[Federal Register Volume 78, Number 235 (Friday, December 6, 2013)]
[Rules and Regulations]
[Pages 73379-73383]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2013-29162]
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Rules and Regulations
Federal Register
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Federal Register / Vol. 78, No. 235 / Friday, December 6, 2013 /
Rules and Regulations
[[Page 73379]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2012-0052]
RIN 3150-AJ12
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Cask
System; Amendment No. 9
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 include Amendment No. 9 to Certificate of Compliance
(CoC) No. 1014. Amendment No. 9 broadens the subgrade requirements for
the HI-STORM 100U part of the HI-STORM 100 Cask System and updates the
thermal model and methodology for the HI-TRAC transfer cask from a two
dimensional thermal-hydraulic model to a more accurate three
dimensional model. The amendment also makes editorial corrections.
DATES: The direct final rule is effective February 19, 2014, unless
significant adverse comments are received by January 6, 2014. 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direct final rule is withdrawn as a result of such comments, timely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 able to ensure consideration only for
comments received on or before this date.
ADDRESSES: Please refer to Docket ID NRC-2012-0052 when contacting the
NRC about the availability of information for this direct final rule.
You may access publicly available information related to this direct
final rule by the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0052. Address
questions about NRC dockets to Carol Gallagher, telephone: 301-287-
3422, email: [email protected]. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library 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]. An electronic copy of the
proposed CoC, including Appendices A and B of the Technical
Specifications (TS), Appendix A--100U and Appendix B--100U of the TS,
and the preliminary safety evaluation report (SER) are available in
ADAMS under Package Accession No. ML120530246.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O-1F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Naiem S. Tanious, Office of Federal
and State Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone: 301-415-
6103, email: [email protected].
SUPPLEMENTARY INFORMATION:
Table of Contents
I. Procedural Background
II. Background
III. Discussion of Changes
IV. Voluntary Consensus Standards
V. Agreement State Compatibility
VI. Plain Writing
VII. Finding of No Significant Environmental Impact: Availability
VIII. Paperwork Reduction Act Statement
IX. Regulatory Analysis
X. Regulatory Flexibility Certification
XI. Backfitting and Issue Finality
XII. Congressional Review Act
I. Procedural Background
This direct final rule is limited to the changes contained in
Amendment No. 9 to CoC No. 1014 and does not include other aspects of
the HI-STORM 100 Cask System design. The NRC is using the ``direct
final rule procedure'' to issue this amendment 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. The amendment to the rule will become
effective on February 19, 2014. However, if the NRC receives
significant adverse comments on this direct final rule by January 6,
2014, 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:
(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 TSs.
For detailed instructions on submitting comments, please see the
companion proposed rule published in
[[Page 73380]]
the Proposed Rule section of this issue of the Federal Register.
II. Background
Section 218(a) of the Nuclear Waste Policy Act (NWPA) of 1982, as
amended, requires that ``the Secretary [of the U.S. 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 [U.S. 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 in part 72 of Title 10 of the Code of Federal
Regulations (10 CFR), ''Licensing Requirements for the Independent
Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and
Reactor-Related Greater then Class C Waste,'' which added a new subpart
K within 10 CFR part 72 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 within 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 (65 FR 25241; May 1, 2000)
that approved the HI-STORM 100 Cask System design and added it to the
list of NRC-approved cask designs in 10 CFR 72.214, ``List of approved
spent fuel storage casks,'' as CoC No. 1014.
III. Discussion of Changes
On September 10, 2010 (ADAMS Accession No. ML102570739), Holtec
International submitted a request to the NRC to amend CoC No. 1014.
Holtec supplemented its request on the following dates: October 1, 2010
(ADAMS Accession No. ML102780596); November 14, 2011 (ADAMS Accession
No. ML11320A185); April 17, 2013 (ADAMS Accession No. ML13114A952); and
May 15, 2013 (ADAMS Accession No. ML13137A067). The amendment broadens
the subgrade requirements for the HI-STORM 100U part of the HI-STORM
100 Cask System, updates the thermal model and methodology for the HI-
TRAC transfer cask from a two dimensional thermal-hydraulic model to a
more accurate three dimensional model, and makes editorial corrections.
The amendment changes are available in ADAMS under Package Accession
No. ML120530246. The ADAMS Accession No. for the HI-STORM 100 Cask
System Amendment No. 9, dated June 20, 2013, is ML120530271.
As documented in the SER (ADAMS Accession No. ML120530329), 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 confinement, shielding, and criticality control.
If there is no loss of confinement, 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. 9 would remain well within the
10 CFR part 20, ``Standards for Protection Against Radiation,'' 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 May 1, 2000, final rule. There will be no
significant change in the types or significant revisions in the amounts
of any effluent released, no significant increase in the individual or
cumulative radiation exposure, and no significant increase in the
potential for or consequences from radiological accidents.
This direct final rule revises the HI-STORM 100 Cask System listing
in 10 CFR 72.214 by adding Amendment No. 9 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 HI-STORM 100 cask 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, ``General license issued,'' may
load spent nuclear fuel into HI-STORM 100 Cask Systems that meet the
criteria of Amendment No. 9 to CoC No. 1014 under 10 CFR 72.212,
``Conditions of general license issued 72.212.''
IV. 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 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.
V. Agreement State Compatibility
Under the ``Policy Statement on Adequacy and Compatibility of
Agreement State Programs'' approved by the Commission on June 30, 1997,
and published in the Federal Register 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 are those that
relate directly 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.
VI. 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
that also follows other best practices appropriate to the subject or
field and the intended audience. The NRC has attempted to use plain
language in promulgating this rule consistent with the Federal Plain
Writing Act guidelines.
VII. Finding of No Significant Environmental Impact: Availability
A. The Action
The action is to amend 10 CFR 72.214 to revise the HI-STORM 100
Cask System listing within the ``List of Approved Spent Fuel Storage
Casks'' to
[[Page 73381]]
include Amendment No. 9 to CoC No. 1014. Under the National
Environmental Policy Act of 1969, as amended, and the NRC 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 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, Holtec, in Amendment No. 9,
requested changes to broaden the subgrade requirements for the HI-STORM
100U part of the HI-STORM 100 Cask Storage System, update the thermal
model and methodology for the HI-TRAC transfer cask from a two
dimensional thermal-hydraulic model to a more accurate three
dimensional model, and make editorial corrections.
C. Environmental Impacts of the Action
The potential environmental impact of using the HI-STORM 100 Cask
System was initially analyzed in the environmental assessment for the
final rule to add the HI-STORM 100 Cask System to the list of approved
spent fuel storage casks in 10 CFR 72.214 (65 FR 25241; May 1, 2000).
The environmental assessment for the May 1, 2000, final rule concluded
that there would be no significant environmental impacts to adding the
HI-STORM 100 Cask System, and therefore, the NRC issued a finding of no
significant impact, which continues to be valid. The environmental
assessment, for this Amendment No. 9, tiers on the environmental
assessment for the May 1, 2000, final rule. Tiering on past
environmental assessments is a standard process under the National
Environmental Policy Act.
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 independent spent fuel storage installation,
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 confinement,
shielding, and criticality control. If there is no loss of confinement,
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. There are no significant changes to
cask design requirements in the proposed CoC amendment. In addition,
because there are no significant design or process changes any
resulting occupational exposure or offsite dose rates from the
implementation of Amendment No. 9 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 May 1, 2000, final rule. There
will be no significant change in the types or significant revisions in
the amounts of any effluent released, no significant increase in the
individual or cumulative radiation exposure, and no significant
increase in the potential for or consequences from radiological
accidents. The staff documented its safety findings in an SER which is
available in ADAMS under Accession No. ML120530329.
D. Alternative to the Action
The alternative to this action is to deny approval of Amendment No.
9 and end the direct final rule. Consequently, any 10 CFR part 72
general licensee that seeks to load spent nuclear fuel into HI-STORM
100 Cask Systems in accordance with the changes described in proposed
Amendment No. 9 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 upon the NRC and the costs 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. 9 to 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: HI-STORM 100
Cask System, Amendment No. 9,'' 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.
VIII. 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.). Existing requirements were
approved by the Office of Management and Budget (OMB), Approval Number
3150-0132.
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.
IX. 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 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 HI-
STORM 100 Cask System design by adding it to the list of NRC-approved
cask designs in 10 CFR 72.214.
On September 10, 2010, Holtec International submitted a request to
the NRC to amend CoC No. 1014. Holtec supplemented its request on the
following dates: October 1, 2010, November 14, 2011, April 17, 2013,
and May 15, 2013. The amendment broadens
[[Page 73382]]
the subgrade requirements for the HI-STORM 100U part of the HI-STORM
100 Cask System, updates the thermal model and methodology for the HI-
TRAC transfer cask from a two dimensional thermal-hydraulic model to a
more accurate three dimensional model, and makes editorial corrections.
The alternative to this action is to withhold approval of
Amendment No. 9 and to require any 10 CFR part 72 general licensee
seeking to load spent nuclear fuel into HI-STORM 100 Cask Systems under
the changes described in Amendment No. 9 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 upon the NRC and the costs to each
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 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 as
satisfactory, and therefore, this action is recommended.
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, Inc. 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. Backfitting and Issue Finality
The NRC has determined that the backfit rule (10 CFR 72.62) does
not apply to this direct final rule. 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.'' The
revision consists of Amendment No. 9, which broadens the subgrade
requirements for the HI-STORM 100U part of the HI-STORM 100 Cask
System, updates the thermal model and methodology for the HI-TRAC
transfer cask from a two dimensional thermal-hydraulic model to a more
accurate three dimensional model, and makes editorial corrections.
Amendment No. 9 to CoC No. 1014 for the Holtec International HI-
STORM 100 Cask System was initiated by Holtec International and was not
submitted in response to new NRC requirements, or an NRC request for
amendment. Amendment No. 9 applies only to new casks fabricated and
used under Amendment No. 9. These changes do not affect existing users
of the HI-STORM 100 Cask System, and the current Amendment No. 8
continues to be effective for existing users. While current CoC users
may comply with the new requirements in Amendment No. 9, this would be
a voluntary decision on the part of current users. For these reasons,
Amendment No. 9 to CoC No. 1014 does not constitute backfitting under
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 10 CFR part 52. Accordingly, no backfit analysis or
additional documentation addressing the issue finality criteria in 10
CFR part 52 has been prepared by the staff.
XII. Congressional Review Act
The Office of Management and Budget has not found this to be a
major rule as defined in the Congressional Review Act.
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, 2238, 2273, 2282, 2021); Energy Reorganization Act
sec. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); National
Environmental Protection Act sec. 102 (42 U.S.C. 4332); Nuclear
Waste Policy Act secs. 131, 132, 133, 135, 137, 141, 148 (42 U.S.C.
10151, 10152, 10153, 10155, 10157, 10161, 10168); sec. 1704, 112
Stat. 2750 (44 U.S.C. 3504 note); Energy Policy Act of 2005, Pub. L.
No. 109-58, 119 Stat. 549 (2005).
Section 72.44(g) also issued under secs. Nuclear Waste Policy
Act 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 is also issued under sec. 218(a) (42 U.S.C.
10198).
0
2. In Sec. 72.214, Certificate of Compliance 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).
Amendment Number 9 Effective Date: February 19, 2014.
SAR Submitted by: Holtec International, Inc.
[[Page 73383]]
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 2nd day of December 2013.
For the Nuclear Regulatory Commission.
Michael R. Johnson,
Acting Executive Director for Operations.
[FR Doc. 2013-29162 Filed 12-5-13; 8:45 am]
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