactive
material. Licensees covered by the
fingerprinting and criminal history
records check requirements of this
proposed rule may decide to transfer
radioactive material away from the site
or may receive radioactive material from
another entity.
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Such transfers or receipts may occur
either as part of a shipment to or from
a domestic company or an international
company. Individuals involved in the
shipment, in particular those employed
by carriers or other organizations
handling shipments, may have
unescorted access to the material during
the shipment process. These persons
may not be employees of the licensee
and thus may not be under the
licensee’s direct control. In this regard,
proposed § 37.21(c) directs that
licensees subject certain classes of
individuals to the access authorization
program. Specifically, the NRC is
proposing that vehicle drivers and
accompanying individuals for road
shipments of category 1 quantities of
radioactive material, movement control
center personnel for shipments of
category 1 quantities of radioactive
material, and any individual whose
assigned duties provide access to
shipment information on category 1
quantities of radioactive material that is
considered to be SGI–M, all be
fingerprinted and undergo background
investigations. This was discussed in
Section II, question B3 of this
document.
21. Who would be relieved from the
background investigation requirements?
Under section 149.b. of the AEA, the
NRC may, by rule, relieve individuals
from the fingerprinting, identification,
and criminal history records check
requirements if it finds that such action
is ‘‘consistent with its obligations to
promote the common defense and
security and to protect the health and
safety of the public.’’ The NRC issued a
final rule, 10 CFR 73.61, relieving
certain individuals who are permitted
unescorted access to radioactive
materials from the fingerprinting,
identification, and criminal history
records checks required by section
149.a. of the AEA (72 FR 4945; February
2, 2007). The individuals relieved from
fingerprinting, identification, and
criminal history records checks under
that rule include Federal, State, and
local officials involved in security
planning; Agreement State employees
who evaluate licensee compliance with
security-related orders; and other
government officials who may need
unescorted access to radioactive
materials or other property subject to
regulation by the Commission as part of
their oversight function. The categories
of individuals relieved by the rule also
include the same individuals as those
previously relieved in an earlier
rulemaking from fingerprinting and
criminal history records check
requirements applicable to safeguards
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information (71 FR 33989; June 13,
2006).
Under this proposed rule, the
Commission proposes to use the same
listing of categories of individuals with
the following modifications. Emergency
response personnel who are responding
to an emergency would be relieved from
the requirements because it is
impossible to predict when emergency
access might be necessary. Employees of
carriers that transport category 2
quantities of radioactive material would
also be relieved. The NRC will rely on
the U.S. Department of Transportation
(DOT) and the Transportation Security
Administration programs for
background investigations of these
personnel.
The individuals that would be
relieved from the background
investigation requirements are
considered trustworthy and reliable by
virtue of their occupational status and
have either already undergone a
background investigation as a condition
of their employment, or are subject to
direct oversight by government
authorities in their day-to-day job
functions.
Certain persons, as part of the duties
of their specific occupation, may be
separately or previously subject to
background investigations, either as a
result of NRC requirements (as under
other requirements for access to SGI or
SGI–M) or as a result of requirements of
other agencies. These persons would not
be subject to separate background
investigation requirements under this
proposed rule; individuals who have
undergone a background investigation,
including fingerprinting, and found
acceptable for unescorted access under
provisions of other such requirements
would not need to undergo another
background investigation nor would a
separate determination of their
trustworthiness and reliability need to
be made.
This rule would not authorize
unescorted access to any radioactive
materials or other property subject to
regulation by the Commission. Rather,
the rule would make clear that a
licensee may permit unescorted access
to certain categories of individuals
otherwise qualified for access without
performing a background investigation.
Licensees would still need to decide
whether to grant or deny an individual
unescorted access independently of this
proposed provision. Any required
training would need to be conducted
before granting unescorted access.
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C. Physical Protection During Use
1. Who would be affected by the
proposed requirements?
Within 30 days of the effective date of
the final rule, each licensee that is
authorized to possess category 1 or
category 2 quantities of radioactive
material would need to submit
information to the NRC concerning the
licensee’s compliance with the security
requirements. The information should
include a statement that the licensee is
implementing a security program. The
licensee should not submit details of the
licensee’s security program,
implementing procedures, security plan,
or other sensitive information.
Any licensee that possesses an
aggregated category 1 or category 2
quantity of radioactive material would
be required to establish, implement, and
maintain a security program meeting the
requirements of 10 CFR subpart C of the
proposed rule. (The NRC would
consider material to be ‘‘aggregated’’ if
an adversary could gain access to a
category 2 or greater quantity by
breaching a common physical barrier.)
Any licensee that is authorized to
possess at least a category 2 quantity of
radioactive material would be required
to develop a security program. However,
the licensee would not be required to
implement the security program unless
the licensee aggregated the material into
a quantity equal to or exceeding the
category 2 threshold. At least 90 days
before aggregating the radioactive
material to a category 2 quantity or
greater, the licensee would be required
to notify the NRC in writing and
implement its security program. This
advance notification would provide
time for NRC to inspect the licensee’s
security program before the licensee
actually aggregated the material.
The NRC recognizes that some
licensees may not always have
quantities of radioactive material that
equal or exceed category 2, and may not
always have a 90-day notice of the need
to cross the threshold for implementing
the security program. Accordingly, the
proposed rule also includes provisions
to cover situations where a licensee may
routinely, but not continuously, possess
aggregated quantities of radioactive
material at or above the category 2
threshold. A licensee whose aggregated
quantity of radioactive material
fluctuates above and below the category
2 threshold more than once in a 90-day
period and thereafter would only need
to notify the NRC the first time that the
security program is implemented. This
notice could then serve to inform the
NRC that the licensee will be
periodically implementing the security
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provisions. If the fluctuation in
aggregated quantity does not reach the
category 2 threshold more than once in
a 90-day period, the licensee would
need to notify the NRC each time a
previously discontinued or new security
program is to be implemented. These
provisions are intended to cover the
situation where a licensee routinely, but
not continuously, has aggregated
quantities of radioactive material at or
above the category 2 threshold so that
they do not need to report to NRC each
time the material is aggregated. This
provides a licensee who may not have
90 days notice an acceptable means to
inform the NRC that they will be
periodically implementing the security
provisions.
To illustrate how aggregation might
work, here are two examples of a
hospital system with a license to
possess materials at different sites.
Hospital A is authorized to possess 0.4
TBq (11 Ci) of cesium-137 at location 1,
0.7 TBq (19 Ci) at location 2, and 0.9
TBq (24 Ci) at location 3, each several
miles apart. Hospital A would be
required to develop a security program
because the total authorization of 2 TBq
(54 Ci) is more than the category 2
threshold. However, Hospital A would
not be required to implement the
security program because no single
location is authorized to possess a
quantity that could be aggregated to the
category 2 threshold of 1TBq (27 Ci).
Hospital B, on the other hand, is
authorized to possess 0.4 TBq (10.8 Ci)
of cesium-137 at location 1, 0.5 TBq
(13.5 Ci) at location 2, and 1.1 TBq (29.7
Ci) at location 3. Hospital B’s total
authorization is also 2 TBq (54 Ci), but
Hospital B would be required to develop
a security program and implement the
program for location 3 if all the material
at that location is aggregated within a
single physical barrier, such as a locked
room, because the total quantity
possessed is above the category 2
threshold of 1 TBq (27 Ci). Therefore,
Hospital B would have to either add
another physical barrier to isolate the
aggregated material; separate the
material into quantities less than
category 2 quantities and place each
behind at least one independent
physical barrier; or develop and
implement a security program at
location 3.
2. What is the objective of the security
program and what are the key security
program requirements?
The proposed rule would require
affected licensees to establish,
implement, and maintain a security
program. The objective of the security
program would be to monitor, and
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without delay detect, assess, and
respond to any actual or attempted
unauthorized access to category 1 or
category 2 quantities of radioactive
materials. The objective was slightly
revised to address actual or attempted
unauthorized access in response to
comments on the preliminary rule
language. A licensee’s security program
would include a written security plan,
implementing procedures, training, use
of security zones, protection of
information, coordination with the
LLEA, testing and maintenance of
security-related equipment, security
measures, and a program review. Each
of these areas is discussed in more
detail in the following questions and
answers.
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3. What should a licensee’s security
plan address?
The purpose of a security plan is to
establish, in writing, the licensee’s
overall security strategy to ensure that
all of the required security measures
work effectively and in an integrated
way for all facilities and operations
where category 1 or category 2
quantities of radioactive material will be
used or stored. The plan would, among
other things, include a description of
the measures and strategies to
implement the security requirements
and describe any site-specific
conditions that affect how the licensee
will implement the requirements.
A licensee would be able to revise its
security plan to address changing
circumstances. Any changes to the
security plan, as well as the original
plan, would be approved by the
individual with overall responsibility
for the security program. The security
plan would be retained until the
Commission terminates the license, and
any superseded portions would be
retained for 5 years.
Security plans are important for the
implementation of a performance-based
regulation. An adequate plan requires a
licensee to analyze the particular
security needs of its individual facilities
and to explain how it will implement its
chosen security measures to ensure that
they work together to meet the
applicable performance objectives.
4. Would a licensee be required to have
security procedures?
Yes, licensees would be required to
develop and maintain written
implementing procedures that
document how the security
requirements and the security plan
would be met. These procedures must
be designed to meet the individualized
security needs of each site where a
category 1 or category 2 quantity of
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radioactive material is used or stored.
Procedures would need to be approved,
in writing, by the individual with
overall responsibility for the security
program. The licensee would be
required to keep a copy of the current
procedures as a record until the
Commission terminates the license.
Superseded portions of the procedures
would be retained for 5 years. Licensees
should not submit procedures to the
NRC as part of the license.
training would be necessary and to
clarify what training records need to be
maintained.
Training is essential if the licensee is
to be adequately prepared for an
effective and coordinated response to
any effort to steal or divert category 1 or
category 2 quantities of radioactive
material. Adequate training is
indispensable for an appropriate
licensee response to an unauthorized
intrusion.
5. What training would be required?
As part of its physical protection
program, each licensee would be
required to conduct training on the
security plan to ensure that those
individuals responsible for
implementation of the plan possess and
maintain the knowledge, skills, and
abilities to carry out their assigned
duties and responsibilities effectively.
The extent of the training would need
to be commensurate with the
individual’s potential involvement in
the security of category 1 or category 2
quantities of radioactive material.
Individuals would have to be instructed
in the licensee’s security program and
implementing procedures, their
responsibilities, and the appropriate
response to alarms. In guidance,
licensees with dedicated security staff
will be encouraged to train their
security personnel in the timely
notification of affected LLEAs during
emergencies. For improved coordination
with LLEAs, such licensees will also be
encouraged to train their security
personnel using drills or table top
exercises during integrated tests of their
monitoring, detection, and response
systems, and to notify affected LLEAs of
opportunities to participate in such
training.
An individual subject to the training
requirements of § 37.43(c) would have
to complete them before being permitted
unescorted access to category 1 or
category 2 quantities of radioactive
material. The licensee would have to
provide refresher training at least once
every 12 months or when significant
changes have been made to the security
program. The refresher training would
address any significant changes; reports
on relevant security issues, problems, or
lessons learned; relevant results from
NRC inspections; and relevant results
from the licensee’s program review and
the testing and maintenance program.
Training records would be maintained
for 5 years and would need to include
training topics, training dates, and the
list of personnel that attended the
training. The rule language was revised
to address comments on the preliminary
rule language to clarify that refresher
6. Would licensees be required to
protect information concerning their
security program?
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Yes. To prevent unauthorized
disclosure, licensees would be required
to limit access to their security plans
and implementing procedures. These
efforts would include measures to allow
access to these documents only to those
individuals who have a need to know
the information to perform their duties
and have been determined to be
trustworthy and reliable based on the
background investigation requirements
set forth in proposed § 37.25(a)(2)
through (a)(10). Licensees would be
required to store security information in
a manner to prevent removal, such as
storage in a locked office or desk
drawer.
To ensure that only trustworthy and
reliable individuals with a need to know
are allowed access to security plans and
procedures, licensees would have to
develop, implement, and maintain,
written policies and procedures to
control access to their security plan and
security procedures. The licensee’s
information protection policies and
procedures would have to ensure the
proper handling and protection of
security plans and implementing
procedures against unauthorized
disclosure. Licensees would be required
to retain copies of the policies and
procedures.
For the purposes of this proposed
requirement, licensees cannot
fingerprint individuals or subject them
to an FBI background investigation to
permit them access to security plans or
procedures, unless those individuals are
also permitted unescorted access to
Category 1 or 2 radioactive materials.
Information previously obtained during
the hiring process may be used to
support a licensee’s determination of an
individual’s trustworthiness and
reliability without having to reverify
that information. Licensees that have
SGI or SGI–M would remain subject to
the more stringent information
protection requirements of 10 CFR
73.21, including fingerprinting and an
FBI criminal records check.
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The NRC is specifically inviting
comment on the requirement to protect
security-related information. Please
consider the following questions in
developing comments:
(1) Do the Agreement States have
adequate authority to impose the
information protection requirements in
this proposed rule?
(2) Can the Agreement States protect
the information from disclosure in the
event of a request under a State’s
Freedom of Information Act, or
comparable State law?
(3) Is the proposed rule adequate to
protect the licensees’ security plan and
implementing procedures from
unauthorized disclosure, are additional
or different provisions necessary, or are
the proposed requirements
unnecessarily strict?
(4) Should other information beyond
the security plan and implementing
procedures be protected under this
proposed requirement?
(5) Should the background
investigation elements for determining
whether an individual is trustworthy
and reliable for access to the security
information be the same as for
determining access to category 1 and
category 2 quantities of radioactive
material (with the exception of
fingerprinting)?
7. What is the purpose of a security
zone?
A security zone would be any area
established by a licensee to provide
physical protection for category 1 or
category 2 quantities of radioactive
material at a licensed facility. All
category 1 and category 2 quantities of
radioactive material at the facility
would have to be used and stored
within a security zone.
The purpose of security zones is to
isolate and control access to the material
to protect it more effectively and deter
theft or diversion by providing, among
other things, more time for licensees
and LLEAs to respond. Isolation
measures would protect category 1 or
category 2 quantities of radioactive
material by allowing access to security
zones only through established access
control points. Access control measures
would allow only approved individuals
to have unescorted access to the security
zone, and ensure that other individuals
with a need for access are escorted by
approved individuals. A security zone
effectively defines where the licensee
will apply these isolation and access
control measures.
To limit unescorted access to only
approved individuals, licensees could
isolate the radioactive materials using
continuous physical barriers that allow
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access to the security zone only through
established access control points; or
licensees could exercise direct control
of the security zone by approved
individuals at all times.
Security zones may be permanent or
temporary. Temporary security zones
would need to be established to meet
transitory or intermittent operating
requirements such as periods of
maintenance, source delivery, and
source replacement. A licensee could
meet the proposed requirement for a
security zone at some temporary job
sites (such as those involving onsite
operations lasting less than a day)
simply by keeping the area under ‘‘direct
supervision’’ by authorized personnel.
Similarly, when work is being done
inside a temporary zone, a licensee
could meet the requirements for
controlling unescorted access by having
the material, persons, and area within
the zone under direct control of
approved individuals at all times.
Because the purpose of security zones
is different from the radiation safety
purposes of the restricted areas and
controlled areas defined in 10 CFR part
20, the security zone does not have to
be the same as either of these areas.
Because measures to control access are
required for both radiation protection
and security, however, a licensee does
have the flexibility to use an area
required for radiation protection
purposes to fulfill the required
functions of a security zone. Thus, for
a temporary well-logging operation
within which the licensee is required by
10 CFR 39.71 to have a ‘‘restricted area’’
to ‘‘maintain direct surveillance * * *
to prevent unauthorized entry into a
restricted area,’’ a licensee could define
a security zone with the same
boundaries as this ‘‘restricted area,’’
which is defined in 10 CFR 20.1003 as
‘‘an area, access to which is limited by
the licensee for the purpose of
protecting individuals against undue
risks from exposure to radiation and
radioactive materials.’’ Similarly, a
radiographer could choose to define a
security zone with the same boundaries
as the ‘‘high radiation area’’ over which
radiography licensees are required by 10
CFR 34.51 to ‘‘maintain direct visual
surveillance * * * to protect against
unauthorized entry.’’ (As defined in 10
CFR 20.1003, a ‘‘high radiation area’’ is
‘‘an area, accessible to individuals, in
which radiation levels from radiation
sources external to the body could result
in an individual receiving a dose
equivalent in excess of a 0.1 rem (1
mSv) in 1 hour at 30 centimeters from
the radiation source or 30 centimeters
from any surface that the radiation
penetrates.’’)
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Because materials licensees are
differently configured and do not lend
themselves to generically defined
physical areas, the security zone
concept permits significant flexibility
for licensees to account for a range of
site-specific concerns. It also provides
regulators with a well-defined and
enforceable requirement keyed to
performance objectives of isolation and
access control.
8. When would special additional
measures for category 1 quantities of
radioactive material be required?
One provision of the proposed rule
would apply to category 1 quantities of
radioactive material during periods of
maintenance, source receipt,
preparation for shipment, installation,
or source removal or exchange.
Licensees would be required to provide,
at a minimum, an approved individual
to maintain continous surveillance of
sources in temporary security zones and
in any security zone in which physical
barriers or intrusion detection systems
have been disabled to allow the
specified activities. The rule language
was clarified in response to comments
on the preliminary rule language.
Due to the natural decay of their
radioactivity, sources lose their
effectiveness as they get older and have
to be replaced or replenished
periodically with new sources to
maintain a device’s expected
performance. Tamper-indicating devices
and other intrusion detection equipment
typically must be disabled to permit the
source to be opened without tripping
alarms. The new sources are typically
shipped by an offsite supplier, who also
often performs removal and exchange or
reinstallation. After replacement, the
removed older sources must be prepared
onsite for shipment back to the
manufacturer or for storage and eventual
disposal. These nonroutine operations
by nonlicensee employees at the
licensee’s site, during a time when
devices for detecting theft or diversion
are disabled, call for additional
measures to compensate for the
temporary increase in vulnerability.
9. What would be required to monitor
and detect an unauthorized entry into a
security zone?
A licensee would be required to
establish and maintain the capability to
continuously monitor and detect all
unauthorized entries into its security
zone(s). Monitoring and detection
would be performed by either a
monitored intrusion detection system
that is linked to an onsite or offsite
central monitoring facility; electronic
devices for intrusion detection alarms
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that would alert nearby facility
personnel; visual monitoring by video
surveillance cameras; or visual
inspection by approved individuals.
The rule language was clarified in
response to comments on the
preliminary rule language.
A licensee would also need the
capability to detect unauthorized
removal of the radioactive material. For
category 1 quantities of radioactive
material, a licensee would need to
immediately detect any attempted
unauthorized removal through the use
of electronic sensors linked to an alarm
or continuous visual surveillance. For
category 2 quantities of radioactive
material, a licensee would need to verify
the presence of the radioactive material
through weekly physical checks, tamper
indicating devices, actual usage of the
material, or other means.
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10. What are the requirements for
personnel communications and data
transmission?
Licensees would be required to
maintain continuous capability for
personnel communication and
electronic data transmission and
processing among site security systems
for any personnel and automated or
electronic systems used to support the
site security systems. Licensees would
be required to have alternative
capability for any system in the event of
loss of the primary means of
communication or data transmission
and processing. The alternative means
could not be subject to the same failure
mode as the primary systems.
11. What would a licensee need to do
when it detects an intrusion into its
security zone?
A licensee’s response to an intrusion
would depend on the licensee’s
assessment of the purpose of the
intrusion, but a response would be
required without delay. If the
unauthorized access appeared to the
licensee to be an actual or attempted
theft, sabotage, or diversion of category
1 or category 2 quantities of radioactive
material, the licensee would have to
immediately notify and request an
armed response from the appropriate
LLEA. An immediate response by the
licensee would permit a more timely
response from law enforcement, thereby
reducing the risk that the material could
be used for malevolent purposes.
Immediate notification would also allow
for early warning to other possible
targets of a simultaneous attempt to
divert material from multiple locations.
A licensee’s decision to call the LLEA
and the NRC would depend not only on
the licensee’s assessment of the intent of
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the unauthorized access but also on
whether the area where the breach
occurred is an area the licensee had
previously determined needed to be
monitored in order to meet the NRC
physical protection requirements. Thus,
a licensee’s assessment and response to
an intrusion alarm in the business office
section of its facility could be entirely
different from its assessment and
response to an intrusion alarm in a
radioactive materials storage area.
12. Can a licensee use automated
devices to assess an intrusion and alert
an LLEA?
Depending on the security system, the
layout of controlled areas, and the
design capabilities of the sensors,
automated devices or systems may be
programmed to automatically summon
LLEA assistance in response to an
intrusion alarm.
13. What coordination would be
required with local law enforcement
agencies?
Licensees would be required to
coordinate, to the extent practicable,
with the LLEA to discuss the LLEA
response to threats to the licensee’s
facility. An LLEA would be defined as
a government entity that has the
authority to make arrests and the
capability to provide an armed
response. In the event of an actual or
attempted theft, sabotage, or diversion
of radioactive material, an armed
response is likely to be necessary.
Adversaries could be well armed, and
the small unarmed or lightly-armed
private security guard service typically
used at byproduct material licensee sites
would not be an adequate substitute for
an LLEA. However, the LLEA need not
be a municipal or county police force.
If a hospital or university campus police
force is the nearest law enforcement
agency to the licensee’s operation
capable of providing an armed response
and making arrests, that police force
would meet the proposed definition of
an LLEA.
A licensee would also have to
consider whether the LLEA could
provide the needed armed response at
all times. Some LLEAs are on duty only
during specified hours, and in such
cases, the licensee would have to
identify and coordinate with the closest
LLEA able to provide an armed response
and arrest perpetrators when the
primary LLEA is off-duty.
Coordination activities include
providing a description of the facility,
radioactive materials, and security
measures and notification that the
licensee will request a timely and armed
response to any actual or attempted
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theft, sabotage, or diversion of the
licensee’s radioactive materials.
Coordination activities also include
requesting information from the LLEA
concerning the LLEA’s capabilities to
provide a timely armed response and to
participate in drills or exercises, and
requesting a contact in order to establish
a means of direct communication. The
licensee would be required to request
that the LLEA enter into a written
agreement with the licensee that
describes the LLEA’s commitments to
provide a response. The licensee would
be required to document its
coordination efforts, including the
dates, times, and locations of meetings
and a list of licensee and LLEA staff
present at the meetings. Licensees
would be required to update their
security plans with affected LLEAs
every 12 months. At the suggestion of a
commenter on the preliminary rule
language, the NRC has added a new
provision for the licensee to request that
the LLEA notify the licensee when the
LLEA’s response capabilities become
degraded. This is not intended to
address a short-term situation where the
LLEA may be responding to another
emergency, but to address conditions
that would last for a longer timeframe,
such as a severe shortage of law
enforcement personnel during a
recovery from a natural disaster.
Coordination with an LLEA is
essential in developing an effective and
efficient physical protection program.
Because certain situations may
necessitate an armed response, a
strategy that is consistent in scope and
timing with realistic potential
vulnerabilities of the subject radioactive
material should be coordinated well in
advance with the LLEA. Another
purpose of coordination is to provide
the responsible LLEA with an
understanding of the potential
consequences associated with
unauthorized use of the radioactive
material of concern, so that the LLEA
can determine the appropriate priority
of its response. The LLEA response
would be needed not only to interdict
and disrupt an attempted theft or
sabotage onsite, but possibly for offsite
coordination to protect public health
and safety, and to mitigate the potential
consequences of unauthorized use of
radioactive material.
14. What if the LLEA declines to
coordinate with a licensee?
The NRC recognizes that it cannot
exercise authority over LLEAs, or any
party, over which a licensee has no
control and the NRC has no legal
jurisdiction. The NRC also recognizes
that an LLEA may have good reasons,
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including resource limitations and
possibly other coinciding events within
its jurisdiction, for not entering into a
formal agreement with a licensee.
An LLEA’s refusal to coordinate with
a licensee would not by itself render a
licensee’s security plan inadequate,
however. In making its determination
on the adequacy of the plan, the NRC
will recognize that in an actual
emergency, State and local government
officials will respond to protect the
health and safety of the public. A
licensee would also be required under
§ 37.45(a)(2) to notify the appropriate
NRC regional office within three
business days if the LLEA has not
responded to a request for coordination
within 60 days of the coordination
request; or if the LLEA notifies the
licensee that the LLEA does not plan to
participate in coordination activities.
The purpose of this notification would
be to allow NRC time to notify the
Department of Homeland Security
(DHS), or where necessary, contact the
LLEA directly, to ensure that the LLEA
understands the importance of adequate
coordination. Through these
interactions, the NRC would obtain
confidence that the LLEA would
respond in the event of an actual
emergency. Thus, if the LLEA refuses to
coordinate beforehand, the licensee
could still comply by making and
documenting periodic good-faith efforts
to elicit the LLEA’s participation in
planning for a timely and effective
response. The licensee would be
required to notify the NRC if the LLEA
declines to engage in coordination
activities.
15. What are the LLEA notification
requirements for work at a temporary
job site?
For temporary job sites (i.e., locations
not specifically identified by the license
for possession of radioactive materials),
the proposed rule would require
licensees to provide advance written
notification to the appropriate LLEA(s)
at least 3 business days in advance if the
licensee plans to use or store category 1
or category 2 quantities of radioactive
material at the temporary job site for
more than 7 consecutive calendar days.
This requirement is intended to ensure
that local law enforcement officers who
might be summoned to such a job site
in the event of a security incident are
aware that they might be summoned,
will know the potentially affected
location, and are able to reach
responsible licensee representatives
before the operations begin if the
officers want additional information.
The NRC is proposing 7 consecutive
calendar days as a threshold for the
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LLEA notification requirement in an
effort to balance the need for timely
LLEA awareness with the need to avoid
licensee notification requirements that
may be out of proportion to the security
risks. The NRC is aware that some
temporary job sites may only be in use
by a licensee for several days a year on
short notice and at unpredictable
intervals. These circumstances make it
difficult for individuals or groups to
plan and execute theft, sabotage, or
diversion even with the help of an
insider.
The notification would need to
include such things as the purpose of
the notification, timeframe and location
for the temporary work, information on
the quantities of radioactive material to
be used or stored at the site, and contact
information.
The proposed notification
requirement would not preclude a
licensee from coordinating with an
LLEA at a temporary job site, if the
LLEA and licensee believe it would be
beneficial to do so. Notification would
give the LLEA essential information
about the time, location, and nature of
the activity so that the LLEA could be
prepared to respond if necessary, and
would provide the LLEA with an
opportunity to request more information
if needed.
The NRC is specifically inviting
comment on the requirement to contact
the LLEA for work at a temporary
jobsite. Please consider the following
questions in developing comments:
(1) Is there any benefit in requiring
that the LLEA be notified of work at a
temporary jobsite?
(2) Should notifications be made by
licensees for work at every temporary
jobsite or only those where the licensee
will be working for longer periods, such
as the 7 day timeframe proposed in the
rule?
(3) If notifications are required, is 7
days the appropriate threshold for
notification of the LLEA or should there
be a different threshold?
(4) Will licensees be able to easily
identify the LLEA with jurisdiction for
temporary jobsites or does this impose
an undue burden?
(5) Are LLEAs interested in receiving
these notifications?
16. Would a licensee be prohibited from
working at a temporary job site if the
licensee couldn’t notify the affected
LLEA(s) 3 business days in advance?
No. The proposed LLEA notification
requirement for temporary job site
operations provides for unforeseen
circumstances under which a licensee
might not be able to provide 3 business
days written advance notice to the
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LLEA. If, due to an emergency or other
unforeseen circumstances, a licensee is
required to work at a temporary job site
for more than 7 consecutive calendar
days and is unable to provide the 3 days
advance written notice to the LLEA
before the licensee’s trip to the site, the
licensee would be required to provide as
much advance notice as possible by
telephone, facsimile, or e-mail.
17. What are the proposed special
requirements for mobile sources?
The proposed rule would require
licensees using mobile devices
containing a category 1 or category 2
quantity of radioactive material to have
two independent physical controls that
form tangible barriers to prevent
unauthorized removal of devices. For
devices in or on a vehicle or trailer, a
licensee would be required to use a
method to disable the vehicle or trailer
when it is not under direct control and
constant surveillance by the licensee.
Licensees would not be allowed to rely
on the removal of an ignition key to
meet this requirement. These provisions
are in addition to the other requirements
in subpart C.
Mobile devices, particularly portable
ones, are likely to be more vulnerable to
attempted theft or diversion because an
adversary could more easily remove
these devices before the licensee or
LLEA has an opportunity to respond.
The objective of this requirement is to
delay intruders long enough for a timely
licensee and LLEA response.
A mobile device is defined in the
proposed rule as a piece of equipment
containing licensed radioactive material
that is either: (1) Mounted on wheels or
casters, or otherwise equipped for
moving without a need for disassembly
or dismounting; or (2) designed to be
hand carried. Mobile devices do not
include stationary equipment installed
in a fixed location, such as an irradiator,
but the proposed definition would
include radiography cameras, source
changers, well logging equipment,
gauges or controllers, storage containers,
lead pigs for holding sources during a
source exchange, and onsite or offsite
transportation packages.
Commenters on the preliminary rule
language requested that the requirement
to disable the vehicle or trailer when not
under direct control and constant
surveillance by the licensee be modified
to provide an exception for oil and gas
field service vehicles that may have to
evacuate a work area quickly due to
extreme hazard. The extra time needed
to overcome a vehicle disabling feature
could delay timely evacuation and
result in bodily harm or death under
certain operating conditions, such as
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fire or loss of well head pressure
control. The NRC recognizes the need to
balance security measures against health
and safety concerns and is willing to
consider some form of relief from the
proposed vehicle disabling
requirements. The NRC is specifically
requesting comment on this issue.
Please consider the following questions
when developing comments on this
issue:
(1) Should relief from the vehicle
disabling provisions be provided?
(2) Have licensees experienced any
problems in implementing this aspect of
the Increased Controls?
(3) Should there be an exemption
written into the regulations or should
licensees with overriding safety
concerns be required to request an
exemption from the regulations to
obtain relief from the provision?
(4) If an exemption is included in the
regulations, should it be a blanket
exemption or a specific exemption for
the oil and gas industry?
(5) Does the disabling provision
conflict with any Occupational Safety
and Health Administration
requirements or any State requirements?
sabotage, or diversion of a category 1 or
category 2 quantity of radioactive
material as soon as possible after
initiating a response, which includes
notification of the LLEA. The licensee
would be required to submit a written
report to the NRC within 30 days after
the initial notification. A licensee would
also be required to report any suspicious
activity related to possible theft,
sabotage, or diversion of category 1 or
category 2 quantities of radioactive
material to both the LLEA and the NRC.
The NRC is specifically requesting
comment on the reporting requirements.
Please consider the following questions
when developing comments on this
issue.
(1) Are these the appropriate items
and thresholds to be reported to the
LLEA?
(2) Are these the appropriate items
and thresholds to be reported to the
NRC?
(3) Should suspicious activities be
reported? If they are reported, what type
of activities should be considered
suspicious?
(4) Is the timeframe for reporting
appropriate?
18. What maintenance, testing, and
calibration requirements would apply to
the security systems?
Licensees would be required to test
intrusion alarms, physical barriers, and
other systems used for securing and
monitoring access to radioactive
material, and these would have to be
maintained in operable condition. Each
intrusion alarm and associated
communication system subject to the
proposed rule’s requirements for
monitoring, detection, and assessment
would have to be inspected and tested
for performance as described in the
licensee’s security plan, but no less
frequently than once every quarter. In
guidance, licensees will also be
encouraged to conduct periodic testing
of the integrated functioning of their
monitoring, detection, and response
systems as a whole, including systems
for notifying affected LLEAs. Licensees
with dedicated security staff will also be
encouraged to notify affected LLEAs of
each opportunity to participate in drills
or table top exercises when licensees
conduct integrated tests of their
monitoring, detection, and response
systems. Licensees would be required to
maintain records of the maintenance,
testing, and calibration activities for 5
years.
20. How would a licensee determine the
effectiveness of the security program?
19. What events would a licensee need
to report to the NRC?
A licensee would be required to
report any actual or attempted theft,
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Licensees would be required to
review the security program every 12
months to confirm compliance with the
requirements. The review would
evaluate the security program content
and implementation. The licensee
would be required to document any
review findings and corrective actions
and the records would need to be
maintained for 5 years.
D. Transportation Security
1. What is the NRC authority to issue
these transportation security
requirements?
Sections 53, 81, and 161 of the AEA,
as amended, provide the NRC with the
statutory authority to issue these
transportation security requirements.
The NRC shares overlapping
jurisdiction over the transport of
radioactive material over public
roadways and by rail with DOT and the
Department of Homeland Security.
2. Why is this material being shipped?
In general, category 1 and category 2
quantities of radioactive material are
shipped to medical institutions,
companies that support medical and
academic institutions, and companies
that manufacture and distribute
radioactive material for various
industrial applications. As radioactive
sources get older, radioactive decay
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33917
decreases the sources’ strength and the
sources lose their effectiveness and have
to be replaced or replenished with new
sources. The older sources must be
transported for disposal or back to the
manufacturer.
In addition, commercial power plants
will occasionally transport large scale
plant equipment that may contain
radioactive material (e.g., steam
generators and reactor vessels) for
disposal.
3. What are the new transportation
security requirements?
In general, the proposed rule includes
requirements for pretransfer checks,
preplanning and coordination of
shipments, advance notification of
shipments, control, monitoring, and
communications during shipments,
procedures and training, investigations
of missing shipments, and reporting of
missing material. Each of these areas is
discussed in more detail in the
following questions and answers.
These requirements would apply to
ground transport of category 1 or
category 2 quantities of radioactive
material shipped in a single package or
in multiple packages in a single
conveyance. Per proposed § 73.35, the
category 1 requirements would also
apply to shipments of irradiated reactor
fuel weighing 100 grams or less in net
weight of irradiated fuel, exclusive of
cladding or other structural or
packaging material, which has a total
external radiation does rate in excess of
1 Sv (100 rem) per hour at a distance of
0.91 m (3 ft) from any accessible surface
without intervening shielding. Note that
a licensee is not responsible for
complying with these requirements
when a carrier aggregates radioactive
material, during transport or storage
incidental to transport, for two or more
conveyances from separate licensees
that individually do not exceed the
limits. As provided in proposed
§ 37.73(c), the shipping licensee would
be responsible for meeting the
requirements unless the receiving
licensee agrees in writing to arrange for
the in-transit physical protection. At the
suggestion of commenters on the
preliminary rule text, the proposed rule
text was revised to clarify that the
requirements would only apply to the
domestic portion of the transportation
for imports and exports.
4. Is verification of the transferee’s
license necessary?
Yes, proposed § 37.71 would require
any licensee transferring category 1 and
category 2 quantities of radioactive
material to a licensee of the NRC or an
Agreement State to verify that the
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transferee’s license authorizes the
receipt of the type, form, and quantity
of radioactive material to be transferred.
For transfers of category 1 quantities of
radioactive material, the transferring
licensee would also be required to verify
that the licensee is authorized to receive
radioactive material at the address
requested for delivery. These
verifications would be conducted with
the license issuing authority, i.e., the
NRC or the appropriate Agreement State
or by using the license verification
system. The license verification system
is a new web-based system that NRC is
developing that may be used to verify
the validity of a license issued by either
NRC or an Agreement State. Although
this system is in the early stages of
development, it will be available before
the effective date of the final rule. If the
system is not available licensees would
need to contact the appropriate
licensing agency. Licensees should
contact the appropriate NRC regional
office to verify the validity of NRC
licensees. Information on Agreement
State contacts is provided on the NRC
web page at https://nrc.stp.ornl.gov/
asdirectory.html. Licensees exporting
material would need to meet the
requirements in 10 CFR part 110 for
checking the documentation that the
recipient has the necessary
authorization under the laws and
regulations of the importing country.
These actions are intended to mitigate
the risk that the material could be
shipped to an unauthorized recipient.
The NRC is considering subjecting the
transfers of category 2 quantities of
radioactive material to the license
address verification requirement. If
category 2 transfers are made subject to
the license address verification
requirement, the transferring licensee
would be required to verify with the
license issuing authority that the
transferee licensee is authorized to
receive radioactive material at the
address requested for delivery. We are
specifically inviting public comment on
several aspects of license and address
verification. In developing comments on
this aspect, consider the following:
(1) Should there be a requirement for
verification of the license for transfers of
category 2 quantities of radioactive
material or would it be acceptable to
wait for the system being developed
before requiring license verification for
transfers of category 2 quantities of
radioactive material?
(2) We are interested in how address
verification might work for shipments to
temporary job sites and the ability of
both licensees and the Agreement States
to comply with such a requirement. For
example, would States be able to
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accommodate such requests with their
current record systems?
(3) We are also seeking comment on
the frequency of the license verification.
For example, should a licensee be
required to check with the licensing
agency for every transfer or would an
annual check (or some other frequency)
of the license be sufficient?
(4) If an annual check is allowed, how
would the transferring licensee know if
a license has been modified since the
last check and that the licensee is still
authorized to receive the material?
5. Is preplanning and coordination of
the shipments necessary?
Yes, § 37.75(a) of the proposed rule
would require preplanning and
coordination of shipment information
for shipments of category 1 quantities of
radioactive material. The shipping
licensee (licensee sending the licensed
material) would be required to
coordinate the departure and arrival
times, including the no-later-than
arrival time, with the receiving licensee
(licensee receiving the licensed
material). This coordination would
reduce the risk that theft or diversion of
the material would go unnoticed or
unreported. The licensee would also
need to preplan and coordinate the
shipment information with the State(s)
through which the shipment will pass.
As part of the coordination activities,
the licensee would be required to
discuss the State’s intention to provide
law enforcement escorts for the
shipments, identify highway route
control quantity shipments, identify safe
havens, and arrange for any positional
information sharing. The purpose of the
information sharing is to ensure
minimal delay of the shipment.
For shipments of category 2 quantities
of radioactive material, § 37.75(b) of the
proposed rule would require that the
shipping licensee verify the shipment
no-later-than arrival time and the actual
arrival time with the receiving licensee.
The definitions section of the
proposed rule would define the term
‘‘no-later-than arrival time’’ as the date
and time that the shipping licensee and
receiving licensee have established as
the time at which an investigation will
be initiated if the shipment has not
arrived at the receiving facility. The nolater-than-arrival time may not be more
than 2 hours after the estimated arrival
time for category 1 shipments and not
more than 4 hours after the estimated
arrival time for category 2 shipments.
Verifying that the shipment arrives on
time provides the licensee with the
means to identify and immediately
report an unusual occurrence that could
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lead to the theft or diversion of the
material.
Commenters on the preliminary draft
rule text suggested that a timeframe be
added to the definition and suggested 24
hours as the appropriate timeframe. The
NRC agrees that the definition would be
strengthened by adding a timeframe;
however, the NRC believes that 2 hours
for category 1 shipments and 4 hours for
category 2 shipments are the
appropriate timeframes. The NRC
believes that 24 hours is too long before
starting an investigation. The sooner an
investigation is started, the better
chance there is of recovering the
material.
6. What does the NRC consider to be a
safe haven?
A definition for the term ‘‘safe haven’’
has been added to the definitions
section of the proposed rule text at the
request of commenters on the
preliminary rule text. A safe haven
would be defined as ‘‘[a] readily
recognizable and readily accessible site
at which security is present or from
which, in the event of an emergency, the
transport crew can notify and wait for
the local law enforcement authorities.’’
The NRC expects safe havens to be
identified and designated by the
licensee.
Licensees should use the following
criteria in identifying safe havens for
shipments: Close proximity to the route,
i.e., readily available to the transport
vehicle; security from local, State, or
Federal assets is present or is accessible
for timely response; the site is well lit,
has adequate parking, and can be used
for emergency repair or to wait for LLEA
response on a 24-hour a day basis; and
additional telephone facilities are
available should the communications
system of the transport vehicle not
function properly. Possible safe haven
sites include: Federal sites having
significant security assets; secure
company terminals; State weigh
stations; truck stops with secure areas;
and LLEA sites, including State police
barracks.
In addition, in response to comments
on the preliminary rule text, the NRC
revised the proposed § 37.75(a)(2) to
clarify that the preplanning and
coordination of all category 1 shipments
with the governor or designee of each
state that the shipment will pass
through will require the identification of
safe havens.
7. Is the shipping licensee required to
notify the receiving licensee if the nolater-than arrival time changes?
Yes. If the no-later-than arrival time
will not be met, then under § 37.75(d) of
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the proposed rule, the shipping licensee
must inform the receiving licensee of
the new no-later-than arrival time for
shipments of category 1 or category 2
quantities of radioactive material. This
provision allows licensees the ability to
modify departure and arrival time due
to unforeseen events and was added at
the suggestion of commenters on the
preliminary rule text.
8. Whom would the licensee notify
when the shipment arrives?
Proposed § 37.75(c) would require
that the receiving licensee notify the
shipping licensee when the shipment of
a category 1 or category 2 quantity of
radioactive material arrives at its
destination. The notification must be no
later than 4 hours after the package
arrives. A timeframe was added to the
proposed rule at the suggestion of
commenters on the preliminary rule
text.
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9. What does State refer to in the
requirements?
As used in the definitions section of
the proposed rule, the term ‘‘State’’
means the 50 States, the District of
Columbia, the Commonwealth of Puerto
Rico, the Virgin Islands, Guam,
American Samoa, and the
Commonwealth of the Northern Mariana
Islands. A list of the contact information
for the governor’s designees is
published annually in the Federal
Register, most recently on July 14, 2009
(74 FR 34053). An updated list is posted
on the NRC Web site at https://nrcstp.ornl.gov/special/designee.pdf.
Copies may also be obtained by
contacting the Director, Division of
Intergovernmental Liaison and
Rulemaking, Office of Federal and State
Materials and Environmental
Management Programs, Nuclear
Regulatory Commission. If the final rule
is approved, the NRC will work with the
States to include a separate column for
contacts for 10 CFR part 37.
10. What advance notifications would
be required?
Proposed § 37.77 would require
advance written notifications for
shipments containing category 1
quantities of radioactive material. The
advance notifications would be made to
the NRC and to any State through which
a shipment was being transported. The
State notification would be made to the
governor or the governor’s designee.
Advance notification provides States
and the NRC with knowledge of
shipments so that in the event there is
an increase in the risk of theft or
diversion of the material, the regulator
could delay or reroute the shipment to
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minimize the risk. This advance
notification also allows States with
escort requirements to engage in
planning to support the shipment.
Advance notifications would not be
required for shipments of category 2
quantities of radioactive material, unless
the shipment falls within the scope of
10 CFR 71.97(b).
11. What information would be
included in an advance notification?
Proposed § 37.77(b) would require the
following information be included in an
advance notification for a category 1
shipment of radioactive material, if
available at the time of notification: (1)
The name, address, and telephone
number of the shipper, carrier, and
receiver of the shipment; (2) the license
number of the shipper and receiver; (3)
a description of the radioactive material
contained in the shipment, including
the radionuclides and quantity; (4) the
point of origin of the shipment and the
estimated time and date that shipment
will commence; (5) the estimated time
and date that the shipment is expected
to enter each State along the route; (6)
the estimated time and date of arrival of
the shipment at the destination; and (7)
the contact and telephone number for
the point of contact. For the purpose of
coordination only, the actual
information in the advance notification
would not be considered to be SGI–M.
Any information that is not available at
the time of the initial notification would
be provided in a revised notification
once the information becomes available.
12. What should a licensee do if the
shipment schedule is revised or the
shipment cancelled?
If the shipment schedule is revised or
cancelled, §§ 37.77(c) and (d),
respectively, of the proposed rule would
require the shipping licensee to notify
the appropriate States and the NRC. The
preliminary rule text required that the
licensee would telephone the governor’s
designees when it discovered that the
schedule would not be met. In response
to comments on the preliminary rule
text, the NRC has modified the proposed
rule text to require that the governor’s
designee be notified without specifying
a specific means for the notification.
13. What should a licensee do if the
shipment does not arrive by the nolater-than arrival time?
Proposed § 37.79(d) would require a
licensee that has shipped category 1 or
category 2 quantities of radioactive
material to initiate an investigation for
any shipment that has not arrived at the
receiving licensee’s facility by the
designated no-later-than arrival time.
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33919
The no-later-than arrival time would be
defined as the date and time that the
shipping licensee and receiving licensee
have established as the time at which an
investigation will be initiated if the
shipment has not arrived at the
receiving facility. The no-later-thanarrival time may not be longer than 2
hours after the estimated arrival time for
a shipment of category 1 quantities of
radioactive material and 4 hours after
the estimated arrival time for a
shipment of category 2 quantities of
radioactive material. Commenters on the
preliminary draft rule text suggested
that a timeframe be added to the
definition and suggested 24 hours as the
appropriate timeframe. The NRC agrees
that the definition would be
strengthened by adding a timeframe;
however, the NRC believes that 2 hours
for category 1 shipments and 4 hours for
category 2 shipments are the
appropriate timeframes. The NRC
believes that 24 hours is too long before
starting an investigation. The sooner an
investigation is started, the better
chance there is of recovering the
material.
14. When must a licensee make
notification that a shipment is lost or
missing?
When a licensee determines that a
shipment of a category 1 quantity of
radioactive material is lost or missing,
§ 37.81(a) of the proposed rule would
require the licensee to notify the LLEA
in the area of the shipment’s last
confirmed location within 1 hour and
then to notify the NRC Operations
Center. Notification to the NRC should
be as prompt as possible, but not at the
expense of causing delay or interference
with the LLEA response to the event.
When a licensee determines that a
shipment of category 2 quantities of
radioactive material is lost or missing,
§ 37.81(b) of the proposed rule would
require the licensee to notify the NRC
Operations Center within 4 hours of
such determination. The licensee would
also be required to immediately notify
the NRC Operations Center if, after 24
hours from its determination that the
shipment was lost or missing, the
location of the material still cannot be
determined.
Early notification provides for a more
timely response from law enforcement,
thereby reducing the risk of the misuse
of the material.
15. Should licensees make notification
that a lost or missing shipment has been
found?
Yes, proposed §§ 37.81(e) and (f), for
category 1 shipments and category 2
shipments respectively, require the
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licensee to notify the NRC Operations
Center when a lost or missing shipment
has been located. This notification
would be considered an update on the
initial notification. Without this
notification, regulatory authorities and
LLEA would waste resources continuing
any search for the material.
16. What would a licensee be required
to do if there is an attempt to steal or
divert a shipment?
For shipments of category 1 quantities
of radioactive material, proposed
§ 37.81(c) would require a licensee who
discovers an actual or attempted theft or
diversion of a shipment, or any
suspicious activity related to a
shipment, to notify the designated LLEA
along the shipment route as soon as
possible. After notifying the LLEA, the
licensee would be required to notify the
NRC Operations Center. The NRC
Operations Center would notify other
affected States and the agency’s Federal
partners. For shipments of category 2
quantities of radioactive material,
proposed § 37.81(d) would require a
licensee who discovers an actual or
attempted theft or diversion of a
shipment, or any suspicious activity
related to a shipment, to notify the NRC
Operations Center as soon as possible.
These security measures enhance the
likelihood that the material will be
successfully protected or recovered and
allows for early warning of other
possible victims of a simultaneous
attempt to divert material from multiple
locations.
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17. What types of procedures and
training are necessary for shipping
category 1 quantities of radioactive
material?
Proposed § 37.79(c)(1) would require
licensees shipping category 1 quantities
of radioactive material to ensure that
normal and contingency procedures are
developed to cover notifications;
communication protocols; loss of
communication; and response to an
actual or attempted theft or diversion of
a shipment, or any suspicious activity
related to a shipment. The licensee
would be required to ensure that
drivers, accompanying personnel,
railroad personnel, and movement
control center personnel are
appropriately trained in the normal and
contingency procedures. Procedures and
training provide reasonable assurance
that these individuals are prepared for
most situations and are able to act
without delay to prevent the theft or
diversion of shipments.
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18. What would be included in the
communication protocols?
Proposed § 37.79(c)(1)(ii) would
require that the communication
protocols include a strategy for the use
of authentication and duress codes and
provisions for refueling or other stops,
detours, and locations where
communication is expected to be
temporarily lost.
19. What are the physical protection
requirements for road shipments of
category 1 quantities of radioactive
material?
Proposed § 37.79(a)(1)(i) would
require that any licensee that ships
category 1 quantities of radioactive
material by road either establish or use
a carrier that has established, movement
control centers that maintain position
information from a location remote from
the activity of the transport vehicle or
trailer. The control centers would be
required to monitor shipments on a
continuous and active monitoring basis
(24 hours a day, 7 days a week), and
have the ability to communicate
immediately, in an emergency, with the
appropriate law enforcement agencies.
Proposed § 37.79(a)(1)(ii) would
require that the licensee ensure that
redundant communications are in place
that would allow the transport to
contact an escort vehicle (if used) and
the movement control center at all
times. The redundant communication
must not be subject to the same
interference factors as the primary
communication method. The same
interference factors mean any two
systems that rely on the same hardware
or software to transmit their signal (e.g.,
cell tower or proprietary network).
Redundant communications provide
drivers with the means to immediately
report an unusual occurrence that could
lead to the theft or diversion of the
material. Early notification would
permit a more timely response from law
enforcement, thereby reducing the risk
of the misuse of the material.
Proposed § 37.79(a)(1)(iii) would
require that the licensee ensure that the
shipments are continuously and actively
monitored by a telemetric position
monitoring system or an alternative
tracking system reporting to a
movement control center. The
movement control center would be
required to provide positive
confirmation of the location, status, and
control over the shipment and be
prepared to implement preplanned
procedures in response to deviations
from the authorized route or to a
notification of actual or attempted theft
or diversion or suspicious activities
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related to the theft, loss, or diversion of
a shipment. These procedures would
include the identification of, and
contact information for, the appropriate
LLEA along the shipment route.
A telemetric position monitoring
system is a data transfer system that
captures information by instrumentation
and/or measuring devices about the
location and status of a transport vehicle
or package between the departure and
destination locations. The gathering of
this information permits remote
monitoring and reporting of the location
of a transport vehicle or package. GPS
and radiofrequency identification
(RFID) are examples of telemetric
position monitoring systems.
If the driving time period is greater
than the maximum number of allowable
hours of service in a 24-hour duty day
as established by the DOT Federal
Motor Carrier Safety Administration,
proposed § 37.79(a)(1)(iv) would require
that the licensee ensure that an
accompanying individual is provided
for the entire shipment. The
accompanying individual may be
another driver. This security measure
provides reasonable assurance that the
material will be protected from theft or
diversion when it is stationary, as well
as in emergency situations where it
becomes necessary for the driver to stop
or leave the vehicle.
20. Would GPS be required?
No, GPS would not be required. For
category 1 material, the NRC is
proposing to require continuous and
active monitoring for shipments.
Continuous and active monitoring
means that at any time while the
shipment is enroute, the licensee must
be knowledgeable of the shipment’s
whereabouts. Not specifying a particular
technology provides licensees with
flexibility to design a continuous and
active monitoring system that meets
their unique circumstances. However,
GPS would be considered an acceptable
method.
21. What are the physical protection
requirements for rail shipments of
category 1 quantities of radioactive
material?
Proposed § 37.79(b)(1)(i) would
require each licensee that ships category
1 quantities of radioactive material by
rail to ensure that rail shipments are
monitored by a telemetric position
monitoring system or an alternative
tracking system reporting to a licensee,
third-party, or railroad communications
center which meets certain criteria. The
communications center would need to
provide positive confirmation of the
location of the shipment and its status.
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The communications center would also
need to be prepared to implement
preplanned procedures in response to
deviations from the authorized route or
to a notification of an actual or
attempted theft or diversion of a
shipment, or any suspicious activity
related to a shipment. These procedures
include the identification of, and
contact information for, the appropriate
LLEA along the shipment route. Rail
shipment tracking provides the means
for a communications center to
immediately report an unusual
occurrence that could lead to the theft
or diversion of the material. Early
notification provides for a more timely
response from LLEAs, thereby reducing
the risk of the misuse of the material.
Proposed § 37.79(b)(1)(ii) would
require that the licensee have an NRCapproved monitoring plan to ensure that
no unauthorized access to the shipment
takes place while the shipment is in a
railroad classification yard. The NRC is
specifically seeking comment on the
feasibility of this requirement. In
developing comments on this aspect,
consider the following questions:
(1) How could surveillance of the
shipment be accomplished while in the
classification yard?
(2) Would the classification yard
allow an individual to accompany a
shipment while the shipment is held in
the classification yard?
(3) What precautions might be
necessary from a personal safety
standpoint?
22. What are the physical protection
requirements for shipments of category
2 quantities of radioactive material?
Proposed § 37.79(a)(2) would require
that a licensee shipping category 2
quantities of radioactive material by
road maintain constant control and/or
surveillance during transit and have the
capability for immediate
communication to summon appropriate
response or assistance. Proposed
§ 37.79(a)(3) (for category 2 road
shipments) and proposed § 37.79(b)(2)
(for category 2 rail shipments), in the
case of the licensee using a common
carrier, would require that licensees use
a carrier that has an established package
tracking system. An established package
tracking system means a documented,
proven, and reliable system routinely
used to transport objects of value. The
package tracking system must allow the
shipper or transporter to identify when
and where the package was last and
when it should arrive at the next point
of control. The licensee would be
required to use a carrier that maintains
constant control and surveillance during
transit and has the capability for
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immediate communication to summon
appropriate response or assistance. The
carrier must also require an authorized
signature prior to releasing the package
for delivery or return.
In general, the licensee must be able
to contact the shipping carrier and
determine the approximate location of
the shipment. Package tracking systems,
such as common overnight delivery
service with standard tracking would be
acceptable. These requirements mitigate
with reasonable assurance the risk of
loss, theft or diversion of the material.
23. How long do records related to a
shipment need to be maintained?
Proposed § 37.71 would require
licensees to retain records documenting
the verification for license authorization
for category 1 quantities of radioactive
material transfers for 5 years. Proposed
§ 37.75(e) would require that licensees
retain records related to preplanning
and coordination for 5 years. Proposed
§ 37.77(e) would require that licensees
retain records related to the advance
notification for shipments of category 1
quantities of radioactive material for 5
years. The requirement for
documentation and record retention
related to the preplanning and
coordination of shipments was added at
the suggestion of commenters on the
preliminary rule language.
24. How is the public protected from
loss, theft, or diversion of these
shipments?
Regulating transport of radioactive
material is a joint responsibility of the
NRC and DOT. The quantities of
radioactive materials being considered
as part of this rulemaking, in general,
are transported in packages (casks) that
meet rigorous NRC safety standards. The
packages are referred to as ‘‘Type B’’
packages in both NRC and DOT
regulations. The NRC fact sheet on
transportation of radioactive materials
can be found at https://www.nrc.gov/
reading-rm/doc-collections/fact-sheets/
transport-spenfuel-radiomats-bg.html.
The carrier transporting radioactive
material must also meet the DOT’s
requirements for shipment of the
radioactive material. A link to the DOT’s
Web site is provided on the NRC’s Web
site at https://www.nrc.gov/materials/
transportation.html.
25. What are the requirements for small
quantities or irradiated reactor fuel?
The proposed rule would add a new
§ 73.35 to Part 73, which would provide
that the requirements for shipments of
irradiated reactor fuel weighing 100 g
(0.22 lb) or less in net weight of
irradiated fuel, exclusive of cladding or
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33921
other structural or packaging material,
which has a total external radiation dose
rate in excess of 1 Sv (100 rem) per hour
at a distance of 0.91 m (3 ft) from any
accessible surface without intervening
shielding, would be the same as the
requirements for shipments of category
1 quantities of radioactive material.
26. What doesn’t this proposed rule
cover?
The proposed rule does not address
air or water transport. Transport of
radioactive material within airports and
by air is regulated by the Federal
Aviation Administration. Transport of
radioactive material within ports and by
waterway is regulated by the U.S. Coast
Guard.
The proposed rule also does not
address transshipments of category 1 or
category 2 quantities of radioactive
material through the United States.
Transshipments are shipments that are
originated by a foreign company in one
country, pass through the United States,
and then continue on to a company in
another country. Transshipments are
regulated by the DOT and DHS.
Finally, this rulemaking does not
address transport of spent fuel, except
irradiated reactor fuel weighing 100 g
(0.22 lb) or less in net weight of
irradiated fuel, exclusive of cladding or
other structural or packaging material,
which has a total external radiation dose
rate in excess of 1 Sv (100 rem) per hour
at a distance of 3 ft from any accessible
surface without intervening shielding.
III. Discussion of Proposed Rule by
Section
Section 30.6
Communications
This section would be revised to
include a reference to the new 10 CFR
part 37.
Section 30.13
Carriers
This section would be revised to
include 10 CFR part 37 in the list of
regulations that exempt common
carriers.
Section 30.32
Licenses
Application for Specific
Paragraph (l) would be added to
require that an application under 10
CFR part 30 include information
concerning whether the applicant’s
proposed security program meets the
requirements of 10 CFR part 37.
Section 30.33 General Requirements
for Issuance of Specific Licenses
Paragraph (a)(4) would be revised to
include a reference to the new 10 CFR
part 37.
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Section 32.1 Purpose and Scope
10 CFR part 37 would be added to the
list of 10 CFR parts that apply to
applications and licenses subject to this
part.
Section 33.1 Purpose and Scope
10 CFR Part 37 would be added to the
list of 10 CFR parts that apply to
applications and licenses subject to this
part.
later-than arrival time, Reviewing
official, Sabotage, Safe haven, Security
zone, Telemetric position monitoring
system, Temporary job site,
Trustworthiness and reliability, and
Unescorted access.
Section 37.7 Communications
This section would specify where all
communications and reports concerning
10 CFR part 37 would be sent.
Section 34.1 Purpose and Scope
10 CFR Part 37 would be added to the
list of 10 CFR parts that apply to
applications and licenses subject to this
part.
Section 35.1 Purpose and Scope
10 CFR Part 37 would be added to the
list of 10 CFR parts that apply to
applications and licenses subject to this
part.
Section 36.1 Purpose and Scope
10 CFR Part 37 would be added to the
list of 10 CFR parts that apply to
applications and licenses subject to this
part.
Section 37.1 Purpose
This section would establish the
purpose for the proposed new 10 CFR
part 37.
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Section 37.3 Scope
This section would establish the
scope of the proposed new 10 CFR part
37. These regulations would apply to
any person licensed by the NRC, who
possesses, uses, or transports category 1
or category 2 quantities of radioactive
material. Paragraph (a) would establish
the applicability for subpart B.
Paragraph (b) would establish the
applicability for subpart C. Paragraph (c)
would establish the applicability for
subpart D.
Section 37.5 Definitions
Definitions of the following terms that
would be included in this part are
identical to the definition of the term in
other parts of this chapter: Act,
Agreement State, Becquerel, Byproduct
material, Commission, Curie,
Government agency, License, Lost or
missing material, Person, State, and
United States. In addition, definitions
for the following terms are included in
this part: Approved individuals, Access
control, Aggregated, Background
investigation, Category 1 quantity of
radioactive material, Category 2 quantity
of radioactive material, Diversion,
Escorted access, Fingerprint Orders,
Isolation, License issuing authority,
Local law enforcement agency, Mobile
device, Movement control center, No-
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Section 37.9 Interpretations
This section would establish that no
interpretations of the meaning of the
regulations in 10 CFR part 37 by any
officer or employee of the Commission
other than a written interpretation by
the General Counsel will be recognized
as binding upon the Commission, unless
specifically authorized by the
Commission in writing.
Section 37.11
Specific Exemptions
This section would establish that the
Commission may grant exemptions from
the requirements of the regulations in 10
CFR part 37 that it determines are
authorized by law and that will not
endanger life or property or the common
defense and security, and are otherwise
in the public interest. Paragraph (b)
would exempt a licensee’s activities
from 10 CFR part 37 to the extent that
the activities are covered under the
physical protection requirements of 10
CFR part 73.
Section 37.13 Information Collection
Requirements: OMB Approval
Paragraph (a) would specify that the
NRC may not conduct or sponsor, and
a person is not required to respond to,
a collection of information unless it
displays a currently valid OMB control
number. Paragraph (b) would list those
sections in 10 CFR part 37 that have
approved information collection
requirements.
Section 37.21 Personnel Access
Authorization Requirements for
Category 1 or Category 2 Quantities of
Radioactive Material
Paragraph (a) of this section would
establish which licensees would need to
comply with the requirements of the
proposed subpart B of 10 CFR part 37.
Paragraph (b) would establish the
general performance objective to ensure
that the individuals subject to the access
authorization program are trustworthy
and reliable.
Paragraph (c)(1) would establish the
individuals that would be subject to the
access authorization program. Paragraph
(c)(2) would allow licensees to not
subject those individuals listed in 10
CFR 37.29(a) through (l) to the
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investigation elements of the access
authorization program. Paragraph (c)(3)
would require that licensees only
approve those individuals whose job
duties permit unescorted access to
category 1 or category 2 quantities of
radioactive material.
Section 37.23 Access Authorization
Program Requirements
This section would establish the
general requirements for the access
authorization program.
Section 37.25 Background
Investigations
This section would establish the
elements of the background
investigation that is necessary before
granting an individual unescorted
access to category 1 or category 2
quantities of radioactive material. The
scope of the initial investigation would
be the past 10 years.
Section 37.27 Requirements for
Criminal History Records Checks of
Individuals Granted Unescorted Access
to Category 1 or Category 2 Quantities
of Radioactive Material
Paragraph (a) would establish the
general requirements for criminal
history records checks of individuals to
be granted unescorted access to category
1 or category 2 quantities of radioactive
material.
Paragraph (b) would prohibit a
licensee from basing a final
determination to deny an individual
unescorted access authorization solely
on the basis of certain information
received from the FBI.
Paragraph (c) would establish the
procedure for submitting fingerprint
records to the NRC.
Section 37.29 Relief From
Fingerprinting, Identification, and
Criminal History Records Checks and
Other Elements of Background
Investigations for Designated Categories
of Individuals Permitted Unescorted
Access to Certain Radioactive Materials
or Other Property
This section would provide relief
from the fingerprinting and criminal
history records check requirements and
the background investigation
requirements of this subpart for the
certain categories of individuals.
Section 37.31
Information
Protection of
This section would outline the
proposed requirements for the
protection and release to authorized
personnel of personal information
collected by a licensee during a
background investigation.
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Section 37.33 Access Authorization
Program Review
This section would outline the
requirements for an annual access
authorization program review to
confirm compliance with the
requirements of subpart B of 10 CFR
part 37 and for comprehensive
corrective actions to be taken in
response to any nonconformance
identified by the review.
Section 37.41
Security Program
Paragraph (a) would establish the
applicability of the security program.
Paragraph (a)(1) would require licensees
that possess an aggregated quantity of
category 1 or category 2 quantities of
radioactive material to develop,
establish, implement, and maintain a
security program. Paragraph (a)(2)
would require those licensees that are
authorized to possess but don’t actually
possess an aggregated quantity to
develop a security program. Paragraph
(a)(2) would also require a licensee to
implement the security program at least
90 days before aggregating radioactive
material to the category 2 threshold and
to notify the NRC of the
implementation.
Paragraph (b) would establish the
general performance objective of the
security program.
Paragraph (c) would establish the
program features that must be addressed
in the security program.
Paragraph (d) would require licensees
that possess a category 1 or category 2
quantity of radioactive material to
submit information concerning the
licensee’s compliance with the security
program requirements within 30 days of
the final rule’s effective date.
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Section 37.43 General Security
Program Requirements
Paragraph (a)(1) would require
licensees to develop a written security
plan that addresses how the licensee
will implement the security program
requirements. Paragraph (a)(2) would
require the security plan to be reviewed
and approved by the individual with
overall responsibility for the security
program. Paragraph (a)(3) would allow a
licensee to revise its security plan to
ensure effective implementation of the
plan. Paragraph (a)(4) would require the
licensee to retain a copy of the current
security plan until the license is
terminated and any security plan
revisions for 5 years.
Paragraph (b)(1) would require
licensees to develop and maintain
written procedures for implementation
of the security plan. Paragraph (b)(2)
would require the procedures to be
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approved by the individual with overall
responsibility for the security program.
Paragraph (b)(3) would require the
licensee to retain a copy of the
procedures until the license is
terminated and any revisions for 5
years.
Paragraph (c) would require licensees
to conduct training and annual refresher
training on the security plan. Licensees
would be required to maintain training
records for 5 years from the date of the
training.
Paragraph (d) would require licensees
to protect the security plan and
implementing procedures from
unauthorized disclosure. Licensees
would be required to develop, maintain
and implement written policies and
procedures for controlling access to, and
for proper handling and protection
against unauthorized disclosure of, the
security plan and implementing
procedures. Only individuals with a
need-to-know and that have been
determined to be trustworthy and
reliable would be able to have access to
the protected information. The
information protection procedures
would be retained for 5 years after the
document is no longer needed.
Section 37.45 LLEA Coordination and
Notification
Paragraph (a) would require that a
licensee attempt to coordinate with an
LLEA and would specify the types of
information to be shared with the LLEA.
Paragraph (b) would establish when
the licensee must notify the LLEA about
planned work at a temporary job site
and the information to be shared in the
notification.
Paragraph (c) would require the
licensee to maintain records of its
coordination activities with any LLEA.
Section 37.47 Security Zones
Paragraph (a) would require licensees
to establish security zones for the use of
category 1 or category 2 quantities of
radioactive material.
Paragraph (b) would require the
establishment of temporary security
zones, as necessary, to meet transitory
or intermittent business activities.
Paragraph (c) would require that
security zones use physical barriers or
direct control of the security zone to
allow unescorted access only to
approved individuals.
Paragraph (d) would require licensees
to provide an approved individual to
maintain constant surveillance of
sources in temporary security zones or
in a security zone in which a physical
barrier or intrusion detection system has
been disabled to allow maintenance,
source receipt, preparation for
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33923
shipment, source installation, or
removal or exchange of category 1
quantities of radioactive material.
Section 37.49 Monitoring, Detection,
and Assessment
Paragraph (a) would require the
licensee to establish and maintain the
capability to continuously monitor and
detect without delay all unauthorized
entries into the security zones.
Paragraph (b) would require the
licensee to assess without delay each
actual or attempted unauthorized entry
into the security zone.
Paragraph (c)(1) would require the
licensee to maintain continuous
capability for personnel communication
and electronic data transmission and
processing among site security systems.
Paragraph (c)(2) would require the
licensee to provide alternative
capabilities for personnel
communication and data transmission
and processing.
Paragraph (d) would require the
licensee to respond without delay to any
actual or attempted unauthorized access
to the security zone.
Section 37.51 Maintenance, Testing,
and Calibration
This section would require licensees
to implement a maintenance, testing,
and calibration program to ensure that
intrusion alarms, associated
communication systems, and other
physical components of the systems
used to secure and detect unauthorized
access to radioactive material are
maintained in operable condition, are
capable of performing their intended
function when needed, and are
inspected and tested for operability and
performance every 3 months. Licensees
would be required to maintain the
maintenance, testing, and calibration
records for 5 years.
Section 37.53
Devices
Requirements for Mobile
This section would require licensees
that possess mobile devices containing
category 1 or category 2 quantities of
radioactive materials to have two
independent physical controls to secure
the radioactive material from
unauthorized removal and to use a
method to disable the vehicle or trailer
when the device is on a vehicle or
trailer.
Section 37.55
Review
Security Program
This section would require licensees
to conduct a review of the security
program every 12 months. The licensee
would be required to document the
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Federal Register / Vol. 75, No. 114 / Tuesday, June 15, 2010 / Proposed Rules
Section 37.79 Requirements for
Physical Protection of Category 1 and
Category 2 Quantities of Radioactive
Material During Shipment
results of the review and any findings
and keep the records for 5 years.
Section 37.57
Reporting of Events
Paragraph (a) would require licensees
to immediately notify the LLEA of any
actual or attempted theft, sabotage, or
diversion of category 1 or category 2
quantities of radioactive material and to
then notify the NRC.
Paragraph (b) would require licensees
to notify the LLEA upon discovery of
any suspicious activity related to the
theft, sabotage, or diversion of category
1 or category 2 quantities of radioactive
material and to then notify the NRC.
Paragraph (c) would require licensees
to submit a written report to the NRC
within 30 days of any report of actual
or attempted theft, sabotage, or
diversion of radioactive material.
Section 37.71 Additional
Requirements for Transfer of Category 1
and Category 2 Quantities of
Radioactive Material
This section would establish new
requirements for licensees transferring
category 1 and category 2 quantities of
radioactive material.
Section 37.73 Applicability of Physical
Protection of Category 1 and Category 2
Quantities of Radioactive Material
During Transit
This section would establish which
requirements apply to licensees
shipping category 1 or category 2
quantities of radioactive material and
what requirements apply during the
domestic portion of a shipment that is
imported from another country. This
section would also allow the receiving
licensee to arrange for the in-transit
physical protection of a shipment
instead of the shipping licensee as long
as the agreement is in writing.
Section 37.75 Preplanning and
Coordination of Shipment of Category 1
or Category 2 Quantities of Radioactive
Material
mstockstill on DSKH9S0YB1PROD with PROPOSALS2
This section would establish the
preplanning and coordination necessary
for a shipment of category 1 or category
2 quantities of radioactive material.
Section 37.77 Advance Notification of
Shipment of Category 1 Quantities of
Radioactive Material.
This section would establish the
requirements for advance notification to
the NRC and the governor of a State, or
the governor’s designee, of the shipment
of category 1 quantities of radioactive
material that will pass through or across
the State.
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This section would establish the
physical protection requirements for
shipments of category 1 and category 2
quantities of radioactive material.
Paragraph (a)(1) would establish the
requirements for shipping a category 1
quantity of radioactive material by road.
Paragraph (a)(2) would establish the
requirements for a licensee that
transports category 2 quantities of
radioactive material by road. Paragraph
(a)(3) would establish the requirements
for a licensee that uses a carrier for
shipping category 2 quantities of
radioactive material.
Paragraph (b)(1) would establish the
requirements for shipping category 1
quantities of radioactive material by rail.
Paragraph (b)(2) would establish the
security requirements for shipping
category 2 quantities of radioactive
material by rail.
Paragraph (c)(1) would require
licensees who make arrangements for
the shipment of category 1 quantities of
radioactive material to develop written
normal and contingency procedures to
address notifications, communication
protocols, loss of communication, and
response to actual or attempted theft or
diversion of a shipment, or any
suspicious activity related to a
shipment. Paragraph (c)(2) would
require licensees to ensure that drivers,
accompanying personnel, train crew,
and movement control center personnel
are trained in and understand both the
normal and contingency procedures.
Paragraph (d) would require the
shipping licensee to immediately
conduct an investigation of any
shipment of category 1 or category 2
quantities of radioactive material that is
lost or unaccounted for after the
designated no-later-than arrival time in
the advance notification.
Section 37.81
Reporting of Events
This section would establish
requirements for the shipping licensee
to make notifications upon the
discovery that a shipment is lost or
missing and upon discovery of any
actual or attempted theft or diversion of
a shipment, or suspicious activities
related to the theft or diversion of a
shipment of either a category 1 or
category 2 quantity of radioactive
material. This section would also
establish requirements for notification
upon recovery of a lost or missing
shipment. Written follow-up reports
would be required for all notifications.
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Section 37.101
Form of Records
This section would establish the
requirements for the storage and
protection of records required by this
part.
Section 37.103
Record Retention
This section would establish the
Commission’s termination of the license
as the end point of the retention period
for any record where a specific retention
period is not specified.
Section 37.105
Inspections
Paragraph (a) would require licensees
to allow the Commission the
opportunity to inspect the materials and
facilities subject to 10 CFR part 37.
Paragraph (b) would require the
licensee to make available for inspection
any records subject to 10 CFR part 37.
Section 37.107
Violations
Paragraph (a) of this section would
establish that the Commission may
obtain an injunction or other court order
to prevent a violation of the AEA, Title
II of the Energy Reorganization Act of
1974, as amended; or a regulation or
order issued under those Acts.
Paragraph (b) of this section would
establish the violations for which the
Commission may obtain a court order
for the payment of a civil penalty
imposed under section 234 of the AEA.
Section 37.109 Criminal Penalties
This section would establish the
sections in 10 CFR part 37 that are
issued under one or more of sections
161b, 161i, or 161o and are therefore
subject to criminal sanctions for willful
violations of, attempted violation of, or
conspiracy to violate the regulation.
Appendix A to 10 CFR Part 37—
Category 1 and Category 2 Radioactive
Materials
Table 1 of this appendix would
establish the radionuclides and
associated thresholds for category 1 and
category 2 quantities of radioactive
material. The appendix would also
provide the methodology for calculating
the sum of fractions for evaluating
combinations of multiple radionuclides.
Section 39.1
Purpose and Scope
10 CFR part 37 would be added to the
list of 10 CFR parts that apply to
applications and licenses subject to this
part.
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Federal Register / Vol. 75, No. 114 / Tuesday, June 15, 2010 / Proposed Rules
Section 51.22 Criterion for Categorical
Exclusion; Identification of Licensing
and Regulatory Actions Eligible for
Categorical Exclusion or Otherwise Not
Requiring Environmental Review
Paragraph (c)(3) would be revised to
include 10 CFR part 37.
Section 71.97 Advance Notification of
Shipment of Irradiated Reactor Fuel and
Nuclear Waste
Paragraph (b) would be revised to
delete the reference to shipments of
irradiated reactor fuel in quantities less
than that subject to the advance
notification requirements of § 73.37(f).
Proposed § 73.35 would provide that
such irradiated reactor fuel shipments
be subject to the same requirements that
apply to shipments of category 1
radioactive material, including the
advance notification requirements.
Section 73.35 Requirements for
Physical Protection of Irradiated Reactor
Fuel (100 Grams or Less) in Transit
A new section would be added to 10
CFR part 73 to address the physical
protection requirements for shipments
of irradiated reactor fuel weighing 100
g (0.22 lb) or less in net weight of
irradiated fuel, exclusive of cladding or
other structural or packaging material,
which has a total external radiation dose
rate in excess of 1 Sv (100 rem) per hour
at a distance of 0.91 m (3 ft) from any
accessible surface without intervening
shielding. The material would be
subject to the same transportation
security requirements as category 1
quantities of radioactive material.
IV. Criminal Penalties
For the purpose of Section 223 of the
AEA, the Commission is proposing to
amend 10 CFR parts 30, 32, 33, 34, 35,
36, 39, 51, 71, and 73 and add new part
37 under one or more of Sections 161b,
161i, or 161o of the AEA. Willful
violations of the rule would be subject
to criminal enforcement.
V. 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
proposed rule would be a matter of
compatibility between the NRC and the
Agreement States, thereby providing
consistency among the Agreement
States and the NRC requirements. The
NRC staff analyzed the proposed 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
Draft 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 or
provisions of Title 10 of the Code of
Federal Regulations. These program
elements are not adopted by Agreement
States. The following table lists the Parts
and Sections that would be created or
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 NRC invites comment on the
compatibility category designations in
the proposed rule and suggests that
commenters refer to Handbook 5.9 of
Management Directive 5.9 for more
information. The NRC notes that, like
the rule text, the compatibility category
designations can change between the
proposed rule and final rule, based on
comments received and Commission
decisions regarding the final rule. The
NRC encourages anyone interested in
commenting on the compatibility
category designations in any manner to
do so during the comment period.
DRAFT COMPATIBILITY TABLE FOR PROPOSED RULE
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Definition Act ....................................................................
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Definition Agreement State ..............................................
Definition Approved individual ..........................................
Definition Background Investigation .................................
Definition Becquerel .........................................................
Definition Byproduct Material ...........................................
Definition Category 1 quantities of radioactive material ..
Definition Category 2 quantities of radioactive material ..
Definition Commission .....................................................
Definition Curie .................................................................
Definition Diversion ..........................................................
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Definition Fingerprint Orders ............................................
Definition Government agency .........................................
Definition Isolation ............................................................
Definition License .............................................................
Definition License issuing agency ....................................
Definition Local law enforcement agency ........................
Definition Lost or missing material ...................................
Definition Mobile device ...................................................
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Definition No-later-than arrival time .................................
Definition Person ..............................................................
Definition Reviewing official .............................................
Definition Sabotage ..........................................................
Definition Safe haven .......................................................
Definition Security zone ...................................................
Definition State .................................................................
Definition Telemetric position monitoring system ............
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Definition Trustworthiness and reliability .........................
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Definition United States ...................................................
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Personal history disclosure ..............................................
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mstockstill on DSKH9S0YB1PROD with PROPOSALS2
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Records ............................................................................
Initial investigation ............................................................
Grandfathering .................................................................
Reinvestigations ...............................................................
General performance objective and requirements ..........
Prohibitions .......................................................................
Procedures for processing fingerprint checks .................
Relief from fingerprinting, identification, and criminal history records checks and other elements of a background investigations for designated categories of individuals permitted unescorted access to certain radioactive materials or other property.
Protection of information ..................................................
Protection of information ..................................................
Access authorization program review ..............................
Applicability ......................................................................
General performance objective ........................................
Program features .............................................................
Information submittal and notification ..............................
Security plan ....................................................................
Implementing procedures .................................................
Training ............................................................................
Training ............................................................................
Protection of Information ..................................................
Protection of Information ..................................................
LLEA coordination ............................................................
LLEA notification for temporary job sites .........................
Records ............................................................................
Security Zones .................................................................
Monitoring and detection ..................................................
Assessment ......................................................................
Personnel communications and data transmission .........
Response .........................................................................
Maintenance, testing, and calibration ..............................
Requirements for mobile devices ....................................
Security program review ..................................................
Reporting of events ..........................................................
Reporting of events ..........................................................
Additional requirements for transfer of category 1 and
category 2 quantities of radioactive material.
Additional requirements for transfer of category 1 and
category 2 quantities of radioactive material.
Applicability of physical protection of category 1 and
category 2 quantities of radioactive material during
transit.
Applicability of physical protection of category 1 and
category 2 quantities of radioactive material during
transit.
Preplanning and coordination of shipment of category 1
or category 2 quantities of radioactive material.
Preplanning and coordination of shipment of category 1
or category 2 quantities of radioactive material.
Advance notification for shipments of category 1 quantities of radioactive material.
Procedures for submitting advance notification ...............
Information to be furnished in advance notification of
shipment.
Revision notice .................................................................
Cancellation notice ...........................................................
Records ............................................................................
Protection of information ..................................................
Shipments by road ...........................................................
Shipments by rail .............................................................
Procedures .......................................................................
Investigations ...................................................................
Reporting of events ..........................................................
Reporting of events ..........................................................
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B
C
B
C
B
C
B
B
B
B
B
B
C
C
B
B
C
C
B
C
B
C
C
NRC
B
B
C
B
B
B
B
B
C
B
C
C
C
B
C
D
B
B
C
B
B
B
B
B
C
NRC
B
B
B
B
B
B
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Federal Register / Vol. 75, No. 114 / Tuesday, June 15, 2010 / Proposed Rules
DRAFT COMPATIBILITY TABLE FOR PROPOSED RULE—Continued
Compatibility
Section
Change
Subject
Existing
37.81(c) ................................
37.81(d) ...............................
37.81(e) ...............................
37.81(f) ................................
37.81(g) ...............................
37.81(h) ...............................
37.101 ..................................
37.103 ..................................
37.105 ..................................
37.107 ..................................
37.109 ..................................
Appendix A ..........................
New
New
New
New
New
New
New
New
New
New
New
New
.....................................
.....................................
.....................................
.....................................
.....................................
.....................................
.....................................
.....................................
.....................................
.....................................
.....................................
.....................................
Reporting of events ..........................................................
Reporting of events ..........................................................
Reporting of events ..........................................................
Reporting of events ..........................................................
Reporting of events ..........................................................
Reporting of events ..........................................................
Form of records ................................................................
Record retention ...............................................................
Inspections .......................................................................
Violations ..........................................................................
Criminal penalties .............................................................
Category 1 and 2 thresholds ...........................................
New
B
B
B
B
C
C
C
C
D
D
D
B
Part 39
39.1 ......................................
Amend .................................
Purpose and scope ..........................................................
D
D
NRC
NRC
B
B
Part 51
51.22(c)(3) ...........................
Amend .................................
Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical
exclusion or otherwise not requiring environmental review.
Part 71
71.97(b) ...............................
Amend .................................
Advance notification of shipment of irradiated reactor
fuel and nuclear waste.
Part 73
73.35 ....................................
New .....................................
VI. Plain Language
The Presidential Memorandum,
‘‘Plain Language in Government
Writing’’ published June 10, 1998 (63 FR
31883), directed that the Government’s
documents be in clear and accessible
language. The NRC requests comments
on this proposed rule specifically with
respect to the clarity and effectiveness
of the language used. Comments should
be sent to the address listed under the
ADDRESSES heading.
mstockstill on DSKH9S0YB1PROD with PROPOSALS2
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 proposed rule, the
NRC would establish security
requirements for the use of category 1
and category 2 quantities of radioactive
materials. The NRC is not aware of any
voluntary consensus standards that
address the proposed subject matter of
this proposed rule. The NRC will
consider using a voluntary consensus
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Requirements for physical protection of irradiated reactor fuel (100 grams or less) in transit.
standard if an appropriate standard is
identified. If a voluntary consensus
standard is identified for consideration,
the submittal should explain why the
standard should be used.
VIII. Finding of No Significant
Environmental Impact: Availability
Under the National Environmental
Policy Act of 1969, as amended, and the
NRC regulations in subpart A of 10 CFR
part 51, the NRC has determined that
this proposed rule, if adopted, would
not be a major Federal action
significantly affecting the quality of the
human environment, and therefore an
environmental impact statement is not
required for this rulemaking. The NRC
has prepared an environmental
assessment and, on the basis of this
environmental assessment, has made a
finding of no significant impact.
The implementation of the proposed
rule’s security requirements would not
result in significant changes to the
licensee’s facilities, nor would such
implementation result in any significant
increase in effluents released to the
environment. Similarly the
implementation of the proposed rule’s
security requirements would not affect
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NRC
occupational exposure requirements. No
major construction or other earth
disturbing activities, on the part of the
affected licensees, is anticipated in
connection with licensee’s
implementation of the proposed rule’s
requirements. The Commission has
determined that the implementation of
this proposed rule would be procedural
and administrative in nature.
The determination of this
environmental assessment is that there
will be no significant impact to the
public from this action. However, the
general public should note that the NRC
welcomes public participation.
Comments on any aspect of the
Environmental Assessment may be
submitted to the NRC as indicated
under the ADDRESSES heading in this
document.
The NRC has sent a copy of the
Environmental Assessment and this
proposed rule to every State Liaison
Officer and requested their comments
on the Environmental Assessment. The
Environmental Assessment may be
examined at the NRC Public Document,
Room O–1F23, 11555 Rockville Pike,
Rockville, MD 20852. The
Environmental Assessment may also be
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mstockstill on DSKH9S0YB1PROD with PROPOSALS2
viewed and downloaded electronically
via the Federal eRulemaking Portal at
https://www.regulations.gov by searching
for Docket Number ID NRC–2008–0120.
IX. Paperwork Reduction Act
Statement
This proposed rule contains new or
amended information collection
requirements that are subject to the
Paperwork Reduction Act of 1995 (44
U.S.C. 3501 et seq.). This rule has been
submitted to the Office of Management
and Budget (OMB) for review and
approval of the information collection
requirements.
Type of submission, new or revision:
New.
The title of the information collection:
‘‘10 CFR Parts 30, 32, 33, 34, 35, 36, 37,
39, 51, 71, and 73, Physical Protection
of Byproduct Material’’
The form number if applicable: NA.
How often the collection is required:
One time for initial compliance
notifications and fingerprints for the
reviewing officials; and as needed for
implementation notifications, event
notifications, notifications of shipments
of radioactive material, and
fingerprinting of new employees.
Who will be required or asked to
report: Licensees that are authorized to
possess and use category 1 or category
2 quantities of radioactive material.
An estimate of the number of annual
responses: 83,666 (88,066 responses
plus 1,400 record keepers).
The estimated number of annual
respondents: 1,917 (2,950 the first year,
1,400 in subsequent years)
An estimate of the total number of
hours needed annually to complete the
requirement or request: 63,446 (5,125
one-time reporting hours, annualized to
1,708 hours plus 12,387 reporting hours
plus 21,694 recordkeeping hours plus
27,657 third-party hours).
Abstract: The NRC is proposing to
amend its regulations to put in place
security requirements for the use of
category 1 and category 2 quantities of
radioactive material. Licensees would
be required to: (1) Develop procedures
for implementation of the security
provisions; (2) develop a security plan
that describes how security is being
implemented; (3) conduct training on
the procedures and security plan;
(4) conduct background investigations
for those individuals permitted access to
category 1 or category 2 quantities of
radioactive material; (5) coordinate with
LLEAs so the LLEAs would be better
prepared to respond in an emergency;
(6) conduct preplanning and
coordination activities before shipping
radioactive material; and (7) implement
security measures for the protection of
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the radioactive material. Licensees
would be required to promptly report
any attempted or actual theft or
diversion of the radioactive material.
Licensees would be required to keep
copies of the security plan, procedures,
background investigation records,
training records, and documentation
that certain activities have occurred.
The NRC is seeking public comment
on the potential impact of the
information collections contained in
this proposed rule and on the following
issues:
1. Is the proposed information
collection necessary for the proper
performance of the functions of the
NRC, including whether the information
will have practical utility?
2. Is the estimate of burden accurate?
3. Is there a way to enhance the
quality, utility, and clarity of the
information to be collected?
4. How can the burden of the
information collection be minimized,
including the use of automated
collection techniques?
A copy of the OMB clearance package
may be viewed free of charge at the NRC
Public Document Room, One White
Flint North, 11555 Rockville Pike, Room
O–1F21, Rockville, MD 20852. The
OMB clearance package and rule are
available at the NRC worldwide Web
site https://www.nrc.gov/public-involve/
doc-comment/omb/ for 60
days after the signature date of this
notice.
Send comments on any aspect of
these proposed regulations related to
information collections, including
suggestions for reducing the burden and
on the above issues, by July 15, 2010 to
the Records and FOIA/Privacy Services
Branch (T–5F52), U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, or by Internet
electronic mail to
Infocollects.Resource@NRC.gov and to
the Christine Kymm (202–395–4638,
ckymn@omb.eop.gov), Desk Officer,
Office of Information and Regulatory
Affairs, NEOB–10202 (3150–xxxx),
Office of Management and Budget,
Washington, DC 20503. Comments on
the proposed information collections
may also be submitted via the Federal
eRulemaking Portal https://
www.regulations.gov, Docket Number ID
NRC–2008–0120. Comments received
after this date will be considered if it is
practical to do so, but assurance of
consideration cannot be given to
comments received after this date.
Public Protection Notification
The NRC may not conduct or sponsor,
and a person is not required to respond
to, a request for information or an
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33929
information collection requirement
unless the requesting document
displays a currently valid OMB control
number.
X. Regulatory Analysis
The Commission has prepared a draft
regulatory analysis on this proposed
regulation. The analysis examines the
costs and benefits of the alternatives
considered by the Commission.
The Commission requests public
comment on the draft regulatory
analysis. Comments on the draft
analysis may be submitted to the NRC
as indicated under the ADDRESSES
heading. The analysis is available for
inspection in the NRC Public Document
Room, 11555 Rockville Pike, Rockville,
MD 20852. The analysis may also be
viewed and downloaded electronically
via the Federal eRulemaking Portal at
https://www.regulations.gov by searching
for Docket Number NRC–2008–0120.
XI. Regulatory Flexibility Certification
The NRC has prepared an initial
regulatory analysis of the impact of this
proposed rule on small entities. The
proposed rule would affect about 300
NRC licensees and an additional 1,100
Agreement State licensees. Affected
licensees include laboratories, reactors,
universities, colleges, medical clinics,
hospitals, irradiators, well loggers, and
radiographers, some of which may
qualify as small business entities as
defined by 10 CFR 2.810. Based on the
draft regulatory analysis conducted for
this action, the costs of the proposed
rule for affected licensees are estimated
to be between $541 million and $743
million (7-percent and 3-percent
discount rate, respectively) total. The
average licensee would have a one-time
cost of approximately $27,000 and an
annual cost of approximately $25,700 to
fully implement the proposed rule. An
additional 1,550 licensees would
experience a one-time cost of about
$3,500 to develop a security program
but would not need to implement the
program. The NRC believes that the
selected alternative reflected in the
proposed rule is the least burdensome,
most flexible alternative that would
accomplish the NRC’s regulatory
objective. The draft Regulatory
Flexibility Analysis is included as
Appendix to this proposed rule.
The NRC is seeking public comment
on the potential impact of the proposed
rule on small entities. The NRC
particularly desires comment from
licensees who qualify as small
businesses, specifically as to how the
proposed regulation will affect them
and how the regulation may be tiered or
otherwise modified to impose less
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Federal Register / Vol. 75, No. 114 / Tuesday, June 15, 2010 / Proposed Rules
stringent requirements on small entities
while still adequately protecting the
public health and safety and common
defense and security. Comments on how
the regulation could be modified to take
into account the differing needs of small
entities should specifically discuss–
(a) The size of the business and how
the proposed regulation would result in
a significant economic burden upon it
as compared to a larger organization in
the same business community;
(b) How the proposed regulation
could be further modified to take into
account the business’s differing needs or
capabilities;
(c) The benefits that would accrue, or
the detriments that would be avoided, if
the proposed regulation was modified as
suggested by the commenter;
(d) How the proposed regulation, as
modified, would more closely equalize
the impact of NRC regulations as
opposed to providing special advantages
to any individuals or groups; and
(e) How the proposed regulation, as
modified, would still adequately protect
the public health and safety and
common defense and security.
Comments should be submitted as
indicated under the ADDRESSES heading.
XII. Backfit Analysis
The NRC has determined that the
backfit rule, which is found in the
regulations at §§ 50.109, 70.76, 72.62,
76.76, and in 10 CFR part 52, does not
apply to this proposed rule because this
amendment would not involve any
provisions that would impose backfits
as defined in 10 CFR chapter I.
Therefore, a backfit analysis is not
required.
List of Subjects
recordkeeping requirements, Scientific
equipment, Security measures.
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 36
Byproduct material, Criminal
penalties, Nuclear materials, Reporting
and recordkeeping requirements,
Scientific equipment, Security
measures.
10 CFR Part 37
Byproduct material, Criminal
penalties, Export, Hazardous materials
transportation, Import, Licensed
material, Nuclear materials, Reporting
and recordkeeping requirements,
Security measures.
10 CFR Part 39
Byproduct material, Criminal
penalties, Nuclear material, Oil and gas
exploration—well logging, Reporting
and recordkeeping requirements,
Scientific equipment, Security
measures, Source material, Special
nuclear material.
10 CFR Part 51
Administrative practice and
procedure, Environmental impact
statement, Nuclear materials, Nuclear
power plants and reactors, Reporting
and recordkeeping requirements.
10 CFR Part 71
10 CFR Part 32
Byproduct material, Criminal
penalties, Labeling, Nuclear materials,
Radiation protection, Reporting and
recordkeeping requirements.
mstockstill on DSKH9S0YB1PROD with PROPOSALS2
10 CFR Part 30
Byproduct material, Criminal
penalties, Government contracts,
Intergovernmental relations, Isotopes,
Nuclear materials, Radiation protection,
Reporting and recordkeeping
requirements.
10 CFR Part 73
10 CFR Part 33
Byproduct material, Criminal
penalties, Nuclear materials, Radiation
protection, Reporting and recordkeeping
requirements.
10 CFR Part 34
Criminal penalties, Packaging and
containers, Radiation protection,
Radiography, Reporting and
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Criminal penalties, Hazardous
materials transportation, Import,
Nuclear materials, Packaging and
containers, Reporting and
recordkeeping requirements.
Criminal penalties, Export, Hazardous
materials transportation, Import,
Nuclear materials, Nuclear power plants
and reactors, Reporting and
recordkeeping requirements, Security
measures.
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. 553; the NRC
is proposing to adopt the following
amendments to 10 CFR parts 30, 32, 33,
34, 35, 36, 37, 39, 51, 71, 73, and 150.
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PART 30—RULES OF GENERAL
APPLICABILITY TO DOMESTIC
LICENSING OF BYPRODUCT
MATERIAL
1. The authority citation for part 30
continues to read as follows:
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); Energy Policy Act of
2005, Pub. L. No. 109–58, 119 Stat. 549
(2005).
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).
2. In § 30.6, the introductory text of
paragraph (a) is revised to read as
follows:
§ 30.6
Communications.
(a) Unless otherwise specified or
covered under the regional licensing
program as provided in paragraph (b) of
this section, any communication or
report concerning the regulations in
parts 30 through 37 and 39 of this
chapter and any application filed under
these regulations may be submitted to
the Commission as follows:
*
*
*
*
*
3. Section 30.13 is revised to read as
follows:
§ 30.13
Carriers.
Common and contract carriers, freight
forwarders, warehousemen, and the U.S.
Postal Service are exempt from the
regulations in this part and parts 31
through 37 and 39 of this chapter and
the requirements for a license set forth
in section 81 of the Act to the extent that
they transport or store byproduct
material in the regular course of carriage
for another or storage incident thereto.
4. In § 30.32 a new paragraph (l) is
added to read as follows:
§ 30.32
Application for specific licenses.
*
*
*
*
*
(l) An application for a specific
license to use, store, or transport
category 1 or category 2 quantities of
radioactive material must include
information concerning whether the
applicant’s proposed security program
meets the requirements in part 37 of this
chapter.
5. In § 30.33, paragraph (a)(4) is
revised to read as follows:
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§ 30.33 General requirements for issuance
of specific licenses.
(a) * * *
(4) The applicant satisfies any special
requirements contained in parts 32
through 37 and 39; and
*
*
*
*
*
PART 32—SPECIFIC DOMESTIC
LICENSES TO MANUFACTURE OR
TRANSFER CERTAIN ITEMS
CONTAINING BYPRODUCT MATERIAL
6. The authority citation for part 32
continues to read as follows:
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. No. 109–58, 119 Stat. 806–810
(42 U.S.C. 2014, 2021, 2021b, 2111).
7. In § 32.1, paragraph (b) is revised to
read as follows:
§ 32.1
Purpose and scope.
*
*
*
*
*
(b) The provisions and requirements
of this part are in addition to, and not
in substitution for, other requirements
of this chapter. In particular, the
provisions of part 30 of this chapter
apply to applications, licenses and
certificates of registration subject to this
part, and the provisions of part 37 of
this chapter apply to applications and
licenses subject to this part.
*
*
*
*
*
8. The authority citation for Part 33
continues to read as follows:
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. No. 109–58, 119 Stat. 806–810
(42 U.S.C. 2014, 2021, 2021b, 2111).
9. Section 33.1 is revised to read as
follows:
mstockstill on DSKH9S0YB1PROD with PROPOSALS2
§ 33.1
Purpose and scope.
This part prescribes requirements for
the issuance of specific licenses of broad
scope for byproduct material (‘‘broad
licenses’’) and certain regulations
governing holders of such licenses. The
provisions and requirements of this part
are in addition to, and not in
substitution for, other requirements of
this chapter. In particular, the
provisions of parts 30 and 37 of this
chapter apply to applications and
licenses subject to this part.
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PART 34—LICENSES FOR
INDUSTRIAL RADIOGRAPHY AND
RADIATION SAFETY REQUIREMENTS
FOR INDUSTRIAL RADIOGRAPHIC
OPERATIONS
PART 36—LICENSES AND RADIATION
SAFETY REQUIREMENTS FOR
IRRADIATORS
10. The authority citation for Part 34
continues to read as follows:
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).
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).
Section 34.45 also issued under sec. 206,
88 Stat. 1246 (42 U.S.C. 5846).
11. Section 34.1 is revised to read as
follows:
§ 34.1
Purpose and scope.
This part prescribes requirements for
the issuance of licenses for the use of
sealed sources containing byproduct
material and radiation safety
requirements for persons using these
sealed sources in industrial
radiography. The provisions and
requirements of this part are in addition
to, and not in substitution for, other
requirements of this chapter. In
particular, the requirements and
provisions of parts 19, 20, 21, 30, 37, 71,
150, 170, and 171 of this chapter apply
to applications and licenses subject to
this part. This rule does not apply to
medical uses of byproduct material.
PART 35—MEDICAL USE OF
BYPRODUCT MATERIAL
12. The authority citation for Part 35
continues to read as follows:
PART 33—SPECIFIC DOMESTIC
LICENSES OF BROAD SCOPE FOR
BYPRODUCT MATERIAL
33931
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. No. 109–58, 119 Stat. 806–810
(42 U.S.C. 2014, 2021, 2021b, 2111).
13. Section 35.1 is revised to read as
follows:
§ 35.1
Purpose and scope.
This part contains the requirements
and provisions for the medical use of
byproduct material and for issuance of
specific licenses authorizing the
medical use of this material. These
requirements and provisions provide for
the radiation safety of workers, the
general public, patients, and human
research subjects. The requirements and
provisions of this part are in addition to,
and not in substitution for, others in this
chapter. The requirements and
provisions of parts 19, 20, 21, 30, 37, 71,
170, and 171 of this chapter apply to
applicants and licensees subject to this
part unless specifically exempted.
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14. The authority citation for Part 36
continues to read as follows:
15. In § 36.1, paragraph (a) is revised
to read as follows:
§ 36.1
Purpose and scope.
(a) This part contains requirements for
the issuance of a license authorizing the
use of sealed sources containing
radioactive materials in irradiators used
to irradiate objects or materials using
gamma radiation. This part also
contains radiation safety requirements
for operating irradiators. The
requirements of this part are in addition
to other requirements of this chapter. In
particular, the provisions of parts 19, 20,
21, 30, 37, 71, 170, and 171 of this
chapter apply to applications and
licenses subject to this part. Nothing in
this part relieves the licensee from
complying with other applicable
Federal, State and local regulations
governing the siting, zoning, land use,
and building code requirements for
industrial facilities.
*
*
*
*
*
16. Part 37 is added to read as follows:
PART 37—PHYSICAL PROTECTION OF
CATEGORY 1 AND CATEGORY 2
QUANTITIES OF RADIOACTIVE
MATERIAL
Subpart A—General Provisions
Sec.
37.1 Purpose.
37.3 Scope.
37.5 Definitions.
37.7 Communications.
37.9 Interpretations.
37.11 Specific exemptions.
37.13 Information collection requirements:
OMB approval.
Subpart B—Background Investigations and
Access Control Program
37.21 Personnel access authorization
requirements for category 1 or category 2
quantities of radioactive material.
37.23 Access authorization program
requirements.
37.25 Background investigations.
37.27 Requirements for criminal history
records checks of individuals granted
unescorted access to category 1 or
category 2 quantities of radioactive
material.
37.29 Relief from fingerprinting,
identification, and criminal history
records checks and other elements of
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background investigations for designated
categories of individuals permitted
unescorted access to certain radioactive
materials or other property.
37.31 Protection of information.
37.33 Access authorization program review.
Subpart C—Physical Protection
Requirements During Use
37.41 Security program.
37.43 General security program
requirements.
37.45 LLEA coordination and notification.
37.47 Security zones.
37.49 Monitoring, detection, and
assessment.
37.51 Maintenance, testing, and calibration.
37.53 Requirements for mobile devices.
37.55 Security program review.
37.57 Reporting of events.
Subpart D—Physical Protection in Transit
37.71 Additional requirements for transfer
of category 1 and category 2 quantities of
radioactive material.
37.73 Applicability of physical protection
of category 1 and category 2 quantities of
radioactive material during transit.
37.75 Preplanning and coordination of
shipment of category 1 or category 2
quantities of radioactive material.
37.77 Advance notification of shipment of
category 1 quantities of radioactive
material.
37.79 Requirements for physical protection
of category 1 and category 2 quantities of
radioactive material during shipment.
37.81 Reporting of events.
Subpart E—[Reserved]
Subpart F—Records
37.101 Form of records.
37.103 Record retention.
Subpart G—Enforcement
37.105 Inspections.
37.107 Violations.
37.109 Criminal penalties.
Appendix A to Part 37—Category 1 and
Category 2 Radioactive Materials
Authority: Secs. 53, 81, 161, 182, 183, 68
Stat. 935, 953, 954, as amended (42 U.S.C.
2111, 2201, 2232, 2233); sec. 223 (42 U.S.C.
2273); sec 234, 83 Stat. 445, as amended; sec.
147, 149 (42 U.S.C. 2133, 2134, 2167, 2168,
2169)
Subpart A—General Provisions
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§ 37.1
Purpose.
This part has been established to
provide the requirements for the
physical protection program for any
licensee that is authorized to possess
category 1 or category 2 quantities of
radioactive material listed in Appendix
A to this part. These requirements
provide reasonable assurance of the
security of category 1 or category 2
quantities of radioactive material by
protecting these materials from theft or
diversion. Specific requirements for
access to material, use of material,
transfer of material, and transport of
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material are included. No provision of
this part authorizes possession of
licensed material.
§ 37.3
Scope.
(a) Subpart B to this part applies to
any person who, under the regulations
in this chapter, is authorized to possess
or use at any site or contiguous sites
subject to the control by the licensee,
category 1 or category 2 quantities of
radioactive material.
(b) Subpart C to this part applies to
any person who, under the regulations
in this chapter, is authorized to possess
or use at any site or contiguous sites
subject to the control by the licensee,
category 1 or category 2 quantities of
radioactive material.
(c) Subpart D applies to any person
who, under the regulations of this
chapter, imports, exports, transports, or
delivers to a carrier for transport in a
single shipment, category 1 or category
2 quantities of radioactive material.
§ 37.5
Definitions.
As used in this part:
Access control means a system for
allowing only approved individuals to
have unescorted access to the security
zone and for ensuring that all other
individuals are subject to escorted
access.
Act means the Atomic Energy Act of
1954 (68 Stat. 919), including any
amendments thereto.
Aggregated means accessible by the
breach of a common physical barrier,
whether the material made accessible is
a single sealed source, multiple sealed
sources, or multiple sources of bulk
radioactive material.
Agreement State means any state with
which the Atomic Energy Commission
or the Nuclear Regulatory Commission
has entered into an effective agreement
under subsection 274b. of the Act. Nonagreement State means any other State.
Approved individual means an
individual whom the licensee has
determined to be trustworthy and
reliable in accordance with subpart B of
this part and who has completed the
training required by § 37.43(c).
Background investigation means the
investigation conducted by a licensee or
applicant to support the determination
of trustworthiness and reliability.
Becquerel (Bq) means one
disintegration per second.
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
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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 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.
Category 1 quantity of radioactive
material means a quantity of radioactive
material meeting or exceeding the
category 1 threshold in Table 1 of
Appendix A to this part. The quantity
is calculated by adding the sum of ratios
of the total activity of each radionuclide
to the category 1 threshold for that
radionuclide. If the ratio is equal to or
exceeds 1, the quantity would be
considered a category 1 quantity.
Category 1 quantities of radioactive
material do not include the
radionuclides contained in irradiated or
mixed oxide fuel.
Category 2 quantity of radioactive
material means a quantity of radioactive
material meeting or exceeding the
category 2 threshold but less than the
category 1 threshold in Table 1 of
Appendix A to this part. The quantity
is calculated by adding the sum of ratios
of the total activity of each radionuclide
to the category 2 threshold for that
radionuclide. If the ratio is equal to or
exceeds 1, the quantity would be
considered a category 2 quantity.
Category 2 quantities of radioactive
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material do not include the
radionuclides contained in irradiated or
mixed oxide fuel.
Commission means the Nuclear
Regulatory Commission or its duly
authorized representatives.
Curie means that amount of
radioactive material which disintegrates
at the rate of 37 billion atoms per
second.
Diversion means the unauthorized
movement of radioactive material
subject to this part to a location different
from the material’s authorized
destination inside or outside of the site
at which the material is used or stored.
Escorted access means
accompaniment while in a security zone
by an approved individual who
maintains line-of-sight surveillance at
all times over an individual who is not
approved for unescorted access.
Fingerprint orders means the orders
issued by the U.S. Nuclear Regulatory
Commission or the legally binding
requirements issued by Agreement
States that require fingerprints and
criminal history records checks for
individuals with unescorted access to
category 1 and category 2 quantities of
radioactive material or Safeguards
Information.
Government agency means any
executive department, commission,
independent establishment, corporation,
wholly or partly owned by the United
States of America which is an
instrumentality of the United States, or
any board, bureau, division, service,
office, officer, authority, administration,
or other establishment in the executive
branch of the Government.
Isolation means protection of category
1 or category 2 quantities of radioactive
material by allowing access to security
zones only through established access
control points.
License, except where otherwise
specified, means a license for byproduct
material issued pursuant to the
regulations in parts 30 through 36 and
39 of this chapter;
License issuing authority means the
licensing agency that issued the license,
i.e. the U.S. Nuclear Regulatory
Commission or the appropriate agency
of an Agreement State;
Local law enforcement agency (LLEA)
means a government entity that has
authority to make arrests and the
capability to provide an armed response
in locations where licensed category 1
or category 2 quantities of radioactive
material are used, stored, or transported.
Lost or missing licensed material
means licensed material whose location
is unknown. It includes material that
has been shipped but has not reached its
destination and whose location cannot
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be readily traced in the transportation
system.
Mobile device means a piece of
equipment containing licensed
radioactive material that is either
mounted on wheels or casters, or
otherwise equipped for moving without
a need for disassembly or dismounting;
or designed to be hand carried. Mobile
devices do not include stationary
equipment installed in a fixed location.
Movement control center means an
operations center that is remote from
transport activity and that maintains
position information on the movement
of radioactive material, receives reports
of attempted attacks or thefts, provides
a means for reporting these and other
problems to appropriate agencies and
can request and coordinate appropriate
aid.
No-later-than arrival time means the
date and time that the shipping licensee
and receiving licensee have established
as the time at which an investigation
will be initiated if the shipment has not
arrived at the receiving facility. The nolater-than-arrival time may not be more
than 2 hours after the estimated arrival
time for shipments of category 1
quantities of radioactive material. The
no-later-than-arrival time may not be
more than 4 hours after the estimated
arrival time for shipments of category 2
quantities of radioactive material.
Person means—
(1) Any individual, corporation,
partnership, firm, association, trust,
estate, public or private institution,
group, Government agency other than
the Commission or the Department of
Energy (except that the Department
shall be considered a person within the
meaning of the regulations in 10 CFR
chapter I to the extent that its facilities
and activities are subject to the licensing
and related regulatory authority of the
Commission under section 202 of the
Energy Reorganization Act of 1974 (88
Stat. 1244), the Uranium Mill Tailings
Radiation Control Act of 1978 (92 Stat.
3021), the Nuclear Waste Policy Act of
1982 (96 Stat. 2201), and section 3(b)(2)
of the Low-Level Radioactive Waste
Policy Amendments Act of 1985 (99
Stat. 1842)), any State or any political
subdivision of or any political entity
within a State, any foreign government
or nation or any political subdivision of
any such government or nation, or other
entity; and
(2) Any legal successor,
representative, agent, or agency of the
foregoing.
Reviewing official means the
individual who shall make the
trustworthiness and reliability
determination of an individual to
determine whether the individual may
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33933
have, or continue to have, unescorted
access to the category 1 or category 2
quantities of radioactive materials that
are possessed by the licensee.
Sabotage means deliberate damage,
with malevolent intent, to a category 1
or category 2 quantity of radioactive
material, a device that contains a
category 1 or category 2 quantity of
radioactive material, or the components
of the security system.
Safe haven means a readily
recognizable and readily accessible site
at which security is present or from
which, in the event of an emergency, the
transport crew can notify and wait for
the local law enforcement authorities.
Security zone means any temporary or
permanent area determined and
established by the licensee for the
physical protection of category 1 or
category 2 quantities of radioactive
material.
State means a State of the United
States, the District of Columbia, the
Commonwealth of Puerto Rico, the
Virgin Islands, Guam, American Samoa,
and the Commonwealth of the Northern
Mariana Islands.
Telemetric position monitoring
system means a data transfer system that
captures information by instrumentation
and/or measuring devices about the
location and status of a transport vehicle
or package between the departure and
destination locations.
Temporary job site means, for the
purposes of this part, a location where
category 1 or category 2 quantities of
radioactive material may be used or
stored other than a location of use that
is specifically identified on the license.
Trustworthiness and reliability are
characteristics of an individual
considered dependable in judgment,
character, and performance, such that
unescorted access to category 1 or
category 2 quantities of radioactive
material by that individual does not
constitute an unreasonable risk to the
public health and safety or common
defense and security. A determination
of trustworthiness and reliability for this
purpose is based upon the results from
a background investigation.
Unescorted access means solitary
access to category 1 or category 2
quantities of radioactive material
granted to an approved individual.
Unescorted access includes solitary
access to sufficient quantities of
radioactive material such that an
individual could successfully
accumulate lesser quantities of material
into a category 1 or category 2 quantity.
United States, when used in a
geographical sense, includes Puerto
Rico and all territories and possessions
of the United States.
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Communications.
Except where otherwise specified or
covered under the regional licensing
program as provided in § 30.6(b), all
communications and reports concerning
the regulations in this part may be sent
as follows:
(a) By mail addressed to: Attn:
Document Control Desk; Director, Office
of Nuclear Reactor Regulation; Director,
Office of New Reactors; Director, Office
of Nuclear Material Safety and
Safeguards; Director, Office of Federal
and State Materials and Environmental
Management Programs; or Director,
Division of Nuclear Security, Office of
Nuclear Security and Incident
Response, as appropriate, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001;
(b) By hand delivery to the NRC’s
offices at 11555 Rockville Pike,
Rockville, Maryland;
(c) Where practicable, by electronic
submission, for example, Electronic
Information Exchange, or CD–ROM.
Electronic submissions must be made in
a manner that enables the NRC to
receive, read, authenticate, distribute,
and archive the submission, and process
and retrieve it a single page at a time.
Detailed guidance on making electronic
submissions can be obtained by visiting
the NRC’s Web site at https://
www.nrc.gov/site-help/esubmittals.html, by e-mail to
MSHD.Resource@nrc.gov; or by writing
the Office of Information Services, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001. The
guidance discusses, among other topics,
the formats the NRC can accept, the use
of electronic signatures, and the
treatment of nonpublic information.
§ 37.9
Interpretations.
Except as specifically authorized by
the Commission in writing, no
interpretations of the meaning of the
regulations in this part by any officer or
employee of the Commission other than
a written interpretation by the General
Counsel will be recognized as binding
upon the Commission.
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§ 37.11
Specific exemptions.
(a) The Commission may, upon
application of any interested person or
upon its own initiative, grant such
exemptions from the requirements of
the regulations in this part as it
determines are authorized by law and
will not endanger life or property or the
common defense and security, and are
otherwise in the public interest.
(b) Any licensee’s activities are
exempt from the requirements of this
part to the extent that its activities are
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covered under the physical protection
requirements of part 73 of this chapter.
§ 37.13 Information collection
requirements: OMB approval.
(a) The Nuclear Regulatory
Commission has submitted the
information collection requirements
contained in this part to the Office of
Management and Budget (OMB) for
approval as required by the Paperwork
Reduction Act (44 U.S.C. 3501 et seq.).
The NRC may not conduct or sponsor,
and a person is not required to respond
to, a collection of information unless it
displays a currently valid OMB control
number. OMB has approved the
information collection requirements
contained in this part under control
number 3150–xxxx.
(b) The approved information
collection requirements contained in
this part appear in §§ 37.21, 37.23,
37.25, 37.27, 37.29, 37.31, 37.33, 37.41,
37.43, 37.45, 37.49, 37.55, 37.57, 37.71,
37.75, 37.77, 37.79, and 37.81.
Subpart B—Background Investigations
and Access Authorization Program
§ 37.21 Personnel access authorization
requirements for category 1 or category 2
quantities of radioactive material.
(a) General.
(1) Each licensee that is authorized to
possess category 1 or category 2
quantities of radioactive material at a
facility shall comply with the
requirements of this subpart, as
appropriate.
(2) Each licensee shall establish,
implement, and maintain its access
authorization program in accordance
with the requirements of this subpart.
(3) By (30 days after the final rule is
published in the Federal Register), each
licensee that is authorized to possess a
category 1 or category 2 quantity of
radioactive material on (effective date of
this rule) shall submit information
concerning the licensee’s compliance
with the requirements of this subpart to
the appropriate NRC regional office
specified in § 30.6.
(4) Each licensee that would become
newly subject to the requirements of
this subpart upon application for
modification of its license shall
implement the requirements of this
subpart, as appropriate, before taking
possession of category 1 or category 2
quantities of radioactive material.
(b) General performance objective.
The licensee’s access authorization
program must ensure that the
individuals specified in paragraph (c)(1)
of this section are trustworthy and
reliable such that they do not constitute
an unreasonable risk to public health
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and safety or the common defense and
security.
(c) Applicability.
(1) Licensees shall subject the
following individuals to an access
authorization program:
(i) Any individual whose assigned
duties require unescorted access to
category 1 or category 2 quantities of
radioactive material;
(ii) Vehicle drivers and accompanying
individuals for road shipments of
category 1 quantities of radioactive
material;
(iii) Movement control center
personnel for shipments of category 1
quantities of radioactive material;
(iv) Any individual whose assigned
duties provide access to shipment
information that is considered to be
Safeguards Information-Modified
Handling related to category 1 quantities
of radioactive material; and
(v) Reviewing officials.
(2) Licensees need not subject the
categories of individuals listed in
§ 37.29(a) through (m) to the
investigation elements of the access
authorization program.
(3) Licensees shall approve for
unescorted access to category 1 or
category 2 quantities of radioactive
material only those individuals with job
duties that require unescorted access to
category 1 or category 2 quantities of
radioactive material.
§ 37.23 Access authorization program
requirements.
(a) Granting unescorted access
authorization.
(1) Licensees shall implement the
requirements of this subpart for granting
initial or reinstated unescorted access
authorization.
(2) Individuals who have been
determined to be trustworthy and
reliable shall also complete the security
training required by § 37.43(c) before
being allowed unescorted access to
category 1 or category 2 quantities of
radioactive material.
(b) Reviewing officials.
(1) Each licensee shall nominate one
or more individuals to be reviewing
officials and shall submit the names of
these individuals and their fingerprints
to the NRC for a criminal history records
check. The nominated individuals shall
undergo the background investigation
aspects that are required by § 37.25(a)(2)
through (a)(9) before their names and
fingerprints are submitted to the NRC.
The fingerprints of the nominated
reviewing official must be taken by a
law enforcement agency, Federal or
State agencies that provide finger
printing services to the public, or
commercial fingerprinting services
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authorized by a State to take
fingerprints.
(2) Reviewing officials must be
required to have unescorted access to
category 1 or category 2 quantities of
radioactive materials or access to
safeguards information, if the licensee
possesses safeguards information, as
part of their job duties.
(3) Reviewing officials cannot approve
other individuals to act as reviewing
officials.
(4) Reviewing officials nominated by
the licensee and approved by the NRC
are the only individuals who may make
trustworthiness and reliability
determinations and permit unescorted
access to category 1 or category 2
quantities of radioactive materials
possessed by the licensee.
(5) Reviewing officials may not make
any trustworthiness and reliability
determinations or permit any individual
to have unescorted access until they
have been approved as a reviewing
official by the NRC.
(6) Individuals nominated as
reviewing officials who receive a
preliminary denial from the NRC have
the right to complete, correct, and
explain information obtained through
the background investigation prior to a
final adverse determination.
(c) Informed consent.
(1) Licensees may not initiate a
background investigation without the
informed and signed consent of the
subject individual. This consent must
include authorization to share personal
information with other individuals or
organizations as necessary to complete
the background investigation. Before a
final adverse determination, the licensee
shall provide the individual with an
opportunity to correct any inaccurate or
incomplete information that is
developed during the background
investigation. Licensees do not need to
obtain signed consent from those
individuals that have undergone a
background investigation under the
Fingerprint Orders. A signed consent
must be obtained prior to any
reinvestigation.
(2) The subject individual may
withdraw his or her consent at any time.
Licensees shall inform the individual
that:
(i) If an individual withdraws his or
her consent, the licensee may not
initiate any elements of the background
investigation that were not in progress
at the time the individual withdrew his
or her consent; and
(ii) The withdrawal of consent for the
background investigation is sufficient
cause for denial or termination of
unescorted access authorization.
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(d) Personal history disclosure. Any
individual who is applying for
unescorted access authorization shall
disclose the personal history
information that is required by the
licensee’s access authorization program
for the reviewing official to make a
determination of the individual’s
trustworthiness and reliability. Refusal
to provide, or the falsification of, any
personal history information required
by this subpart is sufficient cause for
denial or termination of unescorted
access.
(e) Determination basis.
(1) The reviewing official shall
determine whether to grant, deny,
unfavorably terminate, maintain, or
administratively withdraw an
individual’s unescorted access
authorization based on an evaluation of
all of the information required by this
subpart. The reviewing official may
terminate or administratively withdraw
an individual’s unescorted access
authorization based on information
obtained after the background
investigation has been completed and
the individual granted unescorted
access authorization.
(2) The reviewing official may not
permit any individual to have
unescorted access until the reviewing
official has evaluated all of the
information required by this subpart
and determined that the individual is
trustworthy and reliable. The reviewing
official may deny unescorted access to
any individual based on disqualifying
information obtained at any time during
the background investigation.
(3) The licensee shall document the
basis for concluding whether or not
there is reasonable assurance that an
individual granted unescorted access to
category 1 or category 2 quantities of
radioactive material is trustworthy and
reliable. Licensees shall maintain a list
of persons currently approved for
unescorted access authorization and a
list of those individuals that have been
denied unescorted access authorization.
When a licensee determines that a
person no longer requires unescorted
access, the licensee shall immediately
remove the person from the approved
list and take measures to ensure that the
individual is unable to obtain
unescorted access.
(f) Procedures.
(1) Licensees shall develop,
implement, and maintain written
procedures for conducting background
investigations for persons who are
applying for unescorted access
authorization to category 1 or category
2 quantities of radioactive material.
(2) Licensees shall develop,
implement, and maintain written
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33935
procedures for updating background
investigations for persons who are
applying for reinstatement of unescorted
access authorization.
(3) Licensees shall develop,
implement, and maintain written
procedures to ensure that persons who
have been denied unescorted access
authorization are not allowed
unescorted access to category 1 or
category 2 quantities of radioactive
material.
(4) Licensees shall develop,
implement, and maintain written
procedures for the notification of
individuals who are denied unescorted
access. The procedures must include
provisions for the review, at the request
of the affected individual, of a denial or
termination of unescorted access
authorization. The procedure must
contain a provision to ensure that the
individual is informed of the grounds
for the denial or termination of
unescorted access authorization and
allow the individual an opportunity to
provide additional relevant information.
(g) Right to correct and complete
information.
(1) Prior to any final adverse
determination, licensees shall provide
each individual subject to this subpart
with the right to complete, correct, and
explain information obtained as a result
of the licensee’s background
investigation. Confirmation of receipt by
the individual of this notification must
be maintained by the licensee for a
period of 1 year from the date of the
notification.
(2) If after reviewing their criminal
history record an individual believes
that it is incorrect or incomplete in any
respect and wishes to change, correct,
update, or explain anything in the
record, the individual may initiate
challenge procedures. These procedures
include direct application by the
individual challenging the record to the
law enforcement agency that
contributed the questioned information
or a direct challenge as to the accuracy
or completeness of any entry on the
criminal history record to the Federal
Bureau of Investigation, Criminal Justice
Information Services (CJIS) Division,
Attn: SCU, Mod. D–2, 1000 Custer
Hollow Road, Clarksburg, WV 26306 as
set forth in 28 CFR 16.30 through 16.34.
In the latter case, the Federal Bureau of
Investigation (FBI) will forward the
challenge to the agency that submitted
the data, and will request that the
agency verify or correct the challenged
entry. Upon receipt of an official
communication directly from the agency
that contributed the original
information, the FBI Identification
Division makes any changes necessary
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in accordance with the information
supplied by that agency. Licensees must
provide at least 10 days for an
individual to initiate action to challenge
the results of an FBI criminal history
records check after the record being
made available for his or her review.
The licensee may make a final adverse
determination based upon the criminal
history records only after receipt of the
FBI’s confirmation or correction of the
record.
(h) Records.
(1) The licensee shall retain
documentation regarding the
trustworthiness and reliability of
individual employees for 5 years from
the date the individual no longer
requires unescorted access to category 1
or category 2 quantities of radioactive
material.
(2) The licensee shall retain a copy of
the current access authorization
program procedures as a record for 5
years after the procedure is no longer
needed or until the Commission
terminates the license, if the license is
terminated before the end of the
retention period. If any portion of the
procedure is superseded, the licensee
shall retain the superseded material for
5 years after the record is superseded.
(3) The licensee shall retain the list of
persons approved for unescorted access
authorization and the list of those
individuals that have been denied
unescorted access authorization for 5
years after the list is superseded or
replaced.
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§ 37.25
Background investigations.
(a) Initial Investigation. Before
granting an individual unescorted
access to category 1 or category 2
quantities of radioactive material,
licensees shall complete a background
investigation of the individual seeking
unescorted access authorization. The
scope of the investigation must
encompass at least the 10 years
preceding the date of the background
investigation or since the individual’s
eighteenth birthday, whichever is
shorter. The background investigation
must include at a minimum:
(1) Fingerprinting and an FBI
identification and criminal history
records check in accordance with
§ 37.27 or part 73 of this chapter;
(2) Verification of true identity.
Licensees shall verify the true identity
of the individual who is applying for
unescorted access authorization to
ensure that the applicant is who he or
she claims to be. A licensee shall review
official identification documents (e.g.,
driver’s license; passport; government
identification; certificate of birth issued
by the state, province, or country of
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birth) and compare the documents to
personal information data provided by
the individual to identify any
discrepancy in the information.
Licensees shall document the type,
expiration, and identification number of
the identification document, or
maintain a photocopy of identifying
documents on file in accordance with
§ 37.31. Licensees shall certify in
writing that the identification was
properly reviewed, and shall maintain
the certification and all related
documents for review upon inspection;
(3) Employment history evaluation.
Licensees shall complete an
employment history evaluation.
Licensees shall verify the individual’s
employment with each previous
employer for the most recent 10 years
before the date of application;
(4) Verification of education.
Licensees shall verify that the
individual participated in the education
process during the claimed period;
(5) Military history verification.
Licensees shall verify that the
individual was in the military during
the claimed period;
(6) Credit history evaluation.
Licensees shall evaluate the full credit
history of the individual who is
applying for unescorted access
authorization. A full credit history
evaluation must include, but is not
limited to, a review and evaluation of all
of the information that is provided by a
national credit-reporting agency about
the individual’s credit history. For
individuals including foreign nationals
and United States citizens who have
resided outside the United States and do
not have established credit history that
covers at least the most recent 7 years
in the United States, the licensee must
document all attempts to obtain
information regarding the individual’s
credit history and financial
responsibility from some relevant entity
located in that other country or
countries;
(7) Criminal history review.
Reviewing officials shall obtain from
local criminal justice resources the
criminal history records of the
individual who is applying for
unescorted access authorization and
evaluate the information to determine
whether the individual has a record of
local criminal activity that may
adversely impact his or her
trustworthiness and reliability. The
scope of the applicant’s local criminal
history review must cover all residences
of record for the 10-year period
preceding the date of the application for
unescorted access authorization;
(8) Character and reputation
determination. Licensees shall complete
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reference checks to determine the
character and reputation of the
individual who has applied for
unescorted access authorization.
Reference checks may not be conducted
with any person who is known to be a
close member of the individual’s family,
including but not limited to the
individual’s spouse, parents, siblings, or
children, or any individual who resides
in the individual’s permanent
household. Reference checks under this
subpart must be limited to whether the
individual has been and continues to be
trustworthy and reliable;
(9) The licensee shall also, to the
extent possible, obtain independent
information to corroborate that provided
by the individual (e.g., seek references
not supplied by the individual); and
(10) If a previous employer,
educational institution, or any other
entity with which the individual claims
to have been engaged fails to provide
information or indicates an inability or
unwillingness to provide information
within a time frame deemed appropriate
by the licensee but at least after 10
business days of the request, the
licensee shall:
(i) Document the refusal,
unwillingness, or inability in the record
of investigation; and
(ii) Obtain a confirmation of
employment, educational enrollment
and attendance, or other form of
engagement claimed by the individual
from at least one alternate source that
has not been previously used.
(b) Grandfathering. Individuals who
have been determined trustworthy and
reliable for unescorted access to
category 1 or category 2 quantities of
radioactive material under the
Fingerprint Orders do not need to meet
the background investigation elements
in this subpart until the 10-year reinvestigation.
(c) Reinvestigations. Licensees shall
conduct a criminal history update and
credit history reevaluation every 10
years for any individual with
unescorted access to category 1 or
category 2 quantities of radioactive
material. The reinvestigations must be
completed within 10 years of the date
on which these elements were last
completed and must address the 10
years following the previous
investigation.
§ 37.27 Requirements for criminal history
records checks of individuals granted
unescorted access to category 1 or
category 2 quantities of radioactive
material.
(a) General performance objective and
requirements.
(1) Except for those individuals listed
in § 37.29, each licensee subject to the
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provisions of this subpart shall
fingerprint each individual who is to be
permitted unescorted access to category
1 or category 2 quantities of radioactive
material. Licensees shall transmit all
collected fingerprints to the
Commission for transmission to the FBI.
The licensee shall use the information
received from the FBI as part of the
required background investigation to
determine whether to grant or deny
further unescorted access to category 1
or category 2 quantities of radioactive
materials for that individual.
(2) The licensee shall notify each
affected individual that his or her
fingerprints will be used to secure a
review of their criminal history record,
and shall inform him or her of the
procedures for revising the record or
adding explanations to the record.
(3) Fingerprinting is not required if a
licensee is reinstating an individual’s
unescorted access authorization to
category 1 or category 2 quantities of
radioactive materials if:
(i) The individual returns to the same
facility that granted unescorted access
authorization within 365 days of the
termination of his or her unescorted
access authorization; and
(ii) The previous access was
terminated under favorable conditions.
(4) Fingerprints do not need to be
taken if an individual who is an
employee of a licensee, contractor,
manufacturer, or supplier has been
granted unescorted access to category 1
or category 2 quantities of radioactive
material or access to safeguards
information by another licensee, based
upon a background investigation
conducted under this subpart, the
Fingerprint Orders, or part 73 of this
chapter. An existing criminal history
records check file may be transferred to
the licensee asked to grant unescorted
access in accordance with the
provisions of § 37.31(c).
(5) Licensees shall review the
criminal history records as part of the
trustworthiness and reliability
evaluation for each individual seeking
unescorted access authorization to
category 1 or category 2 quantities of
radioactive material.
(6) Licensees shall use the
information obtained as part of a
criminal history records check solely for
the purpose of determining an
individual’s suitability for unescorted
access authorization to category 1 or
category 2 quantities of radioactive
materials or access to Safeguards
Information.
(b) Prohibitions.
(1) Licensees may not base a final
determination to deny an individual
unescorted access authorization to
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category 1 or category 2 quantities of
radioactive material solely on the basis
of information received from the FBI
involving:
(i) An arrest more than 1 year old for
which there is no information of the
disposition of the case; or
(ii) An arrest that resulted in
dismissal of the charge or an acquittal.
(2) Licensees may not use information
received from a criminal history records
check obtained under this subpart in a
manner that would infringe upon the
rights of any individual under the First
Amendment to the Constitution of the
United States, nor shall licensees use
the information in any way that would
discriminate among individuals on the
basis of race, religion, national origin,
gender, or age.
(c) Procedures for processing of
fingerprint checks.
(1) For the purpose of complying with
this subpart, licensees shall use an
appropriate method listed in § 37.7 to
submit to the Office of Administration,
Division of Facilities and Security, Mail
Stop TWB–05 B32M, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0012, one completed, legible
standard fingerprint card (Form FD–258,
ORIMDNRCOOOZ), electronic
fingerprint scan or, where practicable,
other fingerprint record for each
individual requiring unescorted access
to category 1 or category 2 quantities of
radioactive material. Copies of these
forms may be obtained by writing the
Office of Information Services, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, by calling
(301) 415–7232, or by e-mail to
FORMS.Resource@nrc.gov. Guidance on
submitting electronic fingerprints can be
found at https://www.nrc.gov/site-help/esubmittals.html.
(2) Fees for the processing of
fingerprint checks are due upon
application. Licensees shall submit
payment with the application for the
processing of fingerprints through
corporate check, certified check,
cashier’s check, money order, or
electronic payment, made payable to
‘‘U.S. NRC.’’ (For guidance on making
electronic payments, contact the
Security Branch, Division of Facilities
and Security at (301) 492–3531).
Combined payment for multiple
applications is acceptable. The
Commission publishes the amount of
the fingerprint check application fee on
the NRC public Web site. (To find the
current fee amount, go to the Electronic
Submittals page at https://www.nrc.gov/
site-help/e-submittals.html and select
the link for the Criminal History
Program.)
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33937
(3) The Commission will forward to
the submitting licensee all data received
from the FBI as a result of the licensee’s
application(s) for criminal history
records checks.
§ 37.29 Relief from fingerprinting,
identification, and criminal history records
checks and other elements of background
investigations for designated categories of
individuals permitted unescorted access to
certain radioactive materials or other
property.
Fingerprinting, and the identification
and criminal history records checks
required by section 149 of the Atomic
Energy Act of 1954, as amended, and
other elements of the background
investigation are not required for the
following individuals prior to granting
unescorted access to category 1 or
category 2 quantities of radioactive
materials:
(a) An employee of the Commission or
of the Executive Branch of the U.S.
Government who has undergone
fingerprinting for a prior U.S.
Government criminal history records
check;
(b) A Member of Congress;
(c) An employee of a member of
Congress or Congressional committee
who has undergone fingerprinting for a
prior U.S. Government criminal history
records check;
(d) The Governor of a State or his or
her designated State employee
representative;
(e) Federal, State, or local law
enforcement personnel;
(f) State Radiation Control Program
Directors and State Homeland Security
Advisors or their designated State
employee representatives;
(g) Agreement State employees
conducting security inspections on
behalf of the NRC under an agreement
executed under section 274.i. of the
Atomic Energy Act;
(h) Representatives of the
International Atomic Energy Agency
(IAEA) engaged in activities associated
with the U.S./IAEA Safeguards
Agreement who have been certified by
the NRC;
(i) Emergency response personnel
who are responding to an emergency;
(j) Commercial vehicle drivers for
road shipments of category 2 quantities
of radioactive material;
(k) An individual who has had a
favorably adjudicated U.S. Government
criminal history records check within
the last 5 years, under a comparable
U.S. Government program involving
fingerprinting and an FBI identification
and criminal history records check (e.g.
National Agency Check, Transportation
Worker Identification Credentials
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(TWIC) under 49 CFR 1572, Bureau of
Alcohol Tobacco Firearms and
Explosives background check and
clearances under 27 CFR 555, Health
and Human Services security risk
assessments for possession and use of
select agents and toxins under 42 CFR
73, Hazardous Material security threat
assessment for hazardous material
endorsement to commercial drivers
license under 49 CFR 1572, Customs
and Border Patrol’s Free and Secure
Trade (FAST) Program) provided that he
or she makes available the appropriate
documentation. Written confirmation
from the agency/employer that granted
the Federal security clearance or
reviewed the criminal history records
check must be provided to the licensee.
The licensee shall retain this
documentation for a period of 5 years
from the date the individual no longer
requires unescorted access to category 1
or category 2 quantities of radioactive
material;
(l) Any individual who has an active
Federal security clearance, provided
that he or she makes available the
appropriate documentation. Written
confirmation from the agency/employer
that granted the Federal security
clearance or reviewed the criminal
history records check must be provided
to the licensee. The licensee shall retain
this documentation for a period of 5
years from the date the individual no
longer requires unescorted access to
category 1 or category 2 quantities of
radioactive material; and
(m) Any individual employed by a
service provider licensee for which the
service provider licensee has conducted
the background investigation for the
individual and approved the individual
for unescorted access to category 1 or
category 2 quantities of radioactive
material. Written verification from the
service provider must be provided to the
licensee. The licensee shall retain the
documentation for a period of 5 years
from the date the individual no longer
requires unescorted access to category 1
or category 2 quantities of radioactive
material.
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§ 37.31
Protection of information.
(a) Each licensee who obtains
background information on an
individual under this subpart shall
establish and maintain a system of files
and written procedures for protection of
the record and the personal information
from unauthorized disclosure.
(b) The licensee may not disclose the
record or personal information collected
and maintained to persons other than
the subject individual, his or her
representative, or to those who have a
need to have access to the information
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in performing assigned duties in the
process of granting or denying
unescorted access to category 1 or
category 2 quantities of radioactive
material or Safeguards Information. No
individual authorized to have access to
the information may redisseminate the
information to any other individual who
does not have a need to know.
(c) The personal information obtained
on an individual from a background
investigation may be provided to
another licensee:
(1) Upon the individual’s written
request to the licensee holding the data
to redisseminate the information
contained in his or her file; and
(2) The recipient licensee verifies
information such as name, date of birth,
social security number, gender, and
other applicable physical
characteristics.
(d) The licensee shall make
background investigation records
obtained under this subpart available for
examination by an authorized
representative of the NRC to determine
compliance with the regulations and
laws.
(e) The licensee shall retain all
fingerprint and criminal history records
(including data indicating no record)
received from the FBI, or a copy of these
records if the individual’s file has been
transferred, on an individual for 5 years
from the date the individual no longer
requires unescorted access to category 1
or category 2 quantities of radioactive
material.
§ 37.33 Access authorization program
review.
(a) Each licensee shall be responsible
for the continuing effectiveness of the
access authorization program. Each
licensee shall ensure that access
authorization programs are reviewed to
confirm compliance with the
requirements of this subpart and that
comprehensive actions are taken to
correct any noncompliance that is
identified. The review program shall
evaluate all program performance
objectives and requirements. Each
licensee shall ensure that its entire
access program is reviewed at a
frequency not to exceed 12 months.
(b) The results of the reviews, along
with any recommendations, must be
documented. Each review report must
identify conditions that are adverse to
the proper performance of the access
authorization program, the cause of the
condition(s), and, when appropriate,
recommend corrective actions, and
corrective actions taken. The licensee
shall review the findings and take any
additional corrective actions necessary
to preclude repetition of the condition,
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including reassessment of the deficient
areas where indicated.
(c) Review records must be
maintained for 5 years.
Subpart C—Physical Protection
Requirements During Use
§ 37.41
Security program.
(a) Applicability.
(1) Each licensee that possesses an
aggregated quantity of category 1 or
category 2 radioactive material shall
establish, implement, and maintain a
security program in accordance with the
requirements of this subpart.
(2) A licensee that is authorized to
possess at least a category 2 quantity of
radioactive material but does not
possess an aggregated quantity that
equals or exceeds the category 2
threshold shall develop a security
program in accordance with the
requirements of this subpart. At least 90
days before a licensee aggregates
radioactive material to a quantity that
equals or exceeds the category 2
threshold, the licensee shall implement
its security program. The licensee shall
provide written notification to the NRC
regional office specified in § 30.6 of this
chapter that the licensee is now
implementing its security program as
follows:
(i) If the aggregated quantity of
radioactive material fluctuates above
and below the category 2 threshold
more than once in a 90-day period and
will continue to do so indefinitely, the
licensee need only notify the NRC the
first time the security program is to be
implemented. This notification must
inform the NRC that the licensee
aggregates material at or above the
category 2 threshold from time to time
and that the licensee will implement the
security program whenever the material
is aggregated at or above the category 2
threshold. If the security program is
discontinued for more than 90 days,
then the licensee shall notify the NRC
the next time the security program is to
be implemented.
(ii) If the aggregated quantity of
radioactive material does not fluctuate
above and below the category 2
threshold more than once in a 90-day
period, the licensee shall notify the NRC
each time a previously discontinued or
new security program is to be
implemented.
(b) General performance objective.
Each licensee shall establish,
implement, and maintain a security
program that is designed to monitor,
and without delay detect, assess, and
respond to an actual or attempted
unauthorized access to category 1 or
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category 2 quantities of radioactive
material.
(c) Program features. Each licensee’s
security program must include the
program features, as appropriate,
described in §§ 37.43, 37.45, 37.47,
37.49, 37.51, 37.53, and 37.55.
(d) Information submittal and
notification. By (30 days after the final
rule is published in the Federal
Register), each licensee that is
authorized to possess a category 1 or
category 2 quantity of radioactive
material on the effective date of this
regulation shall submit information
concerning the licensee’s compliance
with the requirements of this subpart to
the appropriate Regional Administrator.
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§ 37.43 General security program
requirements.
(a) Security plan.
(1) Each licensee subject to the
requirements of this subpart shall
develop a written security plan. The
purpose of the security plan is to
establish the licensee’s overall security
strategy to ensure the integrated and
effective functioning of the security
program required by this subpart. The
security plan must at a minimum:
(i) Describe the measures and
strategies used to implement the
requirements of this subpart;
(ii) Identify the security resources,
equipment, and technology used to
satisfy the requirements of this subpart;
(iii) Describe any site-specific
conditions that affect implementation of
Commission requirements; and
(iv) Describe the training by which
individuals implementing the security
program will be informed of their
responsibilities and of any changes that
may affect their ability to implement the
security program.
(2) The security plan must be
reviewed and approved by the
individual with overall responsibility
for the security program.
(3) A licensee shall revise its security
plan as necessary to ensure the effective
implementation of Commission
requirements. The licensee shall ensure
that:
(i) The revision has been reviewed
and approved by the individual with
overall responsibility for the security
program and licensee management; and
(ii) The affected individuals are
instructed on the revised plan before the
changes are implemented.
(4) The licensee shall retain a copy of
the current security plan as a record
until the Commission terminates the
license and, if any portion of the plan
is superseded, retain the superseded
material for 5 years after the record is
superseded.
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(b) Implementing procedures.
(1) The licensee shall develop and
maintain written procedures that
document how the requirements of this
subpart and the security plan will be
met.
(2) The implementing procedures and
revisions to these procedures must be
approved in writing by the individual
with overall responsibility for the
security program.
(3) The licensee shall retain a copy of
the current procedure as a record until
the Commission terminates the license
and, if any portion of the procedure is
superseded, retain the superseded
material for 5 years after the record is
superseded.
(c) Training.
(1) Each licensee shall conduct
training on the security plan to ensure
that those individuals responsible for
implementing the security plan possess
and maintain the knowledge, skills, and
abilities to carry out their assigned
duties and responsibilities effectively.
The training must include instruction
in:
(i) The licensee’s security program
and procedures to secure category 1 or
category 2 quantities of radioactive
material, and in the purposes and
functions of the security measures
employed;
(ii) The responsibility to report
promptly to the licensee any condition
that causes or may cause a violation of
Commission requirements;
(iii) The responsibility to report
promptly to the local law enforcement
agency and licensee any actual or
attempted theft, sabotage, or diversion
of category 1 or category 2 quantities of
radioactive material; and
(iv) The appropriate response to
security alarms.
(2) In determining those individuals
who shall be trained on the security
plan, the licensee shall consider each
individual’s assigned activities during
authorized use and response to potential
situations involving actual or attempted
theft, diversion, or sabotage of category
1 or category 2 quantities of radioactive
material. The extent of the training must
be commensurate with the individual’s
potential involvement in the security of
category 1 or category 2 quantities of
radioactive material as detailed in the
licensee’s security plan.
(3) Refresher training must be
provided at a frequency not to exceed 12
months and when significant changes
have been made to the security program.
This training must include:
(i) Review of the training
requirements of paragraph (c) of this
section, and any changes made since the
last training;
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33939
(ii) Reports on any relevant security
issues, problems, and lessons learned;
(iii) Relevant results of NRC
inspections; and
(iv) Relevant results of the licensee’s
program review and testing and
maintenance.
(4) The licensee shall maintain
records of the initial and refresher
training for 5 years from the date of the
training. The training records must
include dates of the training, topics
covered, a list of licensee personnel in
attendance, and related information.
(d) Protection of information.
(1) Except as provided in paragraph
(d)(8) of this section, licensees
authorized to possess category 1 or
category 2 quantities of radioactive
material shall limit access to and
unauthorized disclosure of their
security plan and implementing
procedures.
(2) Efforts to limit access shall include
the development, implementation, and
maintenance of written policies and
procedures for controlling access to, and
for proper handling and protection
against unauthorized disclosure of, the
security plan and implementing
procedures.
(3) Before granting an individual
access to the security plan or
implementing procedures, licensees
shall:
(i) Evaluate an individual’s need to
know the security plan or implementing
procedures; and
(ii) Complete a background
investigation to determine the
individual’s trustworthiness and
reliability. A trustworthy and reliability
determination shall be conducted by the
reviewing official and shall include the
background investigation elements
contained in § 37.25(a)(2) through
(a)(10). The § 37.25(a)(1) fingerprinting
and criminal history records check
requirements shall not be applied to
those individuals who do not require
unescorted access to category 1 or
category 2 quantities of radioactive
material.
(4) Licensees need not subject the
following individuals to the background
investigation elements for protection of
information:
(i) The categories of individuals listed
in § 37.29(a) through (m); or
(ii) Security service provider
employees, provided written
verification that the employee has been
determined to be trustworthy and
reliable by the required background
investigation in § 37.25(a)(2) through
(a)(10) has been provided by the
security service provider.
(5) The licensee shall document the
basis for concluding that an individual
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is trustworthy and reliable and should
be granted access to the security plan or
implementing procedures. Licensees
shall maintain a list of persons currently
approved for access to the security plan
or implementing procedures. When a
licensee determines that a person no
longer needs access to the security plan
or implementing procedures, the
licensee shall immediately remove the
person from the approved list and take
measures to ensure that the individual
is unable to obtain the security plan or
implementing procedures.
(6) When not in use, the licensee shall
store their security plan and
implementing procedures in a manner
to prevent removal. Information stored
in non-removable electronic form must
be password protected.
(7) The licensee shall retain as a
record for 5 years after the document is
no longer needed:
(i) A copy of the information
protection procedures; and
(ii) The list of individuals approved
for access to the security plan or
implementing procedures.
(8) Licensees that possess safeguards
information or safeguards informationmodified handling are subject to the
requirements of § 73.21 of this chapter,
and shall protect any safeguards
information or safeguards informationmodified handling in accordance with
the requirements of that section.
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§ 37.45 LLEA coordination and
notification.
(a) LLEA coordination.
(1) A licensee subject to this subpart
shall provide information to and
coordinate to the extent practicable with
an LLEA for responding to threats to the
licensee’s facility, including any
necessary armed response. The
information provided to the LLEA must
include:
(i) A description of the facilities and
radioactive materials subject to this
subpart;
(ii) A description of the licensee’s
security measures that have been
implemented to comply with this
subpart;
(iii) A notification that the licensee
will request a timely armed response by
the LLEA to any actual or attempted
theft, sabotage, or diversion of category
1 or category 2 quantities of material;
(iv) A request for information about
the LLEA’s capabilities to provide a
timely armed response taking into
consideration the description of the
security measures provided in
paragraph (a)(1)(ii) of this section;
(v) A request to establish a written
agreement with the LLEA that describes
the LLEA’s commitments to provide a
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response in accordance with this
section;
(vi) A request to establish a means of
direct communication with an LLEAdesignated point of contact for security
emergencies involving actual or
attempted theft or sabotage of licensee
materials;
(vii) A request that the LLEA notify
the licensee whenever the LLEA’s
contact information changes;
(viii) A request that the LLEA notify
the licensee whenever the LLEA’s
response capabilities become degraded
or it becomes incapable of providing a
timely armed response; and
(ix) A request for information about
the LLEA’s willingness to participate in
drills and exercises.
(2) The licensee shall notify the
appropriate NRC regional office listed in
§ 30.6(a)(2) of this chapter within three
business days if:
(i) The LLEA has not responded to the
request for coordination within 60 days
of the coordination request; or
(ii) The LLEA notifies the licensee
that the LLEA does not plan to
participate in coordination activities.
(3) The licensee shall document its
efforts to coordinate with the LLEA to
provide a response to threats to the
licensee’s facility. The licensee’s
documentation must include:
(i) Dates, times, and locations of
meetings with the LLEA;
(ii) Licensee personnel present;
(iii) LLEA personnel present; and
(iv) Copies of any correspondence
between the licensee and LLEA.
(4) The licensee shall coordinate with
the LLEA at a frequency no greater than
12 months, or when changes to the
facility design or operation adversely
affect the potential vulnerability of the
licensee’s material to theft, sabotage, or
diversion. The coordination activities
shall include verification of contact
information and response capabilities.
(5) The licensee shall notify the
appropriate NRC regional office listed in
§ 30.6(a)(2) of this chapter within three
business days after the licensee becomes
aware of any applicable state or local
agency requirement that an initial
response to an emergency involving
radioactive materials must be provided
by other than armed LLEA personnel.
(b) LLEA notification for temporary
job sites.
(1) At least three business days prior
to beginning work at temporary job sites
where the licensee will use or store
category 1 or category 2 quantities of
radioactive material for more than seven
consecutive calendar days, the licensee
shall provide advance written
notification to the appropriate LLEA.
Advance notification must include:
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(i) An explanation that the licensee is
required to provide this notification to
the LLEA in accordance with this
section;
(ii) An explanation that the licensee
will request an armed response from the
LLEA in the event of an actual or
attempted theft, sabotage, or diversion
of category 1 or category 2 quantities of
radioactive material at the temporary job
site;
(iii) Information on the quantities of
radioactive material involved and the
potential hazards associated with loss of
control of the material;
(iv) Scheduled start date and expected
duration of the licensee’s work requiring
the use or storage of category 1 or
category 2 quantities of radioactive
materials at the temporary job site for
which this notice is provided;
(v) Address of the temporary job site,
if available, or sufficient directions to
allow the LLEA to determine the
location of the temporary job site;
(vi) Names and contact information
for licensee personnel expected to be
present at the temporary job site and
responsible for the security of category
1 or category 2 quantities of radioactive
material;
(vii) Names and contact information
for other licensee personnel to be
contacted in an emergency or for
additional information;
(viii) Names and contact information
for the NRC Region responsible for
oversight of the licensee’s activities at
the temporary job site that the LLEA
may contact for information; and
(ix) A request that the LLEA confirm
receipt of the notification.
(2) If an emergency or other
unforeseen circumstance does not allow
the licensee to provide three business
days written advance notice to the
LLEA, the licensee shall notify the
LLEA as soon as possible via telephone,
facsimile, or e-mail.
(3) The licensee shall maintain
documentation of all temporary job site
notifications sent to the LLEA and any
confirmations provided by the LLEA.
(c) Records. The licensee shall
maintain records of its coordination
activities with any LLEA in the
development of the licensee’s security
plan, and copies of all documents and
correspondence provided to or received
from any LLEA in accordance with this
section. Records of coordination
activities at a temporary job site must be
maintained for a period of 5 years.
§ 37.47
Security zones.
(a) Licensees shall ensure that all
aggregated category 1 and category 2
quantities of radioactive material are
used or stored within licensee-
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established security zones. Security
zones may be permanent or temporary.
(b) Temporary security zones must be
established as necessary to meet the
licensee’s transitory or intermittent
business activities, such as periods of
maintenance, source delivery, and
source replacement.
(c) Security zones must, at a
minimum, allow unescorted access only
to approved individuals through:
(1) Isolation of category 1 and
category 2 quantities of radioactive
materials by the use of continuous
physical barriers that allow access to the
security zone only through established
access control points; or
(2) Direct control of the security zone
by approved individuals at all times; or
(3) A combination of continuous
physical barriers and direct control.
(d) For category 1 quantities of
radioactive material during periods of
maintenance, source receipt,
preparation for shipment, installation,
or source removal or exchange, the
licensee shall, at a minimum, provide
an approved individual to maintain
continuous surveillance of sources in
temporary security zones and in any
security zone in which physical barriers
or intrusion detection systems have
been disabled to allow such activities.
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§ 37.49 Monitoring, detection, and
assessment.
(a) Monitoring and detection.
(1) Licensees shall establish and
maintain the capability to continuously
monitor and detect without delay all
unauthorized entries into its security
zones. Licensees shall provide the
means to maintain continuous
monitoring and detection capability in
the event of a loss of the primary power
source, or provide for an alarm and
response in the event of a loss of this
capability to continuously monitor and
detect unauthorized entries.
(2) Monitoring and detection must be
performed by:
(i) A monitored intrusion detection
system that is linked to an on-site or offsite central monitoring facility;
(ii) Electronic devices for intrusion
detection alarms that will alert nearby
facility personnel;
(iii) Visual monitoring by video
surveillance cameras; or
(iv) Visual inspection by approved
individuals.
(3) A licensee subject to this subpart
shall also have a means to detect
unauthorized removal of the radioactive
material from the security zone. This
detection capability must provide:
(i) For category 1 quantities of
radioactive material, immediate
detection of any attempted
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unauthorized removal of the radioactive
material from the security zone. Such
immediate detection capability must be
provided by:
(A) Electronic sensors linked to an
alarm;
(B) Continuous monitored video
surveillance; or
(C) Direct visual surveillance.
(ii) For category 2 quantities of
radioactive material, weekly verification
through physical checks, tamper
indicating devices, use, or other means
to ensure that the radioactive material is
present.
(b) Assessment. Licensees shall
immediately assess each actual or
attempted unauthorized entry into the
security zone to determine whether the
unauthorized access was an actual or
attempted theft, sabotage, or diversion.
(c) Personnel communications and
data transmission. For personnel and
automated or electronic systems
supporting the licensee’s monitoring,
detection, and assessment systems,
licensees shall:
(1) Maintain continuous capability for
personnel communication and
electronic data transmission and
processing among site security systems;
and
(2) Provide an alternative
communication capability for
personnel, and an alternative data
transmission and processing capability,
in the event of a loss of the primary
means of communication or data
transmission and processing.
Alternative communications and data
transmission systems may not be subject
to the same failure modes as the primary
systems.
(d) Response. Licensees shall
immediately respond to any actual or
attempted unauthorized access to the
security zones, or actual or attempted
theft, sabotage, or diversion of category
1 or category 2 quantities of radioactive
material at licensee facilities or
temporary job sites. For any
unauthorized access involving an actual
or attempted theft, sabotage, or
diversion of category 1 or category 2
quantities of radioactive material, the
licensee’s response shall include
requesting, without delay, an armed
response from the LLEA.
§ 37.51 Maintenance, testing, and
calibration.
(a) Each licensee subject to this
subpart shall implement a maintenance,
testing, and calibration program to
ensure that intrusion alarms, associated
communication systems, and other
physical components of the systems
used to secure or detect unauthorized
access to radioactive material are
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maintained in operable condition, are
capable of performing their intended
function when needed, and are
inspected and tested for operability and
performance at intervals not to exceed 3
months.
(b) The licensee shall maintain
records on the maintenance, testing, and
calibration activities for 5 years.
§ 37.53
Requirements for mobile devices.
Each licensee that possesses mobile
devices containing category 1 or
category 2 quantities of radioactive
material must:
(a) Have two independent physical
controls to secure the material from
unauthorized removal when the device
is not under direct control and constant
surveillance by the licensee; and
(b) For devices in or on a vehicle or
trailer, utilize a method to disable the
vehicle or trailer when not under direct
control and constant surveillance by the
licensee. Licensees shall not rely on the
removal of an ignition key to meet this
requirement.
§ 37.55
Security program review.
(a) Each licensee shall be responsible
for the continuing effectiveness of the
security program. Each licensee shall
ensure that the security program is
reviewed to confirm compliance with
the requirements of this subpart and
that comprehensive actions are taken to
correct any noncompliance that is
identified. The review must include the
radioactive material security program
content and implementation. Each
licensee shall ensure that the security
program is reviewed at a frequency not
to exceed 12 months.
(b) The results of the review, along
with any recommendations, must be
documented. Each review report must
identify conditions that are adverse to
the proper performance of the security
program, the cause of the condition(s),
and, when appropriate, recommend
corrective actions, and corrective
actions taken. The licensee shall review
the findings and take any additional
corrective actions necessary to preclude
repetition of the condition, including
reassessment of the deficient areas
where indicated.
(c) The licensee shall maintain the
review documentation for 5 years.
§ 37.57
Reporting of events.
(a) The licensee shall immediately
notify the LLEA after initiating an
appropriate response to any actual or
attempted theft, sabotage, or diversion
of a category 1 or category 2 quantity of
radioactive material. As soon as possible
after initiating a response, but not at the
expense of causing delay or interfering
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with the LLEA response to the event,
the licensee shall notify the NRC
Operations Center ((301) 816–5100). In
no case shall the notification to the NRC
be later than 4 hours after the discovery
of any attempted or actual theft,
sabotage, or diversion.
(b) The licensee shall notify the LLEA
upon discovery of any suspicious
activity related to possible theft,
sabotage, or diversion of category 1 or
category 2 quantities of radioactive
material. As soon as possible but not
later than 4 hours after notifying the
LLEA, the licensee shall notify the NRC
Operations Center ((301) 816–5100).
(c) The initial telephonic notification
required by paragraph (a) of this section
must be followed within a period of 30
days by a written report submitted to
the NRC by an appropriate method
listed in § 37.7. The report must include
sufficient information for NRC analysis
and evaluation, including identification
of any necessary corrective actions to
prevent future instances of such
unauthorized access.
Subpart D—Physical Protection in
Transit
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§ 37.71 Additional requirements for
transfer of category 1 and category 2
quantities of radioactive material.
(a) Notwithstanding the requirements
of any other regulation in this chapter,
any licensee transferring category 1
quantities of radioactive material to a
licensee of the Commission or an
Agreement State, prior to conducting
such transfer, shall verify with the
NRC’s license verification system or the
license issuing authority that the
transferee’s license authorizes the
receipt of the type, form, and quantity
of radioactive material to be transferred
and that the licensee is authorized to
receive radioactive material at the
address requested for delivery. The
transferor shall document the
verification.
(b) Notwithstanding the requirements
of any other regulation in this chapter,
any licensee transferring category 2
quantities of radioactive material to a
licensee of the Commission or an
Agreement State, prior to conducting
such transfer, shall verify with the
NRC’s license verification system or the
license issuing authority that the
transferee’s license authorizes the
receipt of the type, form, and quantity
of radioactive material to be transferred.
The transferor shall document the
verification.
(c) The transferor shall keep a copy of
the verification documentation as a
record for 5 years.
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§ 37.73 Applicability of physical protection
of category 1 and category 2 quantities of
radioactive material during transit.
(a) For shipments of category 1
quantities of radioactive material, each
shipping licensee shall comply with the
requirements for physical protection
contained in §§ 37.75(a) and (c) through
(e); 37.77; 37.79(a)(1), (b)(1), (c) and (d);
and 37.81(a), (c), (e), (g), and (h).
(b) For shipments of category 2
quantities of radioactive material, each
shipping licensee shall comply with the
requirements for physical protection
contained in §§ 37.75(b) through (e);
37.79(a)(2), (a)(3), (b)(2), and (d); and
37.81(b), (d), (f), (g), and (h). For those
shipments of category 2 quantities of
radioactive material that meet the
criteria of § 71.97(b) of this chapter, the
shipping licensee shall also comply
with the advance notification provisions
of § 71.97 of this chapter.
(c) The shipping licensee shall be
responsible for meeting the
requirements of this subpart unless the
receiving licensee has agreed in writing
to arrange for the in-transit physical
protection required under this subpart.
(d) Each licensee that imports
category 1 quantities of radioactive
material shall comply with the
requirements for physical protection
contained in §§ 37.75(a)(2) and (c)
through (e); 37.77; 37.79(a)(1), (b)(1), (c),
and (d); and 37.81(a), (c), (e), (g), and (h)
during the domestic portion of the
shipment.
(e) Each licensee that imports category
2 quantities of radioactive material shall
comply with the requirements for
physical protection during transit
contained in §§ 37.75(c) through (e);
37.79(a)(2), (a)(3), (b)(2), and (d); and
37.81(b), (d), (f), (g), and (h) during the
domestic portion of the shipment.
§ 37.75 Preplanning and coordination of
shipment of category 1 or category 2
quantities of radioactive material.
(a) Each licensee that plans to
transport, or deliver to a carrier for
transport, licensed material that is a
category 1 quantity of radioactive
material outside the confines of the
licensee’s facility or other place of use
or storage shall:
(1) Preplan and coordinate shipment
arrival, including the no-later-than
arrival time, and departure times with
the receiving licensee;
(2) Preplan and coordinate shipment
information with the governor or the
governor’s designee of any State through
which the shipment will pass to:
(i) Ensure minimal delays;
(ii) Discuss the State’s intention to
provide law enforcement escorts;
(iii) Arrange for positional
information sharing when requested;
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(iv) Identify Highway Route Control
Quantity shipments (as the term
‘‘Highway Route Control Quantity’’ is
defined in 49 CFR 173.403); and
(v) Identify safe havens; and
(3) Document the preplanning and
coordination activities.
(b) Each licensee that plans to
transport, or deliver to a carrier for
transport, licensed material that is a
category 2 quantity of radioactive
material outside the confines of the
licensee’s facility or other place of use
or storage shall verify and document the
shipment no-later-than arrival time and
the actual shipment arrival with the
receiving licensee. Verification may be
made by e-mail, fax, or written
documentation of a verbal conversation.
(c) Each licensee who receives a
shipment of a category 1 or category 2
quantity of radioactive material shall
notify the shipping licensee within 4
hours when the shipment arrives at its
destination.
(d) Each licensee, who transports or
plans to transport a shipment of a
category 1 or category 2 quantity of
radioactive material, and determines
that the shipment will arrive after the
no-later-than arrival time provided
pursuant to paragraph (a)(1) of this
section, shall promptly notify the
receiving licensee of the new no-laterthan arrival time.
(e) The licensee shall retain a copy of
the documentation for preplanning and
coordination and any revision thereof,
as a record for 5 years.
§ 37.77 Advance notification of shipment
of category 1 quantities of radioactive
material.
As specified in paragraphs (a) and (b)
of this section, each licensee shall
provide advance notification to the NRC
and the governor of a State, or the
governor’s designee, of the shipment of
licensed material in a category 1
quantity, through or across the
boundary of the State, before the
transport, or delivery to a carrier for
transport of the licensed material
outside the confines of the licensee’s
facility or other place of use or storage.
The contact information, including
telephone and mailing addresses, of
governors and governors’ designees, is
available on the NRC Web site at https://
nrc-stp.ornl.gov/special/designee.pdf. A
list of the contact information is also
available upon request from the
Director, Division of Intergovernmental
Liaison and Rulemaking, Office of
Federal and State Materials and
Environmental Management Programs,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555.
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(a) Procedures for submitting advance
notification. (1) The notification must be
made in writing to the office of each
appropriate governor or governor’s
designee and to the NRC’s Director,
Division of Security Policy, Office of
Nuclear Security and Incident
Response, U.S. Nuclear Regulatory
Commission, Washington, DC 20555.
(2) A notification delivered by mail
must be postmarked at least 7 days
before transport of the shipment
commences at the shipping facility.
(3) A notification delivered by any
other means than mail must reach the
office of the governor or the governor’s
designee at least 4 days before transport
of a shipment within or through the
State.
(b) Information to be furnished in
advance notification of shipment. Each
advance notification of shipment of
category 1 quantities of radioactive
material must contain the following
information, if available at the time of
notification:
(1) The name, address, and telephone
number of the shipper, carrier, and
receiver of the category 1 radioactive
material;
(2) The license numbers of the
shipper and receiver;
(3) A description of the radioactive
material contained in the shipment,
including the radionuclides and
quantity;
(4) The point of origin of the shipment
and the estimated time and date that
shipment will commence;
(5) The estimated time and date that
the shipment is expected to enter each
State along the route;
(6) The estimated time and date of
arrival of the shipment at the
destination; and
(7) A point of contact, with a
telephone number, for current shipment
information.
(c) Revision notice.
(1) The licensee shall provide any
information not previously available at
the time of the initial notification, as
soon as the information becomes
available, to the governor of the State or
the governor’s designee and to the
NRC’s Director of Nuclear Security,
Office of Nuclear Security and Incident
Response, U.S. Nuclear Regulatory
Commission, Washington, DC 20555.
(2) A licensee shall promptly notify
the governor of the State or the
governor’s designee of any changes to
the information provided in accordance
with paragraphs (b) and (c)(1) of this
section. The licensee shall also notify
the NRC’s Director, Division of Security
Policy, Office of Nuclear Security and
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Regulatory Commission, Washington,
DC 20555 of any such changes.
(d) Cancellation notice. Each licensee
who cancels a shipment for which
advance notification has been sent shall
send a cancellation notice to the
governor of each State or to the
governor’s designee previously notified
and to the NRC’s Director, Division of
Security Policy, Office of Nuclear
Security and Incident Response. The
licensee shall state in the notice that it
is a cancellation and identify the
advance notification that is being
cancelled.
(e) Records. The licensee shall retain
a copy of the advance notification and
any revision and cancellation notices as
a record for 5 years.
(f) Protection of information. State
officials, State employees, and other
individuals, whether or not licensees of
the Commission or an Agreement State,
who receive schedule information of the
kind specified in § 37.77(b) shall protect
that information against unauthorized
disclosure as specified in § 73.21 of this
chapter.
§ 37.79 Requirements for physical
protection of category 1 and category 2
quantities of radioactive material during
shipment.
(a) Shipments by road.
(1) Each licensee who transports, or
delivers to a carrier for transport, in a
single shipment, a category 1 quantity of
radioactive material shall:
(i) Ensure that movement control
centers are established that maintain
position information from a remote
location. These control centers must
monitor shipments 24 hours a day, 7
days a week, and have the ability to
communicate immediately, in an
emergency, with the appropriate law
enforcement agencies.
(ii) Ensure that redundant
communications are established that
allow the transport to contact the escort
vehicle (when used) and movement
control center at all times. Redundant
communications may not be subject to
the same interference factors as the
primary communication.
(iii) Ensure that shipments are
continuously and actively monitored by
a telemetric position monitoring system
or an alternative tracking system
reporting to a movement control center.
A movement control center must
provide positive confirmation of the
location, status, and control over the
shipment. The movement control center
must be prepared to promptly
implement preplanned procedures in
response to deviations from the
authorized route or a notification of
actual, attempted, or suspicious
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activities related to the theft, loss, or
diversion of a shipment. These
procedures will include, but not be
limited to, the identification of and
contact information for the appropriate
LLEA along the shipment route.
(iv) Provide an individual to
accompany the driver for those highway
shipments with a driving time period
greater than the maximum number of
allowable hours of service in a 24-hour
duty day as established by the
Department of Transportation Federal
Motor Carrier Safety Administration.
The accompanying individual may be
another driver.
(2) Each licensee that transports
category 2 quantities of radioactive
material shall maintain constant control
and/or surveillance during transit and
have the capability for immediate
communication to summon appropriate
response or assistance.
(3) Each licensee who delivers to a
carrier for transport, in a single
shipment, a category 2 quantity of
radioactive material shall:
(i) Use carriers that have established
package tracking systems. An
established package tracking system is a
documented, proven, and reliable
system routinely used to transport
objects of value. In order for a package
tracking system to maintain constant
control and/or surveillance, the package
tracking system must allow the shipper
or transporter to identify when and
where the package was last and when it
should arrive at the next point of
control.
(ii) Use carriers that maintain constant
control and/or surveillance during
transit and have the capability for
immediate communication to summon
appropriate response or assistance; and
(iii) Use carriers that have established
tracking systems that require an
authorized signature prior to releasing
the package for delivery or return.
(b) Shipments by rail.
(1) Each licensee who transports, or
delivers to a carrier for transport, in a
single shipment, a category 1 quantity of
radioactive material shall:
(i) Ensure that rail shipments are
monitored by a telemetric position
monitoring system or an alternative
tracking system reporting to the
licensee, third-party, or railroad
communications center. The
communications center shall provide
positive confirmation of the location of
the shipment and its status. The
communications center shall implement
preplanned procedures in response to
deviations from the authorized route or
to a notification of actual, attempted, or
suspicious activities related to the theft
or diversion of a shipment. These
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procedures will include, but not be
limited to, the identification of and
contact information for the appropriate
LLEA along the shipment route.
(ii) Implement an NRC-approved
monitoring plan that is designed to
prevent the use of the shipment for
malevolent purposes while the
shipment is in the classification yard.
(iii) Ensure that periodic reports to the
communications center are made at
preset intervals.
(2) Each licensee who transports, or
delivers to a carrier for transport, in a
single shipment, a category 2 quantity of
radioactive material shall:
(i) Use carriers that have established
package tracking systems. An
established package tracking system is a
documented, proven, and reliable
system routinely used to transport
objects of value. In order for a package
tracking system to maintain constant
control and/or surveillance, the package
tracking system must allow the shipper
or transporter to identify when and
where the package was last and when it
should arrive at the next point of
control.
(ii) Use carriers that maintain constant
control and/or surveillance during
transit and have the capability for
immediate communication to summon
appropriate response or assistance; and
(iii) Use carriers that have established
tracking systems that require an
authorized signature prior to releasing
the package for delivery or return.
(c) Procedures.
(1) Each licensee who makes
arrangements for the shipment of
category 1 quantities of radioactive
material shall develop written normal
and contingency procedures to address:
(i) Notifications to the communication
center and law enforcement agencies;
(ii) Communication protocols.
Communication protocols must include
a strategy for the use of authentication
and duress codes and provisions for
refueling or other stops, detours, and
locations where communication is
expected to be temporarily lost;
(iii) Loss of communications; and
(iv) Responses to an actual or
attempted theft or diversion of a
shipment, or any suspicious activities
related to a shipment.
(2) Each licensee who makes
arrangements for the shipment of
category 1 quantities of radioactive
material shall ensure that drivers,
accompanying personnel, train crew,
and movement control center personnel
are appropriately trained in normal and
contingency procedures.
(d) Investigations. Each licensee who
makes arrangements for the shipment of
category 1 or category 2 quantities of
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radioactive material shall immediately
conduct an investigation, in
coordination with the receiving
licensee, of any shipment that is lost or
unaccounted for after the designated nolater-than arrival time in the advance
notification.
§ 37.81
Reporting of events.
(a) The shipping licensee shall notify
the appropriate LLEA and the NRC
Operations Center ((301) 816–5100),
within 1 hour of its determination that
a shipment of category 1 quantities of
radioactive material is lost or missing.
The appropriate LLEA would be the law
enforcement agency in the area of the
shipment’s last confirmed location.
During the investigation required by
37.79(d), the shipping licensee will
provide agreed upon updates to the NRC
Operations Center on the status of the
investigation.
(b) The shipping licensee shall notify
the NRC Operations Center ((301) 816–
5100) within 4 hours of its
determination that a shipment of
category 2 quantities of radioactive
material is lost or missing. If, after 24
hours of its determination that the
shipment is lost or missing, the
radioactive material has not been
located and secured, the licensee shall
immediately notify the NRC Operations
Center.
(c) The shipping licensee shall notify
the designated LLEA along the shipment
route, as soon as possible upon
discovery of any actual or attempted
theft or diversion of a shipment or
suspicious activities related to the theft
or diversion of a shipment of a category
1 quantity of radioactive material. As
soon as possible after notifying the
LLEA, the licensee shall notify the NRC
Operations Center ((301) 816–5100)
upon discovery of any actual or
attempted theft or diversion of a
shipment, or any suspicious activity
related to the shipment of category 1
radioactive material.
(d) The shipping licensee shall notify
the NRC Operations Center ((301) 816–
5100), as soon as possible, upon
discovery of any actual or attempted
theft or diversion of a shipment, or any
suspicious activity related to the
shipment, of a category 2 quantity of
radioactive material.
(e) The shipping licensee shall notify
the NRC Operations Center ((301) 816–
5100) and the LLEA as soon as possible
upon recovery of any lost or missing
category 1 quantities of radioactive
material.
(f) The shipping licensee shall notify
the NRC Operations Center ((301) 816–
5100) as soon as possible upon recovery
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of any lost or missing category 2
quantities of radioactive material.
(g) The initial telephonic notification
required by paragraphs (a) through (d)
must be followed within a period of 30
days by a written report submitted to
the NRC by an appropriate method
listed in § 37.7. In addition, the licensee
shall provide one copy of the written
report addressed to the Director,
Division of Security Policy, Office of
Nuclear Security and Incident
Response. The report must include
sufficient information for NRC analysis
and evaluation.
(h) Subsequent to filing the written
report, the licensee shall also report any
additional substantive information on
the loss or theft within 30 days after the
licensee learns of such information.
Subpart E—[Reserved]
Subpart F—Records
§ 37.101
Form of records.
Each record required by this part must
be legible throughout the retention
period specified by each Commission
regulation. The record may be the
original or a reproduced copy or a
microform, provided that the copy or
microform is authenticated by
authorized personnel and that the
microform is capable of producing a
clear copy throughout the required
retention period. The record may also be
stored in electronic media with the
capability for producing legible,
accurate, and complete records during
the required retention period. Records
such as letters, drawings, and
specifications, must include all
pertinent information such as stamps,
initials, and signatures. The licensee
shall maintain adequate safeguards
against tampering with and loss of
records.
§ 37.103
Record retention.
Licensees shall maintain the records
that are required by the regulations in
this part for the period specified by the
appropriate regulation. If a retention
period is not otherwise specified, these
records must be retained until the
Commission terminates the facility’s
license.
Subpart G—Enforcement
§ 37.105
Inspections.
(a) Each licensee shall afford to the
Commission at all reasonable times
opportunity to inspect category 1 or
category 2 quantities of radioactive
material and the premises and facilities
wherein the nuclear material is used,
produced, or stored.
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(b) Each licensee shall make available
to the Commission for inspection, upon
reasonable notice, records kept by the
licensee pertaining to its receipt,
possession, use, acquisition, import,
export, or transfer of category 1 or
category 2 quantities of radioactive
material.
§ 37.107
Violations.
(a) The Commission may obtain an
injunction or other court order to
prevent a violation of the provisions
of—
(1) The Atomic Energy Act of 1954, as
amended;
(2) Title II of the Energy
Reorganization Act of 1974, as
amended; or
(3) A regulation or order issued
pursuant to those Acts.
(b) The Commission may obtain a
court order for the payment of a civil
penalty imposed under section 234 of
the Atomic Energy Act:
(1) For violations of—
(i) Sections 53, 57, 62, 63, 81, 82, 101,
103, 104, 107, or 109 of the Atomic
Energy Act of 1954, as amended:
(ii) Section 206 of the Energy
Reorganization Act;
(iii) Any rule, regulation, or order
issued pursuant to the sections specified
in paragraph (b)(1)(i) of this section;
(iv) Any term, condition, or limitation
of any license issued under the sections
specified in paragraph (b)(1)(i) of this
section.
(2) For any violation for which a
license may be revoked under Section
186 of the Atomic Energy Act of 1954,
as amended.
§ 37.109
Criminal penalties.
(a) Section 223 of the Atomic Energy
Act of 1954, as amended, provides for
33945
criminal sanctions for willful violation
of, attempted violation of, or conspiracy
to violate, any regulation issued under
sections 161b, 161i, or 161o of the Act.
For purposes of section 223, all the
regulations in part 37 are issued under
one or more of sections 161b, 161i, or
161o, except for the sections listed in
paragraph (b) of this section.
(b) The regulations in part 37 that are
not issued under sections 161b, 161i, or
161o for the purposes of section 223 are
as follows: §§ 37.1, 37.3, 37.5, 37.7, 37.9,
37.11, 37.13, 37.107, and 37.109.
Appendix A to Part 37—Category 1 and
Category 2 Radioactive Materials
The terabecquerel (TBq) values are the
regulatory standard. The curie (Ci) values
specified are obtained by converting from the
TBq value. The curie values are provided for
practical usefulness only.
TABLE 1—CATEGORY 1 AND CATEGORY 2 THRESHOLD 1
Category 1
(TBq)
Radioactive material
Americium-241 .............................................................................................
Americium-241/Be .......................................................................................
Californium-252 ............................................................................................
Cobalt-60 .....................................................................................................
Curium-244 ..................................................................................................
Cesium-137 ..................................................................................................
Gadolinium-153 ............................................................................................
Iridium-192 ...................................................................................................
Plutonium-238 ..............................................................................................
Plutonium-239/Be ........................................................................................
Promethium-147 ..........................................................................................
Radium-226 .................................................................................................
Selenium-75 .................................................................................................
Strontium-90 ................................................................................................
Thulium-170 .................................................................................................
Ytterbium-169 ..............................................................................................
Category 1
(Ci)
60
60
20
30
50
100
1,000
80
60
60
40,000
40
200
1,000
20,000
300
Category 2
(TBq)
1,620
1,620
540
810
1,350
2,700
27,000
2,160
1,620
1,620
1,080,000
1,080
5,400
27,000
540,000
8,100
0.6
0.6
0.2
0.3
0.5
1
10
0.8
0.6
0.6
400
0.4
2
10
200
3
Category 2
(Ci)
16.2
16.2
5.40
8.10
13.5
27.0
270
21.6
16.2
16.2
10,800
10.8
54.0
270
5,400
81.0
R1 = activity for radionuclides or source
number 1
R2 = activity for radionuclides or source
number 2
RN = activity for radionuclides or source
number n
AR1 = activity threshold for radionuclides or
source number 1
AR2 = activity threshold for radionuclides or
source number 2
ARN = activity threshold for radionuclides or
source number n
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n
⎡ R1
R
R ⎤
∑ ⎢ AR + AR2 + ARn ⎥ ≥ 1.0
1
2
n⎦
1 ⎣
Part 39—LICENSES AND RADIATION
SAFETY REQUIREMENTS FOR WELL
LOGGING
17. The authority citation for Part 39
continues to read as follows:
Authority: Secs. 53, 57, 62, 63, 65, 69, 81,
82, 161, 182, 183, 186, 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. 2073, 2077, 2092, 2093, 2095,
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2099, 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).
18. In § 39.1, paragraph (a) is revised
to read as follows:
§ 39.1
Purpose and scope.
(a) This part prescribes requirements
for the issuance of a license authorizing
the use of licensed materials including
sealed sources, radioactive tracers,
radioactive markers, and uranium sinker
bars in well logging in a single well.
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1Calculations Concerning Multiple Sources or Multiple Radionuclides.
The ‘‘sum of fractions’’ methodology for evaluating combinations of multiple sources or multiple radionuclides is to be used in determining
whether a facility or activity meets or exceeds the threshold and is thus subject to the physical protection requirements of this part.
I. If multiple sources and/or multiple radionuclides are present in a facility or activity, the sum of the ratios of the activity of each of the radionuclides must be determined to verify the facility or activity is less than the category 1 or category 2 thresholds of Table 1, as appropriate. Otherwise, if the calculated sum of the ratio, using the following equation, is greater than or equal to 1.0, then the facility or activity meets or exceeds
the thresholds of Table 1, and the applicable physical provisions of this part apply.
II. Use the equation below to calculate the sum of the ratios by inserting the actual activity of the applicable radionuclides from Table 1 or of
the individual sources (of the same radionuclides from Table 1) in the numerator of the equation and the corresponding threshold activity from
the Table 1 in the denominator of the equation. Calculations must be performed in metric values (i.e., TBq) and the numerator and denominator
values must be in the same units.
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This part also prescribes radiation safety
requirements for persons using licensed
materials in these operations. The
provisions and requirements of this part
are in addition to, and not in
substitution for, other requirements of
this chapter. In particular, the
provisions of parts 19, 20, 21, 30, 37, 40,
70, 71, and 150 of this chapter apply to
applicants and licensees subject to this
part.
*
*
*
*
*
953, 954, as amended, sec. 1701, 106 Stat.
2951, 2952, 2953 (42 U.S.C. 2073, 2077, 2092,
2093, 2111, 2201,2232, 2233, 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); Energy Policy Act of 2005, Pub.
L. No. 109–58, 119 Stat. 594 (2005). Section
71.97 also issued under sec. 301, Pub. L. 96–
295, 94 Stat. 789–790.
PART 51—ENVIRONMENTAL
PROTECTION REGULATIONS FOR
DOMESTIC LICENSING AND RELATED
REGULATORY FUNCTIONS
§ 71.97 Advance notification of shipment
of irradiated reactor fuel and nuclear waste.
19. The authority citation for Part 51
continues to read as follows:
Authority: Sec. 161, 68 Stat. 948, as
amended, sec. 1701, 106 Stat. 2951, 2952,
2953, (42 U.S.C. 2201, 2297f); 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). Subpart A
also issued under National Environmental
Policy Act of 1969, secs. 102, 104, 105, 83
Stat. 853–854, as amended (42 U.S.C. 4332,
4334, 4335); and Pub. L. 95–604, Title II, 92
Stat. 3033–3041; and sec. 193, Pub. L. 101–
575, 104 Stat. 2835 (42 U.S.C. 2243). Sections
51.20, 51.30, 51.60, 51.80, and 51.97 also
issued under secs. 135, 141, Pub. L. 97–425,
96 Stat. 2232, 2241, and sec. 148, Pub. L.
100–203, 101 Stat. 1330–223 (42 U.S.C.
10155, 10161, 10168). Section 51.22 also
issued under sec. 274, 73 Stat. 688, as
amended by 92 Stat. 3036–3038 (42 U.S.C.
2021) and under Nuclear Waste Policy Act of
1982, sec. 121, 96 Stat. 2228 (42 U.S.C.
10141).
Sections 51.43, 51.67, and 51.109 also
issued under Nuclear Waste Policy Act of
1982, sec. 114(f), 96 Stat. 2216, as amended
(42 U.S.C. 10134(f)).
20. In § 51.22, the introductory text in
paragraph (c)(3) is revised to read as
follows:
§ 51.22 Criterion for categorical exclusion;
identification of licensing and regulatory
actions eligible for categorical exclusion or
otherwise not requiring environmental
review.
*
*
*
*
*
(b) Advance notification is also
required under this section for the
shipment of licensed material, other
than irradiated fuel, meeting the
following three conditions:
*
*
*
*
*
PART 73—PHYSICAL PROTECTION OF
PLANTS AND MATERIALS
23. The authority citation for part 73
continues to read as follows:
Authority: Secs. 53, 161, 149, 68 Stat. 930,
948, as amended, sec. 147, 94 Stat. 780 (42
U.S.C. 2073, 2167, 2169, 2201); sec. 201, as
amended, 204, 88 Stat. 1242, as amended,
1245, sec. 1701, 106 Stat. 2951, 2952, 2953
(42 U.S.C. 5841, 5844, 2297f); sec. 1704, 112
Stat. 2750 (44 U.S.C. 3504 note); Energy
Policy Act of 2005, Pub. L. 109–58, 119 Stat.
594 (2005).
Section 73.1 also issued under secs. 135,
141, Pub. L. 97–425, 96 Stat. 2232, 2241
(42.U.S.C. 10155, 10161). Section 73.37(f)
also issued under sec. 301, Pub. L. 96–295,
94 Stat. 789 (42 U.S.C. 5841 note). Section
73.57 is issued under sec. 606, Pub. L. 99–
399, 100 Stat. 876 (42 U.S.C. 2169).
24. A new § 73.35 is added to read as
follows:
§ 73.35 Requirements for physical
protection of irradiated reactor fuel (100
grams or less) in transit.
21. The authority citation for part 71
continues to read as follows:
Each licensee who transports, or
delivers to a carrier for transport, in a
single shipment, a quantity of irradiated
reactor fuel weighing 100 grams (0.22
pounds) or less in net weight of
irradiated fuel, exclusive of cladding or
other structural or packaging material,
which has a total external radiation dose
rate in excess of 1 sievert (100 rem) per
hour at a distance of 0.91 meters (3 feet)
from any accessible surface without
intervening shielding, shall follow the
physical protection requirements for
category 1 quantities of radioactive
material in Subpart D of Part 37 of this
chapter.
Authority: Secs. 53, 57, 62, 63, 81, 161,
182, 183, 68 Stat. 930, 932, 933, 935, 948,
Dated at Rockville, Maryland, this 26th day
of May, 2010.
*
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22. In § 71.97, the introductory text of
paragraph (b) is revised to read as
follows:
*
*
*
*
(c) * * *
(3) Amendments to parts 20, 30, 31,
32, 33, 34, 35, 37, 39, 40, 50, 51, 52, 54,
60, 61, 63, 70, 71, 72, 73, 74, 81, and 100
of this chapter which relate to—
*
*
*
*
*
PART 71—PACKAGING AND
TRANSPORTATION OF RADIOACTIVE
MATERIAL
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For the Nuclear Regulatory Commission.
Annette Vietti-Cook,
Secretary of the Commission.
Note: This Appendix Will Not Appear in
the Code of Federal Regulations.
Appendix A to This Proposed Rule—
Regulatory Flexibility Analysis for the
Proposed Amendments to 10 CFR Parts
30, 32, 33, 34, 35, 36, 37, 39, 51, 71, 73,
and 150 (Physical Protection of
Byproduct Material)
I. Background
The Regulatory Flexibility Act (RFA), as
amended 5 U.S.C. 601 et seq., requires that
agencies consider the impact of their
rulemakings on small entities and, consistent
with applicable statutes, consider
alternatives to minimize these impacts on the
businesses, organizations, and government
jurisdictions to which they apply.
The NRC has established standards for
determining which NRC licensees qualify as
small entities (10 CFR 2.810). These size
standards were based on the Small Business
Administration’s most common receiptsbased size standards and include a size
standard for business concerns that are
manufacturing entities.
Description of the Reasons That Action by
the Agency Is Being Considered
The NRC has long participated in efforts to
address radioactive source protection and
security. However, the terrorist attacks of
September 11, 2001, heightened concerns
about the use of risk-significant radioactive
materials in a malevolent act. Such an attack
is of particular concern because of the
widespread use of radioactive materials in
the United States by industrial, medical, and
academic institutions. The theft or diversion
of risk-significant radioactive materials could
lead to their malicious use in a radiological
dispersal device or a radiological exposure
device.
Commission regulations provide
requirements for the safe use, transit, and
control of licensed material. A licensee’s loss
of control of risk-significant radioactive
material, whether it is inadvertent or through
a deliberate act, could result in significant
adverse impacts that could reasonably
constitute a threat to the public health and
safety or the common defense and security of
the United States. After the attacks of
September 11, 2001, the Commission
determined that certain licensed material
should be subject to enhanced security
provisions and safeguarded during transport,
and that individuals with unescorted access
to risk-significant radioactive material should
be subject to background investigations. For
additional information see the Discussion
portion of the Statements of Consideration
(SOC).
Succinct Statement of the Objectives of, and
Legal Basis for, the Proposed Rule
The regulatory objective of this rulemaking
is to establish generically applicable security
requirements similar to those previously
imposed by the NRC orders. Although an
order is legally binding on the licensee
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receiving the order, a rule makes the
requirements generally applicable to all
affected licensees. In addition, notice and
comment rulemaking is an open process that
allows for public participation. This
proposed rulemaking would place security
requirements for category 1 and category 2
quantities of radioactive material into the
regulations. In developing the proposed rule,
the NRC considered, among other things, the
various security orders, lessons-learned
during implementation, the
recommendations from the Independent
Review Panel and the Materials Working
Group, and stakeholder comments. The
proposed rule also considered a petition for
rulemaking submitted by the State of
Washington. For additional information see
the Discussion portion of the SOC. The
authority citation sections of the proposed
rule contain the statutory authority for the
proposed rule.
Description of and, Where Feasible, an
Estimate of the Number of Small Entities to
Which the Proposed Rule Will Apply
The proposed rule would affect about 300
NRC licensees and about 1,100 Agreement
State licensees. This includes a wide range of
licensees, including pool-type irradiator
licensees; manufacturer and distributor
licensees; medical facilities with gamma
knife devices; self-shielded irradiator
licensees (including blood irradiators);
teletherapy unit licensees; radiographers;
well loggers; broad scope users; radioisotope
thermoelectric generator licensees; and
licensees that ship or prepare for shipment
category 1 or category 2 quantities of
radioactive material. Some of these licensees
would be considered small entities. In fiscal
year 2008, about 26 percent of materials
licensees qualified as small entities. Using
the same percentage, 364 of the licensees that
would be affected by the proposed rule
would be considered small entities.
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Description of the Projected Reporting,
Recordkeeping, and Other Compliance
Requirements of the Proposed Rule,
Including an Estimate of the Classes of Small
Entities That Will Be Subject to the
Requirements, and the Type of Professional
Skills Necessary for Preparation of Reports
and Records
Licensees would be required to: (1)
Develop procedures for implementation of
the security provisions; (2) develop a security
plan that describes how security is being
implemented; (3) conduct training on the
procedures and security plan: (4) conduct
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background investigations for those
individuals permitted access to category 1 or
category 2 quantities of radioactive material;
(5) coordinate with LLEAs so the LLEAs
would be better prepared to respond in an
emergency; (6) conduct preplanning and
coordination activities before shipping
radioactive material; and (7) implement
security measures for the protection of the
radioactive material. Licensees would be
required to promptly report any attempted or
actual theft or diversion of the radioactive
material. Licensees would be required to
keep copies of the security plan, procedures,
background investigation records, training
records, and documentation that certain
activities have occurred. For additional
information on the requirements, see the SOC
or the proposed rule text. No special skills
are necessary for the preparation of reports or
records.
The average licensee would have a onetime cost of approximately $27,000 and an
annual cost of approximately $25,700 to fully
implement the proposed rule. Much of this
cost would result from the requirements to
have procedures, conduct training, and to
develop a security plan. Although not
required by the various security orders, many
licensees have already developed procedures
and conducted training and may only require
minor revisions; therefore, the actual cost for
some licensees may be lower. Additional
large costs are the weekly physical check of
the category 2 sources and the annual
program review. The NRC views that the
weekly check is a vital part of the security
program, particularly for materials that are
used infrequently. The program review is
important for licensees to review the
effectiveness of the program and to ensure
that requirements are being implemented.
More information on the cost of the proposed
rule is contained in the Regulatory Analysis.
Identification, to the Extent Practicable, of
All Relevant Federal Rules That May
Duplicate, Overlap or Conflict With the
Proposed Rule
Several U.S. Government programs involve
fingerprinting and an FBI identification and
criminal history records check. These
include the National Agency Check;
Transportation Worker Identification
Credentials in accordance with 49 CFR 1572;
Bureau of Alcohol, Tobacco, Firearms, and
Explosives background check and clearances
in accordance with 27 CFR 555; Health and
Human Services security risk assessments for
possession and use of select agents and
toxins in accordance with 42 CFR 73;
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33947
Hazardous Material security threat
assessment for hazardous material
endorsement to commercial drivers license in
accordance with 49 CFR 1572; and Customs
and Border Patrol’s Free and Secure Trade
Program. Any individual that has favorably
undergone the background investigation
required by these programs would be
relieved from the background investigation
elements of the proposed rule as long as the
licensee has appropriate documentation. Any
individual who has an active Federal security
clearance would also be relieved assuming
appropriate documentation is provided.
The Department of Transportation requires
security plans for the transport of highway
route control quantities of radioactive
material in accordance with 49 CFR 172.800.
This provision covers only a small portion of
the category 1 and category 2 quantities of
radioactive material covered by the proposed
rule.
The NRC is not aware of any other relevant
Federal rules that may duplicate, overlap, or
conflict with the proposed rule.
Description of any significant alternatives
to the proposed rule that accomplish the
stated objectives of applicable statutes and
that minimize any significant economic
impact of the proposed rule on small entities,
including alternatives considered, such as:
(1) Establishment of differing compliance or
reporting requirements or timetables that
take into account the resources available to
small entities; (2) clarification, consolidation,
or simplification of compliance and reporting
requirements under the rule for small
entities; (3) use of performance rather than
design standards; and (4) any exemption
from coverage of the rule, or any part thereof,
for such small entities.
As noted earlier, some of the licensees that
would be impacted by the proposed rule are
small businesses. The proposed rule would
impose the minimum requirements that the
NRC believes is necessary to adequately
protect the public health and safety and the
common defense and security. Therefore, the
NRC could not grant relief to small entities
to allow them to implement less effective
measures. The proposed rule would provide
some flexibility in the particular measures
that a licensee could choose to employ.
Licensees affected by the proposed rule have
already implemented the bulk of the
requirements in response to various security
orders.
[FR Doc. 2010–13319 Filed 6–14–10; 8:45 am]
BILLING CODE 7590–01–P
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Agencies
[Federal Register Volume 75, Number 114 (Tuesday, June 15, 2010)]
[Proposed Rules]
[Pages 33902-33947]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-13319]
[[Page 33901]]
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Part II
Nuclear Regulatory Commission
-----------------------------------------------------------------------
10 CFR Parts 30, 32, 33, et al.
Physical Protection of Byproduct Material; Proposed Rule
Federal Register / Vol. 75, No. 114 / Tuesday, June 15, 2010 /
Proposed Rules
[[Page 33902]]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Parts 30, 32, 33, 34, 35, 36, 37, 39, 51, 71, and 73
[NRC-2008-0120]
RIN 3150-AI12
Physical Protection of Byproduct Material
AGENCY: U. S. Nuclear Regulatory Commission.
ACTION: Proposed rule.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is proposing to
amend its regulations to establish security requirements for the use
and transport of category 1 and category 2 quantities of radioactive
material, which the NRC considers to be risk-significant and therefore
to warrant additional protection. Category 1 and category 2 thresholds
are based on those established in the International Atomic Energy
Agency (IAEA) Code of Conduct on the Safety and Security of Radioactive
Sources which NRC endorses. The objective of this proposed rule is to
provide reasonable assurance of preventing the theft or diversion of
category 1 and category 2 quantities of radioactive material. The
proposed regulations would also include security requirements for the
transportation of irradiated reactor fuel that weighs 100 grams or less
in net weight of irradiated fuel. The proposed rule would affect any
licensee that is authorized to possess category 1 or category 2
quantities of radioactive material, any licensee that transports these
materials using ground transportation, and any licensee that transports
small quantities of irradiated reactor fuel.
DATES: Submit comments on the proposed rule by October 13, 2010. Submit
comments specific to the information collection aspects of this
proposed rule by July 15, 2010. Comments received after the above dates
will be considered if it is practical to do so, but the NRC is able to
assure consideration only for comments received on or before these
dates.
ADDRESSES: You may submit comments by any one of the following methods.
Please include Docket ID NRC-2008-0120 in the subject line of your
comments. Comments submitted in writing or in electronic form will be
posted on the NRC Web site and on the Federal rulemaking Web site
Regulations.gov. Because your comments will not be edited to remove any
identifying or contact information, the NRC cautions you against
including any information in your submission that you do not want to be
publicly disclosed.
The NRC requests that any party soliciting or aggregating comments
received from other persons for submission to the NRC inform those
persons that the NRC will not edit their comments to remove any
identifying or contact information, and therefore, they should not
include any information in their comments that they do not want
publicly disclosed.
Federal Rulemaking Web site: Go to https://www.regulations.gov and
search for documents filed under Docket ID NRC-2008-0120. Address
questions about NRC dockets to Carol Gallagher 301-492-3668; e-mail
Carol.Gallagher@nrc.gov.
Mail comments to: Secretary, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, Attn: Rulemakings and Adjudications Staff.
E-mail comments to: Rulemaking.Comments@nrc.gov. If you do not
receive a reply e-mail confirming that we have received your comments,
contact us directly at 301-415-1677.
Hand-deliver comments to: 11555 Rockville Pike, Rockville, Maryland
20852, between 7:30 am and 4:15 pm Federal workdays. (Telephone 301-
415-1677).
Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at
301-415-1101.
You may submit comments on the information collections by the
methods indicated in the Paperwork Reduction Act Statement.
You can access publicly available documents related to this
proposed rule using the following methods:
NRC's Public Document Room (PDR): The public may examine and have
copied for a fee publicly available documents at the NRC's PDR, Public
File Area O-1 F21, One White Flint North, 11555 Rockville Pike,
Rockville, Maryland.
NRC's Agencywide Documents Access and Management System (ADAMS):
Publicly available documents created or received at the NRC are
available electronically at the NRC's Electronic Reading Room at https://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain
entry into ADAMS, which provides text and image files of NRC's public
documents. If you do not have access to ADAMS or if there are problems
in accessing the documents located in ADAMS, contact the NRC's PDR
reference staff at 1-800-397-4209, 301-415-4737 or by e-mail to
pdr.resource@nrc.gov.
Federal Rulemaking Web site: Public comments and supporting
materials related to this proposed rule can be found at https://www.regulations.gov by searching on Docket ID NRC-2008-0120.
FOR FURTHER INFORMATION CONTACT: Merri Horn, Office of Federal and
State Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone: (301) 415-
8126, e-mail: Merri.Horn@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
II. Discussion
A. General Applicability
B. Background Investigation and Access Authorization Program
C. Physical Protection During Use
D. Transportation Security
III. Discussion of Proposed Amendments by Section
IV. Criminal Penalties
V. Agreement State Compatibility
VI. Plain Language
VII. Voluntary Consensus Standards
VIII. Finding of No Significant Environmental Impact: Availability
IX. Paperwork Reduction Act Statement
X. Regulatory Analysis
XI. Regulatory Flexibility Certification
XII. Backfit Analysis
I. Background
The NRC has long participated in efforts to address radioactive
source protection and security. However, the terrorist attacks of
September 11, 2001, heightened concerns about the use of risk-
significant radioactive materials in a malevolent act. Such an attack
is of particular concern because of the widespread use of radioactive
materials in the United States by industrial, medical, and academic
institutions. The theft or diversion of risk-significant quantities of
radioactive materials could lead to their use in a radiological
dispersal device (RDD) or a radiological exposure device (RED).
The NRC's current regulations provide requirements for the safe
use, transit, and control of licensed material. Any loss of control of
risk-significant radioactive material, whether inadvertent or through a
deliberate act, could result in significant adverse impacts that could
reasonably constitute a threat to the public health and safety or the
common defense and security of the United States. In the changed threat
environment after the attacks of September 11, 2001, the Commission
determined that certain licensed material should be subject to enhanced
security requirements and safeguarded during transport, and that
individuals with unescorted access to risk-significant quantities of
radioactive material should be subject to background investigations.
[[Page 33903]]
As part of the development of the enhanced security measures, the
NRC performed vulnerability assessments to identify gaps or
vulnerabilities in security and the effectiveness and costs of certain
physical protection enhancements at various licensed facilities. The
results of the vulnerability assessments were used in the development
of security enhancement orders that were issued to licensees using a
graded approach based on the relative risk and quantity of material
possessed by the licensee. The NRC issued the first series of orders to
certain panoramic and underwater irradiator licensees that possessed
more than 370 TBq (10,000 Ci) of radioactive material (EA-02-249; June
6, 2003) (68 FR 35458; June 13, 2003). The next series of orders were
issued to certain manufacturing and distribution (M&D) licensees (EA-
03-225; January 12, 2004) (69 FR 5375; February 4, 2004). These orders
require the implementation of additional security measures and the
protection of the licensee's physical protection information as
Safeguards Information--Modified Handling (SGI-M). The original orders
are not publicly available because they contain detailed security
requirements that are designated as SGI-M. However, redacted versions
of these orders have been made available to the public (73 FR 33859;
June 13, 2008, and 73 FR 49714; August 22, 2008). These orders were
issued to both NRC and Agreement State licensees under the NRC's
authority to protect the common defense and security. Subsequently, the
NRC issued Increased Control Orders (EA-05-090; November 14, 2005) (70
FR 72128; December 1, 2005) to other licensees authorized to possess
certain risk-significant quantities of radioactive material (category 1
and category 2 quantities). The Increased Control Orders do not contain
safeguards information (SGI) or SGI-M and are available on the NRC's
public Web site at https://www.nrc.gov/security/byproduct/orders.html.
These orders were issued under the NRC's authority to protect public
health and safety, and require licensees to implement enhanced security
measures known as Increased Controls. To effect nationwide
implementation of the Increased Control Orders, each Agreement State
issued legally binding requirements to put enhanced security measures,
identical to the Increased Controls, in place for licensees under that
State's regulatory jurisdiction.
These security orders specifically address the security of
byproduct material possessed in quantities greater than, or equal to,
category 1 and category 2 quantities. The orders provide for enhanced
security measures for such things as license verification before
transfer, intrusion detection and response, access control, and
coordination with local law enforcement authorities (LLEAs). The orders
also contain requirements for the licensee to determine the
trustworthiness and reliability of individuals permitted unescorted
access to risk-significant radioactive materials. The determination
involves a background investigation of the individual. The background
investigations were originally limited to local criminal history
records checks with law enforcement agencies, verification of
employment history, education, personal references, and confirmation of
employment eligibility (legal immigration status).
In 2005, Congress passed, and the President signed, the Energy
Policy Act of 2005 (EPAct). The EPAct amended Section 149 of the Atomic
Energy Act (AEA) to authorize the Commission to require to be
fingerprinted any individual who is permitted unescorted access to
radioactive material or other property subject to regulation by the
Commission that the Commission determines to be of such significance to
the public health and safety or the common defense and security as to
warrant fingerprinting and a Federal Bureau of Investigation (FBI)
criminal history records check. With this new authority, the Commission
determined that individuals who have access to category 1 and category
2 quantities of radioactive material warrant fingerprinting and FBI
criminal history records checks. On October 17, 2006, the NRC issued
orders to panoramic and underwater irradiator licensees (EA-06-248) (71
FR 63043; October 27, 2006), manufacturer and distributor licensees
(EA-06-250) (71 FR 63046; October 27, 2006), and licensees making
shipments of category 1 quantities of radioactive material (EA-06-249)
(71 FR 62302; October 24, 2006) to require fingerprinting and FBI
criminal history records checks for unescorted access to risk-
significant quantities of radioactive material at their facilities. In
issuing these orders, NRC noted that a malevolent act by an individual
with unescorted access to these materials could result in significant
adverse impacts to the public health and safety or the common defense
and security and, thus, necessitated expedited implementation of
fingerprinting requirements. The orders were issued to both NRC and
Agreement State licensees under the NRC's authority to protect the
common defense and security. On December 5, 2007, the NRC issued orders
to all other NRC licensees that possessed category 1 or category 2
quantities of radioactive material (EA-07-305) (72 FR 70901; December
13, 2007) to require fingerprinting and FBI criminal history records
checks for unescorted access to category 1 or category 2 quantities of
radioactive material. These orders were issued under the NRC's
authority to protect the public health and safety and are available on
the NRC public Web site at https://www.nrc.gov/security/byproduct/orders.html. To effect nationwide implementation, each Agreement State
issued legally binding requirements to licensees under their regulatory
jurisdiction.
During the same time period, efforts were underway to enhance
transportation security of category 1 and category 2 quantities of
radioactive materials. The NRC issued two sets of orders to licensees
transporting radioactive material in quantities of concern. The first
set of transportation security orders was issued to certain licensees
that might be expected to transport radioactive materials in quantities
of concern (category 1 quantities) (EA-05-006; July 19, 2005) (70 FR
44407; August 2, 2005). The orders require the implementation of
additional security measures and the protection of the licensee's
physical protection information as SGI-M. The original orders are not
publicly available because they contain detailed security requirements
that are designated as SGI-M. However, a redacted version of the order
is publicly available (73 FR 51016; August 29, 2008). These orders were
issued to both NRC and Agreement State licensees under the NRC's
authority to protect the common defense and security. Subsequently, the
NRC issued orders (EA-05-090; November 14, 2005) (70 FR 72128; December
1, 2005) to other licensees authorized to possess certain risk-
significant quantities of radioactive material (category 2 quantities).
The Increased Control Orders mentioned earlier also contain
requirements for transporting category 2 quantities of radioactive
material.
These security orders specifically address the transportation
security of byproduct material transported in quantities greater than,
or equal to, category 2. The additional security measures contained in
the orders provide for enhanced security measures during transportation
that are beyond the current regulations, including enhanced security in
preplanning and
[[Page 33904]]
coordinating shipments, advance notification of shipments to the NRC
and States through which the shipment will pass, control and monitoring
of shipments that are underway, trustworthiness and reliability of
personnel, information security considerations, and control of mobile
or portable devices.
The requirements put in place by the orders supplement the existing
regulatory requirements. These additional requirements are primarily
intended to provide reasonable assurance of preventing the theft or
diversion of this risk-significant material. These requirements provide
the Commission with reasonable assurance that public health and safety
and the common defense and security continue to be adequately
protected.
Although an order, like a rule, is legally binding on the licensee
receiving the order, a rule is generally applicable to all licensees.
Further, the notice-and-comment rulemaking process allows members of
the public to provide comments on the proposed rule. It is Commission
policy to implement generally applicable requirements through
rulemaking.
If promulgated, this rulemaking would adopt security requirements
for category 1 and category 2 quantities of radioactive material into
the regulations. New requirements for background investigations and an
access authorization program are proposed to ensure that individuals
who have access to these materials have gone through background
investigations and are determined to be trustworthy and reliable. New
requirements are also proposed to establish physical protection systems
to detect, assess, and respond to unauthorized access to category 1 and
category 2 quantities of radioactive material. For transport of the
radioactive materials, new requirements for recipient license
verification; preplanning and coordination of shipments; advance
notification of shipments; notification of shipment delays, schedule
changes, and suspected loss of a shipment; and control and monitoring
of shipments are proposed. The proposed amendments would also include
security requirements for shipments of irradiated reactor fuel that
weighs 100 grams (0.22 pounds (lb)) or less in net weight of irradiated
fuel, exclusive of cladding or other structural or packaging material,
which has a total external radiation dose rate in excess of 1 sievert
(Sv) (100 rem) per hour at a distance of 0.91 meters (m) (3 feet (ft))
from any accessible surface without intervening shielding.
In developing the proposed rule the NRC considered, among other
things, the various security orders, lessons-learned during
implementation of the orders, the recommendations of the Independent
External Review Panel and the Materials Program Working Group, and
stakeholder comments received on the orders and the preliminary rule
language that was posted on Regulations.gov. The Commission chartered
the Independent External Review Panel to: (1) Identify vulnerabilities
in the NRC's materials licensing program with respect to import,
export, specific, and general licenses; (2) validate the ongoing
byproduct material security efforts; and (3) evaluate the apparent
``good faith presumption'' that pervades the NRC licensing process. The
Panel's March 2008 report is available in ADAMS under accession number
ML080700957. The Materials Program Working Group conducted a
comprehensive evaluation of the materials program to identify short-
and long-term strategies to mitigate security vulnerabilities. The
Working Group report contains sensitive information and is not publicly
available. However, the Group's comments on the Panel's report are
publicly available in ADAMS under accession number ML080660424.
In developing the basis for the transportation security aspects of
the rule, NRC held three public meetings to seek public comment on the
development of the technical basis. The NRC published information on
the requirements being considered along with some background
information and a notice of the three meetings (73 FR 826; January 4,
2008). In response the NRC received more than 100 comments from
stakeholders that were used to finalize the technical basis for the
transportation portion of this rulemaking. The comments addressed a
number of issues and concerns. However, most focused on clarifying
requirements, adding efficiencies, and improving the processes that
licensees follow to comply with the additional security measures
currently enforced under security orders.
During the development of the proposed rule, the NRC posted
preliminary rule text for public comment on https://www.regulations.gov
under Docket ID NRC-2008-0120. The posting of the preliminary rule text
was noticed in the Federal Register and included the portions of the
rule that address background investigation and access control aspects
(subpart B) (74 FR 17794; April 17, 2009), enhanced security during use
(subpart C) (74 FR 20235; May 1, 2009), and transportation security
aspects (subpart D) (73 FR 69590; November 19, 2008). The NRC allowed a
45-day comment period for each subpart. In the documents announcing the
availability of the preliminary regulatory text, the NRC made it clear
that it would not respond to any of the comments received during this
pre-rulemaking stage. The NRC did consider the public input on the
preliminary rule text in finalizing the proposed rule, and areas where
they made a substantive change based on the comments are discussed in
this Statement of Considerations. The NRC also made some editorial
changes based on the comments; these changes are not discussed further.
PRM-71-13
On July 16, 2008 (73 FR 40767), the NRC published the resolution
and closure of a petition for rulemaking (PRM) filed by Christine O.
Gregoire, Governor of the State of Washington (PRM-71-13). The NRC
indicated that the issues raised by the petitioner would be considered
in an ongoing rulemaking on the security requirements for the
transportation of radioactive material in quantities of concern.
The petitioner requested that the NRC adopt the use of global
positioning system (GPS) tracking as a national requirement for
vehicles transporting highly radioactive mobile or portable radioactive
devices. The petitioner stated that the Commission could instead grant
States the flexibility to impose more stringent requirements than those
required under the current increased controls. The petitioner believes
that GPS technology is an effective and relatively inexpensive tool
that will help when a vehicle with radioactive material is missing, but
also acknowledged that requiring a GPS on these vehicles does not
ensure that the radiological source will be found. However, the
petitioner believes that these suggestions would give law enforcement a
significant advantage. The NRC considered the issues identified by the
petitioner and the petitioner's suggested approach to address those
issues in the development of this proposed rule.
II. Discussion
The NRC believes that a new part of the Code of Federal Regulations
(CFR) should be established for the security requirements for use of
category 1 and category 2 quantities of radioactive material. The
concept for using a separate part for safety and physical protection
requirements has already been established for special nuclear material
(10 CFR part 73). The
[[Page 33905]]
establishment of a new part for security-related requirements for
byproduct material would be more effective and efficient compared to
interspersing the requirements with safety requirements or placing them
with the part 73 security requirements for special nuclear material. A
new part specifically directed to byproduct material licensees should
make applicable requirements easier for both licensees and other
stakeholders to locate and understand.
This discussion section has been divided into four subsections to
better present information on the proposed rule. Each section presents
information on a different aspect of the proposed rule. Section A
provides information that is generally applicable to all aspects of
this proposed rulemaking. Section B provides information on background
investigations and the access authorization program. Section C provides
information on the physical protection of the materials during use.
Lastly, Section D provides information on transportation security
aspects.
A. General Applicability
1. What action is the NRC taking?
The NRC is proposing to amend its regulations to impose security
requirements for the use of category 1 and category 2 quantities of
radioactive material. The proposed requirements would establish the
objectives and minimum requirements that licensees must meet to protect
against theft or diversion. These requirements are intended to increase
the protection of the public against the unauthorized use of category 1
or category 2 quantities of radioactive material by reducing the risk
of the theft or diversion of the material.
2. Why do the requirements need to be revised?
Prior to September 11, 2001, NRC requirements focused on safety and
preventing inadvertent or accidental exposure of both workers and the
public to these materials. These requirements also indirectly provided
security for the material. However, the events of September 11 made the
NRC take a broader look at its requirements and reevaluate what a
terrorist might do to attain these materials. From this effort, the NRC
identified several areas where additional requirements should be
implemented to improve security. The security requirements need to be
placed in the regulations so that they are generally applicable to all
licensees and to provide an opportunity for all stakeholders to comment
on the proposed requirements.
3. Why doesn't the NRC just keep the orders in effect?
The orders issued by the NRC could stay in place indefinitely.
However, the regulations would not reflect current Commission policy or
requirements. Imposing long-term requirements through orders has not
traditionally been the agency's preferred method of regulation. Orders,
unlike rules, do not apply prospectively to applicants for new
licenses. The NRC would have to periodically issue new orders to cover
new and amended licenses, and perhaps reissue orders periodically to
existing licensees if requirements or administrative practices change.
In order to make the requirements generally applicable to all present
and future licensees, the security-related requirements need to be
placed in the regulations.
Assured that adequate security is in place for these materials
(because of existing regulations and orders), the NRC is now planning
to formally revise its security requirements and gather public and
stakeholder input. The orders would remain in place for NRC licensees
until the final rule becomes effective. Once the final rule is
effective, the NRC will rescind the orders that were issued to its
licensees. For Agreement State licensees that received an NRC order,
the order would remain in place until the Agreement State issues
compatible requirements. Once the State has issued its requirements,
the NRC would rescind the order. Each Agreement State would follow its
own process for replacing the increased control legally binding
requirements with the requirements contained in the final rule.
4. Who would this action affect?
These requirements would apply to NRC or Agreement State licensees
that are authorized to possess category 1 or category 2 quantities of
radioactive material. This includes a wide range of licensees,
including pool-type irradiator licensees; manufacturer and distributor
licensees; medical facilities with gamma knife devices; self-shielded
irradiator licensees (including blood irradiators); teletherapy unit
licensees; radiographers; well loggers; broad scope users; radioisotope
thermoelectric generator licensees; and licensees that ship or prepare
for shipment category 1 or category 2 quantities of radioactive
material. Nearly 1,400 licensees are implementing the various orders
and are the entities that would be impacted by this proposed rule. In
addition, some fuel cycle and reactor licensees that possess sources at
these levels would be impacted. Licensees whose activities are covered
under the physical protection requirements of 10 CFR part 73 would be
exempt from the requirements of 10 CFR part 37. For example, a reactor
licensed under part 50 that also possesses a radiography source would
not need to implement the part 37 provisions if the source is protected
under the reactor security program required by part 73.
5. What are category 1 and category 2 quantities of radioactive
material?
Category 1 quantities of radioactive material have been called
radioactive material in quantities of concern (RAMQC). Category 1 and
category 2 quantities of radioactive material have been called risk-
significant radioactive material and refer specifically to 16
radioactive materials (14 single radionuclides and 2 combinations).
These materials are: americium-241; americium-241/beryllium;
californium-252; curium-244; cobalt-60; cesium-137; gadolinium-153;
iridium-192; plutonium-238; plutonium-239/beryllium; promethium-147;
radium-226; selenium-75; strontium-90 (yttrium-90); thulium-170; and
ytterbium-169. Irradiated fuel and mixed oxide fuel are not included
even though they may contain category 1 or category 2 quantities of
radioactive material; these materials are covered by other regulations.
The thresholds for category 1 and category 2 quantities of radioactive
material are provided in the following table. Terabecquerels is the
official value to be used for determining whether a radioactive
material is a category 1 or category 2 quantity. Because many licensees
use curies in their activities instead of becquerels, the table
provides the curie value at three figures for practical usefulness.
----------------------------------------------------------------------------------------------------------------
Category 1 Threshold Category 2 Threshold
-------------------------------------------------------------------------
Radioactive Material Terabecquerels Terabecquerels
(TBq) Curies (Ci) (TBq) Curies (Ci)
----------------------------------------------------------------------------------------------------------------
Americium-241......................... 60 1,620 0.6 16.2
Americium-241/Beryllium............... 60 1,620 0.6 16.2
[[Page 33906]]
Californium-252....................... 20 540 0.2 5.40
Curium-244............................ 50 1,350 0.5 13.5
Cobalt-60............................. 30 810 0.3 8.10
Cesium-137............................ 100 2,700 1 27.0
Gadolinium-153........................ 1000 27,000 10.0 270
Iridium-192........................... 80 2,160 0.8 21.6
Plutonium-238......................... 60 1,620 0.6 16.2
Plutonium-239/Beryllium............... 60 1,620 0.6 16.2
Promethium-147........................ 40,000 1,080,000 400 10,800
Radium-226............................ 40 1,080 0.4 10.8
Selenium-75........................... 200 5,400 2.0 54.0
Strontium-90 (Yttrium-90)............. 1,000 27,000 10.0 270
Thulium-170........................... 20,000 540,000 200 5,400
Ytterbium-169......................... 300 8,100 3 81.0
----------------------------------------------------------------------------------------------------------------
These materials and thresholds are based on the IAEA Code of
Conduct. The NRC and the international community, led by the IAEA,
revised the IAEA Code of Conduct in 2003 to establish common
international guidance for safety and security measures for radioactive
sources. The IAEA published these results in a document titled ``Code
of Conduct on the Safety and Security of Radioactive Sources.'' A link
to this document can be found on the NRC Web site at https://www.nrc.gov/security/byproduct/enhanced-security.html. In a separate
effort, the U.S. Department of Energy (DOE) and the NRC reviewed the
chemical, physical, and radiological characteristics of each
radioactive material that is licensed in the United States, for its
attractiveness to a terrorist. This effort identified 16 radioactive
materials that could pose a serious threat to people and the
environment. This effort further identified the different quantities or
``thresholds'' of materials that could be useful to a terrorist. The
results of the DOE/NRC effort closely matched the Code of Conduct
Category 2 quantities. The NRC adopted the IAEA Code of Conduct
Category 1 and Category 2 threshold quantities to provide consistency
between domestic and international efforts for security of radioactive
materials that are deemed to be attractive targets for malevolent use.
IAEA, Safety Series RS-G-1.9, Categorization of Radioactive
Sources, provides the underlying methodology for the development of the
Code of Conduct thresholds. Safety guide RS-G-1.9 provides a risk-based
ranking of radioactive sources in five categories in terms of their
potential to cause severe deterministic effects for a range of
scenarios that include both external exposure from an unshielded source
and internal exposure following dispersal. The categorization system
uses the `D' values as normalizing factors. The `D' value is the
radionuclide specific activity of a source that, if not under control,
could cause severe deterministic effects for a range of scenarios that
include both external exposure from an unshielded source and internal
exposure following dispersal of the source material.
6. Why are the requirements limited to these 16 radionuclides?
The Radiation Source Protection and Security Task Force, an
interagency task force established by the EPAct, concluded in its 2006
report to Congress and the President (ADAMS ML062190349) that the
appropriate radioactive sources were being protected and that the IAEA
Code of Conduct serves as an appropriate framework for considering
which sources warrant additional protection. The Task Force did note
that the U.S. Government should periodically reevaluate the list of
radionuclides that warrant additional security and protection.
Therefore, the radionuclides and thresholds could change in the future
and any changes would be addressed in a future rulemaking.
7. What is the sum of fractions methodology or unity rule?
The sum of fractions methodology, also known as the unity rule, is
used to determine if a licensee would be required to implement 10 CFR
part 37 requirements. A licensee may need to implement the requirements
in 10 CFR part 37 even if it does not possess any single source or
single radionuclide in excess of the category 2 thresholds. For
combinations of materials (to include sealed sources, unsealed sources,
and bulk material) and radionuclides, a licensee must include multiple
sources (including bulk material) of the same radionuclide and multiple
sources (including bulk material) of different radionuclides to
determine if the requirements apply. For the purposes of this
calculation, licensees would be required to consider all of the
radioactive material at a facility. The following formula for the unity
rule would be used to determine if a licensee is required to implement
the Part 37 requirements: [(total amount of radionuclide A) / (category
2 threshold of radionuclide A)] + [(total amount of radionuclide B) /
(category 2 threshold of radionuclide B)] + etc.....>= 1. If the sum is
greater than or equal to 1, the licensee would have at least a category
2 quantity of radioactive material, and the 10 CFR part 37 requirements
would apply at that facility.
8. Does the NRC plan to issue guidance on these proposed requirements?
Yes, the NRC plans to issue guidance on the security requirements
for category 1 and category 2 quantities of radioactive materials. The
guidance will be made available for public comment sometime during the
comment period for this proposed rule. The NRC is planning to host at
least one public workshop on the guidance documents. A separate
document announcing the availability of the guidance and the
information on the workshop will be published in the Federal Register.
9. Will all of the information considered to be safeguards information
under the orders now be made public?
No. The orders issued to some licensees contained detailed security
information that could be useful to an adversary. To increase public
awareness and participation, the NRC identified the primary security
concepts behind each security measure and included these concepts in
the proposed rule to allow discussion of the security
[[Page 33907]]
measures in a public forum. But the specific measures that a licensee
puts in place may be considered SGI-M. The final rule on safeguards
information became effective on February 23, 2009 (73 FR 63546; October
24, 2008), and established as SGI-M certain physical protection
information related to panoramic and underwater irradiators that
possess greater than 370 TBq (10,000 Ci) of byproduct material in the
form of sealed sources; manufacturers and distributors of items
containing source material, byproduct material, or special nuclear
material in greater than category 2 quantities; and transportation of
source, byproduct, or special nuclear material in greater than or equal
to category 1 quantities. Physical protection information for other
facilities that fall under the requirements of 10 CFR part 37 would be
considered physical protection information under 10 CFR 2.390(d)(1).
Licensees would also be required to protect the security plan and
implementing information from unauthorized disclosure. The rule
provisions that address SGI-M or include references to the SGI-M
requirements in part 73 are reserved for the NRC and are considered
compatibility category NRC.
10. What is the authority for this proposed rule?
As noted in the background discussion, the NRC issued some orders
under its authority to protect the common defense and security and some
orders under its authority to protect the public health and safety.
With respect to whether the following regulations are being issued
under ``public health and safety'' or ``common defense and security,''
it should be recognized that almost all regulations relating to the
security of materials serve both purposes to some degree. For example,
securing radioactive materials with multiple barriers protects the
public health and safety by preventing the unknowing theft of
radioactive materials--such as someone stealing a vehicle with material
stored in the vehicle but whose target is the vehicle--which could
result in the unintentional exposure of members of the public to the
material. The barriers also protect the common defense and security by
preventing the theft of the radioactive material by potential
terrorists or others targeting the specific material intending to use
it to affect the common defense and security by exposing members of the
public to the material. However, the designation of the authority being
used for these regulations does have significance in determining
whether Agreement States or the NRC will be responsible for overseeing
the implementation of these requirements for Agreement State licensees.
Although the NRC relinquishes its regulatory authority to Agreement
States for certain materials, under Section 274(m) of the AEA no such
agreement will affect the authority of the Commission to take
regulatory action to protect the common defense and security. Thus, as
evidenced by orders issued to Agreement State licensees after the
events of September 11, 2001, the NRC always has the ability to take
necessary steps to address particular common defense and security
needs. If these regulations were to be issued under the NRC's common
defense and security authority, only the NRC would have the authority
to impose these requirements on Agreement State licensees and the NRC
would be responsible for inspection and enforcement of these
requirements for Agreement State licensees.
When regulations such as these complement both the NRC's public
health and safety and common defense and security missions, the
operative question is whether NRC oversight is necessary to fulfill the
common defense and security aspects of the regulations. The NRC
believes that the Agreement States can consistently and adequately
implement the physical protection requirements on a nationwide basis,
and as such, there will be no need for independent NRC action to
protect the common defense and security. The NRC has regular oversight
of individual Agreement State programs through its Integrated Materials
Performance Evaluation Program (IMPEP). As always, the NRC retains the
authority under Section 274(m) to take any necessary actions for
protection of the common defense and security should individual
licensees or State programs develop issues requiring immediate action.
The Commission also has the authority under Section 274(j) to terminate
or suspend all or part of its agreement with a State and reassert the
Commission's licensing and regulatory authority when the Commission
determines that doing so is necessary to protect the public health and
safety. The failure of an individual Agreement State to implement
compatible and adequate legally binding requirements to protect
radioactive materials within its jurisdiction disrupts the entire
national scheme to protect radioactive materials such that it might
raise serious public health and safety or common defense and security
concerns that the NRC would have to address. As long as all Agreement
States continue to implement compatible and adequate security
requirements, there appears to be no benefit to the public health and
safety, or common defense and security, that would justify removing
oversight of these requirements from an established regulatory program
overseeing Agreement State licensees. Implementing these regulations
under the NRC's public health and safety authority would avoid
potential complications with licensees being subject to dual regulation
for a single activity. Thus, the NRC is proposing to issue these
regulations under its public health and safety authority, and these
requirements will be applicable to Agreement State licensees through
the Agreement State Program.
11. When would the rule be effective?
The NRC is recommending that the final rule be effective 270 days
after publication in the Federal Register. This would provide time for
licensees to put in place the necessary programs, develop procedures,
and conduct training on the new requirements. While most of the
provisions are similar to those contained in the orders, there are
differences. The Agreement States would be required to issue compatible
requirements within 3 years. Licensees in an Agreement State would
continue to operate under the orders or other legally binding
requirements until the Agreement State issues compatible requirements.
The provisions put in place for the inspection of licensees in
Agreement States that received the orders issued under common defense
and security would remain in place until the Agreement State implements
the requirements. For those States that entered into 274i Agreements,
the State would continue inspections under the Agreement. For those
States that did not enter into 274i Agreements, the NRC would continue
to conduct the inspections until the State puts in place the new
requirements. The NRC would rescind the orders as the regulatory
requirements become effective.
12. How does the NRC ensure licensees are following these rules?
The NRC and Agreement States conduct inspections to ensure that
licensees are following the requirements. The NRC and Agreement State
inspectors have received training and follow inspection procedures on
how to ascertain whether licensees are meeting security requirements.
Potential violations that are identified will be processed in
accordance with the NRC Enforcement Policy, and depending on the
severity of a violation, licensees could be subject to civil or
criminal
[[Page 33908]]
penalties. Additionally, the NRC has developed enforcement guidance to
ensure consistency in the enforcement process. Agreement State
licensees would be subject to the State's enforcement process.
13. What should I consider as I prepare my comments to the NRC?
Tips for preparing your comments--when submitting your comments,
remember to:
i. Identify the rulemaking (RIN 3150-AI12, NRC-2008-0120).
ii. Explain why you agree or disagree; suggest alternatives and
substitute language for your requested changes.
iii. Describe any assumptions and provide any technical information
and/or data that you used.
iv. If you estimate potential costs or burdens, explain how you
arrived at your estimate in sufficient detail to allow for it to be
reproduced.
v. Provide specific examples to illustrate your concerns, and
suggest alternatives.
vi. Explain your views as clearly as possible.
vii. Make sure to submit your comments by the comment period
deadline identified.
viii. The NRC is particularly interested in your comments
concerning the following issues in Section II: (1) Item B5 of this
document contains a request for comment on whether the reviewing
official should be fingerprinted as part of the trustworthiness and
reliability determination; (2) item B8 contains a request for comment
on the elements of the background investigation; (3) item C6 contains a
request for comment on the protection of information; (4) item C15
contains a request for comment on the need to notify the LLEA before
working at a temporary jobsite; (5) item C17 contains a request for
comment on vehicle disabling requirements for mobile sources; (6) item
C19 contains a request for comment on the reporting requirements; (7)
item D4 contains a request for comment on requiring license
verification before transferring category 2 quantities of radioactive
material; and (8) item D21 contains a request for comment on requiring
an NRC-approved monitoring plan for the classification yard for rail
shipment. In addition, Section V of this document contains a request
for comment on the compatibility designations for the proposed rule;
Section VI contains a request for comment on the use of plain language;
Section VIII contains a request for comment on the environmental
assessment; Section IX contains a request for comment on the
information collection requirements; Section X contains a request for
comment on the draft regulatory analysis; and Section XI contains a
request for comment on the impact of the proposed rule on small
businesses.
B. Background Investigations and Access Authorization Program
1. Who would be required to have an access authorization program?
Any licensee that is authorized to possess category 1 or category 2
quantities of radioactive materials at a facility would need to
determine whether it needs to have an access authorization program. The
licensee would be required to submit information to the NRC concerning
its compliance with the access authorization program requirements. The
information should include a statement that the licensee is or is not
implementing an access authorization program. The statement should not
include details of the licensee's access authorization program or
implementing procedures. Only those licensees that permit unescorted
access to category 1 or category 2 quantities of radioactive material
would be required to establish and implement an access authorization
program. In addition, any applicant for a license or license amendment
to possess category 1 or category 2 quantities of radioactive material
at a facility would be required to establish an access authorization
program before obtaining the radioactive material.
2. What is the objective of the access authorization program?
The main objective of the access authorization program is to ensure
that individuals who have unescorted access to category 1 or category 2
quantities of radioactive material are trustworthy and reliable and do
not constitute an unreasonable risk to the public health and safety or
common defense and security.
3. Who would be subject to the licensee's access authorization program?
The EPAct authorizes the Commission to require fingerprinting of
any individual who is permitted unescorted access to ``any radioactive
material that the Commission determines to be of such significance to
the public health and safety or the common defense and security as to
warrant fingerprinting and background checks.'' The Commission has
determined that the threshold that warrants fingerprinting and
background checks is category 2. Therefore, individuals subject to a
licensee's access authorization program would include anyone permitted
to have unescorted access to category 1 or category 2 quantities of
radioactive material. Unescorted access would be defined as solitary
access to category 1 or category 2 quantities of radioactive material
granted to an approved individual, and includes solitary access to
sufficient quantities of radioactive material such that an individual
could successfully accumulate lesser quantities of material into a
category 1 or category 2 quantity. This would be an individual at the
licensee's facility who has access to various locations within the
licensee's facility and does not address the situation where a
contractor might have access to the facilities of several licensees.
The access authorization program would also include individuals
that have access to SGI-M, such as vehicle drivers and accompanying
individuals for road shipments of category 1 quantities of radioactive
material, movement control center personnel for shipments of category 1
quantities of radioactive material, and any individual whose assigned
duties provide access to shipment information on category 1 quantities
of radioactive material. In response to comments on the preliminary
rule language, the NRC added text to clarify that ``access to shipping
information'' referred to shipping information that was considered to
be SGI-M and not all shipping information.
Those individuals who have unescorted access to certain quantities
of byproduct material could pose a threat to the public health and
safety or the common defense and security because they could divert or
steal risk-significant radioactive material, or could aid others in the
commission of such acts. The Radiation Source Protection and Security
Task Force encouraged the NRC to require fingerprinting and Federal
criminal history checks of any individual with access to category 1 or
category 2 quantities of radioactive material.
Certain categories of individuals would be relieved from the
background investigation aspect of the access authorization program
(see Section II, question B20 and B21). Licensees do have the option to
escort an individual and not make a trustworthiness and reliability
determination. The escorts would need to be approved for unescorted
access.
In response to comments on the preliminary rule language, the NRC
removed a restriction that would prohibit a licensee from granting
unescorted access to anyone that had been previously denied unescorted
[[Page 33909]]
access. The NRC agreed that this was too limiting as information upon
which a denial is based could change, and the individual could be
unfairly denied access in the future.
4. What are the key access authorization program requirements?
The key components of an access authorization program would be the
reviewing official, the informed consent of the subject individual,
personal history disclosure by the subject individual, a background
investigation, use of procedures, and the individual's right to correct
and complete the information on which the decision to grant unescorted
access is based. Each of these areas is discussed in more detail in the
following questions and answers.
5. What is the role of the reviewing official?
The reviewing official would be the individual that makes the
trustworthiness and reliability determinations for the licensee; the
reviewing official determines who could be granted unescorted access
authorization. Note that the Increased Control Fingerprinting Orders
referred to a trustworthiness and reliability official or T&R official
as the individual that made determinations on an individual's
trustworthiness and reliability. Unlike the reviewing official the T&R
official did not have to be fingerprinted and was not reviewed by the
regulator. Licensees would need to nominate one or more individuals to
be a reviewing official and submit their fingerprints to the NRC. The
fingerprints of the nominated individual(s) would need to be taken by
either a law enforcement agency, a Federal or State agency that
provides fingerprinting services to the public, or a commercial
fingerprinting service authorized by a State to take fingerprints.
Before sending the nominated individual's fingerprints to the NRC, the
licensee would need to conduct the rest of the elements of the
background investigation. Reviewing officials must be permitted either
access to safeguards information or unescorted access to category 1 or
category 2 quantities of radioactive material since Section 149 of the
Atomic Energy Act only authorizes the collection of fingerprints for
the purposes of unescorted access or access to safeguards information.
The Commission has requested statutory changes to the Atomic Energy Act
that would permit fingerprints of reviewing officials without requiring
access for these purposes. The NRC would then transmit the nominated
reviewing official's fingerprints to the FBI and would review the
individual's criminal history records and, if appropriate, approve the
reviewing official. Reviewing officials would not be able to make
trustworthiness and reliability determinations until approved by the
NRC. For certain licensees, the NRC may have already approved reviewing
officials, either under the October 17, 2006, orders [(EA-06-248, 71 FR
63043; October 27, 2006), (EA-06-250, 71 FR 53046; October 27, 2006),
and (EA-06-249; 71 FR 62303; October 24, 2006)], under the August 21,
2006, SGI-M orders, or under other regulatory requirements. In those
cases, the reviewing official may continue to act in that capacity for
an expanded set of persons. If the reviewing (or T&R) official has not
had an FBI criminal records history check, he or she would need to be
fingerprinted and receive NRC approval before making additional
trustworthiness and reliability determinations. The NRC believes that
it is important that the individual who is making the final
determination on whether an individual is trustworthy and reliable be
trustworthy and reliable themselves and have undergone the same
background investigation as individuals who would be granted unescorted
access, including fingerprinting and the FBI criminal records check. If
the reviewing official is not fingerprinted, a gap could be created in
the security program that could potentially be exploited. The NRC is
specifically requesting comment on this aspect of the proposed access
authorization program. In developing comments on this issue, consider
the following questions:
(1) Does the reviewing official need to be fingerprinted and have a
FBI criminal records check conducted?
(2) Are the other aspects of the background investigation adequate
to determine the trustworthiness and reliability of the reviewing
official?
(3) Are there other methods that could be used to ensure that the
reviewing official is trustworthy and reliable?
(4) Does the requirement to fingerprint the reviewing official
place too large of a burden on the licensee?
(5) Do Agreement States have the necessary authority to conduct
reviews of the nominated individual's criminal history record?
6. What is informed consent?
Informed consent is the authorization provided by an individual
that allows a background investigation to be conducted to determine
whether the individual is trustworthy and reliable. The signed consent
would include authorization to share personal information with other
individuals or organizations as necessary to complete the background
investigation. An individual would be able to withdraw his or her
consent at any time. After the withdrawal, the licensee would not be
able to initiate any elements of the background investigation that were
not in process at the time of the withdrawal of consent. The licensee
would be required to inform the individual that withdrawal of consent
for the background investigation would be sufficient cause for denial
or termination of unescorted access authorization.
Licensees do not need to obtain signed consent from individuals
that have already undergone a background investigation that included
fingerprinting and an FBI criminal history records check, been
determined to be trustworthy and reliable, and permitted unescorted
access to category 1 or category 2 quantities of radioactive material
under the NRC orders or the legally binding requirements issued by the
Agreement States. A signed consent would be needed for any
reinvestigation.
In response to comments on the preliminary rule language, the NRC
removed provisions for retention of background investigation
information if the individual withdraws consent. If the individual
later seeks unescorted access, the background investigation information
collected during the original attempt could no longer be relied on, and
the investigation would need to be restarted. Requiring the
preservation of this information would place an unnecessary burden on
licensees.
7. What is a personal history disclosure?
The personal history disclosure is the personal history required to
be provided by the individual seeking unescorted access to category 1
or category 2 quantities of radioactive material. The information would
include items such as employment history, education, credit history
(including bankruptcies), and any arrest record. This information would
provide the reviewing official with a starting point for the background
investigation. Failure to provide the information or falsification of
any information could be grounds for denial of the individual's request
for unescorted access authorization or termination of access if the
individual already has access. If the individual provides false
information, it could be an indication that he or she is not
trustworthy or reliable.
[[Page 33910]]
8. What are the components of a background investigation?
A background investigation includes several components:
Fingerprinting and an FBI identification and criminal history records
check; verification of true identity; employment history evaluation;
verification of education; credit history evaluation; criminal history
review; and character and reputation determination.
It is the licensee's responsibility to make a trustworthiness and
reliability determination of an employee, contractor, or other
individual who would be granted unescorted access to category 1 or
category 2 quantities of radioactive material or a device containing
such radioactive material. It is expected that licensees will use their
best efforts to obtain the information required to conduct a background
investigation to determine an individual's trustworthiness and
reliability.
The full credit history evaluation reflects the Commission's intent
that all financial information available through credit reporting
agencies is to be obtained and evaluated as part of the trustworthiness
and reliability evaluation. The Commission recognizes that some
countries may not have routinely accepted credit reporting mechanisms.
Therefore, the Commission allows reviewing officials to use multiple
sources of credit history that could potentially provide information
about a foreign national's financial record and responsibility.
Fingerprinting an individual for a FBI criminal history records
check is an important element of the background investigation. It can
provide comprehensive information regarding an individual's recorded
criminal activities within the U.S. and its territories and the
individual's known affiliations with violent gangs or terrorist
organizations.
The background investigation is a tool to determine whether
individuals are trustworthy and reliable and could be permitted
unescorted access to category 1 or category 2 quantities of radioactive
material. It is essential to ensure that individuals seeking unescorted
access to radioactive material are dependable in judgment, character,
and performance, such that unescorted access to category 1 or category
2 quantities of radioactive material by that individual does not
constitute an unreasonable risk to the public health and safety or
common defense and security.
The NRC is specifically inviting comment on the elements of the
background investigation. Please consider the following questions in
developing comments:
(1) Is a local criminal history review necessary in light of the
requirement for a FBI criminal history records check?
(2) Does a credit history check provide valuable information for
the determination of trustworthiness and reliability?
(3) Do the Agreement States have the authority to require a credit
history check as part of the background investigation?
(4) What are the appropriate elements of a background investigation
and why are any suggested elements appropriate?
(5) Are the elements of the background investigation too subjective
to be effective?
(6) How much time does a licensee typically spend on conducting the
background investigation for an individual?
9. Where does a licensee submit the fingerprints for processing?
Under the EPAct, licensees are required to submit the fingerprints
to the NRC, which forwards the fingerprints to the FBI for processing.
If an individual comes under one of the relief categories specified in
10 CFR 37.29, the licensee would not need to submit the individual's
fingerprints to the NRC.
10. What should a licensee do if an individual or entity contacted as
part of a background investigation refuses to respond?
If a previous employer, educational institution, or any other
entity fails to provide information or indicates an inability or
unwillingness to provide information in a timely manner, the licensee
would be required to document the refusal, unwillingness, or inability
to respond in the record of investigation. The licensee would then need
to obtain confirmation from at least one alternate source that has not
been previously used. In response to comments on the preliminary rule
language, the NRC revised the rule language to provide more flexibility
to licensees as to what would be considered a timely manner.
11. Does an individual have the right to correct his or her criminal
history records?
Yes, an individual has the right to correct his or her criminal
history records before any final adverse determination is made. If the
individual believes that his or her criminal history records are
incorrect or incomplete in any respect, he or she can initiate
challenge procedures. These procedures would include direct application
by the individual challenging the criminal history records to the law
enforcement agency that contributed the questioned information.
Before an adverse determination on a request for unescorted access,
individuals have the right to provide additional information.
12. Is a licensee required to have procedures for conducting background
investigations?
Yes, licensees would be required to develop, implement, and
maintain written procedures for conducting the background
investigations. Procedures would address notification of individuals
denied unescorted access authorization and would also