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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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Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 0 February 4, 2008 L-2008-014 F=PL 10 CFR 50.4 10CFR 50.55a U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Inservice Inspection Plan Third Ten-Year Interval Unit 1 Relief Request 30 Pursuant to 10CFR 50.55a (a)(3)(i), Florida Power and Light Company (FPL) requests approval to implement an alternative to the requirements of Appendix VIII, Supplement 2, as referenced by Supplement 3, within ASME Section XI, 1995 Edition with the 1996 Addenda as required by 10CFR50.55a by providing alternative qualification requirements for UT of ferritic RCS welds from the ID.
The automated ultrasonic techniques to be utilized for the examinations of the Reactor Coolant piping from the ID will have been qualified by demonstration in accordance with the requirements of Appendix VIII, Supplement 3, of the 1995 Edition with Addenda through 1996 of ASME Section XI and proposed alternatives by the Performance Demonstration Initiative (PDI). The use of techniques qualified from the inside surface provides assurance that the Reactor Coolant piping welds have remained free of service related flaws thus enhancing quality and ensuring plant safety and reliability.
Please contact Ken Frehafer at (772) 467-7748 if there are any questions about this submittal.
Very
- ly yours, Gardon L. Johnston Site Vice President St. Lucie Plant Attachment GLJ/KWF an FPL Group company
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 1 of 13 Third Inservice Inspection Interval Relief Request Number 30 Proposed Alternative In Accordance with 10 CFR 50.55a (a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
"Alternative Qualification Requirements for UT of Ferritic RCS Welds from the ID"
- 1. ASME Code Component(s) Affected Class 1 Reactor Coolant System (RCS) welds subject to Ultrasonic (UT) examination from the inside surface (ID).
2. Applicable Code Edition and Addenda
The code of record for the St. Lucie Unit 1 third 10-year inservice inspection interval is the 1989 Edition, no Addenda, of the American Society of Mechanical Engineers (ASME) Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components." 10CFR50.55a requires that "Licensees implementing the 1989 Edition and earlier Editions and Addenda of IWA-2232 of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code must implement the 1995 Edition with the 1996 Addenda of Appendix VIII and the Supplements to Appendix VIII of Section Xl, Division 1, of the ASME Boiler and Pressure Vessel Code."
3. Applicable Code Requirement
Pursuant to 10CFR 50.55a (a)(3)(i), Florida Power and Light Company (FPL) requests approval to implement an'alternative to the requirements of Appendix VIII, Supplement 2, as referenced by Supplement 3, within ASME Section XI, 1995 Edition with the1996 Addenda as required by 10CFR50.55a.
Exam ItmExaminationiDsrpii Cat. No. ~
B-J B9. 11 Essentially 100% volumetric examination of the pressure (R-A) (R1.11) retaining welds in piping in accordance with Figure IWB-2500-8 Code Case N-524 & Risk Informed Program, Essentially 100%
B-J B9.12 volumetric examination required for those portions of the welds (R-A) within the examination boundaries of the intersecting circumferential welds
4. Reason for Request
UT examinations are performed from the inside surface of the RPV outlet nozzle-to-extension and extension-to-pipe and inlet nozzle-to extension and extension-to-elbow welds in accordance with the requirements of 10CFR50.55a, plant
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 2 of 13 Third Inservice Inspection Interval Relief Request Number 30 Technical Specifications, and the 1989 Edition, no Addenda of the ASME Section XI Code. 10CFR50.55a requires the UT equipment, procedures, and personnel to be qualified by performance demonstration in accordance with Appendix VIII of the 1995 Edition with the 1996 Addenda of ASME Section Xl Code. Appendix VIII, Supplement 2, as referenced by Supplement 3, paragraph 2.0 requires that the inside surface be concealed. This is not possible for demonstrations performed from the ID. The 2002 Addenda of ASME Section XI provided additional guidance for the conduct of demonstration activities when performed from the ID. However, 10CFR50.55a specifically prohibits the use of Appendix VIII and the Supplements to Appendix VIII and Article 1-3000 of Section XI of the ASME BPV Code, 2002 Addenda through the latest Edition and Addenda.
- 5. Proposed Alternative and Basis for Use Proposed Alternative:
Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested to implement the alternative paragraphs in Attachment 1 to the requirements of ASME Section XI, Appendix VIII, Supplement 2, as referenced by Supplement 3, of the 1995 Edition with the 1996 Addenda.
Basis for Use:
St. Lucie Unit 1 reactor coolant piping consists of nominal 42 inch ID, 3 3/16 inch minimum thick, hot leg piping and 30 inch ID, 3 inch minimum thick, cold leg elbows attached to the RPV nozzle safe-ends which are fabricated from carbon steel mill cladded with stainless steel. Examinations are performed from the inside surface of the piping.
The examinations of these welds are performed in conjunction with the 10-year RPV examinations from the inside surface using automated Ultrasonic examination techniques qualified in accordance with ASME Section XI, Appendix VIII, Supplement 3. The qualification requirements provided in ASME Section Xl, Supplement 2, as referenced by Supplement 3, do not provide allowances for demonstrations performed from the inside surface of the piping.
Prior to the issuance of the 2002 Addenda of ASME Section XI, the Performance Demonstration Initiative (PDI) administered demonstrations activities for ID examinations in accordance with Supplement 3 as modified by the PDI instructions. The PDI worked with the ASME Code to provide clarification of the intent of Section XI when demonstrations and examinations of carbon steel piping welds were to be performed from the ID. The result was the 2002 Addenda of ASME Section XI which provided additional guidance for the conduct of demonstration activities when performed from the ID. However, 10CFR50.55a specifically prohibits the use of Appendix VIII and the Supplements to Appendix VIII and Article 1-3000 of Section XI of the ASME BPV Code, 2002 Addenda
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 3 of 13 Third Inservice Inspection Interval Relief Request Number 30 through the latest Edition and Addenda. FPL's contractor, AREVA, qualified by demonstration from the ID, in accordance with PDI's implementation of Supplement 3, which is consistent with the requirements described in the 2002 Addenda of ASME Section Xl, Appendix VIII.
The automated ultrasonic techniques to be utilized for the examinations of the Reactor Coolant piping from the ID will have been qualified by demonstration in accordance with the requirements of Appendix VIII, Supplement 3, of the 1995 Edition with Addenda through 1996 of ASME Section XI and proposed alternatives by the Performance Demonstration Initiative (PDI). The use of techniques qualified from the inside surface provides assurance that the Reactor Coolant piping welds have remained free of service related flaws thus enhancing quality and ensuring plant safety and reliability.
- 6. Duration of Proposed Alternative FPL will implement the proposed alternative UT examinations from the inside surface of the RPV outlet nozzle-to-extension and extension-to-pipe and inlet nozzle-to extension and extension-to-elbow welds during the St. Lucie Unit 1 third 10-year Inservice Inspection interval.
- 7. Attachments to Relief Request 30 Attachment 1-Comparison of ASME Section XI, 1995 Edition with Addenda through 1996 and FPL alternatives
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 4 of 13 Third Inservice Inspection Interval Relief Request Number 30 "1u
,U *I"I::LC*I MI:* r_.W*UIMr_~-lNI:E Ia Qualificationtest specimens shall meet the requirements listed herein, unless a set of specimens is designed to accommodate specific limitations stated in the scope of the examination procedure (e.g., pipe size, access limitations). The same specimens may be used to demonstrate both detection and sizing qualification.
1.1 General. 1.1 General No Change The specimen set shall conform to the following Applicable to ferritic piping welds examined requirements. from either the inside (I.D.) or outside (O.D.) surface. The applicable qualification criteria shall be satisfied separately. The specimen set shall conform to the following requirements.
(a) Specimens shall have sufficient volume to No Change No Change minimize spurious reflections that may interfere with the interpretation process.
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 5 of 13 Third Inservice Inspection Interval Relief Request Number 30 (13) I ne specimen set snaii consist OT at least Tour (0) i ne specimen set snaii consist oT at specimens having different nominal pipe diameters least four specimens having different and thicknesses. The set shall include pipe nominal pipe diameters and thicknesses.
specimens not thicker than 0.1 in. more than the The set shall include pipe specimens not minimum thickness, nor thinner than 1.0 in. less than thicker than 0.1 in. (2.5 mm) more than the the maximum thickness for which the examination minimum thickness, nor thinner than 1.0 in.
procedure is applicable. It shall include the minimum (25 mm) less than the maximum thickness and maximum pipe diameters and thicknesses for for which the examination procedure is which the examination procedure is applicable. If the applicable. It shall include the minimum, procedure is applicable to pipe diameters of 24 in. within NPS 1/2, and maximum pipe (610 mm) or larger, the specimen set must include at diameter for which the examination least one specimen 24 in. (610 mm) or larger in procedure is applicable. If the procedure is diameter but need not include the maximum applicable to pipe O.D. of 24 in. (610 mm) diameter. or larger, the specimen set must include at least one specimen 24 in. O.D. (610 mm) or larger but need not include the maximum diameter (c) The specimen set shall include examples of the (c)Taking into consideration the accessible No Change following fabrication condition: scanning surface, the O.D. or I.D. specimen (1) unground weld reinforcement (crowns); set shall include applicable examples of the following fabrication conditions:
(1)unground weld reinforcement (crowns);
(2) wide crowns, such that the total crown width is 1 No Change No Change 1/2 to 2 times the nominal pipe wall thickness;
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 6 of 13 Third Inservice Inspection Interval Relief Request Number 30 ASME SectionX1, 1995 withAdenda through 1096 FLPooe Alenav 10CFRSO. 55a ch~ange (Supplement 2 with Sy ppposen Alternative r, reggirem en (3) geometric conditions that normally require (3)geometric conditions that normally No Change discrimination from flaws (e.g., counterbore, weld require discrimination from flaws (e.g.
root conditions such as excessive I.D. counterbore, weld root conditions such as reinforcement); excessive 1.D. reinforcement for O. D.
scans, or O.D. reinforcement for I.D. scans, as applicable);
(4) typical limited scanning surface conditions (e.g., (4)typical limited scanning surface No Change diametrical shrink, single-side access due to safe conditions (e.g. diametrical shrink, single-ends or fittings). side access due to safe ends or fittings, clad surfaces, or counterbore within the scanning area, as applicable).
(d) All flaws in the specimen set shall be cracks. No Change No Change (1) Mechanical fatigue cracks and thermal fatigue cracks shall be used. At least 75% of the sample set defects shall be mechanically or thermally induced fatigue cracks.
(2) At least 50% of the cracks shall be coincident with No Change No Change fabricated conditions described in (c) above.
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 7 of 13 Third Inservice Inspection Interval Relief Request Number 30
~AS E~Scti~~Xff9~5wit~Addnd~ hrouh I 96wFPL Proposed Alternative ~g
__(up leient 2 with Si~p Jement_3 inserted) ,- --- requiiremen~t~
1.2 Detection Specimens. The specimen set shall No Change No Change include detection specimens that meet the following requirements.
(a) Specimens shall be divided into grading units.
Each grading unit shall include at least 3 in. (76 mm) of weld length. If a grading unit is designed to be unflawed, at least 1 in. (25 mm) of unflawed material shall exist on either side of the grading unit. The segment of weld length used in one grading unit shall not be used in another grading unit. Grading units need not be uniformly spaced around the pipe specimen.
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 8 of 13 Third Inservice Inspection Interval Relief Request Number 30 NO unange NO unange
.i flF PERFC est ritera KNo. of U111ts Crft
<5 10O 12
-' 14 ~<
7 2<
'2 7
10'
'7'11' 24
-12 ;3-3.
13 10 26 . *:.. .4 10, K28 5' 11 .303
- 16. 12 < 3,2 17 12 is18 13 "K7' 19 13 38 20 40. el
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 9 of 13 Third Inservice Inspection Interval Relief Request Number 30 (b) Detection sets shall be selected from Table (L4tLJtL*LIULI bUl eIJUI I IbumIlI qudilIIlLIUI 1
VIIIS2-1. The number of unflawed grading units shall shall be selected from Table VIII-S2-1. The be at least twice the number of flawed grading units. number of unflawed grading units shall be at least twice the number of flawed grading units. For initial procedure qualification, detection sets shall include the equivalent of three personnel qualification sets. To qualify new values of essential variables, at least one personnel qualification set is required.
(c) Flawed grading units shall meet the following No Change No Change criteria for flaw depth, orientation, and type.
(1) A minimum of 1/3 of the flaws, rounded to the next higher whole number, shall have depths between 5% and 30% of the nominal pipe wall thickness. At least 1/3 of the flaws, rounded to the next higher whole number, shall have depths greater than 30% of the nominal pipe wall thickness.
(2) At least one and a maximum of 10% of the flaws, No Change No Change rounded to the next higher whole number, shall be oriented axially. The remainder of the flaws shall be oriented circumferentially.
(3) Service-induced flaws shall be included when No Change No Change available.
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 10 of 13 Third Inservice Inspection Interval Relief Request Number 30 1.S bizing bpecimens. I ne specimen set snaii 1.j stizing bpecimens. i ne specimen set iNJo .nange contain sizing specimens that meet the following shall contain sizing specimens that meet requirements. the following requirements.
(a) The minimum number of flaws shall be ten. (a)The minimum number of flaws shall be ten. For initial procedure qualification, sizing sets shall include the equivalent of three personnel qualification sets. To qualify new values of essential variables at least one personnel qualification set is required.
(b) Flaws in length sizing sample sets shall meet the No Change No Change requirements of para 1.2(c)(1), when given in conjunction with a detection test. When the length sizing test is administered independently, the flaw depth requirements do not apply.
(c) Flaws in the depth sizing sample set shall be No Change No Change distributed as follows:
Flaxro Depth Minlimumif (14 Wall ckness) Number ofFlw 5-30%200%
The remaining flaws shall be in any of the above categories.
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment
.Page 11 of 13 Third Inservice Inspection Interval Relief Request Number 30 Z.U ;UNUU; I UI- I"1-UIVMANL;I Z.u LUUNUUL I Ur r-'-UIKMANUL.
DEMONSTRATIONS DEMONSTRATIONS The specimen inside surface and identification shall When scanning from the O.D., the be concealed from the candidate. All examinations specimen inside surface and identification shall be completed prior to grading the results and shall be concealed from the candidate.
presenting the results to the candidate. Divulgence of When scanning from the I.D., flaw location particular specimen results or candidate viewing of and specimen identification shall be unmasked specimens after the performance obscured to maintain a "blind test". All demonstration is prohibited. examinations shall be completed prior to grading the results and presenting the results to the candidate. Divulgence of particular specimen results or candidate viewing of unmasked specimens after the performance demonstration is prohibited.
2.1 Detection Test. Flawed and unflawed grading No change No Change units shall be randomly mixed.
2.2 Length and Depth Sizing Test 2.2Length and Depth Sizing Test No Change (a) For the length sizing test, the regions of each (a)Each reported flaw in the detection test specimen containing a flaw to be sized shall be shall be length sized. When only length identified to the candidate. The candidate shall sizing is being tested, the regions of each determine the length of the flaw in each region. specimen containing a flaw to be sized may be identified to the candidate. The candidate shall determine the length of the flaw in each region.
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 12 of 13 Third Inservice Inspection Interval Relief Request Number 30 (b) For the depth sizing test, 80% of the flaws shall (U) IIie uUpmi sizirgy test [fay DUe peirmur[ieu be sized at a specific location on the surface of the in conjunction with or separate from the specimen identified to the candidate. For the detection test. When only depth sizing is remaining flaws, the regions of each specimen being tested, the regions of each specimen containing a flaw to be sized shall be identified to the containing a flaw to be sized may be candidate. The candidate shall determine the identified to the candidate. The candidate maximum depth of the flaw in each region. shall determine the maximum depth of the flaw in each region.
3.0 ACCEPTANCE CRITERIA 3.OACCEPTANCE CRITERIA No Change 3.1 Detection Acceptance Criteria. Examination 3.1 Detection Acceptance procedures, (a)Personnel demonstration shall meet the equipment, and personnel are qualified for detection requirements of Table VIII-S2-1 for both when the results of the performance demonstration detection and false calls.
satisfy the acceptance criteria of Table VIIIS2-1 for (b)Procedure qualifications shall both detection and false calls. demonstrate detectability of each flaw within the scope of the procedure.
Successful personnel demonstrations may be combined to satisfy the requirements for procedure qualification.
3.2 Sizing Acceptance Criteria. Examination No Change No Change procedures, equipment, and personnel are qualified for sizing if the results of the performance demonstration satisfy the following criteria:
(a) The RMS error of the flaw lengths estimated by ultrasonics, as compared with the true lengths, shall not exceed 0.75 in. (19 mm);
St. Lucie Unit 1 L-2008-014 Docket No. 50-335 Attachment Page 13 of 13 Third Inservice Inspection Interval Relief Request Number 30 ASME Secation 1995 withrAdendathrough 19966 1' cheng FPL Pooe lentv (Supplement 2with Suplement 3 inserted) ICrequirement~a (b) The RMS error of the flaw depths estimated by No Change No Change ultrasonics, as compared with the true depths, shall not exceed 0.125 in. (3.2 mm).
SUPPLEMENT 3 - QUALIFICATION No Change No Change REQUIREMENTS FOR FERRITIC PIPING WELDS Qualification of examination procedures, equipment, and personnel for ferritic pipe examination shall be accomplished by satisfying the requirements of Supplement 2, except that the sample material shall be ferritic and 75% of the sample set defects shall be mechanically or thermally induced fatigue cracks. In addition, the set shall include pipe specimens not thicker than 0.1 in. (2.5 mm) more than the minimum thickness, nor thinner than 1.0 in. (25 mm) less than the maximum thickness for which the examination procedure is applicable.