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MONTHYEARL-2014-216, License Amendment Request No. 231, Application to Revise Technical Specifications to Revise Ultimate Heat Sink Temperature Limit2014-07-10010 July 2014 License Amendment Request No. 231, Application to Revise Technical Specifications to Revise Ultimate Heat Sink Temperature Limit Project stage: Request L-2014-226, License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit - Request for Emergency Approval2014-07-17017 July 2014 License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit - Request for Emergency Approval Project stage: Request ML14203A6182014-07-18018 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 Project stage: RAI ML15131A5752014-07-18018 July 2014 La - Turkey Point 3 and 4 Request for Additional Information - LAR 231 Project stage: RAI ML14203A6142014-07-18018 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 Project stage: RAI ML14203A6202014-07-21021 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI L-2014-232, Response to Request for Additional Information Regarding License Amendment Request No. 231, Application to Revise Technical Specifications to Revise Ultimate Heat Sink Temperature Limit2014-07-22022 July 2014 Response to Request for Additional Information Regarding License Amendment Request No. 231, Application to Revise Technical Specifications to Revise Ultimate Heat Sink Temperature Limit Project stage: Response to RAI L-2014-235, License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit - Supplement 1, and Response to Request for Additional Information2014-07-22022 July 2014 License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit - Supplement 1, and Response to Request for Additional Information Project stage: Supplement ML14204A8142014-07-22022 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI L-2014-236, Response to Containment and Ventilation Branch Request for Additional Information, Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Temperature Limit2014-07-24024 July 2014 Response to Containment and Ventilation Branch Request for Additional Information, Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Temperature Limit Project stage: Request ML14208A0102014-07-25025 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI ML14208A0112014-07-26026 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI L-2014-237, Response to Request for Additional Information Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit2014-07-26026 July 2014 Response to Request for Additional Information Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit Project stage: Response to RAI ML14216A0722014-07-28028 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI ML14209A0312014-07-28028 July 2014 Environmental Assessment and Finding of No Significant Impact Related to the Ultimate Heat Sink Temperature Limit Project stage: Other NRC-2014-0181, Environmental Assessment and Finding of No Significant Impact Related to the Ultimate Heat Sink Temperature Limit (TAC Nos. MF4392 and MF4393)2014-07-28028 July 2014 Environmental Assessment and Finding of No Significant Impact Related to the Ultimate Heat Sink Temperature Limit (TAC Nos. MF4392 and MF4393) Project stage: Other ML14217A0042014-08-0303 August 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI L-2014-259, Response to Containment and Ventilation Branch Request for Additional Information (RAI-5), Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit2014-08-0404 August 2014 Response to Containment and Ventilation Branch Request for Additional Information (RAI-5), Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit Project stage: Request 2014-07-24
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Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-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-2023-086, 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. ML23095A0072023-04-0404 April 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1431 Revision 5 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-2022-160, 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-2022-110, License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary)2022-08-26026 August 2022 License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary) ML22243A1622022-08-26026 August 2022 Submittal of License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML21265A3722021-09-23023 September 2021 Improved Technical Specifications Conversion, Volume 1, Revision 0, Application of Selection Criteria to the Turkey Point Nuclear Generating Station Unit 3 and Unit 4 Technical Specifications L-2021-158, Contents of the Turkey Point Nuclear Plant, Units 3 and 4 Improved Technical Specifications (Its) Submittal2021-09-22022 September 2021 Contents of the Turkey Point Nuclear Plant, Units 3 and 4 Improved Technical Specifications (Its) Submittal ML21265A3772021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 6, Revision 0, Section 3.1, Reactivity Control Systems ML21265A3852021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 14, Revision 0, Section 3.9, Refueling Operations ML21265A3812021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 9, Revision 0, Section 3.5, Emergency Core Cooling Systems (ECCS) ML21265A3872021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 16, Revision 0, Section 5.0, Administrative Controls ML21265A3792021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 8, Revision 0, Section 3.3, Instrumentation ML21265A3802021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 9, Revision 0, Section 3.4, Reactor Coolant Systems (RCS) ML21265A3842021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 13, Revision 0, Section 3.8, Electrical Power Systems ML21265A3862021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 15, Revision 0, Section 4.0, Design Features ML21265A3782021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 7, Revision 0, Section 3.2, Power Distribution Limits ML21265A3832021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 12, Revision 0, Section 3.7, Plant Systems ML21265A3752021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 4, Revision 0, Chapter 2.0, Safety Limits (Sls) ML21265A3762021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 5, Revision 0, Section 3.0, LCO and SR Applicability ML21265A3732021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 2, Revision 0, Determination of No Significant Hazards Considerations Generic Changes ML21265A3822021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 11, Revision 0, Section 3.6, Containment Systems ML21265A3742021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 3, Revision 0, Chapter 1.0, Use and Application L-2021-071, License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum Tm LOCA Methodology2021-04-15015 April 2021 License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum Tm LOCA Methodology L-2020-157, Supplement to License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2020-11-0505 November 2020 Supplement to License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors L-2020-053, Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program2020-04-0404 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program L-2020-003, License Amendment Request 268, Request to Extend Containment Leakage Rate Test Frequency2020-01-27027 January 2020 License Amendment Request 268, Request to Extend Containment Leakage Rate Test Frequency L-2019-203, License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2019-12-0606 December 2019 License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. L-2019-192, License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements2019-11-0404 November 2019 License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements L-2019-005, License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications2019-02-14014 February 2019 License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications L-2018-219, Supplement to License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals2018-12-0303 December 2018 Supplement to License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals L-2018-203, Supplement to License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement2018-11-20020 November 2018 Supplement to License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement 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-2018-170, License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals2018-10-17017 October 2018 License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals 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 L-2018-177, Subsequent License Renewal Application Safety Review Requests for Confirmation of Information (Rci) Responses2018-10-0909 October 2018 Subsequent License Renewal Application Safety Review Requests for Confirmation of Information (Rci) Responses L-2018-187, Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation2018-10-0505 October 2018 Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation ML18130A4662018-06-12012 June 2018 Amendments Regarding Technical Specifications Pertaining to IST Program and ISI Program Requirements and Surveillance Frequency Control Program Applicability L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications L-2018-044, License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement2018-05-14014 May 2018 License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement L-2018-065, License Amendment Request 258, Revise Reactor Core Safety Limit to Reflect WCAP-17642-PA, Revision 12018-05-0303 May 2018 License Amendment Request 258, Revise Reactor Core Safety Limit to Reflect WCAP-17642-PA, Revision 1 L-2018-082, Turkey Point, Units 3 and 4 - Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version)2018-04-10010 April 2018 Turkey Point, Units 3 and 4 - Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version) L-2018-082, Enclosure 4 to L-2018-082 - Non-Proprietary Reference Documents and Redacted Versions of Proprietary Documents (Public Version)2018-04-10010 April 2018 Enclosure 4 to L-2018-082 - Non-Proprietary Reference Documents and Redacted Versions of Proprietary Documents (Public Version) ML18113A1422018-04-10010 April 2018 Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version) ML18113A1412018-04-10010 April 2018 Enclosure 1 to L-2018-082, Subsequent License Renewal Application, Enclosure Summary ML18113A1342018-04-10010 April 2018 Transmittal of Subsequent License Renewal Application Revision 1 L-2018-086, Subsequent License Renewal Application Appendix E Environmental Report Supplemental Information2018-04-10010 April 2018 Subsequent License Renewal Application Appendix E Environmental Report Supplemental Information 2023-06-28
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10 CFR 50.90 L-2014-235 July 22, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Renewed Facility Operating License Nos. DPR-31 and DPR-41'
Subject:
License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit - Supplement 1, and Response to Request for Additional Information
References:
- 1. Florida Power & Light Company (FPL) Letter L-2014-216, "License Amendment Request No. 231, Application to Revise Technical Specifications to Revise Ultimate Heat Sink Temperature Limit," dated July 10, 2014.
- 2. Florida Power & Light Company Letter L-2014-226, "License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit - Request for Emergency Approval," July 17, 2014.
- 3. Email from NRC Project Manager for Turkey Point to FPL, "Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TAC MF4392 and MF4393)," dated July 18, 2014 (RAIs 1-3)
In Reference 1 Florida Power & Light Company (FPL) requested an amendment to the Technical Specifications (TS) for the Turkey Point Nuclear Plant (Turkey Point), Units 3 and 4. In Reference 2 FPL requested the NRC to review and approve the application on an emergency basis. This letter supplements the application by revising the proposed Surveillance Requirements (SR) for the ultimate heat sink (UHS). The revision to the proposed SRs is contained in Enclosure 1. In addition, Enclosure 2 to this letter provides the FPL response to the Request for Additional Information (RAI) contained in Reference 3.
The Reference 1 application proposed to revise the UHS water temperature limit from 100°F to 104'F with consideration for instrument uncertainty. This supplement revises the proposed wording in the SRs to be consistent with the Limiting Condition for Operation, increases the proposed frequency of verifying UHS water temperature when water temperature exceeds I00°F, and adds a requirement to the SRs to add instrument uncertainty to the indicated value.
Florida Power & Light Company 9760 SW 3 4 4 th St., Florida City, FL 33035 Acc)
Florida Power & Light Company L-2014-235 Supplement to License Amendment Request No. 231 Page 2 of 2 Enclosure I supplements the Reference 1 application and includes a mark-up of TS 3/4.7.4, Ultimate Heat Sink, reflecting the changes discussed above. These changes do not alter the determination of no significant hazards and the environmental considerations contained in the application because the revised request is bounded by the basis for change to a higher UHS temperature limit contained in the original application.
There are no new commitments made in this submission.
The Turkey Point Plant Nuclear Safety Committee has reviewed and approved this supplement to the license amendment application. In accordance with 10 CFR 50.91(b)(1), a copy of this letter is being forwarded to the State Designee of Florida.
If you have any questions or require additional information, please contact Mr. Robert Tomonto at 305-246-7327.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on July 22, 2014.
Very truly yours, Michael Kiley Vice President Turkey Point Nuclear Plant
Enclosures:
- 1. Supplement to Application to Revise Ultimate Heat Sink Temperature Limit
- 2. Response to Request for Additional Information Nos. 1, 2 and 3 cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant Ms. Cindy Becker, Florida Department of Health
Florida Power & Light Company L-2014-235 Supplement to License Amendment Request No. 231 Enclosure 1 Page 1 of 5 Turkey Point Units 3 and 4 License Amendment Request No. 231 Supplement Application to Revise Ultimate Heat Sink Temperature Limit Enclosure 1
- 1. Description
- 2. Proposed Change
- 3. Discussion of Change to the Application
- 4. Reference
- 5. Attachments
- 1. Proposed Technical Specification Page 3/4 7-17 Mark-up
- 2. Change to Technical Specification Bases 3/4.7.4 Mark-Up
Florida Power & Light Company L-2014-235 Supplement to License Amendment Request No. 231 Enclosure I Page 2 of 5 1.0 Description Florida Power & Light Company (FPL) amends the application (Reference 1) to revise the ultimate heat sink (UHS) temperature limit. With this supplement FPL is revising the proposed changes to the Surveillance Requirements (SR).
2.0 Proposed Change This application supplement revises the proposed wording in the SRs to be consistent with the Limiting Condition for Operation (LCO) in Technical Specification (TS) 3/4.7.4, Ultimate Heat Sink, increases the proposed frequency of verifying UHS water temperature when water temperature exceeds 100°F, and adds a requirement to the SRs to add instrument uncertainty to the indicated value. Sections 2.1 and 2.2 below update those same sections contained in the Reference 1 application.
2.1 Current TS and Bases Current TS 3/4.7.4, addresses UHS system operability by requiring that the average supply temperature to the Intake Cooling Water (ICW) system be within specified limits:
LCO 3.7.4 states:
The ultimate heat sink shall be OPERABLE with an average supply water temperature less than or equal to 100°F.
APPLICABILITY is Modes 1, 2, 3, and 4.
The ACTION states:
With the requirements of the above specification not satisfied, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and In 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 />. This ACTION shall be applicable to both units simultaneously.
SR 4.7.4 states:
The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average supply water temperature* to be within its limit.
The asterisk (*) refers to a footnote that reads:
Portable monitors may be used to measure the temperature.
Florida Power & Light Company L-2014-235 Supplement to License Amendment Request No. 231 Enclosure I Page 3 of 5 TS Bases The limit on Ultimate Heat Sink (UHS) temperature in conjunction with the SURVEILLANCE REQUIREMENTS of Technical Specification 3/4.7.2 will ensure that sufficient cooling capacity is available either: (1) To provide normal cool down of the facility, or (2) To mitigate the effects of accident conditions within acceptable limits.
FPL has the option of monitoring the UHS temperature by monitoring the temperature in the ICW system piping going to the inlet of the CCW Heat Exchangers. Monitoring the UHS temperature after the ICW but prior to CCW Heat Exchangers is considered to be equivalent to temperature monitoring before the ICW Pumps. The supply water leaving the ICW Pumps will be mixed and therefore, it will be representative of the bulk UHS temperature to the CCW Heat Exchanger inlet. The effects of the pump heating on the supply water are negligible due to low ICW head and high water volume. Accordingly, monitoring the UHS temperature after the ICW Pumps but prior to the CCW Heat Exchangers provides an equivalent location for monitoring the UHS temperature.
With the implementation of the CCW Heat Exchanger Performance Monitoring Program, the limiting UHS temperature can- be treated as a variable with an absolute upper limit of 100°F without compromising any margin of safety. Demonstration of actual heat exchanger performance capability supports system operation with postulated canal temperatures greater than 100°F. Therefore, an upper TS limit of I 00°F is conservative.
2.2 Proposed TS and Bases Changes The proposed revision to TS 3/4.7.4:
LCO 3.7.4 would state:
The ultimate heat sink shall be OPERABLE with an average supply water temperature less than or equal to 104°F**.
APPLICABILITY remains unchanged.
ACTION required remains unchanged except for the correction of a typographical error.
The capitalized word 'In' before the words 'COLD SHUTDOWN' is properly reduced to lower case because it is not at the beginning of the sentence. This is an administrative change that does not alter the required action. The typographical error was introduced when FPL provided the NRC retyped pages for License Amendments 260 and 255.
Current SR 4.7.4 would be revised as follows:
4.7.4 The ultimate heat sink shall be determined OPERABLE:
Florida Power & Light Company L-2014-235 Supplement to License Amendment Request No. 231 Enclosure I Page 4 of 5
- a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average supply water temperature*
is less than or equal to 104 0F**.
SR 4.7.4.b would be added:
- b. At least once per hour by verifying the average supply water temperature* is less than or equal to 104°F**, when water temperature exceeds 100°F**.
The asterisk (*) refers to a footnote that remains unchanged.
The double asterisk (**) refers to a footnote that would state:
- Instrument uncertainty shall be added to the indicated value.
Also, the wording in SRs 4.7.4.a and 4.7.4.b is revised to be consistent with the LCO when referring to the LCO limit as being 'less than or equal to.'
A mark-up of the proposed TS revision is contained in Attachment 1.
The current TS bases above will be supplemented with the following two paragraphs:
Verifying UHS water temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is adequate to ensure the limit of 104'F is not exceeded when the water temperature is less than 100°F.
Due to daily variations in temperature, when UHS water temperature exceeds I 00°F the water temperature shall be verified at least once per hour to ensure that cooling canal system temperature variations are appropriately captured thus ensuring the Technical Specification limit is not exceeded.
For the UHS water temperature monitoring Surveillance Requirements, instrument measurement uncertainty is added to the indicated value to ensure the Technical Specification limit is not exceeded.
A mark-up of the TS bases revision is contained in Attachment 2.
3.0 Discussion of Change to the Application The Reference 1 application proposed to revise the UHS water temperature limit from lOO°F to 104 0 F with consideration for instrument uncertainty.
The wording in SRs 4.7.4.a and 4.7.4.b is revised to be consistent with the LCO when referring to the LCO limit as being 'less than or equal to.'
Florida Power & Light Company L-2014-235 Supplement to License Amendment Request No. 231 Enclosure I Page 5 of 5 A revision to new TS SR 4.7.4.b is proposed that will increase the frequency of monitoring UHS temperature when water temperature exceeds 100°F from at least once every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to at least once per hour. This increased frequency ensures that cooling canal system temperature variations are appropriately captured. The frequency is based on experience with temperature trends over the course of each day.
A new footnote (**) is added to require instrument uncertainty to be added to the indicated value of UHS water temperature for verifying compliance with the LCO.
The change to the requested revisions to TS 3/4.7.4 contained in this supplement would provide additional restrictions on the verification of UHS water temperature. These revisions to the proposed SRs do not alter the bases in the technical evaluation contained in the Reference I application. FPL concluded therein that safe operation of both Turkey Point units would be assured with UHS water temperature up to 104'F. The conclusion derived from those analyses remains unchanged and bounds the revised request discussed herein.
The revision to the TS changes requested in this supplement do not alter the determination of no significant hazards and the environmental considerations contained in the Reference 1 application because the revised request is bounded by the basis for change to a higher UHS temperature limit contained in the application, and the proposed changes to the TS SRs provide additional restrictions on verifying compliance with the UHS water temperature limit.
4.0 Reference
- 1. Florida Power & Light Company (FPL) Letter L-2014-216, "License Amendment Request No. 231, Application to Revise Technical Specifications to Revise Ultimate Heat Sink Temperature Limit," dated July 10, 2014
Enclosure 1 Attachment I Turkey Point Units 3 and 4 License Amendment Request No. 231 - Supplement Proposed Changes to Technical Specification 3/4.7.4 Page 3/4 7-17 Mark-Up (one page)
PLANT SYSTEMS 3/4.7.4 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.4 The ultimate heat sink shall be OPERABLE with an average supply water temperature less than or equal to 10I APPLICABILITY: MODES 1. 2, 3. and 4.
ACTION:
With the requirements of the above specification not satisfied, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in 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 />. This ACTION shall be applicable to both units simultaneously. AI SURVEILLANCE REQUIREMENTS 4.7.4 The ultimate heat sink shall be determined OPEABL supplywatef tep~tw leo 1PWithin W Ifitclmt.
at l-ast oncc Dor I ~i nourc DV vcrrn:ina mo ~.'orocio I
<j1a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average supply water temperature* is less than or equal to 1040 F**.
<jb. At least once per hour by verifying the average supply water temperature* is less I than or equal to 104°F**, when water temperature exceeds 1OOOF**.
- Portable monitors may be used to measure the temperature.
-ý--**lnstrument uncertainty shall be added to the indicated value. I TURKEY POINT - UNITS 3 & 4 3/4 7-17 AMENDMENT NOS. 2-6 AND 266 1
Enclosure 1 Attachment 2 Turkey Point Units 3 and 4 License Amendment Request No. 231- Supplement Change to Technical Specification Bases 3/4.7.4 Mark-Up (three pages)
REVISION NO.: PROCEDURE TITLE: PAGE:
10 TECHNICAL SPECIFICATION BASES CONTROL PROGRAM 147 of 192 PROCEDURE NO.:
0-ADM-536 TURKEY POINT PLANT ATTACHMENT 2 Technical Specification Bases (Page 131 of 176) 3/4.7.2 Component Cooling Water System The OPERABILITY of the Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single active failure, is consistent with the assumptions used in the safety analyses.
One pump and two heat exchangers provide the heat removal capability for accidents that have been analyzed.
3/4.7.3 Intake Cooling Water System The OPERABILITY of the Intake Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The design and operation of this system, assuming a single active failure, ensures cooling capacity consistent with the assumptions used in the safety analyses.
3/4.7.4 Ultimate Heat Sink lower case The " " " perature in conjunction with theU REQUIREMENTS f Technical Specification 3/4.. "capacity is available either:
(1) To provide normal cooldown of the facility, or (2) To mitigate the effects of accident conditions within acceptable limits.
FPL has the option of monitoring the UHS temperature by monitoring the temperature in the ICW System piping going to the inlet of the CCW Heat Exchangers. Monitoring the UHS temperature after the ICW but prior to CCW Heat Exchangers is considered to be equivalent to temperature monitoring before the ICW Pumps. The supply water leaving the ICW Pumps will be mixed and therefore, it will be representative of the bulk UHS temperature to the CCW Heat Exchanger inlet. The effects of the pump heating on the supply water are negligible due to low ICW head and high water volume.
Accordingly, monitoring the UHS temperature after the ICW Pumps but prior to the CCW Heat Exchangers provides an equivalent location for monitoring the UHS temperature.
REVISION NO.: PROCEDURE TITLE: PAGE:
10 TECHNICAL SPECIFICATION BASES CONTROL PROGRAM 148 of 192 PROCEDURE NO.:
0-ADM-536 TURKEY POINT PLANT ATTACHMENT 2 Technical Specification Bases (Page 132 of 176) 3/4.7.4 (Continued) 4 With the implementation of the CCW Heat changer Performance Monitoring Program, the limiting UHS tem rrature can be treated as a variable with an absolute upper limit of 100°F without compromising any margin of safety. Demonstration of actual heat exchanger performance capability supports system operation with postulated canal temperatures Eý.lle ater than 100Z. Therefore, an upper Technical Specification limit of 1WF is conservt-ti.-j]
3/4.7.5 Control Room Emerciency Ventilation System The OPERABILITY of the Control Room Emergency Ventilation System (CREVS) ensures that: (1) The ambient air temperature does NOT exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system, and (2) The Control Room envelope (CRE) will remain habitable for occupants during and following an uncontrolled release of radioactivity, hazardous chemicals, or smoke. The OPERABILITY of this system in conjunction with Control Room design provisions is based on limiting the radiation exposure to personnel occupying the CRE to 5 rem Total Effective Dose Equivalent (TEDE) for the duration of the accident. The radiological limits are consistent with the requirements of 10 CFR Part 50.67. CRE occupants are protected from chemical hazards in accordance with the limits of Regulatory Guide 1.78.
Insert A Verifying UHS water temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is adequate to ensure the limit of 104'F is not exceeded when the water temperature is less than 100lF. Due to daily variations in temperature, when UHS water temperature exceeds 100°F the water temperature shall be verified at least once per hour to ensure that cooling canal system temperature variations are appropriately captured thus ensuring the Technical Specification limit is not exceeded.
For the UHS water temperature monitoring Surveillance Requirements, instrument measurement uncertainty is added to the indicated value to ensure the Technical Specification limit is not exceeded.
Enclosure 2 Turkey Point Units 3 and 4 License Amendment Request No. 231 Response to Request for Additional Information (RAI)
RAIs 1-3
Florida Power & Light Company L-2014-235 License Amendment Request No. 231 Enclosure 2 Response to Request for Additional Information Page 1 of 2 Turkey Point Units 3 and 4 License Amendment Request No. 231 Response to Request for Additional Information (1-3)
Enclosure 2 By letter dated July 10, 2014, as supplemented by letter dated July 17, 2014, Florida Power & Light Company (FPL) submitted a license amendment request for the Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point). FPL requested revisions to the Turkey Point Technical Specifications (TSs), Section 3/4.7.4, "Ultimate Heat Sink."
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the information provided by FPL and determined that it needs additional information to complete the review. The NRC staff's request for additional information (RAI) was provided to FPL in Reference 1 and the FPL response to RAIs 1-3 is as follows.
NRC RAI 1 Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.36(a) requires each applicant for a license to include proposed TSs as well as a summary statement of the bases or reasons for such specifications. Please provide a copy of the TS Bases associated with the proposed TSs.
FPL Response A copy of the TS bases associated with the proposed revision to the TS is contained in Attachment 2 of Enclosure I in this correspondence.
NRC RAI 2 Paragraph 50.36(c)(3) of 10 CFR states that Surveillance Requirements (SRs) "assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits and that the limiting conditions for operation [LCOs] will be met." The proposed frequency for the new SR 4.7.4.b is "at least once per 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> when water temperature exceeds 100°F [degrees Fahrenheit]." Please provide a justification for the 6-hour frequency that demonstrates that the frequency assures that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCO will be met.
Florida Power & Light Company L-2014-235 License Amendment Request No. 231 Enclosure 2 Response to Request for Additional Information Page 2 of 2 FPL Response As discussed in Section 3.0 of Enclosure I in this correspondence and as shown in the marked-up TS page in Attachment 1 of Enclosure 1, the proposed increased frequency of verifying ultimate heat sink (UHS) water temperature when 100°F is exceeded is revised to at least once per hour from at least once per 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This increased frequency ensures that cooling canal system temperature variations are appropriately captured. The frequency is based on experience with temperature trends over the course of each day, and assures that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCO will be met.
NRC RAI 3 The text referring to the water temperature limit is inconsistent between the LCO 3.7.4 statement and SRs 4.7.4.a and b. The LCO statement uses the text "less than or equal to 104'F," whereas SR 4.7.4.a uses the text "its limit," and SR 4.7.4.b uses the text "the limit." Surveillance requirements assure that the LCO will be met. Therefore, please propose new text referring to the water temperature limit in the SRs that is consistent with the LCO text.
FPL Response As discussed in Sections 2.2 and 3.0 of Enclosure I in this correspondence and as shown in the marked-up TS page in Attachment I of Enclosure 1, the wording of TS SR 4.7.4.a and 4.7.4.b are revised to be consistent with the wording of the LCO. The LCO and SRs state "...less than or equal to..." the 104'F limit.
Reference
- 1. Email from NRC Project Manager for Turkey Point to FPL, "Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TAC MF4392 and MF4393)," dated July 18, 2014 (RAIs 1-3)