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Initiation
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Results
Other: ML060890398, ML060950574, ML073511698, ML081200606, ML081790538, ML090980515, ML092080216, ML092440479, ML100190011, NRC 2009-0113, Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706), NRC 2011-0010, Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
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MONTHYEARML0515202022005-06-0202 June 2005 6/2/05, Turkey Point, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0515201832005-06-0202 June 2005 Request for Additional Information, Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. Project stage: RAI ML0515202272005-06-0303 June 2005 6/3/05, Seabrook, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0603703962006-02-0808 February 2006 RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0603704382006-02-0808 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-basis Accidents at Pressurized-water Reactors Project stage: RAI ML0603801332006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0603704912006-02-0909 February 2006 RAI - Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0608903982006-04-11011 April 2006 Requested Extension of Completion Schedule for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other ML0609505742006-04-13013 April 2006 Approval of GSI-191/GL 2004-02 Extension Request Project stage: Other NRC 2007-0085, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2007-11-16016 November 2007 Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request L-2007-155, Request for Extension of Completion Date of the Generic Letter 2004-02 Actions2007-12-0707 December 2007 Request for Extension of Completion Date of the Generic Letter 2004-02 Actions Project stage: Request ML0735116982007-12-20020 December 2007 GSI-191/GL 2004-02 Extension Request Approval (Tac No. MC4705/4706) Project stage: Other L-2008-030, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-02-27027 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request L-2008-033, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-02-28028 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request L-2008-073, NRC Generic Letter 2004-02 Request for an Extension to the Completion Date for Ex-Vessel Downstream Effects Evaluations2008-04-14014 April 2008 NRC Generic Letter 2004-02 Request for an Extension to the Completion Date for Ex-Vessel Downstream Effects Evaluations Project stage: Request ML0812006062008-04-29029 April 2008 Approval of Extension Request for GL 2004-02 Project stage: Other NRC 2008-0038, Supplemental Response to Generic Letter 2004-02, Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-06-0909 June 2008 Supplemental Response to Generic Letter 2004-02, Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request L-2008-137, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-30030 June 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request L-2008-138, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-30030 June 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request ML0817905382008-07-0101 July 2008 Generic Safety Issue 191/Generic Letter 2004-02, Additional Extension Request Approval Project stage: Other ML0826106902008-09-17017 September 2008 Request for Additional Information Related to GL 2004-02 Project stage: RAI ML0826107052008-09-17017 September 2008 Request for Additional Information (RAI) Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors Project stage: RAI ML0834400782008-12-19019 December 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information Project stage: RAI ML0833806712008-12-22022 December 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information (TAC Mc 4725) Project stage: RAI ML0833001732009-01-0707 January 2009 GSI-191/GL 2004-02 Request for Additional Information Project stage: RAI ML0836589782009-01-16016 January 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information Project stage: RAI ML0835800232009-01-22022 January 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information Project stage: RAI L-2009-063, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2009-03-19019 March 2009 Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Response to RAI L-2009-062, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2009-03-19019 March 2009 Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Response to RAI NRC 2009-0033, Response to Request for Additional Information GSI-191/GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-04-0707 April 2009 Response to Request for Additional Information GSI-191/GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0909805152009-04-0808 April 2009 SONGS - GSI-191 Chemical Effects Project stage: Other L-2009-084, Response to Nrc'S Request for Additional Information2009-04-22022 April 2009 Response to Nrc'S Request for Additional Information Project stage: Request NRC 2009-0053, Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MC4705/4706)2009-06-12012 June 2009 Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MC4705/4706) Project stage: Request NRC 2009-0059, Response to Request for Additional Information GSI-I91/GL 2004-02 Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-06-29029 June 2009 Response to Request for Additional Information GSI-I91/GL 2004-02 Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0920802162009-07-27027 July 2009 Notice of Forthcoming Conference Call with Florida Power and Light Concerning Turkey Point Generic Letter 2004-02 Response Project stage: Other L-2009-180, Responses to Nrc'S Request for Additional Information on Generic Letter 2004-02 Supplemental Responses, Dated 02/27/2008 and 06/30/20082009-07-30030 July 2009 Responses to Nrc'S Request for Additional Information on Generic Letter 2004-02 Supplemental Responses, Dated 02/27/2008 and 06/30/2008 Project stage: Supplement NRC 2009-0077, Response to Request for Additional Information GSI-191/GL 2004-02 (TACs MC4705/4706) Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-07-31031 July 2009 Response to Request for Additional Information GSI-191/GL 2004-02 (TACs MC4705/4706) Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0924404792009-09-11011 September 2009 Summary of Conference Call with Florida Power & Light, to Discuss Generic Letter 2004-02, Potential Impact of Debris Blackage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactor, Responses Project stage: Other NRC 2009-0113, Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706)2009-10-27027 October 2009 Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706) Project stage: Other ML1001900112010-01-19019 January 2010 Notice of Conference Call with Florida Power & Light Concerning Turkey Point Generic Letter 2004-02 Response Project stage: Other ML1003512132010-02-18018 February 2010 Request for Additional Information Regarding GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML1009700022010-04-0909 April 2010 Request for Additional Information, Regarding GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI NRC 2010-0046, Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation Durian Design Basis Accidents at Pressurized-Water Reactors2010-06-11011 June 2010 Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation Durian Design Basis Accidents at Pressurized-Water Reactors Project stage: Supplement ML1019405202010-07-14014 July 2010 Notice of Conference Call with Florida Power and Light Company to Discuss Draft Responses to NRC Requests for Additional Information for Generic Letter 2004-02 Project stage: Draft RAI ML1007407182010-07-28028 July 2010 February 3, 2010, Turkey Point, Unit 3 & 4, Summary of Meeting with Florida Power & Light, on Generic Letter 2004-02 Project stage: Meeting L-2010-205, Responses to Nrc'S Request for Additional Information Dated Feb. 18, 2010 Re Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2010-09-17017 September 2010 Responses to Nrc'S Request for Additional Information Dated Feb. 18, 2010 Re Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML1009903062010-09-22022 September 2010 Request for Additional Information Regarding GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML1025902742010-12-17017 December 2010 Summary of Teleconference Meeting with Florida Power & Light Company, on Generic Letter 2004-02 Project stage: Meeting NRC 2011-0010, Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2011-02-0404 February 2011 Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML1103502052011-02-0404 February 2011 Forthcoming Public Teleconference with NextEra Energy Seabrook, LLC, to Discuss Planned Testing for Seabrook Specific Erosion Project stage: Request 2009-01-07
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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-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. 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-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations 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-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, 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-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results 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-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
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Florida Power & Light Company, 700 Universe Boulevard, Juno Beach, FL 33408 APR 1 4 2008 U. S. Nuclear Regulatory Commission L-2008-073 ATTN: Document Control Desk 10 CFR 50.54(f) 11555 Rockville Pike Rockville, Maryland 20852 Re: Florida Power and Light Company Turkey Point Unit 4 Docket No. 50-251 NRC Generic Letter 2004-02 Request for an Extension to the Completion Date for Ex-Vessel Downstream Effects Evaluations
References:
(1) Letter L-2005-181 from J. A. Stall (FPL) to U. S. Nuclear Regulatory Commission "NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors - Second Response,"
dated September 1, 2005 (2) Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," dated September 13, 2004 (3) Letter L-2006-028 from J. A. Stall (FPL) to U. S. Nuclear Regulatory Commission "Supplement to Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,"
dated January 27, 2006 (4) Letter from B. T. Moroney (U. S. Nuclear Regulatory Commission) to J. A. Stall (FPL) "Turkey Point Plant, Unit No. 4 - Approval of GSI-191/GL 2004-02 Extension Request (TAC No. MC4726)," dated April 13, 2006 (5) Letter L-2008-033 from William Jefferson, Jr. (FPL) to U. S. Nuclear Regulatory Commission "Supplemental Response to NRC Generic Letter 2004-02, 'Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors'," dated February 28, 2008 an FPL Group company
Turkey Point Unit 4, Docket No. 50-251 L-2008-073, Page 2 of 4 By letter L-2005-181 (Reference 1) Florida Power and Light Company (FPL), the Licensee for Turkey Point Unit 4, submitted responses requested to information items 2(a) and 2(b) of Generic Letter (GL) 2004-02 (Reference 2). The responses indicated that corrective actions would be implemented to ensure that the Emergency Core Cooling System and Containment Building Spray recirculation functions under debris loading conditions would be in compliance with the Applicable Regulatory Requirements section of the Generic Letter when all modifications are completed by December 31, 2007.
Subsequently, by letter L-2006-028 (Reference 3), FPL requested an extension to the completion schedule until the end of the Unit 4 spring 2008 refueling outage. By letter dated April 13, 2006 (Reference 4), the NRC staff concluded that it was acceptable to extend the completion date for the corrective actions until the completion of the Turkey Point Unit 4 spring refueling outage (which at that time was scheduled to begin on April 27, 2008.). By letter L-2008-033 (Reference 5), FPL provided a supplemental response to GL 2004-02 for Turkey Point Unit 4 where FPL reconfirmed that a follow-up (updated) supplemental response to GL 2004-02 would be submitted within three months following the spring outage.
As discussed in a teleconference with the NRC staff on March 27, 2008, it was recently identified that the High Head Safety Injection (HHSI) pumps do not meet the shaft stiffness acceptance criteria utilizing the methodology in WCAP-16406-P, Revision 1. In accordance with the provisions (alternative analytical options) of that WCAP, a refined rotor dynamic analysis will be performed to determine if an increased wear limit is acceptable. In addition, a review of existing conservative margins may also be conducted to evaluate wear effects on the pumps. These two options are described in the WCAP. FPL plans to complete this analytical work by June 30, 2008; however, this date is later than the currently scheduled restart for Turkey Point Unit 4. Thus, FPL requests an extension for completing the ex-vessel downstream effects evaluations that support HHSI pump acceptance. If these additional tasks do not demonstrate acceptable results and additional corrective actions are required, FPL will contact the Commission. The results of the downstream effects evaluations will be provided to the NRC staff with the Turkey Point Unit 4 updated supplemental response discussed above.
The discussions that follow support FPL's request to extend the completion of these analyses until June 30, 2008.
Risk Estimate WCAP-1 6362, "PRA Modeling Template for Sump Blockage," provides a general model for sump blockage that was used to perform a simplified risk impact evaluation of extending the completion of Generic Letter 2004-02 actions at Turkey Point Unit 4. The risk impact was limited to large break loss of coolant accidents (LOCAs), because only
Turkey Point Unit 4, Docket No. 50-251 L-2008-073, Page 3 of 4 large break LOCAs are large enough to create enough debris to clog the containment sump. From NUREG/CR-6928, "Industry Average Performance for Components and Initiating Events at U. S. Commercial Nuclear Power Plants", the frequency of a large break LOCA is 1.33E-06 per year. Minimal credit was taken for mitigation of sump blockage. For Turkey Point Unit 4, mitigation includes providing make up fluid to the Unit 4 Refueling Water Storage Tank (RWST) to allow extended injection, and starting the Unit 3 Safety Injection pumps for injection from the Unit 3 RWST. These mitigating actions are based on steps in the Emergency Operating Procedures. A screening value of 0.2 was used for the probability of failing to successfully perform these mitigating activities. The calculated increase in the core damage frequency due to sump clogging is therefore (1.33E-06 per year) x (0.2) = 2.66E-07 per year, which is well below the Regulatory Guide 1.174 definition of less than 1 E-06 per year for a "very small change" in core damage frequency. Therefore, extending the completion date for the ex-vessel downstream effects evaluations, until June 30, 2008, does not pose a significant risk increase.
Permanent Modifications In addition to modifications made in the fall 2006 outage, the remaining permanent modifications are scheduled to be complete before startup from the current spring 2008 outage, as discussed in our letter L-2008-033 (Reference 5). Final modifications include replacement of interim sump strainers with the final/permanent sump strainer system, replacement of existing Reactor Coolant Pump insulation with reflective metallic insulation, and replacement of mechanical seals and removal of the cyclone separators on the containment spray pumps.
Additional Supporting Activities Also, as discussed in our letter L-2008-033 (Reference 5), other supporting activities including analysis, testing and administrative/procedural changes will be completed by the end of the current spring outage. These include coating tests that support a qualified coating Zone Of Influence of 4.0D; integrated debris and chemical effects testing to validate the strainer design (large flume test); walkdowns to identify potential recirculation flow path chokepoints and quantities of latent and miscellaneous debris in the containment; programmatic activities to control the quantity of unqualified/degraded coatings in containment; assessment that current containment housekeeping procedures are acceptable; and configuration control of insulation within containment.
Conclusion In summary, with the exception of the requested analysis extension for the HHSI pumps to June 30, 2008, FPL will have completed planned GL 2004-02 improvements to Turkey Point Unit 4 by the completion of the spring 2008 outage. This results in significantly improved safety margins associated with the containment sumps.
Turkey Point Unit 4, Docket No. 50-251 L-2008-073, Page 4 of 4 It is requested that the NRC respond to this extension request by May 1, 2008.
This information is provided pursuant to the requirements of Section 182a of the Atomic Energy Act of 1954, as amended, and 10 CFR 50.54(f).
Please contact Rajiv S. Kundalkar at (561) 694-4848 if you have any questions regarding this request.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on April / 4- , 2008 Sincerely yours, J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer cc: Regional Administrator, Region II USNRC Project Manager, Turkey Point Senior Resident Inspector, USNRC, Turkey Point
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0 IPL.
Florida Power & Light Company, 700 Universe Boulevard, Juno Beach, FL 33408 APR 1 4 2008 U. S. Nuclear Regulatory Commission L-2008-073 ATTN: Document Control Desk 10 CFR 50.54(f) 11555 Rockville Pike Rockville, Maryland 20852 Re: Florida Power and Light Company Turkey Point Unit 4 Docket No. 50-251 NRC Generic Letter 2004-02 Request for an Extension to the Completion Date for Ex-Vessel Downstream Effects Evaluations
References:
(1) Letter L-2005-181 from J. A. Stall (FPL) to U. S. Nuclear Regulatory Commission "NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors - Second Response,"
dated September 1, 2005 (2) Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," dated September 13, 2004 (3) Letter L-2006-028 from J. A. Stall (FPL) to U. S. Nuclear Regulatory Commission "Supplement to Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,"
dated January 27, 2006 (4) Letter from B. T. Moroney (U. S. Nuclear Regulatory Commission) to J. A. Stall (FPL) "Turkey Point Plant, Unit No. 4 - Approval of GSI-191/GL 2004-02 Extension Request (TAC No. MC4726)," dated April 13, 2006 (5) Letter L-2008-033 from William Jefferson, Jr. (FPL) to U. S. Nuclear Regulatory Commission "Supplemental Response to NRC Generic Letter 2004-02, 'Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors'," dated February 28, 2008 an FPL Group company
Turkey Point Unit 4, Docket No. 50-251 L-2008-073, Page 2 of 4 By letter L-2005-181 (Reference 1) Florida Power and Light Company (FPL), the Licensee for Turkey Point Unit 4, submitted responses requested to information items 2(a) and 2(b) of Generic Letter (GL) 2004-02 (Reference 2). The responses indicated that corrective actions would be implemented to ensure that the Emergency Core Cooling System and Containment Building Spray recirculation functions under debris loading conditions would be in compliance with the Applicable Regulatory Requirements section of the Generic Letter when all modifications are completed by December 31, 2007.
Subsequently, by letter L-2006-028 (Reference 3), FPL requested an extension to the completion schedule until the end of the Unit 4 spring 2008 refueling outage. By letter dated April 13, 2006 (Reference 4), the NRC staff concluded that it was acceptable to extend the completion date for the corrective actions until the completion of the Turkey Point Unit 4 spring refueling outage (which at that time was scheduled to begin on April 27, 2008.). By letter L-2008-033 (Reference 5), FPL provided a supplemental response to GL 2004-02 for Turkey Point Unit 4 where FPL reconfirmed that a follow-up (updated) supplemental response to GL 2004-02 would be submitted within three months following the spring outage.
As discussed in a teleconference with the NRC staff on March 27, 2008, it was recently identified that the High Head Safety Injection (HHSI) pumps do not meet the shaft stiffness acceptance criteria utilizing the methodology in WCAP-16406-P, Revision 1. In accordance with the provisions (alternative analytical options) of that WCAP, a refined rotor dynamic analysis will be performed to determine if an increased wear limit is acceptable. In addition, a review of existing conservative margins may also be conducted to evaluate wear effects on the pumps. These two options are described in the WCAP. FPL plans to complete this analytical work by June 30, 2008; however, this date is later than the currently scheduled restart for Turkey Point Unit 4. Thus, FPL requests an extension for completing the ex-vessel downstream effects evaluations that support HHSI pump acceptance. If these additional tasks do not demonstrate acceptable results and additional corrective actions are required, FPL will contact the Commission. The results of the downstream effects evaluations will be provided to the NRC staff with the Turkey Point Unit 4 updated supplemental response discussed above.
The discussions that follow support FPL's request to extend the completion of these analyses until June 30, 2008.
Risk Estimate WCAP-1 6362, "PRA Modeling Template for Sump Blockage," provides a general model for sump blockage that was used to perform a simplified risk impact evaluation of extending the completion of Generic Letter 2004-02 actions at Turkey Point Unit 4. The risk impact was limited to large break loss of coolant accidents (LOCAs), because only
Turkey Point Unit 4, Docket No. 50-251 L-2008-073, Page 3 of 4 large break LOCAs are large enough to create enough debris to clog the containment sump. From NUREG/CR-6928, "Industry Average Performance for Components and Initiating Events at U. S. Commercial Nuclear Power Plants", the frequency of a large break LOCA is 1.33E-06 per year. Minimal credit was taken for mitigation of sump blockage. For Turkey Point Unit 4, mitigation includes providing make up fluid to the Unit 4 Refueling Water Storage Tank (RWST) to allow extended injection, and starting the Unit 3 Safety Injection pumps for injection from the Unit 3 RWST. These mitigating actions are based on steps in the Emergency Operating Procedures. A screening value of 0.2 was used for the probability of failing to successfully perform these mitigating activities. The calculated increase in the core damage frequency due to sump clogging is therefore (1.33E-06 per year) x (0.2) = 2.66E-07 per year, which is well below the Regulatory Guide 1.174 definition of less than 1 E-06 per year for a "very small change" in core damage frequency. Therefore, extending the completion date for the ex-vessel downstream effects evaluations, until June 30, 2008, does not pose a significant risk increase.
Permanent Modifications In addition to modifications made in the fall 2006 outage, the remaining permanent modifications are scheduled to be complete before startup from the current spring 2008 outage, as discussed in our letter L-2008-033 (Reference 5). Final modifications include replacement of interim sump strainers with the final/permanent sump strainer system, replacement of existing Reactor Coolant Pump insulation with reflective metallic insulation, and replacement of mechanical seals and removal of the cyclone separators on the containment spray pumps.
Additional Supporting Activities Also, as discussed in our letter L-2008-033 (Reference 5), other supporting activities including analysis, testing and administrative/procedural changes will be completed by the end of the current spring outage. These include coating tests that support a qualified coating Zone Of Influence of 4.0D; integrated debris and chemical effects testing to validate the strainer design (large flume test); walkdowns to identify potential recirculation flow path chokepoints and quantities of latent and miscellaneous debris in the containment; programmatic activities to control the quantity of unqualified/degraded coatings in containment; assessment that current containment housekeeping procedures are acceptable; and configuration control of insulation within containment.
Conclusion In summary, with the exception of the requested analysis extension for the HHSI pumps to June 30, 2008, FPL will have completed planned GL 2004-02 improvements to Turkey Point Unit 4 by the completion of the spring 2008 outage. This results in significantly improved safety margins associated with the containment sumps.
Turkey Point Unit 4, Docket No. 50-251 L-2008-073, Page 4 of 4 It is requested that the NRC respond to this extension request by May 1, 2008.
This information is provided pursuant to the requirements of Section 182a of the Atomic Energy Act of 1954, as amended, and 10 CFR 50.54(f).
Please contact Rajiv S. Kundalkar at (561) 694-4848 if you have any questions regarding this request.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on April / 4- , 2008 Sincerely yours, J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer cc: Regional Administrator, Region II USNRC Project Manager, Turkey Point Senior Resident Inspector, USNRC, Turkey Point