Voglio sapere a riguardo di…

54342

Federal Register / Vol. 86, No. 188 / Friday, October 1, 2021 / Rules and Regulations
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-andcomment process. For example, a substantive response is required when:
a The comment causes the NRC to reevaluate or reconsider its position or conduct additional analysis;
b The comment raises an issue serious enough to warrant a substantive response to clarify or complete the record; or c The comment raises a relevant issue that was not previously addressed or considered by the NRC.
2 The comment proposes a change or an addition to the rule, and it is apparent that the rule would be ineffective or unacceptable without incorporation of the change or addition.
3 The comment causes the NRC to make a change other than editorial to the rule, certificate of compliance, or technical specifications.
III. Background Section 218a of the Nuclear Waste Policy Act of 1982, as amended, requires that the Secretary of the Department of Energy shall establish a demonstration program, in cooperation with the private sector, for the dry storage of spent nuclear fuel at civilian nuclear power reactor sites, with the objective of establishing one or more technologies that the Nuclear Regulatory Commission may, by rule, approve for use at the sites of civilian nuclear power reactors without, to the maximum extent practicable, the need for additional site-specific approvals by the Commission. Section 133 of the Nuclear Waste Policy Act states, in part, that the Commission shall, by rule, establish procedures for the licensing of any technology approved by the Commission under Section 219a sic:
218a for use at the site of any civilian nuclear power reactor.
To implement this mandate, the Commission approved dry storage of spent nuclear fuel in NRC-approved casks under a general license by publishing a final rule that added a new
VerDate Sep<11>2014

16:40 Sep 30, 2021

Jkt 256001

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 September 3, 1999 64 FR
48259 that approved the HISTAR 100
Cask System design and added it to the list of NRC-approved cask designs in 72.214 as Certificate of Compliance No. 1008.
IV. Discussion of Changes On December 7, 2018, Holtec International submitted a request to the NRC to renew, for an additional 40
years, the initial certificate and Amendment Nos. 1, 2, and 3 of Certificate of Compliance No. 1008 for the HISTAR 100 Cask System. Holtec International supplemented its request on June 28, 2019, October 10, 2019, December 12, 2019, June 1, 2020, June 11, 2020, November 13, 2020, and November 24, 2020.
The renewal of the initial certificate and Amendment Nos. 1, 2, and 3 were conducted in accordance with the renewal provisions in 72.240. This section of the NRC spent fuel storage regulations authorizes NRC staff to include any additional certificate conditions it deems necessary to ensure the safe operation of the cask during the certificates renewal period. The NRC
included three additional conditions to the renewal of the initial certificate of compliance and Amendment Nos. 1, 2, and 3:
The submittal of an updated final safety analysis report UFSAR to address aging management activities resulting from the renewal of the certificate of compliance. This condition ensures that the UFSAR changes are made in a timely fashion to enable general licensees using the storage system during the period of extended operation to develop and implement necessary procedures.
The requirement that general licensees initiating or using spent fuel dry storage operations with the HI
STAR 100 Cask System ensure that their evaluations are included in the reports required by 72.212, Conditions of general license issued under 72.210.
These reports will include appropriate considerations for the period of extended operation, a review of the UFSAR changes resulting from the certificate of compliance renewal, and a review of the NRC safety evaluation
PO 00000

Frm 00004

Fmt 4700

Sfmt 4700

report SER related to the certificate of compliance renewal.
The requirement that future amendments and revisions to this certificate of compliance include evaluations of the impacts to aging management activities to ensure that they remain adequate for any changes to the structures, systems, and components SSCs.
The NRC made one corresponding change to the technical specifications for the initial certificate of compliance and Amendment Nos. 1, 2, and 3 on the aging management program. The change added a new section, which ensures that general licensees using the storage system develop procedures to address aging management activities required in the period of extended operation.
As documented in the preliminary SER, the NRC performed a safety evaluation of the proposed certificate of compliance renewal request. The NRC
determined that this renewal does not change the cask design or fabrication requirements in the proposed certificate of compliance renewal request. The NRC determined that the design of the cask would continue to maintain confinement, shielding, and criticality control in the event of each evaluated accident condition. In addition, any resulting occupational exposure or offsite dose rates from the renewal of the initial certificate of compliance and Amendment Nos. 1, 2, and 3 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. In its SER for the renewal of the HISTAR 100 Cask System, the NRC
has determined that if the conditions specified in the certificate of compliance to implement these regulations are met, adequate protection of public health and safety will continue to be reasonably assured.
This direct final rule revises the HI
STAR 100 Cask System listing in 72.214 by renewing, for 40 more years, the initial certificate and Amendment Nos. 1, 2, and 3 of Certificate of Compliance No. 1008. The renewal consists of the changes previously described, as set forth in the renewed initial certificate and amendments and their revised technical specifications.
The revised technical specifications are identified in the SER.

E:FRFM01OCR1.SGM

01OCR1