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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-2022-048, Submittal of Refueling Outage SL2-26 Steam Generator Tube Inspection Report2022-03-21021 March 2022 Submittal of Refueling Outage SL2-26 Steam Generator Tube Inspection Report L-2021-220, Submittal of In-Service Inspection Program ISI Fourth Interval - Third Period SL2-26 Owner'S Activity Report (OAR-1)2021-12-27027 December 2021 Submittal of In-Service Inspection Program ISI Fourth Interval - Third Period SL2-26 Owner'S Activity Report (OAR-1) 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 L-2021-112, In-Service Inspection Program, ISI Fifth Interval - First Period SL1-30, Owner'S Activity Report (OAR-1)2021-08-13013 August 2021 In-Service Inspection Program, ISI Fifth Interval - First Period SL1-30, Owner'S Activity Report (OAR-1) L-2020-030, In-Service Inspection Program ISI Fifth Interval - First Period SL1-29 Owner'S Activity Report (OAR-1)2020-02-18018 February 2020 In-Service Inspection Program ISI Fifth Interval - First Period SL1-29 Owner'S Activity Report (OAR-1) L-2020-025, Unit 2 ISI 4th Interval Relief Request 17, Proposed Alternative to Use ASME Code Case N-513-42020-02-0707 February 2020 Unit 2 ISI 4th Interval Relief Request 17, Proposed Alternative to Use ASME Code Case N-513-4 L-2018-239, In-Service Inspection Program ISI Fourth Interval - Second Period - SL2-24 Refueling Outage Owner'S Activity Report (OAR-1)2018-12-28028 December 2018 In-Service Inspection Program ISI Fourth Interval - Second Period - SL2-24 Refueling Outage Owner'S Activity Report (OAR-1) L-2018-135, In-Service Inspection Program, ISI Fourth Interval- Third Period; Fifth Interval- First Period; SL1-28 Owner'S Activity Report (OAR-1)2018-07-0909 July 2018 In-Service Inspection Program, ISI Fourth Interval- Third Period; Fifth Interval- First Period; SL1-28 Owner'S Activity Report (OAR-1) L-2018-110, Submittal of Fifth Ten-Year Inservice Inspection Interval ISI Program Plan, Revision 02018-05-0202 May 2018 Submittal of Fifth Ten-Year Inservice Inspection Interval ISI Program Plan, Revision 0 L-2018-069, Fifth 10-Year Interval - Inservice Testing (1ST) Program Plan2018-03-30030 March 2018 Fifth 10-Year Interval - Inservice Testing (1ST) Program Plan L-2018-042, Snubber Program Plan Submittal for Fifth 10-Year Inservice Testing Interval2018-02-0909 February 2018 Snubber Program Plan Submittal for Fifth 10-Year Inservice Testing Interval L-2017-152, Refueling Outage SL2-23, Steam Generator Tube Inspection Report2017-09-13013 September 2017 Refueling Outage SL2-23, Steam Generator Tube Inspection Report L-2017-070, Refueling Outage SL1-27 Steam Generator Tube Inspection Report2017-04-27027 April 2017 Refueling Outage SL1-27 Steam Generator Tube Inspection Report L-2017-019, Submittal of In-Service Inspection Program, ISI Fourth Interval- Third Period- SL1-27, Owner'S Activity Report (OAR-1)2017-02-0606 February 2017 Submittal of In-Service Inspection Program, ISI Fourth Interval- Third Period- SL1-27, Owner'S Activity Report (OAR-1) L-2017-017, Inservice Inspection Plan, Fourth Ten-Year Unit 1 Relief Request No. 14, Revision 02017-02-0202 February 2017 Inservice Inspection Plan, Fourth Ten-Year Unit 1 Relief Request No. 14, Revision 0 L-2016-088, Report of 10 CFR 50.59 Plant Changes - Docket No. 50-3892016-04-19019 April 2016 Report of 10 CFR 50.59 Plant Changes - Docket No. 50-389 L-2016-089, Refueling Outage SL2-22, Steam Generator Tube Inspection Report2016-04-15015 April 2016 Refueling Outage SL2-22, Steam Generator Tube Inspection Report ML16076A4312016-03-0707 March 2016 St. Lucie, Unit 2, In-Service Inspection Plans Fourth Ten-Year Interval Relief Request 11 L-2016-015, In-Service Inspection Program, ISI Fourth Interval - First Period - SL2-22 Refueling Outage, Owner'S Activity Report (OAR-1)2016-01-21021 January 2016 In-Service Inspection Program, ISI Fourth Interval - First Period - SL2-22 Refueling Outage, Owner'S Activity Report (OAR-1) L-2015-204, In-Service Inspection Program, ISI Fourth Interval - Third Period - SL1-26, Owner'S Activity Report (OAR-1)2015-07-22022 July 2015 In-Service Inspection Program, ISI Fourth Interval - Third Period - SL1-26, Owner'S Activity Report (OAR-1) L-2015-126, License Renewal One-Time Inspection of Class 1 Small Bore Piping Revised Commitments and Revised Inspection Plan2015-05-11011 May 2015 License Renewal One-Time Inspection of Class 1 Small Bore Piping Revised Commitments and Revised Inspection Plan L-2015-063, In-Service Inspection Plans Fourth Ten-Year Interval Unit 2 Relief Request 2 RAI Reply2015-03-0505 March 2015 In-Service Inspection Plans Fourth Ten-Year Interval Unit 2 Relief Request 2 RAI Reply L-2014-360, Inservice Inspection Plan Fourth Ten-Year Interval Relief Request No. 9, Revision 02014-12-0303 December 2014 Inservice Inspection Plan Fourth Ten-Year Interval Relief Request No. 9, Revision 0 L-2014-339, Inservice Inspection Plan - RAI Reply - Third Ten-Year Interval Unit 2 Relief Request No. 142014-11-0303 November 2014 Inservice Inspection Plan - RAI Reply - Third Ten-Year Interval Unit 2 Relief Request No. 14 L-2014-331, TS Correction for Fourth Ten-Year Inservice Inspection Interval License Amendment Request Changes to Snubber Surveillance Requirements2014-10-23023 October 2014 TS Correction for Fourth Ten-Year Inservice Inspection Interval License Amendment Request Changes to Snubber Surveillance Requirements L-2014-277, Inservice Inspection Plan, RAI Reply - Third Ten-Year Interval Unit 2 Relief Request No. 172014-08-28028 August 2014 Inservice Inspection Plan, RAI Reply - Third Ten-Year Interval Unit 2 Relief Request No. 17 L-2014-224, In-Service Inspection Program ISI Fourth Interval - First Period - SL2-21 Refueling Outage Owner'S Activity Report (OAR-l)2014-07-17017 July 2014 In-Service Inspection Program ISI Fourth Interval - First Period - SL2-21 Refueling Outage Owner'S Activity Report (OAR-l) L-2014-206, Third Ten-Year Interval Unit 2 Relief Request No. 142014-06-30030 June 2014 Third Ten-Year Interval Unit 2 Relief Request No. 14 L-2014-208, Third Ten-Year Interval Unit 2 Relief Request No. 172014-06-30030 June 2014 Third Ten-Year Interval Unit 2 Relief Request No. 17 L-2014-113, Refueling Outage SL 1-25, Steam Generator Tube Inspection Special Report2014-04-29029 April 2014 Refueling Outage SL 1-25, Steam Generator Tube Inspection Special Report L-2014-039, Submittal of In-Service Inspection Program ISI Fourth Interval - Second Period - SLI-25 Owner'S Activity Report (OAR-I)2014-02-0606 February 2014 Submittal of In-Service Inspection Program ISI Fourth Interval - Second Period - SLI-25 Owner'S Activity Report (OAR-I) L-2014-027, Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements2014-01-30030 January 2014 Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements L-2013-240, Fourth Ten-Year Interval, Relief Request No. 7, Rev. 02013-08-0505 August 2013 Fourth Ten-Year Interval, Relief Request No. 7, Rev. 0 L-2013-063, In-Service Inspection Program ISI Third Interval - Third Period - Second Outage (SL2-20) Owner'S Activity Report (OAR-1)2013-02-20020 February 2013 In-Service Inspection Program ISI Third Interval - Third Period - Second Outage (SL2-20) Owner'S Activity Report (OAR-1) L-2013-066, Third Ten-Year Interval Unit 2 Relief Request No. 9, Revision 02013-02-13013 February 2013 Third Ten-Year Interval Unit 2 Relief Request No. 9, Revision 0 L-2013-044, Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 5, Revision 02013-02-0404 February 2013 Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 5, Revision 0 L-2012-301, In-Service Inspection Program, ISI Fourth Interval - Second Period - SLI-24 Owner'S Activity Report (OAR-1)2012-07-20020 July 2012 In-Service Inspection Program, ISI Fourth Interval - Second Period - SLI-24 Owner'S Activity Report (OAR-1) L-2010-207, Fourth Ten-Year Interval Relief Request PR-92010-09-14014 September 2010 Fourth Ten-Year Interval Relief Request PR-9 L-2010-202, In-Service Inspection Program, ISI Fourth Interval - First Period - Second Outage (SL1-23), Owner'S Activity Report, (OAR-1)2010-09-0101 September 2010 In-Service Inspection Program, ISI Fourth Interval - First Period - Second Outage (SL1-23), Owner'S Activity Report, (OAR-1) L-2009-183, Submittal of In-Service Inspection Program, ISI Third Interval - Second Period - Second Outage (SL2-18) Owner'S Activity Report (OAR- 1)2009-08-14014 August 2009 Submittal of In-Service Inspection Program, ISI Third Interval - Second Period - Second Outage (SL2-18) Owner'S Activity Report (OAR- 1) L-2009-168, Response to Request for Additional Information, Third Interval Relief Request 312009-07-20020 July 2009 Response to Request for Additional Information, Third Interval Relief Request 31 L-2009-091, Steam Generator Tube Inspection Report2009-04-13013 April 2009 Steam Generator Tube Inspection Report L-2009-036, In-Service Inspection Program Fourth Interval - First Period Owner'S Activity Report (OAR-1) Submittal2009-02-0909 February 2009 In-Service Inspection Program Fourth Interval - First Period Owner'S Activity Report (OAR-1) Submittal L-2008-253, Inservice Inspection Plans, Unit 1 Fourth Inspection Interval RR 4, and Unit 2 Third Inspection Interval RR 112008-12-0303 December 2008 Inservice Inspection Plans, Unit 1 Fourth Inspection Interval RR 4, and Unit 2 Third Inspection Interval RR 11 L-2008-158, Submittal of In-Service Inspection Program Third Interval - Third Period Owner'S Activity Report for SL1-20 and SL1-21 Outages2008-07-21021 July 2008 Submittal of In-Service Inspection Program Third Interval - Third Period Owner'S Activity Report for SL1-20 and SL1-21 Outages L-2008-098, In-Service Inspection Plans, Submittal for the Use of Structural Weld Overlays as an Alternative Repair Technique, Fourth Ten-Year Interval Unit 1 Relief Request 22008-04-29029 April 2008 In-Service Inspection Plans, Submittal for the Use of Structural Weld Overlays as an Alternative Repair Technique, Fourth Ten-Year Interval Unit 1 Relief Request 2 L-2008-067, In-Service Inspection Program, Third Interval - Second Period - First Outage (SL2-17) Owner'S Activity Report (OAR-1)2008-03-26026 March 2008 In-Service Inspection Program, Third Interval - Second Period - First Outage (SL2-17) Owner'S Activity Report (OAR-1) L-2008-043, Fourth Ten-Year Inservice Inspection Interval ISI Program Plan - Revision 02008-03-13013 March 2008 Fourth Ten-Year Inservice Inspection Interval ISI Program Plan - Revision 0 L-2008-014, Inservice Inspection Plan, Third Ten-Year Interval Unit 1 Relief Request 302008-02-0404 February 2008 Inservice Inspection Plan, Third Ten-Year Interval Unit 1 Relief Request 30 L-2007-172, In-Service Inspection Plans Response to Request for Additional Information Re Third Ten-Year Interval Unit 2 Relief Request 102007-10-24024 October 2007 In-Service Inspection Plans Response to Request for Additional Information Re Third Ten-Year Interval Unit 2 Relief Request 10 2022-03-21
[Table view] Category:Letter type:L
MONTHYEARL-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-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, 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-2023-114, 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-2023-099, 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-2023-102, 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-2023-097, 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) 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-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update 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-2023-059, 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-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes 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-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant 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 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-2023-025, 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-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality 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-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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-2022-165, 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-2022-160, 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 2024-01-08
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0 May 11, 2015 FPL. L-2015-126 10 CFR 54 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 2055-0001 St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 License Renewal One-Time Inspection of Class 1 Small Bore Piping Revised Commitments and Revised Inspection Plan
References:
- 1. Safety Evaluation Report Related to the License Renewal o f St. Lucie Nuclear Plant, Units 1 and 2, NUREG-1779, September 2003.
- 2. Generic Aging Lessons Learned (GALL) Report, NUREG-1801, Rev. 2, December 2010.
- 3. FPL Letter L-2014-059, License Renewal One-Time Inspection of Class I Small Bore Piping Revised Commitments, dated March 19, 2014.
- 4. FPL Letter L-2014-265, License Renewal One-Time Inspection of Class 1 Small Bore Piping Inspection Plan Submittal, dated September 3, 2014.
- 5. EPRI MRP Letter to the NRC, No. MRP-2008-054, St. Lucie Unit 1 Retired PZR Safety "A" Nozzle DM Weld Destructive Examination Report, dated August 15, 2008.
The purpose of this letter is to update the Nuclear Regulatory Commission (NRC) that FPL has revised the commitments to inspect the butt welds in small bore piping by destructive examination, if an opportunity presents itself.
Florida Power and Light Company (FPL) has License Renewal (LR) commitments for St.
Lucie Units 1 and 2 to perform a one-time inspection of Class 1 Small Bore Piping prior to the end of the initial operating license term. Specifically, for St. Lucie Unit 1, Commitment 7 listed in Appendix D, Table 1 of Reference 1 and for St. Lucie Unit 2, Commitment 6 listed in Appendix D, Table 2 of Reference 1; state that volumetric inspections of a sample of small bore Class I piping will be performed prior to the end of the initial operating license term.
In accordance with Reference (3), FPL revised these commitments such that this one-time inspection will follow the guidance provided in the Generic Aging Lessons Learned (GALL)
Report, NUREG-1801, Rev 2, Section AMP XI.M35, "One-Time Inspection of ASME Code Class I Small-Bore Piping" (Reference 2). Specifically, as identified above, Commitment 7 for St. Lucie Unit 1 and Commitment 6 for St. Lucie Unit 2 were revised to clarify that based on the guidance provided in the GALL Report, a destructive examination may be performed in lieu of volumetric examination for socket welds.
Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
L-2015-126 Page 2 of 2 GALL Report Revision 2 states that for butt welds, for a one time inspection to detect cracking resulting from thermal and mechanical loading or inter-granular stress corrosion of full penetration welds (butt welds), volumetric examination should be performed. The option of using the destructive examination, if an opportunity presents itself, was not specified for butt welds in the GALL Report.
St. Lucie Unit I has recently completed refueling outage SLI-26, and has completed the examination of the butt welds and socket welds in small bore piping. As a result of installing a modification for replacing a valve, a section of small bore piping was removed which contains a butt weld, which has presented a unique opportunity to perform destructive examination of a butt weld as part of the small bore piping examination. Therefore, FPL is submitting to the NRC (a) a revised commitment change (Attachment 1) and (b) a revised small bore inspection plan (Attachment 2).
Destructive Examination (DE) provides more information on the potentially developing cracks than a volumetric examination. DE is useful in the determination of a specific flaw mechanism, if a flaw is present in the weld. This has been proven previously, when a DE was performed on the retired pressurizer safety valve from St. Lucie Unit 1 during the pressurizer replacement. The destructive evaluation confirmed the indications and flaws found within the retired pressurizer safety "A" nozzle were fabrication defects with no evidence of PWSCC. The flaws were also confirmed to be non-safety significant and did not challenge the structural integrity of the component (Reference 5).
The revised commitments and inspection plan are provided herein in Attachments 1 and 2, respectively.
Should you have any questions, please contact Mr. Eric Katzman, Licensing Manager, at 772-467-7734.
Very truly yours, Christopher Costanzo Site Vice President St. Lucie Plant Attachments
L-2015-126 Attachment 1 Page 1 of 1 St. Lucie Unit 1 and Unit 2 License Renewal Revised Commitments Outstanding Commitments (Reference I , Appendix D, Table 1 and Table 2)
St. Lucie Unit 1 Table 1 Commitment 7 St. Lucie Unit 2 Table 2 Commitment 6 A volumetric inspection of a sample of small bore Class I piping and nozzles will be performed Revised Commitments St. Lucie Unit 1 Table I Commitment 7 St. Lucie Unit 2 Table 2 Commitment 6
- 1. A volumetric inspection of a sample of small bore Class 1 piping and nozzles will be performed. Based on the guidance provided in the GALL Report, Section AMP XI.M35, a destructive examination may be performed in lieu of the volumetric examination.
For each socket weld that is destructively examined credit may be taken as being equivalent to volumetrically examining two socket welds. This one-time inspection will address Class I piping less than 4 inches nominal pipe size (less than NPS 4) and greater than or equal to NPS 1.
- 2. A destructive examination may be performed on a butt weld instead of volumetric examination, if an opportunity presents itself.
Reference Documents:
- 1. Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units I and 2, NUREG-1779, September 2003.
- 2. Generic Aging Lessons Learned (GALL) Report, NUREG-1801, Rev. 2, December 2010.
L-2015-126 Attachment 2 Page 1 of 5 St. Lucie Unit 1 ASME Code Class 1 Small-Bore Piping One Time Inspection Plan, Revision 1
L-2015-126 Attachment 2 Page 2 of 5 Plan Description This plan augments the requirements in American Society of Mechanical Engineers (ASME) Code,Section XI, 1998 edition with Addenda through 2000, and is applicable to small-bore ASME Code Class I piping and systems less than 4 inches nominal pipe size (less than NPS 4) and greater than or equal to NPS 1. The plan includes pipes, fittings, branch connections, and all full and partial penetration (socket) welds. This plan was developed using the Generic Aging Lessons Learned (GALL) Report, NUREG-1801, Rev.
2 XI.M35; One-Time Inspection of ASME Code Classl Small-Bore Piping as guidance.
A one-time inspection to detect cracking resulting from thermal and mechanical loading, vibration, or intergranular stress corrosion of full penetration welds will be performed by volumetric o r destructive examination. A one-time inspection to detect cracking in socket welds will be performed by either volumetric or destructive examination. The number of welds to be examined will be on a sample basis as described in Section 4 of this plan. The sample of welds to be examined will be selected using the risk-informed approach as approved by the NRC for St. Lucie Nuclear Plant, Units No. 1 and 2 -Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. I (TAC NO. MD7739)
These inspections will provide additional assurance that either aging of small-bore ASME Code Class I piping is not occurring or the aging is insignificant, such that a plant-specific Aging Management Program (AMP) is not warranted. Should evidence of cracking be revealed by the one-time inspection, a periodic inspection plan will be developed and implemented using a plant-specific AMP.
A search of the St. Lucie Corrective Action system and the ASME Section XI, Repair and Replacement Reports over the operating history of St. Lucie Unit 1 was performed to determine if any ASME Code Class 1 Small-Bore Piping greater than or equal to NPS 1 and less than NPS 4 had experienced cracking. No instance of cracking of ASME Code Class 1 Small-Bore Piping greater than or equal to NPS I and less than NPS 4 was identified.
Evaluation and Technical Basis
- 1. Scope of Plan: This plan is a one-time inspection of a sample of ASME Code Class I piping less than NPS 4 and greater or equal to NPS 1. This plan includes measures to verify that degradation is not occurring, thereby confirming that there is no need to manage age-related degradation. The one-time inspection plan for ASME Code Class 1 small-bore piping includes locations that are susceptible to cracking. The sample of welds will be selected using the risk-informed approach as approved by the NRC for St.
Lucie Nuclear Plant, Unit No. I - Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. 1 (TAC NO. MD7739).
L-2015-126 Attachment 2 Page 3 of 5 All ASME Class I pipe segments less than 4-inch NPS and greater than equal to 1-inch NPS have the same Low Safety Significance Risk Ranking and, as such, all welds were given the same level of consideration.
- 2. Preventive Actions: This plan is a condition monitoring activity independent of methods to mitigate or prevent degradation.
- 3. Parameters Monitored/Inspected: This inspection is intended to detect potential cracking in ASME Code Class 1 small-bore piping.
- 4. Description of Aging Effects.- This one-time inspection is designed to provide assurance that aging of ASME Code Class 1 small-bore piping is not occurring, or that the effects of aging are not significant. The one-time inspection to detect cracking in socket welds will be either a volumetric or destructive examination. The inspection to detect cracking resulting from thermal and mechanical loading, vibration, or intergranular stress corrosion of full penetration welds will be a volumetric or destructive examination. Volumetric examination will be performed using demonstrated techniques from the ASME Code that are capable of detecting the aging effects in the examination volume of interest. The inspection will be performed at a sufficient number of locations to ensure an adequate sample. This number, or sample size, is based on susceptibility, accessibility, dose considerations, operating experience, and limiting locations of the total population of ASME Code Class I small-bore piping inspections.
The inspection sample size will be at least 3%, up to a maximum of 10 welds, of each weld type, for each operating unit using a methodology to select the most susceptible and risk-significant welds from the risk-informed approach as described above. For socket welds, destructive examination may be performed in lieu of volumetric examinations. Because more information can be obtained from a destructive examination than from nondestructive examination, credit will be taken for each weld destructively examined equivalent to having volumetrically examined two welds.
L-2015-126 Attachment 2 Page 4 of 5 St. Lucie Unit I Weld Type Approx. 3% Sample Size Number (Max 10 Welds Each Type)
I Volumetric OR Destructive Socket 493 15 N/A 5 (NPS-2 and smaller)
Full Penetration 92 3 3 (Greater than NPS-2 and less Less any See Note 1 than NPS-4) destructive Note(s)
- 1) A destructive examination may be performed on a butt weld instead of volumetric examination, if an opportunity presents itself.
Destructive Examination (DE) provides more information on the potentially developing cracks than a volumetric examination. DE is useful in a determination of a specific flaw mechanism, if a flaw is present in the weld. This has been proven previously, when a DE was performed on the retired pressurizer nozzles from St. Lucie Unit 1 pressurizer. (Ref.
EPRI Letter MRP 2008-053, "St. Lucie Unit 1 Retired PZR Safety "A" Nozzle DM Weld Destructive Examination Report, ML0824480225).
- 5. Monitoring and Trending: This is a one-time inspection to determine whether cracking in ASME Code Class 1 small-bore piping resulting from stress corrosion, cyclical (including thermal, mechanical, and vibration fatigue) loading, or thermal stratification and thermal turbulence (MRP 146 and MRP 146S) is an issue. Evaluation of the inspection results may indicate the need for additional or periodic examinations (i.e., a plant-specific AMP for Class I small-bore piping using volumetric inspection methods consistent with ASME Code,Section XI, Subsection IWB).
- 6. Acceptance Criteria: If flaws or indications exceed the acceptance criteria of ASME Code,Section XI, Paragraph IWB-3400, they are evaluated in accordance with ASME Code,Section XI, Paragraph IWB-3131; additional inspections are performed in accordance with ASME Code,Section XI, Paragraph IWB-2430. Evaluation of flaws
L-2015-126 Attachment 2 Page 5 of 5 identified during a volumetric examination of socket welds will be in accordance with IWB-3600.
- 7. Corrective Actions: The site corrective action program, quality assurance procedures, site review and approval process, and administrative controls are implemented in accordance with the requirements of 10 CFR Part 50, Appendix B. Should evidence of cracking be revealed by the one-time inspection, a periodic inspection will be developed and implemented, using a plant-specific AMP.
- 8. Confirmation Process: The requirements of 10 CFR Part 50, Appendix B are used to address the confirmation process.
- 9. Administrative Controls: The requirements of 10 CFR Part 50, Appendix B are used to address the administrative controls.
- 10. Operating Experience: This one-time inspection plan uses volumetric inspection techniques with demonstrated capability and a proven industry record and/or destructive examinations to detect cracking in piping partial penetration welds and base material.
Currently, an industry proven volumetric technique for detection, sizing and performing analytical evaluation of flaws in socket welds has not been established; therefore, a destructive examination will be performed.
EPRI Letter MRP 2008-053, "St. Lucie Unit I Retired PZR Safety "A" Nozzle DM Weld Destructive Examination Report, (ML0824480225) shows that destructive examination of full penetrations welds yield results which may be used to validate NDE. As such, destructive examination may be used on full penetration butt welds.