Letter Sequence Request |
---|
CAC:MF5455, Provide RISK-INFORMED Extended Completion Times - RITSTF Initiative 4B (Approved, Closed) |
|
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
[Table View] |
|
---|
Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
[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-2023-110, 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 ML23151A4362023-05-24024 May 2023 License Amendment Request Revision 3 for the Technical Specifications Conversion to NUREG - 1431 Revision 5 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 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) 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 ML18299A1182018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.304, Revision 3, Fatigue Crack Growth Evaluation, October 12, 2018 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 L-2018-154, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 2 Responses2018-09-14014 September 2018 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 2 Responses 2023-08-07
[Table view] |
Text
April 27, 2017 L-2017-063 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Nuclear Plant, Units 3 and 4 Docket Nos. 50-250 and 50-251 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
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-2017-063 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 In Reference 1, as supplemented by References 5, 6, and 7, 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."
In Reference 8, 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). to the Enclosure provides a marked up TS page showing the revised proposed changes. This page supersedes the corresponding page provided in Reference 7. Attachment 2 to the Enclosure provides a retyped TS page and replaces the corresponding page included in Reference 7. A revised change to the TS Bases, which supersedes the corresponding pages in Reference 7, is provided in Attachment 3.
This RAI response does not alter the conclusions in Reference 1 that the changes do not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the changes.
No new or revised commitments are included in this letter.
Should you have any questions regarding this submittal, please contact Mr. Mitch Guth, Licensing Manager, at (305) 246-6698.
I declare under penalty of perjmy that the foregoing is tiue and correct.
Executed on April 77 , 2017 Sincerely,
/~~L Thomas Summers Regional Vice President - Southern Region Florida Power & Light Company
Florida Power & Light Company L-2017-063 Page 3 of 3 Enclosure cc: NRC Regional Administrator, Region II NRC Senior Resident Inspector NRC Project Manager Ms. Cindy Becker, Florida Department of Health
Florida Power & Light Company L-2017-063 Enclosure Page 1 of 1 Response to Request for Additional Information (RAI)
EICB RAI 7 The licensees supplement dated February 9, 2017, revised the licensees application to exclude the use of the loss of function provisions in TSTF-505, Revision 1; however, the staff identified the remaining functions that appear to include a loss of function.
A. In its supplement dated February 9, 2017, the licensee proposed a new Action 27 in TS Table 3.3-2 that would allow a RICT for the condition when one required instrument channel is inoperable. The proposed Action 27 now states, With one channel inoperable, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or in accordance with the Risk Informed Completion Time Program, or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. TS Table 3.3-2, Functional Unit 3.b.1 (i.e., the Containment Isolation, Phase B Isolation, Manual Initiation function) requires 2 channels to trip and states, Both buttons must be pushed simultaneously to actuate. The licensees proposed Action 27 for Functional Unit 3.b.1 is for one channel inoperable (i.e., when one of the two buttons is inoperable). Therefore, the staff requests the licensee to explain why this condition of the Manual Initiation function (i.e., one manual push button inoperable) is not considered a loss of function and justify why extended operation in this condition is acceptable.
B. In its supplement dated February 9, 2017, the licensee proposed a RICT in Action 18 in TS Table 3.3-2 for when the number of OPERABLE channels is one less than the total number of channels. Action 18 is applicable for Functional Unit 7, Loss of Power, in TS Table 3.3-
- 2. Functional Unit 7.a is for a loss of voltage on the 4.16 kilovolt Buses A and B, has two channels per bus, and requires two channels per bus to trip. The licensees proposed RICT in Action 18 is for when one channel is inoperable. Therefore, the staff requests the licensee to explain why this condition (i.e., loss of one channel of loss of power indication) of Functional Unit 7.a is not considered as a loss of function and justify why extended operation in this condition is acceptable.
FPL Response A. The condition involving one inoperable manual pushbutton results in the inability to manually actuate containment phase B isolation. Therefore, FPL is withdrawing the proposed change to the Action for Functional Unit 3.b.1, Containment Isolation - Phase B Isolation - Manual Initiation, in TS Table 3.3-2. This change eliminates TS page 3/4 3-16 from Attachments 2 and 3 in Reference 7.
B. Functional Unit 7, Loss of Power, in Table 3.3-2 detects loss of voltage, undervoltage, and degraded voltage using a two-out-of two logic. Loss of one channel results in the inability to initiate a loss of power signal; therefore, FPL is withdrawing the proposed change to Action 18 associated with Functional Unit 7. Attachment 1 contains a revised mark-up of the TS page and Attachment 2 provides the retyped TS page. The revised Bases change is included in Attachment 3.
Florida Power & Light Company L-2017-063 Attachment 1 ATTACHMENT 1 Mark-up of the Technical Specification (One page follows)
TABLE 3.3-2 (Continued)
TABLE NOTATION (Continued)
ACTION 18 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Both channels of any one load center may be taken out of service for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in order to perform surveillance testing per Specification 4.3.2.1.
ACTION 19 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
ACTION 20 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.
ACTION 21 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.
ACTION 22 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.
ACTION 23 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, comply with Specification 3.0.3.
Control Room ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolate the control room Emergency Ventilation System and initiate operation of the Control Room Emergency Ventilation System in the recirculation mode.
ACTION 25 - With number of OPERABLE channels one less than the Total number of channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. For subsequent required DIGITAL CHANNEL OPERATIONAL TESTS the inoperable channel may be placed in bypass status for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
or in accordance with the Risk Informed Completion Time Program.
ACTION 26 - With one channel inoperable, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST or TRIP ACTUATING DEVICE OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in accordance with the Risk Informed Completion Time Program.
ACTION 27- With one channel inoperable, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or in accordance with the Risk Informed Completion Time Program, or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
TURKEY POINT - UNITS 3 & 4 3/4 3-22 AMENDMENT NOS. 209 AND 203
Florida Power & Light Company L-2017-063 Attachment 2 ATTACHMENT 2 Retyped Technical Specification Page (One page follows)
TABLE 3.3-2 (Continued)
TABLE NOTATION (Continued)
ACTION 18 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Both channels of any one load center may be taken out of service for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in order to perform surveillance testing per Specification 4.3.2.1.
ACTION 19 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
ACTION 20 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.
ACTION 21 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.
ACTION 22 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.
ACTION 23 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, comply with Specification 3.0.3.
ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolate the Control Room Emergency Ventilation System and initiate operation of the Control Room Emergency Ventilation System in the recirculation mode.
ACTION 25 - With number of OPERABLE channels one less than the Total number of channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in accordance with the Risk Informed Completion Time Program. For subsequent required DIGITAL CHANNEL OPERATIONAL TESTS the inoperable channel may be placed in bypass status for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 26 - With one channel inoperable, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST or TRIP ACTUATING DEVICE OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in accordance with the Risk Informed Completion Time Program.
ACTION 27 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or in accordance with the Risk Informed Completion Time Program, or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
TURKEY POINT - UNITS 3 & 4 3/4 3-22 AMENDMENT NOS. AND
Florida Power & Light Company L-2017-063 Attachment 3 ATTACHMENT 3 Change to the Technical Specification Bases (Two pages follow)
INSERT BASES 1 Actions Action 1 With one Manual Reactor Trip channel inoperable, the inoperable channel must be restored to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or in accordance with the Risk Informed Completion Time Program.
Action 10 With one of the reactor trip breakers (RTB) diverse trip features (undervoltage or shunt trip) inoperable, it must be restored to an OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or in accordance with the Risk Informed Completion Time Program.
Acton 25 With one less than the total number of channels OPERABLE, the Action requires placing the inoperable channel in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in accordance with the Risk Informed Completion Time Program.
Action 26 With one channel inoperable, the Action requires placing the inoperable channel in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in accordance with the Risk Informed Completion Time Program.
Acton 27 With one channel of Manual Initiation inoperable, the Action requires restoring the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or in accordance with the Risk Informed Completion Time Program.
REVISION NO.: PROCEDURE TITLE: PAGE:
19 TECHNICAL SPECIFICATION BASES CONTROL PROGRAM 76 of 211 PROCEDURE NO.:
0-ADM-536 TURKEY POINT PLANT ATTACHMENT 2 Technical Specification Bases (Page 59 of 194) 3/4.3.1 & 3/4.3.2 (Continued)
The Engineered Safety Features Actuation System interlocks perform the following functions:
HIGH STEAM FLOW SAFETY INJECTION BLOCK - This permissive is used to block the safety injection (SI) signal generated by High Steam Line Flow coincident with Low Steam Line Pressure or Low Tavg. The permissive is generated when two out of three Low Tavg channels drop below their setpoints and the manual SI Block/Unblock switch is momentarily placed in the block position.
This switch is a spring return to the normal position type. The permissive will automatically be defeated if two out of three Low Tavg channels rise above their setpoints. The permissive may be manually defeated when two out of three Low Tavg channels are below their setpoints and the manual SI Block/Unblock switch is momentarily placed in the unblock position.
LOW PRESSURIZER PRESSURE SAFETY INJECTION BLOCK -
This permissive is used to block the safety injection signals generated by Low Pressurizer Pressure and High Differential Pressure between the Steam Line Header and any Steam Line. The permissive is generated when two out of three pressurizer pressure permissive channels drop below their setpoints and the manual SI Block/Unblock switch is momentarily placed in the block position.
This is the same switch that is used to manually block the High Steam Flow Safety Injection signals mentioned above. This permissive will automatically be defeated if two out of three pressurizer pressure permissive channels rise above their setpoints.
The permissive may be manually defeated when two out of three pressurizer pressure permissive channels are below their setpoints and the manual SI Block/Unblock switch momentarily placed in the Unblock position.
INSERT BASES 1