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| | project = TAC:MF6980, TAC:MF6981 | | | project = TAC:MF6980, TAC:MF6981 |
| | stage = Other | | | stage = Request |
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| ==References:== | | ==References:== |
| : 1. FPL letter L-2015-255 dated October 15, 2015, "License Amendment Request Containment Vacuum GOTHIC Analyses and Conforming Changes." Accession No. ML15301A765 | | : 1. FPL letter L-2015-255 dated October 15, 2015, "License Amendment Request Containment Vacuum GOTHIC Analyses and Conforming Changes." Accession No. ML15301A765 |
| : 2. NRR E-mail Capture dated March 17, 2016, "Request for Additional Information | | : 2. NRR E-mail Capture dated March 17, 2016, "Request for Additional Information |
| -St Lucie Vacuum Gothic LAR-MF6980/MF6981." Accession No. ML16077A106 In Reference 1 Florida Power & Light Company (FPL) submitted proposed amendments for both St. Lucie units that would revise the containment vacuum analyses using the GOTHIC computer code and other conforming Technical Specification (TS) changes. In Reference 2, the NRC requested additional information (RAI) to complete the review of the proposed amendments. | | -St Lucie Vacuum Gothic LAR-MF6980/MF6981." Accession No. ML16077A106 In Reference 1 Florida Power & Light Company (FPL) submitted proposed amendments for both St. Lucie units that would revise the containment vacuum analyses using the GOTHIC computer code and other conforming Technical Specification (TS) changes. In Reference 2, the NRC requested additional information (RAI) to complete the review of the proposed amendments. |
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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-2024-004, 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
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 ML23013A2032023-01-13013 January 2023 RAI Set 4 Draft Response L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-156, Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response2022-09-19019 September 2022 Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response L-2022-143, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response2022-09-0808 September 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response L-2022-115, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment2022-08-0909 August 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment L-2022-108, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response2022-07-11011 July 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response L-2022-075, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response2022-06-13013 June 2022 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response2022-01-19019 January 2022 License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response L-2021-105, Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2021-05-12012 May 2021 Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2021-065, Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years2021-04-0101 April 2021 Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years L-2020-165, Supplement to Updated Final Response to NRC Generic Letter 2004-022020-12-0404 December 2020 Supplement to Updated Final Response to NRC Generic Letter 2004-02 L-2020-094, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2020-06-26026 June 2020 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2020-061, Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2020-04-30030 April 2020 Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements ML20015A0282020-01-14014 January 2020 NMFS to NRC, Concurrence with Interim Response to Requests for Additional Information for St. Lucie Endangered Species Act Section 7 Consultation L-2019-164, Response to Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Protection Bypass Devices Requirements to Licensee Control2019-09-11011 September 2019 Response to Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Protection Bypass Devices Requirements to Licensee Control L-2019-166, Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response2019-08-21021 August 2019 Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response L-2019-153, Exigent Technical Specification Amendment Request Supplemental RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-25025 July 2019 Exigent Technical Specification Amendment Request Supplemental RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-149, Exigent Technical Specification Amendment Request RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-24024 July 2019 Exigent Technical Specification Amendment Request RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-118, Response to Request for Additional Information Regarding License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2019-06-28028 June 2019 Response to Request for Additional Information Regarding License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2019-107, License Amendment Request - Iodine Removal System Elimination2019-05-17017 May 2019 License Amendment Request - Iodine Removal System Elimination L-2019-056, Inservice Inspection Plan RAI Reply, Fifth Ten-Year Interval Unit 1 Relief Request2019-03-0707 March 2019 Inservice Inspection Plan RAI Reply, Fifth Ten-Year Interval Unit 1 Relief Request L-2018-205, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies2018-11-15015 November 2018 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-153, Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies2018-08-17017 August 2018 Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies L-16-001, Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-24024 May 2018 Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018 Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations L-77-291, Attachment a to L-77-291 Response to NRC Questions of May 24, 19772018-03-29029 March 2018 Attachment a to L-77-291 Response to NRC Questions of May 24, 1977 L-2018-040, Response to Request for Additional Information Regarding License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2018-02-14014 February 2018 Response to Request for Additional Information Regarding License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply L-2018-006, Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b2018-02-0101 February 2018 Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b L-2017-210, Updated Final Response to NRC Generic Letter 2004-022017-12-20020 December 2017 Updated Final Response to NRC Generic Letter 2004-02 L-2017-216, License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 62017-12-19019 December 2017 License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 6 L-2017-209, Response to Request for Additional Information Regarding Fifth 10-Year Inservice Testing (IST) Program Interval Relief Request PR-012017-11-30030 November 2017 Response to Request for Additional Information Regarding Fifth 10-Year Inservice Testing (IST) Program Interval Relief Request PR-01 L-2017-159, Response to Request for Additional Information Regarding Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 3, Revision 02017-09-13013 September 2017 Response to Request for Additional Information Regarding Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 3, Revision 0 L-2017-116, Response to Request for Additional Information Regarding License Amendment Request to Revise the Technical Specifications (TS) for the Reactor Protection System (RPS) Power Rate-of-Change Instrumentation and Add New TS 3.0.52017-07-0303 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise the Technical Specifications (TS) for the Reactor Protection System (RPS) Power Rate-of-Change Instrumentation and Add New TS 3.0.5 L-2016-220, License Amendment Request EDG Day Tank Fuel Volume Change2016-12-0505 December 2016 License Amendment Request EDG Day Tank Fuel Volume Change L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) L-2016-153, Response to Request for Additional Information Regarding License Amendment Request for Biological Opinion License Changes2016-08-11011 August 2016 Response to Request for Additional Information Regarding License Amendment Request for Biological Opinion License Changes L-2016-135, Second Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B2016-07-22022 July 2016 Second Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B L-2016-143, Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents2016-07-15015 July 2016 Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents L-2016-114, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 48.2016-07-0808 July 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 48. L-2016-102, RAI Reply - License Amendment Request, Containment Vacuum Gothic Analyses and Conforming Changes2016-05-0606 May 2016 RAI Reply - License Amendment Request, Containment Vacuum Gothic Analyses and Conforming Changes L-2016-104, RAI Reply - Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle2016-05-0606 May 2016 RAI Reply - Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle L-2016-096, Inservice Inspection Plan, RAI Reply for Fourth Ten-Year Interval Relief Request No. 10, Revision 02016-04-21021 April 2016 Inservice Inspection Plan, RAI Reply for Fourth Ten-Year Interval Relief Request No. 10, Revision 0 L-2016-084, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2, Change in Technical Specifications End States.2016-04-20020 April 2016 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2, Change in Technical Specifications End States. L-2016-040, License Renewal Commitments, Reactor Vessel Internals Aging Management Plan, Response to Request for Additional Information2016-02-26026 February 2016 License Renewal Commitments, Reactor Vessel Internals Aging Management Plan, Response to Request for Additional Information 2023-09-11
[Table view] |
Text
U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 RAI Reply -License Amendment Request L-2016-102 10 CFR50.90 Containment Vacuum GOTHIC Analyses and Conforming Changes
References:
- 1. FPL letter L-2015-255 dated October 15, 2015, "License Amendment Request Containment Vacuum GOTHIC Analyses and Conforming Changes." Accession No. ML15301A765
- 2. NRR E-mail Capture dated March 17, 2016, "Request for Additional Information
-St Lucie Vacuum Gothic LAR-MF6980/MF6981." Accession No. ML16077A106 In Reference 1 Florida Power & Light Company (FPL) submitted proposed amendments for both St. Lucie units that would revise the containment vacuum analyses using the GOTHIC computer code and other conforming Technical Specification (TS) changes. In Reference 2, the NRC requested additional information (RAI) to complete the review of the proposed amendments.
The attachment to this letter provides FPL' s reply to the RAis. The original no significant hazards evaluation in Reference 1 bounds these RAI responses.
If you should have any questions, please contact Mr. Ken Frehafer at (772) 467-7748.
I declare under penalty of perjury that the foregoing is true and correct. Sincerely, t-. &.k,1o Christopher R. Costanzo Site Vice President St. Lucie Plant Attachment cc: NRC Region II Administrator St. Lucie Plant NRC Senior Resident Inspector Ms. Cynthia Becker, Florida Department of Health Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957 MAY " r;: ?.016 L-2016-102 Attachment Page 1of5 Request for Additional Information MF6980/1-SCVB-01 through 08 Responses RAl-MF6980/1-SCVB-O 1 How will the higher Containment Spray (CS) flow rates be incorporated?
Will these CS flow rates be updated in the Updated Final Safety Analysis Reports (UFSARs)?
Does the increase in flow rate impact any additional analyses?
Response:
Based on current system calculations which considered the installation of restricting orifices in the containment spray piping for the extended power uprate, a total spray flow of 6950 GPM for Unit 1 and 7250 GPM for Unit 2 was selected for the vacuum analysis. These flows bound the calculated maximum flows for this event and will be conservative for the vacuum analysis.
These flows will be included in the UFSAR in the discussion of the vacuum analysis in the same manner that flows used for the existing vacuum analysis are described.
With respect to other accident and capability analyses, the UFSAR
- reflects conservative CS pump flow rates with respect to the conditions evaluated (e.g., maximized flowrates for NPSH analyses, etc., Unit 1 Table 6.2-9A and Unit 2 Table 6.2-42). RAl-MF6980/1-SCVB-02 Explain further the conclusion that for Unit 1 the GOTHIC benchmarking results appear more reasonable and conservative than the UFSAR's results. Response:
As shown in the table below, the maximum values of DP(Annulus-Cont.)
and DP(Atm.-Annulus) predicted by GOTHIC are in good agreement (i.e. less than+/- 6%) with the UFSAR values except the maximum value of DP (Annulus-Cont.)
for Case A (i.e. -49% ). Case Cont. Max DP(Annulus-Cont.)
Max DP(Atm. -Annulus)
RH (psid) (psid) UFSAR GOTHIC UFSAR GOTHIC A 0% 0.66 0.986 1.17 1.10 B 40% *0.60 0.584 1.46 1.55 c 100 % 0.27 0.285 2.25 2.33 The comparison of UFSAR Figure 6.2-56 and the chart of GOTHIC results below shows some deviation in the trend of differential pressure transient from the annulus to the containment for Case A Considering that the lower initial containment relative humidity condition should lead to a faster and steeper depressurization in the containment, it can be concluded that GOTHIC prediction seems more reasonable and conservative.
Note that the overlapping of the two differential pressure curves of Cases A and B up to approximately 30 seconds as shown in UFSAR Figure 6.2-56 seems less realistic than the GOTHIC results.
L-2016-102 Attachment Page 2 of 5 Request for Additional Information MF6980/1-SCVB-01 through 08 Responses Note Overlap .. :0.50 II! ffi IE ... ... Ill l!.3'l It 6 020 tirl :,;;::rl*
=:::::+/-:::+/-:+/-Et co) 1* TIME HEC) M&:rrti. **AT*AJER-60F ahlPCH'EMT COOU .. ATEl"-l<>f
"'" FLClllDA POWl:ll &. L.IGHl' ST. LUCI! PL.AMT WOT l PRE:SWRE vs T!M:E UFSAR FIGURE 6.2-56 .. 1o . Tlmfi('5eC)
GOTHIC BENCHMARK 1oii L-2016-102 Attachment Page 3 of 5 Request for Additional Information MF6980/1-SCVB-01 through 08 Responses RAl-MF6980/1-SCVB-03 For Unit 1, the maximum allowable initial differential pressure between the containment and annulus is -0.49 psid. What is the analytical limit used for the updated analyses?
What is the margin between the TS and analytical limit? Response:
The analytical limit is the revised containment external design pressure of -1.04 PSID. The analysis determined the proposed TS value of -0.49 PSID initial differential pressure between the containment and annulus combined with the butterfly valve opening setting of less than or equal to negative 16 inches of water gauge will assure the differE1ntial pressure between the containment and the annulus will not exceed -1.00 PSIP during the analyzed event. The TS does not compare directly with the analytical limit; however, the margin between the revised containment design external pressure and maximum differential pressure from the analysis is 0.04 PSID or 4%. RAl-MF6980/1-SCVB-04 For St. Lucie Unit 2, the maximum allowable initial differential pressure between the containment and annulus is -0.42 psid. What is the analytical limit used for the updated analyses?
What is the margin between the TS and analytical limit? Response:
The analytical limit is the revised containment external design pressure of-1.05 PSID. The analysis determined the proposed TS value of-0.42 PSID initial differential pressure between the containment and annulus combined with the butterfly valve opening setting of less than or equal to negative 14 inches of water gauge will assure the differential pressure between the containment and the annulus will not exceed -1.00 PSID during the analyzed event. The TS does not compare directly with the analytical limit; however, the margin between the revised containment design external pressure and maximum differential pressure from the analysis is 0.05 PSID or 5%. RAl-MF6980/1-SCVB-05 In the St. Lucie Unit 2 benchmarking of GOTHIC, what is the impact of modeling the butterfly valve to open instantaneously with no delay? Response:
Opening the butterfly valve instantaneously with no delay would minimize containment external pressure differential as the butterfly valve will be fully open earlier to allow flow from the annulus to the containment to equalize the pressure.
The results of this benchmarking case showed that the GOTHIC analysis provided a higher external differential pressure than the present UFSAR analysis.
Had a time delay for opening the butterfly valve and time for the butterfly valve to stroke to the full open position been considered, the maximum external pressure differential would be even higher. Using the input that the butterfly valve would open instantaneously with no time delay provided a conservative comparison of the GOTHIC methodology to the current UFSAR methodology.
The input that the butterfly valve opened instantaneously with no time delay was only used for the benchmark case to compare the two methodologies.
The updated analysis conservatively L-201.6-102 Attachment Page 4 of 5 Request for Additional Information MF6980/1-SCVB-01 through 08 Responses considers a 1.15 sec time delay to start opening the butterfly and an additional 8 seconds to reach the full open position.
RAl-MF6980/1-SCVB-06 For both Unit 1 and Unit 2, the butterfly valve setpoints changed by a significant amount and the range was removed from the TSs. How was the valve verified to respond appropriately at these new setpoints?
How will the removal of the range change the operation of the valve? Response:
In accordance with the analysis, the butterfly valves must receive a signal to open when or before the differential pressure from the containment to the annulus reaches the values determined in order to assure the differential pressure between the annulus and containment will not exceed -1.00 PSID, If the butterfly valve opened at a lower differential pressure, the resulting containment differential pressure would be reduced. For this reason it does not seem necessary to specify a range. The AOV calculations have been reviewed.
The torque requirements are mostly from the seating/unseating load and the packing load. The change in opening pressure will have limited impact on the required torque . . The actuators currently have a large margin to the required torque. The AOV calculations will be revised to justify any change to the opening setting. RAl-MF6980/1-SCVB-07 In Attachment 5 to Florida Power & Light (FPL) letter (L-2010-259) dated November 22, 2010 (ML 103560419), for St Lucie Unit 1 extended power uprate, Table 2.6.6-1 specifies total maximum spray flow rate (for 2 pumps) equal to 9000 gpm. For Unit 1, Section 3.2 of the October 15, 2015, LAR specifies a total of 6750 gpm as the current UFSAR spray flow rate and Section 3.3 specifies 6950 gpm as the proposed total spray flow rate. The licensee used 6750 gpm for GOTHIC benchmarking vacuum analysis and 6950 gpm for the proposed GOTHIC vacuum analysis.
Since 9000 gpm is the maximum total containment spray flow rate, please . explain why the proposed analysis is not based on this value. Response:
Section 2.6.6 of Attachment 5 to Florida Power & Light (FPL) letter (L-2010-259) dated November 22, 2010 provides a containment backpressure analysis for assessing the ECCS performance capability.
The following statements were made: Following a loss-of-coolant accident (LOCA), the emergency core cooling system (ECCS) will supply water to the reactor vessel to reflood, and thereby cool the reactor core. The core flooding rate *will increase with increasing containment pressure.
FPL reviewed analyses of the minimum containment pressure that could exist during the period of time until the core is reflooded to confirm the validity of the containment pressure used in ECCS performance capability studies. The initial conditions and boundary conditions are given in LR Table 2.6.6-1. The containment pressure transient applied is conservatively low and includes the effect of the operation of all pressure reducing systems and processes.
- LR Table 2.6.6-1 provides the general parameters used in the. containment model for L-2016-102 Attachment Page 5 of 5 for Additional Information MF6980/1-SCVB-01 through 08 Responses RLBLOCA [Realistic Large Break Loss of Coolant Accident]
analysis.
Ongoing processes ensure that the values and ranges used in the EGGS containment backpressure analyses for RLBLOCA bound the values and ranges of the plant as-operated for those parameters.
Table 2.6.6.1 lists a containment spray flow rate of 9000 GPM for this analysis.
9000 GPM is higher than the current calculated containment spray flow. This flow represents a bounding and conservative value for this containment backpressure analysis; however, this flow was overly conservative for the vacuum analysis.
RAl-MF6980/1-SCVB-08
-In Attachment 5 to Florida Power & Light letter (L-2011-21) dated February 25, 2010, for St Lucie Unit 2 extended power uprate, Table 2.6.6-1 specifies total maximum spray flow rate per. pump 4,500 gpm (for 1 pumps) equal to 9000 gpm for 2 pumps.
- For Unit 2, Section 3.2 of the October 15, 2015, LAR specifies total of 6900 gpm as the current UFSAR spray flow rate and Section 3,3 specifies 7250 gpm as the proposed total spray flow rate. The licensee used 6900 gpm for GOTHIC benchmarking vacuum analysis and 7250 gpm for the proposed GOTH.IC vacuum analysis.
Since 9000 gpm is the maximum total containment spray flow rate, please explain why the proposed analysis is not based on this value. Response:
Based on our review, the referenced letter is L-2011-21 dated February 25, 2011 (ML 110730116).
Section 2.6.6 of Attachment 5 to Flo.rida Power & Light letter (L-2011-21) dated February 25, 2011 provides a containment backpressure analysis for assessing the EGGS performance capability.
The following statements were made: Following a loss-of-coolant accident (LOCA), the emergency.core cooling system (EGGS) will supply water to the reactor vessel to reflood, and thereby cool the reactor core. The core flooding rate will increase with increasing containment pressure.
Florida Power and Light (FPL) " reviewed the analyses*
of the minimum containment pressure that could exist during the period of ti.me until the core is reflooded to confirm the validity of the containment pressure used in EGGS performance capability studies. LR Table 2.6.6-1 lists the containment initial and boundary conditions.
The input parameters that were used in the minimum containment pressure.calculation for EGGS performance analysis 'conservatively bound the as-operated configuration.
Table 2,6.6.1 lists a containment spray flow rate of .9000 GPM (4500 GPM per pump) for this analysis.
9000 GPM is higher than the current calculated containment spray flow. This flow represents a bounding and conservative value for .this containment backpressure analysis; however, this flow was overly conservative forthe vacuum analysis.