Physical Protection of Irradiated Reactor Fuel in Transit, 62695-62716 [2010-25392]
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Federal Register / Vol. 75, No. 197 / Wednesday, October 13, 2010 / Proposed Rules
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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,
or 301–415–4737, or by e-mail to
PDR.Resource@nrc.gov. The draft Part
37 implementation guidance is available
electronically under ADAMS Accession
Number ML101470684.
Federal Rulemaking Web site: Public
comments and supporting materials
related to the implementation guidance,
including the draft implementation
guidance, can be found at https://
www.regulations.gov by searching on
Docket ID NRC–2010–0194. Documents
related to the proposed rule can be
found by searching on Docket ID NRC
2008–0120.
Discussion
The NRC published a proposed rule
that would place the security
requirements for use of Category 1 and
Category 2 quantities of radioactive
material into a new Part 37 of Title 10
of the Code of Federal Regulations. The
proposed rule was published on June
15, 2010 (75 FR 33902) and the public
comment period runs through October
13, 2010. The public comment period
for the proposed rule is being extended
to January 18, 2011, by separate notice.
Documents related to the proposed rule
can be found at https://
www.regulations.gov by searching on
Docket ID NRC 2008–0120.
In conjunction with the proposed
rule, the NRC has developed
implementation guidance. The
implementation document provides
guidance to a licensee or applicant for
implementation of proposed 10 CFR
Part 37, ‘‘Physical Protection of
Byproduct Material,’’ specifically
Category 1 and Category 2 quantities of
radioactive material. It is intended for
use by applicants, licensees, Agreement
States, and NRC staff. The document
describes methods acceptable to the
NRC staff for implementing proposed 10
CFR Part 37. The approaches and
methods described in the document are
provided for information only. Methods
and solutions different from those
described in the document are
acceptable if they meet the requirements
in proposed 10 CFR Part 37. The
guidance is provided in the form of
questions and answers on the provisions
of the proposed rule. The draft
implementation guidance document for
proposed 10 CFR Part 37 is available
electronically under ADAMS Accession
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strengthen the regulations governing the
security of spent nuclear fuel shipments
against malevolent acts.
DATES: The comment period expires
January 11, 2011. Submit comments
specific to the information collection
aspects of this rule by November 12,
2010. Comments received after this date
will be considered if practical to do so,
but the NRC is able to assure
consideration only for comments
received on or before this date.
ADDRESSES: Please include Docket ID:
NRC–2009–0163 in the subject line of
your comments. For instructions on
submitting comments and accessing
documents related to this action, see
Dated at Rockville, Maryland, this 29th day Section I, ‘‘Submitting Comments and
of September 2010.
Accessing Information’’ in the
SUPPLEMENTARY INFORMATION section of
For the Nuclear Regulatory Commission.
this document. You may submit
Mark Thaggard,
comments by any one of the following
Deputy Director, Division of
methods.
Intergovernmental Liaison and Rulemaking,
Federal Rulemaking Web site: Go to
Office of Federal and State Materials and
https://www.regulations.gov and search
Environmental Management Programs.
for documents filed under Docket ID:
[FR Doc. 2010–25784 Filed 10–12–10; 8:45 am]
NRC–2009–0163. Address questions
BILLING CODE 7590–01–P
about the NRC dockets to Carol
Gallagher 301–492–3668; e-mail
Carol.Gallager@nrc.gov.
NUCLEAR REGULATORY
Mail comments to: Secretary, U.S.
COMMISSION
Nuclear Regulatory Commission,
10 CFR Part 73
Washington, DC 20555–0001, ATTN:
Rulemakings and Adjudications Staff.
RIN 3150–AI64
E-mail comments to:
[NRC–2009–0163]
Rulemaking.Comments@nrc.gov. If you
do not receive a reply e-mail confirming
Physical Protection of Irradiated
that we have received your comments,
Reactor Fuel in Transit
contact us directly at (301) 415–1966.
Hand deliver comments to: 11555
AGENCY: Nuclear Regulatory
Rockville Pike, Rockville, Maryland
Commission.
20852, between 7:30 a.m. and 4:15 p.m.
ACTION: Proposed rule.
during Federal workdays. (Telephone
301–415–1966)
SUMMARY: The U.S. Nuclear Regulatory
Fax comments to: Secretary, U.S.
Commission (NRC) is proposing to
Nuclear Regulatory Commission at 301–
amend its security regulations
415–1101.
pertaining to the transport of irradiated
FOR FURTHER INFORMATION CONTACT:
reactor fuel (for purposes of this
rulemaking, the terms ‘‘irradiated reactor Cardelia Maupin, Office of Federal and
State Materials and Environmental
fuel’’ and ‘‘spent nuclear fuel’’ (SNF) are
Management Programs, U.S. Nuclear
used interchangeably). This proposed
Regulatory Commission, Washington,
rule would establish generically
applicable security requirements similar DC 20555–0001, Telephone 301–415–
2312, e-mail: Cardelia.Maupin@nrc.gov.
to those previously imposed by
Commission orders issued after the
SUPPLEMENTARY INFORMATION:
terrorist attacks of September 11, 2001.
I. Submitting Comments and Accessing
The proposed rule would establish the
Information
acceptable performance standards and
II. Background
objectives for the protection of spent
III. Discussion
A. What action is the NRC taking in this
nuclear fuel shipments from theft,
rule?
diversion, or radiological sabotage. The
B. Why revise the requirements?
proposed amendments would apply to
C. What is requested by the State of Nevada
those licensees authorized to possess or
in its petition for rulemaking (PRM–73–
transport spent nuclear fuel. The
10)?
proposed security requirements would
D. What are the DOT routing requirements
also address, in part, a petition for
for spent nuclear fuel shipments?
rulemaking from the State of Nevada
E. What are the NRC routing requirements
(PRM–73–10) that requests that NRC
for spent nuclear fuel shipments?
Number ML101470684, and can also be
found at https://www.regulations.gov by
searching on Docket ID: NRC–2010–
0194.
On July 14, 2010 (75 FR 40756), the
NRC noticed the availability of the
implementation guidance for public
comment. The public comment period
for this guidance was to have expired on
November 12, 2010. The NRC received
several requests to extend the comment
period to January 15, 2011. Due to the
size and complexity of the draft
implementation guidance and the
associated proposed rule, the NRC has
decided to extend the comment period
until January 18, 2011.
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F. Why do the NRC and DOT routing
requirements differ for spent nuclear fuel
shipments?
G. Why require procedures and training for
the security of spent nuclear fuel in
transit?
H. Why require a telemetric position
monitoring system or an alternative
tracking system for continuous
monitoring of spent nuclear fuel
shipments?
I. Why pre-plan and coordinate spent
nuclear fuel shipments?
J. Why require constant visual surveillance
by armed escort?
K. Why require two-way redundant
communication capabilities?
L. Why require background investigations?
M. Why enhance shipment notifications to
NRC?
N. Which type of spent nuclear fuel does
DOE ship?
O. What is a non-classified shipment of
spent nuclear fuel and what are the DOE
requirements for this type of shipment?
P. How are the NRC and DOE requirements
similar and how are they different?
Q. Who would this action affect?
R. Does NRC plan to issue guidance on
these proposed requirements?
S. What should I consider as I prepare my
comments to NRC?
IV. Discussion of the Proposed Amendments
by Section
V. Criminal Penalties
VI. Agreement State Compatibility
VII. Plain Language
VIII. Voluntary Consensus Standards
IX. Finding of No Significant Environmental
Impact: Availability
X. Paperwork Reduction Act Statement
XI. Public Protection Notification
XII. Regulatory Analysis
XIII. Regulatory Flexibility Certification
XIV. Backfit Analysis
I. Submitting Comments and Accessing
Information
Comments submitted in writing or in
electronic form will be posted on the
NRC Web site and on the Federal
rulemaking Web site https://
www.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.
You can access publicly available
documents related to this document
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, Room
O–1 F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland.
NRC’s Agencywide Document Access
and Management System (ADAMS):
Publicly available documents created or
received at 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
the 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, or 301–415–4737, or by
e-mail to PDR Resource.
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–2009–
0163.
Document
PDR
ADAMS
Web
Environmental Assessment .................................................
Regulatory Analysis ............................................................
PRM–73–10 ........................................................................
X
X
X
ML092710448 ....................................................................
ML102710278 ....................................................................
ML092540603 ....................................................................
X
X
X
II. Background
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A. Pre-September 11, 2001
On June 15, 1979 (44 FR 34466), NRC
published an interim final rule in the
Federal Register that established its first
requirements for the physical protection
of spent nuclear fuel in transit. The
interim final rule added 10 CFR 73.37,
‘‘Requirements for Physical Protection of
Irradiated Reactor Fuel in Transit’’ to 10
CFR part 73. After considering public
comments, the Commission affirmed the
interim final rule on June 3, 1980 (45 FR
37399).
The current § 73.37 has changed little
since its promulgation in 1980. These
regulations require licensees to establish
a physical protection system for spent
nuclear fuel shipments that meets the
following objectives: (1) Minimize the
possibilities for radiological sabotage of
spent nuclear fuel shipments, especially
within heavily populated areas, and (2)
facilitate the location and recovery of
spent nuclear fuel shipments that may
have come under the control of
unauthorized persons. The regulation
also provides for: (1) The early detection
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and assessment of attempts to gain
unauthorized access to or control over
spent nuclear fuel shipments, (2) the
notification to the appropriate response
forces of any sabotage events, and (3)
the impeding of attempts at radiological
sabotage of spent nuclear fuel shipments
in heavily populated areas or attempts
to illicitly move such shipments into
heavily populated areas.
Other NRC regulations support the
protection of spent nuclear fuel in
transit. The regulations in § 73.72,
‘‘Requirement for Advance Notice of
Shipment of Formula Quantities of
Strategic Special Nuclear Material,
Special Nuclear Material of Moderate
Strategic Significance, or Irradiated
Reactor Fuel’’ require licensees to notify
NRC in advance about shipments of
spent nuclear fuel. The regulations in
10 CFR part 71, ‘‘Packaging and
Transportation of Radioactive Material,’’
establish requirements for packages
used to transport spent nuclear fuel.
This proposed rule would consider
and address, in part, a petition for
rulemaking submitted by the State of
Nevada. By a letter dated June 22, 1999,
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the State of Nevada submitted a petition
for rulemaking requesting that NRC
strengthen its regulations governing the
security of spent nuclear fuel shipments
against malevolent acts. The NRC
docketed the petition on July 13, 1999,
as Docket No. PRM–73–10 (PRM–73–
10). The NRC published a notice of
receipt of petition and a request for
public comment on September 13, 1999
(64 FR 49410). The Commission review
of this petition was tabled following the
terrorist attacks of September 11, 2001.
The petition was denied, in part, by the
NRC on December 7, 2009 (74 FR
64012). This proposed rulemaking
would consider and address the
remaining requests for the NRC
rulemaking made in PRM–73–10.
B. Post-September 11, 2001
Although the current § 73.37 has
changed little since its promulgation in
1980, there have been significant
changes in the threat environment. The
terrorist attacks of September 11, 2001,
heightened concerns about the use of
risk-significant radioactive materials in
a malevolent act. After the terrorist
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attacks of September 11, 2001, the NRC
issued a series of security-related orders
to specific licensees. In the area of spent
nuclear fuel transit security, the orders
were issued to licensees who shipped or
received, or were planning to ship or
receive, spent nuclear fuel. The orders
were issued as immediately effective
under the NRC’s authority to protect the
common defense and security under the
Atomic Energy Act of 1954, as amended
(AEA). The requirements established by
the orders supplement the existing
regulatory requirements. These
additional security requirements are
primarily intended to ensure that spent
nuclear fuel is shipped in a manner that
protects the common defense and
security, and the public health and
safety.
C. Current Regulatory Framework
About two thousand NRC regulated
shipments of spent nuclear fuel have
been made throughout the United States
since the 1970s. The primary objective
of these shipments has been to move
spent nuclear fuel to interim storage.
These spent fuel shipments are
generally divided into two categories:
commercial shipments or DOE managed
spent nuclear fuel shipments.
Commercial spent nuclear fuel
shipments are from the NRC-licensed
facilities such as commercial nuclear
power reactors, research and test
reactors, and facilities for nondestructive testing and analysis of spent
nuclear fuel. The DOE-managed
shipments involve shipments to DOE
owned interim spent nuclear fuel
storage facilities.
The safe and secure shipment of spent
nuclear fuel requires coordination and
collaboration between various Federal,
State, Tribal and local government
agencies. These organizations work
together to create an orderly pattern for
shipments of spent nuclear fuel.
1. What is the role of NRC in spent
nuclear fuel transit? Generally, the NRC
regulates the design and construction of
spent nuclear fuel shipping containers
for domestic and foreign packages used
to transport spent nuclear fuel solely
within the United States. Although DOT
is the lead government agency
responsible for the approval of export
and import packages, it relies on the
NRC’s evaluation as the basis for
approval of these packages. In addition,
NRC regulates the physical protection of
commercial spent nuclear fuel in transit
against sabotage or other malicious acts,
which is recognized in the DOT routing
regulations in 49 CFR 397.101. The NRC
requirements in 10 CFR Part 73 are
applied to shipments of spent nuclear
fuel from the NRC licensees.
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2. What is the role of DOT in spent
nuclear fuel transit? The DOT regulates
the transportation of hazardous
materials, including spent nuclear fuel
in interstate and intrastate commerce.
Generally, DOT regulates in
consultation with NRC the carriers of
spent nuclear fuel and the conditions of
transport, such as routing, handling and
storage incident to transport, and
vehicle and driver requirements. The
DOT also regulates the labeling,
classification, and marking of all spent
nuclear fuel packages and transport
vehicles.
3. What is the role of DOE? For over
50 years, DOE has transported spent
nuclear fuel to interim storage facilities.
These spent nuclear fuel shipments
have originated from the following: (1)
Foreign research reactors; (2) DOEowned research and defense reactors,
and (3) nuclear powered U.S. Navy
ships. In addition, on a few rare
occasions, the DOE has accepted some
spent nuclear fuel from commercial
nuclear power plants, e.g., Three Mile
Island Unit 2, for storage at its facilities.
The DOE managed shipments of spent
nuclear fuel, unless designated as a
national security shipment, are
conducted under requirements
equivalent to those of DOT and NRC.
The DOE complies with the DOT
highway section criteria and carrier
safety provisions. The DOE spent
nuclear fuel packages are required to
meet the NRC design and performance
criteria in 10 CFR part 71, which is also
stated in the DOT regulations in 49 CFR
173.7(d). Spent nuclear fuel shipments
made by DOE or the DOE contractors are
not subject to the NRC physical
protection requirements because DOE is
not a NRC licensee. DOE’s policy,
however, is that DOE managed spent
nuclear fuel shipments meet or exceed
NRC physical protection requirements.
4. What is the role of State, local, and
Tribal governments? State, local and
Tribal governments play an important
role in the safe and secure transport of
spent nuclear fuel. They assist in route
planning and, for many shipments,
provide armed escorts. They enforce the
DOT highway safety regulations,
including the performance of shipment
inspections. State, local, and Tribal
governments are also responsible for
providing the first line of government
response to accidents and incidents
within their jurisdiction.
III. Discussion
A. What action is NRC taking in this
rule?
The NRC is proposing amendments to
its regulations to enhance the security
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requirements that apply to the
transportation of spent nuclear fuel.
This proposed rulemaking would
establish generically applicable security
requirements similar to those previously
imposed by Commission orders issued
after the terrorist attacks of September
11, 2001. The proposed rulemaking
would also add several new
requirements not derived directly from
the security order requirements, but
developed as a result of insights gained
by performing security assessments of
potential security vulnerabilities
associated with spent nuclear fuel in
transit. Also, the proposed rulemaking
would address, in part, the requests for
the NRC rulemaking raised by PRM–73–
10.
The proposed requirements would
establish acceptable performance
objectives for the protection of spent
nuclear fuel in transit from sabotage,
theft, or diversion for malevolent use.
These requirements would ensure that
spent nuclear fuel is shipped in a
manner that protects the common
defense and security, and public health
and safety.
B. Why revise the requirements?
After the attacks of September 11,
2001, NRC re-evaluated its security
requirements for spent nuclear fuel in
transit. From this effort, additional
measures were identified that would
improve security. The additional
security measures deemed immediately
necessary were issued as orders and
supplemented existing regulations. The
orders are not publically available,
because they contain detailed security
requirements that are designated as
Safeguards Information (SGI). The
proposed revisions are based on the
NRC efforts undertaken since the events
of September 11, 2001, including
issuance of additional security
requirements by orders, insights gained
from implementation of the orders, and
insights gained by performing security
assessments of potential security
vulnerabilities associated with spent
nuclear fuel transportation. The
proposed revisions also reflect portions
of the State of Nevada’s Petition for
Rulemaking (PRM–73–10). The NRC
intends to rescind the security orders
provided the final rule adequately
addresses the security requirements set
forth in those orders. Rescission will be
addressed in the notice of final
rulemaking.
C. What is requested by the State of
Nevada in its petition for rulemaking
(PRM–73–10)?
By a letter dated June 22, 1999, the
State of Nevada submitted a rulemaking
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petition (docketed as PRM–73–10)
requesting that NRC initiates
rulemaking to strengthen its regulations
for the physical protection of spent
nuclear fuel shipments against
radiological sabotage and terrorist acts.
The NRC published a notice of receipt
of petition and a request for public
comment on September 13, 1999 (64 FR
49410). The Commission review of this
petition was tabled following the
terrorist attacks of September 11, 2001.
In PRM–73–10, Nevada requested that
NRC: (1) Clarify the meaning of the term
‘‘hand-carried equipment’’ in 10 CFR
73.1(a)(1)(i)(D); (2) clarify the definition
of the term ‘‘radiological sabotage’’ in 10
CFR 73.2 to include actions against
spent nuclear fuel shipments which are
intended to cause a loss of shielding,
release of radioactive materials or cause
economic damage or social disruption,
regardless of the success or failure of the
action; (3) amend the advance route
approval requirements in 10 CFR
73.37(b)(1)(vi) to require shippers and
carriers of spent nuclear fuel to identify
primary and alternative routes which
avoid heavily populated areas; (4)
require armed escorts along the entire
road shipment route by eliminating the
differential based on population in 10
CFR 73.37(c); (5) require armed escorts
along the entire rail shipment route by
eliminating the differential based on
population in 10 CFR 73.37(d); (6)
amend 10 CFR 73.37(b) by adopting
additional planning and scheduling
requirements for spent nuclear fuel
shipments that are the same as those
required for formula quantities of
special nuclear material by 10 CFR
73.26(b); (7) amend 10 CFR 73.37(d) to
require that rail shipments of spent
nuclear fuel be made in dedicated
trains; and (8) conduct a comprehensive
assessment of the consequences of
terrorist attacks that have the capability
of radiological sabotage.
In this proposed rulemaking, the NRC
will consider the above items raised in
PRM–73–10, except for the first and
eighth items, namely, clarification of the
meaning of the term ‘‘hand-carried
equipment’’ and the conducting of a
comprehensive assessment of the
consequences of terrorist attacks that
have the capability of radiological
sabotage. Rulemaking on the first and
eighth items of PRM–73–10 was denied
by the NRC on December 7, 2009 (74 FR
64012). The remaining items are
addressed below:
PRM–73–10, Item 2: Clarify the
definition of the term ‘‘radiological
sabotage’’ in § 73.2, ‘‘Definitions,’’ and
amend it to expressly include
‘‘deliberate actions which cause, or are
intended to cause economic damage or
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social disruption regardless of the extent
to which public health and safety are
actually endangered by exposure to
radiation.’’
The NRC considers that the existing
definition already encompasses actions
of the type described by the Petitioner.
However, NRC agrees that clarification
may be useful. The NRC is addressing
this petition item by clarifying the
definition of radiological sabotage in the
supporting guidance document
associated with the proposed rule.
PRM–73–10, Item 3: Amend the
advance route approval requirements in
10 CFR 73.37(b)(7) to ‘‘specifically
require shippers and carriers to identify
primary and alternative routes which
minimize highway and rail shipments
through heavily populated areas.’’ Also,
as part of this request, PRM–73–10
stated that NRC should consider
adopting the route selection criteria in
NUREG–0561, Physical Protection of
Shipments of Irradiated Reactor Fuel in
Transit, as part of the regulations, and
specifically require shippers and
carriers to minimize use of routes which
fail to comply with the route selection
criteria.
The NRC considered incorporating
the route selection criteria of NUREG–
0561 into the proposed rule, but
determined that implementing such
criteria may cause conflicts with the
DOT requirements. Sections D through
F below provide additional information
about the differences between DOT and
NRC routing criteria. The PRM–73–10
request for the adoption of routing
criteria from NUREG–0561 was
considered by the NRC and determined
to be not appropriate.
The PRM–73–10 also requested that
NRC amend its regulations to minimize
highway and rail shipments through
heavily populated areas. The NRC is
addressing the goal of minimizing spent
nuclear fuel shipments through heavily
populated areas in the proposed
rulemaking. The proposed revisions to
10 CFR 73.37 would require licensees to
preplan and coordinate their shipments
with the affected States. This issue is
discussed below under ‘‘Why Require
Shipment Preplanning and
Coordination with States?’’ Combining
the NRC proposed requirements, which
include State involvement in licensees’
planning activities, with the
requirements of DOT is expected to
minimize movement of spent nuclear
fuel through heavily populated areas.
PRM–73–10, Items 4 and 5: The
current regulations, § 73.37(c) and (d),
for road and rail shipments,
respectively, require armed escorts in
heavily populated areas, but not in other
areas along the route. PRM–73–10
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requested that NRC eliminate these
differential armed escort requirements
based upon population for both road
and rail spent nuclear fuel shipments.
Proposed §§ 73.37(c) and (d) include
these PRM–73–10 requests. The
differentiation of security requirements
based upon population causes potential
areas of vulnerability along the
shipment route for theft, diversion, or
radiological sabotage. The proposed rule
would require that the same security
requirements for heavily populated
areas apply along the entire route for
road and rail shipments, and at any U.S.
ports where vessels carrying spent fuel
shipments are scheduled to stop.
PRM–73–10, Item 6: Amend § 73.37(b)
by adopting additional planning and
scheduling requirements for spent
nuclear fuel shipments that are the same
as those required for formula quantities
of special nuclear material by § 73.26(b).
The regulations in § 73.26(b) require
that shipments be scheduled to avoid
delays and stops, and to ensure timely
delivery of the shipment.
The NRC agrees that improvements
are needed in the planning and
coordination of shipments and has
addressed this concern in the proposed
amendment. This issue is discussed
below under ‘‘Why Require Shipment
Preplanning and Coordination with
States?’’
PRM–73–10, Item 7: Amend § 73.37(d)
to require that all spent nuclear fuel rail
shipments be made in dedicated trains.
The same NRC security requirements
would apply to a spent nuclear fuel rail
shipment, regardless of whether the
shipment was made using a dedicated
train or a mixed-use train. In either case,
the licensee making the shipment would
be required to ensure that the security
protection measures (both hardware and
personnel) required by the NRC’s
regulations would be present to provide
the requisite high assurance of
protection of public health and safety
and the common defense and security
during the entire duration of the
shipment. The NRC considers the same
level of security will be obtained
regardless of whether the shipment is
made in a dedicated train or mixed-use
train. Thus, this item is not addressed
as a part of the proposed rule.
The NRC invites comments on its
proposed disposition of items 2 through
7 of PRM–73–10 as part of its
consideration of this proposed rule.
Comments should be sent to the address
listed under the ADDRESSES heading of
this document. The PRM–73–10 is
available at ADAMS Accession Number:
ML092540603 and the NRC’s September
13, 1999, notice of receipt of petition
and request for public comments (64 FR
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49410) is available on the Federal
Register’s Web site, https://www.
gpoaccess.gov/fr/.
D. What are the DOT routing
requirements for spent nuclear fuel
shipments?
The DOT has various terms to define
and categorize radioactive material
within the Title 49 of the Code of
Federal Regulations. Within their
definitions, DOT includes a category for
highway route controlled quantity
(HRCQ) which is defined as a quantity
of radioactive material within a single
package that exceeds: (a) 3,000 times the
A1 value of the radionuclides for special
form material or 3,000 times the A2
values of the radionuclides for normal
form material; or (b) 1,000 TBq (27,000
curies), whichever is less. The HRCQ
shipments can be made by all modes of
transport. Spent nuclear fuel shipments
fall under the DOT’s definition of
HRCQ.
For shipments by road, the DOT
requirements for routing radioactive
material are found in 49 CFR Parts 172
(Subpart I—Safety and Security Plans)
and 397 (Subpart D—Routing of Class 7
(Radioactive) Materials). The DOT
highway routing requires carriers to (1)
Ensure routes are chosen based on
minimizing radiological risk; (2)
consider available information on
accident rates, transit time, population
density and activities, and the time of
the day and the day of the week during
which transportation will occur to
determine the level of radiological risk;
and (3) instruct the driver about the
route and the hazards of the shipment.
Furthermore, under the DOT
requirements, HRCQ are transported
only over preferred routes (i.e., the
Interstate Highway System, an
alternative route designated by a State
routing agency, or both), or an Interstate
Highway System bypass or beltway
around a city when available, unless a
State routing agency has designated an
alternative route. Routes can only be
designated after substantive
consultation with affected local
jurisdictions and with any other affected
States to ensure consideration of all
impacts and continuity of affected
routes. A written route plan is to be
prepared by the carrier and provided to
drivers and shippers.
The DOT allows motor carriers and
drivers some deviation from the
preferred route when picking up or
delivering material, making necessary
rest, fuel or motor vehicle repair stops,
or because emergency conditions make
continued use of the preferred route
unsafe or impossible. In addition, a
person may transport irradiated reactor
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fuel only in compliance with a plan that
will ensure the physical security of the
material. The DOT permits variation for
security purposes from the routing
requirements of 49 CFR 397.101 only so
far as necessary to meet the
requirements imposed under such a
plan, or otherwise imposed by NRC in
10 CFR Part 73.
For shipments by rail, the DOT
requirements for routing radioactive
material are found within 49 CFR parts
172, 174 and 209. The DOT requires rail
carriers to compile annual data on
certain shipments of hazardous
materials, including HRCQ. The data is
used to analyze safety and security risks
along rail routes where those materials
are transported; assess alternative
routing options; and make routing
decisions based on those assessments.
Rail carriers must assess the available
routes ensuring, at a minimum, that 27
specific factors are considered. These 27
factors include, but are not limited to,
consideration of rail traffic density,
transit times, number and types of grade
crossings, proximity to iconic targets,
population densities and venues along
the route.
Rail carriers must also seek relevant
information from State, local, and Tribal
officials, as appropriate, regarding
security risks to high-consequence
targets along or in proximity to a route
used by a rail carrier to transport
security-sensitive materials. Oversight is
provided by the DOT Federal Railroad
Administration (FRA), which includes
review and inspection of rail carrier’s
risk analyses and route selection, but
FRA does not pre-approve rail routes. If
FRA determines that a carrier’s route
selection documentation and underlying
analyses are deficient, the carrier may
be required to revise the analyses or
make changes in the route selection. In
addition, if it is determined by DOT that
a particular route chosen by the railroad
is not the safest and most secure
practicable route available, FRA can
require the use of an alternative route
until such time as the identified
deficiencies for the originally chosen
route are corrected by the railroad.
E. What are the NRC routing
requirements for spent nuclear fuel
shipments?
For spent fuel in quantities greater
than 100 grams and exceeding 1 Sv (100
rems) per hour at a distance of 0.91
meters (3 feet) from any accessible
surface without intervening shielding,
licensees are required to transport such
spent nuclear fuel along routes that have
been pre-approved by NRC.
Furthermore, the proposed rule text of
§ 73.37(b)(1) requires licensees to
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preplan and coordinate their routes with
the States, including identification of
safe havens.
The proposed rule does not include
specific routing criteria for licensees to
use when developing routes. However,
the objective of § 73.37 is to minimize
the potential for theft, diversion, or
radiological sabotage for shipments of
spent nuclear fuel. Licenses are
expected to develop routes by
considering criteria including, but not
limited to: the DOT routing criteria,
minimizing transit time, likelihood of
swift response by local law
enforcement, availability of safe havens
(for road shipments), avoidance of
tactically disadvantageous positions,
availability of appropriate rest and
refueling stops (for road shipments), and
availability of good transportation safety
features. When selecting a route by road,
licensees are also expected to conduct
surveys of the proposed route. The
objective of these surveys is to locate
safe havens, evaluate communications
capability along the route, develop local
law enforcement contacts, identify food
and fuel stops for the carrier, and
identify potential driving problems
along the route.
Once a spent nuclear fuel shipment
route request is received, the NRC
reviews it closely. The NRC conducts a
detailed review, considering route
length and minimizing transit time,
local law enforcement and emergency
response contact information, adequacy
of safe haven locations, and
communications capability along the
route. NUREG–0561, ‘‘Physical
Protection of Shipments of Irradiated
Reactor Fuel’’ provides guidance to
licensees seeking the NRC-approval of a
spent nuclear fuel shipping route.
F. Why do the NRC and DOT routing
requirements differ for spent nuclear
fuel shipments?
The objective of § 73.37 is to
minimize the potential for theft,
diversion or radiological sabotage of
spent nuclear fuel shipments; facilitate
the location and recovery of spent fuel
shipments that may have come under
the control of unauthorized persons;
and delay and impede attempts at theft,
diversion or radiological sabotage of
spent nuclear fuel shipments until
response forces arrive. With this in
mind, NRC expects licensees to route
shipments according to the DOT
requirements, and to consider the
adequacy of the route to meet the
objectives of § 73.37. This includes
considering the availability and
adequacy of safe havens along the route
and the communications capabilities
among the transport vehicle, escort
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vehicle, communications center, and
local law enforcement agencies (LLEAs)
for the entire route.
The DOT HRCQ routing regulations
for road shipments are based on
minimizing radiological risk to the
public (49 CFR 397). The HRCQ are to
be transported over preferred routes
which are described in more detail in
question D above. Carriers are permitted
to deviate from preferred routes for
certain conditions including, but not
limited to: security reasons (e.g., as
imposed by NRC in 10 CFR Part 73) and
emergencies. The DOT rail routing
requirements for HRCQ require carriers
to consider both safety and security of
the public when selecting a route (49
CFR 172 and 209). The DOT requires
rail carriers to select routes based on the
criteria described above in question D.
Rail carriers must assess the available
routes using, at a minimum, 27 factors
that address both safety and security of
the transport.
As long as there is coordination
among the licensee, the commercial
carrier and the States of passage, NRC
determined that spent nuclear fuel
shipment primary and alternate routes
for highway and rail can be developed
that satisfy both the DOT and NRC
requirements and guidelines. The NRC
invites comments on the challenges of
selecting routes for spent nuclear fuel
that meets both the DOT and NRC
requirements and guidance.
jlentini on DSKJ8SOYB1PROD with PROPOSALS
G. Why require procedures and training
for the security of spent nuclear fuel in
transit?
The proposed §§ 73.37(b)(3)(v) and
(b)(4) would expressly require that
licensees shipping spent nuclear fuel
develop normal and contingency
procedures. These procedures would
cover notifications; communication
protocols; loss of communication; and
responses to actual, attempted, or
suspicious activities. The proposed
revisions would also require drivers,
accompanying personnel, railroad
personnel, and other movement control
personnel to be adequately trained in
normal and contingency procedures.
These proposed requirements would
ensure that all personnel associated
with the shipment are prepared to
prevent the theft, diversion, or
radiological sabotage of spent nuclear
fuel shipments. The proposed revisions
would address, in part, PRM–73–10
items (3) and (6).
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H. Why require a telemetric position
monitoring system or an alternative
tracking system for continuous
monitoring of spent nuclear fuel
shipments?
The current rule, at § 73.37(b)(4),
requires that the licensee’s physical
protection plan include a
communications center, which will be
staffed continuously by at least one
individual who will monitor the
progress of the spent fuel shipment. The
proposed rule would reflect the
availability of new technology and as
such, the ability to have more active
control over the shipment by the
licensee. The proposed § 73.37(b)(3)(i)
would replace the term
‘‘communications center’’ with the term
‘‘movement control center.’’ The
proposed § 73.37(b)(3)(ii) would also
require that the movement control
center be staffed continuously by at
least one individual, who will actively
monitor the progress of the spent
nuclear fuel shipment and who has the
authority to direct the physical
protection activities. The proposed
§ 73.37(b)(3)(iii) would specify that the
movement control center must monitor
the shipment continuously, i.e., from
the time of delivery of the shipment to
the carrier for transport until safe
delivery of the shipment at its final
destination, and must immediately
notify the appropriate agencies in the
event of a safeguards event under the
provisions of § 10 CFR 73.71.
In addition, the proposed
§§ 73.37(c)(5) and 73.37(d)(4), for road
and rail shipments respectively, would
require movement control centers to use
a telemetric position monitoring system
or an alternative tracking system to
monitor the location and status of
shipments at all times, which would
provide a real time indication of any
potential threats. 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. Global positioning
systems (GPS) and radiofrequency
identification (RFID) are examples of
telemetric position monitoring systems.
Since the movement control center is
required to respond to any actual,
attempted, or suspicious activities, the
proposed requirements would mitigate
the likelihood of theft, diversion, or
radiological sabotage of spent nuclear
fuel shipments.
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I. Why pre-plan and coordinate spent
nuclear fuel shipments?
The current regulations require
limited shipment preplanning and
coordination with NRC, States, and
LLEAs. For example, the current
§ 73.37(f) regulation requires an advance
notification to the Governor (or
designee) by mail to be postmarked at
least 7 days before transport of a
shipment within or through the State;
and require a messenger-delivered
notification to reach the Office of the
Governor (or designee) at least 4 days
before transport of a shipment within or
through the State. Some States have
indicated that the current notification
requirements are insufficient to
adequately plan for a spent nuclear fuel
shipment. In addition, the current
§ 73.37(b)(7) regulation requires
licensees to obtain the advance NRC
approval of the routes used for road and
rail shipments of spent nuclear fuel, but
does not require prior State
coordination of the route. The proposed
amendments would ensure that the
affected States have early and
substantial involvement in the
management of spent nuclear fuel
shipments by participating in the initial
stages of the planning, coordination,
and implementation of the shipment.
Proposed § 73.37(b)(1)(iv) would
require licensees to preplan and
coordinate spent nuclear fuel shipment
information with the Governors of the
States which the shipment will transit
across in order to: (1) Ensure minimal
shipment delays; (2) arrange for State
law enforcement escorts; (3) coordinate
movement control information, as
needed; (4) coordinate safe haven
locations; and (5) coordinate the
shipping route. The proposed
requirements would ensure that no
unusual event associated with the
shipment goes unnoticed or unreported.
These proposed revisions mitigate the
risk of theft, diversion, or radiological
sabotage of a spent nuclear fuel
shipment. These proposed revisions
would address, in part, PRM–73–10
items 3 and 6.
J. Why require constant visual
surveillance by armed escort?
Existing § 73.37(b)(9) requires
constant visual surveillance by an escort
when a shipment is stopped. It does not
specify whether the escort should be
armed. Proposed § 73.37(b)(3)(vii)(C)
would ensure that when a shipment is
stopped, at least one armed escort
maintains constant visual surveillance.
The constant surveillance by an armed
escort while a shipment is stopped
provides assurance that attempts by an
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adversary to either perform radiological
sabotage in place, or to gain control of
the transport to move it to another
location are impeded or stopped. The
requirements of proposed
§ 73.37(b)(3)(vii)(C) would address
parked or stopped road shipments, rail
shipment stops in marshaling areas, and
docked sea shipments. It would also
require periodic reports of shipment
status to the movement control center
by the armed escort. The proposed
§ 73.37(b)(3)(vii)(C) would provide
adequate assurance that spent nuclear
fuel shipments are protected from theft,
diversion, or radiological sabotage when
stopped.
jlentini on DSKJ8SOYB1PROD with PROPOSALS
K. Why require two-way redundant
communication capabilities?
The regulations in the current
§§ 73.37(c), 73.37(d), and 73.37(e)
provide for redundant communication
capabilities; however, the requirements
are specific, i.e., use of citizens band
radio and radiotelephone. In view of the
continued advancements in technology,
these methods of communication could
become obsolete in the near future.
Instead of specifying an acceptable
communications technology, the
proposed revisions describe the
performance characteristics of the
communications capabilities.
Proposed §§ 73.37(c)(3), 73.37(d)(3)
and 73.37(e)(4) would require the
establishment of two-way
communication capabilities for the
transport vehicle and escorts to ensure
contact between the movement control
center and LLEAs at all times. The
revisions would also require the
establishment of alternate capabilities
for the transport vehicle and escorts to
contact the movement control center.
The alternate communications cannot
be subject to the same interference
factors. The same interference factors
are defined as any two systems that rely
on the same hardware or software to
transmit their signal (e.g., cell tower,
proprietary network). These
requirements would provide the
capability for continued communication
between movement control personnel,
which would ensure the prompt
reporting of any incident that could lead
to theft, diversion, or radiological
sabotage.
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L. Why require background
investigations?
1. What is the objective of the
background investigations requirements
for those with unescorted access and
access authorization relative to spent
nuclear fuel in transit?
The proposed rule would add a new
§ 73.38 that would require licensees to
conduct background investigations of
those individuals being considered for
unescorted access or access
authorization relative to spent nuclear
fuel in transit. The main objective of the
background investigations is to ensure
that those individuals who have
unescorted access to spent nuclear fuel
in transit and those individuals who
have access to safeguards information
relative to the spent nuclear fuel
shipment, including but not limited to
armed escorts, drivers, and movement
control personnel are trustworthy and
reliable and do not constitute an
unreasonable risk to the public health
and safety or common defense and
security. These background
investigations are similar to those
already in place for unescorted access to
a commercial nuclear power reactor in
§ 73.56(d), Background Investigation.
2. What is the basis for the
fingerprinting requirements in the
proposed rule?
Section 149 of AEA requires that any
person who is permitted unescorted
access to radioactive materials subject to
regulation by the Commission be
fingerprinted for FBI identification and
criminal history records check.
However, Section 149 also requires that
the Commission make a determination
that such radioactive material is of such
significance to the public health and
safety or the common defense and
security as to warrant fingerprinting and
background checks before the
Commission can exercise the authority
provided by Section 149.
Pursuant to Section 149, the
Commission has determined that the
transportation of irradiated fuel (spent
nuclear fuel) is of such significance to
the public health and safety or the
common defense and security as to
warrant fingerprinting and background
checks for those individuals who have
such access to the materials in transit.
Persons who have ‘‘unescorted access’’
to this material for purposes of Section
149, are persons accompanying the
shipment of spent nuclear fuel during
transit who have direct access and
maintain control over the spent nuclear
fuel. These persons may include, but are
not limited to, the driver armed escorts
and movement control center personnel.
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Therefore, under the authority granted
by Section 149, this rule would impose
a requirement for fingerprinting as a
prerequisite to granting unescorted
access to spent nuclear fuel in transit.
The criminal history records check
obtained as a result of that
fingerprinting would be used by
licensees as part of the overall
background investigation to determine
the trustworthiness and reliability of
these individuals prior to permitting
unescorted access.
3. What are the components of a
background investigation?
Proposed § 73.38(d) lists the
requirements for a background
investigation, including: informed
consent, fingerprinting for an FBI
identification and criminal history
records check; verification of true
identity; employment history
evaluation; verification of education and
military history; credit history
evaluation; local criminal history
review; and character and reputation
determination.
Under proposed § 73.38(e), it is the
licensee’s responsibility to make a
trustworthiness and reliability
determination of an individual who has
unescorted access or access
authorization relative to a spent nuclear
fuel shipment. It is expected that
licensees will use their best efforts to
obtain the information required to
conduct a background investigation to
determine the individuals’
trustworthiness and reliability.
The full credit history evaluation
requirement, in proposed § 73.38(d)(6),
reflects the NRC’s intent that all
financial information available through
credit reporting agencies is to be
obtained and evaluated because it has
the potential to provide highly pertinent
information. The NRC recognizes that
some countries may not have routinely
accepted credit reporting mechanisms,
and therefore, the NRC allows multiple
sources of credit history that could
potentially provide information about a
foreign national’s financial record and
responsibility.
Fingerprinting an individual for an
FBI criminal history records check, as
would be required by the proposed
§ 73.38(d)(3), is an important element of
the background investigation for
determining the trustworthiness and
reliability of an individual. 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. In addition, the
local criminal history review, which
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would be required by the proposed
§ 73.38(d)(7) provides the licensee with
a record of local criminal activity that
may adversely impact an individual’s
trustworthiness and reliability.
It is noted that the proposed
§ 73.38(d)(5)(iv) would require licensees
to document any refusals by outside
entities to provide information on an
individual. If local law enforcement, a
previous employer, an 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 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. An
alternate source could be another person
associated with the entity or institution.
For example, if the human resources
department of a company will not verify
the employment history of the
individual, an alternate source could be
the individual’s supervisor during the
claimed period. The proposed
§ 73.38(d)(10) is patterned after the
requirements of § 73.56(d)(4)(iv).
jlentini on DSKJ8SOYB1PROD with PROPOSALS
4. What information should the licensee
use to determine that an individual is
trustworthy and reliable?
The licensee 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 licensee may not determine that an
individual is trustworthy and reliable
and grant them unescorted access to
spent nuclear fuel in transit until all of
the information for the background
investigation has been obtained and
evaluated. The licensee may deny an
individual unescorted access based on
any information obtained at any time
during the background investigation.
The proposed § 73.38(e) includes a
provision for licensees to document
their determinations of trustworthiness
and reliability.
5. How frequently would a
reinvestigation be required?
The proposed rule would include a
provision, § 73.38(h), that would require
a reinvestigation every 10 years to help
maintain the integrity of the program.
This reinvestigation requirement 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
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trustworthiness and reliability. The
reinvestigation would include
fingerprinting, FBI identification and
criminal history records check, local
criminal history review and credit
history check. The reinvestigation
would not include employment
verification, education verification,
military history verification, or the
character and reputation determination
for the reinvestigation.
6. Are licensees required to protect
information obtained during a
background investigation?
Yes. The proposed §§ 73.38(f)(1)–(2)
would require licensees to protect the
information obtained during a
background investigation. Licensees
would only be permitted to disclose the
information to the subject individual,
the individual’s representative, those
who have a need-to-know to perform
their assigned duties to grant or deny
unescorted access, or an authorized
representative of NRC. This proposed
revision is consistent with the
requirements of § 73.57(f).
7. Could a licensee transfer personal
information obtained during an
investigation to another licensee?
Yes. The proposed § 73.38(f)(3)
includes a provision that 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.
8. Which records are required to be
maintained?
The proposed § 73.38(f)(5) would
require licensees 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 spent
nuclear fuel in transit.
M. Why enhance shipment notifications
to NRC?
The current regulations in
§ 73.72(a)(4) require an NRC
notification, by phone, at least 2 days
before the shipment commences. The
proposed rule would revise § 73.72(a)(4)
to require 2 additional notifications of
NRC, one to be made 2 hours before the
shipment commences, and the other to
be made when the shipment reaches its
final destination. These additional
notifications allow NRC to monitor
spent nuclear fuel shipments, and to
maximize its readiness in case of a
safeguards event. The notification of
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shipment completion allows NRC to
resume normal operations.
To further enhance notification of
NRC, the proposed revision would
remove the § 73.72(b) exemption for
shipments of spent nuclear fuel that are
transported on public roads. Currently,
the requirements of § 73.72(b) exempt
licensees who make a road shipment or
transfer with one-way transit times of
one hour or less between installations of
the licensee from providing advance
notification of the shipment to NRC.
The proposed revision would require
that NRC be informed of any spent
nuclear fuel shipment on a public road
so that NRC is able to monitor spent
nuclear fuel shipments and to maximize
its readiness in case of a safeguards
event. These proposed revisions
mitigate the risk of theft, diversion, or
radiological sabotage of a shipment.
N. Which type of spent nuclear fuel does
DOE ship?
The DOE spent nuclear fuel
shipments generally fall into two
categories: Classified and non-classified
shipments of spent nuclear fuel.
Classified shipments are those
shipments which involve national
security. Classified shipments of spent
nuclear fuel typically consist of spent
fuel from the U.S. Navy. The DOE has
broad authority under the Atomic
Energy Act of 1954, as amended (AEA),
to regulate all aspects of activities
involving radioactive materials that are
undertaken by DOE or on its behalf,
including the transportation of
radioactive materials. The DOE
conducts classified shipments of spent
nuclear fuel using their Office of Secure
Transport (OST). The OST shipments
are escorted full-time by armed,
specially trained (trained in
communications, firearms, tactics,
observation, and use of deadly force)
active duty Navy personnel who
maintain 24-hour surveillance. The OST
Transportation Emergency
Communications Center monitors,
tracks, and provides communication
with every shipment. The NRC does not
regulate classified shipments of spent
nuclear fuel.
O. What is a non-classified shipment of
spent nuclear fuel and what are the
DOE requirements for this type of
shipment?
Non-classified shipments of spent
nuclear fuel typically consist of spent
fuel from commercial nuclear power
reactors and research and test reactors.
The DOE policy for non-classified spent
nuclear fuel shipments are found under
the DOE Orders 460.1C, Packaging and
Transportation Safety and 460.2A,
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jlentini on DSKJ8SOYB1PROD with PROPOSALS
Departmental Materials Transportation
and Packaging Management. As a
matter of policy, the DOE non-classified
spent nuclear fuel shipments are
conducted under the requirements and
standards applicable to comparable
commercial shipments, i.e., the NRC
requirements, except if there is a
determination that national security or
another critical interest requires
different action.
The DOE requirements are set forth in
the DOE Manual 460.2–1A, Radioactive
Material Transportation Practices
Manual. In this manual, it states that
‘‘Security will be provided in
compliance with the NRC requirements
in 10 CFR Part 73 for shipments subject
to a NRC license. Other DOE shipments
will be undertaken in a manner that
meets or exceeds the NRC security
requirements.’’ The DOE organizations
and contractors ensure that in-transit
requirements are addressed, including
developing security plans,
implementing information and physical
security access controls, training,
escorts, inspections, tracking,
communications, and employee
background checks.
P. How are the NRC and DOE
requirements similar and how are they
different?
As stated in O above, given the DOE
policy to ‘‘meet or exceed’’ the NRC
security requirements, the NRC and
DOE requirements are similar. Similar
to the NRC requirements, the DOE
program organizations are expected to
liaison with Federal, State, local and
Tribal law enforcement/security
officials regarding such shipments. This
liaison should include a determination
as to whether the State, Tribal or local
jurisdictions are planning to provide
escorts for the shipment. The DOE also
expects drivers and escorts to maintain
constant surveillance of the shipment.
One major difference between the
NRC and DOE requirements deals with
the tracking and monitoring of spent
nuclear fuel shipments. The DOE
requires the use of their Transportation
Tracking and Communications System
(TRANSCOM). In the proposed rule,
NRC requires continuous and active
monitoring of spent nuclear fuel
shipments, but, a particular tracking
method is not specified. The NRC
determined that providing the
performance objectives for continuous
and active monitoring, rather than
specifying a particular system gives a
licensee flexibility to choose a system
that works with their shipping situation.
Another difference between the NRC
and DOE requirements is the protection
of information. For NRC, information
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associated with a spent fuel shipment
(i.e., shipment schedules and security
plans) are protected as safeguards
information (SGI) as specified by the
requirements of §§ 73.21 and 73.22. The
DOE does not have a system of
information protection comparable to
SGI. Shipment information for the DOE
non-classified spent nuclear fuel
shipment is official use only, unless
there is a reason to designate it as
classified.
vii. Make sure to submit your
comments by the comment period
deadline.
viii. See Section VII of the preamble
for the request for comments on the use
of plain language and Section XII for the
request for comments on the draft
regulatory analysis.
Q. Who would this action affect?
The proposed amendments affect all
the NRC licensees that are authorized to
possess and transport spent nuclear
fuel. This includes, but is not limited to,
licensees of commercial power reactors,
research and test reactors, and
independent spent fuel storage
installations, who transport, or deliver
to a carrier for transport, in a single
shipment, a quantity of irradiated
reactor fuel in excess of 100 grams (0.22
lbs) 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 rems) per hour at a distance
of .91 meters (3 feet) from any accessible
surface without intervening shielding.
The proposed rule would revise
§ 73.37(a)(1) to include the International
System of Measurement (SI)
accompanied by the equivalent English
units in parentheses for the weight and
dose rate measurements. This is under
the NRC’s metrication policy (57 FR
46202, October 7, 1992), and the Metric
Conversion Act of 1975, 15 U.S.C. 205a
et seq. The proposed rule would also
add a footnote to clarify that the term
‘‘irradiated reactor fuel,’’ as used in 10
CFR 73.37 fn.1, means ‘‘spent nuclear
fuel.’’
R. Does NRC plan to issue guidance on
these proposed requirements?
In conjunction with this the proposed
rulemaking, NRC is revising NUREG–
0561, ‘‘Physical Protection of Shipments
of Irradiated Reactor Fuel in Transit,’’
which was published in June 1980, to
address the new requirements in the
proposed rule. NUREG–0561 provides
general guidance to licensees
concerning the establishment of an
acceptable security program for spent
nuclear fuel shipments.
S. What should I consider as I prepare
my comments to NRC?
Tips for preparing your comments:
When submitting your comments,
remember to:
i. Identify the rulemaking (Docket ID:
NRC–2009–0163).
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.
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IV. Discussion of the Proposed
Amendments by Section
A. Proposed § 73.37(a)(1)
B. Proposed § 73.37(a)(1)(i)
The language in the current regulation
solely addresses potential radiological
sabotage of spent nuclear fuel
shipments. The proposed rule would
revise § 73.37(a)(1)(i) to clarify that any
attempted theft or diversion of spent
nuclear fuel shipments is also covered
by this regulation.
The proposed rule would also revise
§§ 73.37(a)(1)(i) and (a)(2)(iii) to remove
the distinction between heavily
populated areas and other areas through
or across which a spent nuclear fuel
shipment may pass. The differentiation
of security requirements based upon
population densities creates potential
vulnerabilities in the physical security
of the shipment. The proposed
requirement of armed escorts
throughout the shipment route
minimizes the risk of theft, diversion, or
radiological sabotage. The proposed
revisions would also address items 4
and 5 of the PRM–73–10.
C. Proposed § 73.37(a)(2)
The proposed rule would revise
§ 73.37(a)(2) to insert ‘‘system’’ after the
word phrase ‘‘physical protection’’ to
read as ‘‘physical protection system.’’
This change provides consistency in the
terminology used throughout 10 CFR
Part 73.
The proposed revision would
renumber the paragraphs in
§ 73.37(a)(2). The current
§ 73.37(a)(2)(ii) would become the
proposed § 73.37(a)(2)(iii), and the
current § 73.37(a)(2)(iii) would become
the proposed § 73.37(a)(2)(ii). The
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proposed rule would revise the current
§ 73.37(a)(2)(iii) to clarify that the
licensee should delay, as well as
impede, any attempted theft, diversion,
or radiological sabotage of spent nuclear
fuel shipments.
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D. Proposed § 73.37(b)
This overall section is revised to
provide a logical, step-by-step approach
to the development of a physical
protection system for spent nuclear fuel
shipments that is more user-friendly.
E. Proposed § 73.37(b)(1)
The proposed rule would add a new
section entitled, ‘‘Preplan and
Coordinate Spent Nuclear Fuel
Shipments,’’ which is explained in
further detail below. The proposed rule
would move and incorporate the current
§ 73.37(b)(1) into a new § 73.37(b)(2).
The proposed rule would add a new
§ 73.37(b)(1)(i) which requires that
licensees instruct armed escorts on the
use of deadly force. The existing
provisions of § 73.37 provide
performance objectives to be achieved
by the physical protection system for
spent nuclear fuel shipments. These
performance objectives are not specific
about the degree of force an armed
escort may use in protecting shipments.
Specifically, the licensee is to ensure
that each non-LLEA armed escort delay
or impede attempted acts of theft,
diversion, or radiological sabotage by
using force sufficient to counter the
force directed at that person, including
the use of deadly force when there is a
reasonable belief that the use of deadly
force is necessary in self-defense or in
the defense of others, or any other
circumstances as authorized by
applicable Federal or State law. The
requirements for use of deadly force are
established under applicable Federal
and State laws (i.e., the States through
which the shipment is passing). It
should be noted that the proposed
revision is not authorizing the use of
deadly force, but instead is ensuring
that the armed guards are
knowledgeable of the Federal and State
statutes that apply regarding the use of
deadly force. The statutes regarding the
use of deadly force may vary depending
on the jurisdiction in which the
shipment is located. Armed escorts are
expected to carry out their assigned
duties, including implementation of
contingency procedures in case of
attack, in a manner consistent with the
legal requirements applicable to other
private armed guards in a particular
jurisdiction. The LLEA personnel
escorts are exempt from this
requirement since they are subject to,
and should have received training on,
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State and Federal restrictions regarding
the use of deadly force.
The proposed rule would add new
§§ 73.37(b)(1)(ii) and 73.37(b)(1)(iii),
which are accounting and control
measures that ensure that only
authorized individuals receive the
shipment. The proposed requirements
would reduce the risk of theft,
diversion, or radiological sabotage of the
spent nuclear fuel.
The proposed rule would re-designate
§ 73.37(b)(8) as § 73.37(b)(1)(iv) and
revise it to include requirements for
licensees to preplan and coordinate
spent nuclear fuel shipments with
States. The preplanning and
coordination would include efforts to
minimize intermediate stops and delays,
arranging for State law enforcement
escorts, the sharing of positional
information and the development of
route information, including the
location of safe havens. The proposed
amendments would ensure that States
have early and substantial involvement
in the management of spent nuclear fuel
shipments by participating in the initial
stages of the planning, coordination,
and implementation of the shipment.
The proposed rule would re-designate
§ 73.37(b)(6) as § 73.37(b)(1)(v) and
revise it to make minor editorial
changes.
The proposed rule would re-designate
§ 73.37(b)(7) as § 73.37(b)(1)(vi) and
revise it to expand the requirements for
preplanning and coordination with
NRC. The proposed § 73.37(b)(1)(vi)
would require licensees to identify the
locations of safe havens along road
shipment routes, obtain the NRC route
approval prior to the 10-day advance
notice required by § 73.72(a)(2), and
provide specific information to NRC,
such as identification of the shipper,
consignee, carriers, transfer points,
modes of shipment, and a description of
shipment security arrangements. In
addition the proposed § 73.37(b)(1)(vi)
reminds licensees that they must also
comply with the applicable DOT routing
requirements.
The proposed rule would add a new
§ 73.37(b)(1)(vii), which requires the
documentation of preplanning and
coordination activities.
F. Proposed § 73.37(b)(2)
The proposed rule would re-designate
§ 73.37(f), the advance notifications
provision, as § 73.37(b)(2) and would
revise it to include: (1) A reference to
§ 73.22 SGI protection requirements, (2)
a reference to the NRC Web site listing
contact information for State governors
and governors’ designees, (3) a
requirement to include within the
notification the license number of the
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shipper and receiver, and (4) a
requirement to provide the estimated
date and time of arrival of the shipment
at the destination. The proposed
§ 73.37(b)(2) would also include new
recordkeeping and shipment
cancellation notification requirements.
G. Proposed § 73.37(b)(3)
The proposed rule would add a new
§ 73.37(b)(3) entitled, ‘‘Transportation
Physical Protection Program.’’ The
proposed § 73.37(b)(3) would both
streamline and combine existing
requirements in §§ 73.37(b)(3)–(5) and
73.37(b)(9)–(11).
Proposed § 73.37(b)(3)(i) would
introduce the term ‘‘movement control
center,’’ which replaces the term
‘‘communication center’’ used in the
current regulation. The term ‘‘movement
control center’’ is used for consistency
with physical protection terminology
and to better define the role and
responsibilities of the facility. The
movement control center is defined as
an operations center which is remote
from transport activity and which
maintains periodic position information
on the movement of the shipment,
receives reports of attempted theft,
diversion, or radiological sabotage,
provides a means for reporting these
and other problems to appropriate
agencies, and can request and
coordinate appropriate aid.
The proposed rule would re-designate
§ 73.37(b)(4) as § 73.37(b)(3)(ii) and
revise it to reflect that the movement
control center personnel will have the
authority to direct physical protection
activities. The proposed rule would also
add a new § 73.37(b)(3)(iii), which will
clarify the duties of the movement
control center personnel.
The proposed rule would re-designate
§ 73.37(b)(5) as § 73.37(b)(3)(iv) and
revise it to make minor editorial
changes.
The proposed rule would add a new
§ 73.37(b)(3)(v), which requires
licensees to develop, maintain, and
implement written physical protection
procedures to address access controls,
duties of the movement control center
personnel, drivers, armed escorts and
other individuals responsible for the
security of the shipment, reporting of
safeguards events, communications
protocols, and normal conditions
operating procedures.
The proposed rule would add a new
§ 73.37(b)(3)(vi), which incorporates the
recordkeeping requirements of the
current §§ 73.37(b)(2) and (3).
The proposed rule would re-designate
§ 73.37(b)(10) as § 73.37(b)(3)(vii)(A)
and revise it to include additional
training requirements described in
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sections III and IV of Part 73, Appendix
B. This revision is a clarification of the
existing requirements in § 73.37. The
current § 73.37(b)(10) refers to training
requirements in 10 CFR part 73,
Appendix D. Appendix D, in turn, refers
to requirements in 10 CFR part 73,
Appendix B, III and IV. For clarity, the
proposed revision would add a direct
reference to Appendix B.
The proposed rule would re-designate
§ 73.37(b)(11) as § 73.37(b)(3)(vii)(B) and
revise it by changing the escort’s
requirement to contact the movement
control center from ‘‘at least every 2
hours’’ to contacts at ‘‘random intervals,
not to exceed 2 hours.’’ The proposed
provision would also change
‘‘communications center’’ to ‘‘movement
control center.’’
The proposed rule would re-designate
the current § 73.37(b)(9) as
§ 73.37(b)(3)(vii)(C) and would revise it
by further clarifying the escort’s
responsibilities when the shipment
vehicle is stopped, or the shipment
vessel is docked. The proposed
revisions would ensure that when a
shipment is stationary at least one
armed escort maintains constant visual
surveillance. The proposed rule also
would provide for periodic reports of
shipment status to the movement
control center by the armed escort.
H. Proposed § 73.37(b)(4)
The proposed rule would re-designate
§ 73.37(b)(2) as § 73.37(b)(4)(i)–(iii),
‘‘Contingency and Response
Procedures,’’ and would add additional
requirements. The proposed rule would
add new §§ 73.37(b)(4)(i) and
73.37(b)(4)(ii), which would require
licensees to develop and implement
contingency and response procedures,
and would require licensees to train
personnel in these procedures. The
current requirements in § 73.37(b) do
not specifically require personnel
training, but only require escorts to
receive instructions. The proposed rule
would expressly require that written
procedures are developed and that all
personnel associated with the transport
and security of the shipment are
adequately trained to carry out their
responsibilities. The proposed revisions
provide reasonable assurance of a more
timely and effective response to any
attempted theft, diversion, or
radiological sabotage. A response to an
event must be initiated without delay in
order to have a high probability of
success. The response is more likely to
be timely and effective if roles,
responsibilities, and actions are clearly
delineated and understood in advance.
The proposed rule would also add a
new § 73.37(b)(4)(iii), which would
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incorporate the current § 73.37(b)(2)
recordkeeping requirements.
The proposed rule would re-designate
§ 73.37(b)(3) as § 73.37(b)(4)(iv) and
revise it to include the requirement that
the contingency and response
procedures direct the escort to take the
necessary steps to delay or impede theft,
diversion, or radiological sabotage of
spent nuclear fuel in transit.
I. Proposed § 73.37(c)
The proposed rule would revise
§ 73.37(c)(1) and delete § 73.37(c)(2) to
eliminate the distinction between
heavily populated areas and other areas
through which a road shipment of spent
nuclear fuel shipment may pass.
Proposed § 73.37(c)(1) would require
armed escorts for the entire shipment
route. In addition, a new
§ 73.37(c)(1)(iii) would require nonLLEA armed escorts to have a minimum
of two weapons. The NRC has
determined that it is prudent to require
a minimum of two weapons for each
armed escort.
The proposed deletion of the current
§ 73.37(c)(2) would result in a
renumbering of the section. The
proposed rule would re-designate
current § 73.37(c)(3) as § 73.37(c)(2) and
revise it as described below. The
requirements in the current § 73.37(c)(3)
describe specific acceptable types of
communication devices, i.e., use of
citizens band radio, radiotelephone,
which may become obsolete in the near
future. Instead of specifying an
acceptable communications technology,
the proposed § 73.37(c)(2) revisions
describe the performance characteristics
of the communications capabilities.
The proposed rule would re-designate
§ 73.37(c)(4) as § 73.37(c)(3) and
§ 73.37(c)(5) as § 73.37(c)(4). The
proposed rule would add a new
§ 73.37(c)(5), which would require
continuous and active monitoring of the
shipment by a telemetric position
monitoring system or an alternative
tracking system. The proposed revisions
would ensure that shipments are
continuously and actively monitored by
a tracking system that communicates
continuous position information to a
movement control center. This
requirement would allow the movement
control center to receive positive
confirmation of the location, status, and
control of the shipment. These
requirements would ensure immediate
detection of any deviations from the
authorized route, which will provide a
prompt notification of any emergency or
safeguards event. The proposed
revisions would facilitate a more timely
and effective response.
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J. Proposed § 73.37(d)
The proposed rule would revise
§ 73.37(d)(1) and delete § 73.37(d)(2) to
eliminate the distinction between
heavily populated areas and other areas
through which a rail shipment of spent
nuclear fuel may pass. The proposed
§ 73.37(d)(1) would require armed
escorts for the entire shipment route.
The proposed rule would add a new
§ 73.37(d)(2) to require a minimum of 2
weapons for non-LLEA armed escorts.
The proposed rule would revise
§ 73.37(d)(3), which describes
acceptable types of communication
devices. The NRC recognizes that these
devices may become obsolete in the
near future. Instead of specifying
acceptable communications technology,
the proposed § 73.37(d)(3) describes the
performance characteristics of the
communication capabilities. The
proposed rule would also add a new
§ 73.37(d)(4) which would address
continuous and active monitoring of the
shipment by a telemetric position
monitoring system or an alternative
tracking system.
K. Proposed § 73.37(e)
The proposed rule would revise
§§ 73.37(e)(1) and (e)(2) to eliminate the
distinction between heavily populated
areas and other areas for sea shipments
of spent nuclear fuel. The proposed
§ 73.37(e)(1)(i) would require armed
escorts at any U.S. port where vessels
carrying spent nuclear fuel shipments
are docked. Proposed § 73.37(e)(1)(i)
would also require a minimum of two
weapons for each non-LLEA escort. The
proposed rule would revise § 73.37(e)(3)
to eliminate the listing of
communication devices. Instead of
specifying acceptable communication
technology, proposed § 73.37(e)(3)
would describe the performance
characteristics of the communication
capabilities.
L. Proposed § 73.37(f)
The proposed rule would re-designate
the current § 73.37(f) as § 73.37(b)(2). A
newly proposed § 73.37(f) would require
an immediate investigation if a
shipment is lost or unaccounted for after
the designated no-later-than arrival
time. This proposed requirement would
facilitate the location and recovery of
shipments that may have come under
control of unauthorized persons.
M. Proposed § 73.37(g)
The proposed rule would delete the
reference to § 73.37(f)(3) and insert the
reference to § 73.37(b)(2)(iii) to reflect
the reorganization of § 73.37. It would
also ensure that the final rule for the
‘‘Protection of Safeguards Information’’
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(October 24, 2008, 73 FR 63546) is
reflected in the proposed rulemaking.
Under § 73.22(a), information to be
protected as safeguards information in
the proposed § 73.37 would include: (1)
Schedules, itineraries, arrangements
with LLEA, and locations of safe
havens, which is the information
described in § 73.37(b)(1), and
§§ 73.37(b)(2)(iii)–(b)(2)(v); (2) the
physical security plan, which is the
information described in § 73.37(b)(3);
(3) the procedures for response to
security contingency events, and the
tactics and capabilities required to
defend against attempted theft,
diversion, or sabotage, which is the
information described in § 73.37(b)(4);
and portions of inspection reports,
evaluations, audits, or investigations
that contain details of a licensee’s or
applicant’s physical security system,
which is the information described in
§ 73.37(f). In addition, according to
§ 73.22(a), vehicle immobilization
features, intrusion alarm devices, and
communications systems, including
communication limitations, are also
considered safeguards information.
N. Proposed § 73.38
Proposed § 73.38 would establish the
personnel access authorization
requirements for granting an individual
unescorted access or access
authorization relative to spent nuclear
fuel in transit. Proposed § 73.38(a)(1)
would specify the licensees subject to
the requirements in the proposed
section. Proposed § 73.38(a)(2) would
provide that licensees are required to
establish, implement, and maintain the
overall effectiveness of the access
authorization program. Proposed
§ 73.38(b) would establish the general
performance objective to ensure that the
individuals subject to the access
authorization program are trustworthy
and reliable. Proposed § 73.38(c)(1)
would specify the individuals that
would be subject to the access
authorization program. Proposed
§ 73.38(c)(2) would indicate that
individuals listed in § 73.59 are not
subject to the investigative elements of
the access authorization program.
Proposed § 73.38(d) would establish
the background investigation
requirements for individuals seeking
unescorted access or access
authorization relative to spent nuclear
fuel in transit. For an individual seeking
unescorted access or access
authorization relative to spent nuclear
fuel in transit, proposed §§ 73.38(d)(1)–
(9) would require licensees to conduct
fingerprinting and an FBI identification
and criminal history records check;
verification of true identity;
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employment history evaluation,
verification of education; military
history verification; credit history
evaluation; criminal history review;
character reputation and determination;
and obtain independent information,
respectively. Proposed § 73.38(d)(10)
would allow a licensee to rely upon an
alternate source that has not been
previously used, if the licensee cannot
obtain information on an individual
from their previous employer,
educational institution, or any other
entity with which the individual claims
to have been engaged. Proposed
§ 73.38(d)(10) is patterned after
§ 73.56(d)(4)(iv)(B).
Proposed § 73.38(e) would require
licensees to make and document
trustworthiness and reliability
determinations after obtaining and
evaluating the information required by
§§ 73.38(d)(1)–(9). Licensees would be
required to maintain records of
trustworthiness and reliability for 5
years from the date the individual no
longer requires unescorted access or
access authorization relative to spent
nuclear fuel shipments.
Proposed § 73.38(f) would require
licenses to protect the information
obtained from background
investigations, while allowing licensees
to transfer background information on
an individual to another licensee if the
individual makes a written request for
such transfer. Proposed § 73.38(f) would
allow a licensee to rely on the
background information transferred
from another licensee, provided that the
receiving licensee verifies the name,
date of birth, social security number,
sex, and other applicable physical
characteristics to ensure that the
individual is the person whose file has
been transferred.
A number of individuals who would
be subject to the background
investigation portion of this proposed
rule may have recently satisfied similar
requirements under the prior NRC
orders. For such individuals, it would
be an unnecessary use of resources to refingerprint them. Thus, proposed
§ 73.38(g) would permit persons to
essentially re-use the results of a
fingerprint check that has been created
within 5 years of the effective date of
the rule. This would not be ‘‘relieving’’
such individuals from the rule, but
rather permitting them to satisfy the
fingerprinting requirements by other
means. It is important to emphasize,
however, that a licensee’s ability to use
previous fingerprinting results is not a
substitute for the licensee
independently concluding that the
person is suitable for unescorted access
to spent nuclear fuel in transit,
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including subjecting the person to all
other applicable requirements of the
background investigation that would be
required by § 73.38(d).
Proposed § 73.38(h) would establish
the requirements for reinvestigation of
individuals with unescorted access to
spent nuclear fuel in transit. Proposed
§ 73.38(h) would establish completion
of reinvestigations within 10 years of
the last investigation. The scope of the
investigation would be the past 10 years
and would consist of fingerprinting and
a FBI identification and criminal history
records check; criminal history review;
and credit history re-evaluation.
Proposed § 73.38(i) would establish the
requirements for individuals to selfreport legal actions taken by a law
enforcement authority or court of law to
which the individual has been subject
that could result in incarceration or a
court order or that requires a court
appearance. This paragraph requires the
recipient of the report, if the recipient
is not the reviewing official, to promptly
convey the report to the reviewing
official who will then evaluate the
implications of those actions with
respect to the individual’s
trustworthiness and reliability.
Proposed § 73.38(j) would establish
the requirements that licensees would
be required to develop, implement, and
maintain written procedures for
conducting the background
investigations for persons applying for
unescorted access or access
authorization relative to spent nuclear
fuel in transit. The procedures should
address notification of individuals
denied unescorted access or access
authorization, including the basis for
the denial or termination. The
procedures should also provide for the
review of the information by the
affected individuals. It should also
ensure that individuals who have been
denied unescorted access or access
authorization are not allowed
unescorted access to spent nuclear fuel.
These individuals could be escorted by
an approved individual. These
individuals should not receive access to
safeguards information relative to spent
nuclear fuel in transit.
Proposed § 73.38(k) would establish
the requirements that 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
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information. Proposed § 73.38(l) would
establish the requirements that licensees
retain documentation relative to the
trustworthiness and reliability
determination for 5 years after the
individual no longer requires
unescorted access or access
authorization. The proposed rule would
also require that corrected or new
information be actively communicated
by the recipient to other licensees.
O. Proposed § 73.72(a)(4)
The proposed rule would revise
§ 73.72(a)(4) to require 2 additional
notifications of NRC, 1 to be made 2
hours before the commencement of the
shipment and the other to be made
when the shipment arrives at its final
destination. The current requirements of
§ 73.72 require notification 2 days
before the shipment commences, but not
2 hours before the shipment begins or
when it ends.
P. Proposed § 73.72(a)(5)
The proposed rule would revise
§ 73.72(a)(5) to clarify the meaning of
the language ‘‘greater than ±6 hours’’ that
appears in the section. The proposed
revision deletes ‘‘greater’’ and inserts
‘‘more,’’ and deletes the symbol ‘‘±.’’
Q. Proposed § 73.72(b)
The current requirements in § 73.72(b)
exempt licensees who make a road
shipment or transfer with one-way
transit times of one hour or less between
installations of the licensee from
providing advance notification of the
shipment to NRC. The proposed
amendment would remove this
exemption from the regulations. This
proposed revision would ensure that
NRC is informed of any spent nuclear
fuel shipment on a public road, even
those of short duration, and NRC is
prepared to respond to an emergency or
safeguards event. It would mitigate the
risk of theft, diversion, or radiological
sabotage of a shipment.
TABLE 1—CROSS REFERENCE OF PROPOSED REGULATIONS WITH EXISTING REGULATIONS
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The proposed regulation
Existing regulation
73.37(a)(1) ................................................................................................
73.37(a)(2) ................................................................................................
73.37(b)(1)(i)–(iii) ......................................................................................
73.37(b)(1)(iv)(A) ......................................................................................
73.37(b)(1)(iv)(B) ......................................................................................
73.37(b)(1)(iv)(C) ......................................................................................
73.37(b)(1)(iv)(D) ......................................................................................
73.37(b)(1)(v) ............................................................................................
73.37(b)(1)(vi) ...........................................................................................
73.37(b)(1)(vi)(A) ......................................................................................
73.37(b)(1)(vi)(B) ......................................................................................
73.37(b)(1)(vi)(C) ......................................................................................
73.37(b)(1)(vii) ..........................................................................................
73.37(b)(2) ................................................................................................
73.37(b)(2)(i) .............................................................................................
73.37(b)(2)(ii) ............................................................................................
73.37(b)(2)(iii) ...........................................................................................
73.37(b)(2)(iv) ...........................................................................................
73.37(b)(2)(v) ............................................................................................
73.37(b)(2)(vi) ...........................................................................................
73.37(b)(3)(i) .............................................................................................
73.37(b)(3)(ii) ............................................................................................
73.37(b)(3)(iii) ...........................................................................................
73.37(b)(3)(iv) ...........................................................................................
73.37(b)(3)(v) ............................................................................................
73.37(b)(3)(vi) ...........................................................................................
73.37(b)(3)(vii)(A) .....................................................................................
73.37(b)(3)(vii)(B) .....................................................................................
73.37(b)(3)(vii)(C) .....................................................................................
73.37(b)(4)(i) .............................................................................................
73.37(b)(4)(ii) ............................................................................................
73.37(b)(4)(iii) ...........................................................................................
73.37(b)(4)(iv) ...........................................................................................
73.37(c) .....................................................................................................
73.37(c)(1) ................................................................................................
(none—paragraph deleted) ......................................................................
73.37(c)(2) ................................................................................................
73.37(c)(3) ................................................................................................
73.37(c)(4) ................................................................................................
73.37(c)(5) ................................................................................................
73.37(c)(6) ................................................................................................
73.37(d) ....................................................................................................
73.37(d)(1) ................................................................................................
(none—paragraph deleted) ......................................................................
73.37(d) ....................................................................................................
73.37(d)(2) ................................................................................................
73.37(d)(3) ................................................................................................
73.37(d)(4) ................................................................................................
73.37(e) ....................................................................................................
73.37(e)(1) ................................................................................................
73.37(e)(2) ................................................................................................
73.37(e)(3) ................................................................................................
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73.37(a)(1).
73.37(a)(2).
New (no existing equivalent).
73.37(b)(8).
New (no existing equivalent).
New (no existing equivalent).
New (no existing equivalent).
73.37(b)(6).
73.37(b)(7).
New (no existing equivalent).
73.37(b)(7).
73.37(b)(7).
New (no existing equivalent).
73.37 (b)(1) & 73.37(f).
73.37(f)(1).
73.37(f)(2).
73.37(f)(3).
73.37(f)(4).
73.37(f)(4).
73.70.
New (no existing equivalent).
73.37(b)(4).
73.37(b)(4).
73.37(b)(5).
New (no existing equivalent).
73.37(b)(3).
73.37(b)(10).
73.37(b)(11).
73.37(b)(9).
73.37(b)(2).
73.37(b)(2).
73.37(b)(2).
73.37(b)(3).
73.37(c).
73.37(c)(1).
73.37(c)(2).
New (no existing equivalent).
73.37(c)(3).
73.37(c)(4).
73.37(c)(5).
New (no existing equivalent).
73.37(d).
73.37(d)(1).
73.37(d)(2).
73.37(d).
New (no existing equivalent).
73.37(d)(3).
New (no existing equivalent).
73.37(4).
73.37(e)(1).
New (no existing equivalent).
73.37(e)(2).
Sfmt 4702
62707
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TABLE 1—CROSS REFERENCE OF PROPOSED REGULATIONS WITH EXISTING REGULATIONS—Continued
The proposed regulation
Existing regulation
73.37(e)(4) ................................................................................................
73.37(f) .....................................................................................................
73.37(g) ....................................................................................................
73.38 .........................................................................................................
73.72(a)(1) ................................................................................................
73.72(a)(4)(i)–(iii) ......................................................................................
73.72(a)(5) ................................................................................................
(none—exemption deleted from existing) ................................................
73.72(b) ....................................................................................................
73.37(e)(3).
New—incorporates 73.71 reporting provisions.
73.37(g).
New—incorporates background investigations.
73.72(a)(1).
73.72(a)(4).
73.72(a)(5).
73.72(b).
New (no existing equivalent—new exemption).
jlentini on DSKJ8SOYB1PROD with PROPOSALS
V. Criminal Penalties
For the purpose of Section 223 of the
AEA, the NRC is proposing to amend 10
CFR Part 73 under one or more of
Sections 161b, 161i, or 161o of the AEA.
Willful violations of the rule would be
subject to criminal enforcement.
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 of
this document.
VI. Agreement State Compatibility
Under the Policy Statement on
Adequacy and Compatibility of
Agreement State Programs approved by
the Commission on June 30, 1997, and
published in the Federal Register on
September 3, 1997 (62 FR 46517), this
rule is classified as a Compatibility
Category NRC. The NRC analyzed the
proposed rule under the procedure
established within Part III,
‘‘Categorization Process for the NRC
Program Elements,’’ of Directive
Handbook 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 in this
category are those that relate directly to
areas of regulation reserved to NRC by
the AEA, or the provisions of 10 CFR.
Although an Agreement State may not
adopt program elements reserved to
NRC, it may wish to inform its licensees
of certain requirements via a mechanism
that is consistent with the particular
State’s administrative procedure laws
but does not confer regulatory authority
on the State. The regulation of spent
nuclear fuel is reserved to NRC and
cannot be relinquished to an Agreement
State. Thus, this rulemaking will have
no impact on Agreement States’
regulatory programs. Therefore,
Agreement States will not need to make
conforming changes to their regulations.
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. The NRC is proposing to (1)
Amend § 73.37, which contains the
requirements for the physical protection
of spent nuclear fuel in transit; (2) add
a new § 73.38, which establishes the
requirements for a background
investigation of individuals applying for
unescorted access to spent nuclear fuel
shipments; and (3) amend § 73.72,
which contains the requirements for the
advance notification of NRC of spent
nuclear fuel along with other special
nuclear material. This action does not
constitute the establishment of a
standard that establishes generally
applicable requirements.
VII. Plain Language
The Presidential Memorandum ‘‘Plain
Language in Government Writing,’’
published June 10, 1998 (63 FR 31885),
directed that the Government’s
documents be written in clear and
accessible language. The NRC requests
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VIII. Voluntary Consensus Standards
IX. 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, 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
licensees’ facilities, nor would such
implementation result in any significant
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increase in effluents released to the
environment. Similarly, the
implementation of the proposed rule’s
security requirements would not affect
occupational exposure requirements. No
major construction or other earth
disturbing activities, on the part of
affected licensees, is anticipated in
connection with licensees’
implementation of the proposed rule’s
requirements. The NRC 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 NRC
welcomes public participation.
Comments on any aspect of the
environmental assessment may be
submitted to NRC as indicated under
the ADDRESSES heading in this
document.
The NRC will send a copy of the
environmental assessment and this
proposed rule to every State Liaison
Officer, and will request their comments
on the environmental assessment. The
environmental assessment may be
examined at the NRC Public Document
Room, O–1 F21, 11555 Rockville Pike,
Rockville, MD 20852.
X. 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 for review and approval of
the information collection requirements.
Type of submission, new or revision:
Revision.
The title of the information collection:
10 CFR part 73, ‘‘Physical Protection of
Plants and Materials,’’ The Proposed
Rule.
The form number if applicable: NA.
How often the collection is required:
On occasion.
Who will be required or asked to
report: NRC licensees that are
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Federal Register / Vol. 75, No. 197 / Wednesday, October 13, 2010 / Proposed Rules
authorized to possess and transport
spent nuclear fuel in excess of 100
grams (0.22 lbs) in net weight exclusive
of cladding or other material, which has
a total radiation level in excess of 1 Sv
(100 rems) per hour at a distance of .91
meters (3 feet) from any accessible
surface without regard to any
intervening shielding.
An estimate of the number of annual
responses: 360 (342 responses + 18
recordkeepers).
The estimated number of annual
respondents: 18.
An estimate of the total number of
hours needed annually to complete the
requirement or request: 1,058 (59 hrs
per respondent).
Abstract: The NRC is proposing to
amend its regulations to enhance the
requirements for the safety and security
of spent nuclear fuel during transit and
to make these applicable to all licensees
by placing them in the 10 CFR. The
proposed rulemaking would establish
the minimum performance standards
and objectives for the protection of
spent nuclear fuel shipments from theft,
diversion or radiological sabotage. The
proposed amendments would affect
licensees authorized to possess or
transport spent nuclear fuel.
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 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–1 F21, Rockville, MD 20852. The
OMB clearance package and the
proposed rule are available for 60 days
after the signature date of this notice at
the NRC worldwide Web site: https://
www.nrc.gov/public-involve/doccomment/omb/.
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 November 12,
2010 to the Records and FOIA/Privacy
Services Branch (T–5 F52), U.S. Nuclear
Regulatory Commission, Washington,
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DC 20555–0001, or by Internet
electronic mail to
Infocollects.Resource@NRC.gov and to
the Desk Officer, Office of Information
and Regulatory Affairs, NEOB–10202
(RIN–3150–AI64), 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, Document ID:
NRC–2009–0163. 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.
XI. 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
information collection requirement
unless the requesting document
displays a currently valid OMB control
number.
62709
List of Subjects in 10 CFR Part 73
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
proposes to adopt the following
amendments to 10 CFR part 73.
PART 73—PHYSICAL PROTECTION OF
PLANTS AND MATERIALS
1. The authority citation for part 73
continues to read as follows:
XII. Regulatory Analysis
The NRC has prepared a draft
regulatory analysis on this proposed
regulation. The analysis examines the
costs and benefits of the alternatives
considered by the NRC.
The NRC requests public comment on
the draft regulatory analysis. Comments
on the draft analysis may be submitted
to NRC as indicated under the
ADDRESSES heading. The analysis is
available for inspection in the NRC
Public Document Room, 11555
Rockville Pike, Room 0–1 F21,
Rockville, MD 20852.
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).
2. Section 73.37 is revised to read as
follows:
XIII. Regulatory Flexibility
Certification
Under the Regulatory Flexibility Act
of 1980 (5 U.S.C. 605(b)), the
Commission certifies that this rule
would not, if promulgated, have a
significant economic impact on a
substantial number of small entities.
The companies that possess or transport
spent nuclear fuel do not fall within the
scope of the definition of ‘‘small
entities’’ set forth in the Regulatory
Flexibility Act or the size standards
established by NRC (10 CFR 2.810).
XIV. Backfit Analysis
The NRC has determined that the
backfit rule (§§ 50.109, 70.76, 72.62, or
76.76) 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.
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§ 73.37 Requirements for physical
protection of irradiated reactor fuel in
transit.
(a) Performance objectives. (1) Each
licensee who transports, or delivers to a
carrier for transport, in a single
shipment, a quantity of irradiated
reactor fuel 1 in excess of 100 grams
(0.22 lbs) 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 rems) per hour at
a distance of .91 meters (3 feet) from any
accessible surface without intervening
shielding, shall establish and maintain,
or make arrangements for, and assure
the proper implementation of, a
physical protection system for
shipments of such material that will
achieve the following objectives:
(i) Minimize the potential for theft,
diversion, or radiological sabotage of
spent nuclear fuel shipments; and
(ii) Facilitate the location and
recovery of spent fuel shipments that
may have come under the control of
unauthorized persons.
1 For purposes of 10 CFR 73.37, the terms
‘‘irradiated reactor fuel’’ and ‘‘spent nuclear fuel’’ are
used interchangeably.
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Federal Register / Vol. 75, No. 197 / Wednesday, October 13, 2010 / Proposed Rules
(2) To achieve these objectives, the
physical protection system shall:
(i) Provide for early detection and
assessment of attempts to gain
unauthorized access to, or control over,
spent fuel shipments;
(ii) Delay and impede attempts at
theft, diversion, or radiological sabotage
of spent nuclear fuel shipments until
response forces arrive; and
(iii) Provide for notification to the
appropriate response forces of any
attempts at theft, diversion, or
radiological sabotage of a spent nuclear
fuel shipment.
(b) General requirements. To achieve
the performance objectives of paragraph
(a) of this section, a physical protection
system established and maintained, or
arranged for, by the licensee shall
include the following elements:
(1) Preplan and Coordinate Spent
Nuclear Fuel Shipments. Each licensee
shall:
(i) Ensure that each armed escort is
instructed on the use of force sufficient
to counter the force directed at the
person, including the use of deadly
force when the armed escort has a
reasonable belief that the use of deadly
force is necessary in self-defense or in
the defense of others, or any other
circumstances, as authorized by
applicable Federal and State laws. This
requirement does not apply to members
of local law enforcement agencies
performing escort duties.
(ii) Preplan and coordinate shipment
itineraries to ensure that the receiver at
the final delivery point is present to
accept the shipment.
(iii) Ensure written certification of any
transfer of custody.
(iv) Preplan and coordinate shipment
information with the governor of a State,
or the governor’s designee, of a
shipment of spent nuclear material
through or across the boundary of the
State, in order to:
(A) Minimize intermediate stops and
delays;
(B) Arrange for State law enforcement
escorts;
(C) Arrange for positional information
sharing when requested; and
(D) Develop route information,
including the identification of safe
havens.
(v) Arrange with local law
enforcement authorities along the
shipment route, including U.S. ports
where vessels carrying spent nuclear
fuel shipments are docked, for their
response to an emergency or a call for
assistance.
(vi) Preplan and coordinate with NRC
to obtain advance approval of the routes
used for road and rail shipments of
spent nuclear fuel, and of any U.S. ports
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where vessels carrying spent nuclear
fuel shipments are scheduled to stop. In
addition to the requirements of this
section, routes used for shipping spent
nuclear fuel shall comply with the
applicable requirements of the DOT
regulations in 49 CFR in particular those
identified in § 71.5. The advance
approval application shall provide:
(A) For road shipments, the route
should include locations of safe havens
that have been coordinated with the
appropriate State(s).
(B) The NRC approval shall be
obtained prior to the 10-day advance
notification requirement in § 73.72 of
this part.
(C) Information to be supplied to NRC
shall include, but is not limited to, the
following:
(1) Shipper, consignee, carriers,
transfer points, modes of shipment; and
(2) A statement of shipment security
arrangements, including, if applicable,
points where armed escorts transfer
responsibility for the shipment.
(vii) Document the preplanning and
coordination activities.
(2) Advance Notifications. Prior to the
shipment of spent nuclear fuel outside
the confines of the licensee’s facility or
other place of use or storage, a licensee
subject to this section shall provide
notification to NRC, under § 73.72 of
this part, and the governor of the State,
or the governor’s designee, of the spent
nuclear fuel shipment. Contact
information for each State, 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, U.S. Nuclear Regulatory
Commission, Washington, DC 20555.
The licensee shall comply with the
following criteria in regard to each
notification:
(i) Procedures for submitting advance
notification. (A) The notification must
be in writing and sent to the office of
each appropriate governor or the
governor’s designee.
(B) A notification delivered by mail
must be postmarked at least 7 days
before transport of a shipment within or
through the State.
(C) A notification delivered by any
other method 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.
(ii) Information to be furnished in
advance notification of shipment. The
notification must include the following
information:
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(A) The name, address, and telephone
number of the shipper, carrier and
receiver of the shipment and the license
number of the shipper and receiver;
(B) A description of the shipment as
specified by DOT in 49 CFR 172.202
and 172.203(d); and
(C) A listing of the routes to be used
within the State.
(iii) Separate Enclosure. The licensee
shall provide the following information,
under § 73.22(f)(1), in a separate
enclosure to the written notification:
(A) The estimated date and time of
departure from the point of origin of the
shipment;
(B) The estimated date and time of
entry into the State;
(C) The estimated date and time of
arrival of the shipment at the
destination;
(D) For the case of a single shipment
whose schedule is not related to the
schedule of any subsequent shipment, a
statement that schedule information
must be protected under the provisions
of §§ 73.21 and 73.22 until at least 10
days after the shipment has entered or
originated within the State; and
(E) For the case of a shipment in a
series of shipments whose schedules are
related, a statement that schedule
information must be protected under the
provisions of §§ 73.21 and 73.22 until
10 days after the last shipment in the
series has entered or originated within
the State, and an estimate of the date on
which the last shipment in the series
will enter or originate within the State.
(iv) Revision notice. A licensee shall
notify by telephone a responsible
individual in the office of the governor
or in the office of the governor’s
designee of any schedule change that
differs by more than 6 hours from the
schedule information previously
furnished under § 73.37(b)(2)(iii), and
shall inform that individual of the
number of hours of advance or delay
relative to the written schedule
information previously furnished.
(v) Cancellation notice. Each licensee
who cancels a shipment for which
advance notification has been sent shall
send a cancellation notice to the
governor or to the governor’s designee of
each State 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 canceled.
(vi) Records. The licensee shall retain
a copy of the preplanning and
coordination activities, advance
notification, and any revision or
cancellation notice as a record for 3
years under § 73.70.
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(3) Transportation Physical Protection
System. (i) The physical protection
system established under § 73.37(a)(1)
shall include armed escorts to protect
spent nuclear fuel shipments and a
movement control center staffed and
equipped to monitor and control spent
nuclear fuel shipments, to communicate
with local law enforcement authorities,
and to respond to safeguards
contingencies.
(ii) The movement control center
must be staffed continuously by at least
one individual who will actively
monitor the progress of the spent
nuclear fuel shipment and who has the
authority to direct the physical
protection activities.
(iii) The movement control center
personnel must monitor the shipment
continuously, i.e., 24-hours per day,
from the time the shipment commences,
or if delivered to a carrier for transport,
from the time of delivery of the
shipment to the carrier, until safe
delivery of the shipment at its final
destination, and must immediately
notify the appropriate agencies in the
event of a safeguards event under the
provisions of § 73.71.
(iv) The movement control center
personnel and the armed escorts must
maintain a written log for each spent
nuclear fuel shipment, which will
include information describing the
shipment and significant events that
occur during the shipment. The log
must be available for review by
authorized NRC personnel for a period
of at least 3 years following completion
of the shipment.
(v) The licensee shall develop,
maintain, revise and implement written
transportation physical protection
procedures which address the
following:
(A) Access controls to ensure no
unauthorized persons have access to the
shipment and safeguards information;
(B) Duties of the movement control
center personnel, drivers, armed escorts
and other individuals responsible for
the security of the shipment;
(C) Reporting of safeguards events
under § 73.71;
(D) Communications protocols that
include a strategy for the use of
authentication and duress codes, the
management of refueling or other stops,
detours, and the loss of
communications, temporarily or
otherwise; and
(E) Normal conditions operating
procedures.
(vi) The licensee shall retain as a
record the transportation physical
protection procedures for 3 years after
the close of period for which the
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licensee possesses the spent nuclear
fuel.
(vii) The transportation physical
protection system shall:
(A) Provide that escorts (other than
members of local law enforcement
agencies, or ship’s officers serving as
unarmed escorts) have successfully
completed the training required by
Appendix D of this part, including the
equivalent of the weapons training and
qualifications program required of
guards, as described in sections III and
IV of Appendix B of this part, to assure
that each such individual is fully
qualified to use the assigned weapons;
(B) Provide that shipment escorts
make calls to the movement control
center at random intervals, not to
exceed 2 hours, to advise of the status
of the shipment for road and rail
shipments, and for sea shipments while
shipment vessels are docked at U.S.
ports; and
(C) Provide that at least one armed
escort remains alert at all times,
maintains constant visual surveillance
of the shipment, and periodically
reports to the movement control center
at regular intervals not to exceed 30
minutes during periods when the
shipment vehicle is stopped, or the
shipment vessel is docked.
(4) Contingency and Response
Procedures. (i) In addition to the
procedures established under paragraph
(b)(3)(v) of this section, the licensee
shall establish, maintain, and follow
written contingency and response
procedures to address threats, thefts,
and radiological sabotage related to
spent nuclear fuel in transit.
(ii) The licensee shall ensure that
personnel associated with the shipment
shall be appropriately trained regarding
contingency and response procedures.
(iii) The licensee shall retain the
contingency and response procedures as
a record for 3 years after the close of
period for which the licensee possesses
the spent nuclear fuel.
(iv) The contingency and response
procedures must direct that, upon
detection of the abnormal presence of
unauthorized persons, vehicles, or
vessels in the vicinity of a spent nuclear
fuel shipment or upon detection of a
deliberately induced situation that has
the potential for damaging a spent
nuclear fuel shipment, the armed escort
will:
(A) Determine whether or not a threat
exists;
(B) Assess the extent of the threat, if
any;
(C) Implement the procedures
developed under paragraph (b)(4)(i) of
this section;
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(D) Take the necessary steps to delay
or impede threats, thefts, or radiological
sabotage of spent nuclear fuel, and
(E) Inform local law enforcement
agencies of the threat and request
assistance without delay, but not to
exceed 15 minutes after discovery.
(c) Shipments by road. In addition to
the provisions of paragraph (b) of this
section, the physical protection system
for any portion of a spent nuclear fuel
shipment by road shall provide that:
(1) The transport vehicle is:
(i) Occupied by at least 2 individuals,
1 of whom serves as an armed escort,
and escorted by an armed member of the
local law enforcement agency in a
mobile unit of such agency; or
(ii) Led by a separate vehicle occupied
by at least 1 armed escort, and trailed
by a third vehicle occupied by at least
1 armed escort.
(2) As permitted by law, all armed
escorts are equipped with a minimum of
2 weapons. This requirement does not
apply to local law enforcement agency
personnel who are performing escort
duties.
(3) The transport vehicle and each
escort vehicle are equipped with
redundant communication abilities that
provide for 2-way communications
between the transport vehicle, the escort
vehicle(s), the movement control center,
local law enforcement agencies, and one
another at all times. Alternate
communications should not be subject
to the same failure modes as the primary
communication.
(4) The transport vehicle is equipped
with the NRC-approved features that
permit immobilization of the cab or
cargo-carrying portion of the vehicle.
(5) The transport vehicle driver has
been familiarized with, and is capable of
implementing, transport vehicle
immobilization, communications, and
other security procedures.
(6) 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 shall provide
positive confirmation of the location,
status, and control over the shipment.
The movement control center shall
implement preplanned procedures in
response to deviations from the
authorized route or a notification of
actual, attempted, or suspicious
activities related to the theft, loss,
diversion, or radiological sabotage of a
shipment. These procedures will
include, but not be limited to, the
identification of and contact
information for the appropriate local
law enforcement agency along the
shipment route.
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(d) Shipments by rail. In addition to
the provisions of paragraph (b) of this
section, the physical protection system
for any portion of a spent nuclear fuel
shipment by rail shall provide that:
(1) A shipment car is accompanied by
2 armed escorts (who may be members
of a local law enforcement agency), at
least 1 of whom is stationed at a
location on the train that will permit
observation of the shipment car while in
motion.
(2) As permitted by law, all armed
escorts are equipped with a minimum of
2 weapons. This requirement does not
apply to local law enforcement agency
personnel who are performing escort
duties.
(3) The train operator(s) and each
escort are equipped with redundant
communication abilities that provide for
2-way communications between the
transport, the escort vehicle(s), the
movement control center, local law
enforcement agencies, and one another
at all times. Alternate communications
should not be subject to the same failure
modes as the primary communication.
(4) Rail shipments are monitored by a
telemetric position monitoring system
or an alternative tracking system
reporting to the licensee, third-party, or
railroad movement control center. The
movement control center shall provide
positive confirmation of the location of
the shipment and its status. The
movement control 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, diversion,
or radiological sabotage of a shipment.
These procedures will include, but not
be limited to, the identification of and
contact information for the appropriate
local law enforcement agency along the
shipment route.
(e) Shipments by sea. In addition to
the provisions of paragraph (b) of this
section, the physical protection system
for any portion of a spent nuclear fuel
shipment that is by sea shall provide
that:
(1) A shipment vessel, while docked
at a U.S. port is protected by:
(i) Two armed escorts stationed on
board the shipment vessel, or stationed
on the dock at a location that will
permit observation of the shipment
vessel; or
(ii) A member of a local law
enforcement agency, equipped with
normal local law enforcement agency
radio communications, who is stationed
on board the shipment vessel, or on the
dock at a location that will permit
observation of the shipment vessel.
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(2) As permitted by law, all armed
escorts are equipped with a minimum of
2 weapons. This requirement does not
apply to local law enforcement agency
personnel who are performing escort
duties.
(3) A shipment vessel while within
U.S. territorial waters shall be
accompanied by an individual, who
may be an officer of the shipment
vessel’s crew, who will assure that the
shipment is unloaded only as
authorized by the licensee.
(4) Each armed escort is equipped
with redundant communication abilities
that provide for 2-way communications
between the vessel, the movement
control center, local law enforcement
agencies, and one another at all times.
Alternate communications should not
be subject to the same failure modes as
the primary communication.
(f) Investigations. Each licensee who
makes arrangements for the shipment of
spent nuclear fuel 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.
(g) State officials, State employees,
and other individuals, whether or not
licensees of the Commission, who
receive information of the kind
specified in paragraph (b)(2)(iii) of this
section and any other safeguards
information as defined in § 73.22(a)
shall protect that information against
unauthorized disclosure as specified in
§§ 73.21 and 73.22 of this part.
3. Add § 73.38 to read as follows:
§ 73.38 Personnel access authorization
requirements for irradiated reactor fuel in
transit.
(a) General. (1) Each licensee who
transports, or delivers to a carrier for
transport, in a single shipment, a
quantity of spent nuclear fuel as
described in § 73.37 (a)(1) shall comply
with the requirements of this section, as
appropriate, before any spent nuclear
fuel is transported or delivered to a
carrier for transport.
(2) Each licensee shall establish,
implement, and maintain its access
authorization program under the
requirements of this section.
(i) Each licensee shall be responsible
for the continuing effectiveness of the
access authorization program.
(ii) Each licensee shall ensure that the
access authorization program is
reviewed at an appropriate frequency to
confirm compliance with the
requirements of this section and that
comprehensive actions are taken to
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correct any noncompliance that is
identified.
(iii) The review shall evaluate all
program performance objectives and
requirements.
(iv) Each review report must
document conditions that are adverse to
the proper performance of the access
authorization program, the cause of the
condition(s), and when appropriate,
recommended corrective actions, and
corrective actions taken. The licensee
shall review the audit findings and take
any additional corrective actions
necessary to preclude repetition of the
condition, including reassessment of the
deficient areas where indicated.
(3) By (30 days after date the final rule
is published in the Federal Register),
each licensee that is subject to this
provision on (effective date of final rule)
shall implement the requirements of
this section through revisions to its
physical security plan.
(b) General performance objective.
The licensee’s access authorization
program must ensure that the
individuals specified in paragraph (c) of
this section are trustworthy and reliable
such that they do not constitute an
unreasonable risk to public health 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 to whom a licensee
intends to grant unescorted access to
spent nuclear fuel in transit, including
employees of a contractor or vendor;
(ii) Any individual whose duties and
responsibilities permit the individual to
take actions by physical or electronic
means that could adversely impact the
safety, security, or emergency response
to spent nuclear fuel in transit (i.e.,
movement control personnel, vehicle
drivers, or other individuals
accompanying spent nuclear fuel
shipments)
(iii) Any individual whose duties and
responsibilities include implementing a
licensee’s physical protection program
under § 73.37, including but not limited
to, non-LLEA armed escorts;
(iv) Any individual whose assigned
duties and responsibilities provide
access to spent nuclear fuel shipment
information that is considered to be
Safeguards Information under
§ 73.22(a)(2); and
(v) The licensee access authorization
program reviewing official.
(2) Persons identified in § 73.59 are
not subject to the investigative elements
of the access authorization program.
(d) Background Investigation. Before
allowing an individual to have
unescorted access or access
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authorization relative to spent nuclear
fuel 2 in transit the licensees shall
complete a background investigation as
defined in § 73.2 of the individual
seeking to have unescorted access or
access authorization. The scope of the
investigation must encompass at least
the past 10 years, or if 10 years of
information is not available then as
many years in the past that information
is available. The background
investigation does not apply to Federal,
State or local law enforcement
personnel who are performing escort
duties. The background investigation
must include, but is not limited to, the
following elements:
(1) Informed consent. Licensees shall
not initiate any element of a background
investigation without the informed and
signed consent of the subject individual.
This consent shall include authorization
to share personal information with
appropriate entities. The licensee to
whom the individual is applying for
access authorization shall inform the
individual of his or her right to review
information collected to assure its
accuracy, and provide the individual
with an opportunity to correct any
inaccurate or incomplete information
that is developed by the licensee.
(i) The subject individual may
withdraw his or her consent at any time.
Licensees shall inform the individual
that:
(A) Withdrawal of his or her consent
will remove the individual’s application
for access authorization under the
licensee’s access authorization program;
and
(B) Other licensees shall have access
to information documenting the
withdrawal.
(ii) If an individual withdraws his or
her consent, licensees may not initiate
any elements of the background
investigation that were not in progress
at the time the individual withdrew his
or her consent, but shall complete any
background investigation elements that
are in progress at the time consent is
withdrawn. The licensee shall record
the status of the individual’s application
for access authorization. Additionally,
licensees shall collect and maintain the
individual’s application for access
authorization; his or her withdrawal of
consent for the background
investigation; the reason given by the
individual for the withdrawal; and any
pertinent information collected from the
background investigation elements that
were completed. This information must
2 For purposes of 10 CFR 73.38, the terms
‘‘irradiated reactor fuel’’ as described in 10 CFR
73.37 and ‘‘spent nuclear fuel’’ are used
interchangeably.
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be shared with other licensees under
paragraph (l)(4) of this section.
(iii) Licensees shall inform, in writing,
any individual who is applying for
access authorization that the following
actions are sufficient cause for denial or
unfavorable termination of access
authorization status:
(A) Refusal to provide a signed
consent for the background
investigation;
(B) Refusal to provide, or the
falsification of, any personal history
information required under this section,
including the failure to report any
previous denial or unfavorable
termination of access authorization;
(C) Refusal to provide signed consent
for the sharing of personal information
with other licensees under paragraph
(d)(5)(v) of this section; or
(D) Failure to report any arrests or
legal actions specified in paragraph (f)
of this section.
(2) Personal history disclosure. Any
individual who is required to have a
background investigation under this
section 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 section is
sufficient cause for denial or
termination of access authorization.
(3) Fingerprinting. Fingerprinting and
an FBI identification and criminal
history records check under § 73.57.
(4) Verification of true identity.
Licensees shall verify the true identity
of an individual who is applying to have
access authorization to ensure that the
applicant is who they claim to be. A
licensee shall review official
identification documents (e.g., driver’s
license, passport, government
identification, State, province, or
country of birth issued certificate of
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, or maintain a
photocopy of identifying documents on
file under § 73.38(c). Licensees shall
certify and affirm in writing that the
identification was properly reviewed
and maintain the certification and all
related documents for review upon
inspection.
(5) Employment history evaluation.
Licensees shall ensure that an
employment history evaluation has been
completed on a best effort basis, by
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62713
questioning the individual’s present and
former employers, and by determining
the activities of the individual while
unemployed.
(i) For the claimed employment
period, the individual must provide the
reason for any termination, eligibility
for rehire, and other information that
could reflect on the individual’s
trustworthiness and reliability.
(ii) If the claimed employment was
military service the individual shall
provide a characterization of service,
reason for separation, and any
disciplinary actions that could affect a
trustworthiness and reliability
determination.
(iii) If education is claimed in lieu of
employment, the individual shall
provide any information related to the
claimed education that could reflect on
the individual’s trustworthiness and
reliability and, at a minimum, verify
that the individual was registered for
the classes and received grades that
indicate that the individual participated
in the educational process during the
claimed period.
(iv) 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 3 business days of the request,
the licensee shall:
(A) Document this refusal or
unwillingness in the licensee’s record of
the investigation; and
(B) 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.
(v) When any licensee is seeking the
information required for an access
authorization decision under this
section and has obtained a signed
release from the subject individual
authorizing the disclosure of such
information, other licensees shall make
available the personal or access
authorization information requested
regarding the denial or unfavorable
termination of an access authorization.
(vi) In conducting an employment
history evaluation, the licensee may
obtain information and documents by
electronic means, including, but not
limited to, telephone, facsimile, or email. Licensees shall make a record of
the contents of the telephone call and
shall retain that record, and any
documents or electronic files obtained
electronically, under paragraph (l) of
this section.
(6) Credit history evaluation.
Licensees shall ensure the evaluation of
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the full credit history of any individual
who is applying for access authorization
relative to spent nuclear fuel in transit.
A full credit history evaluation must
include, but is not limited to, an inquiry
to detect potential fraud or misuse of
social security numbers or other
financial identifiers, and a review and
evaluation of all of the information that
is provided by a national creditreporting agency about the individual’s
credit history. For 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. The
licensee shall evaluate the entire
criminal history record of an individual
who is applying for access authorization
to determine whether the individual has
a record of criminal activity that may
adversely impact his or her
trustworthiness and reliability. The
scope of the applicant’s criminal history
review must cover all residences of
record for the 10 year period preceding
the date of application for access
authorization.
(8) Character and reputation
determination. Licensees shall ascertain
the character and reputation of an
individual who has applied for access
authorization relative to spent nuclear
fuel in transit by conducting reference
checks. 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. The
reference checks must focus on the
individual’s reputation for
trustworthiness and reliability.
(9) Obtain independent Information.
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).
(e) Determination of Trustworthiness
and Reliability; Documentation. (1) The
licensee shall determine whether to
grant, deny, unfavorably terminate,
maintain, or administratively withdraw
an individual’s access authorization
based on an evaluation of all of the
information required by this section.
The licensee may terminate or
administratively withdraw an
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individual’s access authorization based
on information obtained after the
background investigation has been
completed and the individual granted
access authorization.
(2) The licensee may not permit any
individual to have unescorted access or
access authorization until all of the
information required by this section has
been evaluated by the reviewing official
and the reviewing official has
determined that the individual is
trustworthy and reliable. The licensee
may deny unescorted access or access
authorization to any individual based
on disqualifying information obtained at
any time during the background
investigation.
(f) Protection of Information. (1)
Licensees shall protect background
investigation information from
unauthorized disclosure.
(2) Licensees may not disclose the
background investigation information
collected and maintained to persons
other than the subject individual, his/
her representative, or to those who have
a need to know in performing assigned
duties related to the process of granting
or denying unescorted access to spent
nuclear fuel in transit. No individual
authorized to have access to the
information may re-disseminate the
information to any other individual who
does not have a need to know.
(3) The personal information obtained
on an individual from a background
investigation may be transferred to
another licensee:
(i) Upon the individual’s written
request to the licensee holding the data
to re-disseminate the information
contained in his/her file; and
(ii) The acquiring licensee verifies
information such as name, date of birth,
social security number, sex, and other
applicable physical characteristics for
identification.
(4) The licensee shall make
background investigation records
obtained under this section available for
examination by an authorized
representative of NRC to determine
compliance with applicable laws and
regulations.
(5) The licensee shall retain all
fingerprint and criminal history records
received from the FBI, or a copy if the
file has been transferred, on an
individual (including data indicating no
record) for 5 years from the date the
individual no longer requires
unescorted access or access
authorization relative to spent nuclear
fuel in transit.
(g) Grandfathering. For purposes of
this section, licensees are not required
to obtain the fingerprints of any person
who has been fingerprinted, pursuant to
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an NRC order or regulation, for an FBI
identification and criminal history
records check within the 5 years of the
effective date of this rule.
(h) Reinvestigations. Licensees shall
conduct fingerprinting and FBI
identification and criminal history
records check, a criminal history
review, and credit history re-evaluation
every 10 years for any individual who
has unescorted access authorization to
spent nuclear fuel in transit. The
reinvestigations must be completed
within 10 years of the date on which
these elements were last completed and
should address the 10 years following
the previous investigation.
(i) Self-reporting of legal actions. (1)
Any individual who has applied for an
access authorization or is maintaining
an access authorization under this
section shall promptly report to the
reviewing official, his or her supervisor,
or other management personnel
designated in licensee procedures any
legal action(s) taken by a law
enforcement authority or court of law to
which the individual has been subject
that could result in incarceration or a
court order or that requires a court
appearance, including but not limited to
an arrest, an indictment, the filing of
charges, or a conviction, but excluding
minor civil actions or misdemeanors
such as parking violations or speeding
tickets. The recipient of the report shall,
if other than the reviewing official,
promptly convey the report to the
reviewing official. On the day that the
report is received, the reviewing official
shall evaluate the circumstances related
to the reported legal action(s) and redetermine the reported individual’s
access authorization status.
(2) The licensee shall inform the
individual of this obligation, in writing,
prior to granting unescorted access or
certifying access authorization.
(j) Access Authorization Procedures.
(1) Licensees shall develop, implement,
and maintain written procedures for
conducting background investigations
for persons who are applying for
unescorted access or access
authorization for spent nuclear fuel in
transit.
(2) Licensees shall develop,
implement, and maintain written
procedures for updating background
investigations for persons who are
applying for reinstatement of unescorted
access or access authorization.
(3) Licensees shall develop,
implement, and maintain written
procedures to ensure that persons who
have been denied unescorted access or
access authorization are not allowed
access to spent nuclear fuel in transit or
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information relative to spent nuclear
material in transit.
(4) Licensees shall develop,
implement, and maintain written
procedures for the notification of
individuals who are denied unescorted
access or access authorization for spent
nuclear fuel in transit. The procedures
must include provisions for the review,
at the request of the affected individual,
of a denial or termination of unescorted
access or 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 or
access authorization and allow the
individual an opportunity to provide
additional relevant information.
(k) Right to correct and complete
information. (1) Prior to any final
adverse determination, licensees shall
provide each individual subject to this
section 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.
(l) 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 or access
authorization relative to spent nuclear
fuel in transit.
(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
or access authorization and the list of
those individuals that have been denied
unescorted access or access
authorization for 5 years after the list is
superseded or replaced.
(4) Licensees who have been
authorized to add or manipulate data
that is shared with licensees subject to
this section shall ensure that data linked
to the information about individuals
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who have applied for unescorted access
or access authorization, which is
specified in the licensee’s access
authorization program documents, is
retained.
(i) If the shared information used for
determining individual’s
trustworthiness and reliability changes
or new or additional information is
developed about the individual, the
licensees that acquire this information
shall correct or augment the data and
ensure it is shared with licensees
subject to this section. If the changed,
additional or developed information has
implications for adversely affecting an
individual’s trustworthiness and
reliability, licensees who discovered or
obtained the new, additional or changed
information, shall, on the day of
discovery, inform the reviewing official
of any licensee access authorization
program under which the individual is
maintaining his or her unescorted
access or access authorization status of
the updated information.
(ii) The reviewing official shall
evaluate the shared information and
take appropriate actions, which may
include denial or unfavorable
termination of the individual’s
unescorted access or access
authorization. If the notification of
change or updated information cannot
be made through usual methods,
licensees shall take manual actions to
ensure that the information is shared as
soon as reasonably possible. Records
maintained in any database(s) must be
available for the NRC review.
(5) If a licensee administratively
withdraws an individual’s unescorted
access or access authorization status
caused by a delay in completing any
portion of the background investigation
or for a licensee initiated evaluation, or
re-evaluation that is not under the
individual’s control, the licensee shall
record this administrative action to
withdraw the individual’s unescorted
access or unescorted access
authorization with other licensees
subject to this section. However,
licensees shall not document this
administrative withdrawal as denial or
unfavorable termination and shall not
respond to a suitable inquiry conducted
under the provisions of 10 CFR part 26,
a background investigation conducted
under the provisions of this section, or
any other inquiry or investigation as
denial nor unfavorable termination.
Upon favorable completion of the
background investigation element that
caused the administrative withdrawal,
the licensee shall immediately ensure
that any matter that could link the
individual to the administrative action
is eliminated from the subject
PO 00000
Frm 00024
Fmt 4702
Sfmt 4702
62715
individual’s access authorization or
personnel record and other records,
except if a review of the information
obtained or developed causes the
reviewing official to unfavorably
terminate or deny the individual’s
unescorted access.
4. In § 73.71, paragraphs (a)
introductory text, (a)(1), (a)(4), (a)(5) and
(b) are revised to read as follows:
§ 73.71 Requirement for advance notice of
shipment of formula quantities of strategic
special nuclear material, special nuclear
material of moderate strategic significance,
or irradiated reactor fuel.
(a) A licensee, other than one
specified in paragraph (b) of this
section, who, in a single shipment,
plans to deliver to a carrier for transport,
to take delivery at the point where a
shipment is delivered to a carrier for
transport, to import, to export, or to
transport a formula quantity of strategic
special nuclear material, special nuclear
material of moderate strategic
significance, or irradiated reactor fuel 3
required to be protected in accordance
with § 73.37, shall:
(1) Notify in writing the Director,
Division of Security Policy, Office of
Nuclear Security and Incident
Response, using any appropriate
method listed in § 73.4. Classified
notifications shall be sent to the NRC
headquarters classified mailing address
listed in appendix A to this part.
*
*
*
*
*
(4) The NRC Headquarters Operations
Center shall be notified about the
shipment status by telephone at the
phone numbers listed in appendix A to
this part. Classified notifications shall
be made by secure telephone. The
notifications shall take place at the
following intervals:
(i) At least 2 days before
commencement of the shipment;
(ii) Two hours before commencement
of the shipment; and
(iii) Once the shipment is received at
its destination.
(5) The NRC Headquarters Operations
Center shall be notified by telephone of
schedule changes of more than 6 hours
at the phone numbers listed in
Appendix A to this part. Classified
notifications shall be made by secure
telephone.
(b) A licensee who conducts an onsite transfer of spent nuclear fuel that
does not travel upon or cross a public
highway is exempt from the
requirements of this section for that
transfer.
3 For purposes of 10 CFR 73.72, the terms
‘‘irradiated reactor fuel’’ as described in 10 CFR
73.37 and ‘‘spent nuclear fuel’’ are used
interchangeably.
E:\FR\FM\13OCP1.SGM
13OCP1
62716
Federal Register / Vol. 75, No. 197 / Wednesday, October 13, 2010 / Proposed Rules
Dated at Rockville, Maryland, this 1st day
of October 2010.
For the Nuclear Regulatory Commission.
Annette Vietti-Cook,
Secretary of the Commission.
[FR Doc. 2010–25392 Filed 10–12–10; 8:45 am]
BILLING CODE 7590–01–P
DEPARTMENT OF TRANSPORTATION
Federal Aviation Administration
14 CFR Part 39
[Docket No. FAA–2010–1021; Directorate
Identifier 2010–CE–053–AD]
RIN 2120–AA64
Airworthiness Directives; Pacific
Aerospace Limited Model FU24–954
and FU24A–954 Airplanes
Federal Aviation
Administration (FAA), Department of
Transportation (DOT).
ACTION: Notice of proposed rulemaking
(NPRM).
AGENCY:
We propose to adopt a new
airworthiness directive (AD) for the
products listed above that would
supersede two existing ADs. This
proposed AD results from mandatory
continuing airworthiness information
(MCAI) originated by an aviation
authority of another country to identify
and correct an unsafe condition on an
aviation product. The MCAI describes
the unsafe condition as:
SUMMARY:
To prevent possible in-flight failure of the
vertical stabiliser, leading to loss of control
of the aircraft * * *
The proposed AD would require actions
that are intended to address the unsafe
condition described in the MCAI.
DATES: We must receive comments on
this proposed AD by November 29,
2010.
You may send comments by
any of the following methods:
• Federal eRulemaking Portal: Go to
https://www.regulations.gov. Follow the
instructions for submitting comments.
• Fax: (202) 493–2251.
• Mail: U.S. Department of
Transportation, Docket Operations, M–
30, West Building Ground Floor, Room
W12–140, 1200 New Jersey Avenue, SE.,
Washington, DC 20590.
• Hand Delivery: U.S. Department of
Transportation, Docket Operations, M–
30, West Building Ground Floor, Room
W12–140, 1200 New Jersey Avenue, SE.,
Washington, DC 20590, between 9 a.m.
and 5 p.m., Monday through Friday,
except Federal holidays.
jlentini on DSKJ8SOYB1PROD with PROPOSALS
ADDRESSES:
VerDate Mar<15>2010
19:22 Oct 12, 2010
Jkt 223001
Examining the AD Docket
You may examine the AD docket on
the Internet at https://
www.regulations.gov; or in person at the
Docket Management Facility between
9 a.m. and 5 p.m., Monday through
Friday, except Federal holidays. The AD
docket contains this proposed AD, the
regulatory evaluation, any comments
received, and other information. The
street address for the Docket Office
(telephone (800) 647–5527) is in the
ADDRESSES section. Comments will be
available in the AD docket shortly after
receipt.
FOR FURTHER INFORMATION CONTACT: Karl
Schletzbaum, Aerospace Engineer, FAA,
Small Airplane Directorate, 901 Locust,
Room 301, Kansas City, Missouri 64106;
telephone: (816) 329–4146; fax: (816)
329–4090.
SUPPLEMENTARY INFORMATION:
Comments Invited
We invite you to send any written
relevant data, views, or arguments about
this proposed AD. Send your comments
to an address listed under the
ADDRESSES section. Include ‘‘Docket No.
FAA–2010–1021; Directorate Identifier
2010–CE–053–AD’’ at the beginning of
your comments. We specifically invite
comments on the overall regulatory,
economic, environmental, and energy
aspects of this proposed AD. We will
consider all comments received by the
closing date and may amend this
proposed AD because of those
comments.
We will post all comments we
receive, without change, to https://
regulations.gov, including any personal
information you provide. We will also
post a report summarizing each
substantive verbal contact we receive
about this proposed AD.
Discussion
On February 4, 2004, we issued AD
2004–03–29, Amendment 39–13473 (69
FR 6553; February 11, 2004) and on
June 30, 2008, we issued AD 2008–14–
12, Amendment 39–15607 (73 FR
40951; July 17, 2008). Those ADs
required actions intended to address an
unsafe condition on the products listed
above.
Since we issued AD 2008–14–12,
Pacific Aerospace Limited has
developed a new vertical stabilizer
design to eliminate the cracking in the
vertical stabilizer that occurred with the
original design. The new vertical
stabilizer design incorporates a forward
spar and is a failsafe structure.
The Civil Aviation Authority (CAA),
which is the aviation authority for New
Zealand, has issued AD DCA/FU24/178,
PO 00000
Frm 00025
Fmt 4702
Sfmt 4702
dated April 30, 2009 (referred to after
this as ‘‘the MCAI’’), to correct an unsafe
condition for the specified products.
The MCAI states:
To prevent possible in-flight failure of the
vertical stabiliser, leading to loss of control
of the aircraft * * *
Replace the vertical stabiliser with P/N 08–
32005–2 by accomplishing modification
PAC/FU/0345 in accordance with the
instructions in Pacific Aerospace Limited
Mandatory SB No. PACSB/FU/094 issue1
dated 14 August 2008 * * *
The MCAI requires replacement of the
vertical stabilizer with a new design that
incorporates a forward spar and is a
failsafe structure. You may obtain
further information by examining the
MCAI in the AD docket.
Relevant Service Information
Pacific Aerospace Limited has issued
Mandatory Service Bulletin PACSB/FU/
094, Issue 1, dated August 14, 2008. The
actions described in this service
information are intended to correct the
unsafe condition identified in the
MCAI.
FAA’s Determination and Requirements
of the Proposed AD
This product has been approved by
the aviation authority of another
country, and is approved for operation
in the United States. Pursuant to our
bilateral agreement with this State of
Design Authority, they have notified us
of the unsafe condition described in the
MCAI and service information
referenced above. We are proposing this
AD because we evaluated all
information and determined the unsafe
condition exists and is likely to exist or
develop on other products of the same
type design.
Differences Between This Proposed AD
and the MCAI or Service Information
We have reviewed the MCAI and
related service information and, in
general, agree with their substance. But
we might have found it necessary to use
different words from those in the MCAI
to ensure the AD is clear for U.S.
operators and is enforceable. In making
these changes, we do not intend to differ
substantively from the information
provided in the MCAI and related
service information.
We might also have proposed
different actions in this AD from those
in the MCAI in order to follow FAA
policies. Any such differences are
highlighted in a Note within the
proposed AD.
Costs of Compliance
We estimate that this proposed AD
will affect 3 products of U.S. registry.
E:\FR\FM\13OCP1.SGM
13OCP1
Agencies
[Federal Register Volume 75, Number 197 (Wednesday, October 13, 2010)]
[Proposed Rules]
[Pages 62695-62716]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-25392]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Part 73
RIN 3150-AI64
[NRC-2009-0163]
Physical Protection of Irradiated Reactor Fuel in Transit
AGENCY: Nuclear Regulatory Commission.
ACTION: Proposed rule.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is proposing to
amend its security regulations pertaining to the transport of
irradiated reactor fuel (for purposes of this rulemaking, the terms
``irradiated reactor fuel'' and ``spent nuclear fuel'' (SNF) are used
interchangeably). This proposed rule would establish generically
applicable security requirements similar to those previously imposed by
Commission orders issued after the terrorist attacks of September 11,
2001. The proposed rule would establish the acceptable performance
standards and objectives for the protection of spent nuclear fuel
shipments from theft, diversion, or radiological sabotage. The proposed
amendments would apply to those licensees authorized to possess or
transport spent nuclear fuel. The proposed security requirements would
also address, in part, a petition for rulemaking from the State of
Nevada (PRM-73-10) that requests that NRC strengthen the regulations
governing the security of spent nuclear fuel shipments against
malevolent acts.
DATES: The comment period expires January 11, 2011. Submit comments
specific to the information collection aspects of this rule by November
12, 2010. Comments received after this date will be considered if
practical to do so, but the NRC is able to assure consideration only
for comments received on or before this date.
ADDRESSES: Please include Docket ID: NRC-2009-0163 in the subject line
of your comments. For instructions on submitting comments and accessing
documents related to this action, see Section I, ``Submitting Comments
and Accessing Information'' in the SUPPLEMENTARY INFORMATION section of
this document. You may submit comments by any one of the following
methods.
Federal Rulemaking Web site: Go to https://www.regulations.gov and
search for documents filed under Docket ID: NRC-2009-0163. Address
questions about the NRC dockets to Carol Gallagher 301-492-3668; e-mail
Carol.Gallager@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) 415-1966.
Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m. during Federal workdays.
(Telephone 301-415-1966)
Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at
301-415-1101.
FOR FURTHER INFORMATION CONTACT: Cardelia Maupin, Office of Federal and
State Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, Telephone 301-415-
2312, e-mail: Cardelia.Maupin@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Submitting Comments and Accessing Information
II. Background
III. Discussion
A. What action is the NRC taking in this rule?
B. Why revise the requirements?
C. What is requested by the State of Nevada in its petition for
rulemaking (PRM-73-10)?
D. What are the DOT routing requirements for spent nuclear fuel
shipments?
E. What are the NRC routing requirements for spent nuclear fuel
shipments?
[[Page 62696]]
F. Why do the NRC and DOT routing requirements differ for spent
nuclear fuel shipments?
G. Why require procedures and training for the security of spent
nuclear fuel in transit?
H. Why require a telemetric position monitoring system or an
alternative tracking system for continuous monitoring of spent
nuclear fuel shipments?
I. Why pre-plan and coordinate spent nuclear fuel shipments?
J. Why require constant visual surveillance by armed escort?
K. Why require two-way redundant communication capabilities?
L. Why require background investigations?
M. Why enhance shipment notifications to NRC?
N. Which type of spent nuclear fuel does DOE ship?
O. What is a non-classified shipment of spent nuclear fuel and
what are the DOE requirements for this type of shipment?
P. How are the NRC and DOE requirements similar and how are they
different?
Q. Who would this action affect?
R. Does NRC plan to issue guidance on these proposed
requirements?
S. What should I consider as I prepare my comments to NRC?
IV. Discussion of the Proposed Amendments by Section
V. Criminal Penalties
VI. Agreement State Compatibility
VII. Plain Language
VIII. Voluntary Consensus Standards
IX. Finding of No Significant Environmental Impact: Availability
X. Paperwork Reduction Act Statement
XI. Public Protection Notification
XII. Regulatory Analysis
XIII. Regulatory Flexibility Certification
XIV. Backfit Analysis
I. Submitting Comments and Accessing Information
Comments submitted in writing or in electronic form will be posted
on the NRC Web site and on the Federal rulemaking Web site https://www.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.
You can access publicly available documents related to this
document 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, Room O-
1 F21, One White Flint North, 11555 Rockville Pike, Rockville,
Maryland.
NRC's Agencywide Document Access and Management System (ADAMS):
Publicly available documents created or received at 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 the 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, or 301-415-4737, or by e-mail to
PDR Resource.
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-2009-0163.
----------------------------------------------------------------------------------------------------------------
Document PDR ADAMS Web
----------------------------------------------------------------------------------------------------------------
Environmental Assessment...................... X ML092710448........................... X
Regulatory Analysis........................... X ML102710278........................... X
PRM-73-10..................................... X ML092540603........................... X
----------------------------------------------------------------------------------------------------------------
II. Background
A. Pre-September 11, 2001
On June 15, 1979 (44 FR 34466), NRC published an interim final rule
in the Federal Register that established its first requirements for the
physical protection of spent nuclear fuel in transit. The interim final
rule added 10 CFR 73.37, ``Requirements for Physical Protection of
Irradiated Reactor Fuel in Transit'' to 10 CFR part 73. After
considering public comments, the Commission affirmed the interim final
rule on June 3, 1980 (45 FR 37399).
The current Sec. 73.37 has changed little since its promulgation
in 1980. These regulations require licensees to establish a physical
protection system for spent nuclear fuel shipments that meets the
following objectives: (1) Minimize the possibilities for radiological
sabotage of spent nuclear fuel shipments, especially within heavily
populated areas, and (2) facilitate the location and recovery of spent
nuclear fuel shipments that may have come under the control of
unauthorized persons. The regulation also provides for: (1) The early
detection and assessment of attempts to gain unauthorized access to or
control over spent nuclear fuel shipments, (2) the notification to the
appropriate response forces of any sabotage events, and (3) the
impeding of attempts at radiological sabotage of spent nuclear fuel
shipments in heavily populated areas or attempts to illicitly move such
shipments into heavily populated areas.
Other NRC regulations support the protection of spent nuclear fuel
in transit. The regulations in Sec. 73.72, ``Requirement for Advance
Notice of Shipment of Formula Quantities of Strategic Special Nuclear
Material, Special Nuclear Material of Moderate Strategic Significance,
or Irradiated Reactor Fuel'' require licensees to notify NRC in advance
about shipments of spent nuclear fuel. The regulations in 10 CFR part
71, ``Packaging and Transportation of Radioactive Material,'' establish
requirements for packages used to transport spent nuclear fuel.
This proposed rule would consider and address, in part, a petition
for rulemaking submitted by the State of Nevada. By a letter dated June
22, 1999, the State of Nevada submitted a petition for rulemaking
requesting that NRC strengthen its regulations governing the security
of spent nuclear fuel shipments against malevolent acts. The NRC
docketed the petition on July 13, 1999, as Docket No. PRM-73-10 (PRM-
73-10). The NRC published a notice of receipt of petition and a request
for public comment on September 13, 1999 (64 FR 49410). The Commission
review of this petition was tabled following the terrorist attacks of
September 11, 2001. The petition was denied, in part, by the NRC on
December 7, 2009 (74 FR 64012). This proposed rulemaking would consider
and address the remaining requests for the NRC rulemaking made in PRM-
73-10.
B. Post-September 11, 2001
Although the current Sec. 73.37 has changed little since its
promulgation in 1980, there have been significant changes in the threat
environment. The terrorist attacks of September 11, 2001, heightened
concerns about the use of risk-significant radioactive materials in a
malevolent act. After the terrorist
[[Page 62697]]
attacks of September 11, 2001, the NRC issued a series of security-
related orders to specific licensees. In the area of spent nuclear fuel
transit security, the orders were issued to licensees who shipped or
received, or were planning to ship or receive, spent nuclear fuel. The
orders were issued as immediately effective under the NRC's authority
to protect the common defense and security under the Atomic Energy Act
of 1954, as amended (AEA). The requirements established by the orders
supplement the existing regulatory requirements. These additional
security requirements are primarily intended to ensure that spent
nuclear fuel is shipped in a manner that protects the common defense
and security, and the public health and safety.
C. Current Regulatory Framework
About two thousand NRC regulated shipments of spent nuclear fuel
have been made throughout the United States since the 1970s. The
primary objective of these shipments has been to move spent nuclear
fuel to interim storage. These spent fuel shipments are generally
divided into two categories: commercial shipments or DOE managed spent
nuclear fuel shipments. Commercial spent nuclear fuel shipments are
from the NRC-licensed facilities such as commercial nuclear power
reactors, research and test reactors, and facilities for non-
destructive testing and analysis of spent nuclear fuel. The DOE-managed
shipments involve shipments to DOE owned interim spent nuclear fuel
storage facilities.
The safe and secure shipment of spent nuclear fuel requires
coordination and collaboration between various Federal, State, Tribal
and local government agencies. These organizations work together to
create an orderly pattern for shipments of spent nuclear fuel.
1. What is the role of NRC in spent nuclear fuel transit?
Generally, the NRC regulates the design and construction of spent
nuclear fuel shipping containers for domestic and foreign packages used
to transport spent nuclear fuel solely within the United States.
Although DOT is the lead government agency responsible for the approval
of export and import packages, it relies on the NRC's evaluation as the
basis for approval of these packages. In addition, NRC regulates the
physical protection of commercial spent nuclear fuel in transit against
sabotage or other malicious acts, which is recognized in the DOT
routing regulations in 49 CFR 397.101. The NRC requirements in 10 CFR
Part 73 are applied to shipments of spent nuclear fuel from the NRC
licensees.
2. What is the role of DOT in spent nuclear fuel transit? The DOT
regulates the transportation of hazardous materials, including spent
nuclear fuel in interstate and intrastate commerce. Generally, DOT
regulates in consultation with NRC the carriers of spent nuclear fuel
and the conditions of transport, such as routing, handling and storage
incident to transport, and vehicle and driver requirements. The DOT
also regulates the labeling, classification, and marking of all spent
nuclear fuel packages and transport vehicles.
3. What is the role of DOE? For over 50 years, DOE has transported
spent nuclear fuel to interim storage facilities. These spent nuclear
fuel shipments have originated from the following: (1) Foreign research
reactors; (2) DOE-owned research and defense reactors, and (3) nuclear
powered U.S. Navy ships. In addition, on a few rare occasions, the DOE
has accepted some spent nuclear fuel from commercial nuclear power
plants, e.g., Three Mile Island Unit 2, for storage at its facilities.
The DOE managed shipments of spent nuclear fuel, unless designated
as a national security shipment, are conducted under requirements
equivalent to those of DOT and NRC. The DOE complies with the DOT
highway section criteria and carrier safety provisions. The DOE spent
nuclear fuel packages are required to meet the NRC design and
performance criteria in 10 CFR part 71, which is also stated in the DOT
regulations in 49 CFR 173.7(d). Spent nuclear fuel shipments made by
DOE or the DOE contractors are not subject to the NRC physical
protection requirements because DOE is not a NRC licensee. DOE's
policy, however, is that DOE managed spent nuclear fuel shipments meet
or exceed NRC physical protection requirements.
4. What is the role of State, local, and Tribal governments? State,
local and Tribal governments play an important role in the safe and
secure transport of spent nuclear fuel. They assist in route planning
and, for many shipments, provide armed escorts. They enforce the DOT
highway safety regulations, including the performance of shipment
inspections. State, local, and Tribal governments are also responsible
for providing the first line of government response to accidents and
incidents within their jurisdiction.
III. Discussion
A. What action is NRC taking in this rule?
The NRC is proposing amendments to its regulations to enhance the
security requirements that apply to the transportation of spent nuclear
fuel. This proposed rulemaking would establish generically applicable
security requirements similar to those previously imposed by Commission
orders issued after the terrorist attacks of September 11, 2001. The
proposed rulemaking would also add several new requirements not derived
directly from the security order requirements, but developed as a
result of insights gained by performing security assessments of
potential security vulnerabilities associated with spent nuclear fuel
in transit. Also, the proposed rulemaking would address, in part, the
requests for the NRC rulemaking raised by PRM-73-10.
The proposed requirements would establish acceptable performance
objectives for the protection of spent nuclear fuel in transit from
sabotage, theft, or diversion for malevolent use. These requirements
would ensure that spent nuclear fuel is shipped in a manner that
protects the common defense and security, and public health and safety.
B. Why revise the requirements?
After the attacks of September 11, 2001, NRC re-evaluated its
security requirements for spent nuclear fuel in transit. From this
effort, additional measures were identified that would improve
security. The additional security measures deemed immediately necessary
were issued as orders and supplemented existing regulations. The orders
are not publically available, because they contain detailed security
requirements that are designated as Safeguards Information (SGI). The
proposed revisions are based on the NRC efforts undertaken since the
events of September 11, 2001, including issuance of additional security
requirements by orders, insights gained from implementation of the
orders, and insights gained by performing security assessments of
potential security vulnerabilities associated with spent nuclear fuel
transportation. The proposed revisions also reflect portions of the
State of Nevada's Petition for Rulemaking (PRM-73-10). The NRC intends
to rescind the security orders provided the final rule adequately
addresses the security requirements set forth in those orders.
Rescission will be addressed in the notice of final rulemaking.
C. What is requested by the State of Nevada in its petition for
rulemaking (PRM-73-10)?
By a letter dated June 22, 1999, the State of Nevada submitted a
rulemaking
[[Page 62698]]
petition (docketed as PRM-73-10) requesting that NRC initiates
rulemaking to strengthen its regulations for the physical protection of
spent nuclear fuel shipments against radiological sabotage and
terrorist acts. The NRC published a notice of receipt of petition and a
request for public comment on September 13, 1999 (64 FR 49410). The
Commission review of this petition was tabled following the terrorist
attacks of September 11, 2001.
In PRM-73-10, Nevada requested that NRC: (1) Clarify the meaning of
the term ``hand-carried equipment'' in 10 CFR 73.1(a)(1)(i)(D); (2)
clarify the definition of the term ``radiological sabotage'' in 10 CFR
73.2 to include actions against spent nuclear fuel shipments which are
intended to cause a loss of shielding, release of radioactive materials
or cause economic damage or social disruption, regardless of the
success or failure of the action; (3) amend the advance route approval
requirements in 10 CFR 73.37(b)(1)(vi) to require shippers and carriers
of spent nuclear fuel to identify primary and alternative routes which
avoid heavily populated areas; (4) require armed escorts along the
entire road shipment route by eliminating the differential based on
population in 10 CFR 73.37(c); (5) require armed escorts along the
entire rail shipment route by eliminating the differential based on
population in 10 CFR 73.37(d); (6) amend 10 CFR 73.37(b) by adopting
additional planning and scheduling requirements for spent nuclear fuel
shipments that are the same as those required for formula quantities of
special nuclear material by 10 CFR 73.26(b); (7) amend 10 CFR 73.37(d)
to require that rail shipments of spent nuclear fuel be made in
dedicated trains; and (8) conduct a comprehensive assessment of the
consequences of terrorist attacks that have the capability of
radiological sabotage.
In this proposed rulemaking, the NRC will consider the above items
raised in PRM-73-10, except for the first and eighth items, namely,
clarification of the meaning of the term ``hand-carried equipment'' and
the conducting of a comprehensive assessment of the consequences of
terrorist attacks that have the capability of radiological sabotage.
Rulemaking on the first and eighth items of PRM-73-10 was denied by the
NRC on December 7, 2009 (74 FR 64012). The remaining items are
addressed below:
PRM-73-10, Item 2: Clarify the definition of the term
``radiological sabotage'' in Sec. 73.2, ``Definitions,'' and amend it
to expressly include ``deliberate actions which cause, or are intended
to cause economic damage or social disruption regardless of the extent
to which public health and safety are actually endangered by exposure
to radiation.''
The NRC considers that the existing definition already encompasses
actions of the type described by the Petitioner. However, NRC agrees
that clarification may be useful. The NRC is addressing this petition
item by clarifying the definition of radiological sabotage in the
supporting guidance document associated with the proposed rule.
PRM-73-10, Item 3: Amend the advance route approval requirements in
10 CFR 73.37(b)(7) to ``specifically require shippers and carriers to
identify primary and alternative routes which minimize highway and rail
shipments through heavily populated areas.'' Also, as part of this
request, PRM-73-10 stated that NRC should consider adopting the route
selection criteria in NUREG-0561, Physical Protection of Shipments of
Irradiated Reactor Fuel in Transit, as part of the regulations, and
specifically require shippers and carriers to minimize use of routes
which fail to comply with the route selection criteria.
The NRC considered incorporating the route selection criteria of
NUREG-0561 into the proposed rule, but determined that implementing
such criteria may cause conflicts with the DOT requirements. Sections D
through F below provide additional information about the differences
between DOT and NRC routing criteria. The PRM-73-10 request for the
adoption of routing criteria from NUREG-0561 was considered by the NRC
and determined to be not appropriate.
The PRM-73-10 also requested that NRC amend its regulations to
minimize highway and rail shipments through heavily populated areas.
The NRC is addressing the goal of minimizing spent nuclear fuel
shipments through heavily populated areas in the proposed rulemaking.
The proposed revisions to 10 CFR 73.37 would require licensees to
preplan and coordinate their shipments with the affected States. This
issue is discussed below under ``Why Require Shipment Preplanning and
Coordination with States?'' Combining the NRC proposed requirements,
which include State involvement in licensees' planning activities, with
the requirements of DOT is expected to minimize movement of spent
nuclear fuel through heavily populated areas.
PRM-73-10, Items 4 and 5: The current regulations, Sec. 73.37(c)
and (d), for road and rail shipments, respectively, require armed
escorts in heavily populated areas, but not in other areas along the
route. PRM-73-10 requested that NRC eliminate these differential armed
escort requirements based upon population for both road and rail spent
nuclear fuel shipments.
Proposed Sec. Sec. 73.37(c) and (d) include these PRM-73-10
requests. The differentiation of security requirements based upon
population causes potential areas of vulnerability along the shipment
route for theft, diversion, or radiological sabotage. The proposed rule
would require that the same security requirements for heavily populated
areas apply along the entire route for road and rail shipments, and at
any U.S. ports where vessels carrying spent fuel shipments are
scheduled to stop.
PRM-73-10, Item 6: Amend Sec. 73.37(b) by adopting additional
planning and scheduling requirements for spent nuclear fuel shipments
that are the same as those required for formula quantities of special
nuclear material by Sec. 73.26(b). The regulations in Sec. 73.26(b)
require that shipments be scheduled to avoid delays and stops, and to
ensure timely delivery of the shipment.
The NRC agrees that improvements are needed in the planning and
coordination of shipments and has addressed this concern in the
proposed amendment. This issue is discussed below under ``Why Require
Shipment Preplanning and Coordination with States?''
PRM-73-10, Item 7: Amend Sec. 73.37(d) to require that all spent
nuclear fuel rail shipments be made in dedicated trains.
The same NRC security requirements would apply to a spent nuclear
fuel rail shipment, regardless of whether the shipment was made using a
dedicated train or a mixed-use train. In either case, the licensee
making the shipment would be required to ensure that the security
protection measures (both hardware and personnel) required by the NRC's
regulations would be present to provide the requisite high assurance of
protection of public health and safety and the common defense and
security during the entire duration of the shipment. The NRC considers
the same level of security will be obtained regardless of whether the
shipment is made in a dedicated train or mixed-use train. Thus, this
item is not addressed as a part of the proposed rule.
The NRC invites comments on its proposed disposition of items 2
through 7 of PRM-73-10 as part of its consideration of this proposed
rule. Comments should be sent to the address listed under the ADDRESSES
heading of this document. The PRM-73-10 is available at ADAMS Accession
Number: ML092540603 and the NRC's September 13, 1999, notice of receipt
of petition and request for public comments (64 FR
[[Page 62699]]
49410) is available on the Federal Register's Web site, https://www.gpoaccess.gov/fr/.
D. What are the DOT routing requirements for spent nuclear fuel
shipments?
The DOT has various terms to define and categorize radioactive
material within the Title 49 of the Code of Federal Regulations. Within
their definitions, DOT includes a category for highway route controlled
quantity (HRCQ) which is defined as a quantity of radioactive material
within a single package that exceeds: (a) 3,000 times the A1
value of the radionuclides for special form material or 3,000 times the
A2 values of the radionuclides for normal form material; or
(b) 1,000 TBq (27,000 curies), whichever is less. The HRCQ shipments
can be made by all modes of transport. Spent nuclear fuel shipments
fall under the DOT's definition of HRCQ.
For shipments by road, the DOT requirements for routing radioactive
material are found in 49 CFR Parts 172 (Subpart I--Safety and Security
Plans) and 397 (Subpart D--Routing of Class 7 (Radioactive) Materials).
The DOT highway routing requires carriers to (1) Ensure routes are
chosen based on minimizing radiological risk; (2) consider available
information on accident rates, transit time, population density and
activities, and the time of the day and the day of the week during
which transportation will occur to determine the level of radiological
risk; and (3) instruct the driver about the route and the hazards of
the shipment. Furthermore, under the DOT requirements, HRCQ are
transported only over preferred routes (i.e., the Interstate Highway
System, an alternative route designated by a State routing agency, or
both), or an Interstate Highway System bypass or beltway around a city
when available, unless a State routing agency has designated an
alternative route. Routes can only be designated after substantive
consultation with affected local jurisdictions and with any other
affected States to ensure consideration of all impacts and continuity
of affected routes. A written route plan is to be prepared by the
carrier and provided to drivers and shippers.
The DOT allows motor carriers and drivers some deviation from the
preferred route when picking up or delivering material, making
necessary rest, fuel or motor vehicle repair stops, or because
emergency conditions make continued use of the preferred route unsafe
or impossible. In addition, a person may transport irradiated reactor
fuel only in compliance with a plan that will ensure the physical
security of the material. The DOT permits variation for security
purposes from the routing requirements of 49 CFR 397.101 only so far as
necessary to meet the requirements imposed under such a plan, or
otherwise imposed by NRC in 10 CFR Part 73.
For shipments by rail, the DOT requirements for routing radioactive
material are found within 49 CFR parts 172, 174 and 209. The DOT
requires rail carriers to compile annual data on certain shipments of
hazardous materials, including HRCQ. The data is used to analyze safety
and security risks along rail routes where those materials are
transported; assess alternative routing options; and make routing
decisions based on those assessments. Rail carriers must assess the
available routes ensuring, at a minimum, that 27 specific factors are
considered. These 27 factors include, but are not limited to,
consideration of rail traffic density, transit times, number and types
of grade crossings, proximity to iconic targets, population densities
and venues along the route.
Rail carriers must also seek relevant information from State,
local, and Tribal officials, as appropriate, regarding security risks
to high-consequence targets along or in proximity to a route used by a
rail carrier to transport security-sensitive materials. Oversight is
provided by the DOT Federal Railroad Administration (FRA), which
includes review and inspection of rail carrier's risk analyses and
route selection, but FRA does not pre-approve rail routes. If FRA
determines that a carrier's route selection documentation and
underlying analyses are deficient, the carrier may be required to
revise the analyses or make changes in the route selection. In
addition, if it is determined by DOT that a particular route chosen by
the railroad is not the safest and most secure practicable route
available, FRA can require the use of an alternative route until such
time as the identified deficiencies for the originally chosen route are
corrected by the railroad.
E. What are the NRC routing requirements for spent nuclear fuel
shipments?
For spent fuel in quantities greater than 100 grams and exceeding 1
Sv (100 rems) per hour at a distance of 0.91 meters (3 feet) from any
accessible surface without intervening shielding, licensees are
required to transport such spent nuclear fuel along routes that have
been pre-approved by NRC. Furthermore, the proposed rule text of Sec.
73.37(b)(1) requires licensees to preplan and coordinate their routes
with the States, including identification of safe havens.
The proposed rule does not include specific routing criteria for
licensees to use when developing routes. However, the objective of
Sec. 73.37 is to minimize the potential for theft, diversion, or
radiological sabotage for shipments of spent nuclear fuel. Licenses are
expected to develop routes by considering criteria including, but not
limited to: the DOT routing criteria, minimizing transit time,
likelihood of swift response by local law enforcement, availability of
safe havens (for road shipments), avoidance of tactically
disadvantageous positions, availability of appropriate rest and
refueling stops (for road shipments), and availability of good
transportation safety features. When selecting a route by road,
licensees are also expected to conduct surveys of the proposed route.
The objective of these surveys is to locate safe havens, evaluate
communications capability along the route, develop local law
enforcement contacts, identify food and fuel stops for the carrier, and
identify potential driving problems along the route.
Once a spent nuclear fuel shipment route request is received, the
NRC reviews it closely. The NRC conducts a detailed review, considering
route length and minimizing transit time, local law enforcement and
emergency response contact information, adequacy of safe haven
locations, and communications capability along the route. NUREG-0561,
``Physical Protection of Shipments of Irradiated Reactor Fuel''
provides guidance to licensees seeking the NRC-approval of a spent
nuclear fuel shipping route.
F. Why do the NRC and DOT routing requirements differ for spent nuclear
fuel shipments?
The objective of Sec. 73.37 is to minimize the potential for
theft, diversion or radiological sabotage of spent nuclear fuel
shipments; facilitate the location and recovery of spent fuel shipments
that may have come under the control of unauthorized persons; and delay
and impede attempts at theft, diversion or radiological sabotage of
spent nuclear fuel shipments until response forces arrive. With this in
mind, NRC expects licensees to route shipments according to the DOT
requirements, and to consider the adequacy of the route to meet the
objectives of Sec. 73.37. This includes considering the availability
and adequacy of safe havens along the route and the communications
capabilities among the transport vehicle, escort
[[Page 62700]]
vehicle, communications center, and local law enforcement agencies
(LLEAs) for the entire route.
The DOT HRCQ routing regulations for road shipments are based on
minimizing radiological risk to the public (49 CFR 397). The HRCQ are
to be transported over preferred routes which are described in more
detail in question D above. Carriers are permitted to deviate from
preferred routes for certain conditions including, but not limited to:
security reasons (e.g., as imposed by NRC in 10 CFR Part 73) and
emergencies. The DOT rail routing requirements for HRCQ require
carriers to consider both safety and security of the public when
selecting a route (49 CFR 172 and 209). The DOT requires rail carriers
to select routes based on the criteria described above in question D.
Rail carriers must assess the available routes using, at a minimum, 27
factors that address both safety and security of the transport.
As long as there is coordination among the licensee, the commercial
carrier and the States of passage, NRC determined that spent nuclear
fuel shipment primary and alternate routes for highway and rail can be
developed that satisfy both the DOT and NRC requirements and
guidelines. The NRC invites comments on the challenges of selecting
routes for spent nuclear fuel that meets both the DOT and NRC
requirements and guidance.
G. Why require procedures and training for the security of spent
nuclear fuel in transit?
The proposed Sec. Sec. 73.37(b)(3)(v) and (b)(4) would expressly
require that licensees shipping spent nuclear fuel develop normal and
contingency procedures. These procedures would cover notifications;
communication protocols; loss of communication; and responses to
actual, attempted, or suspicious activities. The proposed revisions
would also require drivers, accompanying personnel, railroad personnel,
and other movement control personnel to be adequately trained in normal
and contingency procedures. These proposed requirements would ensure
that all personnel associated with the shipment are prepared to prevent
the theft, diversion, or radiological sabotage of spent nuclear fuel
shipments. The proposed revisions would address, in part, PRM-73-10
items (3) and (6).
H. Why require a telemetric position monitoring system or an
alternative tracking system for continuous monitoring of spent nuclear
fuel shipments?
The current rule, at Sec. 73.37(b)(4), requires that the
licensee's physical protection plan include a communications center,
which will be staffed continuously by at least one individual who will
monitor the progress of the spent fuel shipment. The proposed rule
would reflect the availability of new technology and as such, the
ability to have more active control over the shipment by the licensee.
The proposed Sec. 73.37(b)(3)(i) would replace the term
``communications center'' with the term ``movement control center.''
The proposed Sec. 73.37(b)(3)(ii) would also require that the movement
control center be staffed continuously by at least one individual, who
will actively monitor the progress of the spent nuclear fuel shipment
and who has the authority to direct the physical protection activities.
The proposed Sec. 73.37(b)(3)(iii) would specify that the movement
control center must monitor the shipment continuously, i.e., from the
time of delivery of the shipment to the carrier for transport until
safe delivery of the shipment at its final destination, and must
immediately notify the appropriate agencies in the event of a
safeguards event under the provisions of Sec. 10 CFR 73.71.
In addition, the proposed Sec. Sec. 73.37(c)(5) and 73.37(d)(4),
for road and rail shipments respectively, would require movement
control centers to use a telemetric position monitoring system or an
alternative tracking system to monitor the location and status of
shipments at all times, which would provide a real time indication of
any potential threats. 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. Global positioning
systems (GPS) and radiofrequency identification (RFID) are examples of
telemetric position monitoring systems. Since the movement control
center is required to respond to any actual, attempted, or suspicious
activities, the proposed requirements would mitigate the likelihood of
theft, diversion, or radiological sabotage of spent nuclear fuel
shipments.
I. Why pre-plan and coordinate spent nuclear fuel shipments?
The current regulations require limited shipment preplanning and
coordination with NRC, States, and LLEAs. For example, the current
Sec. 73.37(f) regulation requires an advance notification to the
Governor (or designee) by mail to be postmarked at least 7 days before
transport of a shipment within or through the State; and require a
messenger-delivered notification to reach the Office of the Governor
(or designee) at least 4 days before transport of a shipment within or
through the State. Some States have indicated that the current
notification requirements are insufficient to adequately plan for a
spent nuclear fuel shipment. In addition, the current Sec. 73.37(b)(7)
regulation requires licensees to obtain the advance NRC approval of the
routes used for road and rail shipments of spent nuclear fuel, but does
not require prior State coordination of the route. The proposed
amendments would ensure that the affected States have early and
substantial involvement in the management of spent nuclear fuel
shipments by participating in the initial stages of the planning,
coordination, and implementation of the shipment.
Proposed Sec. 73.37(b)(1)(iv) would require licensees to preplan
and coordinate spent nuclear fuel shipment information with the
Governors of the States which the shipment will transit across in order
to: (1) Ensure minimal shipment delays; (2) arrange for State law
enforcement escorts; (3) coordinate movement control information, as
needed; (4) coordinate safe haven locations; and (5) coordinate the
shipping route. The proposed requirements would ensure that no unusual
event associated with the shipment goes unnoticed or unreported. These
proposed revisions mitigate the risk of theft, diversion, or
radiological sabotage of a spent nuclear fuel shipment. These proposed
revisions would address, in part, PRM-73-10 items 3 and 6.
J. Why require constant visual surveillance by armed escort?
Existing Sec. 73.37(b)(9) requires constant visual surveillance by
an escort when a shipment is stopped. It does not specify whether the
escort should be armed. Proposed Sec. 73.37(b)(3)(vii)(C) would ensure
that when a shipment is stopped, at least one armed escort maintains
constant visual surveillance. The constant surveillance by an armed
escort while a shipment is stopped provides assurance that attempts by
an
[[Page 62701]]
adversary to either perform radiological sabotage in place, or to gain
control of the transport to move it to another location are impeded or
stopped. The requirements of proposed Sec. 73.37(b)(3)(vii)(C) would
address parked or stopped road shipments, rail shipment stops in
marshaling areas, and docked sea shipments. It would also require
periodic reports of shipment status to the movement control center by
the armed escort. The proposed Sec. 73.37(b)(3)(vii)(C) would provide
adequate assurance that spent nuclear fuel shipments are protected from
theft, diversion, or radiological sabotage when stopped.
K. Why require two-way redundant communication capabilities?
The regulations in the current Sec. Sec. 73.37(c), 73.37(d), and
73.37(e) provide for redundant communication capabilities; however, the
requirements are specific, i.e., use of citizens band radio and
radiotelephone. In view of the continued advancements in technology,
these methods of communication could become obsolete in the near
future. Instead of specifying an acceptable communications technology,
the proposed revisions describe the performance characteristics of the
communications capabilities.
Proposed Sec. Sec. 73.37(c)(3), 73.37(d)(3) and 73.37(e)(4) would
require the establishment of two-way communication capabilities for the
transport vehicle and escorts to ensure contact between the movement
control center and LLEAs at all times. The revisions would also require
the establishment of alternate capabilities for the transport vehicle
and escorts to contact the movement control center. The alternate
communications cannot be subject to the same interference factors. The
same interference factors are defined as any two systems that rely on
the same hardware or software to transmit their signal (e.g., cell
tower, proprietary network). These requirements would provide the
capability for continued communication between movement control
personnel, which would ensure the prompt reporting of any incident that
could lead to theft, diversion, or radiological sabotage.
L. Why require background investigations?
1. What is the objective of the background investigations requirements
for those with unescorted access and access authorization relative to
spent nuclear fuel in transit?
The proposed rule would add a new Sec. 73.38 that would require
licensees to conduct background investigations of those individuals
being considered for unescorted access or access authorization relative
to spent nuclear fuel in transit. The main objective of the background
investigations is to ensure that those individuals who have unescorted
access to spent nuclear fuel in transit and those individuals who have
access to safeguards information relative to the spent nuclear fuel
shipment, including but not limited to armed escorts, drivers, and
movement control personnel are trustworthy and reliable and do not
constitute an unreasonable risk to the public health and safety or
common defense and security. These background investigations are
similar to those already in place for unescorted access to a commercial
nuclear power reactor in Sec. 73.56(d), Background Investigation.
2. What is the basis for the fingerprinting requirements in the
proposed rule?
Section 149 of AEA requires that any person who is permitted
unescorted access to radioactive materials subject to regulation by the
Commission be fingerprinted for FBI identification and criminal history
records check. However, Section 149 also requires that the Commission
make a determination that such radioactive material is of such
significance to the public health and safety or the common defense and
security as to warrant fingerprinting and background checks before the
Commission can exercise the authority provided by Section 149.
Pursuant to Section 149, the Commission has determined that the
transportation of irradiated fuel (spent nuclear fuel) is of such
significance to the public health and safety or the common defense and
security as to warrant fingerprinting and background checks for those
individuals who have such access to the materials in transit. Persons
who have ``unescorted access'' to this material for purposes of Section
149, are persons accompanying the shipment of spent nuclear fuel during
transit who have direct access and maintain control over the spent
nuclear fuel. These persons may include, but are not limited to, the
driver armed escorts and movement control center personnel.
Therefore, under the authority granted by Section 149, this rule
would impose a requirement for fingerprinting as a prerequisite to
granting unescorted access to spent nuclear fuel in transit. The
criminal history records check obtained as a result of that
fingerprinting would be used by licensees as part of the overall
background investigation to determine the trustworthiness and
reliability of these individuals prior to permitting unescorted access.
3. What are the components of a background investigation?
Proposed Sec. 73.38(d) lists the requirements for a background
investigation, including: informed consent, fingerprinting for an FBI
identification and criminal history records check; verification of true
identity; employment history evaluation; verification of education and
military history; credit history evaluation; local criminal history
review; and character and reputation determination.
Under proposed Sec. 73.38(e), it is the licensee's responsibility
to make a trustworthiness and reliability determination of an
individual who has unescorted access or access authorization relative
to a spent nuclear fuel shipment. It is expected that licensees will
use their best efforts to obtain the information required to conduct a
background investigation to determine the individuals' trustworthiness
and reliability.
The full credit history evaluation requirement, in proposed Sec.
73.38(d)(6), reflects the NRC's intent that all financial information
available through credit reporting agencies is to be obtained and
evaluated because it has the potential to provide highly pertinent
information. The NRC recognizes that some countries may not have
routinely accepted credit reporting mechanisms, and therefore, the NRC
allows multiple sources of credit history that could potentially
provide information about a foreign national's financial record and
responsibility.
Fingerprinting an individual for an FBI criminal history records
check, as would be required by the proposed Sec. 73.38(d)(3), is an
important element of the background investigation for determining the
trustworthiness and reliability of an individual. 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. In
addition, the local criminal history review, which
[[Page 62702]]
would be required by the proposed Sec. 73.38(d)(7) provides the
licensee with a record of local criminal activity that may adversely
impact an individual's trustworthiness and reliability.
It is noted that the proposed Sec. 73.38(d)(5)(iv) would require
licensees to document any refusals by outside entities to provide
information on an individual. If local law enforcement, a previous
employer, an 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 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. An alternate source
could be another person associated with the entity or institution. For
example, if the human resources department of a company will not verify
the employment history of the individual, an alternate source could be
the individual's supervisor during the claimed period. The proposed
Sec. 73.38(d)(10) is patterned after the requirements of Sec.
73.56(d)(4)(iv).
4. What information should the licensee use to determine that an
individual is trustworthy and reliable?
The licensee 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 licensee may not determine that an individual is
trustworthy and reliable and grant them unescorted access to spent
nuclear fuel in transit until all of the information for the background
investigation has been obtained and evaluated. The licensee may deny an
individual unescorted access based on any information obtained at any
time during the background investigation. The proposed Sec. 73.38(e)
includes a provision for licensees to document their determinations of
trustworthiness and reliability.
5. How frequently would a reinvestigation be required?
The proposed rule would include a provision, Sec. 73.38(h), that
would require a reinvestigation every 10 years to help maintain the
integrity of the program. This reinvestigation requirement 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
fingerprinting, FBI identification and criminal history records check,
local criminal history review and credit history check. The
reinvestigation would not include employment verification, education
verification, military history verification, or the character and
reputation determination for the reinvestigation.
6. Are licensees required to protect information obtained during a
background investigation?
Yes. The proposed Sec. Sec. 73.38(f)(1)-(2) would require
licensees to protect the information obtained during a background
investigation. Licensees would only be permitted to disclose the
information to the subject individual, the individual's representative,
those who have a need-to-know to perform their assigned duties to grant
or deny unescorted access, or an authorized representative of NRC. This
proposed revision is consistent with the requirements of Sec.
73.57(f).
7. Could a licensee transfer personal information obtained during an
investigation to another licensee?
Yes. The proposed Sec. 73.38(f)(3) includes a provision that 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.
8. Which records are required to be maintained?
The proposed Sec. 73.38(f)(5) would require licensees 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 spent nuclear
fuel in transit.
M. Why enhance shipment notifications to NRC?
The current regulations in Sec. 73.72(a)(4) require an NRC
notification, by phone, at least 2 days before the shipment commences.
The proposed rule would revise Sec. 73.72(a)(4) to require 2
additional notifications of NRC, one to be made 2 hours before the
shipment commences, and the other to be made when the shipment reaches
its final destination. These additional notifications allow NRC to
monitor spent nuclear fuel shipments, and to maximize its readiness in
case of a safeguards event. The notification of shipment completion
allows NRC to resume normal operations.
To further enhance notification of NRC, the proposed revision would
remove the Sec. 73.72(b) exemption for shipments of spent nuclear fuel
that are transported on public roads. Currently, the requirements of
Sec. 73.72(b) exempt licensees who make a road shipment or transfer
with one-way transit times of one hour or less between installations of
the licensee from providing advance notification of the shipment to
NRC. The proposed revision would require that NRC be informed of any
spent nuclear fuel shipment on a public road so that NRC is able to
monitor spent nuclear fuel shipments and to maximize its readiness in
case of a safeguards event. These proposed revisions mitigate the risk
of theft, diversion, or radiological sabotage of a shipment.
N. Which type of spent nuclear fuel does DOE ship?
The DOE spent nuclear fuel shipments generally fall into two
categories: Classified and non-classified shipments of spent nuclear
fuel. Classified shipments are those shipments which involve national
security. Classified shipments of spent nuclear fuel typically consist
of spent fuel from the U.S. Navy. The DOE has broad authority under the
Atomic Energy Act of 1954, as amended (AEA), to regulate all aspects of
activities involving radioactive materials that are undertaken by DOE
or on its behalf, including the transportation of radioactive
materials. The DOE conducts classified shipments of spent nuclear fuel
using their Office of Secure Transport (OST). The OST shipments are
escorted full-time by armed, specially trained (trained in
communications, firearms, tactics, observation, and use of deadly
force) active duty Navy personnel who maintain 24-hour surveillance.
The OST Transportation Emergency Communications Center monitors,
tracks, and provides communication with every shipment. The NRC does
not regulate classified shipments of spent nuclear fuel.
O. What is a non-classified shipment of spent nuclear fuel and what are
the DOE requirements for this type of shipment?
Non-classified shipments of spent nuclear fuel typically consist of
spent fuel from commercial nuclear power reactors and research and test
reactors. The DOE policy for non-classified spent nuclear fuel
shipments are found under the DOE Orders 460.1C, Packaging and
Transportation Safety and 460.2A,
[[Page 62703]]
Departmental Materials Transportation and Packaging Management. As a
matter of policy, the DOE non-classified spent nuclear fuel shipments
are conducted under the requirements and standards applicable to
comparable commercial shipments, i.e., the NRC requirements, except if
there is a determination that national security or another critical
interest requires different action.
The DOE requirements are set forth in the DOE Manual 460.2-1A,
Radioactive Material Transportation Practices Manual. In this manual,
it states that ``Security will be provided in compliance with the NRC
requirements in 10 CFR Part 73 for shipments subject to a NRC license.
Other DOE shipments will be undertaken in a manner that meets or
exceeds the NRC security requirements.'' The DOE organizations and
contractors ensure that in-transit requirements are addressed,
including developing security plans, implementing information and
physical security access controls, training, escorts, inspections,
tracking, communications, and employee background checks.
P. How are the NRC and DOE requirements similar and how are they
different?
As stated in O above, given the DOE policy to ``meet or exceed''
the NRC security requirements, the NRC and DOE requirements are
similar. Similar to the NRC requirements, the DOE program organizations
are expected to liaison with Federal, State, local and Tribal law
enforcement/security officials regarding such shipments. This liaison
should include a determination as to whether the State, Tribal or local
jurisdictions are planning to provide escorts for the shipment. The DOE
also expects drivers and escorts to maintain constant surveillance of
the shipment.
One major difference between the NRC and DOE requirements deals
with the tracking and monitoring of spent nuclear fuel shipments. The
DOE requires the use of their Transportation Tracking and
Communications System (TRANSCOM). In the proposed rule, NRC requires
continuous and active monitoring of spent nuclear fuel shipments, but,
a particular tracking method is not specified. The NRC determined that
providing the performance objectives for continuous and active
monitoring, rather than specifying a particular system gives a licensee
flexibility to choose a system that works with their shipping
situation.
Another difference between the NRC and DOE requirements is the
protection of information. For NRC, information associated with a spent
fuel shipment (i.e., shipment schedules and security plans) are
protected as safeguards information (SGI) as specified by the
requirements of Sec. Sec. 73.21 and 73.22. The DOE does not have a
system of information protection comparable to SGI. Shipment
information for the DOE non-classified spent nuclear fuel shipment is
official use only, unless there is a reason to designate it as
classified.
Q. Who would this action affect?
The proposed amendments affect all the NRC licensees that are
authorized to possess and transport spent nuclear fuel. This includes,
but is not limited to, licensees of commercial power reactors, research
and test reactors, and independent spent fuel storage installations,
who transport, or deliver to a carrier for transport, in a single
shipment, a quantity of irradiated reactor fuel in excess of 100 grams
(0.22 lbs) 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 rems) per hour at a distance
of .91 meters (3 feet) from any accessible surface without intervening
shielding.
R. Does NRC plan to issue guidance on these proposed requirements?
In conjunction with this the proposed rulemaking, NRC is revising
NUREG-0561, ``Physical Protection of Shipments of Irradiated Reactor
Fuel in Transit,'' which was published in June 1980, to address the new
requirements in the proposed rule. NUREG-0561 provides general guidance
to licensees concerning the establishment of an acceptable security
program for spent nuclear fuel shipments.
S. What should I consider as I prepare my comments to NRC?
Tips for preparing your comments: When submitting your comments,
remember to:
i. Identify the rulemaking (Docket ID: NRC-2009-0163).
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.
viii. See Section VII of the preamble for the request for comments
on the use of plain language and Section XII for the request for
comments on the draft regulatory analysis.
IV. Discussion of the Proposed Amendments by Section
A. Proposed Sec. 73.37(a)(1)
The proposed rule would revise Sec. 73.37(a)(1) to include the
International System of Measurement (SI) accompanied by the equivalent
English units in parentheses for the weight and dose rate measurements.
This is under the NRC's metrication policy (57 FR 46202, October 7,
1992), and the Metric Conversion Act of 1975, 15 U.S.C. 205a et seq.
The proposed rule would also add a footnote to clarify that the term
``irradiated reactor fuel,'' as used in 10 CFR 73.37 fn.1, means
``spent nuclear fuel.''
B. Proposed Sec. 73.37(a)(1)(i)
The language in the current regulation solely addresses potential
radiological sabotage of spent nuclear fuel shipments. The proposed
rule would revise Sec. 73.37(a)(1)(i) to clarify that any attempted
theft or diversion of spent nuclear fuel shipments is also covered by
this regulation.
The proposed rule would also revise Sec. Sec. 73.37(a)(1)(i) and
(a)(2)(iii) to remove the distinction between heavily populated areas
and other areas through or across which a spent nuclear fuel shipment
may pass. The differentiation of security requirements based upon
population densities creates potential vulnerabilities in the physical
security of the shipment. The proposed requirement of armed escorts
throughout the shipment route minimizes the risk of theft, diversion,
or radiological sabotage. The proposed revisions would also address
items 4 and 5 of the PRM-73-10.
C. Proposed Sec. 73.37(a)(2)
The proposed rule would revise Sec. 73.37(a)(2) to insert
``system'' after the word phrase ``physical protection'' to read as
``physical protection system.'' This change provides consistency in the
terminology used throughout 10 CFR Part 73.
The proposed revision would renumber the paragraphs in Sec.
73.37(a)(2). The current Sec. 73.37(a)(2)(ii) would become the
proposed Sec. 73.37(a)(2)(iii), and the current Sec. 73.37(a)(2)(iii)
would become the proposed Sec. 73.37(a)(2)(ii). The
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proposed rule would revise the current Sec. 73.37(a)(2)(iii) to
clarify that the licensee should delay, as well as impede, any
attempted theft, diversion, or radiological sabotage of spent nuclear
fuel shipments.
D. Proposed Sec. 73.37(b)
This overall section is revised to provide a logical, step-by-step
approach to the development of a physical protection system for spent
nuclear fuel shipments that is more user-friendly.
E. Proposed Sec. 73.37(b)(1)
The proposed rule would add a new section entitled, ``Preplan and
Coordinate Spent Nuclear Fuel Shipments,'' which is explained in
further detail below. The proposed rule would move and incorporate the
current Sec. 73.37(b)(1) into a new Sec. 73.37(b)(2).
The proposed rule would add a new Sec. 73.37(b)(1)(i) which
requires that licensees instruct armed escorts on the use of deadly
force. The existing provisions of Sec. 73.37 provide performance
objectives to be achieved by the physical protection system for spent
nuclear fuel shipments. These performance objectives are not specific
about the degree of force an armed escort may use in protecting
shipments.
Specifically, the licensee is to ensure that each non-LLEA armed
escort delay or impede attempted acts of theft, diversion, or
radiological sabotage by using force sufficient to counter the force
directed at that person, including the use of deadly force when there
is a reasonable belief that the use of deadly force is necessary in
self-defense or in the defense of others, or any other circumstances as
authorized by applicable Federal or State law. The requirements for use
of deadly force are established under applicable Federal and State laws
(i.e., the States through which the shipment is passing). It should be
noted that the proposed revision is not authorizing the use of deadly
force, but instead is ensuring that the armed guards are knowledgeable
of the Federal and State statutes that apply regarding the use of
deadly force. The statutes regarding the use of deadly force may vary
depending on the jurisdiction in which the shipment is located. Armed
escorts are expected to carry out their assigned duties, including
implementation of contingency procedures in case of attack, in a manner
consistent with the legal requirements applicable to other private
armed guards in a particular jurisdiction. The LLEA personnel escorts
are exempt from this requirement since they are subject to, and should