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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 July 20, 2009 F=PL L-2009-168 10 CFR 50.4 10 CFR 50.55a U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Response to Request for Additional Information Unit I Third Interval Relief Request 31 On February 6, 2009, FPL submitted relief request 31 for the St. Lucie Unit 1 Third ISI Interval.
The relief request dealt with the impracticality to meet the code required volume coverage of some welds in the reactor vessel as required by the ASME Code, 1989 Edition, no addenda, as clarified by Code Case N-460 due to configuration and/or the presence of permanent attachments. Relief is requested in accordance with 10CFR50.55a(g)(5)(iii). The NRC requested additional information via email that was subsequently posted in ADAMS as ML091590627.
The responses to the RAI questions are within Attachment 1. Attachment 2 contains the revised relief request.
Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant Attachments ESK/KWF an FPL Group company
-I St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 1 Page 1 of 2 2.1 Request for Relief 31, ASME Code,Section XI, Examination Category B-A, Items B 1.11, B1.12, B 1.21 and B1.22, Reactor Pressure Vessel Shell Welds and Bottom Head Welds The licensee's submittal states in section 6.0, Proposed Alternative and Basis for Use, first paragraph:
FPL [Florida Power and Light Company] performed inservice examinations of selected welds in accordance with the requirements of 10 CFR 50.55a, plant technical specifications, and the 1989 Edition, No Addenda, of the American Society of MechanicalEngineers (ASME) Boiler and Pressure Vessel Code, Section X1.
In the fourth paragraph of the same section, the licensee's submittal states:
FPL performed ultrasonic[(UT)] examinations of all reactor vessel welds in accordance with the requirements of 10 CFR 50.55a, plant technical specifications, and the 1995 Edition, No Addenda, of ASME [Code,] Section X1 to the maximum extent possible.
2.1.1 Please clarify which Edition and Addenda of the ASME Code,Section XI was used to examine the reactor pressure vessel (RPV) welds.
FPL Response: The typographical error has been corrected in the paragraph. FPL performed inservice examinations of selected welds in accordance with the requirements of 10CFR50.55a, plant technical specifications, and the 1989 Edition, No Addenda, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI. The 1995 Edition with Addenda through 1996 was utilized for ASME Section XI, Appendix VIII.
7 St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 1 Page 2 of 2 The licensee requested relief from examining 100% of the ASME Code-required volumes for RPV welds: Shell-to-Lower Shell Circumferential Weld (9-203), RPV Circumferential Bottom Head-to-Lower Shell Weld (10-203), RPV Upper Shell Longitudinal Seam Weld at 15 Degrees (1-203B) and RPV Lower Head Peel Segment Welds (204-03-A through F). The licensee has provided technical descriptions and sketches; however, it is unclear from the licensee's submittal how these appurtenances specifically limit the subject examinations. For example, the roll-out sketches do not provide dimensions and there is no description of the ultrasonic scanning apparatus, or any other details of the listed obstruction (e.g., size, shape, proximity to the weld, etc.).
2.1.2 Please submit further specific information to support the basis for each limited examination in Request for Relief 31, and therefore, demonstrate impracticality. Include descriptions (written and/or sketches, as necessary) of the interferences to applied nondestructive examination (NDE) techniques. As applicable, describe NDE equipment, show accessibility limitations, and discuss whether alternative methods or advanced technologies could be employed to maximize ASME Code coverage.
FPL Response: Figure 1 has been added which provides an illustration of the contact UT head used for scanning from the vessel shell. Additional figures have been added to provide the dimensions and locations of obstructions and views of each of the affected welds showing the interference caused by the permanent attachments on the TWS robot and the affect the obstructions had on scanning. The Ultrasonic (UT) techniques for each weld were reviewed to determine if additional coverage could be achieved. For the welds included in this relief request, it is not possible to remove the permanently attached obstructions to increase ASME Code coverage without significant work, increased radiation exposure, and/or damage to the plant.
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 1 of 20 St. Lucie Unit I THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 Relief Request In Accordance with 10 CFR50.55a(g)(5)(iii)
--Inservice Inspection Impracticality--
- 1. ASME Code Component(s) Affected Class 1 pressure retaining welds in the reactor pressure vessel (RPV).
- 2. Applicable Code Edition and Addenda The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Rules for Inservice Inspection of Nuclear Power Plant Components,Section XI, 1989 Edition, No Addenda. The 1995 Edition with Addenda through 1996 was utilized for ASME Section XI, Appendix VIII.
- 3. Applicable Code Requirement Cxat Item No. Examnin~ation Requirements B1.10 Essentially 100% volumetric examination of all B-A B1.11 longitudinal and circumferential shell welds (does not B13.12 include shell to flange weld).
B1.20 Essentially 100% volumetric examination of accessible
___ B1.22 length of circumferential and meridional head welds.
As defined by 10CFR50.55a(g)(6)(ii)(A)(2) and ASME Code Case N-460, essentially 100% means more than 90% of the examination volume of each weld where reduction in coverage is due to interference by another component or part geometry.
- 4. Impracticality of Compliance Due to the configuration of the Reactor Vessel, it is impractical to meet the examination coverage requirements of the ASME Code,Section XI, 1989 Edition, No Addenda, as clarified by Code Case N-460. Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iii). These areas were found during the 3rd 10-year inservice inspection interval.
When examined, the welds listed within this request did not receive the required code volume coverage due to their configuration and/or the presence of permanent attachments. These scanning limitations prohibit essentially 100% ultrasonic examination coverage of the required examination volume.
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 2 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION I Described below, coupled with figures, are details of the examination limitations by weld description. Figure 1 provides an illustration of the contact UT head used for scanning from the vessel shell. Figures 2 through 15 provide the dimensions and locations of obstructions and views of each of the affected welds showing the interference caused by the permanent attachments on the Trans World System (TWS) robot and the affect of the obstructions on scanning.
RPV Intermediate Shell-to-Lower Shell Circumferential Weld (9-203)
Examination Category B-A, Item B1.11 The examination of the Figure IWB-2500-2 A-B-C-D volume is limited due to the six surveillance capsule holders. Access to approximately 16.9% of the examination volume is restricted. The remaining examination volume was examined with techniques which have been qualified by demonstration in accordance with Supplements 4 & 6 of the 1995 Edition with Addenda through 1996 of the ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative Protocol. This weld was examined from both sides of the weld, scanning both parallel and perpendicular. These ultrasonic examinations did not reveal any recordable or reportable flaws in accordance with the ASME Code Section XI, 1989 Edition, No Addenda.
Figure 2 is a view of the TWS robot in the vessel shell region showing scan limitations caused by the six surveillance capsule holders. The weld is covered by the six surveillance capsule holders. Figure 3 provides dimensional information for the six surveillance capsule holders and their affect on scanning.
Figure 4 is a roll out view showing the reactor vessel inside surface scan areas (cross hatched) and the locations of limited areas due to the presence of the six surveillance capsule holders.
RPV Circumferential Bottom Head-to-Lower Shell Weld (10-203)
Examination Category B-A, Item B1.21 The examination of the Figure IWB-2500-3 A-B-C-D volume is limited due to the proximity of the Core Barrel Stabilizers and Core Lugs. Access to approximately 29.4% of the examination volume is restricted. The remaining examination volume was examined with techniques which have been qualified by demonstration in accordance with Supplements 4 & 6 of the 1995 Edition with Addenda through 1996 of the ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative Protocol. This weld was examined from both sides of the weld, scanning both parallel and perpendicular to the weld. The ultrasonic examination identified three IWB-3510 acceptable indications in accordance with the ASME Code Section XI, 1989 Edition, No Addenda, acceptance criteria.
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 3 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 Figure 5 is a view of the TWS robot in the vessel shell region showing scan limitations caused by the Core Barrel Stabilizers and Core Lugs. Figure 6 provides dimensional information for the core barrel stabilizers and core lugs and their locations in the reactor vessel. Figure 7 is a roll out view showing the reactor vessel inside surface scan areas (cross hatched) for the bottom head-to-lower shell weld and the locations of limited areas due to the presence of the core barrel stabilizers and core lugs.
RPV Upper Shell Longitudinal Seam Weld at 15 Degrees (1-203B)
Examination Category B-A, Item B1.12 The examination of the Figure IWB-2500-2 A-B-C-D volume is limited due to the outlet nozzle at zero degrees integral extension. Access to approximately 36.8%
of the examination volume is restricted. The remaining examination volume was examined with techniques which have been qualified by demonstration in accordance with Supplements 4 & 6 of the 1995 Edition with Addenda through 1996 of the ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative Protocol. This weld was examined from both sides of the weld, scanning both parallel and perpendicular. These ultrasonic examinations did not reveal any recordable or reportable flaws in accordance with the ASME Code Section XI, 1989 Edition, No Addenda.
Figures 8 and 9 are views of the TWS robot in the vessel shell region showing the scan limitation caused by the outlet nozzle at zero degrees integral extension. Figure 10 provides dimensional information and the affect the outlet nozzle at zero integral extension had on scanning. Figure 11 is a roll out view showing the reactor vessel inside surface scan areas (cross hatched) for the upper shell longitudinal seam weld at 15 degrees.
RPV Lower Head Peel Segment Welds (204-03-A through F)
Examination Category B-A, Item B1.22 The examination of the Figure IWB-2500-3 E-F-G-H volume is limited due to the proximity of the flow baffle. Access to approximately 46.7% of welds 204-03-B, 204-03-D, 204-03-F and 56.6% of welds 204-03-A, 204-03-C, 204-03-E examination volume is restricted due to limited access behind the flow baffle.
The remaining examination volume was examined with techniques which have been qualified by demonstration in accordance with Supplements 4 & 6 of the 1995 Edition with Addenda through 1996 of the ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative Protocol. The welds were examined from both sides of the weld, scanning both parallel and perpendicular to the weld. These ultrasonic examinations did not reveal any recordable or reportable flaws in accordance with the ASME Code Section XI, 1989 Edition, No Addenda.
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 4 of 20 St. Lucie Unit I THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 Figures 12 and 13 are views of the TWS robot in the vessel shell region showing scan limitations due to limited access behind the flow baffle and core lugs.
Figure 14 provides dimensional information for the core lugs and core baffle and their affect on scanning. Figure 15 is a roll out view showing the reactor vessel inside surface scan areas (cross hatched) for the peel segment welds and the locations of the core lugs.
- 5. Burden Caused by Compliance It is not possible to obtain ultrasonic interrogation of greater than 90% of the required examination volume due to interference caused by configuration and/or permanent attachments. Examinations were performed to the maximum extent possible. For the welds listed in this relief request, it is not possible to remove the permanently attached obstructions to increase ASME Code coverage without significant work, increased radiation exposure, and/or damage to the plant.
- 6. Proposed Alternative and Basis for Use Proposed Alternative
- 1) Periodic system pressure tests in accordance with ASME Section XI Category B-P, Table IWB-2500-1.
- 2) Conduct ultrasonic examinations to the maximum extent possible.
Basis FPL performed inservice examinations of selected welds in accordance with the requirements of 10CFR50.55a, plant technical specifications, and the 1989 Edition, No Addenda, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section X1. The 1995 Edition with Addenda through 1996 was utilized for ASME Section X1, Appendix VIII. When a component has conditions which limit the examination volume, Florida Power and Light is required to submit the information to the enforcement and regulatory authorities having jurisdiction at the plant site. This Relief Request has been written to address areas where those types of conditions exist and the required amount of coverage was reduced below the minimum acceptable.
FPL performed mechanized ultrasonic examinations of the reactor vessel during the November 2008 refueling outage.
10 CFR 50.55a(g)(4) recognizes that throughout the service life of a nuclear power facility, components which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements set forth in the ASME Code to the extent practical within the limitations of design, geometry and materials of construction of the components.
K-St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 5 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 The mechanized techniques employed for examination from the RPV inside have been demonstrated in accordance with Supplements 4 & 6 of the 1995 Edition with Addenda through 1996 of the ASME Code Section XI, Appendix VIII, using the Performance Demonstration Initiative Protocol. The Ultrasonic (UT) techniques for each weld were reviewed to determine if additional coverage could be achieved. Access for examination of the affected welds from the outside of the reactor vessel is not possible. Access and permanently installed attachments inside the reactor vessel limit additional scanning of the welds included in this request for relief.
In addition to the required ultrasonic examination, the interior of the reactor vessel, including welded attachments, received a visual examination in accordance with Table IWB-2500-1, Examination Categories B-N-i, B-N-2 and B-N-3. The visual examinations revealed no indications.
The subject welds were also examined in the second interval during the 10-year reactor vessel examination. The second interval examinations did not reveal any reportable flaws.
The extent of examination volume achieved ultrasonically, the alternate scans performed, and the system pressure tests provide assurance of an acceptable level of quality and safety.
- 7. Duration of Proposed Alternative Third Inservice Inspection Interval February 11, 1998 to February 10, 2008
- 8. References 10CFR50.55a ASME Section XI, "Rules For Inservice Inspection of Nuclear Power Plant Components,"
1989 Edition, No Addenda ASME Section XI, Division 1, Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds, Section Xl, Division 1" ASME Section XI, Appendix VIII, "Rules For Inservice Inspection of Nuclear Power Plant Components," 1995 Edition with Addenda through 1996
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 6 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION I CONTACT E*OCK END CONTACT HEAD DIRECTIONAL ARROW 2x3 jT HEAD CON Fl("C.U1 RAT 10 N FOR SHELI. SSC.ANNING (AS VIEWED FROM BACK OF ROBOHANOD COUPLING)
Illustration of the typical UT head configuration used for vessel shell weld scanning. Overall head dimensions are approximately 12" x 8".
Figure 1
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 7 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 RPV Intermediate Shell-to-Lower Shell Circumferential Weld (9-203)
View of TWS robot in vessel shell region showing scan limitation caused by the surveillance capsule holders. The weld is covered by the surveillance capsule holders.
Figure 2
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 8 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION I 270' AND, DIMENSIONS SHON IN.INCHES.
'TOL£ SCAN ARE-A. ,OF" WELD','--.20 IS LIMITED DUE ITO6: SURVEILLNCE HOLDERS T'OTAL WE.LD. LEN(VH= 5416.R1 "INC-HES, SHO-$UIWEILLANCE" HOLDER OBSTRUCTED RPV Intermediate Shell-to-Lower Shell Circumferential Weld (9-203)
Figure 3
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 9 of 20 St. Lucie Unit I THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 1' 270 ' IT 9i 18i' 7-203 RPV Intermediate Shell-to-Lower Shell Circumferential Weld (9-203)
Figure 4
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 10 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 RPV Circumferential Bottom Head-to-Lower Shell Weld (10-203)
View of TWS robot in lower vessel shell region showing scan limitation caused by the Core Barrel Stabilizers and Core Lugs. The weld examination is obstructed by the Core Barrel Stabilizers and Core Lugs.
Figure 5
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 11 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1
-SURVEILLANCE HdLDERý,
CORE BARREL
,STABILIZER-90'
-WEL, 1O31-ý203I BAFFLE-TyP, 9x.
RPV Circumferential Bottom Head-to-Lower Shell Weld (10-203)
Figure 6
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 12 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 i59 270" q 90* 180.
V/I WO.... ...... 5 RPV Circumferential Bottom Head-to-Lower Shell Weld (10-203)
Figure 7
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 13 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 RPV Upper Shell Longitudinal Seam Weld at 15 Degrees (1-203B)
View of TWS robot in upper vessel nozzle belt region showing scan limitation caused by the outlet nozzle reinforcement. The weld intersects the outlet nozzle and limits head movement.
Figure 8
, I . x St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 14 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 RPV Upper Shell Longitudinal Seam Weld at 15 Degrees (1-203B)
View of TWS robot in upper vessel nozzle belt region showing scan limitation caused by the outlet nozzle reinforcement. The weld intersects the outlet nozzle and limits head movement.
Figure 9
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 15 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 Ii J.
RPV Upper Shell Longitudinal Seam Weld at 15 Degrees (1-203B)
Figure 10
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 16 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION I 180" 2 70" 0 90" i 80-7-203. -
- .-, - ,(l* /- ,\ /+/ */ \ ,/ 'I
/ IL 71 203A 1' 2038 1 -
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Figure 11
1 0 'A St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 17 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 RPV Lower Head Peel Segment Welds (204-03-A through F)
View of TWS robot in lower head above flow baffle showing scan limitation caused by the baffle and core lugs. This view shows both the circumferential weld and peel welds. The affected lower head peel welds are partially covered by the baffle.
Figure 12
I I A1 St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 18 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION I RPV Lower Head Peel Segment Welds (204-03-A through F)
View of TWS robot in lower head below flow baffle showing scan limitation caused by the baffle. The affected welds are partially covered by the baffle. The affected lower head peel welds are partially covered by the baffle.
Figure 13
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2 Page 19 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 FLOW RPV Lower Head Peel Segment Welds (204-03-A through F)
Figure 14
St. Lucie Unit 1 L-2009-168 Docket No. 50-335 Attachment 2
- 0 Page 20 of 20 St. Lucie Unit 1 THIRD INSPECTION INTERVAL RELIEF REQUEST NUMBER 31, REVISION 1 1 00 270" 0 90, 180" 0 0;,
M-203 0 01
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.. .......i l m m -'r-2D4-02 20,-0-C . 204-03-A 204-03-F 204-03-E 20.-03-D.
210' 03B 20- 330' 30 9(0 150" RPV Lower Head Peel Segment Welds (204-03-A through F)
Figure 15