Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: L-2021-063, Subsequent License Renewal Application Notification, L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report, L-2022-108, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response, L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4, ML21215A316, ML21285A107, ML21351A238, ML21351A239, ML21351A241, ML21351A248, ML21354A837, ML21356A011, ML22010A094, ML22010A096, ML22010A097, ML22010A100, ML22012A263, ML22012A282, ML22012A391, ML22013A277, ML22013A282, ML22013A284, ML22013A288, ML22013A292, ML22013A293, ML22013A294, ML22013A295, ML22013A296, ML22013A297, ML22013A301, ML22013A302, ML22013A303, ML22013A304, ML22013A305, ML22013A307, ML22013A316, ML22013A317, ML22013A334, ML22188A086, ML23200A123
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MONTHYEARL-2021-064, Request for Exemption from the Schedular Requirements of 10 CFR 54.17 (C)2021-03-17017 March 2021 Request for Exemption from the Schedular Requirements of 10 CFR 54.17 (C) Project stage: Request L-2021-063, Subsequent License Renewal Application Notification2021-03-17017 March 2021 Subsequent License Renewal Application Notification Project stage: Other ML21215A3192021-08-0303 August 2021 Appendix E - Applicant'S Environmental Report for St. Lucie Project stage: Request ML21215A3152021-08-0303 August 2021 Application for Subsequent Renewed Facility Operating Licenses Project stage: Request ML21215A3162021-08-0303 August 2021 Enclosure 1: Subsequent License Renewal Application Enclosures Summary Project stage: Other ML21215A3172021-08-0303 August 2021 Enclosure 2: Affidavits Supporting Withholding Proprietary Information from Public Disclosure Project stage: Request L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report2021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report Project stage: Other ML21285A1072021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1 Project stage: Other L-2021-209, Refueling Outage SL1-30 Steam Generator Tube Inspection Report2021-11-0101 November 2021 Refueling Outage SL1-30 Steam Generator Tube Inspection Report Project stage: Request ML22013A2772021-11-21021 November 2021 2.4 Structural Scoping and Screening Breakout Questions Project stage: Other ML21356A0112021-12-17017 December 2021 Trp 148.3 and 148.4 St Lucie SLRA Breakout Questions Project stage: Other ML21351A2482021-12-17017 December 2021 Trp 26 St. Lucie SLRA - Fire Protection Breakout Questions Project stage: Other ML21351A2412021-12-17017 December 2021 Trp 15 St. Lucie SLRA - Internal Coatings Breakout Questions - Allik Project stage: Other ML21351A2392021-12-17017 December 2021 Trp 14 St. Lucie SLRA - Buried Pipe Breakout Questions - Allik.Docx Project stage: Other ML21351A2382021-12-17017 December 2021 Trp 148.1 St. Lucie SLRA - Breakout Questions for TLAA Section 4.7.1 Rev. 1 Project stage: Other ML21354A8372021-12-20020 December 2021 Trp 11 St. Lucie SLRA Breakout Questions Project stage: Other ML22013A2922021-12-21021 December 2021 Trp 41 St. Lucie SLRA - Breakout Questions Project stage: Other ML22013A2822021-12-21021 December 2021 SLRA - Breakoutt Questions Corrosion OE Project stage: Other ML22013A2842021-12-21021 December 2021 Trp 18 St. Lucie SLRA - Breakout Questions Bolting Integrity Project stage: Other ML22013A2882021-12-21021 December 2021 Trp 23 & 147.8 St. Lucie SLRA - Breakout Questions Cranes AMP-TLAA Project stage: Other ML22013A2932021-12-21021 December 2021 Trp 45 St. Lucie SLRA - Breakout Questions Masonry Walls Project stage: Other ML22013A2942021-12-21021 December 2021 Trp 46 St. Lucie SLRA - Breakout Questions Structures Monitoring Project stage: Other ML22013A2952021-12-21021 December 2021 Trp 47 St. Lucie SLRA - Breakout Questions Project stage: Other ML22013A2962021-12-21021 December 2021 Trp 74 St. Lucie SLRA - Breakout Questions Project stage: Other ML22013A2972021-12-21021 December 2021 Trp 77 St. Lucie SLRA - Breakout Questions Corrosion Structural Project stage: Other ML22013A3012021-12-21021 December 2021 TRP60 St. Lucie SLRA - Breakout Questions Fatigue Monitoring Project stage: Other ML22013A3022021-12-21021 December 2021 Trp 143.1 St Lucie SLRA - Breakout Questions Class 1 Fatigue Project stage: Other ML22013A3032021-12-21021 December 2021 Trp 143.2 St Lucie SLRA - Breakout Questions Non-Class 1 Fatigue Project stage: Other ML22013A3042021-12-21021 December 2021 Trp 143.3 St Lucie SLRA - Breakout Questions EAF Project stage: Other ML22013A3052021-12-21021 December 2021 Trp 143.4 St Lucie SLRA - Breakout Questions HELB Project stage: Other ML21356A5772021-12-22022 December 2021 Slar Breakout Questions - Fire Protection Scoping and Screening Project stage: Approval ML22010A0942022-01-0404 January 2022 Trp 29 St. Lucie SLRA - Tank Breakout Project stage: Other ML22010A0962022-01-0505 January 2022 Trp 010 St Lucie SLRA - Boricacidcorrbreakoutq - Makar Project stage: Other ML22010A0972022-01-0707 January 2022 Trp 038 Psl Internal Surfaces Breakout Questions - Allik Project stage: Other ML22010A1002022-01-0707 January 2022 Trp 033 Psl Selective Leaching Breakout Questions - Allik Project stage: Other ML22012A2632022-01-10010 January 2022 Trp 3 - St. Lucie Psl SLRA Breakout Question Reactor Head Closure Stud Bolting Project stage: Other ML22012A2822022-01-10010 January 2022 TRP142- St. Lucie SLRA Section 4.2 - Breakout Questions Project stage: Other ML22013A3342022-01-11011 January 2022 TRP16 - St. Lucie SLRA Breakout Questions_Pwr Internals Project stage: Other ML22130A6542022-01-11011 January 2022, 21 January 2022 SLRA - Audit Report - Audit Questions Transmitted to Florida Power & Light (FPL) Project stage: Request ML22013A3072022-01-11011 January 2022 Trp 084 St Lucie SLRA - Ssnial Scclombreakoutq Project stage: Other ML22012A3912022-01-11011 January 2022 Scoping and Screening 2.3.3.2 & 2.3.3.4 St. Lucie SLRA - Breakout Questions Project stage: Other ML22013A3162022-01-12012 January 2022 Trp 020 - St. Lucie SLRA Breakout Questions_Occw Project stage: Other ML22013A3172022-01-12012 January 2022 Trp 030 - St. Lucie SLRA Breakout Questions_Fuel Oil Project stage: Other L-2022-044, Subsequent License Renewal Application Revision 1, Supplement 22022-04-13013 April 2022 Subsequent License Renewal Application Revision 1, Supplement 2 Project stage: Supplement L-2022-071, Subsequent License Renewal Application Revision 1 - Supplement 32022-05-19019 May 2022 Subsequent License Renewal Application Revision 1 - Supplement 3 Project stage: Supplement L-2022-075, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response2022-06-13013 June 2022 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response Project stage: Request ML22188A0862022-07-0707 July 2022 SLRA - Audit Report Project stage: Other L-2022-108, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response2022-07-11011 July 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response Project stage: Other L-2022-154, Subsequent License Renewal Application Revision 1, Supplement 42022-09-22022 September 2022 Subsequent License Renewal Application Revision 1, Supplement 4 Project stage: Supplement L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response Project stage: Request 2022-01-11
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Category:Letter type:L
MONTHYEARL-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review L-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-011, 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 Applications2024-03-13013 March 2024 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-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules 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-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump 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-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 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-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report 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-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) 2024-08-07
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes 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-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 ML23013A2032023-01-13013 January 2023 RAI Set 4 Draft Response L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-156, Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response2022-09-19019 September 2022 Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response L-2022-143, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response2022-09-0808 September 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response L-2022-115, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment2022-08-0909 August 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment L-2022-108, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response2022-07-11011 July 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response L-2022-075, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response2022-06-13013 June 2022 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response2022-01-19019 January 2022 License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response L-2021-105, Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2021-05-12012 May 2021 Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2021-065, Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years2021-04-0101 April 2021 Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years L-2020-165, Supplement to Updated Final Response to NRC Generic Letter 2004-022020-12-0404 December 2020 Supplement to Updated Final Response to NRC Generic Letter 2004-02 L-2020-094, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2020-06-26026 June 2020 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2020-061, Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2020-04-30030 April 2020 Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements ML20015A0282020-01-14014 January 2020 NMFS to NRC, Concurrence with Interim Response to Requests for Additional Information for St. Lucie Endangered Species Act Section 7 Consultation L-2019-164, Response to Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Protection Bypass Devices Requirements to Licensee Control2019-09-11011 September 2019 Response to Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Protection Bypass Devices Requirements to Licensee Control L-2019-166, Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response2019-08-21021 August 2019 Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response L-2019-153, Exigent Technical Specification Amendment Request Supplemental RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-25025 July 2019 Exigent Technical Specification Amendment Request Supplemental RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-149, Exigent Technical Specification Amendment Request RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-24024 July 2019 Exigent Technical Specification Amendment Request RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-118, Response to Request for Additional Information Regarding License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2019-06-28028 June 2019 Response to Request for Additional Information Regarding License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2019-107, License Amendment Request - Iodine Removal System Elimination2019-05-17017 May 2019 License Amendment Request - Iodine Removal System Elimination L-2019-056, Inservice Inspection Plan RAI Reply, Fifth Ten-Year Interval Unit 1 Relief Request2019-03-0707 March 2019 Inservice Inspection Plan RAI Reply, Fifth Ten-Year Interval Unit 1 Relief Request L-2018-205, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies2018-11-15015 November 2018 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-153, Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies2018-08-17017 August 2018 Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies L-16-001, Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-24024 May 2018 Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. 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 L-77-291, Attachment a to L-77-291 Response to NRC Questions of May 24, 19772018-03-29029 March 2018 Attachment a to L-77-291 Response to NRC Questions of May 24, 1977 L-2018-040, Response to Request for Additional Information Regarding License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2018-02-14014 February 2018 Response to Request for Additional Information Regarding License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply L-2018-006, Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b2018-02-0101 February 2018 Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b L-2017-210, Updated Final Response to NRC Generic Letter 2004-022017-12-20020 December 2017 Updated Final Response to NRC Generic Letter 2004-02 L-2017-216, License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 62017-12-19019 December 2017 License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 6 L-2017-209, Response to Request for Additional Information Regarding Fifth 10-Year Inservice Testing (IST) Program Interval Relief Request PR-012017-11-30030 November 2017 Response to Request for Additional Information Regarding Fifth 10-Year Inservice Testing (IST) Program Interval Relief Request PR-01 L-2017-159, Response to Request for Additional Information Regarding Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 3, Revision 02017-09-13013 September 2017 Response to Request for Additional Information Regarding Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 3, Revision 0 L-2017-116, Response to Request for Additional Information Regarding License Amendment Request to Revise the Technical Specifications (TS) for the Reactor Protection System (RPS) Power Rate-of-Change Instrumentation and Add New TS 3.0.52017-07-0303 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise the Technical Specifications (TS) for the Reactor Protection System (RPS) Power Rate-of-Change Instrumentation and Add New TS 3.0.5 L-2016-220, License Amendment Request EDG Day Tank Fuel Volume Change2016-12-0505 December 2016 License Amendment Request EDG Day Tank Fuel Volume Change 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) L-2016-153, Response to Request for Additional Information Regarding License Amendment Request for Biological Opinion License Changes2016-08-11011 August 2016 Response to Request for Additional Information Regarding License Amendment Request for Biological Opinion License Changes L-2016-135, Second Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B2016-07-22022 July 2016 Second Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B L-2016-143, Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents2016-07-15015 July 2016 Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents L-2016-114, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 48.2016-07-0808 July 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 48. L-2016-102, RAI Reply - License Amendment Request, Containment Vacuum Gothic Analyses and Conforming Changes2016-05-0606 May 2016 RAI Reply - License Amendment Request, Containment Vacuum Gothic Analyses and Conforming Changes L-2016-104, RAI Reply - Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle2016-05-0606 May 2016 RAI Reply - Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle L-2016-096, Inservice Inspection Plan, RAI Reply for Fourth Ten-Year Interval Relief Request No. 10, Revision 02016-04-21021 April 2016 Inservice Inspection Plan, RAI Reply for Fourth Ten-Year Interval Relief Request No. 10, Revision 0 2024-06-26
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October 26, 2022 L-2022-165 10 CFR 54.17 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11545 Rockville Pike One White Flint North Rockville, MD 20852-2746 St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 Renewed Facility Operating Licenses DPR-67 and NPF-16 SUBSEQUENT LICENSE RENEWAL APPLICATION - AGING MANAGEMENT REQUEST FOR ADDITIONAL INFORMATION (RAI) 4.3.1-1a SECOND ROUND) - CLASS 1 FATIGUE RESPONSE
References:
1. FPL Letter L-2021-192 dated October 12, 2021 - Subsequent License Renewal Application -
Revision 1 (ADAMS Accession No. ML21285A107) 2. FPL Letter L-2022-043 dated April 7, 2022 - Subsequent License Renewal Application Revision 1 - Supplement 1 (ADAMS Accession No. ML22097A202) 3. FPL Letter L-2022-044 dated April 13, 2022 - Subsequent License Renewal Application Revision 1 - Supplement 2 (ADAMS Accession No. ML22103A014) 4. FPL Letter L-2022-071 dated May 19, 2022 - Subsequent License Renewal Application Revision 1 - Supplement 3 (ADAMS Accession No. ML22139A083) 5. NRC Email and Attachment dated May 12, 2022, St. Lucie SLRA - Request for Additional Information Set #1 (FINAL) (ADAMS Accession Nos. ML22133A002, ML22133A003) 6. NRC Email and Attachment dated May 26, 2022, St. Lucie SLRA RCI Set 1 Final (ADAMS Accession Nos. ML22147A086, ML22147A087) 7. FPL Letter L-2022-075 dated June 13, 2022 - Subsequent License Renewal Application -
Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response (ADAMS Accession No. ML22164A802) 8. FPL Letter L-2022-081 dated June 30, 2022 - Subsequent License Renewal Application -
Aging Management Requests for Additional Information (RAI) Set 1B Response (ADAMS Accession No. ML22181A147) 9. FPL Letter L-2022-154 dated September 22, 2022 - Subsequent License Renewal Application Revision 1 - Supplement 4 (ADAMS Accession No. ML22265A134) 10.NRC Email and Attachment dated September 26, 2022, St. Lucie SLRA - Request for Additional Information (Second Round #2 - Class ) (ADAMS Accession Nos.
ML22270A148, ML22270A149)
Florida Power & Light Company
15430 Endeavor Drive, Jupiter, FL 33478
St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2022-165 l Page 2 of 2 Florida Power & Light Company (FPL), owner and licensee for St. Lucie Nuclear Plant (PSL) Units 1 and 2, has submitted a revised and supplemented subsequent license renewal application (SLRA) for the Facility Operating Licenses for PSL Units 1 and 2 (References 1-4). Based on the NRCs review of the SLRA, the NRC issued its Set 1 RAIs and RCI to FPL (References 5 and 6).
References 7 and 8 provided responses to the RAIs and RCI with additional clarifying information provided in Reference 9. Upon review of these responses, the NRC requested additional information regarding the response to RAI 4.3.1-1a in Reference 10. The attachment to this letter provides the requested additional information in response to RAI 4.3.1-1a.
The attachment includes associated revisions to the SLRA (Enclosure 3 Attachment 1 of Reference 1, as supplemented by References 2 - 4) denoted by strikethrough (deletion) and/or bold red underline (insertion) text. Previous SLRA revisions are denoted by bold black text. SLRA table revisions are included as excerpts from each affected table.
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 26TH day of October 2022.
Sincerely, William Digitally signed by William Maher DN: cn=William Maher, o=Nuclear, ou=Nuclear Licensing Projects, Maher email=william.maher@fpl.com, c=US Date: 2022.10.26 09:19:50 -04'00' William D. Maher Licensing Director - Nuclear Licensing Projects Florida Power & Light Company
Attachment:
PSL Response to NRC RAI No. 4.3.1-1a Cc: Regional Administrator, USNRC, Region II Senior Resident Inspector, USNRC, St. Lucie Plant Chief, USNRC, Division of New and Renewed Licenses Senior Project Manager, USNRC, Division of New and Renewed Licenses Chief, Bureau of Radiation Control, Florida Department of Health
St. Lucie Units 1 and 2 Dockets 50-335 and 50-389 PSL Response to NRC RAI No. 4.3.1-1a L-2022-165 Attachment 1 Page 1 of 8 Metal Fatigue of Class 1 Components RAI 4.3.1-1a Regulatory Basis:
Pursuant to 10 CFR 54.21(c), the SLRA must include an evaluation of time-limited aging analyses (TLAAs). The applicant must demonstrate that (i) the analyses remain valid for the period of extended operation, (ii) the analyses have been projected to the end of the period of extended operation, or (iii) the effects of aging on the intended function(s) will be adequately managed for the period of extended operation.
Background:
In the June 30, 2022, response to RAI 4.3.1-1, the applicant explained that cycle counting is not performed on the following design transients of St. Lucie Unit 1: (1) low volume control and makeup; (2) cold feed following hot standby; (3) actuation of main or auxiliary spray; (4) low pressure safety injection, 40ºF water into 300ºF cold leg; (5) opening of safety injection return line valves; and (6) loss of feedwater flow (ADAMS Accession No. ML22181A147).
The applicant explained that cycle counting is not performed on these transients based on (1) the component CUF (cumulative usage factor) value associated with the transients is not greater than 0.1 or (2) if the CUF of an associated component is greater than 0.1, the contribution of each transient to the CUF is not greater than 0.1.
Issue:
The applicants response to RAI 4.3.1-1 does not clearly address how the applicant considered the combined effects of these transients on CUF in the determination of cycle counting exclusion. Multiple uncounted transients could cause combined contributions to the overall CUF of a component so that the fatigue monitoring may be ineffective.
In relation to this concern, the staff noted that the following reference describes the applicants CUF evaluation for the Class 1 components and reactor coolant system piping of St. Lucie Unit 1 (
Reference:
PSL-1FSC-01-005, Revision 1, Screening of ASME Class 1 Components for License Renewal TLAA Thermal Fatigue). The reference addresses the CUF contributions of limiting transients for each component, where a limiting transient is a transient contributing to the CUF of a component more than 0.1 and is also called a fatigue-sensitive transient.
The reference also indicates that the overall CUF contribution of non-limiting transients is in the range from 0.21 to 0.78 for the following Unit 1 components: (1) steam generator primary head at divider seat bar; (2) pressurizer bottom head support skirt; (3) surge line resistance temperature detector (RDT) nozzle; and (4) surge line sample nozzle. The staff is seeking clarification whether the non-limiting transients for these components include multiple uncounted transients.
St. Lucie Units 1 and 2 Dockets 50-335 and 50-389 PSL Response to NRC RAI No. 4.3.1-1a L-2022-165 Attachment 1 Page 2 of 8 Request:
Clarify whether two or more uncounted transients are included in the non-limiting transients for the following Unit 1 components: (1) steam generator primary head at divider seat bar; (2) pressurizer bottom head support skirt; (3) surge line RTD nozzle; and (4) surge line sample nozzle. If so, discuss why cycle counting is not needed for the transients even though multiple uncounted transients could cause combined contributions to the overall CUF of a component so that the fatigue monitoring may be ineffective.
PSL Response:
The response below provides clarification whether two or more uncounted transients are included in the non-limiting transients for the four PSL-1 RCS Class 1 component locations identified in the NRC request.
(1) Steam generator primary head at divider seat bar The supporting references in Reference 1 identify the following transients considered in the fatigue analysis for the steam generator primary head at divider seat bar.
Acceptable Transient Transient Disposition Disposition not Counted in Committed to for not Transients Evaluated to Count per SLRA Table Count per Counting for Fatigue Attachments 1 4.3.1-1 of Attachment 4 Provided and 3 of Reference 2 of Reference 3 Below Reference 3 Warmup* / Cooldown Y Plant Loading / Unloading Y 10% Step Load Increase /
Y Decrease Cold Feedwater Following Y
Hot Standby Normal Plant Variations Y Primary Coolant Pump Y
Start / Stop Reactor Trip** Y Loss of Primary Flow** Y Loss of Load** Y Operating Basis Y
Earthquake Primary Leak Test Y Secondary Leak Test Y
St. Lucie Units 1 and 2 Dockets 50-335 and 50-389 PSL Response to NRC RAI No. 4.3.1-1a L-2022-165 Attachment 1 Page 3 of 8 The total CUF at this component location is 0.957, of which 0.746 is due to Heatup /
Cooldown (0.606) and Warmup / Cooldown Lumped (Reactor Trip + Loss of Flow + Loss of Load = 0.14). A cumulative fatigue usage of 0.211, therefore, is associated with the remaining transients, which are discussed as follows:
Committed to count in SPEO x Plant Loading / Unloading (Note that very few plant loading and unloading transients have occurred to date at PSL-1 and PSL-2 as both units have historically been operated as base-loaded units. Since there is large margin between the actual transient counts to date and the design limit of 15,000 cycles, the plant loading and unloading transients are currently not counted during the 60-year PEO. However, this transient will be counted in the 80-year SPEO, as explained in Attachment 4 of Reference 3) x 10% Step Load Increase / Decrease (counted in the SPEO, per Attachment 4 of Reference 3) x Primary Leak Test (counted in the SPEO, per Table 4.3.1-1 of Reference 2) x Secondary Leak Test (counted in the SPEO, per Table 4.3.1-1 of Reference 2)
Acceptable disposition for not counting already established x Normal Plant Variations (acceptable not to count, per Attachment 1 of Reference 3) x Primary Coolant Pump Start / Stop (acceptable not to count, per Attachment 1 of Reference 3) x Operating Basis Earthquake (acceptable not to count, per Attachment 3 of Reference 3)
As discussed in the response to Attachment 1 of Reference 3, there are 1,000,000 Normal Plant Variations cycles, which is considered an infinite number. The Normal Plant Variations transient is considered in fatigue analyses to account for minor changes in pressure and temperature that by themselves do not contribute to fatigue usage. This transient provides conservatism in the calculated design CUF value.
As discussed in Section 4.7.4 of the SLRA (Reference 2), not more than 2,000 Reactor Coolant Pump Start / Stop cycles are conservatively projected through the SPEO based on 500 Heatup and Cooldown cycles. This provides a margin of at least 50% to the 4,000 cycles used in the design fatigue analysis. Since this transient does not contribute more than 0.1 to the CUF, the contribution would be not more than 0.05.
As also discussed in the responses presented in Attachments 1 and 3 of Reference 3, cycle monitoring is not required for the Operating Basis Earthquake due to the large projected cycle margin.
The only remaining transient to discuss is the Cold Feedwater Following Hot Standby transient. The margin between the projected 80-year transient cycles and design cycles for the counted transients in SLRA Table 4.3.1-1 (Reference 2) is 60% or greater. It is therefore reasonable to conclude that the number of Cold Feedwater Following Hot Standby
St. Lucie Units 1 and 2 Dockets 50-335 and 50-389 PSL Response to NRC RAI No. 4.3.1-1a L-2022-165 Attachment 1 Page 4 of 8 transient cycles in 80 years of operation will also be significantly less than the large number (15,000) of cycles used in the design analysis. As with the Reactor Coolant Pump Start /
Stop cycles, if a conservative margin of 50% is applied, this transient would contribute 0.05 to the CUF.
In summary, there are a total of four uncounted transients: Normal Plant Variations, Primary Coolant Pump Start / Stop, Operating Basis Earthquake and Cold Feedwater Following Hot Standby. The total contribution to the CUF from these uncounted transients is expected to be not more than 0.1 due to the significant margin between 80-year projections and cycles assumed in design fatigue calculations. This is consistent with the value of 0.1 used as a cutoff for any single fatigue-sensitive transient in SIR-01-102 (Reference 4) and confirms that the methodology utilized to determine which design transients require counting by the PSL Fatigue Monitoring AMP is acceptable and provides reasonable assurance that the effects of aging will be managed such that the intended function(s) of components within the scope of SLR will be maintained during the SPEO.
The above discussion justifying why cycle counting is not needed for any transients included in the non-limiting transients for the steam generator primary head at divider seat bar alleviates the concern that multiple uncounted transients could cause combined contributions to the overall CUF of the steam generator primary head at divider seat bar such that fatigue monitoring may be ineffective.
(2) Pressurizer bottom head support skirt The Reference 1 calculation provides the license renewal CUF evaluation for the original PSL-1 pressurizer component locations. The pressurizer bottom head support skirt component location is included in that CUF evaluation. However, as discussed in Section 4.3.1 of the PSL SLRA (Reference 2), the original PSL-1 pressurizer, including the bottom head support skirt, was replaced in 2005. Therefore, the CUF evaluation for the original pressurizer component locations in Reference 1 are no longer applicable and have been superseded by the fatigue analysis performed by Framatome for the replacement pressurizer.
To address this RAI, the CUF evaluation of the corresponding PSL-1 replacement pressurizer component location, which is referred to as the pressurizer head skirt connection, is provided in this response. The Framatome fatigue analysis for the replacement pressurizer head skirt connection limiting component location calculated an overall CUF value greater than 0.1. Since this overall CUF value exceeds the license renewal CUF screening criteria of 0.1, additional review is required to identify those transients that need to be counted by the PSL Fatigue Monitoring AMP. This review concludes that there are only two transients, plant heatup and plant cooldown, that provide a CUF contribution of greater than 0.1 to the overall CUF value. Therefore, these two transients require counting by the PSL Fatigue Monitoring AMP. The other transients included in the fatigue analysis for this limiting component location provide a total less than the license renewal CUF screening criteria of 0.1.
St. Lucie Units 1 and 2 Dockets 50-335 and 50-389 PSL Response to NRC RAI No. 4.3.1-1a L-2022-165 Attachment 1 Page 5 of 8 For completeness, the table below identifies all the transients included in the fatigue analysis for replacement pressurizer head skirt limiting component location:
Transient Transient Counted Committed to Transients Evaluated in Table 4.3.1-1 of Count per for Fatigue Reference 2 Attachment 4 of Reference 3 Heatup / Cooldown Y Plant Loading / Unloading Y Reactor Trip Y Leak Test Y The table above demonstrates that all transients included in the PSL-1 replacement pressurizer head skirt fatigue analysis will be counted by the PSL Fatigue Monitoring AMP during the SPEO, regardless of the magnitude of their CUF contributions. In addition, this review of the PSL-1 replacement pressurizer head skirt fatigue analysis confirms that there are no multiple uncounted transients that could cause combined contributions to the overall CUF of a component such that fatigue monitoring might be ineffective.
(3) Surge line RTD nozzle The Reference 1 supporting reference identifies both stratified and non-stratified transients evaluated for fatigue of the surge line RTD nozzle. Stratified transients consist of a defined set of transients that occur during Heatup and Cooldown at various differential temperatures between the pressurizer and hot leg, which are accounted for in counting the Heatup /
Cooldown transients and the Hot Standby 90°F transient, which is covered by the Cooldown transient per Table 2-1 of Reference 4.
The list of non-stratified transients is as follows:
Acceptable Transient Transient Disposition Disposition not Counted in Committed to for not Transients Evaluated to Count per SLRA Table Count per Counting for Fatigue Attachments 1 4.3.1-1 of Attachment 4 Provided and 3 of Reference 2 of Reference 3 Below Reference 3 Heatup / Cooldown Y Plant Loading / Unloading Y 10% Step Load Increase /
Y Decrease Reactor Trip Y Leak Test at Heatup /
Y Cooldown Normal Plant Variations Y Loss of Flow (Load) Y
St. Lucie Units 1 and 2 Dockets 50-335 and 50-389 PSL Response to NRC RAI No. 4.3.1-1a L-2022-165 Attachment 1 Page 6 of 8 Acceptable Transient Transient Disposition Disposition not Counted in Committed to for not Transients Evaluated to Count per SLRA Table Count per Counting for Fatigue Attachments 1 4.3.1-1 of Attachment 4 Provided and 3 of Reference 2 of Reference 3 Below Reference 3 Loss of Secondary Y
Pressure No Load
- Y Seismic (Operating Basis Y
Earthquake)
Although listed here as a transient, this is not a design transient and represents a static, zero load stress state (zero pressure and ambient conditions).
There are two uncounted transients: Normal Plant Variations and Operating Basis Earthquake. The No Load transient is not a loading condition; rather it is a static stress state used in fatigue analyses to account for transient cycles not otherwise paired in the fatigue table and provide conservatism in the calculated CUF value.
There are 1,000,000 Normal Plant Variations cycles, which is considered an infinite number.
The Normal Plant Variations transient is considered in fatigue analyses to account for minor changes in pressure and temperature that by themselves do not contribute to fatigue usage.
This transient provides conservatism in the calculated design CUF value.
The total CUF contribution (of the uncounted transients) is 0.027, which is below the value of 0.1 used as a cutoff for any single fatigue-sensitive transient in SIR-01-102 (Reference 4).
This confirms that the methodology utilized to determine which design transients require counting by the PSL Fatigue Monitoring AMP is acceptable and provides reasonable assurance that the effects of aging will be managed such that the intended function(s) of components within the scope of SLR will be maintained during the SPEO.
The above discussion justifying why cycle counting is not needed for any transients included in the non-limiting transients for the surge line RTD nozzle alleviates the concern that multiple uncounted transients could cause combined contributions to the overall CUF of the surge line RTD nozzle such that fatigue monitoring may be ineffective.
(4) Surge line sample nozzle The Reference 1 supporting reference identifies both stratified and non-stratified transients evaluated for fatigue of the surge line sample nozzle. Stratified transients consist of a defined set of transients that occur during Heatup and Cooldown at various differential temperatures between the pressurizer and hot leg, which are accounted for in counting the Heatup / Cooldown transients and the Hot Standby 90°F transient, which is covered by the Cooldown transient per Table 2-1 of Reference 4.
The list of non-stratified transients is as follows:
St. Lucie Units 1 and 2 Dockets 50-335 and 50-389 PSL Response to NRC RAI No. 4.3.1-1a L-2022-165 Attachment 1 Page 7 of 8 Acceptable Transient Transient Disposition Disposition not Counted in Committed to for not Transients Evaluated to Count per SLRA Table Count per Counting for Fatigue Attachments 1 4.3.1-1 of Attachment 4 Provided and 3 of Reference 2 of Reference 3 Below Reference 3 Heatup / Cooldown Y Plant Loading / Unloading Y 10% Step Load Increase /
Y Decrease Reactor Trip Y Leak Test at Heatup /
Y Cooldown Normal Plant Variations Y Loss of Flow (Load) Y Loss of Secondary Y
Pressure No Load
- Y Seismic (Operating Basis Y
Earthquake)
Although listed here as a transient, this is not a design transient and represents a static, zero load stress state (zero pressure and ambient conditions).
There are two uncounted transients: Normal Plant Variations and Operating Basis Earthquake. The No Load transient is not a loading condition; rather it is a static stress state used in fatigue analyses to account for transient cycles not otherwise paired in the fatigue table and provide conservatism in the calculated CUF value.
There are 1,000,000 Normal Plant Variations cycles, which is considered an infinite number.
The Normal Plant Variations transient is considered in fatigue analyses to account for minor changes in pressure and temperature that by themselves do not contribute to fatigue usage.
This transient provides conservatism in the calculated design CUF value.
The total CUF contribution (of the uncounted transients) is 0.098, which is below the value of 0.1 used as a cutoff for any single fatigue-sensitive transient in SIR-01-102 (Reference 4) and confirms that the methodology utilized to determine which design transients require counting by the PSL Fatigue Monitoring AMP is acceptable and provides reasonable assurance that the effects of aging will be managed such that the intended function(s) of components within the scope of SLR will be maintained during the SPEO.
The above discussion justifying why cycle counting is not needed for any transients included in the non-limiting transients for the surge line sample nozzle alleviates the concern that multiple uncounted transients could cause combined contributions to the overall CUF of the surge line sample nozzle such that the fatigue monitoring may be ineffective.
St. Lucie Units 1 and 2 Dockets 50-335 and 50-389 PSL Response to NRC RAI No. 4.3.1-1a L-2022-165 Attachment 1 Page 8 of 8
==
Conclusion:==
The evaluations above confirm that the methodology utilized to determine which design transients require counting by the PSL Unit 1 and 2 Fatigue Monitoring AMP is acceptable and provides reasonable assurance that the effects of aging will be managed such that the intended function(s) of components within the scope of SLR will be maintained during the SPEO.
References:
- 1. FPL Calculation No. PSL-1FSC-01-005, Revision 1, Screening of ASME Class 1 Components for License Renewal TLAA Thermal Fatigue, dated September 19, 2001
- 2. FPL Letter L-2021-192 dated October 12, 2021, Subsequent License Renewal Application - Revision 1 (ADAMS Accession No. ML21285A107)
- 3. FPL Letter L-2022-081 dated June 30, 2022, Subsequent License Renewal Application -
Aging Management Requests for Additional Information (RAI) Set 1B Response (ADAMS Accession No. ML22181A147)
- 4. Structural Integrity Associates Report No. SIR-01-102, Revision 3, Thermal Cycle Evaluation for St. Lucie Units 1 and 2, dated November 7, 2014 Associated SLRA Revisions:
None.
Associated
Enclosures:
None.