ML24051A171
| ML24051A171 | |
| Person / Time | |
|---|---|
| Issue date: | 06/07/2024 |
| From: | Raymond Furstenau NRC/EDO |
| To: | |
| References | |
| 89FR52999, NRC-2024-0041, RIN 3150-AL08 | |
| Download: ML24051A171 (24) | |
Text
[7590-01-P]
NUCLEAR REGULATORY COMMISSION
[NRC-2024-0041]
RIN 3150-AL08
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100
Cask System, Certificate of Compliance No. 1014, Renewed Amendment No. 16
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 Cask System
listing within the List of approved spent fuel storage casks to include Renewed
Amendment No. 16 to Certificate of Compliance No. 1014. Renewed Amendment No. 16
revises the certificate of compliance to add a new overpack, include the ability to use
computational fluid dynamics analysis to evaluate site-specific accident scenarios,
modify the cask design, modify operational and testing requirements, and make changes
to the final safety analysis report.
DATES: This direct final rule is effective September 9, 2024, unless significant adverse
comments are received by July 25, 2024. If this direct final rule is withdrawn as a result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-2024-0041,
at https://www.regulations.gov. If your material cannot be submitted using
https://www.regulations.gov, call or email the individuals listed in the FOR FURTHER
INFORMATION CONTACT section of this document for alternate instructions.
You can read a plain language description of this direct final rule at
https://www.regulations.gov/docket/NRC-2024-0041. For additional direction on
obtaining information and submitting co mments, see Obtaining Information and
Submitting Comments in the SUPPLEME NTARY INFORMATION section of this
document.
FOR FURTHER INFORMATION CONTACT: Alexandra Terres, Office of Nuclear
Materials Safety and Safeguards, telephone: 301-415-7000, email:
Alexandra.Terres@nrc.gov and Yen-Ju Chen, Office of Nuclear Materials Safety and
Safeguards, telephone: 301-415-1018 email: Yen-Ju.Chen@nrc.gov. Both are staff of
the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
2 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-2024-0041 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-2024-0041. Address questions about NRC dockets to Helen
Chang, telephone: 301-415-3228, email: Helen.Chang@nrc.gov. For technical
questions contact the individuals listed in the FOR FURTHER INFORMATION
CONTACT section of this document.
- NRCs 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
3 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 this document are provided
in the Availability of Documents section.
- NRCs PDR: The PDR, where you may examine and order copies of publicly
available documents, is open by appointment. To make an appointment 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 a.m. and 4 p.m. eastern time, Monday through Friday, except Federal
Holidays.
B. Submitting Comments
Please include Docket ID NRC-2024-0041 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 individuals listed in the FOR
FURTHER INFORMATION CONTACT section of this document for alternate
instructions.
The NRC cautions you not to include identif ying or contact information that you
do not want to be publicly disclosed in y our comment submission. The NRC will post all
comment submissions at https://www.regulat ions.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 w ant to be publicly disclosed in their comment
submission. Your request should state that the NRC does not routinely edit comment
4 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 changes contained in Renewed Amendment No. 16 to
Certificate of Compliance No. 1014 and does not include other aspects of the HI-
STORM 100 Cask System design. The NRC is using the direct final rule procedure to
issue this amendment because it represents a limited and routine change to an existing
certificate of compliance that is expected to be non-controversial. Adequate protection of
public health and safety continues to be reasonably assured. The amendment to the rule
will become effective on September 9, 2024. However, if the NRC receives any
significant adverse comment on this direct fi nal rule by July 25, 2024, 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 rules 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
5 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 iss ue 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, 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 [t]he Commission shall, by rule, establish
procedures for the licensing of any te chnology approved by the Commission under
Section 219(a) [sic: 218(a)] for use at the site of any civilian nuclear power reactor.
6 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 May 1, 2000 (65 FR 25241), that approved the HI-
STORM 100 Cask System design and added it to the list of NRC-approved cask designs
in § 72.214 as Certificate of Compliance No. 1014.
IV. Discussion of Changes
On March 9, 2021, Holtec International submitted a request to the NRC to amend
Certificate of Compliance No. 1014 for the HI-STORM 100 Cask System. Holtec
International supplemented its request on t he following dates: August 11, 2021, August
31, 2022, September 9, 2022, October 3, 2022, January 4, 2023, January 5, 2023,
January 13, 2023, March 17, 2023, and September 20, 2023. On February 17, 2022,
Holtec International requested to remove the certificate of compliance (CoC)
reorganization, also known as graded approach, from this amendment. 1 The Renewed
Amendment No. 16 revises the certificate of compliance to:
1 On May 6, 2021, Holtec submitted a request for Amendment No. 16 to CoC No. 1014 (Package ML21126A266, incoming letter ML21126A267), which included the CoC reorganization, known as graded approach. On February 17, 2022, Holtec requested to remove the graded approach from Amendment No. 16 (ML22048C221). Therefore, this direct final rule, and its companion proposed rule only address Amendment No. 16 to CoC No. 1014, as updated.
7
- Add a new unventilated high density (UVH) overpack, HI-STORM 100
UVH, which includes high density concrete for shielding. The UVH is to be used with the
MPC-32M and MPC-68M.
- Include the ability to use the computational fluid dynamics (CFD) analysis
to evaluate site-specific fire accident scenario.
- Modify the vent and drain penetrations to include the option of a second
port cover plate.
- Include the ability to use CFD analysis to evaluate site-specific burial
under debris accident scenario.
- Include the ability to use water without glycol in the HI-TRAC water jacket
during transfer operations below 32°F based on the site-specific MPC total heat loads.
- Change the hydrostatic pressure test of the MPC acceptance criteria to
be examination for leakage only.
- Remove post hydrostatic test liquid penetrant and magnetic particle
examination.
- Reduce the minimum cooling time for pressurized water reactor fuel from
2 years to 1 year.
Renewed Amendment No. 16 also revises the final safety analysis report
(FSAR), appendix 1.D, Specification for Plain Concrete in the HI-STORM Family of
Overpacks, to enhance certain requirements, to add certain revised shielding
assumptions following a significant thermal event, and to add critical characteristics for
concrete employed in the HI-STORM 100 UVH System. Renewed Amendment No. 16
replaces the fuel qualification tables in the FSAR, chapter 2, and in the CoC, including
the equation for calculation of the maximum allowable burnup as a function of the
8 cooling time and cooling time dependent coefficients, with simpler sets of burnup and
cooling time limits.
The changes to the aforementioned documents are identified with revisions bars
in the margin of each document .
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, t he 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 Renewed Amendment No. 16 would
remain well within the limits specified by 10 CFR part 20, Standards for Protection
Against Radiation. Therefore, 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 Holtec International HI-STORM 100
Cask System cask design, when used under the conditions specified in the certificate 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 100 casks
that meet the criteria of Renewed Amendment No. 16 of Certificate of Compliance No.
1014.
9 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 im practical. In this direct final rule, the NRC
revises the Holtec International HI-STORM 100 Cask System design listed in § 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
10 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
NRCs 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, ther efore, 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 § 72.214 to revise the Holtec International HI-STORM
100 Cask System listing within the List of approved spent fuel storage casks to include
Renewed Amendment No. 16 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 desi gn 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, Renewed
Amendment No. 16 revises the certificate of compliance as follows:
11
- Add a new UVH overpack, HI-STORM 100 UVH, which includes high
density concrete for shielding. The UVH is to be used with the MPC-32M
and MPC-68M.
- Include the ability to use the CFD analysis to evaluate site-specific fire
accident scenario.
- Modify the vent and drain penetrations to include the option of a second
port cover plate.
- Include the ability to use CFD analysis to evaluate site-specific burial
under debris accident scenario.
- Include the ability to use water without glycol in the HI-TRAC water jacket
during transfer operations below 32°F based on the site-specific MPC
total heat loads.
- Change the hydrostatic pressure test of the MPC acceptance criteria to
be examination for leakage only. Remove post hydrostatic test liquid
penetrant and magnetic particle examination.
- Reduce the minimum cooling time for pressurized water reactor fuel from
2 years to 1 year.
Renewed Amendment No. 16 also revises the final safety analysis report (FSAR)
appendix 1.D, Specification for Plain Concrete in the HI-STORM Family of Overpacks, to
enhance certain requirements, to add certain revised shielding assumptions following a
significant thermal event, and to add critical characteristics for concrete employed in the
HI-STORM 100 UVH System. Renewed Amendment No. 16 replaces the fuel
qualification tables in the FSAR, chapter 2, and in the CoC, including the equation for
calculation of the maximum allowable burnup as a function of the cooling time and
cooling time dependent coefficients, with simpler sets of burnup and cooling time limits.
12 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 R enewed Amendment No. 16 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 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 ra tes from the implementation of Renewed
Amendment No. 16 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
13 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 t he preliminary safety evaluation report.
D. Alternative to the Action
The alternative to this action is to deny approval of Renewed Amendment No. 16
and not issue the direct final rule. Consequently, any 10 CFR part 72 general licensee
that seeks to load spent nuclear fuel into Holtec International HI-STORM 100 Cask
System in accordance with the changes described in proposed Renewed Amendment
No. 16 would have 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 have to review, a separate exemption request, thereby increasing the
administrative burden upon the NRC and the cost s to each licensee. The environmental
impacts would be the same as the proposed action.
E. Alternative Use of Resources
Approval of Renewed Amendment No. 16 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
14 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
NRCs regulations in subpart A of 10 CFR part 51, Environmental Protection
Regulations for Domestic Licensing and Related Regulatory Functions. Based on the
foregoing environmental assessment, the NRC concl udes that this direct final rule, List
of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask
System, Certificate of Compliance No. 1014, Renewed Amendment No. 16, 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
15 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 (§ 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 casks certificate of
compliance; and 3) the conditions of the general license are met. A list of NRC-approved
cask designs is contained in § 72.214. On May 31, 2000 (65 FR 25241), the NRC issued
an amendment to 10 CFR part 72 that approved the HI-STORM 100 Cask System by
adding it to the list of NRC-approved cask designs in § 72.214.
March 9, 2021, as supplemented on August 11, 2021, August 31, 2022,
September 9, 2022, October 3, 2022, January 4, 2023, January 5, 2023, January 13,
16 2023, March 17, 2023, and September 20, 2023, Holtec International submitted a
request to amend the HI-STORM 100 Cask System as described in Section IV,
Discussion of Changes, of this document.
The alternative to this action is to withhold approval of Renewed Amendment No.
16 and to require any 10 CFR part 72 general licensee seeking to load spent nuclear
fuel into Holtec International HI-STORM 100 Cask System under the changes described
in Renewed Amendment No. 16 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 administrat ive 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 safe ty 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 (§ 72.62) does not apply to this
direct final rule. Therefore, a backfit analysis is not required. This direct final rule revises
17 Certificate of Compliance No. 1014 for the Holtec International HI-STORM 100 Cask
System, as currently listed in § 72.214. The revision consists of the changes in Renewed
Amendment No. 16 previously described, as set forth in the revised certificate of
compliance and technical specifications.
Renewed Amendment No. 16 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. Renewed Amendment No. 16 applie s only to new casks fabricated and
used under Renewed Amendment No. 16. These changes do not affect existing users of
the Holtec International HI-STORM 100 Cask System, and the current Amendment No.
15 continues to be effective for existing users. While current users of this storage system
may comply with the new requirements in Renewed Amendment No. 16, this would be a
voluntary decision on the part of current users.
For these reasons, Renewed Amendment No. 16 to Certificate of Compliance
No. 1014 does not constitute backfitting under § 72.62 or § 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
18 The documents identified in the following table are available to interested
persons as indicated.
DOCUMENT ADAMS ACCESSION NO. / WEB LINK / FEDERAL REGISTER CITATION
Amendment Request Documents Holtec International, Submittal of HI- ML21068A360 (package)
STORM 100 Multipurpose Canister Storage System Amendment 16 Request, dated March 9, 2021 HI-STORM 100 Amendment 16 ML21223A045 (package)
Responses to Requests for Supplemental Information, dated August 11, 2021 HI-STORM 100 Amendment 16 ML22243A269 (package)
Responses to Requests for Additional Information (Batches 1 and 2), dated August 31, 2022 Holtec International, HI-STORM 100 ML22249A347 (package)
Amendment 16 Responses to Requests for Additional Information (Batch 2), dated September 9, 2022 HI-STORM 100 Amendment 16 ML22276A286 (package)
Responses to Requests for Additional Information (Batch 3), dated October 3, 2022 Holtec International, HI-STORM 100 ML23005A000 (package)
Amendment 16 Responses to Requests for Additional Information (Batch 4), dated January 4, 2023 Holtec International, HI-STORM 100 ML23005A273 (package)
Amendment 16 Responses to Requests for Additional Information (Batch 4) -
Additional Supporting Document, dated January 5, 2023 Holtec International, HI-STORM 100 ML23013A337 (package)
Amendment 16 Responses to Requests for Additional Information (Batch 5), dated January 13, 2023 HI-STORM 100 Amendment 16 RAI 3-3 ML23076A271 (package)
Clarification, dated March 17, 2023 HI-STORM 100 Amendment 16 ML23263B122 (package)
Responses to Second Round Requests for Additional Information, dated September 20, 2023 19 Holtec International - HI-STORM 100 ML22048C222 Multipurpose Canister Storage System Amendment 19, dated February 17, 2022 Technical Specifications Proposed Certificate of Compliance No. ML23123A104 1014, Amendment 16 Proposed Technical Specifications, ML23123A105 Appendix A, Certificate of Compliance No.
1014, Amendment 16 Proposed Technical Specifications, ML23123A106 Appendix B, Certificate of Compliance No. 1014, Amendment 16 Proposed Technical Specifications, ML23123A107 Appendix C, Certificate of Compliance No. 1014, Amendment 16 Proposed Technical Specifications, ML23123A108 Appendix D, Certificate of Compliance No. 1014, Amendment 16 Proposed Technical Specifications, ML23123A109 Appendix A-100U, Certificate of Compliance No. 1014, Amendment 16 Proposed Technical Specifications, ML23123A110 Appendix B-100U, Certificate of Compliance No. 1014, Amendment 16 Preliminary Safety Evaluation Report Preliminary Certificate of Compliance ML23123A112 1014 Amendment 16 Safety Evaluation Report Additional Documents Final Rule, Storage of Spent Fuel in 55 FR 29181 NRC-Approved Storage Casks at Power Reactor Sites, published July 18, 1990 Final Rule, List of Approved Spent Fuel 65 FR 25241 Storage Casks: Holtec HI-STORM 100 Addition, published May 1, 2000 Revision to Policy Statement, Agreement 82 FR 48535 State Program Policy Statement; Correction, published October 18, 2017 Presidential Memorandum, Plain 63 FR 31885 Language in Government Writing, published June 10, 1998
The NRC may post materials related to this document, including public
comments, on the Federal rulemaking website at https://www.regulations.gov under
20 Docket ID NRC-2024-0041. 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-2024-0041); 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
- 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.
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- 2. In § 72.214, Certificate of Compliance No. 1014 is revised to read as follows:
§ 72.214 List of approved spent fuel storage casks.
Certificate Number: 1014.
Initial Certificate Effective Date: May 31, 2000, superseded by Renewed Initial Certificate
Effective Date: August 2, 2023.
Amendment Number 1 Effective Date: July 15, 2002, superseded by Renewed
Amendment Number 1 Effective Date: August 2, 2023.
Amendment Number 2 Effective Date: June 7, 2005, superseded by Renewed
Amendment Number 2 Effective Date: August 2, 2023.
Amendment Number 3 Effective Date: May 29, 2007, superseded by Renewed
Amendment Number 3 Effective Date: August 2, 2023.
Amendment Number 4 Effective Date: January 8, 2008, superseded by Renewed
Amendment Number 4 Effective Date: August 2, 2023.
Amendment Number 5 Effective Date: July 14, 2008, superseded by Renewed
Amendment Number 5 Effective Date: August 2, 2023.
Amendment Number 6 Effective Date: August 17, 2009, superseded by Renewed
Amendment Number 6 Effective Date: August 2, 2023.
Amendment Number 7 Effective Date: December 28, 2009, superseded by Renewed
Amendment Number 7 Effective Date: August 2, 2023.
Amendment Number 8 Effective Date: May 2, 2012, as corrected on November 16, 2012
(ADAMS Accession No. ML12213A170); superseded by Amendment Number 8,
Revision 1, Effective Date: February 16, 2016; superseded by Renewed Amendment
22 Number 8, Revision 1 Effective Date: August 2, 2023.
Amendment Number 9 Effective Date: March 11, 2014, superseded by Amendment
Number 9, Revision 1, Effective Date: March 21, 2016, as corrected on August 25, 2017
(ADAMS Accession No. ML17236A451); superseded by Renewed Amendment Number
9, Revision 1 Effective Date: August 2, 2023.
Amendment Number 10 Effective Date: May 31, 2016, as corrected on August 25, 2017
(ADAMS Accession No. ML17236A452); superseded by Renewed Amendment Number
10 Effective Date: August 2, 2023.
Amendment Number 11 Effective Date: February 25, 2019, as corrected (ADAMS
Accession No. ML19343B024); superseded by Renewed Amendment Number 11
Effective Date: August 2, 2023.
Amendment Number 12 Effective Date: February 25, 2019, as corrected on May 30,
2019 (ADAMS Accession No. ML19109A111); further corrected December 23, 2019
(ADAMS Accession No. ML19343A908); superseded by Renewed Amendment Number
12 Effective Date: August 2, 2023.
Amendment Number 13 Effective Date: May 13, 2019, as corrected on May 30, 2019
(ADAMS Accession No. ML19109A122); further corrected December 23, 2019 (ADAMS
Accession No. ML19343B156); superseded by Renewed Amendment Number 13
Effective Date: August 2, 2023.
Amendment Number 14 Effective Date: December 17, 2019, as corrected (ADAMS
Accession No. ML19343B287); superseded by Renewed Amendment Number 14
Effective Date: August 2, 2023.
Amendment Number 15 Effective Date: June 14, 2021, superseded by Renewed
Amendment Number 15 Effective Date: August 2, 2023.
Renewed Amendment Number 16 Effective Date: September 9, 2024.
23 Renewed Amendment Number 17 Effective Date: January 16, 2024.
Safety Analysis Report (SAR) Submitted by: Holtec International.
Title:
Final Safety Analysis Report for the HI-STORM 100 Cask System.
Docket Number: 72-1014.
Certificate Expiration Date: May 31, 2020.
Renewed Certificate Expiration Date: May 31, 2060.
Model Number: HI-STORM 100.
Dated: June 7, 2024.
For the Nuclear Regulatory Commission.
/RA/
Raymond V. Furstenau, Acting Executive Director for Operations.
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