Letter Sequence Other |
---|
EPID:L-2020-SLR-0002, Enclosure 4, Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version) (Approved, Closed) |
Results
Other: L-2021-129, Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses, L-2021-144, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses, L-2021-157, L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses, L-2021-172, Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response, L-2021-190, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 1, L-2021-199, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses, L-2021-200, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response, L-2021-223, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response, L-2021-224, Subsequent License Renewal Application - First Annual Update, L-2021-248, Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response, ML21005A058, ML21015A214, ML21036A217, ML21208A447, ML21214A035, ML21302A019
|
MONTHYEARML20329A2642020-11-16016 November 2020 Enclosure 4, Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version) Project stage: Request ML21006A4172021-01-15015 January 2021 Subsequent License Renewal Acceptance Letter Project stage: Acceptance Review ML21015A2142021-01-15015 January 2021 Subsequent License Renewal Application Acceptance Federal Register Notice FRN Project stage: Other ML21005A0582021-01-15015 January 2021 Subsequent License Renewal Application - Portal Letter Project stage: Other ML21036A2172021-03-0101 March 2021 SLRA - Proprietary Determination Letter Project stage: Other L-2021-081, Subsequent License Renewal Application - Aging Management Supplement 12021-04-21021 April 2021 Subsequent License Renewal Application - Aging Management Supplement 1 Project stage: Supplement ML21161A1192021-06-10010 June 2021 RAIs Set 1 Final Aging Management of Irradiated Concrete and Steel Reactor Vessel Supports Final Project stage: Request L-2021-129, Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses2021-07-0808 July 2021 Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses Project stage: Other L-2021-147, Subsequent License Renewal Application - Aging Management Supplement 3 Revision 12021-07-26026 July 2021 Subsequent License Renewal Application - Aging Management Supplement 3 Revision 1 Project stage: Supplement ML21214A0432021-08-0202 August 2021 SLRA June 30, 2021, Public Meeting Discussion Questions Project stage: Request L-2021-144, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses2021-08-11011 August 2021 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses Project stage: Other ML21214A0352021-08-16016 August 2021 Subsequent License Renewal Application (SLRA) Compiled Aging Management Audit Breakout Questions Project stage: Other ML21208A4472021-08-16016 August 2021 Subsequent License Renewal Application Aging Management Audit Report Project stage: Other L-2021-155, Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response2021-08-30030 August 2021 Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response Project stage: Request L-2021-157, L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses2021-09-10010 September 2021 L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses Project stage: Other L-2021-172, Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response2021-09-20020 September 2021 Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response Project stage: Other L-2021-174, NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response2021-10-0101 October 2021 NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response Project stage: Request ML21286A6042021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final Project stage: Request L-2021-200, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response2021-10-25025 October 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Project stage: Other L-2021-190, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 12021-11-0303 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 1 Project stage: Other ML21292A1852021-11-0303 November 2021 Letter to Applicant Point Beach Nuclear Plant, Units 1 and 2 Notice of Availability of the Draft Plant-Specific Supplement 23, Second Renewal Project stage: Draft Other L-2021-199, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses2021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Project stage: Other ML21302A0192021-11-10010 November 2021 Maintenance of Reference Material at the Lester Public Library Associated with the Staff'S Review Project stage: Other ML21312A5202021-11-10010 November 2021 Proprietary Determination Letter SLRA Safety RAIs Set 1 Response Project stage: RAI L-2021-221, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 12021-11-19019 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 1 Project stage: Supplement L-2021-224, Subsequent License Renewal Application - First Annual Update2021-11-30030 November 2021 Subsequent License Renewal Application - First Annual Update Project stage: Other L-2021-223, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response2021-12-0909 December 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response Project stage: Other L-2021-248, Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response2022-01-0606 January 2022 Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response Project stage: Other ML22041A3342022-02-23023 February 2022 Transmittal Letter for Point Beach Final SE for SLRA Review to AA La 2-9 (3) Project stage: Approval ML22054A1082022-02-23023 February 2022 Subsequent License Renewal Application Safety Evaluation Public Project stage: Approval ML22054A1062022-02-23023 February 2022 Srla Safety Evaluation Documents and Transmittal Letter Project stage: Request ML22139A2292022-05-25025 May 2022 Transmittal Letter for Point Beach Final SE for SLRA Review Rev1 Project stage: Approval ML22139A2282022-05-25025 May 2022 Srla Safety Evaluation Revision 1 Documents and Transmittal Letter Project stage: Request 2021-04-21
[Table View] |
|
---|
Category:Letter type:L
MONTHYEARL-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-048, Core Operating Limits Report (COLR) Cycle 40 (U2C40)2023-03-18018 March 2023 Core Operating Limits Report (COLR) Cycle 40 (U2C40) L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-036, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2023-02-24024 February 2023 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2023-011, Response to Requests for Additional Information (Rais) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed2023-02-21021 February 2023 Response to Requests for Additional Information (Rais) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-177, Subsequent License Renewal Application - Second Annual Update2022-11-28028 November 2022 Subsequent License Renewal Application - Second Annual Update L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-161, U1R40 Steam Generator Tube Inspection Report2022-10-13013 October 2022 U1R40 Steam Generator Tube Inspection Report L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2022-10-0404 October 2022 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-164, Technical Specification Bases and Technical Requirements Manual Change Summary2022-10-0404 October 2022 Technical Specification Bases and Technical Requirements Manual Change Summary L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-150, 10 CFR 50 Appendix E Evacuation Time Estimate Study for Point Beach Nuclear Plant2022-09-13013 September 2022 10 CFR 50 Appendix E Evacuation Time Estimate Study for Point Beach Nuclear Plant L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-022022-07-29029 July 2022 Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 L-2022-124, Refueling Outage U1R40 Owner'S Activity Report (OAR-1) for Inservice Inspections2022-07-20020 July 2022 Refueling Outage U1R40 Owner'S Activity Report (OAR-1) for Inservice Inspections L-2022-065, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations; Request for Comment2022-04-20020 April 2022 Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations; Request for Comment L-2022-039, and Point Beach, Units 1 & 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2022-04-14014 April 2022 and Point Beach, Units 1 & 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2022-012, Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3)2022-03-16016 March 2022 Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2022-013, Subsequent License Renewal Application - Environmental Report Review Review Request for Additional Information (RAI) No. HCR-1 Supplemental Response2022-01-25025 January 2022 Subsequent License Renewal Application - Environmental Report Review Review Request for Additional Information (RAI) No. HCR-1 Supplemental Response L-2021-248, Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response2022-01-0606 January 2022 Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response L-2021-240, Subsequent License Renewal Application - Aging Management Request for Additional Information Set 13 Response2022-01-0606 January 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information Set 13 Response L-2021-223, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response2021-12-0909 December 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response L-2021-224, Subsequent License Renewal Application - First Annual Update2021-11-30030 November 2021 Subsequent License Renewal Application - First Annual Update L-2021-222, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Revision 12021-11-23023 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Revision 1 L-2021-221, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 12021-11-19019 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 1 L-2021-208, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 9 Response Supplement 12021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 9 Response Supplement 1 L-2021-199, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses2021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses L-2021-190, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 12021-11-0303 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 1 L-2021-200, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response2021-10-25025 October 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response 2024-01-26
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response L-2023-011, Response to Requests for Additional Information (Rais) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed2023-02-21021 February 2023 Response to Requests for Additional Information (Rais) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed ML23011A2802023-01-11011 January 2023 Units 1 and 2 - Response to Requests for Additional Information (Rals) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed . ML22229A1052022-08-17017 August 2022 Response to Questions Regarding Point Beach Nuclear Power Plant with Attachment NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, L-2022-013, Subsequent License Renewal Application - Environmental Report Review Review Request for Additional Information (RAI) No. HCR-1 Supplemental Response2022-01-25025 January 2022 Subsequent License Renewal Application - Environmental Report Review Review Request for Additional Information (RAI) No. HCR-1 Supplemental Response L-2021-240, Subsequent License Renewal Application - Aging Management Request for Additional Information Set 13 Response2022-01-0606 January 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information Set 13 Response L-2021-248, Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response2022-01-0606 January 2022 Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response L-2021-223, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response2021-12-0909 December 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response L-2021-222, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Revision 12021-11-23023 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Revision 1 L-2021-199, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses2021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses L-2021-208, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 9 Response Supplement 12021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 9 Response Supplement 1 L-2021-190, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 12021-11-0303 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 1 L-2021-200, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response2021-10-25025 October 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response L-2021-174, NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response2021-10-0101 October 2021 NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response L-2021-172, Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response2021-09-20020 September 2021 Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response L-2021-173, Subsequent License Renewal Application-Aging Management Request for Additional Information (RAI) Set 8 Response2021-09-16016 September 2021 Subsequent License Renewal Application-Aging Management Request for Additional Information (RAI) Set 8 Response L-2021-157, L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses2021-09-10010 September 2021 L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses L-2021-165, Submittal of Subsequent License Renewal Application - Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses Supplement 12021-09-10010 September 2021 Submittal of Subsequent License Renewal Application - Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses Supplement 1 L-2021-155, Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response2021-08-30030 August 2021 Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response L-2021-154, Subsequent License Renewal Application -Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 3 Responses2021-08-25025 August 2021 Subsequent License Renewal Application -Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 3 Responses L-2021-144, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses2021-08-11011 August 2021 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses L-2021-116, Subsequent License Renewal Application Environmental Report Review Requests for Confirmation Of/Additional Information (Rci/Ral) Set Response2021-06-10010 June 2021 Subsequent License Renewal Application Environmental Report Review Requests for Confirmation Of/Additional Information (Rci/Ral) Set Response NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information NRC-2018-0050, Response to Request for Additional Information Regarding License Amendment Request 288, Request to Extend Containment Leakages Rate Test Frequency2018-11-16016 November 2018 Response to Request for Additional Information Regarding License Amendment Request 288, Request to Extend Containment Leakages Rate Test Frequency NRC 2018-0044, Supplement to Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, ...2018-09-28028 September 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, ... NRC 2018-0038, Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear2018-08-10010 August 2018 Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear NRC 2018-0014, NextEra Energy Point Beach, LLC, Construction Truss License Amendment Request 278, Response to Request for Additional Information2018-04-12012 April 2018 NextEra Energy Point Beach, LLC, Construction Truss License Amendment Request 278, Response to Request for Additional Information L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018 Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations ML17363A1452017-12-21021 December 2017 Response to Request for Additional Information Regarding License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor NRC 2017-0052, Supplement to LAR 287, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants2017-10-26026 October 2017 Supplement to LAR 287, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants NRC 2017-0041, to License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2017-08-21021 August 2017 to License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors NRC 2017-0010, Response to Final Request for Additional Information Steam Generator License Amendment Request for H* Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region2017-04-20020 April 2017 Response to Final Request for Additional Information Steam Generator License Amendment Request for H* Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region NRC 2017-0008, Response to Final Request for Additional Information on Steam Generator Tube Inspection Report2017-02-23023 February 2017 Response to Final Request for Additional Information on Steam Generator Tube Inspection Report L-2016-137, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage...2016-12-15015 December 2016 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage... NRC 2016-0048, Response to Request for Additional Information Regarding LAR 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-11-0404 November 2016 Response to Request for Additional Information Regarding LAR 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) NRC-2016-0033, Response to Request for Additional Information, License Amendment Request 279, Elimination of Technical Specification Section 3.7.14, Primary Auxiliary Building Ventilation2016-07-27027 July 2016 Response to Request for Additional Information, License Amendment Request 279, Elimination of Technical Specification Section 3.7.14, Primary Auxiliary Building Ventilation NRC 2016-0029, Response to Request for Additional Information Regarding License Amendment Request 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-07-11011 July 2016 Response to Request for Additional Information Regarding License Amendment Request 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program NRC 2016-0012, Response to Request for Additional Information, License Amendment Request 271 Associated with NFPA 8052016-04-0707 April 2016 Response to Request for Additional Information, License Amendment Request 271 Associated with NFPA 805 NRC 2016-0008, Response to Request for Additional Information on NFPA 805 License Amendment Request 2712016-02-22022 February 2016 Response to Request for Additional Information on NFPA 805 License Amendment Request 271 NRC 2016-0006, License Amendment Request 277. Revision to Staff Augmentation Times in the Emergency Plan, Supplemental Response to Request for Additional Information No. 5 -Correction to Table 5.12016-02-0909 February 2016 License Amendment Request 277. Revision to Staff Augmentation Times in the Emergency Plan, Supplemental Response to Request for Additional Information No. 5 -Correction to Table 5.1 NRC 2016-0003, License Amendment Request 277, Revision to Staff Augmentation Times in the Plant Emergency Plan, Supplemental Response to Request for Additional Information No. 52016-01-26026 January 2016 License Amendment Request 277, Revision to Staff Augmentation Times in the Plant Emergency Plan, Supplemental Response to Request for Additional Information No. 5 NRC 2015-0068, Request for Additional Information for Relief Request 2-RR-11 - MF66152015-11-19019 November 2015 Request for Additional Information for Relief Request 2-RR-11 - MF6615 NRC-2015-0069, Response to Request for Information Supporting Flooding Hazards Reevaluation Report Audit2015-11-0606 November 2015 Response to Request for Information Supporting Flooding Hazards Reevaluation Report Audit 2023-08-07
[Table view] |
Text
NEXTera ENERGY .
POINT BEACH September 20, 2021 L-2021-172 10 CFR 54.17 U.S. Nuclear Regulatory Corrunission Attention: Document Control Desk 11545 Rockville Pike One \Vhite Flint North Rockville, MD 20852-2746 Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 SUBSEQUENT LICENSE RENEWAL APPLICATION -AGING MANAGEMENT REQUEST FOR ADDITIONAL INFORMATION (RAI) SET 7 RESPONSE
References:
- 1. NextEra Energy Point Beach, LLC (NEPB) Letter NRC 2020-0032 dated November 16, 2020, Application for Subsequent Renewed Facility Operating Licenses (ADAMS Package Accession No. ML20329A292)
- 2. U.S. Nuclear Regulatory Corrunission (NRC) Letter dated January 15, 2021, Point Beach Nuclear Plant, Units 1 and 2 - Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Notice of Opportunity to Request a Hearing Regarding the NextEra Energy Point Beach, LLC Application for Subsequent License Renewal (EPID No. L-2020-SLR-0002)
(ADAMS Accession No. ML21006A417)
- 3. NRC Letter dated January 15, 2021, Point Beach Nuclear Plant, Units 1 and 2 - Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review (ADAMS Accession No. ML21007A260)
- 4. US Nuclear Regulatoty Corrunission Meeting with NextEra Energy Concerning the Point Beach Subsequent License Renewal Application Review - June 3, 2021 Public Meeting (ADAMS Accession No. ML21148A116)
- 5. NRC Email and Attachment dated August 20, 2021, Point Beach SLRA RAI Set 7 Final (ADAMS Accession Nos. ML21242A219, ML21242A220)
NEPB, owner and licensee for Point Beach Nuclear Plant (PBN) Units 1 and 2, has submitted a subsequent license renewal application (SLRA) for the Facility Operating Licenses for PBN Units 1 and 2 (Reference 1).
On January 15, 2021, the NRC determined that NEPB's SLRA was acceptable and sufficient for docketing (Reference 2), and onJanuaty 15, 2021 issued the regulatory audit plan for the aging management portion of the SLRA review (Reference 3). Based on the information exchanged and discussions held during the public meeting held on June 3, 2021 (Reference 4), the NRC issued its Set 7 RAI to NEPB (Reference 5). The attachment indexed on page 3 of this letter provides the response to this information request.
NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241
Document Control Desk L-2021-172 Page 2 Should you have any questions regarding this submittal, please contact me at (561) 304-6256 or William.Maher@fpl.com.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 20 1" day of September 2021.
Sincerely, William Olgila1ty signed by \'/illla m Maher DN:cn=WilllamMahe1, 0= Nuclear, ou =NuclearlkenslllgProjects, emall=wlll lam.mahe10 fplcom, Maher c=US Dale: 2021 .09.20 09: 1 8~ -04'00' William D. Maher Licensing Director - Nuclear Licensing Projects Cc: Administrator, Region III, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Public Service Commission \Visconsin
Document Control Desk L-2021-172 Page 3 Attachment Index Attachment RAI No. Subject No.
1 4.7.2-1 Leak-Before-Break of Reactor Coolant System Au."iliary Piping
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 4.7.2-1 L-2021-172 Attachment 1 Page 1 of 7
- 1. SLRA Section 4.7 .2, "Leak-Before-Break of Reactor Coolant System Auxiliary
. Piping" RAI 4.7.2-1 Regulatory Basis:
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 54.21 (c), the SLRA shall include an evaluation of time-limited aging analyses (TLAAs). The applicant shall demonstrate that (i) the analyses remain valid for the subsequent period of extended operation; (ii) the analyses have been projected to the end of the subsequent period of extended operation; or (iii) the effects of aging on the intended function(s) will be adequately managed for the subsequent period of extended operation.
Background:
SLRA Section 4.7.2, "Leak-Before-Break [LBB] of Reactor Coolant System Auxiliary Piping," identifies the potential for thermal aging of the auxiliary line piping components and fatigue crack growth as the aging effects that must be addressed for subsequent license renewal (SLR). SLRA Section 4.7.2 states that thermal aging of the stainless steel weld material was considered in the evaluations of the pressurizer surge line, the residual heat removal (RHR) system, and the accumulator line (see WCAP-15065-P-A, Revision 1, "Technical Justification for Eliminating Pressurizer Surge Line Rupture as the Structural Design Basis for Point Beach Units 1 and 2 Nuclear Plants," June 2001; WCAP-15105-P-A, Revision 1, "Technical Justification for Eliminating Residual Heat Removal (RHR) Rupture as the Structural Design Basis for Point Beach Units 1 and 2 Nuclear Plants," June 2001; and WCAP-15107-P-A, Revision 1, 'Technical Justification for Eliminating Accumulator Rupture as the Structural Design Basis for Point Beach Units 1 and 2 Nuclear Plants," June 2001) by assuming saturated conditions (fully aged).
In addition, SLRA Section 4.7.1, "Leak-Before-Break of Reactor Coolant System Loop Piping," and WCAP-14439-P, Revision 4, "Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Point Beach Nutlear Plant Units 1 and 2 for the Subsequent License Renewal Program (80 Years)," June 2020, address thermal aging effects on the cast austenitic stainless steel components for the LBB analyses of the Point Beach reactor coolant loop piping.
Issue:
SLRA Enclosure 4, Attachment 17, Westinghouse LTR-SDA-11-20-06, Revision 1, "Leak-Before-Break Reconciliation of the Point Beach Units 1 and 2 Pressurizer Surge Line, Residual Heat Removal Line, and Accumulator Line Piping Systems for the Subsequent License Renewal Program," May 4, 2020, does not discuss the disposition of thermal aging of the stainless steel welds as described in SLRA Section 4.7.2 and does not provide a basis for that disposition in the SLRA.
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 4.7.2-1 L-2021-172 Attachment 1 Page 2 of 7 In addition, the equation used to implement the assumption of "saturated cond itions (fully aged)" in the calculations is Eq. 3
] (k] /m 2) =73.4 + 83.5 !:i.a (mm)0.643 in NUREG/CR-6428, "Effects of Thermal Aging on Fracture Toughness and Charpy-lmpact Strength of Stainless Steel Pipe Welds," May 1996 ("Revision O") , which is described as "the lower-bound J-R curve for both SAWs [submerged arc welds] and SMAWs [shielded metal arc welds] ." A more recent report, NUREG/CR-6428, Revision 1, "Effects of Thermal Aging on Fracture Toughness and Charpy-lmpact Strength of Stainless Steel Pipe Welds ," August 2018 ("Revision 1"), identifies Eq. 22
] (k] /m 2) = 117 !:i.a (mm) 0A5 as the recommended lower bound J-R curve for thermally aged SAWs and SMAWs. Eq .
22 of Revision 1 is approximately 25% lower than Eq. 3 of Revision 0 at a crack growth
(!:i.a) value of 1 mm.
Request:
- 1. What is the basis for the disposition of 10 CFR 54 .21 (c)(1 )(i) in SLRA Section 4 .7.2 as it pertains to thermal aging of stainless steel welds?
- 2. In its consideration of the TLAA related to LBB analyses for the reactor coolant system auxiliary piping , did the applicant consider the updated analysis on lower bound thermal aging of stainless steel welds from NUREG/CR-6428, Revision 1, relative to the assumptions made in WCAP-15065-P-A, Revision 1, WCAP-15105-P-A, Revision 1, and WCAP-15107-P-A, Revision 1?
- 3. Would the use of the updated lower bound thermal aging curves for stainless steel welds from NUREG/CR-6428, Revision 1 affect the conclusions in SLRA Section 4.7.2?
- 4. As cited in SLRA Section 4.7.1, WCAP-14439-P , Revision 4 addresses thermal aging effects on the cast austenitic stainless steel components for the LBB analyses of the Point Beach reactor coolant loop piping. Was thermal aging of the stainless steel welds considered in this report, and would use of the updated lower bound thermal aging curves for stainless steel welds from NUREG/CR-6428 ,
Revision 1 affect the conclusions in SLRA Section 4. 7 .1?
NEPB Response:
- 1. The statement from Section 4. 7.2 of the SLRA, regarding thermal aging of stainless steel weld material, is based on the original NRC Staff Safety Evaluation Reports (SERs), which are now archived within the auxiliary line LBB reports for Point Beach Units 1 and 2:
Pressu rizer Surge Line WCAP-15065-P-A, Revision 1 (Reference 1);
SER dated 12/15/2000 (ADAM Accession Number ML003777863)
RHR Line WCAP-15105-P-A, Revision 1 (Reference 2);
SER dated 12/18/2000 (ADAM Accession Number ML003777964)
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 4.7.2-1 L-2021-172 Attachment 1 Page 3 of 7 Accumulator Line WCAP-15107-P-A, Revision 1 (Reference 3);
SER dated 11/7/2000 (ADAM Accession Number ML003767681)
Section 4.1 in each of these SE Rs includes a discussion related to thermal aging of stainless steel welds and summarizes evaluations performed by the NRC Staff.
It is noted that the evaluation considering the effects of thermal aging on stainless steel welds was not performed by Westinghouse and is not typical of any Westinghouse LBB analyses (past or current) that have been submitted to the NRC . Therefore, Westinghouse is not cognizant of the specific details of the Staffs independent evaluations discussed in Section 4.1 of the SERs.
For notable precedents, the Subsequent License Renewal Application for Turkey Point Units 3 and 4 was issued in 2019. This application included LBB evaluations for reactor coolant loop (RCL) and auxiliary piping systems, with no evaluation related to NUREG-6428 or the thermal aging of stainless steel weld materials.
Specifically, the SER for the Turkey Point SLRA (updated in December of 2019) includes the following statement regarding thermal embrittlement on auxiliary piping systems (page 4-65 of Reference 4):
"The staff a/so finds that, because the subject piping does not contain CASS, thermal embrittlement is not an issue; therefore, a TLAA is not necessary to address material property changes due to thermal aging embrittlement."
It should be noted that the materials for the Turkey Point Units 3 and 4 auxiliary piping components (i.e. surge, RHR, and accumulator) and welds are the same as Point Beach Units 1 and 2, as such there are no CASS components in the piping systems.
Furthermore, as part of the Surry RCL LBB evaluations (see Section 4.7.3.2.2 of Surry SLR SER; Reference 5), the Staff accepted that the aged fracture toughness of the wrought and cast stainless steel base metal is more limiting than that of the stainless steel weld metal. Therefore, no additional thermal aging analysis was needed for the stainless steel weld metal in the LBB evaluations for the Surry RCL.
The Surry auxiliary lines (accumulator, surge, RHR, safety injection, and loop bypass) were also evaluated for LBB. Similar to the Point Beach auxiliary lines, the Surry lines are also made of non-CASS stainless steel base metal and SMAW or SAW welds. For these non-CASS materials, no thermal aging was necessary for the Surry auxiliary lines. The Staff has accepted the Surry auxiliary lines LBB evaluation on August 20, 2021 based on the understanding that there is no additional thermal aging embrittlement for the non-CASS base and weld metals (see Section 3.3.1 of Reference 6).
Similarly, the NRC SER for the License Renewal for Vogtle Units 1 and 2 was issued in April of 2009 (Reference 7). Again, the LBB evaluations and SER for the RCL and auxiliary piping do not include any coritent specific to NUREG-6428 or the thermal aging of stainless steel weld materials.
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 4.7.2-1.
L-2021-172 Attachment 1 Page 4 of 7 Therefore, the Westinghouse LBB evaluations performed in WCAP-15065-P-A, Revision 1, WCAP-15105-P-A, Revision 1, and WCAP-15107-P-A, Revision 1 have been evaluated and determined to remain valid for the Subsequent Period of Extended Operation (SPEO) in accordance with 10CFR54.21 (c)(1 )(i).
- 2. Thermal aging of stainless steel welds is not considered in the Westinghouse LBB evaluations of the Point Beach Units 1 and 2 pressurizer surge line (WCAP-15065-P-A, Reference 1), RHR line (WCAP-15105-P-A, Reference 2), nor accumulator line (WCAP'.'"15107-P-A, Reference 3). These evaluations are consistent with guidance from the Generic Aging Lessons Learned (GALL) Report (Reference 8) and the GALL Subsequent License Renewal (SLR) Report (Reference 9). NUREG-1801 and NUREG-2191 endorse addressing thermal aging of cast austenitic stainless steel (CASS) base metals for piping systems. NUREG-1801 and NUREG-2191 do not mention NUREG-6428, nor recognize thermal aging of stainless steel welds as an aging effect necessitating management for the PEO and SPEO, respectively.
Additi.onally, there are no known NRC Interim Staff Guidance (ISG) documents pertaining to thermal aging of stainless steel welds. The response to Request 1 (above) details recent LBB precedents for Turkey Point, Surry, and Vogtle (References 4 through 7), which demonstrate acceptance of LBB evaluations without thermal aging of stainless steel welds. See also response to Request 3 (below) regarding Revision 0 versus Revision 1 of NUREG-6428. The Westinghouse LBB methodology for Point Beach Units 1 and 2, with respect to thermal aging of piping and weld materials, is consistent with recent .license renewal applications (References 4, 5, and 7, .as discussed in response to Request 1).
- 3. As noted in response to Request 1, the stainless steel weld thermal aging evaluations for the Point Beach Units 1 and 2 auxiliary piping systems were performed by the NRC Staff during the initial review in 2000 for WCAP-15065-P (Reference 1), WCAP-15105-P (Reference 2), and WCAP-15107-P (Reference 3). I Per Section 4.1 of the SE Rs attached to each LBB report, the Staff justifies the use of the unaged lower-bound J-R curve from NUREG-6428 as appropriate for evaluating thermal aging:
" ...lower bound J-R curve used by the staff was actually developed by Wilkowski and Ghadiali at Batte/le Columbus Laboratory as a fit to unaged [emphasis added] SS weld data, but the conclusions of Reference 3 [NUREG-6428, Revision O] noted that there was little observed change in the fracture toughness behavior with thermal aging for those welds that began with inferior fracture toughness properties."
The unaged and aged lower-bound J-R curve equations are not updated between Revision 0 and Revision 1 of NUREG-6428 (see equations below). The only update in Revision 1 of NUREG-6428 is to provide the standard power law curve fit equations for both unaged and aged J-R curves (see discussion in Section 3.2.3
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 4.7.2-1 L-2021-172 Attachment 1 Page 5 of 7 and Figure 3-13 and Figure 3-14 of NUREG-6428, Revision 1). As discussed above, only the unaged lower-bound fracture toughness curve was used per the justification given above for the NRC Staff review and approval of the LBB lines.
Unaged lower bound fracture toughness:
j (::!z) = 73.4 + 83.5 Lla(mm) 0 643 Equation (3) in NUREG-6428 Revision 0, Equation (18) in NUREG-6428 Revision 1 j(kj /m 2 ) = 138 Lla(mm)D.4 5 Equation (19) in NUREG-6428 Revision 1 Aged fracture toughness:
j(kj /m 2 ) = 40 + 83.5 Lla(mm) 0 *6 4 3 Equation (4) in NUREG-6428 Revision 0, Equation (21) in NUREG-6428 Revision 1 j(kj /m 2 ) = 117 Lla(mm)D.4 5 Equation (22) in NUREG-6428 Revision 1 As discussed in Section 3.2.3 and Figure 3-13 and Figure 3-14 of NUREG-6428, Revision 1, the thermal aging correlations in NUREG-6428 Revision 1 remain the same as Revision 0. Thus, the conclusions in the original SERs of WCAP-15065-P-A (Reference 1), WCAP-15105-P-A (Reference 2), and WCAP-15107-P-A (Reference 3) are still applicable to the SLR LBB evaluations . The NRC Staff review for the current 80-year application should be consistent and remain unchanged from the original review of these LBB lines since the NUREG-6428 Revision 0 had already provided both the unaged and aged correlations for stainless steel welds.
As justified in WCAP-15065-P-A (Reference 1), WCAP-15105-P-A (Reference 2),
and WCAP-15107-P-A (Reference 3), fracture mechanics evaluations for LBB are primarily based on a limit load evaluation methodology (with applied Z-factor to account for reduced toughness of SMAW/SAW welds), considering the tensile properties of the base metal, which are more limiting than the tensile properties of the weld material.
- 4.
- Thermal aging of stainless steel welds was not considered for the RCL piping of Point Beach Units 1 and 2 in WCAP-14439-P, Revision 4. This is consistent with all past (and current) Westinghouse LBB evaluations for RCL piping. As noted in the response to Request item 1, SERs for Turkey Point Units 3 and 4 (Reference 4), Surry Units 1 and 2 (Reference 5), and Vogtle Units 1 and 2 (Reference 7) provide examples of prior approvals that do not evaluate thermal aging of stainless steel weld materials for the RCL piping systems. Specifically, for the Surry SER (Section 4.7.3.2.2 of Reference 5), the Staff accepted that the aged fracture
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 4.7.2-1 L-2021-172 Attachment 1 Page 6 of 7 toughness of the wrought and cast stainless steel base metal is more limiting than that of the stainless steel weld metal. Likewise, the SER for first License Renewal for Point Beach Units 1 and 2 (Reference 10, Section 4.4.4 for RCL piping LBB) does not consider thermal aging of stainless steel weld materials.
Consistent with the response for Request item 2, the evaluation of LBB for the RCL piping is based on guidance from NUREG-1801 (Reference 8) and NUREG-2191 (Reference 9). Again, these references endorse addressing thermal aging of CASS base metals for piping systems, but do not recognize thermal aging of stainless steel welds nor do these references mention NUREG-6428.
The RCL fracture mechanics evaluations, supporting LBB, are based on either a limit load evaluation methodology (with welding process Z-factors) considering the limiting tensile properties of the base 1J1etal, or an Elastic Plastic Fracture Mechanics (EPFM) evaluation considering the thermally aged CASS base metal properties.
Summary and Conclusions The subject of this RAI is specific to the thermal aging of stainless steel welds. The responses, herein, show that the Westinghouse analyses for Leak-Before-Break of the Point Beach RCL and auxiliary piping systems do not consider thermal aging of stainless steel weld materials. Precedents for LBB applications at Turkey Point, Surry, and Vogtle (References 4 through 7) demonstrate recent acceptance of LBB evaluations without thermal aging of stainless steel welds. Furthermore, basis
- documents; GALL (Reference 8), GALL-SLR (Reference 9), and current ISGs do not specifically recognize thermal aging of stainless steel welds.
The research into thermal aging of stainless steel welds, documented in NUREG-6428, has not changed significantly. Material testing data and lower bound fracture toughness J-R curves are consistent between Revision 0 (1996) and Revision 1 (2018) of NUREG-6428. With no change to the lower bound fracture toughness, the original Staff review and approval of the Point Beach auxiliary line LBB evaluations remains applicable for the 80-year SPEO.
The Point Beach LBB analyses of the RCL and auxiliary piping systems are consistent with industry guidance and recent precedents. These evaluations remain applicable for .
the 80-year SPEO.
References:
- 1. Westinghouse Report, WCAP-15065-P-A Revision 1, "Technical Justification for Eliminating Pressurizer Surge Line Rupture as the Structural Design Basis for Point Beach Units 1 and 2 Nuclear Plants," June 2001
- 2. Westinghouse Report, WCAP-15105-P-A Revision 1, "Technical Justification for Eliminating Residual Heat Removal (RHR) Rupture as the Structural Design Basis for Point Beach Units 1 and 2 Nuclear Plants," June 2001
Point Beach Nuclear Plant Units 1 and 2 Dockets 5Q-266 and 50-301 NEPB Response to NRC RAI No. 4.7.2-1 L-2021-172 Attachment 1 Page 7 of 7
- 3. Westinghouse Report, WCAP-15107-P-A Revision 1, "Technical Justification for Eliminating Accumulator Rupture as the Structural Design Basis for Point Beach Units 1 and 2 Nuclear Plants," June 2001
- 4. U.S. NRC, "Safety Evaluation Report Related to the Subsequent License Renewal of Turkey Point Generating Units 3 and 4," December 2019 (ADAM Accession Number ML19191A057)
- 5. U.S. NRC, "Safety Evaluation Report Related to the Subsequent License Renewal of Surry Power Station, Units 1 and 2," March 2020 (ADAM Accession Number ML20052F520)
- 6. U.S. NRC, "Surry Power Station, Units 1 and 2 - Issuance of Amendment Nos.
304 and 304 Re: Leak-Before-Break for Pressurizer Surge, Residual Heat Removal, Safety Injection Accumulator, Reactor Coolant System Bypass and Safety Injection Lines," August 20, 2021 (ADAMS Accession Number ML21175A185)
- 7. U.S. NRC, "Safety Evaluation Report Related to the License Renewal of Vogtle Electric Generating Plant, Units 1 and 2," Volume 2, April 2009 (ADAMS Accession Number ML091320236)
- 8. U.S. NRC , NUREG-1801, Revision 2, "Generic Aging Lessons Learned (GALL)
Report - Final Report, " December 2010 (ADAMS Accession Number ML103490041)
- 9. U.S. NRC, NUREG-2191, Volume 2, "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report- Final Report," July 2017(ADAMS Accession Number ML17187A204)
- 10. U.S. NRC , NUREG-1839, "Safety Evaluation Report Related to the License Renewal of the Point Beach Nuclear Plant, Units 1 and 2," December 2005 (ADAMS Accession Number ML053420137)
Associated SLRA Revisions:
None.
Associated
Enclosures:
None.