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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:Legal-Affidavit
MONTHYEARML23333A0192023-11-27027 November 2023 Att. K- Bill Powers 2023 Expert Declaration ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - 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-2023-069, 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-2023-010, 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-2022-166, 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 ML22243A1622022-08-26026 August 2022 Submittal of License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML22172A2072022-06-16016 June 2022 Affidavit Dated June 16, 2022 ML22144A3922022-05-18018 May 2022 Affidavit Dated May 18 2022, Executed by Phillip A. Opsal - Framatome (Public Available) L-2022-073, Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-05-0303 May 2022 Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 ML22101A2042022-04-0606 April 2022 Nextera/Fpl Affidavit for Proprietary Presentation for April 13, 2022 Public Meeting Re Planned Turkey Point Digital Instrumentation and Controls License Amendment Request ML22115A1772022-03-12012 March 2022 Affidavit Dated March 12 2022, Executed by Phillip A. Opsal - Framatome ML22063A4482022-03-0202 March 2022 Nextera/Fpl Affidavit for Proprietary Presentation for March 7, 2022, Public Meeting ML22047A1342022-02-14014 February 2022 Affidavit Dated February 14, 2022, Executed by Paul S. Manzon 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 ML21200A1572021-07-18018 July 2021 July 18, 2021 - Framatome Affidavit for Nextera/Fpl Meeting Slides for July 22, 2021 Partially Closed Meeting Concerning Control Room Digital Modernization ML21159A1652021-06-0404 June 2021 Affidavit for Nextera Tricon Presentation for Turkey Point 5th Presubmittal Meeting ML21047A2152021-02-16016 February 2021 Affidavit for NRC Presubmittal Meeting Telecon February 18, 2021 Open Meeting - FPL Safety System Replacement Project LAR - Nonproprietary ML21011A2352021-01-11011 January 2021 Affidavit for Slides for January 13, 2021 Presubmittal Meeting with NextEra Concerning Digital I&C L-2020-104, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 7 for Train a and B Component Cooling Water (CCW) Supply and Return Piping2020-09-18018 September 2020 Fifth Ten-Year Inservice Inspection Interval Relief Request No. 7 for Train a and B Component Cooling Water (CCW) Supply and Return Piping 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 ML18299A1142018-10-24024 October 2018 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 4 Responses ML18296A0242018-10-16016 October 2018 Set 3 Response to Request for Additional Information to Subsequent License Renewal Application Safety Review 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) 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) ML18053A1372018-02-16016 February 2018 Subsequent License Renewal Application - Supplement 2 L-2018-039, License Renewal Application - Supplement 12018-02-0909 February 2018 License Renewal Application - Supplement 1 L-2017-062, Request for Withholding Information from Public Disclosure Subsequent License Renewal Notification2017-03-30030 March 2017 Request for Withholding Information from Public Disclosure Subsequent License Renewal Notification L-2016-202, Notice of Intent to Pursue License Renewal, Request for Withholding from Public Disclosure2017-03-0303 March 2017 Notice of Intent to Pursue License Renewal, Request for Withholding from Public Disclosure L-2015-189, License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement2015-10-0606 October 2015 License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement ML12027A0422012-01-12012 January 2012 Westinghouse Input to NRC Frapcon Models Related to the Turkey Point Unit 3 & 4 Extended Power Uprate (EPU) License Amendment Request (LAR) (Cover Letter) L-2011-100, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Nuclear Performance and Code Review Issues2011-05-18018 May 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Nuclear Performance and Code Review Issues ML1035601812010-12-20020 December 2010 License Amendment Request for Extended Power Uprate, Attachment 05; Westinghouse & Areva Affidavits for Attachment 4 L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 05; Westinghouse & Areva Affidavits for Attachment 42010-12-20020 December 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 05; Westinghouse & Areva Affidavits for Attachment 4 L-2010-113, License Amendment Request for Extended Power Uprate, Attachment 13; Westinghouse Affidavit for Attachment 122010-08-11011 August 2010 License Amendment Request for Extended Power Uprate, Attachment 13; Westinghouse Affidavit for Attachment 12 L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 11; Westinghouse Affidavit for Attachment 102010-07-26026 July 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 11; Westinghouse Affidavit for Attachment 10 ML1035601872010-07-26026 July 2010 License Amendment Request for Extended Power Uprate, Attachment 11; Westinghouse Affidavit for Attachment 10 L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 09; Cameron Affidavit for Attachment 82010-07-16016 July 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 09; Cameron Affidavit for Attachment 8 ML1035601852010-07-16016 July 2010 License Amendment Request for Extended Power Uprate, Attachment 09; Cameron Affidavit for Attachment 8 ML18228A1321979-03-0909 March 1979 Licensee'S Response to Untimely Request for Hearing of Mark P. Oncavage L-78-323, Submit Supplemental Information for Proposed Amendment to Facility Operating Licenses to Operate Until Next Refueling Prior to Conducting Steam Generator Inspection1978-10-0202 October 1978 Submit Supplemental Information for Proposed Amendment to Facility Operating Licenses to Operate Until Next Refueling Prior to Conducting Steam Generator Inspection ML18227B3061978-08-25025 August 1978 Application for Extension of Time 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-78-233, 07/11/1978 Letter Request to Amend Appendix a of Facility Operating Licenses1978-07-11011 July 1978 07/11/1978 Letter Request to Amend Appendix a of Facility Operating Licenses 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 L-78-123, 04/10/1978 Response to Request for Additional Information Proposed Inservice Inspection and Pump & Valve Test Programs1978-04-10010 April 1978 04/10/1978 Response to Request for Additional Information Proposed Inservice Inspection and Pump & Valve Test Programs ML18227D4111978-03-0707 March 1978 Transmitting Steam Generator Repair Report, Revision 2 ML18227D8091978-01-27027 January 1978 01/27/1978 Letter Request to Amend Appendix a of Facility Operating Licenses ML18227B2801978-01-27027 January 1978 Submit Proposed Facility Operating Licenses with ECCS Reanalysis 2023-09-22
[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] |
Text
Q oS'P +S R-GULATORY INFORMATION DISTRIBUTION SYST M (RIDS>
DISTRIBUTION FOR INCOMING MATERIAL 50-250'251 SEC: STELLQ V QRG. Ul-lRIG R E DQCDATE 08/Q9/78 NRC FL PWR 5 LIGHT DATE RCVD: 08/14/7c DOCTYP-: LETTER NOTARIZED: YE COPIES RECEIVED SUBJECT LTR - ENCL 40 FORWARDING LIC NOS DPR-3i 8: 41 APPL FOR AMEND: TECH SPEC PROPOSED CHANGE CONCERNING REVISION TO Tf<E ECCS COOLING PERFORMANCE AS LISTED AND REQUESTING
, ROVISIONS OF NRC"S 06/07/78 ORDER BE DELETED... NOTARIZED 08/09/78.
,"LANT NAME: TURKEY PT N3 REVIEWER INITIAL: X JM TURKEY PT 04 DISTRIBUTER INITIAL: ~
DISTRIBUTION O- THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FQR AFTFR ISSUANCEOF OPERATING LICFNSE.
(DISTRIBUTION CODE AOOi)
FOR ACTION: BR Cl.II EF ORB01 BC+4 W/7 ENCL INTERNAL: REG FI'LE4f+W/ENCL NRC PDP++W/ENCL I-8. E++W/2 ENCL OELD++LTR ONLY HANAUER<;ccW/ENCL CORE PERI=QRMANCE BR++W/ENCL AD FQR SYS 8. PROJ++W/ENCL ENG I NEER ING BR++W/ENCL REACTOR SAFETY BR++W/ENCL PLANT SYSTEMS BR++W/ENCL EEB++W/ENCL EFFLUENT TREAT SYS+~W/ENCL J. MCGOUGH~f+W/ENCL EXTERNAL: LPDR'S MIAMI i FL++W/ENCL TERA~f4W/ENCL NSIC~~W/ENCL ACRS CAT B++W/ib ENCL
.ISTRIBUTION: LTR 40 ENCL 39 CONTROL NBR: 782190052 SIZE: 3P+29P t 8f M %%%8f%%%%%%4+wf+%%%%%4%%%4%%%4%4. Tf)E END %% M 4%c% 3f%%%%44 %%%%%%4 %%%4%4%%%%%%
FLORIOA POWER 8t LIGHT COMPANY August 9, 1978 L-78-264 Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Mashington, 0. C. 20555
Dear Mr. Stello:
Re ~
Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 An Order for Modification of License, dated June 7, 1978, was issued by the Commission for Turkey Point Units 3 and 4. The Order amended Facility Operating Licenses DPR-31 and DPR-41 by adding the following provisions:
(1) As soon as possible, the licensee shall submit a re-evaluation of ECCS cooling performance calculated in accordance with the Mestinghouse Evaluation Model, approved by the NRC staff and corrected for the errors described herein.
(2) Until further authorization by the Commission, the Technical Specification limit for total nuclear peaking factor (Fq) for the facility shall be limited to 2.03 and 1.91 for Unit Nos.
3 and 4, respectively.
(3) Until further authorization by the Commission, the licensee shall conduct the operating surveillance program described in.
tionss, its letter of April 10, 1978.
Mestinghouse has reevaluated ECCS cooling performance in accordance with a corrected evaluation model that we understand has been approved by the NRC staff. The reevaluation supports a Technical Specification limit for total nuclear peaking factor (F<) of 2.03 for both Units 3 and 4, assuming 255 steam generator tube plugging. Based on Mestinghouse core physics calcula-the maximum values of Fq that could occur for the remainder of Unit 3, Cycle 5 and for the upcoming Unit 4, Cycle 5 are 2.02 and 2.00, respectl'vely Because the maximum predicted Fq values are less than the maximum allowable value derived from the corrected ECCS evaluation, the augmented surveillance procedures discussed in Florida Power 8 Light Company (FPL) letter L-78-127 of April 10, 1978 will not be necessary during Cycle 5 of both Units 3 and 4.
PEOPLE... SERVING PEOPLE
Director of Nuclear Reactor Regulation Page Two As a result of the ECCS reevaluation performed in compliance with the Commission's Order of June 7, FPL submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating Licenses OPR-31 and DPR-41. l<e also request that the provisions of the June 7 Order be deleted. The proposed amendments to Appendix A are described below and shown on the a'ccompanying Technical Specifications bearing the date of this letter in the lower right hand corner.
Pa e 3.2-3 Specification 3.2.6.a (Power Distribution Limits) is revised to reflect the results of the correct d Westinghouse ECCS evaluation.
Fi ures 3.2-3 and 3.2-3a The current figures are deleted and replaced with a single Figure 3.2-3 (Hot Channel Factor Normalized Operating Envelope) that is valid for an Fq of 2.03 and steam generator tube plugging <251..
Pa es 83.2-4 and 83.2-6 Bases Section B3.2 (Control and Power Distribution Limits) is revised to delete superseded Fq values.
The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Conmittee and the Florida Power 8 Light Company Nuclear Review Board.
They have concluded that it does not involve an unreviewed safety question.
Yery ly yours, obert E. Uhrig Yice President REU/HAS/cpc
'ttachment cc: Yu . James P. O'Reilly, Region II Robert Lowenstein, Esquire
reactivity insertion upon ejection greater than 0.3/= Q k/k at rated po~er.
Inoperable rod worth shall be determined within 4 weeks.
- b. A control rod shall be considered inoperable (a) the rod cannot be moved by the CRDH, or if (b) the rod is misaligned from its bank by more than 15 inches, or (c) the rod drop time is not met.
- c. If a control rod cannot be moved by the drive mechanism, shutdown margin shall be increased by boron addition to compensate for the with-drawn worth of the inoperable rod.
'5. CONTROJ ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation mon-itor alarm are not operable rod positions shall be logged once per shift and after a load change greater than 10/ of rated power. If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93/ of rated power.
- 6. POWER DISTRIBUTION LZMITS
- a. Hot channel factors:
With steam generator tube plugging < 25%, the hot channel factors (defined in the basis) must meet the following limits at all times except during low power physics tests:
F (Z) < (2.03/P) x K(Z), for P > .5 q
F (Z) < (4.06) x K(Z), for P < .5 F~N < 1.55 (1.+ 0.2 (1-P) }
Where P is the fraction of rated power at which the core is operating; K(Z) is the function given in Figure 3.2-3; Z is the core height location of F If predicted Fq exceeds 2.03, the power will be limited to the rated power multiplied by the ratio of 2.03 divided by the predicted Fc, or augmented surveillance of hot channel factors shall be implemented.
- b. Following initial loading before the reactor is operated above 75% of rated power and at regular effective full rated power monthly intervals thereafter, power distribution maps, using the movable detector system shall be made, to confirm that the hot channel factor limits of the speci-fication are satisfied. For the purpose of this comparison, 302 3
HOT CHANNEL FACTOR-NORMALIZED OPERATING ENVELOPE (FOR STEAM GENERATOR TUBE PLUGG ING + 25% GQd Fq 2 0 3)
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An upper bound envelope as defined by the normalized peaking factor axial dependence of Figure 3.2-3 has been determined to be consistent with the technical specifications on power distribution control as given in Section 3.2.
When an F q
measurement is taken, both experimental. error and manufacturing tolerance must be allowed .for. Five percent is the appropriate experimental uncertainty allowance for a full core map taken with the movable incore detector flux mapping system and three percent is the appropriate allowance for manufacturing tolerance.
In the specified limit of F~, there is an 8 percent allowance for uncertain-ties which means that normal operation of the core is expected to result in F~<1.55/1.08. The logic behind'he larger uncertainty in this case is that (a) normal perturbations in the radial power shape (e.g., rod misalign-
'ent) affect P> , in most cases without necessarily. affecting F , (b) although the operator has a direct influence on F through movement of rods, and can limit it q to the desired value, he has no direct control over F~ N and (c) an error in the predictions for radial power shape, which may be detected during startup physics tests can be compensated for in F by tighter axial control, q
but compensation for FN is less readily available. When a measurement of P is taken, e~erimental error must be allowed for and 4X is the appro-
>
priate allowance for a full core map taken with the movable incore detec'tor flux mapping system.
Measurements of the hot channel factors are required as part of start-up physics tests, at least once each full rated power month of operation, and whenever abnormal power distribution conditions require a reduction of core power to a level based on measured hot channel factors. The incore map taken following initial loading provides confirmation of the basic nuclear B3.2-4
Flux Difference (Ag) and a reference value which. corresponds to the full design power equilibrium value of Axial Offset (Axial Offset ~ A4/fractional power). The reference value of flux difference varies with power level and burnup but expressed as axial offset it varies only with burnup.
The technical specifications on power distribution control assure that the F upper bound envelope as defined by Figure 3.2-3 is not exceeded and xenon q
distributions are not developed which at a later time, would causa greater local power peaking even though the"flux difference is then within the limits specified by the procedure.
The target (or reference) value of flux difference is determined as follows.
At any time that equilibrium xenon conditions have been established, the in-dicated flux difference is noted with part length rods withdrawn from the core and with the full length rod control rod bank more than 190 steps withdrawn (i.e., normal rated power operating position appropriate for the time in life.
Control rods are usually withdrawn farther as burnup proceeds). This value, divided by the fraction of design power at which the core was operating is the design power value of the target flux difference. Values for all other core power 1'evels are obtained by multiplying tne design power value by the fractional power. Since the indicated equilibrium value was noted, no allowances for excore detector error are necessary and indicated deviation of
+5% dI are permitted from the indicated reference value. During periods where extensive load following is required, it may be impractical to establish the required core conditions for measuring the target flux difference every rated power month. For this reason, methods are permitted by Xtem 6c of Section 3.2 for updating the target flux differences. Figure B3.2-1 shows a typica1 construction of the target flux difference band at BOL and Figure B3.2-2 shows the typical variation of the full power value with burnup.
Strict co'ntrol of the flux difference (and rod position) is not as necessary during part power operation. This is because xenon distribution control at part power is not as significant as the control at full power and allowance has been made in predicting tne heat flux peaking factors for less strict con-trol at part power. Strict control of the flux difference is not possible during certain physics tests or during the required, periodic excore calibra-B3.2-6
TABLE 1 LARGE BREAK TIME SEQUENCE OF EVENTS DECL (Sec)
START 0.0 Rx Trip Signal 0.535 S. I. Signal 0. 77.
Acc. Injection 16.1 End of Bypass 27.60 End of Blowdown 27.79 Bottom of Core Recovery 46.03 Acc. Empty 60.14 Pump Injection 25. 77
TABLE 2 LARGE BREAK DECL Results Peak Clad Temp. 'F 2173 Peak Clad Location Ft. 6.25 Local Zr/H20 Rxn(max)% 7.678 Local Zr/H20 Location Ft. 6.25 Total Zr/H20 Rxn <0.3 Hot Rod Burst Time sec 32.0 Hot Rod Burst Location Ft ~ 6. 25 Calculation Core Power Met 102% of 2200 Peak Linear Power kw/ft 102% of 11.53 Peaking Factor 2. 03 Accumulator Water Volume (ft3 ) 875 (per accumulator)
Cycle Analyzed Cycle Unit 3 and Unit 4 5
Page 1 of 3 TABLE 3 LARGE BREAK CONTAINMENT DATA (DRY CONTAINMENT) 6 NET FREE VOLUME 1.55 x 10 Ft INITIAL CONDITIONS Pressure 14.7 psia Temperature 90 'F RWST Temperature 39 'F Service Water Temperature 63 'F Outside Temperature 39 'F SPRAY SYSTEM Number of Pumps Operating 2 Runout Flow Rate 1450 gpm Actuation Time 26 secs SAFEGUARDS FAN COOLERS Number of Fan Coolers Operating 3 Fastests Post Accident Initiation of Fan Coolers 26 secs
Page 2 of 3 TABLE 3 (CONTINUED)
CONTAINMENT DATA (DRY CONTAINNENT)
STRUCTURAL HEAT SINKS THICKNESS AREA (INCH)
(FT )
Paint 0.006996 Carbon Steel 0.20 51824. 69 Carbon Steel 0.006996 996054.9 Paint 0.006996 Carbon Steel 0.4896 35660.11 Carbon Steel 0.4896 11886.7 Paint 0.006996 Carbon Steel 0.2898 Concrete 24.0 102000.0 Carbon Steel 0.2898 Concrete 24.0 34000.0 Paint 0.006996 Carbon Steel 1.56 4622.69 Carbon Steel 1.56 1540.89 Paint 0.006996 Carbon Steel 5.496 1277.87 Carbon Steel 5.496 425.93 Paint 0.006996 Carbon Steel 2.748 951.525 Carbon Steel 2.748 317.175 Paint 0.006996 Carbon Steel 0.03 23550.0 Paint 0.006996 Carbon Steel 0.063 80368.5 Paint 0.006996 Carbon Steel 0.10 42278.25 Paint 0.006996 Carbon Steel 0.006996 76800.0 Stainless Steel 0.4404 768.0
Page 3 of 3 TABLE 3 (CONTINUED)
CONTAINMENT DATA (DRY CONTAINMENT)
STRUCTURAL HEAT SINKS THI CKNESS AREA
( INCH) (FT )
Stainless Steel 2.1264 3704.0 Stainless Steel 0.1398 Concrete 24.0 14392. 0 Concrete 24 ' 59132.0
TABLE 4 REFLOOD MASS AND ENERGY RELEASES - DECLG (CD=0.4)
TINE MASS FLOWRATE ENERGY FLOWRATE (LBm/SEC)
(10 BTU/SEC) 46.028 0.0 0.0 47.653 0.2476 0.0032 53.696 34.83 0.4511 63.653 89.23 1.108 76.653 92.04 1.142 91.953 187.08 1.416 108.153 261.56 1.579 125.253 273.11 1.562 162.253 280.75 1.482 202.853 287.45 1.392
TABLE 5 BROKEN LOOP ACCUMULATOR FLOW TO CONTAINMENT FOR LIMITING CASE DECLG (CD=0.5) 25/
STEAM GENERATOR TUBE PLUGGING TIME (SEC) MASS FLOWRATE (LBm/SEC) 0.0 0.0 0.02 2770.1 2.00 2349.7 4.00 2083.2 6.00 1890.7 8.00 1748.9 10.0 1634.1 15.0 1417.4 20.0 1257.6 25.0 1157.3 30.0 1079.1 35.0 1014. 1 37.9 981. 7
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STATE OF FLORIDA ).
) ss COUNTY OF DADE )
Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power & Light Company, the Applicant herein:
That he has executed the foregoing document; that the statements made in this said document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Applicant.
Robert E. Uhrig Subscribed and sworn to before me this day of l9 7&-
NOTARY PUBLI , z.n and for the County of Dade, State of Florida NOTA'USUC STATE OF FLOAIOA at LARGE hlY CQhlf CGGION 'r'G~IRES h~ARCII 27, ISQ My commission expires: BGNGEQ il".v hIAYeeo eoNGI'IG AGENcY