Letter Sequence Request |
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CAC:MF5455, Provide RISK-INFORMED Extended Completion Times - RITSTF Initiative 4B (Approved, Closed) CAC:MF5456, Provide RISK-INFORMED Extended Completion Times - RITSTF Initiative 4B (Approved, Closed) |
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MONTHYEARML16036A3072016-02-18018 February 2016 Regulatory Audit Plan in Support of the License Amendment Requests to Implement Risk-Informed Technical Specifications Initiative 4b Project stage: Other ML16105A4592016-04-14014 April 2016 NRR E-mail Capture - Request for Additional Information Re. Turkey Point 3 & 4 LAR-236 (CACs MF5455 & MF5456) Project stage: RAI ML16110A0042016-04-18018 April 2016 NRR E-mail Capture - Request for Additional Information - Turkey Point 3 & 4 LAR-236 (CACs MF5455 & MF5456) Project stage: RAI ML16154A3392016-06-0101 June 2016 NRR E-mail Capture - Request for Additional Information Re. Turkey Point 3 & 4 LAR-236 (CACs MF5455 & MF5456) Project stage: RAI L-2016-116, Response to Request for Additional Information Regarding License Amendment Request 236, Revision to TS to Adopt Risk Informed Completion Time TSTF-505, Revision 1,Provide Risk-Informed Extended Completion Times.2016-06-16016 June 2016 Response to Request for Additional Information Regarding License Amendment Request 236, Revision to TS to Adopt Risk Informed Completion Time TSTF-505, Revision 1,Provide Risk-Informed Extended Completion Times. Project stage: Response to RAI ML16154A0122016-06-21021 June 2016 Summary of NRC Audit of Turkey Point Nuclear Generating Unit Nos. 3 and 4 for License Amendment Request No. 236 Project stage: Other L-2016-136, Second Response to Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide...2016-08-11011 August 2016 Second Response to Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide... Project stage: Response to RAI L-2017-006, Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b.2017-02-0909 February 2017 Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b. Project stage: Supplement ML17090A1252017-03-30030 March 2017 NRR E-mail Capture - Request for Additional Information Re. Turkey Point TSTF-505 LAR 236 (CACs MF5455 and MF5456) Project stage: RAI L-2017-063, Response to Third Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide ...2017-04-27027 April 2017 Response to Third Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide ... Project stage: Request ML17213A2102017-06-27027 June 2017 NRR E-mail Capture - Draft Request for Additional Information - Turkey Point 3 & 4 LAR-236 (CACs MF5455 & MF5456) Project stage: Draft RAI ML17222A2312017-07-18018 July 2017 NRR E-mail Capture - Draft Request for Additional Information - Turkey Point 3 & 4 LAR-236 (CACs MF5455 & MF5456) Project stage: Draft RAI ML17222A0042017-08-0303 August 2017 NRR E-mail Capture - Additional Draft RAI Related to the Turkey Point TSTF-505 LAR Project stage: Draft RAI ML17223A0612017-08-10010 August 2017 NRR E-mail Capture - Request for Additional Information - Turkey Point 3 & 4 LAR-236 (CACs MF5455 & MF5456) Project stage: RAI L-2017-168, Response to Fourth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed..2017-10-30030 October 2017 Response to Fourth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed.. Project stage: Request L-2018-001, Supplement to Response to Fourth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide..2018-02-15015 February 2018 Supplement to Response to Fourth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide.. Project stage: Supplement ML18061A0172018-03-0101 March 2018 NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4, Request for Additional Information Regarding License Amendment Request 256 (CAC Nos. MF5455 and MF5456; EPID L-2014-0002) Project stage: RAI L-2014-000, Response to Fifth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed....2018-03-22022 March 2018 Response to Fifth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed.... Project stage: Request L-2018-061, Response to Fifth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed....2018-03-22022 March 2018 Response to Fifth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed.... Project stage: Request ML18138A0002018-04-19019 April 2018 NRR E-mail Capture - Draft Request for Additional Information - Turkey Point 3 and 4 LAR 236 (CAC Nos. MF5455 and MF5456; EPID L-2014-0002) Project stage: Draft RAI ML18138A4652018-05-17017 May 2018 NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4, Request for Additional Information Regarding License Amendment Request 236 (CAC Nos. MF5455 and MF5456; EPID L-2014-0002) Project stage: RAI L-2018-118, Response to Sixth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed..2018-06-12012 June 2018 Response to Sixth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed.. Project stage: Request ML18151A4342018-06-14014 June 2018 Summary of NRC Audit Regarding License Amendment Request to Adopt Risk-Informed Completion Times in Technical Specifications (CAC Nos. MF5372 and MF5373; EPID L-2014-LLA-0002) Project stage: Other ML18303A2432018-10-26026 October 2018 NRR E-mail Capture - (External_Sender) NRC Notification of State of Florida Regarding Turkey Point 3 and 4 License Amendments - Regarding the Addition of Risk-Informed Completion Times Project stage: Other ML18270A4292018-12-0303 December 2018 Issuance of Amendments Nos. 284 and 278 Regarding Adoption of Risk-Informed Completion Times in Technical Specifications (CAC Nos. MF5455 and MF5456; EPID L-2014-LLA-0002) Project stage: Approval 2017-06-27
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Category:Letter type:L
MONTHYEARL-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-011, 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 Applications2024-03-13013 March 2024 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-2024-014, Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-008, Supplement to 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 Cycles2024-02-0909 February 2024 Supplement to 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-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 2024-08-12
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes 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-2023-110, 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-2023-098, 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-2023-069, 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 ML23151A4372023-05-24024 May 2023 Attachment 3: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database ML23151A4362023-05-24024 May 2023 License Amendment Request Revision 3 for the Technical Specifications Conversion to NUREG - 1431 Revision 5 ML23095A0082023-04-0404 April 2023 Attachment 2 - Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database 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-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-2022-166, 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-2022-136, 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-2022-051, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II, Supplement Information and Response to Request for Additional Information2022-03-29029 March 2022 Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II, Supplement Information and Response to Request for Additional Information L-2021-213, Response to Request for Additional Information Regarding License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum LOCA Methodology2021-11-19019 November 2021 Response to Request for Additional Information Regarding License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum LOCA Methodology L-2021-207, Response to Request for Additional Information for ISI Relief Request No. 102021-10-25025 October 2021 Response to Request for Additional Information for ISI Relief Request No. 10 L-2021-197, Response to Request for Additional Information for ISI Relief Request No. 102021-10-15015 October 2021 Response to Request for Additional Information for ISI Relief Request No. 10 ML21258A3792021-09-14014 September 2021 Response to Request for Additional Information, Relief Requests 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1), Extension of Inspection Interval for Turkey Point Unit 3 and Unit 4 Reactor. L-2020-111, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Report2020-06-24024 June 2020 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Report L-2020-081, Response to Request for Additional Information Regarding License Amendment Request 264, Adopt Emergency Action Level Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor2020-06-0808 June 2020 Response to Request for Additional Information Regarding License Amendment Request 264, Adopt Emergency Action Level Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor L-2020-083, Supplemental Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Re2020-05-21021 May 2020 Supplemental Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Re L-2020-071, Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements2020-04-16016 April 2020 Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements L-2020-064, Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information2020-04-0909 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information ML20098F3412020-04-0707 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information L-2019-135, Response to Request for Additional Information Regarding License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications2019-07-22022 July 2019 Response to Request for Additional Information Regarding License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications ML19158A5032019-06-0707 June 2019 NRC to NMFS, NRC Responses to NMFS Requests for Additional Information for Turkey Point ESA Section 7 Consultation L-2019-114, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 10, RAI No. B.2.3.28-1b Updated Response2019-06-0404 June 2019 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 10, RAI No. B.2.3.28-1b Updated Response L-2019-048, Response to Request for Additional Information (Rai), Subsequent License Renewal Application Safety Review Revision 1, Second Submittal Set 82019-03-15015 March 2019 Response to Request for Additional Information (Rai), Subsequent License Renewal Application Safety Review Revision 1, Second Submittal Set 8 L-2019-037, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 9 Responses2019-03-0606 March 2019 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 9 Responses L-2019-033, Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses2019-03-0101 March 2019 Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses ML19056A1252019-02-25025 February 2019 Turky Point SLRA RAIs 1 2 3 4 5 6 7 8 9 11 - Set 8 Rev 1 Irradiated Concrete-Steel Responses L-2019-012, Response to Follow-on NRC RAI No. B.2.3.9-1 a2019-02-13013 February 2019 Response to Follow-on NRC RAI No. B.2.3.9-1 a L-2019-023, Response to Request for Additional Information Regarding License Amendment Request 265, Revise NFPA-805 License Condition for Reactor Coolant Pump Seals2019-01-31031 January 2019 Response to Request for Additional Information Regarding License Amendment Request 265, Revise NFPA-805 License Condition for Reactor Coolant Pump Seals L-2018-234, Subsequent License Renewal Application Safety Review Request for Additional Information (RAI) Set 5 Response 4.3.5-2 Revision2018-12-21021 December 2018 Subsequent License Renewal Application Safety Review Request for Additional Information (RAI) Set 5 Response 4.3.5-2 Revision L-2018-223, Subsequent License Renewal Application Safety Review - November 15, 2018 Public Meeting Action Item Responses2018-12-14014 December 2018 Subsequent License Renewal Application Safety Review - November 15, 2018 Public Meeting Action Item Responses L-2018-222, Subsequent License Renewal Application Safety Review - November 13, 2018 Public Meeting Discussion Topic Responses2018-12-12012 December 2018 Subsequent License Renewal Application Safety Review - November 13, 2018 Public Meeting Discussion Topic Responses L-2018-218, Supplemental Response to Request for Additional Information (RAI) Set 1, Subsequent License Renewal Application Environmental Review2018-11-28028 November 2018 Supplemental Response to Request for Additional Information (RAI) Set 1, Subsequent License Renewal Application Environmental Review L-2018-191, Supplemental Responses Requests for Additional Information (RAI) Set 7 Subsequent License Renewal Application Safety Review2018-11-28028 November 2018 Supplemental Responses Requests for Additional Information (RAI) Set 7 Subsequent License Renewal Application Safety Review L-2018-193, Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review2018-11-0202 November 2018 Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review L-2018-166, WCAP-15355-NP, Revision 0, a Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings.2018-10-31031 October 2018 WCAP-15355-NP, Revision 0, a Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings. ML18299A1142018-10-24024 October 2018 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 4 Responses L-2018-175, Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses2018-10-17017 October 2018 Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses L-2018-176, Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items2018-10-17017 October 2018 Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items ML18296A0242018-10-16016 October 2018 Set 3 Response to Request for Additional Information to Subsequent License Renewal Application Safety Review ML18299A1162018-10-15015 October 2018 Structural Integrity Associates Engineering Report No. 1700109.401P, Revision 7 - Redacted, Evaluation of Environmentally-Assisted Fatigue for Turkey Point Units 3 and 4 for Subsequent License Renewal ML18299A1172018-10-12012 October 2018 Framatome Calculation No. 32-9280712, Rev. 002, Tp CRDM Lower Joint Environmentally Assisted Fatigue Dated October 12, 2018 (Non-Proprietary) ML18299A1182018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.304, Revision 3, Fatigue Crack Growth Evaluation, October 12, 2018 L-2018-174, Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines2018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines ML18283A3102018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application Environmental Review L-2018-169, Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review2018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review 2024-05-06
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June 12, 2018 L-2018-118 10 CFR 50.90 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Turkey Point Nuclear Plant, Units 3 and 4 Docket Nos. 50-250 and 50-251
Subject:
Response to Sixth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, "Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b"
References:
- 1. Florida Power & Light Company letter L-2014-369, "License Amendment Request No. 236 Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, 'Provide Risk-Informed Extended Completion Times -RITSTF Initiative 4B'," December 23, 2014 (.ML15029A297)
- 2. NRC E-mail "Request for Additional Information re. Turkey Point 3 & 4 LAR-236 (CACs MF5455 & MF5456)," April 14, 2016 (.ML16105A459)
- 3. NRC E-mail "Request for Additional Information -Turkey Point 3 & 4 LAR-236 (CACs MF5455 & MF5456)," April 18, 2016 (.ML16110A004)
- 4. NRC E-mail "Request for Additional Information re. Turkey Point 3 & 4 LAR-236 (CACs MF54555 & MF5456)," June 1, 2016 (.ML16154A339)
- 5. Florida Power & Light Company letter L-2016-116, "Response to Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, 'Provide Risk-Informed Extended Completion Times- RITSTF Initiative 4b'," June 16, 2016
(.ML16180A178)
- 6. Florida Power & Light Company letter L-2016-136, "Second Response to Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1,
'Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b'," August 11, 2016 (.ML16243A104)
Florida Power & Light Company 9760 SW 344 St., Homestead, FL 33035
L-2018-118 Page 2 of 3
- 7. Florida Power & Light Company letter L-2017-006, "Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, 'Provide Risk-Informed Extended Completion Times -
RITSTF Initiative 4b'," February 9, 2017 (ML17060A249)
- 8. NRC E-mail "Request for Additional Information Re. Turkey Point TSTF-505 LAR 236 (CACs MF5455 and MF5456)" March 30, 2017
- 9. Florida Power & Light Company letter L 2017-063, "Response to Third Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1,
'Provide Risk-Informed Extended Completion Times -RITSTF Initiative 4b'," April 27, 2017 (ML17117A618)
- 10. NRC E-mail "Request for Additional Information - Turkey Point 3 & 4 LAR-236 (CACs MF5455 & MF5456)," August 10, 2017 (ML17223A061)
- 11. Florida Power & Light Company letter 2017-168 "Response to Fourth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1,
Provide Risk-Informed Extended Completion Times -RITSTF Initiative 4b," October 30, 2017 (ML17303A768)
- 12. Florida Power & Light Company letter 2018-001, "Supplement to Response to Fourth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, 'Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b',"
February 15, 2018 (ML18046A597)
- 13. NRC E-mail "Turkey Point Nuclear Generating Unit Nos. 3 and 4, Request for Additional Information Regarding License Amendment Request 256 (CAC Nos. MF5455 and MF5456; EPID L-2014-0002)," March 1, 2018 (ML18061A017)
- 14. Florida Power & Light Company letter 2018-061, "Response to Fifth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, 'Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b'," March 22, 2018 (ML18081A063)
- 15. NRC E-mail "Turkey Point Generating Unit Nos. 3 and 4, Request for Additional Information Regarding License Amendment Request 236 (CAC Nos. MF5455 and MF5456; EPID L-2014-0002)," May 17, 2018 In Reference 1, as supplemented by References 5, 6, 7, 9, 11, 12, and 14, Florida Power & Light Company (FPL) submitted license amendment request (LAR) 236 for Turkey Point Units 3 and 4.
The proposed amendment would revise the Technical Specifications (TS) to implement TSTF-505, Revision 1, "Provide Risk-Informed Extended Completion Times RITSTF [Risk Informed TSTF]
Initiative 4b."
L-2018-118 Page 3 of 3 In Reference 15, the NRC staff requested additional information to support its review of the LAR.
The enclosure to this letter provides FPL's response to the request for additional information (RAI).
The attachment to the enclosure provides markups of the operating licenses for Turkey Point Units 3 and 4 that add a license condition regarding implementation items and PRA methods used in the Risk Informed Completion Time Program. These markups supersede the markups of the operating licenses provided previously in Reference 12.
This response to the RAI does not alter the conclusions in Reference 1 that the change does not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the change.
No new or revised commitments are included in this letter.
Should you have any questions regarding this submittal, please contact Robert Hess, Licensing Manager, at (305) 246-4112.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on June~' 2018 Sincerely,
~
RobertCoffey Regional Vice President - Southern Region Florida Power & Light Company Enclosure cc: NRC Regional Administrator, Region II NRC Senior Resident Inspector NRC Project Manager Ms. Cindy Becker, Florida Department of Health
L-2018-118 Enclosure Page 1 of 5 ENCLOSURE Response to Request for Additional Information APLA RAI-12.01 Remaining Unresolved F&Os APLA RAI-12, dated August 10, 2017 (ADAMS Accession No. ML17223A061), noted that eleven facts and observations (F&Os) were identified in the LAR as unresolved and requested a resolution. In the February 15, 2018, supplemental response to APLA RAI-12, FPL stated that the eleven findings listed as unresolved in the LAR have been closed by an independent assessment (IA) team in accordance with the NRC approved F&O closeout process. FPL further stated that the F&O closeout identified 43 F&Os that were reported as resolved in the LAR but that the IA team concluded required additional documentation or justification. The RAI response included a table of these F&Os, the F&O IA team's comments, and FPLs disposition of the IA team comments for the risk-informed completion time (RICT) calculations. Many of the IA team's comments stated that no documentation confirming FPLs stated resolution was found and, therefore, the F&O could not be closed. In FPLs disposition for RICT responses, FPL generally states that "[d]ocumentation updates are needed" and that there is "[n]o impact on the RICT." The NRC staff has reviewed the information and concludes that when the IA team was unable to identify documentation to verify that the resolution proposed by FPL was implemented, FPL's stated resolution is assumed to have been implemented, but not documented, and therefore there is no impact on the RICT. For several F&Os discussed below, however, it appeared that the documentation available indicated that the resolution proposed by FPL may not have been implemented as summarized, and therefore, the conclusion that there is no impact on the RICT needs additional justification.
- a. HR-A2-01 In Attachment 3 of the February 15, 2018, RAI response, the F&O IA team commented that the licensee was using an alternative approach to identify, screen, and quantify pre- initiators from the approach assumed in HR-A2 in the probabilistic risk assessment (PRA) standard.
Based on the limited information provided in Table 1 of Enclosure 2 of the LAR, and Enclosure 3 of the February 15, 2018, RAI response, it appears all potential pre- initiator human errors are quantitatively screened based on using a relatively low screening value. The American Society of Mechanical Engineers (ASME) Standard does not address quantitative screening. Additionally, RICT calculations may include multiple structures, systems, and components that are inoperable, which can significantly alter PRA results and invalidate previous quantitative screening decisions.
In addition to the use of an alternative approach, the IA team noted that some values seem to differ between the documentation and the PRA model.
- 1. Please summarize the new approach to identifying and including pre-initiator human errors in the PRA and justify its applicability for RICT calculations. For example, why are screening values of 3E-03 and 3E-4 expected to capture all pre-initiator
L-2018-118 Enclosure Page 2 of 5 human errors that would become important under configurations for which a RICT may be calculated. Alternatively, implement or provide an implementation item in the response to APLA RAI 15.01 about implementing a method consistent with the ASME Standard.
- 2. Please confirm that the PRA model and the documentation are aligned.
FPL Response
- 1. As an implementation item, FPL will use a systematic process to review calibration procedures and practices to identify activities, that if performed incorrectly, can have an adverse impact on the automatic initiation of standby safety equipment, consistent with the ASME standard. (See RAI 15.01b)
- 2. The PRA model and documentation will be aligned as part of response 12.0la.1.
- b. QU-3 Table 1 of Enclosure 2 of the LAR states that changes to the mutually exclusive event combinations, flag file, circular logic breaks, and recovery rule file are documented in the change database and the model updates. However, the F&O team found no evidence of documentation of the recovery or the mutually exclusive files. Improper modeling of these issues can affect the RICT calculations. In its February 15, 2018, disposition of the F&O team's finding, the licensee states that the finding will have no impact on the RICT calculation; however, the basis for that disposition is not clear without a well-documented evaluation. Please summarize how recovery and the mutually exclusive events are identified, evaluated, modeled, and documented.
FPL Response The recovery rules are modeled in a recovery rule file. The identification and evaluation of the recovery rules are documented in the HRA calculations supporting the model updates.
Mutually exclusive basic events are explicitly modeled in the CAFTA fault tree for each accident sequence. Typically, this applies to maintenance alignments where multiple trains are not intentionally taken out-of-service at the same time, or "non-sense" basic event combinations.
Changes to the mutually exclusive modelling are evaluated and discussed in the Turkey Point (PTN) PRA Model Update Document for the current model of record. This is reviewed and approved through the model maintenance process.
An enhancement to the quantification notebook to cross-reference the location of the sources for the evaluation of the recovery rules and mutually exclusive rules is in progress but has no impact on quantification of a RICT.
L-2018-118 Enclosure Page 3 of 5
- c. IFSN-A2-01, IFSN-A4-01 Table 1 of Enclosure 2 of the LAR for IFSN-A2-01 states that no credit for floor drains or operator actions to mitigate a flood was taken, and therefore, there was no need to credit flood alarms. Table 1 of Enclosure 2 of the LAR for IFSN-A4-01 states that calculations for flood volumes and subsequent flooding heights had been documented. The F&O team comments identified a PRA document that stated that a reasonable time for the flood to be terminated was based on alarms. In general, timing considerations for operators to terminate the flood is logical, otherwise unreasonable flood damage would have to be assumed. The F&O team also identified at least one drain that appeared to have been assessed. The F&O team could not identify specific calculations on room equipment floods and propagation, nor the input to those calculations (such as time to termination and floor drains).
Please summarize how flooding alarms, human actions, and floor drains have been included in the PRA to determine flood volumes and flood heights. If additional changes are needed to the PRA to resolve these F&Os, provide an implementation item in- the response to APLA RAI 15.01 summarizing the changes.
FPL Response The PTN internal flooding document states "In reality, the duration of a release of floodwater will be determined by when the operators are alerted to the problem, the steps that must be taken to terminate the release and whether these are taken expeditiously. In this analysis, however, no action by the operators that might curtail a flood scenario was considered: floods were allowed to persist for long periods of time (- 12 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) unless the flood source is finite ... Since no credit is taken for operator actions that would mitigate any leak, spray, or rupture, no human reliability analysis was necessary."
Flood alarms and human actions are not included in the PRA, as documented in the PTN internal flood analysis. As stated in the internal flooding analysis, "Credit was always taken for installed floor drains of 24-in. diameter or greater. However, the functioning of smaller drains (typically of 4-in. diameter) cannot be assumed particularly if pumps that may themselves be submerged are relied upon to empty sumps. Therefore, in general, the consequences of.flooding were normally calculated allowing for the possibility that the drains and sump pumps do not function unless their functioning exacerbates the situation."
Documentation enhancements to clarify the presence of flood alarms, dikes, curbs, sumps, drains, sump pumps, spray shields, water tight doors, etc. will be added to the internal flooding analysis.
Calculations for the capacities of drains, and the amount of water retained by sumps, berms, dikes, etc. and how these factors are accounted for in flood volumes and SSC impacts from flooding will be added to the internal flooding analysis as addendums to provide supporting information.
L-2018-118 Enclosure Page 4 of 5
- d. IGN-A7 Table 1 of Enclosure 2 of the LAR for IGN-A7 states that supplemental walkdowns were performed to identify any missing ignition sources and the analysis was updated accordingly.
The F&O team commented that not all ignitions sources that have been identified have been included in the fire PRA. FPL responded that any effect of and missing sources is bounded by the NUREG-2180, "Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities (DELORES-VEWFIRE)"
sensitivity study. The referenced sensitivity study for NUREG-2180 measures the impact of using a PRA model of fire detection that has since been retired and replaced with a new model.
It has no relationship to missing ignition sources. Therefore, the impact of the missing ignition sources is unknown.
Further, FPL states that, "[a] model change is required to add the new ignition sources in the cable spreading room." Please confirm that all relevant ignition sources are included in the fire PRA or provide an implementation item in the response to APLA RAI 15.01 summarizing changes to the PRA that will resolve this F&O.
FPL Response As an implementation item, ignition sources identified in finding 1-18 and subsequent extent of condition walkdowns will be included in the fire PRA. (See RAI 15.0lb)
APLA RAI-15.01 Implementation Item In APLA RAI-15, dated August 10, 2017, the NRC staff requested that several issues (very early warning fire detection system (VEWFDS), human error probability (HEP) floor, and unresolved F&Os) critical to the acceptance of the RICT program be considered for inclusion in a table of implementation items to be completed before implementation of the RICT program. Although FPL states in its February 15, 2018, RAI response that, "[t]he methodology in NUREG-2180 will be incorporated into the Turkey Point Fire PRA model," modeling VEWFDS with NUREG-2180 was not one of the items that FPL proposed as an implementation item in its response to APLA RAI-15. FPL proposed one implementation item for using the HEP floor, and one other implementation item that all F&O "findings will be closed." This general statement does not provide sufficient clarity to support issuing a license amendment.
- a. Provide an implementation item confirming that the VEWFDS modeling in accordance with NUREG-2180 will be used
- b. Provide other implementation item(s), as appropriate, summarizing how the PRA model will be changed for F&Os whose resolution requires changes to the PRA model (i.e., not including any that only need additional documentation) prior to RICT implementation.
L-2018-118 Enclosure Page 5 of 5 FPL Response Table of implementation items:
Item Implementation Date
- 1. The VEWFDS modeling in accordance with NUREG-2180 will be incorporated into the Turkey Point PRA model.
- 2. FPL will use a systematic process to review calibration procedures and practices to identify activities, that if performed incorrectly, can have an adverse impact on the automatic initiation of standby safety equipment.
(See RAI 12.01a)
- 3. Ignition sources identified in finding 1-18 and subsequent extent of condition walkdowns will be included in the fire PRA. (See RAI 12.01d).
Prior to implementation
- 4. New scenarios identified as part of finding 10-20 to of the Risk Informed address Turbine Generator fires will be included in the Completion Time fire PRA. Program
- 5. Confirm that the all hazards CDF and LERF estimates achieved using NRC accepted methods will be less than 1E- 04 per year and 1E-05 per year, respectively.
- 6. Implement a joint HEP floor of 1E-06 in the internal events model. For future model updates, once the HFE combinations have been analyzed and the HEP floor of 1E-06 applied, individual HFE combination probabilities may be set below 1E-06 if a detailed analysis is performed and technical justification is provided.
L-2018-118 Attachment Page 1 of 4 ATTACHMENT Markup of the Unit 3 and Unit 4 Operating Licenses
L-2018-118 Attachment Page 2 of 4 INSERTOL I. FPL is authorized to implement the Risk Informed Completion Time Program as approved in License Amendment No. XXX subject to the following conditions:
- 1. FPL will complete the items listed in the table of implementation items in the enclosure to FPL letter L-2018-118 dated June 12, 2018 prior to implementation of the Risk Informed Completion Time Program.
- 2. The risk assessment approach and methods, shall be acceptable to the NRC, be based on the as-built, as-operated, and maintained plant, and reflect the operating experience of the plant as specified in RG 1.200. Methods to assess the risk from extending the completion times must be PRA methods accepted as part of this license amendment, or other methods approved by the NRC for generic use. If the licensee wishes to change its methods, and the change is outside the bounds of this license condition, the licensee will seek prior NRC approval via a license amendment.
L-2018-118 8 Attachment Page 3 of 4 H. PAD TCD Safety Analyses
- 1. PAD 4.0 TCD has been specifically approved for use for the Turkey Point licensing basis analyses. Upon NRC's approval of a revised generic version of PAD that accounts for Thermal Conductivity Degradation (TCD), FPL will within six months:
- a. Demonstrate that PAD 4.0 TCD remains conservatively bounding in licensing basis analyses when compared to the new generically approved version of PAD w/TCD, or
- b. Provide a schedule for the re-analysis using the new generically approved version of PAD w/TCD for any of the affected licensing basis
!INSERT OL~ analyses.
- 4. This renewed license is effective as of the date of issuance, and shall expire at midnight July 19, 2032.
FOR THE NUCLEAR REGULATORY COMMISSION Signed by Samuel J. Collins, Director Office of Nuclear Reactor Regulation Attachments:
Appendix A - Technical Specifications for Unit 3 Appendix B - Environmental Protection Plan Date of Issuance: June 6, 2002 Renewed License No. DPR-31 Amendment No. ~
L-2018-118 8 Attachment Page 4 of 4 H. PAD TCD Safety Analyses
- 1. PAD 4.0 TCD has been specifically approved for use for the Turkey Point licensing basis analyses. Upon NRC's approval of a revised generic version of PAD that accounts for Thermal Conductivity Degradation (TCD), FPL will within six months:
- a. Demonstrate that PAD 4.0 TCD remains conservatively bounding in licensing basis analyses when compared to the new generically approved version of PAD wrrCD, or
- b. Provide a schedule for the re-analysis using the new generically
!INSERT~ approved version of PAD wrrCD for any of the affected licensing basis analyses.
- 4. This renewed license is effective as of the date of issuance, and shall expire at midnight April 10, 2033.
FOR THE NUCLEAR REGULATORY COMMISSION Signed by Samuel J. Collins, Director Office of Nuclear Reactor Regulation Attachments:
Appendix A - Technical Specifications for Unit 4 Appendix B - Environmental Protection Plan Date of Issuance: June 6, 2002 Renewed License No. DPR-41 Amendment No. ~
L-2018-118 8 Attachment Page 3 of 4 H. PAD TCD Safety Analyses
- 1. PAD 4.0 TCD has been specifically approved for use for the Turkey Point licensing basis analyses. Upon NRC's approval of a revised generic version of PAD that accounts for Thermal Conductivity Degradation (TCD), FPL will within six months:
- a. Demonstrate that PAD 4.0 TCD remains conservatively bounding in licensing basis analyses when compared to the new generically approved version of PAD w/TCD, or
- b. Provide a schedule for the re-analysis using the new generically approved version of PAD w/TCD for any of the affected licensing basis jlNSERTOL~ analyses.
- 4. This renewed license is effective as of the date of issuance, and shall expire at midnight July 19, 2032.
FOR THE NUCLEAR REGULATORY COMMISSION Signed by Samuel J. Collins, Director Office of Nuclear Reactor Regulation Attachments:
Appendix A - Technical Specifications for Unit 3 Appendix B - Environmental Protection Plan Date of Issuance: June 6, 2002 Renewed License No. DPR-31 Amendment No. ~
L-2018-118 8 Attachment Page 4 of 4 H. PAD TCD Safety Analyses
- 1. PAD 4.0 TCD has been specifically approved for use for the Turkey Point licensing basis analyses. Upon NRC's approval of a revised generic version of PAD that accounts for Thermal Conductivity Degradation (TCD), FPL will within six months:
- a. Demonstrate that PAD 4.0 TCD remains conservatively bounding in licensing basis analyses when compared to the new generically approved version of PAD w!TCD, or
- b. Provide a schedule for the re-analysis using the new generically i'NSERTe approved version of PAD w!TCD for any of the affected licensing basis analyses.
- 4. This renewed license is effective as of the date of issuance, and shall expire at midnight April 10, 2033.
FOR THE NUCLEAR REGULATORY COMMISSION Signed by Samuel J. Collins, Director Office of Nuclear Reactor Regulation Attachments:
Appendix A- Technical Specifications for Unit 4 Appendix B - Environmental Protection Plan Date of Issuance: June 6, 2002 Renewed License No. DPR-41 Amendment No. ~