ML23277A003

Issuance of Amendments Regarding Adoption of TSTF-370

ML23277A003
Person / Time
Site:	Byron, Braidwood
Issue date:	12/11/2023
From:	Joel Wiebe Plant Licensing Branch III
To:	Rhoades D Exelon Generation Co
Wiebe J
References
EPID L-2023-LLA-0087
Download: ML23277A003 (25)

Text

December 11, 2023

Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 234, 234, 234, AND 234 REGARDING ADOPTION OF TSTF-370 (EPID L-2023-LLA-0087)

Dear Mr. Rhoades:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 234 to Renewed Facility Operating License No. NPF-72 and Amendment No. 234 to Renewed Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2, respectively, and Amendment No. 234 to Renewed Facility Operating License No. NPF-37 and Amendment No. 234 to Renewed Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively. The amendments are in response to your application dated June 7, 2023.

The amendments extend the completion time from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Condition B of Technical Specification 3.5.1, Accumulators. The changes are consistent with NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-370, Increase Accumulator Completion Time From 1 Hour to 24 Hours.

D. Rhoades

Copies of the related Safety Evaluation and Notices and Environmental Findings are also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.

Sincerely,

/RA/

Joel S. Wiebe, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. STN 50-456, STN 50-457, STN 50-454, and STN 50-455

Enclosures:

1. Amendment No. 234 to NPF-72

2. Amendment No. 234 to NPF-77

3. Amendment No. 234 to NPF-37

4. Amendment No. 234 to NPF-66

5. Safety Evaluation

6. Notices and Environmental Findings

cc: Listserv

CONSTELLATION ENERGY GENERATION, LLC

DOCKET NO. STN 50-456

BRAIDWOOD STATION, UNIT 1

AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE

Amendment No. 234 Renewed License No. NPF-72

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

A. The application for amendment by Constellation Energy Generation, LLC (the licensee) dated June 7, 2023, 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. Accordingly, the renewed license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-72 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendix A as revised through Amendment No. 234 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications

Date of Issuance: December 11, 2023

CONSTELLATION ENERGY GENERATION, LLC

DOCKET NO. STN 50-457

BRAIDWOOD STATION, UNIT 2

AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE

Amendment No. 234 Renewed License No. NPF-77

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

A. The application for amendment by Constellation Energy Generation, LLC (the licensee) dated June 7, 2023, 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 2

2. Accordingly, the renewed license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-77 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendix A as revised through Amendment No. 234 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications

Date of Issuance: December 11, 2023

ATTACHMENT TO LICENSE AMENDMENT NOS. 234 AND 234

RENEWED FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77

BRAIDWOOD STATION, UNITS 1 AND 2

DOCKET NOS. STN 50-456 AND STN 50-457

Replace the following pages of the Renewed Facility Operating Licenses and 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 Licenses

REMOVE INSERT

License NPF-72 License NPF-72 License NPF-77 License NPF-77 Technical Specifications

REMOVE INSERT 3.5.1 - 1 3.5.1 - 1

(2) Constellation Energy Generation, LLC, 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, as described in the Final Safety Analysis Report, as supplemented and amended;

(3) Constellation Energy Generation, LLC, 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 monitoring equipment calibration, and as fission detectors in amounts as required;

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

(5) Constellation Energy Generation, LLC, 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

The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications

The Technical Specifications contained in Appendix A as revised through Amendment No. 234 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Renewed License No. NPF-72 Amendment No. 234

(2) Constellation Energy Generation, LLC, 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, as described in the Final Safety Analysis Report, as supplemented and amended;

(3) Constellation Energy Generation, LLC, 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 monitoring equipment calibration, and as fission detectors in amounts as required;

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

(5) Constellation Energy Generation, LLC, 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. The 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

The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications

The Technical Specifications contained in Appendix A as revised through Amendment No. 234 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Renewed License No. NPF-77 Amendment No. 234

Accumulators 3.5.1

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators

LCO 3.5.1 Four ECCS accumulators shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with Reactor Coolant System (RCS) pressure

> 1000 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. One accumulator A.1 Restore boron 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable due to concentration to boron concentration within limits.

not within limits.

B. One accumulator B.1 Restore accumulator inoperable for reasons to OPERABLE status. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> other than Condition A.

C. Required Action andC.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A AND or B not met.

C.2 Reduce RCS pressure 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 1000 psig.

D. Two or more D.1 Enter LCO 3.0.3. Immediately accumulators inoperable.

BRAIDWOOD UNITS 1 & 2 3.5.1 1 Amendment 2348 CONSTELLATION ENERGY GENERATION, LLC

DOCKET NO. STN 50-454

BYRON STATION, UNIT NO. 1

AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE

Amendment No. 234 Renewed License No. NPF-37

1. The U.S. Nuclear Regulatory Commission (the Commission) has found th at:

A. The application for amendment by Constellation Energy Generation, LLC (the licensee) dated June 7, 2023, complies with the standards a nd requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission s 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 th e Commissions regulations;

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

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

Enclosure 3

- 2 -

2. Accordingly, the renewed license is amended by changes to the Technical Specificat ions as indicated in the attachment to this licen se amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-37 is hereby amended to read as follo ws:

(2) Technical Specifications

The Technical Specifications contained in Appendix A as revised through Amendment No. 234 and the Environmental Protection Plan contained in Appendix B, both of which are attached her eto, are hereby incorporated into this renewed license. The licen see shall operate the facility in accordance with the Technical Specifications and the Environmental Protectio n Plan.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications

Date of Issuance: December 11, 2023 CONSTELLATION ENERGY GENERATION, LLC

DOCKET NO. STN 50-455

BYRON STATION, UNIT NO. 2

AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE

Amendment No. 234 Renewed License No. NPF-66

1. The U.S. Nuclear Regulatory Commission (the Commission) has found th at:

A. The application for amendment by Constellation Energy Generation, LLC (the licensee) dated June 7, 2023, complies with the standards a nd requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission s 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 th e Commissions regulations;

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

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

Enclosure 4

- 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-66 is hereby amended to read as follo ws:

(2) Technical Specifications

The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amend ment No. 234, and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renew ed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications

Date of Issuance: December 11, 2023 ATTACHMENT TO LICENSE AMENDMENT NOS. 234 AND 234

RENEWED FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66

BYRON STATION, UNIT NOS. 1 AND 2

DOCKET NOS. STN 50-454 AND STN 50-455

Replace the following pages of the Renewed Facility Operating Licenses and 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 Licenses

REMOVE INSERT

License NPF-37 License NPF-37 License NPF-66 License NPF-66 Technical Specifications

REMOVE INSERT 3.5.1 - 1 3.5.1 - 1

- 3 -

(2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordan ce with the limitations for storage and amounts required for reactor oper ation, as described in the Updated Final Safety Analysis Report, as supplemented and amended;

(3) 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 nucle ar material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibrati on, and as fission detectors in amounts as requir ed;

(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or spec ial nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparat us or components; and

(5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as m ay be produced by the operation of the facility.

C. The renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set fort h 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 th e additional conditions specified or incorporated below:

(3) Maximum Power Level

The licensee is authorized to operate the facility at reactor co re power levels not in excess of 3645 megawatts thermal (100 percen t rated power) in accordance with the condit ions specified herein.

(2) Technical Specifications

The Technical Specifications contained in Appendix A as revised through Amendment No. 234 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Enviro nmental Protection Plan.

(3) Deleted.

(4) Deleted.

Renewed License No. NPF-37 Amendment No. 234

- 3 -

(2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordan ce with the limitations for storage and amounts required for reactor oper ation, as described in the Updated Final Safety Analysis Report, as supplemented and amended;

(3) 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 nucle ar material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibrati on, and as fission detectors in amounts as requir ed;

(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or spec ial nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparat us or components; and

(5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as m ay be produced by the operation of the facility.

C. The renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set fort h 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 th e additional conditions specified or incorporated below:

(3) Maximum Power Level

The licensee is authorized to operate the facility at reactor co re power levels not in excess of 3645 megawatts thermal (100 percen t rated power) in accordance with the condit ions specified herein.

(2) Technical Specifications

The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 23 4, and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Enviro nmental Protection Plan.

(3) Deleted.

Renewed License No. NPF-66 Amendment No. 234 Accumulators 3.5.1

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators

LCO 3.5.1 Four ECCS accumulators shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with Reactor Coolant System (RCS) pressure

> 1000 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

A. One accumulator A.1 Restore boron 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable due to concentration to boron concentration within limits.

not within limits.

B. One accumulator B.1 Restore accumulator inoperable for reasons to OPERABLE status. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> other than Condition A.

C. Required Action andC.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A AND or B not met.

C.2 Reduce RCS pressure 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 1000 psig.

D. Two or more D.1 Enter LCO 3.0.3. Immediately accumulators inoperable.

BYRON UNITS 1 & 2 3.5.1 1 Amendment 23406 December 11, 2023

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 234, 234, 234, AND 234 TO RENEWED FACI LITY OPERATING LICENSE NOS. NFP-72, NFP-77, NFP-37, AND NFP-66 CONSTELLATION ENERGY GENERATION, LLC BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-456, 50-457, 50-454, AND 50-455

Application (i.e., initial and supplements) Safety Evaluation Date June 7, 2023 (Agencywide Documents Access December 11, 2023 and Management System (ADAMS) Accession Principal Contributors to Safety Evaluation No. ML23158A296) Matthew Hamm

1.0 INTRODUCTION

Constellation Energy Generation, LLC (the licensee) requested amendments to the technical specifications (TSs) for Braidwood Station, Units 1 and 2 (Braidwood), and Byron Station, Unit Nos. 1 and 2 (Byron). Specifically, the completion time (CT) of Required Action B.1 in TS 3.5.1, Accumulators, would be extended from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The licensee stated that the proposed changes are consistent with Technical Specifications Task Force Traveler (TSTF)-

370, Increase Accumulator Completion Tim e From 1 Hour to 24 Hours Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML003771365 and ML003771348. The U.S. Nuclear Regulatory Commission (NRC, the Commission) staff published a model safety evaluation (SE) relating to this technical specification (TS) improvement for comment in the Federal Register (FR) on July 15, 2002 (67 FR 46542), and published a model application on March 12, 2003 (68 FR 11880), as part of the Consolidated Line Item Improvement Process (CLIIP).

Accumulators are part of the emergency core cooling system of Westinghouse nuclear steam supply system (NSSS) plants. Their purpose is to supply water to the reactor vessel during the blowdown phase of a loss-of-coolant accident. The accumulators are large volume tanks filled with borated water and pressurized with nitrogen. The cover-pressure is less than that of the reactor coolant system (RCS) so that following an accident, when the RCS pressure decreases below tank pressure, the accumulators inject their borated water into the RCS cold legs.

Enclosure 5

2.0 REGULATORY EVALUATION

2.1 Applicable Regulations

Title 10 of the Code of Federal Regulations (10 CFR), section 50.36(b) states that TSs 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 categories of items required to be in the TSs are provided in 10 CFR 50.36(c). As required by 10 CFR 50.36(c)(2), the TSs will include limiting conditions for operation (LCOs), which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the LCO can be met.

2.2 Applicable Regulatory Guidance

The NRC staffs guidance for the review of TSs is in chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition, dated March 2010 (ML100351425).

As described therein, as part of the regulatory standardization effort, the NRC staff has prepared standard technical specifications (STS) for each of the LWR nuclear designs, including the Westinghouse NSSS plants. Accordingly, th e staffs review includes consideration of whether the proposed changes are consistent with the applicable STS, NUREG-1431, 1 as modified by NRC-approved travelers. NRC Regulatory Issue Summary 2000-006, Consolidated Line Item Improvement Process for Adopting Standard Technical Specifications Changes for Power Reactors, dated March 20, 2000 (ML003693442), describes the process available to licensees for proposed adoption of generic changes to STS.

2.3 Applicable Changes to STS

Topical Report (TR) WCAP-15049, Risk-Informed Evaluation of an Extension to Accumulator Completion Times, dated August 1998 (ML20237D093; non-publicly available), was approved by the NRC by letter dated February 19, 1999 (ML20196L106; non-publicly available). TR WCAP-15049 evaluates the risk associated with extending the accumulator CT from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for reasons other than boron concentration being out of specification. In its letter dated February 19, 1999, the NRC staff stated that it will not repeat its review of the matters described in TR WCAP-15049 when the report appears as a reference in license applications, except to ensure that the material presented applies to the specific plant involved.

Wolf Creek Generating Station was the first plant to receive plant-specific approval for changes to the accumulator CT on April 27, 1999 (ML20206D447).

TSTF-370 was transmitted to the NRC staff by letter dated November 22, 2000, as a means to incorporate the TR WCAP-15049 evaluations into the STS for Westinghouse NSSS plants. After TSTF-370 was approved in 2003, the related changes were incorporated into Revision 3.0 of

1 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, Westinghouse Plants, NUREG-1431, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, dated September 2021 (ML21259A155 and ML21259A159, respectively).

NUREG-1431, the STS for Westinghouse NSSS pl ants. Subsequent revisions 4.0 and 5.0 have maintained the TSTF-370-related changes.

2.4 Proposed Braidwood and Byron TS Changes

The proposed changes would revise the CT from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Condition B of the Braidwood and Byron TS 3.5.1. Condition B currently specifies a CT of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore the RCS accumulator to operable status when declared inoperable due to any reason except not being within the required boron concentration limits.

3.0 TECHNICAL EVALUATION

The NRC staff reviewed TSTF-370, the staffs model SE related to TSTF-370, the staffs model application related to TSTF-370 and the licensees plant-specific request to adopt the TSTF-370-related changes.

In section 2.1, Applicability of Published Safety Evaluation, of attachment 1 to the license amendment request, the licensee stated:

Constellation Energy Generation, LLC (CEG) has reviewed the safety evaluation published on July 15, 2002 (67 FR 46542) as part of the CLIIP. This verification included a review of the NRCs evaluation as well as the supporting information provided to support TSTF-370 (i.e., WCAP-15049-A, Risk-Informed Evaluation of an Extension to Accumulator Completion Times, dated May 18,1999). CEG has assessed Braidwood and Byron Probabilistic Risk Assessment (PRA) model differences from the PRA models in WCAP-15049-A and concluded that the differences do not impact the conclusions of WCAP-15049-A. The justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC are applicable to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, and justify these amendments for the incorporation of the changes into the Braidwood and Byron Technical Specifications.

Section 3.0 of the NRC staffs model SE for TSTF-370-related changes states, in part: The analysis and acceptance provided in this [safety evaluation], as demonstrated by WCAP-15049, covers all Westinghouse NSSS plants regardless of plant vintage and number of loops.

The NRC staff determined that the proposed TSTF-370-related changes are justified by the staffs model SE since Braidwood and Byron are Westinghouse NSSS plants considered in TR WCAP-15049. The staff also determined that the requirements of 10 CFR 50.36 will continue to be met because the TS will continue to be derived from the licensees analyses and evaluation, per 10 CFR 50.36(b), and the TS will continue to require the licensee to shut down the reactor or follow acceptable remedial actions when the LCO is not met, per 10 CFR 50.36(c)(2).

Therefore, the staff concludes that the proposed changes are acceptable.

4.0 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.

NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NOS. 234, 234, 234, AND 234 TO RENEWED FACILITY OPERATING LICENSE NOS. NFP-72, NFP-77, NFP-37, AND NFP-66 CONSTELLATION ENERGY GENERATION, LLC BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-456, 50-457, 50-454, AND 50-455

Application (i.e., initial and supplements) Safety Evaluation Date June 7, 2023 (Agencywide Documents December 11, 2023 Access and Management System Principal Contributors to Safety Evaluation (ADAMS) Accession No. ML23158A296) Matthew Hamm

1.0 INTRODUCTION

Constellation Energy Generation, LLC (the licensee) requested amendments to the technical specifications (TSs) for Braidwood Station, Units 1 and 2 (Braidwood), and Byron Station, Unit Nos. 1 and 2 (Byron). Specifically, the completion time of Required Action B.1 in TS 3.5.1, Accumulators, would be extended from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The licensee stated that the proposed changes are consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-370, Increase Accumulator Completion Time from 1 Hour to 24 Hours Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML003771365 and ML003771348. The U.S. Nuclear Regulatory Commission (NRC, the Commission) staff published a model safety evaluation (SE) relating to this TS improvement for comment in the Federal Register (FR) on July 15, 2002 (67 FR 46542), and published a model application on March 12, 2003 (68 FR 11880), as part of the Consolidated Line Item Improvement Process (CLIIP).

2.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Illinois State official was notified of the proposed issuance of the amendments on October 3, 2023. The State official had no comments.

3.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with respect to the installation or use of facility components located within the restricted area as defined in Title 10 of the Code of Federal Regulations (10 CFR), part 20. The NRC staff has determined that the amendments involve no significant increase 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, and there has been no public comment on such finding published in the Federal Register on October 3, 2023 (88 FR 68162).

Enclosure 6

Accordingly, the amendments meet the eligibility cr iteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). 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.

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