ML25066A164
| ML25066A164 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 03/13/2025 |
| From: | Scott Wall NRC/NRR/DORL/LPL3 |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| EPID L-2024-LLA-0055 | |
| Download: ML25066A164 (1) | |
Text
March 13, 2025 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 - AUDIT
SUMMARY
FOR LICENSE AMENDMENT REQUEST REGARDING LICENSE AMENDMENT REQUEST REGARDING DELETION OF TECHNICAL SPECIFICATION 5.6.5.b.5 (EPID L-2024-LLA-0055)
Dear David Rhoades:
By letter dated April 25, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24116A112), Constellation Energy Generation, LLC (Constellation, the licensee), submitted a License Amendment Request (LAR) for Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2. Specifically, the proposed LAR would delete Technical Specification 5.6.5.b.5 associated with the anticipated transients without scram moderator temperature coefficient limit.
To support its review, by letter dated August 29, 2024 (ML24227A052), the U.S. Nuclear Regulatory Commission (NRC) staff notified the licensee that they would conduct a regulatory audit through an online portal (also known as electronic portal, ePortal, electronic reading room) established by the licensee. The regulatory audit summary is enclosed with this letter.
If you have any questions, please contact me at (301) 415-2855, or by email at Scott.Wall@nrc.gov.
Sincerely,
/RA/
Scott P. Wall, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456, and STN 50-457
Enclosure:
Regulatory Audit Summary cc: Listserv
Enclosure REGULATORY AUDIT
SUMMARY
REGARDING LICENSE AMENDMENT REQUEST TO DELETE TECHNICAL SPECIFICATION 5.6.5.B.5 BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 CONSTELLATION ENERGY GENERATION, LLC.
DOCKET NOS. STN 50-454, STN 50-455, STN 50-456, AND STN 50-457
1.0 BACKGROUND
By letter dated April 25, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24116A112), Constellation Energy Generation, LLC (Constellation, the licensee), submitted a License Amendment Request (LAR) for Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2. Specifically, the proposed LAR would delete Technical Specification 5.6.5.b.5 associated with the anticipated transients without scram moderator temperature coefficient limit.
The U. S. Nuclear Regulatory Commission (NRC) staff performed a preliminary review of the LAR and determined that a regulatory audit would assist in the timely completion of the review.
An audit plan was provided to the licensee on August 29, 2024 (ML24227A052), which provided the list of requested documents and other details pertaining to the audit. The purpose of the audit was to gain an understanding of the information needed to support the NRC staffs licensing decision regarding the LAR and to develop requests for additional information (RAIs),
if necessary. The information submitted in support of the LAR is under final review, and any additional information needed to support the LAR review will be formally requested by the NRC staff using the RAI process in accordance with Office of Nuclear Reactor Regulation (NRR)
Office Instruction LIC-101, Revision 6, License Amendment Review Procedures (ML19248C539).
The regulatory audit is a planned license or regulation-related activity that includes the examination and evaluation of primarily non-docketed information. The regulatory audit is conducted with the intent to gain understanding, to verify information, and/or to identify information, that will require docketing to support the basis of a licensing or regulatory decision.
Performing a regulatory audit of the licensees information is expected to assist the NRC staff in efficiently conducting its review or gain insights on the licensees processes or procedures.
Information that the NRC staff relies upon to make the safety determination must be submitted on the docket. However, the NRC staff may review supporting information retained as records under Title 10 of the Code of Federal Regulations (10 CFR) section 50.71, Maintenance of records, making of reports, and/or 10 CFR 54.37, Additional records and recordkeeping requirements, which, although not required to be submitted as part of the licensing action, would help the NRC staff better understand the licensees submitted information.
2.0 SCOPE By letter dated August 29, 2024, the NRC staff issued an audit plan. To support discussions, the NRC staff provided audit questions with items for CEG to clarify. CEG posted answers to these questions to the online portal. All audit questions were discussed. Technical discussions were focused on anticipated transients without scram (ATWS) events.
3.0 AUDIT TEAM The NRC audit team included the following:
Joel Wiebe, Plant Licensing Branch III (LPL3)
Jeff Circle, Probabilistic Risk Assessment (PRA), Licensing Branch A (APLA)
Malcolm Patterson, APLA Joshua Wilson, Technical Specifications Branch (STSB)
Charley Peabody, Jr., Nuclear Systems Performance Branch (SNSB)
Logan Gaul, SNSB 4.0 DOCUMENT AND FILES REVIEWED Item #
Document Title 1
WCAP-11992, Joint Westinghouse Owners Group / Westinghouse Program:
ATWS Rule Administration Process 2
BB PRA-012 R10 Appendix H - Internal Flooding Uncertainty 3
BB PRA-026 R5, Uncertainty Assessment Notebook 4
BW PRA-021.12 - Fire PRA Uncertainty and Sensitivity - Rev 2 5
BY PRA-021.12 - Fire PRA Uncertainty and Sensitivity - Rev 2 6
BB-LAR-021 R0, Eliminate ATWS UET Requirement for Byron / Braidwood 7
BB PRA-005.22 R1 FLEX 9
ER-AA-600-1012, Rev 014, Risk Management Documentation 10 ER-AA-600-1015, Rev 020, FPIE PRA Model Update 11 ER-AA-600-1061, Rev 007, Fire PRA Model Update and Control 12 SG-SGMP-17-30 Byron Unit 2 B2R20 Steam Generator Condition Monitoring and Operational Assessment 13 CN-TA-10-47, Rev 000, 20110215, ATWS ANALYSIS FOR THE BYRON BRAIDWOOD UNIT 1 AND 2 MEASUREMENT UNCERTAINTY RECAPTURE MUR PROGRAM 5.0 RESULTS OF THE AUDIT As a result of the audit, the NRC staff gained a better understanding of the licensees analyses and calculations that provide the technical support for the LAR. No RAIs were issued to the licensee as a result of this audit.
ML25066A164 NRR-106 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/SNSB/BC NAME SWall SRohrer DMurdock DATE 03/07/2025 03/10/2025 03/11/2025 OFFICE NRR/DRA/APLA/BC NRR/DSS/STSB/BC NRR/DORL/LPL3/BC (A)
NAME RPascarelli SMehta IBerrios DATE 03/10/2025 03/12/2025 03/13/2025 OFFICE NRR/DORL/LPL3/PM NAME SWall DATE 03/13/2025