[Federal Register Volume 79, Number 174 (Tuesday, September 9, 2014)]
[Rules and Regulations]
[Pages 53281-53285]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2014-21418]



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  Federal Register / Vol. 79, No. 174 / Tuesday, September 9, 2014 / 
Rules and Regulations  

[[Page 53281]]



NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

[NRC-2014-0120]
RIN 3150-AJ42


List of Approved Spent Fuel Storage Casks: Holtec International 
HI-STORM Underground Maximum Capacity Canister Storage System, 
Certificate of Compliance No. 1040

AGENCY: Nuclear Regulatory Commission.

ACTION: Direct final rule.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its 
spent fuel storage regulations by adding the Holtec International HI-
STORM Underground Maximum Capacity (UMAX) Canister Storage System, 
Certificate of Compliance (CoC) No. 1040, to the ``List of approved 
spent fuel storage casks.'' Holtec International intends to provide an 
underground storage option compatible with the Holtec International HI-
STORM FLOOD/WIND (FW) System (CoC No. 1032). The HI-STORM UMAX Canister 
Storage System stores a hermetically sealed canister containing spent 
nuclear fuel in an in-ground vertical ventilated module. The HI-STORM 
UMAX Canister Storage System is designed to provide long-term 
underground storage of loaded multi-purpose canisters previously 
certified for storage in CoC No. 1032.

DATES: The final rule is effective November 24, 2014, unless a 
significant adverse comment is received by October 9, 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direct final rule is withdrawn as a result of such comments, timely 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-2014-0120 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 any of the following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0120. 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 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 O-1F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Gregory R. Trussell, Office of Federal 
and State Materials and Environmental Management Programs, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-
6445, 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. Environmental Assessment and Finding of No Significant 
Environmental Impact
VIII. Paperwork Reduction Act Statement
IX. Regulatory Flexibility Certification
X. Regulatory Analysis
XI. Backfitting and Issue Finality
XII. Congressional Review Act
XIII. Availability of Documents

I. Procedural Background

    The NRC is using the ``direct final rule procedure'' to add CoC No. 
1040 to the list of approved spent fuel storage casks because the 
Holtec International HI-STORM UMAX Canister Storage System is similar 
to other previously approved spent fuel storage cask systems and, 
therefore, 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 November 24, 2014. However, if the NRC 
receives significant adverse comments on this direct final rule by 
October 9, 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)

[[Page 53282]]

to the rule, CoC, or Technical Specifications (TSs).
    For detailed instructions on filing comments, please see the 
companion proposed rule published in 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 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.

III. Discussion of Changes

    By letter dated June 29, 2012, and as supplemented on July 16, 
2012; November 20 and January 30, 2013; April 2, April 19, June 21, 
August 28, December 6, December 31, January 13; and January 28, 2014, 
Holtec International submitted an application to add the HI-STORM UMAX 
Canister Storage System to the list of approved spent fuel storage 
casks in 10 CFR part 72. The HI-STORM UMAX Canister Storage System is a 
spent fuel storage system designed to be in full compliance with the 
requirements of 10 CFR part 72. Holtec International intends to provide 
an underground storage option compatible with the Holtec International 
HI-STORM FW System as described in the Final Safety Analysis Report 
(FSAR) for the HI-STORM FW System. The underground structure system is 
described in the FSAR for the HI-STORM UMAX Canister Storage System. 
The HI-STORM UMAX Canister Storage System stores a hermetically sealed 
canister containing spent nuclear fuel (SNF) in an in-ground vertical 
ventilated module (VVM). The HI-STORM UMAX Canister Storage System is 
designed to provide long-term underground storage of loaded multi-
purpose canisters (MPC) previously certified for storage in CoC No. 
1032. The HI-STORM UMAX VVM is the underground equivalent of the HI-
STORM FW storage module. Although the storage cavity dimensions and the 
air ventilation system in the HI-STORM UMAX VVM have been selected to 
enable it to also store all MPCs certified for storage in the HI-STORM 
100 storage module, CoC No. 1040 does not approve the storage of all 
MPCs certified for storage in the HI-STORM 100 storage module in the 
HI-STORM UMAX VVM at this time. The HI-STORM UMAX Canister Storage 
System can store either Pressurized Water Reactor or Boiling Water 
Reactor fuel assemblies in the MPC-37 or MPC-89 models, respectively. 
The number associated with the MPC is the maximum number of fuel 
assemblies the MPC can contain in the fuel basket. The external 
diameters of the MPC-37 and MPC-89 are identical to allow the use of a 
single storage module design, however the height of the MPC, as well as 
the storage module and transfer cask, are variable based on the SNF to 
be loaded.
    As documented in the safety evaluation report (SER), the NRC staff 
performed a detailed safety evaluation of the proposed CoC request 
submitted by Holtec International.
    The HI-STORM UMAX Canister Storage System, 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 
HI-STORM UMAX Canister Storage Systems that meet the criteria of CoC 
No. 1040 under 10 CFR 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 add the 
Holtec International HI-STORM UMAX Canister Storage System design to 
the listing 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, and 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).

VII. Environmental Assessment and Finding of No Significant 
Environmental Impact

A. The Action

    The action is to amend 10 CFR 72.214 to add the Holtec 
International HI-STORM UMAX Canister Storage System to the listing 
within the ``List of approved spent fuel storage casks'' as CoC No. 
1040. 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

[[Page 53283]]

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 adds CoC No. 1040 for the Holtec 
International HI-STORM UMAX Canister Storage 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 International intends to provide an underground 
storage option compatible with the Holtec International HI-STORM FW 
System.

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 CoC addition 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 UMAX Canister Storage 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 HI-STORM UMAX Canister Storage System 
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. In addition, any 
resulting occupational exposure or offsite dose rates from the use of 
the HI-STORM UMAX Canister Storage System would remain well within the 
10 CFR part 20 limits. Therefore, the proposed addition of CoC No. 1040 
will not result in 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 
significant revisions in the amounts of 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 the SER for this addition.

D. Alternative to the Action

    The alternative to this action is to withhold approval of this new 
design and issue a site-specific license to each utility that proposes 
to use the casks. This alternative would cost both the NRC and 
utilities more time and money for each site-specific license. 
Conducting site-specific reviews would ignore the procedures and 
criteria currently in place for the addition of new cask designs that 
can be used under a general license, and would be in conflict with NWPA 
direction to the Commission to approve technologies for the use of 
spent fuel storage at the sites of civilian nuclear power reactors 
without, to the maximum extent practicable, the need for additional 
site reviews. This alternative also would tend to exclude new vendors 
from the business market without cause and would arbitrarily limit the 
choice of cask designs available to power reactor licensees. This final 
rule will eliminate the above problems and is consistent with previous 
Commission actions. Further, the rule will have no adverse effect on 
public health and safety. Therefore, the environmental impacts would be 
the same or less than the action.

E. Alternative Use of Resources

    Approval of the addition of CoC No. 1040 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 UMAX Canister Storage System, Certificate of 
Compliance No. 1040,'' 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 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).

X. 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 June 29, 2012, and as supplemented on July 16, 2012; November 20 
and January 30, 2013; April 2, April 19, June 21, August 28, December 
6, December 31, January 13; and January 28, 2014, Holtec International 
submitted an application to add the HI-STORM UMAX Canister Storage 
System.
    The alternative to this action is to withhold approval of this new 
design

[[Page 53284]]

and issue a site-specific license to each utility that proposes to use 
the casks. This alternative would cost both the NRC and utilities more 
time and money for each site-specific license. Conducting site-specific 
reviews would ignore the procedures and criteria currently in place for 
the addition of new cask designs that can be used under a general 
license, and would be in conflict with NWPA direction to the Commission 
to approve technologies for the use of spent fuel storage at the sites 
of civilian nuclear power reactors without, to the maximum extent 
practicable, the need for additional site reviews. This alternative 
also would tend to exclude new vendors from the business market without 
cause and would arbitrarily limit the choice of cask designs available 
to power reactor licensees. This final rule will eliminate the above 
problems and is consistent with previous Commission actions. Further, 
the rule will have no adverse effect on public health and safety.
    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.

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 adds CoC No. 1040 for the Holtec 
International HI-STORM UMAX Canister Storage System to the ``List of 
approved spent fuel storage casks.''
    The addition of CoC No. 1040 for the Holtec International HI-STORM 
UMAX Canister Storage System was initiated by Holtec International and 
was not submitted in response to new NRC requirements, or an NRC 
request for amendment. The addition of CoC No. 1040 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

    This action is not a major rule as defined in the Congressional 
Review Act (5 U.S.C. 801-808).

XIII. 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.

------------------------------------------------------------------------
                Document                       ADAMS Accession No.
------------------------------------------------------------------------
CoC No. 1040...........................  ML14122A443.
Safety Evaluation Report...............  ML14122A441.
Technical Specifications, Appendix A...  ML14122A444.
Technical Specifications, Appendix B...  ML14122A442.
Application............................  ML12363A282.
Application supplemental July 16, 2012.  ML12205A134.
Application supplemental November 20,    ML12348A483.
 2012.
Application supplemental January 30,     ML13032A008.
 2013.
Application supplemental April 2, 2013.  ML13107B249.
Application supplemental April 19, 2013  ML13114A191.
Application supplemental June 21, 2013.  ML13175A363.
Application supplemental August 28,      ML13261A062.
 2013.
Application Supplemental December 6,     ML13343A169.
 2013.
Application supplemental December 31,    ML14002A402.
 2013.
Application supplemental January 13,     ML14015A145.
 2014.
Application supplemental January 28,     ML14030A055.
 2014.
------------------------------------------------------------------------

    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-2014-0120. 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-2014-0120); (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, 2238, 2273, 2282, 2021); Energy Reorganization Act 
secs. 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 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. 1040 is added to read 
as follows:


Sec.  72.214  List of approved spent fuel storage casks.

* * * * *
    Certificate Number: 1040.
    Initial Certificate Effective Date: November 24, 2014.
    SAR Submitted by: Holtec International, Inc.
    SAR Title: Final Safety Analysis Report for the Holtec 
International HI-STORM UMAX Canister Storage System.
    Docket Number: 72-1040.
    Certificate Expiration Date: September 9, 2034.
    Model Number: MPC-37, MPC-89.

    Dated at Rockville, Maryland, this 22nd day of August 2014.


[[Page 53285]]


    For the Nuclear Regulatory Commission.
Darren B. Ash,
Acting Executive Director for Operations.
[FR Doc. 2014-21418 Filed 9-8-14; 8:45 am]
BILLING CODE 7590-01-P