[Federal Register Volume 80, Number 24 (Thursday, February 5, 2015)]
[Rules and Regulations]
[Pages 6430-6435]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-02310]
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NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2014-0233]
RIN 3150-AJ47
List of Approved Spent Fuel Storage Casks: Holtec International
HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Amendment
No. 8, Revision No. 1
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its
spent fuel storage regulations by revising the Holtec International HI-
STORM 100 Cask System listing within the ``List of approved spent fuel
storage casks'' to add Revision No. 1 to Amendment No. 8 (effective May
2, 2012, and corrected on November 16, 2012), to the Certificate of
Compliance (CoC) No. 1014. Amendment No. 8, Revision No. 1, changes
burnup/cooling time limits for thimble plug devices; changes Metamic-HT
material testing requirements; changes Metamic-HT material minimum
guaranteed values; and updates fuel definitions to allow boiling water
reactor fuel affected by certain corrosion mechanisms with specific
guidelines to be classified as undamaged fuel.
DATES: The direct final rule is effective April 21, 2015, unless
significant adverse comments are received by March 9, 2015. If the
direct final rule is withdrawn as a result of such comments, timely
notice of the withdrawal will be published in the Federal Register.
Comments received after this date will be considered if it is practical
to do so, but the NRC staff is
[[Page 6431]]
able to ensure consideration only for comments received on or before
this date. Comments received on this direct final rule will also be
considered to be comments on a companion proposed rule published in the
Proposed Rules section of this issue of the Federal Register.
ADDRESSES: You may submit comments by any one of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0233. Address
questions about NRC dockets to Carol Gallagher, telephone: 301-287-
3422; email: [email protected]. For technical questions, please
contact the individual listed in the FOR FURTHER INFORMATION CONTACT
section of this document.
Email comments to: [email protected]. If you do
not receive an automatic email reply confirming receipt, then contact
us at 301-415-1677.
Fax comments to: Secretary, U.S. Nuclear Regulatory
Commission at 301-415-1101.
Mail comments to: Secretary, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, ATTN: Rulemakings and
Adjudications Staff.
Hand deliver comments to: 11555 Rockville Pike, Rockville,
Maryland 20852, between 7:30 a.m. and 4:15 p.m. (Eastern Time) Federal
workdays; telephone: 301-415-1677.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Gregory R. Trussell, Office of Nuclear
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001; telephone: 301-415-6445, email:
[email protected].
SUPPLEMENTARY INFORMATION:
Table of Contents
I. Obtaining Information and Submitting Comments
II. Procedural Background
III. Background
IV. Discussion of Changes
V. Voluntary Consensus Standards
VI. Agreement State Compatibility
VII. Plain Writing
VIII. Environmental Assessment and Finding of No Significant
Environmental Impact
IX. Paperwork Reduction Act Statement
X. Regulatory Flexibility Certification
XI. Regulatory Analysis
XII. Backfitting and Issue Finality
XIII. Congressional Review Act
XIV. Availability of Documents
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2014-0233 when contacting the NRC
about the availability of information for this action. You may obtain
publicly-available information related to this action by any of the
following methods:
Federal rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0233.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to: [email protected]. For
the convenience of the reader, instructions about obtaining materials
referenced in this document are provided in the ``Availability of
Documents'' section.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2014-0233 in the subject line of your
comment submission, in order to ensure that the NRC is able to make
your comment submission available to the public in this docket.
The NRC cautions you not to include identifying or contact
information in comment submissions that you do not want to be publicly
disclosed in your comment submission. The NRC will post all comment
submissions at http://www.regulations.gov as well as enter the comment
submissions into ADAMS, and the NRC does not routinely edit comment
submissions to remove identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment into ADAMS.
II. Procedural Background
This direct final rule is limited to adding Amendment No. 8,
Revision No. 1, which will supersede Amendment No. 8 (effective May 2,
2012, and corrected on November 16, 2012), to CoC No. 1014 to the
``List of approved spent fuel storage casks,'' and does not include
other aspects of the Holtec International HI-STORM 100 Cask System
design. Amendment No. 8 continues to be effective but is now being
modified with respect to certain specified provisions, as outlined in
Amendment No. 8, Revision 1, which apply to all general licensees using
the casks for Independent Spent Fuel Storage Installations (ISFSI).
Thus, Amendment No. 8, Revision 1, supersedes the previously issued
Amendment No. 8 (effective May 2, 2012, and corrected on November 16,
2012). In requesting this revision, Holtec indicated that it has not
manufactured any cask under CoC No. 1014, Amendment No. 8, and,
consequently, no ISFSI licensee has placed such a cask into service.
The NRC is using the ``direct final rule procedure'' to issue this
revision because it represents a limited and routine change to an
existing CoC that is expected to be noncontroversial. Adequate
protection of public health and safety continues to be ensured. This
amendment to the rule will become effective on April 21, 2015. However,
if the NRC receives significant adverse comments on this direct final
rule by March 9, 2015, then the NRC will publish a document that
withdraws this action and will subsequently address the comments
received in a final rule as a response to the companion proposed rule
published in the Proposed Rule section of this issue of the Federal
Register. Absent significant modifications to the proposed revisions
requiring republication, the NRC will not initiate a second comment
period on this action.
A significant adverse comment is a comment where the commenter
explains why the rule would be inappropriate, including challenges to
the rule's underlying premise or approach, or would be ineffective or
unacceptable without a change. A comment is adverse and significant if:
(1) The comment opposes the rule and provides a reason sufficient
to require a substantive response in a notice-and-comment process. For
example, a substantive response is required when:
[[Page 6432]]
(a) The comment causes the NRC staff to reevaluate (or reconsider)
its position or conduct additional analysis;
(b) The comment raises an issue serious enough to warrant a
substantive response to clarify or complete the record; or
(c) The comment raises a relevant issue that was not previously
addressed or considered by the NRC staff.
(2) The comment proposes a change or an addition to the rule, and
it is apparent that the rule would be ineffective or unacceptable
without incorporation of the change or addition.
(3) The comment causes the NRC staff to make a change (other than
editorial) to the rule, CoC, or Technical Specifications (TSs).
For detailed instructions on filing comments, please see the
ADDRESSES section of this document.
III. Background
Section 218(a) of the Nuclear Waste Policy Act (NWPA) of 1982, as
amended, requires that ``the Secretary [of the Department of Energy]
shall establish a demonstration program, in cooperation with the
private sector, for the dry storage of spent nuclear fuel at civilian
nuclear power reactor sites, with the objective of establishing one or
more technologies that the [Nuclear Regulatory] Commission may, by
rule, approve for use at the sites of civilian nuclear power reactors
without, to the maximum extent practicable, the need for additional
site-specific approvals by the Commission.'' Section 133 of the NWPA
states, in part, that ``[the Commission] shall, by rule, establish
procedures for the licensing of any technology approved by the
Commission under Section 219(a) [sic: 218(a)] for use at the site of
any civilian nuclear power reactor.''
To implement this mandate, the Commission approved dry storage of
spent nuclear fuel in NRC-approved casks under a general license by
publishing a final rule which added a new subpart K in part 72 of Title
10 of the Code of Federal Regulations (10 CFR) entitled, ``General
License for Storage of Spent Fuel at Power Reactor Sites'' (55 FR
29181; July 18, 1990). This rule also established a new subpart L in 10
CFR part 72 entitled, ``Approval of Spent Fuel Storage Casks,'' which
contains procedures and criteria for obtaining NRC approval of spent
fuel storage cask designs. The NRC subsequently issued a final rule on
May 1, 2000 (65 FR 25241), that approved the Holtec International HI-
STORM 100 Cask System design and added it to the list of NRC-approved
cask designs in 10 CFR 72.214 as CoC No. 1014.
IV. Discussion of Changes
By letter dated August 21, 2013, and as supplemented on December
20, 2013, and February 28, 2014, Holtec International submitted a
revision request for the Holtec International HI-STORM 100 Cask System,
CoC No. 1014, Amendment No. 8. As a revision, the CoC will supersede
the previous version of the CoC and TSs that were effective May 2,
2012, as corrected on November 16, 2012, in their entirety. Amendment
No. 8, Revision No. 1, changes burnup/cooling time limits for thimble
plug devices; changes Metamic-HT material testing requirements; changes
Metamic-HT material minimum guaranteed values; and updates fuel
definitions to allow boiling water reactor fuel affected by certain
corrosion mechanisms within specific guidelines to be classified as
undamaged fuel.
As documented in the safety evaluation report (SER), the NRC staff
performed a detailed safety evaluation of the proposed CoC amendment
request. There are no significant changes to cask design requirements
in the proposed CoC amendment. Considering the specific design
requirements for each accident condition, the design of the cask would
prevent loss of containment, shielding, and criticality control. If
there is no loss of containment, shielding, or criticality control, the
environmental impacts would be insignificant. This amendment does not
reflect a significant change in design or fabrication of the cask. In
addition, any resulting occupational exposure or offsite dose rates
from the implementation of Amendment No. 8, Revision No. 1, would
remain well within the 10 CFR part 20 limits. Therefore, the proposed
CoC changes will not result in any radiological or non-radiological
environmental impacts that significantly differ from the environmental
impacts evaluated in the environmental assessment supporting the July
18, 1990, final rule. There will be no significant change in the types
or amounts of any effluent released, no significant increase in
individual or cumulative radiation exposure and no significant increase
in the potential for or consequences of radiological accidents.
This direct final rule revises the Holtec International HI-STORM
100 Cask System listing in 10 CFR 72.214 by adding Amendment No. 8,
Revision No. 1, to CoC No. 1014. The amendment consists of the changes
previously described, as set forth in the revised CoC and TSs. The
revised TSs are identified in the SER.
The amended Holtec International HI-STORM 100 Cask System design,
when used under the conditions specified in the CoC, the TSs, and the
NRC's regulations, will meet the requirements of 10 CFR part 72;
therefore, adequate protection of public health and safety will
continue to be ensured. When this direct final rule becomes effective,
persons who hold a general license under 10 CFR 72.210 may load spent
nuclear fuel into the Holtec International HI-STORM 100 Cask Systems
that meet the criteria of Amendment No. 8, Revision No. 1, to CoC No.
1014 under 10 CFR 72.212.
V. Voluntary Consensus Standards
The National Technology Transfer and Advancement Act of 1995 (Pub.
L. 104-113) requires that Federal agencies use technical standards that
are developed or adopted by voluntary consensus standards bodies unless
the use of such a standard is inconsistent with applicable law or
otherwise impractical. In this direct final rule, the NRC will revise
the Holtec International HI-STORM 100 Cask System design listed in 10
CFR 72.214. This action does not constitute the establishment of a
standard that contains generally applicable requirements.
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 direct final rule is classified as Compatibility Category
``NRC.'' Compatibility is not required for Category ``NRC''
regulations. The NRC program elements in this category relate directly
and exclusively to areas of regulation reserved to the NRC by the
Atomic Energy Act of 1954, as amended, or the provisions of 10 CFR.
Although an Agreement State may not adopt program elements reserved to
the 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.
VII. Plain Writing
The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal
agencies to write documents in a clear, concise, well-organized manner.
The NRC has written this document to be consistent with the Plain
Writing Act, as well as the Presidential memorandum, ``Plain Language
in Government Writing,'' published June 10, 1998 (63 FR 31883).
[[Page 6433]]
VIII. Environmental Assessment and Finding of No Significant
Environmental Impact
A. The Action
The action is to amend 10 CFR 72.214 to revise the Holtec
International HI-STORM 100 Cask System listing within the ``List of
approved spent fuel storage casks'' to revise Amendment No. 8
(effective May 2, 2012, and corrected on November 16, 2012), of CoC No.
1014 by adding Amendment No. 8, Revision No. 1. Under the National
Environmental Policy Act of 1969, as amended, and the NRC's regulations
in subpart A of 10 CFR part 51, ``Environmental Protection Regulations
for Domestic Licensing and Related Regulatory Functions,'' the NRC has
determined that this 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. The
NRC has made a finding of no significant impact on the basis of this
environmental assessment.
B. The Need for the Action
This direct final rule amends the CoC for the Holtec International
HI-STORM 100 Cask System design within the list of approved spent fuel
storage casks that power reactor licensees can use to store spent fuel
at reactor sites under a general license. Specifically, Amendment No.
8, Revision No. 1, changes burnup/cooling time limits for thimble plug
devices; changes Metamic-HT material testing requirements; changes
Metamic-HT material minimum guaranteed values; and updates fuel
definitions to allow boiling water reactor fuel affected by certain
corrosion mechanisms within specific guidelines to be classified as
undamaged fuel.
C. Environmental Impacts of the Action
On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10
CFR part 72 to provide for the storage of spent fuel under a general
license in cask designs approved by the NRC. The potential
environmental impact of using NRC-approved storage casks was initially
analyzed in the environmental assessment for the 1990 final rule. The
environmental assessment for this Amendment No. 8, Revision No. 1,
tiers off of the environmental assessment for the July 18, 1990, final
rule. Tiering on past environmental assessments is a standard process
under the National Environmental Policy Act.
Holtec International HI-STORM 100 Cask Systems are designed to
mitigate the effects of design basis accidents that could occur during
storage. Design basis accidents account for human-induced events and
the most severe natural phenomena reported for the site and surrounding
area. Postulated accidents analyzed for an ISFSI, the type of facility
at which a holder of a power reactor operating license would store
spent fuel in casks in accordance with 10 CFR part 72, include tornado
winds and tornado-generated missiles, a design basis earthquake, a
design basis flood, an accidental cask drop, lightning effects, fire,
explosions, and other incidents.
Considering the specific design requirements for each accident
condition, the design of the cask would prevent loss of containment,
shielding, and criticality control. If there is no loss of containment,
shielding, or criticality control, the environmental impacts would be
insignificant. This amendment does not reflect a significant change in
design or fabrication of the cask. In addition, because there are no
significant designs or production process changes, any resulting
occupational exposures or offsite dose rates from the implementation of
Amendment No. 8, Revision No. 1, would remain well within the 10 CFR
part 20 limits. Therefore, the proposed CoC changes will not result in
either radiological or non-radiological environmental impacts that
significantly differ from the environmental impacts evaluated in the
environmental assessment supporting the July 18, 1990, final rule.
There will be no significant change in the types or amounts of any
effluent released, no significant increase in individual or cumulative
radiation exposures, and no significant increase in the potential for
or consequences from radiological accidents. The staff documented its
safety findings in the SER for this amendment.
D. Alternative to the Action
The alternative to this action is to deny approval of the changes
in Amendment No. 8, Revision No. 1, and terminate the direct final
rule. Consequently, any 10 CFR part 72 general licensee that seeks to
load spent nuclear fuel into Holtec International HI-STORM 100 Cask
Systems in accordance with the changes described in proposed Amendment
No. 8, Revision No. 1, would have to request an exemption from the
requirements of 10 CFR 72.212 and 72.214. Under this alternative,
interested licensees would have to prepare, and the NRC would have to
review, a separate exemption request, thereby increasing the
administrative burden on the NRC and the cost to each licensee.
Therefore, the environmental impacts would be the same or less than the
action.
E. Alternative Use of Resources
Approval of Amendment No. 8, Revision No. 1, of CoC No. 1014 would
result in no irreversible commitments of resources.
F. Agencies and Persons Contacted
No agencies or persons outside the NRC were contacted in connection
with the preparation of this environmental assessment.
G. Finding of No Significant Impact
The environmental impacts of the action have been reviewed under
the requirements in 10 CFR part 51. Based on the foregoing
environmental assessment, the NRC concludes that this direct final rule
entitled, ``List of Approved Spent Fuel Storage Casks: Holtec
International HI-STORM 100 Cask System, Certificate of Compliance No.
1014, Amendment No. 8, Revision No. 1,'' will not have a significant
effect on the human environment. Therefore, the NRC has determined that
an environmental impact statement is not necessary for this direct
final rule.
IX. Paperwork Reduction Act Statement
This direct final rule does not contain any information collection
requirements and, therefore, is not subject to the Paperwork Reduction
Act of 1995 (44 U.S.C. 3501 et seq.).
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.
X. Regulatory Flexibility Certification
Under the Regulatory Flexibility Act of 1980 (5 U.S.C. 605(b)), the
NRC certifies that this direct final rule will not, if issued, have a
significant economic impact on a substantial number of small entities.
This direct final rule affects only nuclear power plant licensees and
Holtec International. These entities 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 the NRC (10 CFR
2.810).
XI. Regulatory Analysis
On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10
CFR part 72 to provide for the storage of spent nuclear fuel under a
general
[[Page 6434]]
license in cask designs approved by the NRC. Any nuclear power reactor
licensee can use NRC-approved cask designs to store spent nuclear fuel
if it notifies the NRC in advance, the spent fuel is stored under the
conditions specified in the cask's CoC, and the conditions of the
general license are met. A list of NRC-approved cask designs is
contained in 10 CFR 72.214.
On May 1, 2000 (65 FR 25241), the NRC issued an amendment to 10 CFR
part 72 that approved the Holtec International HI-STORM 100 Cask System
design by adding it to the list of NRC-approved cask designs in 10 CFR
72.214.
On August 21, 2013, and as supplemented on December 20, 2013, and
February 28, 2014, Holtec International submitted a revision request
for the HI-STORM 100 Cask System, CoC No. 1014, Amendment No. 8, as
described in Section III, ``Discussion of Changes,'' of this document.
The alternative to this action is to withhold approval of the
changes requested in Amendment No. 8, Revision No. 1, and require any
10 CFR part 72 general licensee seeking to load spent nuclear fuel into
the Holtec International HI-STORM 100 Cask System under the changes
described in Amendment No. 8, Revision No. 1, to request an exemption
from the requirements of 10 CFR 72.212 and 72.214. Under this
alternative, each interested 10 CFR part 72 licensee would have to
prepare, and the NRC would have to review, a separate exemption
request, thereby increasing the administrative burden on the NRC and
the costs to each affected licensee.
Approval of this direct final rule is consistent with previous NRC
actions. Further, as documented in the SER and the environmental
assessment, the direct final rule will have no significant adverse
effect on public health and safety or the environment. This direct
final rule has no significant identifiable impact or benefit on other
Government agencies. Based on this regulatory analysis, the NRC
concludes that the requirements of the direct final rule are
commensurate with the NRC's responsibilities for public health and
safety and the common defense and security. No other available
alternative is believed to be satisfactory, and therefore, this action
is recommended.
XII. Backfitting and Issue Finality
The NRC has determined that the backfit rule (10 CFR 72.62) does
not apply to this direct final rule and therefore, a backfit analysis
is not required. This direct final rule revises CoC No. 1014 for the
Holtec International HI-STORM 100 Cask System, as currently listed in
10 CFR 72.214, ``List of approved spent fuel storage casks.'' Amendment
No. 8, Revision No. 1, changes burnup/cooling time limits for thimble
plug devices; changes Metamic-HT material testing requirements; changes
Metamic-HT material minimum guaranteed values; and updates fuel
definitions to allow boiling water reactor fuel affected by certain
corrosion mechanisms within specific guidelines to be classified as
undamaged fuel.
Holtec has not manufactured any cask under CoC No. 1014, Amendment
No. 8, and, consequently, no ISFSI licensee has placed such a cask into
service. Therefore, the changes in CoC No. 1014, Amendment No. 8,
Revision No. 1 which are approved in this direct final rule do not fall
within the definition of backfitting in 10 CFR 72.62, 10 CFR
50.109(a)(1), or otherwise represent an inconsistency with the issue
finality provisions applicable to combined licenses in part 52. In
addition, the changes in CoC No. 1014, Amendment No. 8, Revision No. 1
do not apply to casks which were manufactured to other amendments of
CoC No. 1014, and, therefore, have no effect on current ISFSI licensees
using casks which were manufactured to other amendments of CoC No.
1014. While any current CoC user may comply with the new requirements
in Amendment No. 8, Revision No. 1, this would be a voluntary decision
on the part of current users. For these reasons, NRC approval of CoC
No. 1014, Amendment No. 8, Revision No. 1, does not constitute
backfitting for users of the HI-STORM 100 Cask System which were
manufactured to other amendments of CoC No. 1014, under 10 CFR 72.62,
10 CFR 50.109(a)(1), or the issue finality provisions applicable to
combined licenses in 10 CFR part 52.
For the reasons set forth above, no backfit analysis or additional
documentation addressing the issue finality criteria in 10 CFR part 52
has been prepared by the NRC.
XIII. Congressional Review Act
This action is not a major rule as defined in the Congressional
Review Act (5 U.S.C. 801-808).
XIV. Availability of Documents
The documents identified in the following table are available to
interested persons through one or more of the following methods, as
indicated.
------------------------------------------------------------------------
ADAMS Accession
Document No.
------------------------------------------------------------------------
CoC No. 1014, Amendment No. 8, Revision No. 1......... ML14262A478
Safety Evaluation Report.............................. ML14262A476
Technical Specifications, Appendix A.................. ML14262A480
Technical Specifications, Appendix B.................. ML14262A479
Application (portions are non-public/proprietary)..... ML13235A082
December 20, 2013, Application Supplement............. ML14009A271
February 28, 2014, Application Supplement............. ML14064A344
------------------------------------------------------------------------
The NRC may post materials related to this document, including
public comments, on the Federal rulemaking Web site at http://www.regulations.gov under Docket ID NRC-2014-0233. The Federal
rulemaking Web site allows you to receive alerts when changes or
additions occur in a docket folder. To subscribe: 1) navigate to the
docket folder (NRC-2014-0233); 2) click the ``Sign up for Email
Alerts'' link; and 3) enter your email address and select how
frequently you would like to receive emails (daily, weekly, or
monthly).
List of Subjects in 10 CFR Part 72
Administrative practice and procedure, Criminal penalties, Manpower
training programs, Nuclear materials, Occupational safety and health,
Penalties, Radiation protection, Reporting and recordkeeping
requirements, Security measures, Spent fuel, Whistleblowing.
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; the Nuclear Waste Policy Act of 1982, as
amended; and 5 U.S.C. 552 and 553; the NRC is adopting the following
amendments to 10 CFR part 72.
PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF
SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-
RELATED GREATER THAN CLASS C WASTE
0
1. The authority citation for part 72 continues to read as follows:
Authority: Atomic Energy Act secs. 51, 53, 57, 62, 63, 65, 69,
81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42 U.S.C.
2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233,
2234, 2236, 2237, 2239, 2273, 2282, 2021); Energy Reorganization Act
secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851);
National Environmental Policy Act sec. 102 (42 U.S.C. 4332); Nuclear
Waste
[[Page 6435]]
Policy Act secs. 131, 132, 133, 135, 137, 141, 148 (42 U.S.C. 10151,
10152, 10153, 10155, 10157, 10161, 10168); Government Paperwork
Elimination Act sec. 1704 (44 U.S.C. 3504 note); Energy Policy Act
of 2005, Pub. L. 109-58, 119 Stat. 788 (2005).
Section 72.44(g) also issued under Nuclear Waste Policy Act
secs. 142(b) and 148(c), (d) (42 U.S.C. 10162(b), 10168(c), (d)).
Section 72.46 also issued under Atomic Energy Act sec. 189 (42
U.S.C. 2239); Nuclear Waste Policy Act sec. 134 (42 U.S.C. 10154).
Section 72.96(d) also issued under Nuclear Waste Policy Act sec.
145(g) (42 U.S.C. 10165(g)).
Subpart J also issued under Nuclear Waste Policy Act secs.
117(a), 141(h) (42 U.S.C. 10137(a), 10161(h)).
Subpart K also issued under Nuclear Waste Policy Act sec. 218(a)
(42 U.S.C. 10198).
0
2. In Sec. 72.214, Certificate of Compliance No. 1014 is revised to
read as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1014.
Initial Certificate Effective Date: May 31, 2000.
Amendment Number 1 Effective Date: July 15, 2002.
Amendment Number 2 Effective Date: June 7, 2005.
Amendment Number 3 Effective Date: May 29, 2007.
Amendment Number 4 Effective Date: January 8, 2008.
Amendment Number 5 Effective Date: July 14, 2008.
Amendment Number 6 Effective Date: August 17, 2009.
Amendment Number 7 Effective Date: December 28, 2009.
Amendment Number 8 Effective Date: May 2, 2012, as corrected on
November 16, 2012 (ADAMS Accession No. ML12213A170, superseded by
Amendment Number 8, Revision 1 on April 21, 2015.
Amendment Number 8, Revision No.1 Effective Date: April 21, 2015.
Amendment Number 9 Effective Date: March 11, 2014.
SAR Submitted by: Holtec International.
SAR Title: Final Safety Analysis Report for the HI-STORM 100 Cask
System.
Docket Number: 72-1014.
Certificate Expiration Date: May 31, 2020.
Model Number: HI-STORM 100.
* * * * *
Dated at Rockville, Maryland, this 26th day of January, 2015.
For the Nuclear Regulatory Commission.
Mark A. Satorius,
Executive Director for Operations.
[FR Doc. 2015-02310 Filed 2-4-15; 8:45 am]
BILLING CODE 7590-01-P