Letter Sequence Response to RAI |
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EPID:L-2018-LLA-0181, License Amendment Request to Reduce the Number of Control Element Assemblies (Approved, Closed) |
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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
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- I= PL .. U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington DC 20555-0001 RE: St. Lucie Unit 2 Docket No. 50-389 NOV 1 5 2018 Renewed Facility Operating Licenses NPF-16 L-2018-205 10 CFR 50.90 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies
References:
- 1. Florida Power & Light Company letter L-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies, June 29,2018 (ADAMS Accession No. ML18180A094)
- 2. Florida Power & Light Company letter L-2018-153, Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies, August 17, 2018 (ADAMS Accession No. ML18229A050)
- 3. St. Lucie Plant, Unit No.2, Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies (EPID L-2018-0181)
October 22, 2018 (ADAMS Accession No. ML18296A205)
In Reference 1, as supplemented by Reference 2, Florida Power & Light Company (FPL) requested an amendment to Renewed Facility Operating License NPF-16 for St. Lucie Unit 2. The proposed license amendment modifies the St. Lucie Unit 2 Technical Specifications (TS) by reducing the specified number of control element assemblies (CEAs) from 91 to 87 in support of a planned modification to permanendy remove four 4-element (mini-dual)
CEAs from the reactor core. The proposed license amendment relatedly deletes a reference to the 4-element CEAs in a TS definition.
In Reference 3, the NRC requested additional information deemed necessary to complete its review. ------+h&-@ndesu+/-&-te
-fui.s-l@tt&-prev-id@s-Wl:s-r@Sf>en-s&-te-th
&-NRGs-reEJU@St-fer-additien-al
-infe:tcm.a-tien(RAI). The response provides additional information that clarifies the application, does not expand the scope of the application as originally noticed, and does not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register. This letter contains no new or revised regulatory commitments.
Should you have any questions regarding this submittal, please contact Mr. Michael Snyder, St. Lucie Licensing Manager, at (772) 467-7036.
St. Lucie Nuclear Plant Docket No. 50-389 I declare under penalty of perjury that the foregoing is true and correct. Executed on NOV 1 5 2018 Sincerely, Daniel DeBoer Site Director-St. Lucie Nuclear Plant, Units 1 and 2 Florida Power & Light Company
Enclosure:
FPL Response to Request for Additional Information cc: USNRC Regional Administrator, Region II USNRC Project Manager, St. Lucie Nuclear Plant, Units 1 and 2 USNRC Senior Resident Inspector, St. Lucie Nuclear Plant, Units 1 and 2 Ms. Cindy Becker, Florida Department of Health L-2018-205 Page 2 of2 St. Lucie Nuclear Plant L-201 8-205 Docket No. 50-389 Enclosure Page 1 of 6 Enclosure Florida Power & Light Company Response to NRC Request for Additional Information (RAI)
Regarding St. Lucie Unit 2 License Amendment Request to Reduce the Number of Control Element Assemblies
St. Lucie Nuclear Plant L-201 8-205 Docket No. 50-389 Enclosure Page 2 of 6 In Reference 1, as supplemented by Reference 2, FPL requested a license amendment to modif y the St. Lucie Unit 2 TS by reducing the specified number of CEAs from 91 to 87 in support of a planned modification to permanently remove four 4
-element (mini
-dual) CEAs from the reactor core. The proposed license amendment relatedly delete s a reference to the 4
-element CEAs in a TS definition.
In Reference 3, the Reactor Systems Branch (SRXB) of the NRC Office of Nuclear Reactor Regulation requested additional information, as indicated below.
FPL's response follows:
SRXB-RAI-1: Shutdown Margin Regulatory Basis
- Appendix A, "General Design Criteria [GDC] for Nuclear Power Plants," to Title 10 of the Code of Federal Regulations, Part 50; GDC-25, "Protection System Requirements for Reactivity Control Malfunctio n s", GDC-26, "Reactivity Control System Redun dancy and Capability
" a nd GDC-27, "Combined Reactivity Control Systems Capability"
.
GDC-25 re quires, in par t , that the p rotection sys tem shall be designed to assure that t he speci fied acceptable fuel design limits are not exceeded for any single malfunction of the reactivity control systems.
GDC-26 re quires, in par t , that two i ndependent reactivity control systems of different design principles sh a ll b e provided. One of the systems shall use control r ods. The s econd reacti vity control system shall b e capable of reliably con trolling the r ate of reactivity changes resulting f r o m planned, normal power changes t o assure acceptable fuel design limits are not exceeded. One of the sys tems shall be capable of holding t h e reactor c o re sub critical under cold c onditions.
GDC-27 re quires, in par t , that the r eactivity control systems shall be des igned to have a combined capability, in conjuncti o n with poison addition by the emergency core cooling system, of reliably controlling r eactivity changes to assure that t he capability to cool the core is mai ntained.
The current St. Lucie 2 design bases that satisfy these design criteria are to provide the amount of reactivity available from insertion of withdrawn CEAs under all power operating conditions, even when the highest worth CEA fails to insert, at least one percent shutdown margin after cooldown to hot zero power, and any additional shutdown reactivity requirements assumed in the safety analyses.
Request As stated in the LAR, a calculation specific to St. Lucie 2 was performed to evaluate the impact of the removal of the four 4
-element CEAs on the total worth of reactivity systems and the subsequent available shutdown margin. Provide the following information related to the calculation:
(1) Brief description including computer codes for the approved methodology to perform the calculation, (2) Summary of the calculation assumptions and conditions, e.g. the highest worth CEA fails to insert etc.,
St. Lucie Nuclear Plant L-201 8-205 Docket No. 50-389 Enclosure Page 3 of 6 (3) Calculation results on the shutdown margin showing the difference between "With" and "Without" four 4-element CEAs, (4) Based on (3), a justification for the removal of four 4
-element CEAs by taking into account the calculation uncertainties (e.g. uncertainties applied to Updated Final Safety Analysis Report (UFSAR)
Table 4.3.6) and the compensatory measure, if required, for the reduction in the shutdown margin due to the removal of four 4
-element CEAs.
FPL Response:
(1) The methodology used in performing the CEA reactivity worth and the subsequent shutdown margin calculation is the same as currently used in all the St. Lucie Unit 2 neutronics calculations. This methodology, WCAP
-11596-P-A (Reference 4), is NRC approved and listed in St. Lucie Unit 2 TS 6.9.1.11.b.1. The computer code used is the PHOENIX-P/ANC code package.
(2) The neutronics calculation for total rod worth and shutdown margin included conservative methodology assumptions such as skewing xenon to the limits of Axial Shape Index (ASI) in Core Operating Limits Report (COLR) Figure 3.2
-4, highest worth CEA stuck in the fully withdrawn position and 10% total rod worth uncertainty.
(3) To ensure the elimination of four 4
-element CEAs does not pose problems in meeting the COLR limits, a separate sample core loading pattern was developed for Cycle 21 without using the four 4
-element CEAs. The excess shutdown margin in this calculation, with the highest worth CEA stuck in the fully withdrawn position, was 1059 pcm at the beginning
-of-cycle (BOC) and 330 pcm at the end
-of-cycle (EOC). (The excess shutdown margin is the margin above the COLR limit of 3600 pcm). The corresponding excess shutdown margins with the original Cycle 21 design, i.e. with the four 4
-element CEAs, was 1245 pcm at BOC and 356 pcm at EOC. Since the worth of the highest stuck rod is loading pattern dependent, the excess shutdown margin varies from cycle to cycle and can be controlled via the core design.
(4) The calculation demonstrated that the shutdown margin requirements with the highest worth CEA stuck in the fully withdrawn position can be easily met without the use of the four 4-element CEAs. Additionally, if needed, excess shutdown margin can be controlled by altering the core design and fuel load during the design phase of a reload cycle.
SRXB-RAI-2: Steam Line Break Analysis Regulatory Basis - GDC-10, "Reactor Design", GDC-15, "Reactor Coolant System Design", GDC-20 "Protection System Fu nction", and GDC-26. GDC-10 re quires, in par t , that the r eactor core a nd associa ted coolant, control, and protection systems shall be designed wi t h appropria t e margin to assure that specified acce ptable fu e l design St. Lucie Nuclear Plant L-201 8-205 Docket No. 50-389 Enclosure Page 4 of 6 limits are not exceeded during any condition of normal operation, includi n g the effects of anticipa ted operatio n al occurrences.
GDC-15 re quires, in par t , that the r eactor coola n t system and assoc i at e d auxiliary, control, and protection systems be designed wi t h sufficient margin to assure that the design co nditions of t h e reactor c oolant press u re boundary are not exceeded during a ny condition of normal opera tion, including anticipated operational occurrences.
GDC-20 re quires, in par t , that the p rotection sys tem shall be designed (1) to initiate automatically the operati o n of appropri ate systems including the reactivity control systems, and (2) to sense acci dent conditi o ns and initiate the operation of systems and components important to safety.
GDC-26 requires , in par t , that two i ndependent reactivity control systems of different design principles sh a ll be provided.
One of the systems shall use control r ods. The s econd reacti vity control system shall b e capable of reliably con trolling the r ate of reactivity changes resulting f r o m planned, normal power changes t o assure acceptable fuel design limits are not exceeded. One of the sys tems shall be capable of holding t h e reactor c o re sub critical under cold c onditions.
The current St. Lucie 2 design bas e s that satisfy these desi g n criteria are to provide the amount of reactivity available from insertion of withdrawn CEAs under all power operating c onditions, e ven when the highest wo rth CEA fails to insert, at le a st one perc e nt shutdown margin after cooldown t o hot zero power, and any additional shutdown reactivity requirements assumed in the safety analyse s. Request As stated in the LAR, a calculation s pecific to St. Lucie 2 was performed to evaluate the impact of the removal of the four 4-element CEAs on the s team line break analysis. P rovide the following in formation related to the calcula tion:
(1) Brief descri ption inclu d i n g computer codes for t h e approved methodology to perform the calc ulation, (2) Summary of the calc ulation assumptions and co nditions, e.g. the highest worth CEA fails to i nsert etc.,
(3) Calculation results on t h e total reactivity balance for the rated thermal power and associated fuel peaking fac tors showing the differe nce between "With" and "Without" fo u r 4-element CEAs, (4) Based on (3), a justi fication for the removal of fo u r 4-element CEAs by ta king into account the calcula tion uncertainti e s. FPL Response
(1) The methodology used in performing the steam line break reactivity balance was the same as that used for other St. Lucie Unit 2 neutronics calculations. This methodology, WCAP
-
St. Lucie Nuclear Plant L-201 8-205 Docket No. 50-389 Enclosure Page 5 of 6 11596-P-A (Reference 4), is NRC approved and is listed in St. Lucie Unit 2 T S 6.9.1.11.b.1. The computer code used is the PHOENIX
-P/ANC code package.
(2) The Cycle 21 steam line break reactivity balance calculation performed using the Reference 4 methodology, assumed conservative methodology assumptions which include highest worth rod stuck in the fully withdrawn position in the limiting (coldest) region of the core, and also analyzing the impact of other high worth rods being stuck in the fully withdrawn position.
The statepoint used is conservative with respect to parameters such as the reactor coolant system pressure, temperature and flow.
(3) The Cycle 21 steam line break reactivity balance calculation showed that the worst reactivity change was 3661 pcm for the case with the four 4-element CEAs, while the change was 3643 pcm for the case without the four 4
-element CEAs. The peak linear heat rate was 12.52 kW/ft for the case with the four 4-element CEAs, while the peak linear heat rate was 13.26 kW/ft for the case without the four 4
-element CEAs. The peak linear heat rate value without the four 4
-element CEAs remained well below the limit of 22 kW/ft. (4) The calculation showed that the steam line break analysis reactivity balance impact is minimal with the four 4
-element CEAs removed, using the same analysis methodology and assumptions. The removal of the four 4-element CEAs is thus justified as being acceptable from core design considerations.
SRXB-RAI-3: Core Bypass Fl o w: Regulatory Basis - GDC-10 GDC-10 re quires, in par t , that the r eactor core a nd associa ted coolant, control, and protection systems shall be designed wi t h appropria t e margin to assure that specified acce ptable fu e l design limits are not exceeded during any condition of normal operation, includi n g the effects of anticipa ted operatio n al occurrences.
Request Clarify the following inf ormation as described in LAR:
(1) The design bypass flow fraction of t otal core flow at rated co r e flow condi tions that is used in the current St. Lucie 2 UFSAR C h apter 15 safe t y analysis, (2) The new bypass flow (f raction of ra ted core flo w) after removal of the four 4-element CEAs, (3) The bypass flow fraction (of rated c o re flow) assumed in the fuel vendor's reload an alysis, (4) The measured current total bypass flow fraction (of rated c o re flow) at rated core fl o w conditions.
St. Lucie Nuclear Plant L-201 8-205 Docket No. 50-389 Enclosure Page 6 of 6 FPL Response
- (1) St. Lucie Unit 2 transitioned to Framatome fuel beginning with Cycle 23 in Spring 2017. The core bypass flow prior to the implementation of fuel design change was a conservative value of 3.7% of the design reactor coolant system (RCS) flow. The transition to Framatome fuel increased the core bypass flow by approximately 0.17% to a design bypass flow value of 3.87%. The St. Lucie Unit 2 current Chapter 15 safety analysis conservatively uses a bypass flow of 4.2% of design RCS flow for all fuel related analyses.
(2) The removal of four 4-element CEAs will increase the core bypass flow conservatively by approximately 0.04% of the design RCS flow. The new bypass flow is estimated to become (3.87% + 0.04%) = 3.91%.
(3) The Framatome (current fuel vendor) reload analysis conservatively assumes a core bypass flow of 4.2% of design RCS flow, which bounds the bypass flow of 3.91% of design RCS flow resulting from the removal of the four 4
-element CEAs.
(4) There is no current measurement of core bypass flow. The value of 3.7%, used in analysis prior to the transition to Framatome fuel, was justified to be conservative for the previous fuel vendor's Chapter 15 analyses based on the values presented in UFSAR Table 4.4
-3, "Reactor Coolant Flows in Bypass Channels
". The currently used new bypass flow of 4.2% has more than sufficient margin to cover the impact of the Framatome fuel and bound the minor impact on bypass flow resulting from the removal of the four 4
-element CEAs, as discussed above.
References:
(1) Florida Power & Light Company letter L
-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies, June 29, 2018 (ADAMS Accession No. ML18180A094)
(2) Florida Power & Light Company letter L
-2018-153, Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies, August 17, 2018 (ADAMS Accession No. ML18229A050)
(3) St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies (EPID L
-2018-0181) October 22, 2018 (ADAMS Accession No. ML18296A205)
(4) WCAP-11596-P-A, "Qualification of the PHOENIX
-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988 (Westinghouse Proprietary).