ML20336A135

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Enclosure 1 - Direct Final Rule CoC No. 1014, Amendment No. 15
ML20336A135
Person / Time
Issue date: 03/16/2021
From: Margaret Doane
NRC/EDO
To:
Cox Vanessa
Shared Package
ML20332A081 List:
References
NRC-2020-0257, RIN 3150-AK53
Download: ML20336A135 (23)
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Text

[7590-01-P]

NUCLEAR REGULATORY COMMISSION 10 CFR Part 72

[NRC-2020-0257]

RIN 3150-AK53 List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Amendment No. 15 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 Amendment No. 15 to Certificate of Compliance No. 1014. Amendment No. 15 amends the certificate of compliance to add a new overpack and a new transfer cask, revise allowed content for storage, and make other changes to the storage system.

DATES: This direct final rule is effective June 14, 2021, unless significant adverse comments are received by April 28, 2021. If this direct final rule is withdrawn as a result of such comments, timely notice of the withdrawal will be published in the Federal

Register. Comments received after this date will be considered if it is practical to do so, but the NRC is able to ensure consideration only for comments received on or before this date. Comments received on this direct final rule will also be considered to be comments on a companion proposed rule published in the Proposed Rules section of this issue of the Federal Register.

ADDRESSES: You may submit comments by any of the following methods:

  • Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0221. Address questions about NRC dockets to Dawn Forder; telephone: 301-415-3407; e-mail: Dawn.Forder@nrc.gov. For technical questions contact the individuals listed in the FOR FURTHER INFORMATION CONTACT section of this document.
  • E-mail comments to: Rulemaking.Comments@nrc.gov. If you do not receive an automatic e-mail reply confirming receipt, then contact us at 301-415-1677.
  • Mail comments to: Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, ATTN: Rulemakings and Adjudications Staff.

For additional direction on obtaining information and submitting comments, see Obtaining Information and Submitting Comments in the SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Yen-Ju Chen, Office of Nuclear Material Safety and Safeguards; telephone: 301-415-1018; e-mail: Yen-Ju.Chen@nrc.gov or Vanessa Cox, Office of Nuclear Material Safety and Safeguards; telephone: 301-415-8342; e-mail: Vanessa.Cox@nrc.gov. Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

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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-2020-0257 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:

  • NRCs Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select Begin Web-based ADAMS Search. For problems with ADAMS, please contact the NRCs Public Document Room (PDR) reference staff at 1-800-397-4209, 3

301-415-4737, or by e-mail 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.

  • Attention: The PDR, where you may examine and order copies of public documents, is currently closed. You may submit your request to the PDR via e-mail at PDR.Resource@nrc.gov or call 1-800-397-4209 between 8:00 a.m. and 4:00 p.m.

(EST), Monday through Friday, except Federal holidays.

B. Submitting Comments The NRC encourages electronic comment submission through the Federal Rulemaking Web Site (https://www.regulations.gov). Please include Docket ID NRC-2020-0257 in your comment submission.

The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information.

If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment into ADAMS.

II. Rulemaking Procedure 4

This rule is limited to the changes contained in Amendment No. 15 to Certificate of Compliance No. 1014 and does not include other aspects of the Holtec International 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. The NRC has determined that, with the requested changes, adequate protection of public health and safety will continue to be reasonably assured. The amendments to the rule will become effective on [INSERT DATE 75 DAYS AFTER DATE OF PUBLICATION IN THE FEDERAL REGISTER]. However, if the NRC receives significant adverse comments 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 subsequently address the comments received in a final rule as a response to the companion proposed rule published in the Proposed Rules section of this issue of the Federal Register. Absent significant modifications to the proposed revisions requiring republication, the NRC will not initiate a second comment period on this action.

A significant adverse comment is a comment where the commenter explains why the rule would be inappropriate, including challenges to the 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 response is required when:

a) The comment causes the NRC staff to reevaluate (or reconsider) its position 5

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; or
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 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 6

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 Holtec International HI-STORM 100 Cask System 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. 1014.

IV. Discussion of Changes On March 20, 2019, Holtec International submitted a request to amend Certificate of Compliance No. 1014 for the HI-STORM 100 Cask System. Holtec International supplemented its request on September 16, 2019; April 28, 2020; May 15, 2020; June 12, 2020; June 22, 2020; July 30, 2020; August 14, 2020; September 1, 2020; and September 25, 2020. Amendment No. 15 revises the certificate of compliance as follows:

1. Adds a new version of a transfer cask, HI-TRAC MS (maximum shielded),

which includes an option for variable weight of the lead and water jacket and cooling passages to the bottom lid. HI-TRAC MS is to be used with all multipurpose canisters (MPCs) approved for use in Amendment Nos. 0 through 14 to the HI-STORM 100 System and the newly proposed MPC-32M, MPC-32 Version 1, and MPC-68 Version 1.

2. Includes MPC-32M for storage in the HI-STORM 100 System.

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3. Includes MPC-32 Version 1 and MPC-68 Version 1 for storage in HI-STORM 100 System.
4. Adds the new overpack, HI-STORM 100S Version E, and allows it to be used with all MPCs approved for use in Amendment Nos. 0 through 14 to the HI-STORM 100 System and the newly proposed MPC-32M, MPC-32 Version 1, and MPC-68 Version 1.
5. Adds three additional boiling water reactor fuel types to the approved content for MPC-68M: 10x10I, 10x10J, and 11x11A.
6. Lowers the allowed ambient temperature from 80 °F to 70 °F for HI-STORM 100S Version E.
7. Adds HI-DRIP and dry ice jacket ancillary system as additional cooling when the MPC is loaded in the HI-TRAC transfer cask.
8. Allows for partial gadolinium credit for boiling water reactor fuel assemblies types 10x10 and 11x11 assembly classes in MPC-68M.
9. Includes allowance for canisters currently loaded under earlier amendments which had different helium leak test requirements.
10. Updates Drawing No. 7195 for the MPC-68M by removing dimensions which are not used in the safety analysis.
11. Includes dry ice jacket as optional alternate cooling method for short-term operation of the loaded HI-TRAC.

Holtec International originally proposed an additional change, which it did not pursue and the staff did not review. As Holtec International listed this change as proposed change #9 and the staffs preliminary safety evaluation report retained Holtec Internationals numbering, the preliminary safety evaluation report refers to changes 9, 10, and 11 as proposed changes 10, 11, and 12, respectively.

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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. This amendment does not reflect a significant change in design or fabrication of the cask. In addition, any resulting occupational exposure or offsite dose rates from the implementation of Amendment No. 15 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 determined that the amended Holtec International HI-STORM 100 Cask System 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 Holtec International HI-STORM 100 Cask System casks that meet the criteria of Amendment No. 15 to Certificate of Compliance No. 1014.

V. Voluntary Consensus Standards 9

The National Technology Transfer and Advancement Act of 1995 (Pub. L. 104-113) requires that Federal agencies use technical standards that are developed or adopted by voluntary consensus standards bodies unless the use of such a standard is inconsistent with applicable law or otherwise impractical. In this direct final rule, the NRC will revise the Holtec International HI-STORM 100 Cask System design listed in

§ 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. Although an Agreement State may not adopt program elements reserved to the NRC, and the Category NRC does not confer regulatory authority on the State, the State may wish to inform its licensees of certain requirements by means consistent with the particular States administrative procedure laws.

VII. Plain Writing The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal agencies to 10

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 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, 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 § 72.214 to revise the Holtec International HI-STORM 100 Cask System listing within the List of approved spent fuel storage casks to include Amendment No. 15 to Certificate of Compliance No. 1014.

B. The Need for the Action This direct final rule amends the certificate of compliance for the Holtec International HI-STORM 100 Cask System design within the list of approved spent fuel storage casks that power reactor licensees can use to store spent fuel at reactor sites under a general license. Specifically, Amendment No. 15 amends the certificate of compliance as described in Section IV, Discussion of Changes, of this document, for 11

the use of the Holtec International HI-STORM 100 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 Amendment No. 15 tiers off of the environmental assessment for the July 18, 1990, final rule. Tiering on past environmental assessments is a standard process under the National Environmental Policy Act of 1969, as amended.

The Holtec International HI-STORM 100 Cask System is designed to mitigate the effects of design basis accidents that could occur during storage. Design basis accidents account for human-induced events and the most severe natural phenomena reported for the site and surrounding area. Postulated accidents analyzed for an independent spent fuel storage installation, the type of facility at which a holder of a power reactor operating license would store spent fuel in casks in accordance with 10 CFR part 72, 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.

The design of the cask would prevent loss of confinement, shielding, and criticality control in the event of each evaluated accident condition. If confinement, shielding, or criticality control are maintained, the environmental impacts resulting from an accident would be insignificant. This amendment does not reflect a significant change in design or fabrication of the cask. Because there are no significant design or 12

process changes, any resulting occupational exposure or offsite dose rates from the implementation of Amendment No. 15 would remain well within the 10 CFR part 20 limits. Therefore, the proposed certificate of compliance changes will not result in any radiological or non-radiological environmental impacts that significantly differ from the environmental impacts evaluated in the environmental assessment supporting the July 18, 1990, final rule. There will be no significant change in the types or significant revisions in the amounts of any effluent released, no significant increase in the individual or cumulative radiation exposures, and no significant increase in the potential for or consequences 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. 15 and not issue the direct final rule. Consequently, any 10 CFR part 72 general licensee that seeks to load spent nuclear fuel into a Holtec International HI-STORM 100 Cask System in accordance with the changes described in Amendment No. 15 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 costs to each licensee. The environmental impacts would be the same as the proposed action.

E. Alternative Use of Resources Approval of Amendment No. 15 to Certificate of Compliance No. 1014 would result in no irreversible commitment of resources.

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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 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 concludes that this direct final rule entitled List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Amendment No. 15 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.

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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 (§ 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 1, 2000 (65 FR 25241), the 15

NRC issued an amendment to 10 CFR part 72 that approved the Holtec International HI-STORM 100 Cask System design by adding it to the list of NRC-approved cask designs in § 72.214.

On March 20, 2019, and as supplemented on September 16, 2019; April 28, 2020; May 15, 2020; June 12, 2020; June 22, 2020; July 30, 2020; August 14, 2020; September 1, 2020; and September 25, 2020, 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 Amendment No. 15 and to require any 10 CFR part 72 general licensee seeking to load spent nuclear fuel into the Holtec International HI-STORM 100 Cask System under the changes described in Amendment No. 15 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 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.

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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 amends Certificate of Compliance No. 1014 for the Holtec International HI-STORM 100 Cask System, as currently listed in § 72.214. The amendment consists of the changes in Amendment No. 15 previously described, as set forth in the revised certificate of compliance and technical specifications.

Amendment No. 15 to Certificate of Compliance No. 1014 for the Holtec International HI-STORM 100 Cask System was initiated by Holtec International and was not submitted in response to new NRC requirements, or an NRC request for amendment. Amendment No. 15 applies only to new casks fabricated and used under Amendment No. 15. These changes do not affect existing users of the Holtec International HI-STORM 100 Cask System, and previous amendments continue to be effective for existing users. While current users of this storage system may comply with the new requirements in Amendment No. 15, this would be a voluntary decision on the part of existing users.

For these reasons, Amendment No. 15 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 17

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.

Document ADAMS Accession No.

Submission of Holtec International HI-STORM 100 Cask System Certificate of Compliance No.

ML19092A192 (package) 1014, Amendment 15 Request, dated March 20, 2019 Submission of Response to the U.S. Nuclear Regulatory Commission Request for Supplemental Information for Amendment 15 to ML19277G818 (package)

Certificate of Compliance No. 1014 for Holtec International HI-STORM 100 Cask System, dated September 16, 2019 Submission of Response to the U.S. Nuclear Regulatory Commission for Request for Additional Information for Amendment 15 to ML20128J292 (package)

Certificate of Compliance No. 1014 for Holtec International HI-STORM 100 Cask System, dated April 28, 2020 Submission of Response to the U.S. Nuclear Regulatory Commission for Requests for Additional Information 3-1 and 3-6 for ML20136A475 (package)

Amendment 15 to Certificate of Compliance No. 1014 for Holtec International HI-STORM 100 Cask System, dated May 15, 2020 Submission of Response to the U.S. Nuclear Regulatory Commission for Request for Additional Information 8-1 for Amendment 15 to ML20164A294 (package)

Certificate of Compliance No. 1014 for Holtec International HI-STORM 100 Cask System, dated June 12, 2020 18

Submission of Response to the U.S. Nuclear Regulatory Commission for Request for Additional Information 4-9 for Amendment 15 to ML20174A397 (package)

Certificate of Compliance No. 1014 for Holtec International HI-STORM 100 Cask System, dated June 22, 2020 Submission of Response to the U.S. Nuclear Regulatory Commission for Requests for Additional Information 6-1, 6-2, 6-7, 6-8 and 11-1 for Amendment 15 to Certificate of ML20213C679 (package)

Compliance No. 1014 for Holtec International HI-STORM 100 Cask System, dated July 30, 2020 Submission of Response to the U.S. Nuclear Regulatory Commission for Request for Additional Information for Amendment 15 to ML20229A001 (package)

Certificate of Compliance No. 1014 for Holtec International HI-STORM 100 Cask System, dated August 14, 2020 Submission of Supplement to Holtec Internationals Request for Amendment 15 to Certificate of Compliance No. 1014 for Holtec ML20245E462 (package)

International HI-STORM 100 Cask System, dated September 1, 2020 Submission of Supplement to Holtec Internationals Request for Amendment 15 to Certificate of Compliance No. 1014 for Holtec ML20269A425 (package)

International HI-STORM 100 Cask System, dated September 25, 2020 User Need Memorandum for Rulemaking for the Holtec International HI-STORM 100 Cask ML20295A413 System, Amendment No. 15 to Certificate of Compliance No. 1014, dated January 27, 2021 Proposed CoC 1014 Amendment No. 15 CoC ML20295A415 Proposed CoC 1014 Amendment No. 15 ML20295A416 Appendix A Proposed CoC 1014 Amendment No. 15 ML20295A417 Appendix B Proposed CoC 1014 Amendment No. 15 ML20295A418 Appendix C Proposed CoC 1014 Amendment No. 15 ML20295A419 Appendix D 19

Proposed CoC 1014 Amendment No. 15 ML20295A420 Appendix A-100U Proposed CoC 1014 Amendment No. 15 ML20295A421 Appendix B-100U Preliminary CoC 1014 Amendment No. 15 ML20295A422 Safety Evaluation Report The NRC may post materials related to this document, including public comments, on the Federal Rulemaking website at http://www.regulations.gov under Docket ID NRC-2020-0257.

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:

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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.

2. In § 72.214, revise Certificate of Compliance 1014 to read as follows:

§ 72.214 List of approved spent fuel storage casks.

Certificate Number: 1014.

Initial Certificate Effective Date: May 31, 2000.

Amendment Number 1 Effective Date: July 15, 2002.

Amendment Number 2 Effective Date: June 7, 2005.

Amendment Number 3 Effective Date: May 29, 2007.

Amendment Number 4 Effective Date: January 8, 2008.

Amendment Number 5 Effective Date: July 14, 2008.

Amendment Number 6 Effective Date: August 17, 2009.

Amendment Number 7 Effective Date: December 28, 2009.

Amendment Number 8 Effective Date: May 2, 2012, as corrected on November 16, 2012 (ADAMS Accession No. ML12213A170); superseded by Amendment Number 8, Revision 1, Effective Date: February 16, 2016.

Amendment Number 8, Revision 1, Effective Date: February 16, 2016.

Amendment Number 9 Effective Date: March 11, 2014, superseded by Amendment Number 9, Revision 1, on March 21, 2016.

Amendment Number 9, Revision 1, Effective Date: March 21, 2016, as corrected 21

(ADAMS Accession No. ML17236A451).

Amendment Number 10 Effective Date: May 31, 2016, as corrected (ADAMS Accession No. ML17236A452).

Amendment Number 11 Effective Date: February 25, 2019, as corrected (ADAMS Accession No. ML19343B024).

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).

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).

Amendment Number 14 Effective Date: December 17, 2019, as corrected (ADAMS Accession No. ML19343B287).

Amendment Number 15 Effective Date: [INSERT DATE 75 DAYS AFTER PUBLICATION IN THE FEDERAL REGISTER].

Safety Analysis Report (SAR) Submitted by: Holtec International.

SAR

Title:

Final Safety Analysis Report for the HI-STORM 100 Cask System.

Docket Number: 72-1014.

Certificate Expiration Date: May 31, 2020.

Model Number: HI-STORM 100.

Dated this March 16, 2021.

For the Nuclear Regulatory Commission.

/RA/

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Margaret M. Doane, Executive Director for Operations.

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