[Federal Register Volume 84, Number 192 (Thursday, October 3, 2019)]
[Rules and Regulations]
[Pages 52747-52751]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-21209]



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 Rules and Regulations
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  Federal Register / Vol. 84, No. 192 / Thursday, October 3, 2019 / 
Rules and Regulations  

[[Page 52747]]



NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

[NRC-2019-0160]
RIN 3150-AK36


List of Approved Spent Fuel Storage Casks: Holtec International 
HI-STORM 100 Multipurpose Canister Cask System, Certificate of 
Compliance No. 1014, Amendment No. 14

AGENCY: Nuclear Regulatory Commission.

ACTION: Direct final rule.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its 
spent fuel storage regulations by revising the Holtec International HI-
STORM 100 Multipurpose Canister Cask System listing within the ``List 
of approved spent fuel storage casks'' to include Amendment No. 14 to 
Certificate of Compliance No. 1014. Amendment No. 14 revises the 
technical specifications to add new heat loading patterns, reduce the 
minimum cooling time, allow use of a damaged fuel isolator for storing 
damaged fuel, and modify the description of vents in overpack. 
Amendment No. 14 also makes other administrative changes to the 
technical specifications. These revisions are discussed in more detail 
in the ``Discussion of Changes'' section of this document.

DATES: This direct final rule is effective December 17, 2019, unless 
significant adverse comments are received by November 4, 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direct final rule is withdrawn as a result of such comments, timely 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 https://www.regulations.gov and search for Docket ID NRC-2019-0160. 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: Yen-Ju Chen, Office of Nuclear 
Material Safety and Safeguards; telephone: 301-415-1018; email: [email protected] or Torre Taylor, Office of Nuclear Material Safety and 
Safeguards; telephone: 301-415-7900; 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-2019-0160 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 https://www.regulations.gov and search for Docket ID NRC-2019-0160.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at https://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, 301-415-4737, 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-2019-0160 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 
https://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.

[[Page 52748]]

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. 14 to Certificate of Compliance No. 1014 and does not 
include other aspects of the Holtec International HI-STORM 100 
Multipurpose Canister Cask System (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 December 17, 2019. However, if the NRC receives 
significant adverse comments on this direct final rule by November 4, 
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 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.
    (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 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, 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 (65 FR 25241).

IV. Discussion of Changes

    On October 31, 2018, as supplemented on November 6, 2018, February 
28, 2019, April 5, 2019, April 23, 2019, May 13, 2019, and August 8, 
2019, Holtec International submitted a request to amend Certificate of 
Compliance No. 1014 for the HI-STORM 100 Cask System. Amendment No. 14 
revises the technical specifications to: (1) Add three new regionalized 
Quarter Symmetric Heat Load loading patterns for the multipurpose 
canister (MPC)-68M; (2) reduce the minimum cooling time to 1 year for 
all fuel types for storage in the MPC-68M; (3) use a damaged fuel 
isolator for damaged fuel stored in the MPC-68M; and (4) modify the 
description of the vents in the overpack in the certificate of 
compliance and remove the word ``four'' from Section 1.b describing the 
air inlet and outlet vents. Amendment No. 14 also makes other 
administrative changes to the technical specifications. The revised 
certificate of compliance and technical specifications are identified 
and evaluated in the preliminary safety evaluation report.
    As documented in that preliminary safety evaluation report, the NRC 
performed a safety evaluation of the proposed certificate of compliance 
amendment request. 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. 
14 would remain well within the limits specified by 10 CFR part 20, 
``Standards for Protection Against Radiation.'' 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.
    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 Sec.  72.210 may, consistent with the license conditions under 
Sec.  72.212, load spent nuclear fuel into those HI-STORM 100 Cask 
System casks that meet the criteria of Amendment No. 14 to Certificate 
of Compliance No. 1014.

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

[[Page 52749]]

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 Sec.  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 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 chapter I. 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

    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 direct 
final 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.

A. The Action

    The action is to amend Sec.  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. 14 to 
Certificate of Compliance No. 1014.

B. The Need for the Action

    This direct final rule amends the certificate of compliance 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. 14 updates the certificate of compliance 
to: (1) Add three new regionalized Quarter Symmetric Heat Load loading 
patterns for the MPC-68M; (2) reduce the minimum cooling time to 1 year 
for all fuel types for storage in the MPC-68M; (3) use a damaged fuel 
isolator for damaged fuel stored in the MPC-68M; and (4) modify the 
description of the vents in the overpack in the certificate of 
compliance and remove the word ``four'' from Section 1.b describing the 
air inlet and outlet vents. Amendment No. 14 also makes other 
administrative changes to the technical specifications.

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. 14 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.
    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 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. 14 would 
remain well within 10 CFR part 20 limits. Therefore, the proposed 
certificate of compliance 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 exposures, and no significant increase in the 
potential for, or consequences of, radiological accidents.
    The NRC documented its safety findings in a preliminary safety 
evaluation report.

D. Alternative to the Action

    The alternative to this action is to deny approval of Amendment No. 
14 and not issue 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 in accordance with the 
changes described in proposed Amendment No. 14 would have to request an 
exemption from the requirements of Sec. Sec.  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. The environmental impacts would be the same as the proposed 
action.

E. Alternative Use of Resources

    Approval of Amendment No. 14 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.

[[Page 52750]]

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. 
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 Multipurpose Canister Cask 
System, Certificate of Compliance No. 1014, Amendment No. 14,'' 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 (Sec.  
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 Sec.  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 Sec.  72.214.
    On October 31, 2018, and as supplemented on November 6, 2018, 
February 28, 2019, April 5, 2019, April 23, 2019, May 13, 2019, and 
August 8, 2019, Holtec International submitted an application to amend 
the Holtec International HI-STORM 100 Multipurpose Canister 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. 14 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. 14 to request an 
exemption from the requirements of Sec. Sec.  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 (Sec.  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 Sec.  72.214. The amendment consists of the changes 
in Amendment No. 14 previously described, as set forth in the revised 
certificate of compliance and technical specifications.
    Amendment No. 14 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. 14 applies 
only to new casks fabricated and used under Amendment No. 14. These 
changes do not affect existing users of the Holtec International HI-
STORM 100 Cask System, and previous amendments continue to be effective 
for existing users. While current certificate of compliance users may 
comply with the new requirements in Amendment No. 14, this would be a 
voluntary decision on the part of current users.
    For these reasons, Amendment No. 14 to Certificate of Compliance 
No. 1014 does not constitute backfitting under Sec.  72.62 or Sec.  
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 the following methods.

------------------------------------------------------------------------
                Document                        ADAMS accession No.
------------------------------------------------------------------------
Letter from Holtec International          ML18331A052
 Transmitting Request for Amendment No.
 14 to Certificate of Compliance No.
 1014, October 31, 2018.
Attachment 1: Summary of Request for      ML18331A043
 Amendment No. 14 to Certificate of
 Compliance No. 1014, October 31, 2018.
Attachment 2: Proposed Amendment No. 14   ML18331A046
 to Certificate of Compliance No. 1014,
 October 31, 2018.
Attachment 3: Proposed Amendment No. 14   ML18331A047
 to Certificate of Compliance No. 1014,
 Appendix A, October 31, 2018.
Attachment 4: Proposed Amendment No. 14   ML18331A048
 to Certificate of Compliance No. 1014,
 Appendix B, October 31, 2018.

[[Page 52751]]

 
Attachment 5: Final Safety Analysis       ML18331A049
 Report Proposed Changes, October 31,
 2018.
Letter from Holtec International          ML18324A577
 Transmitting Supplement to Amendment
 Request, November 6, 2018.
Letter from Holtec International          ML19065A053
 Transmitting Responses to NRC's 1st
 Round of Requests for Additional
 Information for Amendment No. 14,
 February 28, 2019.
Attachment 2: Requests for Additional     ML19065A027
 Information, Combined Responses, Non-
 Proprietary, February 28, 2019.
Attachment 3: Final Safety Analysis       ML19065A029
 Report Proposed Changes, Non-
 Proprietary, February 28, 2019.
Attachment 4: Summary of Proposed         ML19065A030
 Changes, Non-Proprietary, February 28,
 2019.
Letter from Holtec International          ML19101A339
 Transmitting Responses to Clarification
 Questions, April 5, 2019.
Attachment 1: Responses to Clarification  ML19101A337
 Questions, April 5, 2019.
Attachment 2: Final Safety Analysis       ML19114A289
 Report (Proposed Revision 16B), April
 5, 2019.
Letter from Holtec International,         ML19121A280
 Submittal of Responses to Clarification
 Questions, April 23, 2019.
Final Safety Analysis Report (Proposed    ML19121A279
 Revision 16B), Chapter 2, Changed
 Pages, April 5, 2019.
Letter from Holtec International,         ML19140A278
 Submittal of Responses to Clarification
 Questions, dated May 13, 2019.
Final Safety Analysis Report (Proposed    ML19140A277
 Revision 16B), Chapter 2, Changed
 Pages, May 13, 2019.
Proposed Certificate of Compliance No.    ML19120A058
 1014 Amendment No. 14, Certificate of
 Compliance for Spent Fuel Storage Casks.
Proposed Certificate of Compliance No.    ML19120A059
 1014 Amendment No. 14, Technical
 Specifications, Appendix A.
Proposed Certificate of Compliance No.    ML19120A061
 1014 Amendment No. 14, Technical
 Specifications, Appendix B.
Proposed Certificate of Compliance No.    ML19120A062
 1014 Amendment No. 14, Technical
 Specifications, Appendix A-100U.
Proposed Certificate of Compliance No.    ML19120A063
 1014 Amendment No. 14, Technical
 Specifications, Appendix B-100U.
Certificate of Compliance No. 1014        ML19120A064
 Amendment No. 14, Preliminary Safety
 Evaluation Report.
Email from J. Tomlinson, Holtec,          ML19224A393
 regarding administrative change to HI-
 Storm 100 Amendment 14 CoC, Appendix B,
 August 8, 2019.
------------------------------------------------------------------------

    The NRC may post materials related to this document, including 
public comments, on the Federal Rulemaking website at https://www.regulations.gov under Docket ID NRC-2019-0160. 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-2019-0160); (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, 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 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 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 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, as corrected 
(ADAMS Accession No. ML19109A111).
    Amendment Number 13 Effective Date: May 13, 2019, as corrected 
(ADAMS Accession No. ML19109A122).
    Amendment Number 14 Effective Date: December 17, 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 17th day of September, 2019.

    For the Nuclear Regulatory Commission.
Daniel H. Dorman,
Acting Executive Director for Operations.
[FR Doc. 2019-21209 Filed 10-2-19; 8:45 am]
 BILLING CODE 7590-01-P