[Federal Register Volume 84, Number 38 (Tuesday, February 26, 2019)]
[Rules and Regulations]
[Pages 6055-6059]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-02886]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

[NRC-2019-0030]
RIN 3150-AK28


List of Approved Spent Fuel Storage Casks: Holtec International 
HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Amendment 
No. 13

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. 13 to Certificate of 
Compliance No. 1014. Amendment No. 13 revises Appendix B of the 
technical specifications to update the initial uranium weight for the 
16x16B and 16x16C assembly classes to match the value for 16x16A.

DATES: This direct final rule is effective May 13, 2019, unless 
significant adverse comments are received by March 28, 2019. If this 
direct final rule is withdrawn as a result of such comments, timely 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 is 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 of the following methods:
     Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2019-0030. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions contact 
the individuals 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: Christian Jacobs, Office of Nuclear 
Material Safety and Safeguards; telephone: 301-415-6825; email: 
[email protected] or Gregory R. Trussell, Office of Nuclear 
Material Safety and Safeguards; telephone: 301-415-6244; email: 
[email protected]. Both are staff of the U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001.

SUPPLEMENTARY INFORMATION: 

Table of Contents

I. Obtaining Information and Submitting Comments
II. Rulemaking Procedure
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-2019-0030 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 website: Go to http://www.regulations.gov and search for Docket ID NRC-2019-0030.
     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 ``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-

[[Page 6056]]

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-2019-0030 in your comment submission.
    The NRC cautions you not to include identifying or contact 
information 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. 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. Rulemaking Procedure

    This direct final rule is limited to the changes contained in 
Amendment No. 13 to Certificate of Compliance 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 
certificate of compliance 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 May 13, 
2019. However, if the NRC receives significant adverse comments on this 
direct final rule by March 28, 2019, 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 Rules 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, Certificate of Compliance, or technical 
specifications.
    For detailed instructions on filing comments, please see the 
companion proposed rule published in the Proposed Rules section of this 
issue of the Federal Register.

III. Background

    Section 218(a) of the Nuclear Waste Policy Act of 1982, as amended, 
requires that ``[t]he 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 Nuclear 
Waste Policy Act 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 HI-STORM 100 Cask System 
design and added it to the list of NRC-approved cask designs in 10 CFR 
72.214 as Certificate of Compliance No. 1014.

IV. Discussion of Changes

    On November 19, 2018, Holtec International submitted a request to 
the NRC to amend Certificate of Compliance No. 1014 by adding Amendment 
No. 13. Amendment 13 revises Table 2.1-2: Pressurized Water Reactor 
(PWR) Fuel Assembly Characteristics of Appendix B of the technical 
specifications to update the initial uranium weight for the 16x16B and 
16x16C assembly classes to match the value for 16x16A.
    As documented in the preliminary safety evaluation report, the NRC 
performed a safety review of the proposed Certificate of Compliance 
amendment request. Based on its review, the staff determined that there 
is reasonable assurance that: (1) The activities authorized by the 
amended certificate can be conducted without endangering the health and 
safety of the public, and (2) these activities will be conducted in 
compliance with the applicable regulations of 10 CFR part 72. There are 
no significant changes to cask design requirements in the proposed 
amendment. Considering the specific design requirements for each 
accident condition, the design of the cask would prevent loss of 
containment, shielding, and criticality control in the event of an 
accident. The 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. 
13 would remain well within the 10 CFR part 20 limits. There will be no 
significant change in the types or 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 Holtec International HI-STORM 
100 Cask System listing in 10 CFR 72.214 by adding Amendment No. 13 to 
Certificate of Compliance No. 1014. This amendment consists of the 
changes

[[Page 6057]]

previously described, as set forth in the revised certificate of 
compliance and technical specifications. The revised technical 
specifications are identified in the preliminary safety evaluation 
report.
    The amended Holtec International HI-STORM 100 Cask System design, 
when used under the conditions specified in the Certificate of 
Compliance, technical specifications, 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 100 Cask 
System casks that meet the criteria of Amendment No. 13 to Certificate 
of Compliance 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, ``List of approved spent fuel storage casks.'' 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 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, and the 
Category ``NRC'' does not confer regulatory authority on the State, the 
State may wish to inform its licensees of certain requirements by means 
consistent with the particular State's administrative procedure laws.

VII. 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 
31885).

VIII. Environmental Assessment and Finding of No Significant 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 include Amendment No. 13 to 
Certificate of Compliance No. 1014. Amendment No. 13 revises Table 2.1-
2: PWR Fuel Assembly Characteristics of Appendix B of the technical 
specifications to update the initial uranium weight for the 16x16B and 
16x16C assembly classes to match the value for 16x16A.

B. The Need for the Action

    This direct final rule adds an amended Certificate of Compliance 
for the Holtec International HI-STORM 100 Cask System design to 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. 13 revises Table 2.1-2: PWR Fuel Assembly 
Characteristics of Appendix B of the technical specifications to update 
the initial uranium weight for the 16x16B and 16x16C assembly classes 
to match the value for 16x16A.

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 Amendment No. 13 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 of 1969, as amended.
    The Holtec International HI-STORM 100 Cask System is 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 in the event of an accident. If 
there is no loss of confinement, shielding, or criticality control, the 
environmental impacts resulting from an accident would be 
insignificant. This amendment does not reflect a significant change in 
design or fabrication of the cask.
    Because there are no significant design or process changes, any 
resulting occupational exposure or offsite dose rates from the 
implementation of Amendment No. 13 would remain well within the 10 CFR 
part 20 limits. Therefore, the proposed 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 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 the preliminary 
safety evaluation report.

D. Alternative to the Action

    The alternative to this action is to deny approval of Amendment No. 
13 and end the direct final rule. Consequently, any 10 CFR part 72 
general licensee that seeks to load spent nuclear fuel into the Holtec 
International HI-STORM 100 Cask System and utilize the technical 
specifications in accordance with the changes described in proposed 
Amendment No. 13, 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

[[Page 6058]]

each licensee. Therefore, the environmental impacts would be the same, 
or more likely greater than, the proposed action.

E. Alternative Use of Resources

    Approval of Amendment No. 13 to Certificate of Compliance No. 1014 
would result in no irreversible commitment 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 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.'' 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. 13,'' 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 new or amended 
collections of information subject to the Paperwork Reduction Act of 
1995 (44 U.S.C. 3501 et seq.). Existing collections of information were 
approved by the Office of Management and Budget, 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 
Office of Management and Budget 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 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 Certificate of 
Compliance, 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 November 19, 2018, Holtec International submitted a request to 
the NRC to amend Certificate of Compliance No. 1014 by adding Amendment 
No. 13. Holtec International submitted this application to amend the 
Holtec International HI-STORM 100 Cask System as described in Section 
IV, ``Discussion of Changes,'' of this document.
    The alternative to this action is to withhold approval of Amendment 
No. 13 and to 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. 13 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 preliminary safety evaluation 
report and environmental assessment, this 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 this 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.

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. Therefore, a backfit analysis is 
not required. This direct final rule revises Certificate of Compliance 
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 requests changes to Table 2.1-2: PWR Fuel 
Assembly Characteristics of Appendix B of the technical specifications 
to update the initial uranium weight for the 16x16B and 16x16C assembly 
classes to match the value for 16x16A.
    Amendment No. 13 to Certificate of Compliance 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. 13 applies 
only to new casks fabricated and used under Amendment No. 13. These 
changes do not affect existing users of the Holtec International HI-
STORM 100 Cask System, and the current Amendment No. 12 continues to be 
effective for existing users. While current users of this storage 
system may comply with the new requirements in Amendment No. 13, this 
would be a voluntary decision on the part of current users.
    For these reasons, Amendment No. 13 to Certificate of Compliance 
No. 1014 does not constitute backfitting under 10 CFR 72.62 or 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, the NRC staff has not prepared a backfit analysis for this 
rulemaking.

XIII. Congressional Review Act

    This direct final rule is not a rule as defined in the 
Congressional Review Act.

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.

[[Page 6059]]



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                                                                                   ADAMS Accession No./ Web link/
                                     Document                                        Federal Register Citation
----------------------------------------------------------------------------------------------------------------
Letter from Holtec International dated November 19, 2018, Submitting Request for                    ML18325A154
 Amendment No. 13 to Certificate of Compliance No. 1014..........................
Proposed Certificate of Compliance No. 1014 Amendment No. 13, Certificate of                        ML18351A173
 Compliance for Spent Fuel Storage Casks.........................................
Proposed Certificate of Compliance No. 1014 Amendment No. 13, Technical                             ML18351A174
 Specifications, Appendix A......................................................
Proposed Certificate of Compliance No. 1014 Amendment No. 13, Technical                             ML18351A175
 Specifications, Appendix B......................................................
Proposed Certificate of Compliance No. 1014 Amendment No. 13, Technical                             ML18351A176
 Specifications, Appendix A-100U.................................................
Proposed Certificate of Compliance No. 1014 Amendment No. 13, Technical                             ML18351A177
 Specifications, Appendix B-100U.................................................
Certificate of Compliance No. 1014 Amendment No. 13, Preliminary Safety                             ML18351A178
 Evaluation Report...............................................................
----------------------------------------------------------------------------------------------------------------

    The NRC may post materials related to this document, including 
public comments, on the Federal Rulemaking website at http://www.regulations.gov under Docket ID NRC-2019-0030. The Federal 
Rulemaking website allows you to receive alerts when changes or 
additions occur in a docket folder. To subscribe: (1) Navigate to the 
docket folder (NRC-2019-0030); (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, Hazardous waste, Indians, 
Intergovernmental relations, Nuclear energy, Penalties, Radiation 
protection, Reporting and recordkeeping requirements, Security 
measures, 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 of 1954, 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, 2210e, 
2232, 2233, 2234, 2236, 2237, 2238, 2273, 2282, 2021); Energy 
Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C. 
5841, 5842, 5846, 5851); National Environmental Policy Act of 1969 
(42 U.S.C. 4332); Nuclear Waste Policy Act of 1982, secs. 117(a), 
132, 133, 134, 135, 137, 141, 145(g), 148, 218(a) (42 U.S.C. 
10137(a), 10152, 10153, 10154, 10155, 10157, 10161, 10165(g), 10168, 
10198(a)); 44 U.S.C. 3504 note.


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); superseded by 
Amendment 8, Revision 1 Effective Date: February 16, 2016.
    Amendment Number 8, Revision 1 Effective Date: February 16, 2016.
    Amendment Number 9 Effective Date: March 11, 2014, superseded by 
Amendment Number 9, Revision 1, on March 21, 2016.
    Amendment Number 9, Revision 1, Effective Date: March 21, 2016, as 
corrected (ADAMS Accession No. ML17236A451).
    Amendment Number 10 Effective Date: May 31, 2016, as corrected 
(ADAMS Accession No. ML17236A452).
    Amendment Number 11 Effective Date: February 25, 2019.
    Amendment Number 12 Effective Date: February 25, 2019.
    Amendment Number 13 Effective Date: May 13, 2019.
    Safety Analysis Report (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 14th day of February, 2019.

    For the Nuclear Regulatory Commission.
Margaret M. Doane,
Executive Director for Operations.
[FR Doc. 2019-02886 Filed 2-25-19; 8:45 am]
 BILLING CODE 7590-01-P