ML22300A137
| ML22300A137 | |
| Person / Time | |
|---|---|
| Issue date: | 12/21/2022 |
| From: | Dan Dorman NRC/EDO |
| To: | |
| References | |
| NRC-2022-0181, RIN 3150-AK88 | |
| Download: ML22300A137 (20) | |
Text
[7590-01-P]
NUCLEAR REGULATORY COMMISSION
[NRC-2022-0181]
RIN 3150-AK88
List of Approved Spent Fuel Storage Casks: Holtec Internationa l HI-STORM
Flood/Wind Multipurpose Canister Storage System, Certificate of Compliance No.
1032, Amendment No. 6
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 S torage Module Flood/Wind
(HI-STORM FW) Multipurpose Canister Storage System listing with in the List of
approved spent fuel storage casks to include Amendment No. 6 t o Certificate of
Compliance No. 1032. Amendment No. 6 revises and clarifies des ign and operational
requirements in the certificate of compliance for the HI-STORM FW overpack. This
amendment also incorporates additional clarifications as well a s editorial changes that
do not change the substantive technical information of the cert ificate of compliance.
DATES: This direct final rule is effective March 22, 2023, unless si gnificant adverse
comments are received by February 6, 2023. If this direct fina l rule is withdrawn as a
result of such comments, timely notice of the withdrawal will b e published in the Federal
Register. Comments received after this date will be considered if it i s practical to do so,
but the NRC is able to ensure consideration only for comments r eceived 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 inst ructions.
For additional direction on obtaining information and submittin g comments,
see Obtaining Information and Submitting Comments in the SUPP LEMENTARY
INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Norma Garcia Santos, Office of Nuclear
Material Safety and Safeguards, telephone: 301-415-6999, email :
Norma.GarciaSantos@nrc.gov and Gregory Trussell, Office of Nuclear Material Safety
and Safeguards, telephone: 301-415-6244, email: Gregory.Trussell@nrc.gov. Both are
staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
2 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 Im pact 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 pu blicly 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 NR C dockets to Dawn
Forder, telephone: 301-415-3407, email: Dawn.Forder@nrc.gov. For technical
questions contact the individual listed in the FOR FURTHER INFO RMATION CONTACT
section of this document.
- NRCs Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the ADA MS Public
3 Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the
search, select Begin Web-based ADAMS Search. For problems wi th ADAMS, please
contact the NRCs Public Document Room (PDR) reference staff at 1-800-397-4209,
301-415-4737, or by email to PDR.Resource@nrc.gov. For the convenience of the
reader, instructions about obtaining materials referenced in th is document are provided
in the Availability of Documents section.
- NRCs PDR: You may examine and purchase copies of public documents,
by appointment, at the NRCs PDR, Room P1 B35, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852. To make an appointm ent to visit the PDR,
please send an email to PDR.Resource@nrc.gov or call 1-800-397-4209 or 301-415-
4737, between 8:00 a.m. and 4:00 p.m. eastern time, Monday thro ugh 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 al ternate
instructions.
The NRC cautions you not to include identifying or contact info rmation 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 e nter the comment
submissions into ADAMS. The NRC does not routinely edit commen t submissions to
remove identifying or contact information.
4 If you are requesting or aggregating comments from other person s 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 dis closed in their comment
submission. Your request should state that the NRC does not routinely edit comment
submissions to remove such information before making the commen t 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 H oltec International
Storage Multipurpose Flood/Wind (HI-STORM FW or Holtec Internat ional HI-STORM
FW) Cask System design. The NRC is using the direct final rule pr ocedure to issue
this amendment because it represents a limited and routine chan ge to an existing
certificate of compliance that is expected to be non-controvers ial. Adequate protection
of public health and safety continues to be reasonably assured. The amendment to the
rule will become effective on [INSERT DATE 75 DAYS AFTER DATE OF
PUBLICATION IN THE FEDERAL REGISTER]. However, if the NRC receives any
significant adverse comment on this direct final rule by [INSERT DATE 30 DAYS
AFTER DATE OF PUBLICATION IN THE FEDERAL REGISTER], then the NRC will
publish a document that withdraws this action and will subseque ntly address the
comments received in a final rule as a response to the companio n proposed rule
published in the Proposed Rules section of this issue of the Federal Register or as
otherwise appropriate. In general, absent significant modifica tions to the proposed
revisions requiring republication, the NRC will not initiate a second comment period on 5
this action.
A significant adverse comment is a comment where the commenter explains why
the rule would be inappropriate, including challenges to the ru les underlying premise or
approach, or would be ineffective or unacceptable without a cha nge. A comment is
adverse and significant if:
- 1) The comment opposes the rule and provides a reason sufficie nt to require a
substantive response in a notice-and-comment process. For exam ple, a substantive
response is required when:
a) The comment causes the NRC to reevaluate (or reconsider) it s position or
conduct additional analysis;
b) The comment raises an issue serious enough to warrant a sub stantive
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, a nd it is apparent
that the rule would be ineffective or unacceptable without inco rporation of the change or
addition.
- 3) The comment causes the NRC to make a change (other than edi torial) to the
rule, certificate of compliance, or technical specifications.
III. Background
Section 218(a) of the Nuclear Waste Policy Act of 1982, as ame nded, 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
6 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 ru le, establish procedures for
the licensing of any technology approved by the Commission unde r Section 219(a) [sic:
218(a)] for use at the site of any civilian nuclear power react or.
To implement this mandate, the Commission approved dry storage of spent
nuclear fuel in NRC-approved casks under a general license by p ublishing 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 Pow er 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 conta ins 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 §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, 2 020, December
21, 2020, August 2, 2021, and November 29, 2021, Holtec Interna tional submitted a
request to amend Certificate of Compliance No. 1032 for the HI-STORM Flood/Wind
7 Multipurpose Canister Storage Sy stem. 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 durin g handling of
heavy loads within the 10 CFR part 72 jurisdictional boundary;
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 c larify that
the minimum cell ID and minimum cell wall thickness are nominal
dimensions; and
- incorporate additional clarifications and editorial changes t hat do not
substantively change the technical information of the certifica te of
compliance.
As documented in the preliminary safety evaluation report, the NRC performed a
safety evaluation of the proposed certificate of compliance ame ndment request. The
NRC determined that this amendment does not reflect a significa nt 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 critical ity control in the event of
each evaluated accident condition. In addition, any resulting occupational exposure or
8 offsite dose rates from the implementation of Amendment No. 6 w ould remain well within
the limits specified by 10 CFR part 20, Standards for Protecti on 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 c onsequences from
radiological accidents.
The NRC staff determined that the amended HI-STORM FW Cask Sys tem
design, when used under the conditions specified in the certifi cate of compliance, the
technical specifications, and the NRCs 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 license under § 72.210 may, consistent with the license conditions under
§ 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. 10 32.
V. Voluntary Consensus Standards
The National Technology Transfer and Advancement Act of 1995 ( Pub. L. 104-
113) requires that Federal agencies use technical standards tha t 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 § 72.2 14, List of
approved spent fuel storage casks. This action does not const itute the establishment of
a standard that contains generally applicable requirements.
9 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 Ca tegory NRC - Areas of
Exclusive NRC Regulatory Authority. The NRC program elements i n this category are
those that relate directly to areas of regulation reserved to t he NRC by the Atomic
Energy Act of 1954, as amended, or the provisions of 10 CFR cha pter I. Therefore,
compatibility is not required for program elements in this cate gory.
VII. Plain Writing
The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federa l 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 we ll as the Presidential
Memorandum, Plain Language in Government Writing, published J une 10, 1998 (63
FR 31885).
VIII. Environmental Assessment and Finding of No Significant I mpact
Under the National Environmental Policy Act of 1969, as amende d, and the
NRCs regulations in 10 CFR part 51, Environmental Protection Regulations for
Domestic Licensing and Related Regulatory Functions, the NRC h as determined that
this direct final rule, if adopted, would not be a major Federa l action significantly affecting
the quality of the human environment and, therefore, an environ mental impact statement
10 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 § 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 stora ge 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, Discussi on 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 lic ense 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 A ct of 1969, as amended.
The HI-STORM FW Cask System is designed to mitigate the effect s of design
11 basis accidents that could occur during storage. Design basis accidents account for
human-induced events and the most severe natural phenomena repo rted for the site and
surrounding area. Postulated accidents analyzed for an indepen dent 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, a nd 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 c hanges, any resulting
occupational exposure or offsite dose rates from the implementa tion 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 environmenta l impacts that significantly
differ from the environmental impacts evaluated in the environm ental assessment
supporting the July 18, 1990, final rule. There will be no sig nificant change in the types
or significant revisions in t he amounts of any effluent released, no significant increase in
the individual or cumulative radiation exposures, and no signif icant increase in the
potential for, or consequences from, radiological accidents. T he 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 Amendmen t 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 Syst em in accordance
12 with the changes described in proposed Amendment No. 6 would ha ve to request an
exemption from the requirements of §§ 72.212 and 72.214. Under this alternative,
interested licensees would have to prepare, and the NRC would h ave to review, a
separate exemption request, thereby increasing the administrati ve burden upon the NRC
and the costs to each licensee. The environmental impacts woul d be the same as the
proposed action.
E. Alternative Use of Resources
Approval of Amendment No. 6 to Certificate of Compliance No. 1 032 would result
in no irreversible commitment of resources.
F. Agencies and Persons Contacted
No agencies or persons outside the NRC were contacted in conne ction with the
preparation of this environmental assessment.
G. Finding of No Significant Impact
The environmental impacts of the action have been reviewed und er the
requirements in the National Environmental Policy Act of 1969, as amended, and the
NRCs regulations in subpart A of 10 CFR part 51, Environmenta l Protection
Regulations for Domestic Licensing and Related Regulatory Funct ions. Based on the
foregoing environmental assessment, the NRC concludes that this direct final rule, List
of Approved Spent Fuel Storage Casks: Holtec International HI-S TORM Flood/Wind
Multipurpose Canister Storage System, Certificate of Compliance No. 1032, Amendment
No. 6, will not have a significant effect on the human environ ment. Therefore, the NRC
has determined that an environmental impact statement is not ne cessary for this direct
13 final rule.
IX. Paperwork Reduction Act Statement
This direct final rule does not contain any new or amended coll ections of
information subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
Existing collections of informat ion 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 requir ed to respond
to, a request for information or an information collection requ irement unless the
requesting document displays a currently valid Office of Manage ment 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 signifi cant economic impact on a
substantial number of small entities. This direct final rule a ffects only nuclear power
plant licensees and Holtec International. These entities do no t fall within the scope of
the definition of small entities set forth in the Regulatory Fl exibility Act or the size
standards established by the NRC (§ 2.810).
14 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 gen eral license in cask
designs approved by the NRC. Any nuclear power reactor license e can use NRC-
approved cask designs to store spent nuclear fuel if 1) it noti fies the NRC in advance; 2)
the spent fuel is stored under the conditions specified in the casks certificate of
compliance; and 3) the conditions of the general license are me t. A list of NRC-
approved cask designs is contained in § 72.214. On March 28, 2 011 (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 t he list of NRC-approved cask designs in §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 Interna tional 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 Amen dment No. 6 and to
require any 10 CFR part 72 general licensee seeking to load spe nt nuclear fuel into the
HI-STORM FW Cask System under the changes described in Amendmen t No. 6 to
request an exemption from the requirements of §§ 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 licens ee.
Approval of this direct final rule is consistent with previous NRC actions. Further,
as documented in the preliminary safety evaluation report and e nvironmental
assessment, this direct final rule will have no adverse effect on public health and safety
15 or the environment. This direct final rule has no significant identifiable impact or benefit
on other government agencies. Based on this regulatory analysi s, the NRC concludes
that the requirements of this direct final rule are commensurat e with the NRC's
responsibilities for public health and safety and the common de fense 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 (§ 72.62) does no t apply to this
direct final rule. Therefore, a backfit analysis is not requir ed. This direct final rule
revises Certificate of Compliance No. 1032 for the HI-STORM FW Cask System, as
currently listed in § 72.214. The revision consists of the cha nges in Amendment No. 6
previously described, as set forth in the revised certificate o f 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 s ubmitted in response to
new NRC requirements, or an NRC request for amendment. Amendme nt No. 6 applies
only to new casks fabricated and used under Amendment No. 6. T hese changes do not
affect existing users of the HI-STORM FW Cask System, and the c urrent 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 § 72.62 or § 50.109(a)(1), or otherwise represent
16 an inconsistency with the issue finality provisions applicable to combined licenses in 10
CFR part 52. Accordingly, the NRC has not prepared a backfit a nalysis for this
rulemaking.
XIII. Congressional Review Act
This direct final rule is not a rule as defined in the Congress ional Review Act.
XIV. Availability of Documents
The documents identified in the following table are available to interested
persons as indicated.
DOCUMENT ADAMS ACCESSION NO. / WEB LINK / FEDERAL REGISTER CITATION Submission of a Request to Amend the U.S. ML19282C357 (package)
Nuclear Regulatory Commission Certificate of Compliance No. 1032, October 2, 2019 Holtec Responses to HI-STORM FW Amd. 6 ML20182A860 (package)
Requests for Supplemental Information, June 30, 2020 Holtec Responses to HI-STORM FW Amd. 6 ML20356A328 Requests for Additional Information, December 21, 2020 Supplemental Responses to HI-STORM FW ML21214A130 (package)
Amd. 6 Requests for Additional Information, August 2, 2021 Holtec International Revised Supplemental ML21333A137 (package)
Responses for HI-STORM FW Amd. 6 Requests for Additional Information, November 29, 2021 Certificate of Compliance No. 1032 ML22145A411 Amendment No. 6 Preliminary Safety Evaluation Report Draft Certificate of Compliance No. 1032 ML22145A408 Amendment No. 6
17 Proposed Certificate of Compliance No. 1032 ML22145A409 Amendment No. 6 Technical Specifications, Appendix A Proposed Certificate of Compliance No. 1032 ML22145A410 Amendment No. 6 Approved Contents and Design Features, Appendix B User Need Memorandum for Rulemaking for ML22145A407 the HI-STORM Flood/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 w ebsite allows
members of the public to receive alerts when changes or additio ns occur in a docket
folder. To subscribe: 1) navigate to the docket folder (NRC-2 022-0181), 2) click the
Subscribe link, and 3) enter an email address and click on th e Subscribe link.
List of Subjects in 10 CFR Part 72
Administrative practice and procedure, Hazardous waste, Indian s,
Intergovernmental relations, Nuc lear energy, Penalties, Radiation protection, Reporting
and recordkeeping requirements, Security measures, Spent fuel, Whistleblowing.
For the reasons set out in the preamble and under the authorit y of the Atomic
Energy Act of 1954, as amended; the Energy Reorganization Act o f 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:
18 PART 72 - LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE
- 1. The authority citation for part 72 continues to read as fol lows:
Authority: Atomic Energy Act of 1954, secs. 51, 53, 57, 62, 63, 65, 69, 8 1, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42 U.S.C. 2071, 20 73, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2210e, 2232, 2233, 2234, 2236, 2237, 22 38, 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 (4 2 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.
- 2. In § 72.214, revise Certificate of Compliance No. 1032 to read as follows:
§ 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: [INSERT DATE 75 DAYS AFTER
PUBLICATION IN THE FEDERAL REGISTER].
19 Amendment Number 7 [Reserved]
Amendment Number 8 Effective Date: October 11, 2022.
SAR Submitted by: Holtec International.
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.
/RA/
Daniel H. Dorman, Executive Director for Operations.
20