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Category:Graphics incl Charts and Tables
MONTHYEARML22054A1382022-02-16016 February 2022 February 24, 2022 ITS Public Meeting Material - Florida Power and Light L-2021-138, GL 2004-02 Debris Transport Calculation Non-Conservatism2021-07-15015 July 2021 GL 2004-02 Debris Transport Calculation Non-Conservatism ML19221B5832019-07-25025 July 2019 Biological Opinion for Turkey Point Nuclear Plant Units 3 and 4 License Renewal L-2019-020, Subsequent License Renewal Application Environmental Report Environmental Authorizations Updated Information2019-01-23023 January 2019 Subsequent License Renewal Application Environmental Report Environmental Authorizations Updated Information ML18187A0282018-07-23023 July 2018 Numeric Nutrient Criteria Violations ML18187A0322018-07-23023 July 2018 Water Gradient Charts L-2018-067, Units 1 and 2 - Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Units 1 and 2 - Submittal of Joint Plant Access Shared Information Table L-2016-109, Official Service List Changes and Distribution for Safeguards Information and Official Use Only-Security-Related Information2016-05-11011 May 2016 Official Service List Changes and Distribution for Safeguards Information and Official Use Only-Security-Related Information ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15054A0372015-02-23023 February 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Fire PRA Facts and Observations for Turkey Point Nuclear Generating Stations, Units 3 and 4 ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 L-2008-002, Corporate Merger of Decommissioning Trustee2008-01-0303 January 2008 Corporate Merger of Decommissioning Trustee ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists L-2005-141, 10 CFR 50.55a Request for Mechanical Clamping Device Used as Piping Pressure Boundary2005-06-20020 June 2005 10 CFR 50.55a Request for Mechanical Clamping Device Used as Piping Pressure Boundary ML0501202612005-01-12012 January 2005 December Monthly Report on the Status of Open TIAs Assigned to NRR ML0434802422004-12-29029 December 2004 November Monthly Report on the Status of Open TIAs Assigned to NRR ML18227B2811978-09-27027 September 1978 Submit Appendix a, Revised ECCS Analysis L-78-297, Supplemental Information on Request to Amend Facility Operating Licenses Additional Information1978-09-13013 September 1978 Supplemental Information on Request to Amend Facility Operating Licenses Additional Information L-78-271, 08/16/1978 Letter Thermal & Hydraulic Safety Limits1978-08-16016 August 1978 08/16/1978 Letter Thermal & Hydraulic Safety Limits L-78-264, 08/09/1978 Letter Order for Amendment to Facility Operating Licenses DPR-31 & DPR-411978-08-0909 August 1978 08/09/1978 Letter Order for Amendment to Facility Operating Licenses DPR-31 & DPR-41 L-78-217, 06/22/1978 Letter Proposed Modifications to Technical Specification Figure 2.1-1, Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation1978-06-22022 June 1978 06/22/1978 Letter Proposed Modifications to Technical Specification Figure 2.1-1, Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation ML18227B7861978-01-0303 January 1978 Letter Transmitting Procedure for Evaluation of Maximum Setpoint Overshoot Heat Input Transient & Supplement to July 1977 Report of Pressure Mitigating Systems, Transient Analysis Results L-77-381, Letter Transmitting Revision 1 to Steam Generator Repair Report Which Was Forwarded on 9/20/19771977-12-20020 December 1977 Letter Transmitting Revision 1 to Steam Generator Repair Report Which Was Forwarded on 9/20/1977 ML18227D2661977-05-10010 May 1977 05/10/1977 Letter Groundwater Monitoring Data Report No. 59 for May 1977 Monitoring Period for E-Series Wells, and Results of Transmissivity Test for Quarter Ending March 1977 L-77-106, 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty1977-04-0404 April 1977 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty ML18227B0141977-02-0202 February 1977 Response to Request for Additional Information on ECCS Reevaluation Supplemental Information ML18227D2901977-01-0707 January 1977 Submit Refueling Information (Cycle 4) Which Will Not Involve Any Unreviewed Safety Questions ML18227D2911977-01-0707 January 1977 Submit Refueling Information (Cycle 4) Which Will Not Involve Any Unreviewed Safety Questions ML18227C9041977-01-0303 January 1977 Letter Transmitting Copy of Revised ECCS Calculations Report Forwarded on 12/30/1976 with Several Revised Pages to Improve Clarity L-77-434, Answers to Question Nos. 2 and 7 and Revised Answers to Questions 8 and 9 Pertaining to the Steam Generators Tube Integrity Supplemental Information1976-12-30030 December 1976 Answers to Question Nos. 2 and 7 and Revised Answers to Questions 8 and 9 Pertaining to the Steam Generators Tube Integrity Supplemental Information L-76-438, Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt1976-12-30030 December 1976 Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt L-76-225, Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a Tech Spec, Concerning Cask Handling1976-06-24024 June 1976 Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a Tech Spec, Concerning Cask Handling L-76-201, Letter Submits Proposed Amendment to Facility Operating License with Supplemental Information Submitted as Appendix B of Spent Fuel Storage Facility Modification Safety Analysis Report1976-05-25025 May 1976 Letter Submits Proposed Amendment to Facility Operating License with Supplemental Information Submitted as Appendix B of Spent Fuel Storage Facility Modification Safety Analysis Report L-76-199, Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ...1976-05-21021 May 1976 Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ... ML18227A9811975-09-30030 September 1975 Submit Appendix Nos. a, B, C, D, E, F, G, H, I, J. L-75-246, Responding to Letter of 5/15/75, Letter Furnishing Analyses & Other Relevant Info to Determine Potential for Occurrence & Potential Consequences of Secondary System Fluid Flow Instability (Water Hammer)1975-07-0303 July 1975 Responding to Letter of 5/15/75, Letter Furnishing Analyses & Other Relevant Info to Determine Potential for Occurrence & Potential Consequences of Secondary System Fluid Flow Instability (Water Hammer) ML18227A4671975-03-21021 March 1975 Letter Reporting Abnormal Occurrence No. 251-75-4 of Lateral Restraints for Spent Fuel Racks Broken, in Unit 4 on 3/12/1975 ML18227D1101975-02-0707 February 1975 Letter Re Description of Cycle 2 Reload Fuel 2022-02-16
[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
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t NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL (TEMPORARY FORM) t CONTROL NO:
FILE FROM. Florida Power & Light Co. DATE OF DOC DATE REC'D LTR TWX RPT OTHER Miami, Fla.
Robert.E Uhri TO: ORIG CC OTHER SENTNRC PDR George Lear 3 Signed SENT LOCAL PDR
'LASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
0-250 251 DESCRIPTION ENCLOSURES:
Ltr. Re our ltr. of 5-15-75, analyses 6 other relevant info needed to determine the potenti for occurrence 6 potential consequences of secondary system fluid flow instability (wate
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PLANT NAME: Turkey Point 3 6 4 FOR ACTION/INFORMATION BUTLER (L) SCHWENCER (L) ZIEMANN (L) RERAN (E)
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Operating Reactors Branch No. 3 Division of Reactor Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Lear:
TURKEY POINT NIT S. 3 AND 4 DOCKET NOS. 50-250 AND 50-251 WATER HAMMER I PWR F DWATER SYSTEMS Your letter of May 15, 1975, requested that we provide you with analyses and other relevant information needed to determine the potential for occurrence and the potential consequences of secondary system fluid flow instability ("water hammer") in our nuclear plants. The following input, numbered to correspond to your questions, is provided.
l.'t is expected that the following operating occurrences could cause the level of the water/steam interface in the steam generator to drop below the feedwater inlet nozzle:
A. Loss of Normal Feedwater (FSAR Section 14.1.11).
Loss of normal feedwater can be caused by a pipe break, pump failures, valve malfunctions, or loss of outside ac power. Steam generator water level will fall as steam flow continues to dissipate stored and generated heat from the reactor coolant. When the level has fallen to the low-low level point, a reactor trip will occur (if it has not already been manually initiated) and three turbine-driven auxiliary feedwater pumps will start automatically. The transient will produce a lower water level if the initial water level is low, the initial reactor power is high, or the auxiliary feed rate is low.
B. Reactor Trip (FSAR Table 7.2-1 lists various trips)
A rapid down power transient results in a collapse of secondary side steam voids and an initial decrease in steam generator level ("shrink"). If the initial water level is low and reactor power is high, the transient may result in uncovering the feedwater inlet nozzle.
7321 HELPING BUILD FLOFI IDA
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Mr. George Lear, Chief Page Two July 3, 1975
- 2. Feedwater piping isometric diagrams are contained in an attachment to this letter.
- 3. There have been three known occurrences of "water hammer" in feedwater piping at Turkey Point Unit Nos. 3 and 4.
They were reported to the Director Region II, Directorate of Regulatory Operations. on February 6, 1974, in a letter response to Regulatory Operations Information Request No.
74-1.
The first occurrence was indicated by body-to-bonnet leakage and slight elongation of some body-to-bonnet bolts on the 3B feedwater check valve.
The second occurrence was indicated by the same kind of leakage and bolt elongation on the 4B feedwater check valve.
The third occurrence was indicated by the following deformations discovered inside containment during an outage of Unit No. 4. They occurred on the "A" steam generator feedwater piping.
A. Some expansion bolts for two hydraulic pipe restraints had been pulled approximately one inch out of a concrete wall.
B. Two spring hanger mounting plates had been deformed.
C. There had been slight plastic deformation in a located in the piping leading to the steam 90'lbow generator feedwater nozzle.
The corrective action was to minimize the length of feedwater piping which could drain into the steam generator through the feed ring. This was done by shortening the horizontal length of pipe at the level of the feedwater inlet nozzle. The piping now turns'own through a approximately five feet from the steam generator.
90'lbow This modification was performed on the "A" and "B" steam generator feedwater piping for both units. The feedwater piping for the "C" steam generators was not modified because the eight foot horizontal length at the nozzle elevation was evaluated and found to be acceptable. There has been no evidence of water hammer occurrences in steam generator feedwater piping since completion of the modifications.
Mr. George Lear, Chief Page Three July 3, 1975
- 4. Analyses of the feedwater and auxiliary feedwater piping using dynamic forcing functions have not been performed.
Based on our operating experience following modifications to feedwater piping (described in section 3 of this letter), we feel functions.
it may not be necessary to develop forcing These modifications have been satisfactory in that there has been no further water hammer damage since their completion.
A test program designed to study the "water hammer" phenomena has not been developed specifically for Turkey Point. However, because several of their operating plants have experienced water hammer, our NSSS vendor has initiated a research effort to study the causes of this problem and determine possible remedies.
following conclusions reached so far are considered The applicable to our Turkey Point nuclear plant:
A. Water hammer can be generated by partial drainage of the feedwater line through the feed ring when steam generator water level drops below the ring. Steam enters through the ring and is condensed at the inter-face with the cold water being supplied by the auxiliary feedwater system. This generates steam flow in a direction opposite the incoming feedwater flow. Ifita water seal is then formed anywhere in the piping, could trap a steam bubble which could then rapidly collapse and force a water slug down the feed line.
B. The potential water hammer force is greater if a greater horizontal length of feedwater piping is available for acceleration of the water slug.
C. =-
Water slug formation may not occur at reduced feedwater flow rates.
D. Water slugs are most likely formed when the feed ring has been partially refilled.
In order to avoid duplication of the NSSS vendor effort, we have not initiated an independent water hammer test.
program at Turkey Point. Also, the plant modifications described in sections 3 and 6 of this letter have apparently eliminated or at least reduced the effects of water hammer because no new indications of water hammer damage have been observed since the modifications were made.
I' Mr. George Lear, Chief Page Four July 3, 1975
- 5. In the event of a design basis loss-of-coolant accident with concurrent turbine trip and loss of offsite power, the following is expected to occur (FSAR Sections 14.1.12 and 14.3.1):
The reactor trips on low pressurizer level. Safety injection is initiated automatically on low pressurizer level in conjunction with low pressurizer pressure. (In this case, reactor trip and initiation of safety injection can also be caused by high contain-ment pressure.) Complete loss of off-site power and turbine trip cause a loss of power to auxiliaries.
Both emergency diesels start on initiation of the safety injection signal and automatically supply power to emergency loads. Core heat is transferred to the primary coolant and then to the secondary system in the steam generators. Steam system pressure subsequently increases and the steam system power relief valves are automatically opened to the atmosphere. If steam flow through the power relief valves is not sufficient, the steam generator self-actuated safety valves may tem-porarily lift to augment steam flow. Normal feedwater flow is lost upon initiation of the accident, but steam driven auxiliary feed pumps automatically start to supply makeup feedwater to the steam generators. (Also, a safety injection signal will stop normal feedwater flow and start auxiliary flow.) Steam generator water level will decrease rapidly due to a reduction of steam generator void fraction on the secondary side and also because steam flow continues after normal feedwater flow stops. A delay in establishing full auxiliary feedwater flow could result in uncovering of the steam generator feedwater inlet nozzle. The control room reactor operator monitors steam generator water level and controls auxiliary feedwater flow with remotely operated control valves.
- 6. Modifications to the feedwater piping to steam generators "A" and "B" have been made on Turkey Point Unit Nos. 3 and 4.
These modifications were based on NSSS vendor recommendations.
In all cases, the modification was to reduce the horizontal run of feedwater piping entering the steam generator at the level of the feedwater inlet nozzle. Such a piping change minimizes the effect of water hammer by reducing the length of feedwater piping that can drain into the steam generator.
Subsequent vendor research has confirmed that the probability of damage from water hammer can be kept to a minimum by elimination of long horizontal pipe runs at the level of the steam generator feedwater inlet nozzle.
0 4 Mr. George Lear, Chief Page Five July 3, 1975 NSSS vendor research has also resulted in a recommendation to limit auxiliary feed flow rate to 150 gpm during recovery of a drained feedwater inlet nozzle under other than emergency conditions. This is a conservative limit to minimize the probability of water hammer.
Auxiliary feed flow is manually controlled at Turkey Point with the operator routinely limiting flow rate to the minimum necessary to meet operating requirements. Specific administrative means or other more positive means such as interlocks have not been incorporated into plant design or procedure. We feel that such means have not been definitely determined as necessary for our nuclear plants. However, we shall be reviewing subsequent results from NSSS vendor test programs and, if necessary, shall reevaluate our position based on those results.
Very t uly yours, Robert E. Uhrig Vice President REU/MAS/cpc Attachment cc: Jack R. Newman, Esquire
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