[Federal Register Volume 88, Number 4 (Friday, January 6, 2023)]
[Rules and Regulations]
[Pages 949-953]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2022-28633]
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Rules and Regulations
Federal Register
________________________________________________________________________
This section of the FEDERAL REGISTER contains regulatory documents
having general applicability and legal effect, most of which are keyed
to and codified in the Code of Federal Regulations, which is published
under 50 titles pursuant to 44 U.S.C. 1510.
The Code of Federal Regulations is sold by the Superintendent of Documents.
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Federal Register / Vol. 88, No. 4 / Friday, January 6, 2023 / Rules
and Regulations
[[Page 949]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2022-0181]
RIN 3150-AK88
List of Approved Spent Fuel Storage Casks: Holtec International
HI-STORM Flood/Wind Multipurpose Canister Storage System, Certificate
of Compliance No. 1032, Amendment No. 6
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
Storage Module Flood/Wind (HI-STORM FW) Multipurpose Canister Storage
System listing within the ``List of approved spent fuel storage casks''
to include Amendment No. 6 to Certificate of Compliance No. 1032.
Amendment No. 6 revises and clarifies design and operational
requirements in the certificate of compliance for the HI-STORM FW
overpack. This amendment also incorporates additional clarifications as
well as editorial changes that do not change the substantive technical
information of the certificate of compliance.
DATES: This direct final rule is effective March 22, 2023 unless
significant adverse comments are received by February 6, 2023. 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direct final rule is withdrawn as a result of such comments, timely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: Submit your comments, identified by Docket ID NRC-2022-0181,
at https://www.regulations.gov. If your material cannot be submitted
using https://www.regulations.gov, call or email the individual listed
in the FOR FURTHER INFORMATION CONTACT section of this document for
alternate instructions.
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: Norma Garcia Santos, Office of Nuclear
Material Safety and Safeguards, telephone: 301-415-6999, email:
[email protected] and Gregory 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 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-2022-0181 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-2022-0181. Address
questions about NRC dockets to Dawn Forder, telephone: 301-415-3407,
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 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, by appointment, at the NRC's PDR, Room P1 B35, One White
Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. To make
an appointment to visit the PDR, please send an email to
[email protected] or call 1-800-397-4209 or 301-415-4737, between
8:00 a.m. and 4:00 p.m. eastern time, Monday through Friday, except
Federal holidays.
B. Submitting Comments
Please include Docket ID NRC-2022-0181 in your comment submission.
The NRC requests that you submit comments through the Federal
rulemaking website at https://www.regulations.gov. If your material
cannot be submitted using https://www.regulations.gov, call or email
the individual or individuals listed in the FOR FURTHER INFORMATION
CONTACT section of this document for alternate instructions.
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
[[Page 950]]
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 rule is limited to the changes contained in Amendment No. 6 to
Certificate of Compliance No. 1032 and does not include other aspects
of the Holtec International Storage Multipurpose Flood/Wind (HI-STORM
FW or Holtec International HI-STORM FW) 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 non-controversial.
Adequate protection of public health and safety continues to be
reasonably assured. The amendment to the rule will become effective on
March 22, 2023. However, if the NRC receives any significant adverse
comment on this direct final rule by February 6, 2023, 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 or as otherwise
appropriate. In general, 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.
III. Background
Section 218(a) of the Nuclear Waste Policy Act of 1982, as amended,
states 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 ``[t]he 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 that 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
March 28, 2011 (76 FR 17019), that approved the Holtec International
HI-STORM FW System design and added it to the list of NRC approved cask
designs in Sec. 72.214, ``List of approved spent fuel storage casks,''
as Certificate of Compliance No. 1032.
IV. Discussion of Changes
By letter dated October 2, 2019, and supplemented on June 30, 2020,
December 21, 2020, August 2, 2021, and November 29, 2021, Holtec
International submitted a request to amend Certificate of Compliance
No. 1032 for the HI-STORM Flood/Wind Multipurpose Canister Storage
System. Amendment No. 6 revises the certificate and technical
specifications as follows:
add anchored configuration for the HI-STORM FW overpack;
allow use of non-single failure proof lifting equipment
during handling of heavy loads within the 10 CFR part 72 jurisdictional
boundary;
revise LCO 3.1.2, ``SFSC Heat Removal System
Operability,'' to allow an engineering evaluation to be performed in
lieu of transferring the multipurpose canister (MPC) into a transfer
cask;
revise the Radioactive Effluent Control Program to no
longer require annual submittal of a separate radioactive effluent
report [10 CFR 72.44(d)(3)] for the HI-STORM FW system;
revise the allowable contents for the MPC-37, -89, and -
32ML to clarify fuel debris requirements permitted for storage;
revise the MPC-37, -89, and -32ML basket design features
to clarify that the minimum cell ID and minimum cell wall thickness are
nominal dimensions; and
incorporate additional clarifications and editorial
changes that do not substantively change the technical information of
the certificate of compliance.
As documented in the preliminary safety evaluation report, the NRC
performed a safety evaluation of the proposed certificate of compliance
amendment request. The NRC determined that this amendment does not
reflect a significant change in design or fabrication of the cask.
Specifically, the NRC determined that the design of the cask would
continue to maintain confinement, shielding, and criticality control in
the event of each evaluated accident condition. In addition, any
resulting occupational exposure or offsite dose rates from the
implementation of Amendment No. 6 would remain well within the limits
specified by 10 CFR part 20, ``Standards for Protection Against
Radiation.'' Thus, the NRC found 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 NRC staff determined that the amended HI-STORM FW Cask System
design, when used under the conditions specified in the certificate of
compliance, the 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 reasonably
assured. When this direct final rule becomes effective, persons who
hold a general
[[Page 951]]
license under Sec. 72.210 may, consistent with the license conditions
under Sec. 72.212, load spent nuclear fuel into HI-STORM FW Cask
Systems that meet the criteria of Amendment No. 6 to Certificate of
Compliance No. 1032.
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 revises the
HI-STORM FW Cask System design listed in Sec. 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 ``Agreement State Program Policy Statement'' approved by
the Commission on October 2, 2017, and published in the Federal
Register on October 18, 2017 (82 FR 48535), this rule is classified as
Compatibility Category NRC--Areas of Exclusive NRC Regulatory
Authority. 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. Therefore, compatibility is not required for program
elements in this category.
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 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 HI-STORM FW Cask
System design listing within the ``List of approved spent fuel storage
casks'' to include Amendment No. 6 to Certificate of Compliance No.
1032.
B. The Need for the Action
This direct final rule amends the certificate of compliance for the
HI-STORM FW Cask System design within the list of approved spent fuel
storage casks to allow power reactor licensees to store spent fuel at
reactor sites in casks with the approved modifications under a general
license. Specifically, Amendment No. 6 revises the certificate of
compliance as described in Section IV, ``Discussion of Changes,'' of
this document, for the use of the HI-STORM FW Cask 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 analyzed
in the environmental assessment for the 1990 final rule. The
environmental assessment for this Amendment No. 6 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 HI-STORM FW 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, can 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.
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. 6 would remain well
within the 10 CFR part 20 limits. The NRC has also determined that the
design of the cask as modified by this rule would maintain confinement,
shielding, and criticality control in the event of an accident.
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 exposures, and no significant increase in the
potential for, or consequences from, radiological accidents. The NRC
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.
6 and not issue the direct final rule. Consequently, any 10 CFR part 72
general licensee that seeks to load spent nuclear fuel into the HI-
STORM FW Cask System in accordance with the changes described in
proposed Amendment No. 6 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. 6 to Certificate of Compliance No. 1032
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
[[Page 952]]
NRC concludes that this direct final rule, ``List of Approved Spent
Fuel Storage Casks: Holtec International HI-STORM Flood/Wind
Multipurpose Canister Storage System, Certificate of Compliance No.
1032, Amendment No. 6,'' 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 (1) it notifies the NRC in advance; (2) the spent fuel
is stored under the conditions specified in the cask's certificate of
compliance; and (3) the conditions of the general license are met. A
list of NRC-approved cask designs is contained in Sec. 72.214. On
March 28, 2011 (76 FR 17019), the NRC issued an amendment to 10 CFR
part 72 that approved the HI-STORM FW Cask System design by adding it
to the list of NRC-approved cask designs in Sec. 72.214.
By letter dated October 2, 2019, and supplemented on June 30, 2020,
December 21, 2020, August 2, 2021, and November 29, 2021, Holtec
International submitted a request to amend Certificate of Compliance
No. 1032 for the HI-STORM FW 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. 6 and to require any 10 CFR part 72 general licensee seeking to
load spent nuclear fuel into the HI-STORM FW Cask System under the
changes described in Amendment No. 6 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; 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.
1032 for the HI-STORM FW Cask System, as currently listed in Sec.
72.214. The revision consists of the changes in Amendment No. 6
previously described, as set forth in the revised certificate of
compliance and technical specifications.
Amendment No. 6 to Certificate of Compliance No. 1032 for the HI-
STORM FW 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. 6 applies only to new casks fabricated and
used under Amendment No. 6. These changes do not affect existing users
of the HI-STORM FW Cask System, and the current Amendments Nos. 0 to 5
and 8 continue to be effective for existing users. While current users
of this storage system may comply with the new requirements in
Amendment No. 6, this would be a voluntary decision on the part of
current users.
For these reasons, Amendment No. 6 to Certificate of Compliance No.
1032 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 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 as indicated.
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ADAMS accession No./ web link/Federal Register
Document citation
----------------------------------------------------------------------------------------------------------------
Submission of a Request to Amend the U.S. Nuclear ML19282C357 (package).
Regulatory Commission Certificate of Compliance No. 1032,
October 2, 2019.
Holtec Responses to HI-STORM FW Amd. 6 Requests for ML20182A860 (package).
Supplemental Information, June 30, 2020.
Holtec Responses to HI-STORM FW Amd. 6 Requests for ML20356A328.
Additional Information, December 21, 2020.
Supplemental Responses to HI-STORM FW Amd. 6 Requests for ML21214A130 (package).
Additional Information, August 2, 2021.
Holtec International Revised Supplemental Responses for HI- ML21333A137 (package).
STORM FW Amd. 6 Requests for Additional Information,
November 29, 2021.
Certificate of Compliance No. 1032 Amendment No. 6 ML22145A411.
Preliminary Safety Evaluation Report.
Draft Certificate of Compliance No. 1032 Amendment No. 6... ML22145A408.
Proposed Certificate of Compliance No. 1032 Amendment No. 6 ML22145A409.
Technical Specifications, Appendix A.
[[Page 953]]
Proposed Certificate of Compliance No. 1032 Amendment No. 6 ML22145A410.
Approved Contents and Design Features, Appendix B.
User Need Memorandum for Rulemaking for the HI-STORM Flood/ ML22145A407.
Wind Multipurpose Canister Storage System, Amendment No. 6.
----------------------------------------------------------------------------------------------------------------
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-2022-0181. In addition, the
Federal rulemaking website allows members of the public to receive
alerts when changes or additions occur in a docket folder. To
subscribe: (1) navigate to the docket folder (NRC-2022-0181), (2) click
the ``Subscribe'' link, and (3) enter an email address and click on the
``Subscribe'' link.
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, revise Certificate of Compliance No. 1032 to read
as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1032.
Initial Certificate Effective Date: June 13, 2011, superseded by
Amendment Number 0, Revision 1, on April 25, 2016.
Amendment Number 0, Revision 1, Effective Date: April 25, 2016.
Amendment Number 1 Effective Date: December 17, 2014, superseded by
Amendment Number 1, Revision 1, on June 2, 2015.
Amendment Number 1, Revision 1, Effective Date: June 2, 2015.
Amendment Number 2 Effective Date: November 7, 2016.
Amendment Number 3 Effective Date: September 11, 2017.
Amendment Number 4 Effective Date: July 14, 2020.
Amendment Number 5 Effective Date: July 27, 2020.
Amendment Number 6 Effective Date: March 22, 2023.
Amendment Number 7 [Reserved]
Amendment Number 8 Effective Date: October 11, 2022.
SAR Submitted by: Holtec International.
SAR Title: Final Safety Analysis Report for the HI-STORM FW System.
Docket Number: 72-1032.
Certificate Expiration Date: June 12, 2031.
Model Number: HI-STORM FW MPC-37, MPC-89.
* * * * *
Dated: December 21, 2022.
For the Nuclear Regulatory Commission.
Daniel H. Dorman,
Executive Director for Operations.
[FR Doc. 2022-28633 Filed 1-5-23; 8:45 am]
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