ML25322A260
| ML25322A260 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  (NPF-086) |
| Issue date: | 12/02/2025 |
| From: | V Sreenivas Plant Licensing Branch 1 |
| To: | Coffey R Florida Power & Light Co |
| References | |
| EPID L-2025-LLA-0025, EPID L-2025-LLA-0058 | |
| Download: ML25322A260 (0) | |
Text
December 2, 2025 Mr. Robert Coffey Executive Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.
Juno Beach, FL 33408
SUBJECT:
SEABROOK STATION, UNIT 1 -
SUMMARY
OF REGULATORY AUDIT IN SUPPORT OF LICENSE AMENDMENT REQUEST TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER 505, REVISION 2, PROVIDE RISK-INFORMED EXTENDED COMPLETION TIMES - RITSTF INITIATIVE 4B AND TO ADOPT 10 CFR 50.69, RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS FOR NUCLEAR POWER REACTORS (EPID L-2025-LLA-0025 AND L-2025-LLA-0058)
Dear Mr. Coffey:
By letter dated February 3, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25034A143), and by letter dated March 21, 2025 (ADAMS Accession No. ML25080A172), NextEra Energy Seabrook, LLC (NextEra, the licensee) submitted license amendment requests (LARs) to amend the licenses for Seabrook Station, Unit 1, Renewed Facility Operating License No. NPF-86. The proposed LARs would adopt Technical Specifications Task Force Traveler 505 (TSTF-505), Revision 2, Provide Risk-informed Extended Completion Times, RITSTF Initiative 4b and Title 10 of the Code of Federal Regulations 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors, respectively.
The U.S. Nuclear Regulatory Commission (NRC) staff conducted a virtual regulatory audit from May 1, 2025, through October 31, 2025, to support its review of the LAR. During the regulatory audit, the NRC staff reviewed documents and held discussions with members of NextEra and its representatives. The regulatory audit summary is enclosed with this letter.
If you have any questions, please contact me by telephone at 301-415-5107 or by email to V.Sreenivas@nrc.gov.
Sincerely,
/RA/
V. Sreenivas, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Regulatory Audit Summary cc: Listserv
Enclosure REGULATORY AUDIT
SUMMARY
BY THE OFFICE OF NUCLEAR REACTOR REGULATION TO SUPPORT THE REVIEW OF LICENSE AMENDMENT REQUEST TO ADOPT TSTF-505, REVISION 2 AND 10 CFR 50.69 NEXTERA ENERGY SEABROOK, LLC SEABROOK STATION, UNIT 1 DOCKET NO. 50-443
1.0 BACKGROUND
By letter dated February 3, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25034A143), and by letter dated March 21, 2025 (ML25080A172),
NextEra Energy Seabrook, LLC (NextEra, the licensee) submitted license amendment requests (LARs) to amend the licenses for Seabrook Station, Unit 1(Seabrook) Renewed Facility Operating License No. NPF-86. The proposed LARs would adopt Technical Specifications Task Force Traveler 505 (TSTF-505), Revision 2, Provide Risk-informed Extended Completion Times, RITSTF Initiative 4b and 10 CFR 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors, respectively.
Information that the U.S. Nuclear Regulatory Commission (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) 50.71 and/or 10 CFR 54.37, which, although not required to be submitted as part of the licensing action, would help the NRC staff better understand the licensees submitted information. To support its review of the TSTF-505 LAR, the NRC staff issued a regulatory audit plan on March 28, 2025 (ML25057A434). The NRC supplemented this plan, by email dated April 21, 2025 (ML25114A113), to include additional items to support the review of the 10 CFR 50.69 LAR. The purpose of the audit is to review the documentation related to the subject of its application (e.g., calculations and reports) that were not submitted on the Seabrook docket, to acquire additional understanding about the amendment request, and to determine whether additional information is needed to be docketed to complete the NRC staffs safety evaluation.
2.0 AUDIT ACTIVITIES The NRC audit team consisted solely of NRC staff. Attachment 1 of this audit summary lists the individuals that took part in or attended the audit. The NRC audit team conducted a virtual regulatory audit from May 1, 2025, through October 31, 2025. Throughout the audit period, the NRC audit team would use an internet-based portal provided by the licensee to review primarily non-docketed information related to the application. On June 20, 2025, the NRC staff submitted audit questions to the licensee. A formal, virtual audit meeting with the licensee was held from July 15-17, 2025.
Technical discussions were focused on the following major areas: probabilistic risk assessment, external hazards, TSs, and electrical engineering. Non-docketed information provided by the licensee in response to audit questions and the formal meeting is listed in Attachment 2 of this audit summary. There were no open items from audit discussions, and the only deviation from the audit plan was a few small NRC staff differences, (including the fact that there was no contractor support from Pacific Northwest National Laboratory (PNNL)), and that the audit ended up being a combined TSTF-505 and 10 CFR 50.69 audit. NextEra asked the NRC to ask requests for additional information (RAIs) (in lieu of NextEra supplementing their application) in order for NextEra to provide documentation of certain audit discussion points on the docket.
3.0 RESULTS OF THE AUDIT As a result of the audit, the NRC staff gained a better understanding of the licensees analyses and calculations supporting the implementation of the provisions of TSTF-505, Revision 2, and 10 CFR 50.69. Several RAIs were issued to the licensee on August 7, 2025 (ML25219A763).
The licensee provided a response to the RAIs on September 5, 2025 (ML25251A063).
Attachments:
- 1. List of NRC Participants
- 2. List of Licensee Participants
- 3. List of Documents Reviewed
List of Participants U.S. Nuclear Regulatory Commission (NRC) Audit Team Name Email Review Area (Organization)
Ricardo Lantigua (1)
Ricardo.Lantigua@nrc.gov Plant Licensing Branch LPL 1 (LPL1)
Alexander Schwab (2)
Alexander.Schwab@nrc.gov PRA Licensing Branch A (APLA)
Jeff Circle Jeff.Circle@nrc.gov David Gennardo (3)
David.Gennardo@nrc.gov Jay Robinson Jay.Robinson@nrc.gov PRA Licensing Branch B (APLB)
Charles Moulton Charles.Moulton@nrc.gov Sunwoo Park Sunwoo.Park@nrc.gov PRA Licensing Branch C (APLC)
Steven Alferink Steven.Alferink@nrc.gov Ellery Coffman Ellery.Coffman@nrc.gov Edmund Kleeh Edmund.Kleeh@nrc.gov Electrical Engineering Branch (EEEB)
Adakou Foli Adakou.Foli@nrc.gov Jason English Jason.English@nrc.gov Instrumentation and Controls Branch (EICB)
Ming Li Ming.Li@nrc.gov Robert Torres Davis Roberto.TorresDavis@nrc.gov Mechanical Engineering and Inservice Testing Branch (EMIB)
Hanry Wagage Hanry.Wagage@nrc.gov Containment and Plant Systems Branch (SCPB)
Jo Ambrosini Josephine.Ambrosini@nrc.gov Nuclear Systems Performance Branch (SNSB)
Khadijah West Khadijah.West@nrc.gov Technical Specifications Branch (STSB)
(1) NRR Division of Operating Reactor Licensing Project Manager (2) Technical Lead for TSTF-505 (3) Technical Lead for 50.69
List of Licensee Participants Name Email Review Area (Organization)
Keith Vincent Keith.Vincent@fpl.com NextEra Energy NextEra Energy NextEra Energy Jarrett Mack Jarrett.Mack@fpl.com Jadie Palenzuela Jadie.Palenzuela@fpl.com Jerry Phillabaum Jerry.Phillabaum@fpl.com NextEra Energy Jensen Hughes Robert Kirchner RKirchner@jensenhughes.com David Passehl DPassehl@jensenhughes.com Jensen Hughes Jensen Hughes Jensen Hughes Usama Farradj ufarradj@jensenhughes.com Marie Schmehl MSchmehl@jensenhughes.com Edward Parsley EParsley@jensenhughes.com Jensen Hughes Jensen Hughes Vince Andersen VAndersen@jensenhughes.com Leo Shanley LShanley@jensenhughes.com Jensen Hughes
List of Documents Reviewed The licensee provided an extensive list of supporting documents (e.g., analyses, calculations, reports, drawings, and procedures) on the Seabrook document portal available during the audit period. Below lists the documents available on the portal that the NRC audit team reviewed during the audit.
-Seabrook Station PRA 2005 Peer Review
-Seabrook Station Generating Station Internal Flooding PRA Peer Review Report
-Seabrook PRA Finding Level Fact and Observation Independent Assessment
-Seabrook Internal Events Probabilistic Risk Assessment Peer Review Findings Closure
-Seabrook Station Peer Review Report ASME PRA Standard Element LE
-Focused Scope Peer Review of Appendix X F&O Closure of the Seabrook Internal Events and Internal Flood Probabilistic Risk Assessment
-Peer Review of the Seabrook Fire Probabilistic Risk Assessment
-Seabrook Station PRA Capability Assessment, SBK-PRA-QUALITY-R0
-SBK PRA Finding Level Fact and Observation Independent Assessment, SBK-PRA-PEER-IAT-RICT-1
-Assessment of Key Assumptions and Sources of Uncertainty for the Seabrook Station PRA
-Extended Loss of All AC Power with SEPS, FSG-0.0
-Alternate CST Makeup, FSG-6
-Loss of Vital Instrumentation or Control Power, FSG-7
-Seabrook Unit 1 At-Power Fire PRA, Fire Risk Model Notebook
-Safety Evaluation Report related to the Operation of Seabrook Station, Units 1 and 2, NUREG-0896 Supplement No. 3
-Seabrook Nuclear Power Plant Tornado Missile Analysis
-Seabrook Station Response to NEI Open Phase Condition Initiative
-Seabrook Station, Unit No. 1 - Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System
-Seabrook Unit 1 At-Power Fire PRA, Qualitative Screening, Quantification, and Uncertainty Analysis Notebook
-Fire Basic Event Importance Measures
-External Hazards Assessment for Seabrook Station, SKB-PRA-EXTERNAL
-AR Report, NRC RIS 2015-06 Tornado Missile Protection Requires Review
-Beyond Design Basis Flooding Mitigating Strategy Assessment, EE-10-005 Rev. 0
-Seabrook Station-Other Hazards PRA
-Risk to Seabrook Station from Regional Meteorite Impact
-RICT Estimates for TSTF-505 (RICT) Program LAR Submittal for the Seabrook Station PRA, SBK-PRA-LAR-RICT-ESTIMATES, Rev. 0
-Seabrook PRA Phoenix Online Risk Monitor Model, SBK-PRA-OLM, Rev. 1
-Probabilistic Risk Assessment (PRA) Program, EN-AA-105
-PRA Configuration Control and Model Maintenance, EN-AA-105-1000
-Risk Informed Completion Time (RICT) Program, OP-AA-110, Rev. 1
-Implementation of the Risk Informed Completion Time (RICT) Program, OP-AA-110-1000, Rev.
2
-Risk Management Actions for the Risk Informed Completion Time Program, OP-AA-110-1001, Rev. 1
-Seabrook Station Probabilistic Safety Study - 2019 Update, Section 14.0 Containment Analysis
-CIS Sensitivity - Containment Penetration Size Sensitivity to Small Release, MC 885
-Inservice Testing Reference, SITR
-SBK Elec Distribution System
-SBK Tech Specs Bases
-UFSAR Tables 8.1-1, Safety Loads and Functions, 8.3-1, EDG Loading Sequence LOOP-SI, and 8.3-5, Battery Loading - Safety-Related Batteries
-UFSAR Figures 8.3-37, 8.3-39, 8.3-40, 8.3-41, 8.3-42, 8.3-58, 8.3-59, and 8.3-61
-SBK PRA Data Analysis Notebook, SBK-PRA-DATA, Rev. 0
-Section 10.3.7, Solid State Protection System (SSPS)
-Calvert Cliffs Response to RAIs Regarding LAR to Adopt 10 CFR 50.69 (ML19183A012)
-Seabrook NRC Staff Review of High Frequency Confirmation Associated with Reevaluated Seismic Hazard Implementing NTTF Recommendation 2.1 (ML18138A451)
-Peach Bottom NRC Letter Transmitting Conclusion that No Further Review is Required Concerning Recommendation 2.1 (ML19053A469)
- Seabrook SBK-L-17136 Seismic High Frequency Confirmation Report for the Reevaluated Seismic Hazard Information (ML17241A150)
-Seabrook NRC Letter Pursuant to 10 CFR 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of NTTF from Fukushima Accident (ML15208A049)
-Seabrook Seismic Hazard and Screening Report in Response to 10 CFR 50.54(f) Request from NRC Regarding NTTF Recommendation 2.1 Fukushima Accident (ML14092A413)
-Seabrook Supplement to Response to NRC 10 CFR 50.54(f) NTTF Recommendation 2.3, Seismic (ML13275A202)
-Seabrook NRC Staff Assessment of Seismic Walkdown Report Supporting NTTF Recommendation 2.3 Related to Fukushima Accident (ML13364A311)
-Seabrook SBK-L-17135, Seismic Mitigating Strategies Assessment (MSA) Report for Reevaluated Seismic Hazard Information - NEI 12-06 Appendix H (ML17241A140)
-Seabrook NRC Staff Review of Mitigation Strategies Assessment Report of the Impact of the Reevaluated Seismic Hazard (ML18236A191)
-Seabrook NRC Staff Review of Interim Evaluation Associated with Reevaluated Seismic Hazard NTTF Recommendation 2.1 (ML15282A019)
-Peach Bottom Supplemental Information to Support LAR to Adopt 10 CFR 50.69 (ML18157A260)
-EPRI NP-6041-SL Revision 1, A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)
-Watts Bar Amendments 134 and 38 Regarding Adoption of 10 CFR 50.69 (ML20076A194)
-NRC Letter to Power Reactor Licensees, Final Determination Regarding Recommendation 2.1 (ML15194A015)
-Watts Bar LAR to Adopt 10 CFR 50.69 (ML18334A363)
-Vogtle Response to RAIs Regarding LAR to Incorporate Seismic PRA into the 10 CFR 50.69 Categorization Process (ML18052B342)
-EPRI 3002017583, Alternative Approaches for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization (ML21082A170)
-LaSalle Response to RAIs Regarding LAR to Adopt 10 CFR 50.69 (ML20290A791)
-LaSalle Response to RAIs Regarding LAR to Adopt 10 CFR 50.69 (ML21022A130)
-EPRI 3002012988, Alternative Approaches for Addressing Seismic Risk in 10CFR50.69 Risk-Informed Categorization Technical Update July 2018
-Clinton Response to RAIs Regarding LAR to Adopt TSTF-505 and 10 CFR 50.69 (ML20329A433)
-NRC Letter to All Licensees Regarding Recommendations 2.1, 2.3, and 9.3 of Insights from Fukushima Dai-ichi Accident (ML12053A340)
-Peach Bottom Response to RAIs Regarding Recommendation 2.1 of Insights from Fukushima Dai-ichi Accident (ML18240A065)
-Seabrook SBK-L-14229 Expedited Seismic Evaluation Process Report Regarding Recommendation 2.1 of NTTF Fukushima Accident (ML14360A016)
-Peach Bottom Correction to NRC Letter Transmitting Conclusion that No Further Review is Required Concerning Recommendation 2.1 (ML19248C756)
-Vogtle LAR to Modify Approved 10 CFR 50.69 Categorization Process (ML17173A875)
-Vogtle Amendments 196 and 179 Regarding Application of Seismic PRA into Previously Approved 10 CFR 50.69 Categorization Process (ML18180A062)
-Watts Barr Response to RAIs Regarding Recommendation 2.1 of Insights from the Fukushima Dai-ichi Accident (ML17181A485)
-Watts Bar Seismic PRA Supplemental Information (ML18100A966)
-Watts Bar NRC Letter Transmitting Conclusion that No Further Review is Required Concerning Recommendation 2.1 (ML18115A138)
-Risk-Informed Engineering Programs (RIEP) 10 CFR 50.69, EN-AA-112, Revision 001
-RIEP Active Component Risk Significance Insights, EN-AA-112-1000, Revision 001
-RIEP (10 CFR 50.69) Passive Component Categorization, EN-AA-112-1001, Revision 001
-RIEP (10 CFR 50.69) Categorization for Structures, Systems, and Components, EN-AA-112-1002, Revision 001
-RIEP (10 CFR 50.69) Alternative Treatment Requirements, EN-AA-112-1003, Revision 001
-RIEP SSC Categorization Integrated Decision-Making Panel, EN-AA-112-1004, Revision 001
-RIEP Requirements for Immediate Reviews, Periodic Reviews, and Performance Monitoring, EN-AA-112-1005, Revision 001
-Integrated Decision-Making Panel for Risk-Informed Programs, LI-AA-1003, Revision 001
-Response to Natural Phenomena Affecting Plant Operations, SEA Procedure ON1090.13, R29
-Severe Weather Conditions, SEA Procedure OS1200.03, R32
-Seabrook PRA Finding Level Fact and Observation Independent Assessment, SBK-PRA-PEER-IAT-RICT-2, Rev. 0
-Seabrook Unit 1 At-Power Fire PRA, Ignition Frequency Notebook, SBK-BFJR-23-038, Rev. 2
-Seabrook Unit 1 At-Power Fire PRA, Fire Scenario Selection Notebook, SBK-BFJR-23-039, Rev. 2
-Attachment 2-SBK FSS Spreadsheet DATA Tab
-ATTACHMENT_3_-_IGNITION_FREQUENCY_CALCULATIONS_Rev 1_Transient Ignition Sources Tab
-ATTACHMENT_3_-_IGNITION_FREQUENCY_CALCULATIONS_Rev 1_Transient Survey Results Tab
- via eConcurrence NRR-106 OFFICE NRR/DORL/LPL1/PM*
NRR/DORL/LPL1/LA*
NRR/DRA/APLA/BC*
NAME VSreenivas KEntz RPascarelli DATE 11/21/2025 11/21/2025 11/25/2025 OFFICE NRR/DORL/LPL1/BC (A)*
NRR/DORL/LPL1/PM NAME UShoop VSreenivas DATE 11/26/2025 12/2/2025