ML24177A269

Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program

ML24177A269
Person / Time
Site:	Comanche Peak
Issue date:	08/07/2024
From:	Samson Lee Plant Licensing Branch IV
To:	Peters K Vistra Operations Company
Lee, Samson
References
EPID: L-2024-LLA-0023 TSTF-591
Download: ML24177A269 (1)

Text

August 7, 2024

Ken J. Peters Executive Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Vistra Operations Company LLC Comanche Peak Nuclear Power Plant 6322 N FM 56 P.O. Box 1002 Glen Rose, TX 76043

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -

ISSUANCE OF AMENDMENT NOS. 188 AND 188, RESPECTIVELY, RE:

REVISION TO TECHNICA L SPECIFICATIONS TO ADOPT TSTF-591, REVISE RISK INFORMED COMPLETION TIME (RICT) PROGRAM (EPID L-2024-LLA-0023)

Dear Ken Peters:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 188 to Renewed Facility Operating License No. NPF-87 and Amendment No. 188 to Renewed Facility Operating License No. NPF-89 for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated February 28, 2024, as supplemented by letter dated April 1, 2024.

The amendments revise TSs to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-591, Revise Risk Informed Completion Time (RICT) Program.

K. Peters

A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.

Sincerely,

/RA/

Samson S. Lee, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-445 and 50-446

Enclosures:

1. Amendment No. 188 to NPF-87

2. Amendment No. 188 to NPF-89

3. Safety Evaluation

cc: Listserv

COMANCHE PEAK POWER COMPANY LLC

AND VISTRA OPERATIONS COMPANY LLC

COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NO. 1

DOCKET NO. 50-445

AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE

Amendment No. 188 Renewed License No. NPF-87

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Vistra Operations Company LLC (Vistra OpCo) dated February 28, 2024, as supplemented by letter dated April 1, 2024, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I;

B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;

C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations;

D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

Enclosure 1

- 2 -

2. Accordingly, the license is amended by changes to the Technical Specif ications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-87 is hereby amended to read as follo ws:

(2) Technical Specifications and Environmental Protection Plan

The Technical Specifications contained in Appendix A as revised through Amendment No. 188 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this renewed license. Vistra OpCo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. The license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Jennivine K. Rankin, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications

Date of Issuance: August 7, 2024 COMANCHE PEAK POWER COMPANY LLC

AND VISTRA OPERATIONS COMPANY LLC

COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NO. 2

DOCKET NO. 50-446

AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE

Amendment No. 188 Renewed License No. NPF-89

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Vistra Operations Company LLC (Vistra OpCo) dated February 28, 2024, as supplemented by letter dated April 1, 2024, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I;

B. The facility will operate in conformity with the application, the provision s of the Act, and the rules and regulations of the Commission;

C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the healt h and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations;

D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

Enclosure 2

- 2 -

2. Accordingly, the license is amended by changes to the Technical Specif ications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-89 is hereby amended to read as follo ws:

(2) Technical Specifications and Environmental Protection Plan

The Technical Specifications contained in Appendix A as revised through Amendment No. 188 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this renewed license. Vistra OpCo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Jennivine K. Rankin, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications

Date of Issuance: August 7, 2024 ATTACHMENT TO LICENSE AMENDMENT NO. 188

TO RENEWED FACILITY OPERATING LICENSE NO. NPF-87

AND AMENDMENT NO. 188

TO RENEWED FACILITY OPERATING LICENSE NO. NPF-89

COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2

DOCKET NOS. 50-445 AND 50-446

Replace the following pages of Renewed Facility Operating License Nos. NPF-87 and NPF-89, and the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Renewed Facility Operating License No. NPF-87

REMOVE INSERT 3 3

Renewed Facility Operating License No. NPF-89

REMOVE INSERT 3 3

Technical Specifications

REMOVE INSERT 5.5-19 5.5-19 5.6-6 5.6-6

(3) Vistra OpCo, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended;

(4) Vistra OpCo, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitori ng equipment calibration, and as fission detectors in amounts as required;

(5) Vistra OpCo, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and

(6) Vistra OpCo, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level

Vistra OpCo is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 13 and 3612 megawatts thermal starting with Cycle 14 in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan

The Technical Specifications contained in Appendix A as revised through Amendment No. 188 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this renewed license. Vistra OpCo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Antitrust Conditions

DELETED

(4) License Transfer

The CP PowerCo Decommissioning Master Trust Agreement for the facility at the time the license transfers are effected and thereafter, is subject to the following:

Unit 1 Amendment No. 188

(2) CP PowerCo, pursuant to 10 CFR Part 50, to possess the facility at the designated location in Somervell County, Texas in accordance with the procedures and limitations set forth in this renewed license;

(3) Vistra OpCo, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended;

(4) Vistra OpCo, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitori ng equipment calibration, and as fission detectors in amounts as required;

(5) Vistra OpCo, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and

(6) Vistra OpCo, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level

Vistra OpCo is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 11 and 3612 megawatts thermal starting with Cycle 12 in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan

The Technical Specifications contained in Appendix A as revised through Amendment No. 188 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this renewed license. Vistra OpCo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Antitrust Conditions

DELETED

(4) License Transfer

Unit 2 Amendment No. 188 Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.23 Risk Informed Completion Time Program (continued)

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COMANCHE PEAK - UNITS 1 AND 2 5.5-19Amendment No. 183 Reporting Requirements 5.6

5.6 Reporting Requirements

5.6.9 Steam Generator Tube Inspection Report (continued)

d. An analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection (the forward-looking tube integrity assessment) relative to the applicable performance criteria, including the analysis methodology, inputs, and results;

e. The number and percentage of tubes plugged to date, and the effective plugging percentage in each SG;

f. The results of any SG secondary side inspections;

g. For Unit 2, the primary to secondary leakage rate observed in each SG (if it is not practical to assign the leakage to an individual SG, the entire primary to secondary leakage should be conservatively assumed to be from one SG) during the cycle preceding the inspection which is the subject of the report;

h. For Unit 2, the calculated accident induced leakage rate from the portion of the tubes below 14.01 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calculated accident induced leakage rate from the most limiting accident is less than 3.16 times the maximum operational primary to secondary leakage rate, the report should describe how it was determined; and

i. For Unit 2, the results of monitoring for tube axial displacement (slippage). If slippage is discovered, the implications of the discovery and corrective action shall be provided.

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COMANCHE PEAK - UNITS 1 AND 2 5.6-6Amendment No. 158, 182 

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

RELATED TO AMENDMENT NO. 188 TO

RENEWED FACILITY OPERATING LICENSE NO. NPF-87

AND AMENDMENT NO. 188 TO

RENEWED FACILITY OPERATING LICENSE NO. NPF-89

COMANCHE PEAK POWER COMPANY LLC

AND VISTRA OPERATIONS COMPANY LLC

COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2

DOCKET NOS. 50-445 AND 50-446

1.0 INTRODUCTION

By letter dated February 28, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24059A390), as supplemented by letter dated April 1, 2024 (ML24092A236), Vistra Operations Company LLC (Vistra OpCo, the licensee) submitted a license amendment request (LAR) for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Comanche Peak), for approval to revise technical specifications (TSs) based on Technical Specifications Task Force (TSTF) Traveler TSTF-591, Revision 0, Revise Risk Informed Completion Time (RICT) Program (TSTF-591) (ML22081A224), and the associated U.S.

Nuclear Regulatory Commission (NRC or the Commission) staffs final safety evaluation (SE) of TSTF-591 (ML23262B230).

The proposed changes would revise TS 5.5.23, R isk Informed Completion Time Program, by referencing Regulatory Guide (RG) 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities, Revision 3, December 2020 (ML20238B871), instead of RG 1.200, Revision 2, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities, March 2009 (ML090410014). The proposed changes would also add a requirement in TS Section 5.6, Reporting Requirements, for the licensee to submit a report to the NRC before calculating a RICT using a newly developed method.

Description of RICT Program

The TS limiting conditions for operations (LCOs) are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO is not

Enclosure 3

met, the licensee must shut down the reactor or follow any remedial or required action (e.g.,

testing, maintenance, or repair activity) permitted by the TSs until the condition can be met. The remedial actions (i.e., ACTIONS) associated with an LCO contain Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are required action(s) and completion times (CTs). The CTs are referred to as the front stops in the context of this SE. For certain Conditions, the TS require exiting the Mode of Applicability of an LCO (i.e., shutdown the reactor).

Topical Report (TR) Nuclear Energy Institute (NEI) 06-09, Risk Informed Technical Specifications Initiative 4b: Risk Managed Technical Specifications (RMTS), Revision 0-A (NEI 06-09-A) (Package ML122860402), provides a methodology for extending existing CTs and thereby delay exiting the operational mode of applicability or taking Required Actions if risk is assessed and managed within the limits and programmatic requirements established by a RICT Program.

1.1 Proposed TS Changes to Adopt TSTF-591

TS 5.5.23, Risk Informed Completion Time Program

TS 5.5.23, which describes the RICT program, would be revised. Existing paragraph e would be replaced with the paragraph e below. Paragraphs f and g would be added.

e. A RICT calculation must include the following hazard groups: Internal flood and internal events PRA [probabilistic risk assessment] model, internal fire PRA model, seismic penalty factor, and extreme winds and tornado penalty factor. Changes to these means of assessing the hazard groups require prior NRC approval.

f. The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities.

g. A report shall be submitted in accordance with Specification 5.6.10 before a newly developed method is used to calculate a RICT.

TS 5.6.10, Risk Informed Completion Time Program Upgrade Report

A new specification, TS 5.6.10, would be added as follows:

Risk Informed Completion Time (RICT) Program Upgrade Report

A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:

a. The PRA models upgraded to include newly developed methods;

b. A description of the acceptability of the newly developed methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, Newly Developed Method Requirements and Peer Review;

c. Any open findings from the peer-review of the implementation of the newly developed methods and how those findings were dispositioned; and

d. All changes to key assumptions related to newly developed methods or their implementation.

1.2 Additional Proposed TS Changes

In addition to the changes proposed consistent with TSTF-591 discussed in section 1.1, the licensee proposed the variations below.

1.2.1 Editorial Variations

The licensee noted that Comanche Peak TSs have different numbering than standard technical specifications (STSs).

1.2.2 Other Variations

The licensee noted that Comanche Peak RICT Program, paragraph e, is different from TSTF-505, Revision 2 wording used as the starting point in TSTF-591. The licensee stated these differences in paragraph e do not affect the applicability of the proposed change.

2.0 REGULATORY EVALUATION

2.1 Applicable Regulatory Requirements and Guidance

Title 10 of the Code of Federal Regulations (10 CFR) 50.36(b) requires that:

Each license authorizing operation of a utilization facility will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to [10 CFR] 50.34 [Contents of applications; technical information]. The Commission may include such additional technical specifications as the Commission finds appropriate.

The categories of items required to be in the TSs are listed in 10 CFR 50.36(c).

The provisions of 10 CFR 50.36(c)(5), state, in part, that [a]dministrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.

NRC RGs provide one way to ensure that the regulations continue to be met. The NRC staff considered during its review of the proposed changes, along with industry guidance endorsed by the NRC, the guidance in RG 1.200, Revision 3, Acceptability of Probabilistic Risk Assessment Results for Risk-Inform ed Activities, December 2020.

NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP):

Chapter 19, Section 19.2, Review of Risk Information Used to Support Permanent Plant-Specific Changes to the Licensing Basis: General Guidance, June 2007 (ML071700658).

Chapter 16, Section 16.0, Technical Specifications, Revision 3, March 2010 (ML100351425). The NRC staffs review includes consideration of whether the proposed changes are consistent with the NRC NURE G-1431, Standard Technical Specifications, Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, September 2021 (ML21259A155 and ML21259A159, respectively).

Chapter 16, Section 16.1, Risk-Informed Decision Making: Technical Specifications, March 2007 (ML070380228).

NEI 06-09-A, Revision 0, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS) Guidelines, provides guidance for risk-informed TS. The NRC staff issued a final SE approving NEI 06-09 on May 17, 2007 (ML071200238).

NEI 17-07, Revision 2, Performance of PRA Peer Reviews Using the ASME/ANS PRA Standard, provides guidance material for conducting and documenting a PRA peer review using the American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS)

PRA Standard, issued August 2019 (ML19231A182).

Pressurized Water Reactor Owners Group (PWROG) TR PWROG-19027-NP, Revision 2, Newly Developed Method Requirements and Peer Review, establishes the definitions, processes, and technical requirements necessary to implement newly developed methods, issued July 2020 (ML20213C660). RG 1.200, Revision 3, endorsed specified portions of PWROG-19027-NP.

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes to Adopt TSTF-591

The NRC staff compared the licensees proposed TS changes in section 1.1 of this SE against the changes approved in the SE for TSTF-591. The NRC staff finds that the licensees proposed changes to the Comanche Peak TSs in section 1.1 of this SE are consistent with those found acceptable in TSTF-591.

In the final SE for TSTF-591, the NRC staff concluded that the TSTF-591 proposed changes to STS 5.5.20, Risk Informed Completion Time Program, and the proposed addition of STS 5.6.8, Risk Informed Completion Time (RICT) Program Upgrade Report, were acceptable.

These modifications were acceptable because, as discussed in that SE, they continued to ensure the PRA models used to calculate a RICT are maintained and upgraded by the licensees appropriate use of endorsed guidance (i.e., the ASME/ANS PRA Standard requirements, and specific industry guidance th at the NRC staff has determined are sufficient for determining the acceptability of PRA models and newly developed methods for use in the RICT program). Furthermore, as discussed in the SE for TSTF-591, the addition of reporting requirements does not preclude any NRC staff oversight of PRA changes performed to ensure the PRA model(s) continue to be maintained and upgraded consistent with RG 1.200,

Revision 3. Therefore, the NRC staff found that the proposed changes to the RICT Program and addition of the RICT Program Upgrade Report requirements were acceptable because they continued to meet the requirements of 10 CFR 50.36(c)(5) by providing administrative controls necessary to assure operation of the facility in a safe manner. For these same reasons, the NRC staff concludes that the corresponding pro posed changes to the Comanche Peak TSs in section 1.1 of this SE continue to meet the requirements of 10 CFR 50.36(c)(5).

3.2 Additional Proposed Changes

In addition to the changes proposed consistent with TSTF-591 discussed in section 1.1, the licensee proposed variations discussed in section 1.2, which are discussed below.

3.2.1 Variations That Do Not Affect the Applicability of TSTF-591

The LAR noted that the Comanche Peak TSs have different numbering than STS. The NRC staff finds that the different TS numbering changes proposed in the LAR are acceptable because they do not alter TS requirements.

3.2.2 Variations That Do Affect the Applicability of TSTF-591

The LAR noted that Comanche Peak RICT Program, paragraph e, is different from TSTF-505, Revision 2 wording used as the starting point in TSTF-591. The NRC staff finds that these differences are acceptable and do not affect the applicability of the changes proposed to adopt TSTF-591.

3.3 TS Change Consistency

The NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with chapter 16.0 of the SRP and are therefore acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Texas State official was notified of the proposed issuance of the amendments on June 17, 2024. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant incr ease in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration published in the Federal Register on May 14, 2024 (89 FR 42000), and there has been no public comment on such finding. The amendment also relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Andrea Russell, NRR

Date: August 7, 2024

ML24177A269 *concurrence via email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA* NRR/DSS/STSB/BC* OGC*

NAME SLee PBlechman SMehta IMurphy DATE 6/25/2024 6/27/2024 6/13/2024 7/9/2024 OFFICE NRR/DORL/LPL4/BC* NRR/DORL/LPL4/PM*

NAME JRankin SLee DATE 8/7/2024 8/7/2024