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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] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. ML23095A0072023-04-0404 April 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1431 Revision 5 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-110, License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary)2022-08-26026 August 2022 License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary) ML22243A1622022-08-26026 August 2022 Submittal of License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML21265A3722021-09-23023 September 2021 Improved Technical Specifications Conversion, Volume 1, Revision 0, Application of Selection Criteria to the Turkey Point Nuclear Generating Station Unit 3 and Unit 4 Technical Specifications L-2021-158, Contents of the Turkey Point Nuclear Plant, Units 3 and 4 Improved Technical Specifications (Its) Submittal2021-09-22022 September 2021 Contents of the Turkey Point Nuclear Plant, Units 3 and 4 Improved Technical Specifications (Its) Submittal ML21265A3772021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 6, Revision 0, Section 3.1, Reactivity Control Systems ML21265A3852021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 14, Revision 0, Section 3.9, Refueling Operations ML21265A3812021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 9, Revision 0, Section 3.5, Emergency Core Cooling Systems (ECCS) ML21265A3872021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 16, Revision 0, Section 5.0, Administrative Controls ML21265A3792021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 8, Revision 0, Section 3.3, Instrumentation ML21265A3802021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 9, Revision 0, Section 3.4, Reactor Coolant Systems (RCS) ML21265A3842021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 13, Revision 0, Section 3.8, Electrical Power Systems ML21265A3862021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 15, Revision 0, Section 4.0, Design Features ML21265A3782021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 7, Revision 0, Section 3.2, Power Distribution Limits ML21265A3832021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 12, Revision 0, Section 3.7, Plant Systems ML21265A3752021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 4, Revision 0, Chapter 2.0, Safety Limits (Sls) ML21265A3762021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 5, Revision 0, Section 3.0, LCO and SR Applicability ML21265A3732021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 2, Revision 0, Determination of No Significant Hazards Considerations Generic Changes ML21265A3822021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 11, Revision 0, Section 3.6, Containment Systems ML21265A3742021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 3, Revision 0, Chapter 1.0, Use and Application L-2021-071, License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum Tm LOCA Methodology2021-04-15015 April 2021 License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum Tm LOCA Methodology L-2020-157, Supplement to License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2020-11-0505 November 2020 Supplement to License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors L-2020-053, Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program2020-04-0404 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program L-2020-003, License Amendment Request 268, Request to Extend Containment Leakage Rate Test Frequency2020-01-27027 January 2020 License Amendment Request 268, Request to Extend Containment Leakage Rate Test Frequency L-2019-203, License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2019-12-0606 December 2019 License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. L-2019-192, License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements2019-11-0404 November 2019 License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements L-2019-005, License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications2019-02-14014 February 2019 License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications L-2018-219, Supplement to License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals2018-12-0303 December 2018 Supplement to License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals L-2018-203, Supplement to License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement2018-11-20020 November 2018 Supplement to License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement L-2018-175, Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses2018-10-17017 October 2018 Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses L-2018-170, License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals2018-10-17017 October 2018 License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals L-2018-176, Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items2018-10-17017 October 2018 Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items L-2018-177, Subsequent License Renewal Application Safety Review Requests for Confirmation of Information (Rci) Responses2018-10-0909 October 2018 Subsequent License Renewal Application Safety Review Requests for Confirmation of Information (Rci) Responses L-2018-187, Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation2018-10-0505 October 2018 Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation ML18130A4662018-06-12012 June 2018 Amendments Regarding Technical Specifications Pertaining to IST Program and ISI Program Requirements and Surveillance Frequency Control Program Applicability L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications L-2018-044, License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement2018-05-14014 May 2018 License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement L-2018-065, License Amendment Request 258, Revise Reactor Core Safety Limit to Reflect WCAP-17642-PA, Revision 12018-05-0303 May 2018 License Amendment Request 258, Revise Reactor Core Safety Limit to Reflect WCAP-17642-PA, Revision 1 L-2018-082, Turkey Point, Units 3 and 4 - Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version)2018-04-10010 April 2018 Turkey Point, Units 3 and 4 - Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version) L-2018-082, Enclosure 4 to L-2018-082 - Non-Proprietary Reference Documents and Redacted Versions of Proprietary Documents (Public Version)2018-04-10010 April 2018 Enclosure 4 to L-2018-082 - Non-Proprietary Reference Documents and Redacted Versions of Proprietary Documents (Public Version) ML18113A1422018-04-10010 April 2018 Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version) ML18113A1412018-04-10010 April 2018 Enclosure 1 to L-2018-082, Subsequent License Renewal Application, Enclosure Summary ML18113A1342018-04-10010 April 2018 Transmittal of Subsequent License Renewal Application Revision 1 L-2018-086, Subsequent License Renewal Application Appendix E Environmental Report Supplemental Information2018-04-10010 April 2018 Subsequent License Renewal Application Appendix E Environmental Report Supplemental Information 2023-06-28
[Table view] Category:Safety Evaluation
MONTHYEARML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML22307A1152022-11-28028 November 2022 Authorization of Relief Request No. 10 Part II Related to Repair of Intake Cooling Water Discharge Piping (EPID L-2022-LLR-0032) (Non-Proprietary) ML22028A0662022-05-24024 May 2022 Issuance of Amendment Nos. 296 and 289 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology (EPID L-2021-LLA-0070)- Non-Proprietary ML22123A1922022-05-10010 May 2022 Authorization of Relief Request Nos. 8 and 9 Regarding Extension of Inspection Interval for Reactor Pressure Vessel Welds ML22069A7112022-03-16016 March 2022 Authorization of Relief Request No. 10 Regarding Use of ASME Code Case N-513-4 for Extended Period for Intake Cooling Water Discharge Piping ML21032A0202021-02-26026 February 2021 Issuance of Amendment Nos. 295 and 268 Concerning Extension of Containment Leak Rate Testing Frequency ML20198M4982021-01-27027 January 2021 Issuance of Amendment Nos. 294 and 267 Regarding Emergency Action Level Scheme Upgrade (EPID L-2019-LLA-0271) (L-2019-203) ML20287A5512020-11-0606 November 2020 Approval of Alternative to Use ASME Code Section XI IWA-4340 - for Repairs of Component Cooling Water System Piping ML20237F3852020-10-20020 October 2020 Issuance of Amendment Nos. 293 and 286 Regarding Containment Atmospheric Radioactivity Ventilation Isolation and Leakage Detection System ML20104B5272020-04-16016 April 2020 Issuance of Exigent Amendment No. 291 Concerning the Deferral of Steam Generator Inspections ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19266A5852019-12-17017 December 2019 Issuance of Amendment Nos. 289 and 283 Technical Specification Applicability to Equipment Shared Between Units and Exception to Technical Specification 4.0.4 ML19031C8912019-08-15015 August 2019 Issuance of Amendment Nos. 288 and 282 Regarding Revised Reactor Core Safety Limit to Reflect WCAP-17642-PA Revision 1 ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19064A9032019-03-27027 March 2019 Issuance of Amendments Regarding Transition License Conditions for Reactor Coolant Pump Seals ML18354A6732019-03-18018 March 2019 Issuance of Amendments Regarding Technical Specifications Changes to Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement ML18270A4292018-12-0303 December 2018 Issuance of Amendments Nos. 284 and 278 Regarding Adoption of Risk-Informed Completion Times in Technical Specifications (CAC Nos. MF5455 and MF5456; EPID L-2014-LLA-0002) ML18255A3602018-11-14014 November 2018 Issuance of Amendments Regarding Technical Specifications Changes to Address Non-Conservative Actions for Containment and Control Room Ventilation Functions ML18130A4662018-06-12012 June 2018 Amendments Regarding Technical Specifications Pertaining to IST Program and ISI Program Requirements and Surveillance Frequency Control Program Applicability ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18071A0802018-04-0606 April 2018 Correction to Safety Evaluation for Amendment Nos. 278 and 273 Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) ML18019A0782018-03-19019 March 2018 Issuance of Amendments Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID L-2017-LLA-0213) ML18018A5592018-02-20020 February 2018 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) ML17228A5632017-10-26026 October 2017 Issuance of Amendments Regarding Technical Specifications for High-Range Noble Gas Effluent Monitors ML17209A3192017-09-28028 September 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Actuation ML17213A8632017-08-29029 August 2017 Safety Evaluation for Relief Request No. PR-03, for the Fifth 10 Year Inservice Testing Interval Regarding Boric Acid Transfer Pump Testing Instrumentation ML17172A1152017-08-0303 August 2017 Turkey Point Nuclear Plant Generating Unit Nos. 3 and 4 - Issuance of Amendments Regarding Technical Specifications for Control Room Emergency Ventilation System (CAC Nos. MF8221 and MF8222) ML17122A1402017-05-10010 May 2017 Safety Evaluation for Relief Request No. 5 for Fifth 10-Year Inservice Inspection Interval ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML16335A1952017-02-14014 February 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Pumps ML17004A2922017-02-0909 February 2017 Issuance of Amendments Regarding Technical Specifications for Snubbers ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16279A4552016-10-28028 October 2016 Turkey Point Nuclear Generating Station Units 3 & 4 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16293A7782016-10-26026 October 2016 Turkey Point Nuclear Generating, Unit Nos. 3 and 4 - Safety Evaluation for Relief Request No. 4 for Fifth 10 Year Inservice Inspection Interval - Risk-Informed Inservice Inspection Program (CAC Nos. MF7277 and MF7278) ML16120A4732016-06-20020 June 2016 Issuance of Amendments Regarding Technical Specifications for Moderator Temperature Coefficient Measurements ML16004A0192016-04-26026 April 2016 Issuance of Amendments Regarding Technical Specification Figure for the Boric Acid Tank Minimum Volume ML16040A3732016-03-29029 March 2016 Issuance of Amendments Regarding Technical Specifications for Communications and the Manipulator Crane ML16047A1182016-03-0909 March 2016 Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval - Alternative for Examination of Snubbers (CAC Nos. MF6386 and MF6387) ML16008B0722016-02-25025 February 2016 Issuance of Amendments Regarding Technical Specifications for Facility Staff Qualifications for Licensed Operators ML16011A4402016-02-0101 February 2016 Safety Evaluation for Relief Request No. 2 for the Fifth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations of the Regenerative Heat Exchanger Welds (MF6384-MF6385) ML16011A2052016-01-22022 January 2016 Safety Evaluation for Relief Request No. PR-02, for the Fifth 10-Year Inservice Testing Interval Regarding Requirements for the Quarterly Testing of the Residual Heat Removal Pumps (CAC Nos. MF6388 & MF6389) ML15350A2032015-12-23023 December 2015 Safety Evaluation for Relief Request No. 16, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15352A1622015-12-23023 December 2015 Safety Evaluation for Relief Request No. 17, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A2402015-12-11011 December 2015 Safety Evaluation for Relief Request No. 15, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A1082015-12-0909 December 2015 Safety Evaluation for Relief Request No. PR-01, for the Fifth 10-Yeaer Inservice Testing Interval Regarding Requirements for the Quarterly Testing of the Boric Acid Transfer Pumps ML15294A4432015-11-0909 November 2015 Issuance of Amendments Regarding Emergency Core Cooling System Technical Specifications ML15271A3252015-10-14014 October 2015 Safety Evaluation for Relief Request No. 1, Revision 1 for Fifth 10-Year Inservice Inspection Interval - Repair of Pressurizer Stainless Steel Heater Sleeve Without Flaw Removal ML15233A3792015-09-28028 September 2015 Issuance of Amendments Regarding Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses 2024-01-22
[Table view] Category:Technical Specification
MONTHYEARL-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-2021-096, 10 CFR 50.59(d)(2) Summary Report2021-05-11011 May 2021 10 CFR 50.59(d)(2) Summary Report L-2019-055, Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2019-03-26026 March 2019 Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications ML18257A0312018-10-0505 October 2018 Correction to Amendment Nos. 279 and 274 Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID l-2017-LLA-0213) L-2018-100, Submittal of 10 CFR 50.59(d)(2) Summary Report2018-04-25025 April 2018 Submittal of 10 CFR 50.59(d)(2) Summary Report L-2017-100, License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program ...2017-06-28028 June 2017 License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program ... L-2017-006, Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b.2017-02-0909 February 2017 Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b. L-2016-128, License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps2016-06-30030 June 2016 License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps L-2016-128, Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps2016-06-30030 June 2016 Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps L-2014-369, License Amendment Request No. 236 Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B.2014-12-23023 December 2014 License Amendment Request No. 236 Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B. L-2014-028, LAR-230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2014-07-0808 July 2014 LAR-230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process L-2014-033, License Amendment Request LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2014-04-0909 April 2014 License Amendment Request LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-2013-219, License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d2013-07-12012 July 2013 License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d L-2012-314, License Amendment Request No. 224 Regarding Technical Specification 3/4.6.2.3 - Recirculation Ph Control System and Natb Basket Minimum Loading Requirement2012-09-0606 September 2012 License Amendment Request No. 224 Regarding Technical Specification 3/4.6.2.3 - Recirculation Ph Control System and Natb Basket Minimum Loading Requirement ML11293A3682012-06-15015 June 2012 Technical Specification Pages - Issuance of Amendments Regarding Extended Power Uprate L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases2011-11-16016 November 2011 Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases L-2011-276, Supplemental Response Regarding License Amendment Request No. 194, Control Room Habitability TSTF-448, and Changes to Technical Specification 3.7.5, Control Room Emergency Ventilation System2011-08-0101 August 2011 Supplemental Response Regarding License Amendment Request No. 194, Control Room Habitability TSTF-448, and Changes to Technical Specification 3.7.5, Control Room Emergency Ventilation System ML11195A1472011-07-29029 July 2011 Issuance of Amendments Regarding Cyber Security Program L-2011-264, Response to NRC Request for Additional Information on License Amendment Request (LAR-194) Re Control Room Envelope Habitability2011-07-18018 July 2011 Response to NRC Request for Additional Information on License Amendment Request (LAR-194) Re Control Room Envelope Habitability L-2010-115, 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 20092010-06-0404 June 2010 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 2009 L-2009-177, Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results2009-07-30030 July 2009 Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results L-2009-093, Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel2009-04-15015 April 2009 Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel L-2009-033, Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels.2009-02-16016 February 2009 Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels. L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/082008-11-10010 November 2008 Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08 L-2007-175, Rod Position Indication Systems2007-11-12012 November 2007 Rod Position Indication Systems L-2007-131, Administrative Changes to Technical Specifications to Remove Notes Regarding the Inoperability of Rod Position Indication for Control Rods F-8 (Unit 4) and M-6 (Unit 3)2007-09-0505 September 2007 Administrative Changes to Technical Specifications to Remove Notes Regarding the Inoperability of Rod Position Indication for Control Rods F-8 (Unit 4) and M-6 (Unit 3) L-2007-083, License Amendment Request (LAR 192) Inoperable Rod Position Indication2007-05-17017 May 2007 License Amendment Request (LAR 192) Inoperable Rod Position Indication L-2006-074, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-04-27027 April 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity L-2005-243, 10 CFR 50.59 Report2005-12-0808 December 2005 10 CFR 50.59 Report L-2005-006, Proposed License Amendment Reactor Trip System Technical Specifications Changes2005-03-22022 March 2005 Proposed License Amendment Reactor Trip System Technical Specifications Changes L-2005-008, Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers2005-01-20020 January 2005 Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers ML0412503672004-04-23023 April 2004 Proposed License Amendments Accident Monitoring Instrumentation Technical Specification 3.3.3.3 L-77-174, 06/09/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Revised 05/03/1976 Proposal on Subject of Air Filtration Systems1977-06-0909 June 1977 06/09/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Revised 05/03/1976 Proposal on Subject of Air Filtration Systems L-77-130, 04/28/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Proposed Valve Test, Pump Test, and Inservice Inspection Programs1977-04-28028 April 1977 04/28/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Proposed Valve Test, Pump Test, and Inservice Inspection Programs 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 ML18227C7331976-11-0101 November 1976 Referring to Letter of 5/20/1976 Which Proposed Tech Spec Changes Relating to Containment Building Tendon Surveillance Program, Letter Advising Changes Are Not Acceptable 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 ... L-76-200, 05/20/1976 Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons1976-05-20020 May 1976 05/20/1976 Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons L-76-189, 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters,1976-05-13013 May 1976 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters, L-76-192, 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes1976-05-0303 May 1976 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes ML18227D8631976-02-25025 February 1976 02/25/1976 Letter Request to Amend Appendix a of Facility Operating License. Proposes Technical Specification Changes Relating to Control Rod Insertion Limits for Unit 4, Cycle 3 ML18227D6721975-01-30030 January 1975 Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a, Proposing Addition of Limiting Conditions for Operation & Surveillance Requirements 2023-10-11
[Table view] Category:Amendment
MONTHYEARL-2019-055, Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2019-03-26026 March 2019 Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications ML18257A0312018-10-0505 October 2018 Correction to Amendment Nos. 279 and 274 Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID l-2017-LLA-0213) L-2017-100, License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program ...2017-06-28028 June 2017 License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program ... L-2016-128, License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps2016-06-30030 June 2016 License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps L-2016-128, Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps2016-06-30030 June 2016 Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps L-2014-028, LAR-230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2014-07-0808 July 2014 LAR-230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process L-2014-033, License Amendment Request LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2014-04-0909 April 2014 License Amendment Request LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-2013-219, License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d2013-07-12012 July 2013 License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d ML11293A3682012-06-15015 June 2012 Technical Specification Pages - Issuance of Amendments Regarding Extended Power Uprate ML11195A1472011-07-29029 July 2011 Issuance of Amendments Regarding Cyber Security Program L-2009-177, Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results2009-07-30030 July 2009 Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results L-2009-093, Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel2009-04-15015 April 2009 Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel L-2009-033, Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels.2009-02-16016 February 2009 Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels. L-2007-175, Rod Position Indication Systems2007-11-12012 November 2007 Rod Position Indication Systems L-2007-131, Administrative Changes to Technical Specifications to Remove Notes Regarding the Inoperability of Rod Position Indication for Control Rods F-8 (Unit 4) and M-6 (Unit 3)2007-09-0505 September 2007 Administrative Changes to Technical Specifications to Remove Notes Regarding the Inoperability of Rod Position Indication for Control Rods F-8 (Unit 4) and M-6 (Unit 3) L-2007-083, License Amendment Request (LAR 192) Inoperable Rod Position Indication2007-05-17017 May 2007 License Amendment Request (LAR 192) Inoperable Rod Position Indication L-2006-074, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-04-27027 April 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity L-2005-006, Proposed License Amendment Reactor Trip System Technical Specifications Changes2005-03-22022 March 2005 Proposed License Amendment Reactor Trip System Technical Specifications Changes L-2005-008, Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers2005-01-20020 January 2005 Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers ML0412503672004-04-23023 April 2004 Proposed License Amendments Accident Monitoring Instrumentation Technical Specification 3.3.3.3 L-77-174, 06/09/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Revised 05/03/1976 Proposal on Subject of Air Filtration Systems1977-06-0909 June 1977 06/09/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Revised 05/03/1976 Proposal on Subject of Air Filtration Systems L-77-130, 04/28/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Proposed Valve Test, Pump Test, and Inservice Inspection Programs1977-04-28028 April 1977 04/28/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Proposed Valve Test, Pump Test, and Inservice Inspection Programs 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 ML18227C7331976-11-0101 November 1976 Referring to Letter of 5/20/1976 Which Proposed Tech Spec Changes Relating to Containment Building Tendon Surveillance Program, Letter Advising Changes Are Not Acceptable 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 ... L-76-200, 05/20/1976 Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons1976-05-20020 May 1976 05/20/1976 Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons L-76-189, 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters,1976-05-13013 May 1976 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters, L-76-192, 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes1976-05-0303 May 1976 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes ML18227D8631976-02-25025 February 1976 02/25/1976 Letter Request to Amend Appendix a of Facility Operating License. Proposes Technical Specification Changes Relating to Control Rod Insertion Limits for Unit 4, Cycle 3 ML18227D6721975-01-30030 January 1975 Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a, Proposing Addition of Limiting Conditions for Operation & Surveillance Requirements 2019-03-26
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Il IIII I 50-25 251 I'ILE NVtvlULII NITC DISTBIDUTION I&i PAB I 50 DOCI(FT MATI:-ITIAL e o I II@M; 03" 1a ower 1g 0. DATE OF DOCUMENT Miami,'lor'dia 5-21-76 R.E. Uhrig DATE AECCIVCO 5-26-76 r L]LETTLA ]NOTOAIZEO f'AOP. INI'VT I'OIIM NUMOEA OF COI'IES AECEIVCO 8 OA G INAL I S IF I E 0 UNC LASS QCOPY 40 I OESCAIPTION LNCLOSV AC ILtr. notarized 5-25-76, Re. our 2-17-76 ltr. Tran Proposed Amdt. to Facility Operating'icenses ithe following....... Chanqe to Tech. Sppc.. consisting of revisions to OL regarding the reactor caolant system pressure temperature limits...w/Written Safety'Evaluation..;...
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~ F.O. ROX 013100, FhLAML, FLORIDA 33101 1'AO1I $ 00FOO FLORIDA POWER 8I LIGHT COMPANY DO04k Chhk May 21, 1976 L-76-199 Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Division of Operating Reactors Nuclear Regulatory Commission U. S.
Washington Dear Mr.
DC Stello:
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Mel I Se440 lj'e:
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 ln accordance with 10 CFR 50.30, Florida Power & Light Company submits herewith three (3) signed originals and forty (40) conformed of a request to amend Appendix A of Facility Operating 'opies Licenses DPR-31 and DPR-41.
On February 17, 1976, by letter from George Lear to Robert E. Uhrig, your office requested that we review the reactor coolant system .
pressure-temperature limits in the Turkey Point Technical Specifi-cations to'etermine if they are in full compliance with 10 CFR Part 50, Appendix G, "Fracture Toughness Requirements." We have conducted such a review and find that appropriate Technical Spe-
'cification changes are necessary.
We're also proposing changes in response to an April 14, 1975 letter from George Lear to R. E. Uhrig which requested that heatup and cooldown rates in the Turkey Point Technical Specifications be expressed as "'F in any one hour" instead of "'F/hr." The intent is to increase operational flexibility and decrease the possibility of a Technical Specification violation by more clearly specifying the time interval over wh'ich a temperature change is to be averaged.
The proposed changes are as described below and as shown on the accompanying Technical. Specification pages bearing the date of this letter in the "lower right hand corner.
3
~Pa e V The List of Figures is revised to include new Figures 3.l-la through 3.l-ld, 3.1-. 2a through 3.1-2d, B3.1-1, and B3.1-2.
Pa es 3.1-2 throu h 3.1-4 These pages are revised such that Specification 3.1.2.1 applies to Unit 3 only and Specification 3.1.2.2 applies to Unit 4 only. The heatup and cooldown rates are expressed in terms of " F in any one 86 HELPING BUILD FLORIDA
Mr. Victor Stello page 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />" instead of "'F/hr." The heatup and cooldown rate limits are based on test results obtained. from the surveillance capsules most recently removed from the reactors. Page 3.1-4 is revised such that the final part of Specification 3.1.2 no longer appears on that page.
Fi ures 3.1-la throu h 3.1-1d and 3.1-2a throu h 3.1-2d New reactor coolant system pressure-temperature limit curves are.
provided for Units 3 and 4. The new curves are based'n analysis of data obtained from the most recent reactor vessel surveillance capsules. Figure 3.1-2 is deleted.
Pa es B3.1-1 throu h B3.1-4 Revised bases pages are included in support of the proposed amendment.
Fi ures B3.1-1 and B3.1-2 Two new figures are added to Bases Section B3.1.
/
The proposed changes meet the requirements of 10 CFR Part 50, Appendix G.
The proposed amendment has been reviewed and the conclusion reached that it does not involve a significant. hazards consideration; therefore, prenoticing pursuant to 10 CFR 2.105 should not be required. A written safety evaluation is attached.
Very truly yours, Robert E. Uhrig Vice President REU:tg Attachment r
cc: Mr. Norman C. Moseley, Jack R. Newman, Esquire
STMZ OP FLORIDA )
) SS COUNTY OP DK)E )
Robert Ee Uh&gg bGLng erst 4uly QUorng deposes and says:
That he ia a Vice President of Flora.da Power 5 Xight Company, Q 'the Licensee horeint That he haa executed the foregoing documents that the;.~
statements made in thea said document are true and correct to tho beat of hio knowledge, information and belief, and that ho Xs authorised to execute the document on behalf of said Xicensee.
Robart E. Uhrig Subscribed and avorn to before mo Thea A. day oE 1976 Notary ubl c n anO Nor t o County oR DadeP tata << ~~o<<da NdTAA ~"<<<<;,'IvF of f II'".'PA n" I ~"~
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LIST OF FIGURES
~Pi use Title TECHNXCAL SPECIFXCATIONS 2~1 1 Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation
- 2. 1-2 Reactor Core Thermal and Hydraulic Safety Limits, Two Loop Operation 3.1-la Reactor Coolant System .Pressure Limits: Unit 3 Heatup and Cooldown thru-ld E
3\ 1 2a Reactor Coolant System Pressure Limits:. Unit 4 Heatup and Cooldown thru-2d 3~2 1 Control Group Insertion Limits for Unit 4, Three Loop Operation 3.2-la Control Group Insertion Limits for Unit 4, Two Loop Operation
- 3. 2-3.b Control Group Xns rtion Li...its for Unit 3, Three Loop Oper"tion 3.2-1c Control Group Insertion Limits for Unit 3, Two Loop Operation 302-2 Required Shutdown Margin 3~ 2 3 Hot Channel Factor Normalized Operating Envelope
- 3. 2-4 Maximum Allowable Local Kl</FT 4.12-1 Sampling Locations
- 6. 1-1 Offsite Organization Chart
- 6. 1-2 Plant Organization Chart B3.1-1 Effect of Fluence and Copper Content on Shift of RT , for Reactor Vessel Steels Exposed to 550'F Temperature
~ B3.1-2 Fast Neutron Fluence (E>lMEV) as a function of Effective Full Power Years B3. 2-1 Target Band on Indicated Flux-Difference as a Function of Operating Power Level B3.2-2 Permissible Operating Band on Indicated Flux Difference as a Function of Burnup 5/21/76
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UNIT 3
- 2. PRESSURE-TEMPERATURE LIMITS
- 1. Unit 3 The Reactor Coolant System (except for the pressurizer) pressure 'and temperature shall be limited during heatup, cooldown, criticality (except for low power physics tests), and inservice leak and hydrostatic testing in accordance with the limit lines shown on Figures 3.l-la through 3.l-ld. Allowable pressure-temperature combinations are BELOW AND TO THE RIGHT of the lines on the Figures. Heatup and cooldown rate limits are:
- a. A maximum heatup rate of 100 'F in any'ne hour.
- b. A maximum cooldown'ate. of 100 'F in any one hour.
c ~ A maximum temperature change of > 5 'F in any one hour during hydrostatic testing operation above system design pressure.
The pressurizer pressure and temperature shallbe limited in accordance with, the following:
- d. The pressur'zer, shall be limited +o a maximum heatup or cooldown rate of 200 'F in any one hour.
- e. The pressurizer shall be limited to a maximum Reactor Coolant System spray water temperature differential of 320 'F.
With any of the above limits exceeded, restore the temperature and/or pressure within the limits within 30 minutes; determine that the RCS or pressurizer remains acceptable for continued operations or, power, be in at least Hot Shutdown within the next if at 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The reactor shall not be made critical unless the moderator temperature coefficient is zero or negative.
When the coefficient is greater than zero, the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization. These moderator temperature coefficient conditions do not apply f:o low power physics tests.
3.1-2 5/21/76
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- 2. Unit 4 The Reactor Coolant System (except for the pressurizer) pressure and temperature shall be limited during heatup, cooldown, criticality (except for'ow power physics tests), and inservice leak and hydrostatic testing in accordance with the limit lines shown on Figures 3.1-2a through 3.1-2d. Allowable pressure-temperature combinations are BELOW AND TO THE RXGHT of the lines on the Figures. Heatup and cooldown rate limits are:
- a. A maximum heatup rate of 100 'F in any one hour.
- b. A maximum cooldown rate of 100 'F in any one hour.
- c. A maximum temperature change of a 5 'F in any one hour during hydrostatic testing operation above system design pressure.
The pressurizer pressure and temperature shall be limited in accordance with the following:
- d. The pressurizer shall be limited to a maximum heatU'p-or cooldown rate of 2QQ 'F in an>> one hour.
- e. The pressurizer shall, be .limited to a maximum Reactor Coolant System spray water temperature differential of 320 'F.
With any of the above limits exceeded, restore the temperature and/or pressure within the limits within 30 minutes; determine that the RCS or pressurizer remains acceptable for continued operations or, within if next at power, be in at least Hot Shutdown the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Cold Shutdown. within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The reactor shall not be made critical unless the moderator temperature coefficient is zero or negative.
When the coefficient is greater than zero, the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization. These moderator temperature
,coefficient conditions do not apply to low power physics tests.
3.1-3 5/21/".6
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3~ LEAKAGE a Any reactor coolant system leakage indication in excess
.of 1 gpm shall be the,subject of an investigation and
~
evaluation initiated within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />" of the. indication (ex.
I water inventory changes, radiation level increases, visual or audible indication). A leak shall be assu'med to exist til it I is determined that no unsafe condition exists
= . end that the indicated leak cannot be sub -tantiated.
Leakage of reactor coolant through reactor,.pump seals end system valves.to connecting closed systems from which
-coolant can be returned to the reactor. coolant system sh~
l not be -considered as leakage except that such losses sha11
- aot exceed 30Igpm.
Xf a reactor coolant system leakage indication is .
-.proven real, and. is not evaluated as safe, or ex-ceeds 10 gpm, reactor shutdown shall be initiated within 24 hours of the initial indication.
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Xf reactor coolant leakage exists through a fault in the system boundary that cannot be isolated (ex. vessels, giping, valve bodies) the reactor shall be shutdown and cool dotm to cold shutdown shall be initiated within
'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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shall consider the source 4
end magnitude of the leak, rates of change'.of
. detection variables, and if shutdown is required
- this evaluation shall be used to determine shut-
'down rates and conditions. A written log of the
~
ection taken shall be made as soon as practicable.
.The evaluation shall assure that no potent9.al gross leak is developing and that: potential re-3.case of activity will be within the guidelines
'of 10CFR20.
3.1-4 5/21/76
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.100 150 200 '50 300 350 -
400 450 500 550 Tavg (ND(GATED. TEMPERATURE ( F )
FIGURE 3.1=la TURKEY POINT UNIT 3 REACTOR COOLANT HEATUP LIMITATIONSAPPLICABLE FOR PERIODS UP TO 5 EFFECTIVE FULL POWER YEARS.
4 ~ ' ~
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2000 WELD METALCU = 0. 3)%
INITIALRTNDT 3'F jkjdgL'!i 1
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1
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~ 1800
~
AT 5 EFFECTIVE FULL POWER YEARS H:
."'} tt'! iotf iet ~
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RTNDT AT I/O THICKNESS = 194 F, 1
ttt! le I! .eat!:!t< I~
RTNDT AT 3/4 THICKNESS=- 131'F ~ ~
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COOLDOiVN RATES tiU i~Bi i.ij !4 ~ ~ ,1
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'F/HR = .:.' Q~
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INDI GATED TEMPERATURE ('F
~ FIGURE3.l-lb TURKEY POR!IT UNIT 3 REACTOR COOLANT COOLDOWN LIMITATIONSAPPLICABLE FOR PERIODS
)
UP TO'5 EFFECTIVE FULL POWER YEARS.
~ '
ei 4
'I ~ ' I I~ 6 ~ ~ I II I
4 sa ao oa 44444 k@ 4 2600ppot.o+-pp !P1V'ftf J.I!Ijffpjpf'400....
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j jiii i!!;:ij Itji lli! ("'i}" 'Iii 'ij!j!: .:il} !!i))1!.'. :I ~;,::
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WELD METAL CU "- 0. 31% ~~4 t iiI I I'i i!H tf ,ii. ~..
1!' !'.ii I'sfll Il (
f}.) :etta'l-..:.i!el ~1 IN)TIALRTNDT = 3'F ~
Ii!ii'kjj AT ) 0 EFFECTIVE FULL POWER YEARS I !:;ijj tii'i! '"
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~ 1800:.,.:::.:
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0 50 100 200 250 300 350 . 400 450 500 550
} ND 1 CATE 0 TENi PERATUREI j'F )
e FIGURE 3.l-lc TURKEY POINT UNIT 3 REACTOR COOLANT HEATUP LIMITATIONSAPPLICABLE "OR. PERIODS i
FROM 5 TO 10 EFFECTIVE FULL POWER YEARS.
F p
H ~
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2000 WELD METAL CU = 0.3I% is[it I I ill >>aj if>>ti:I: ttt:}:!::l ~'I Cn ji'..:I[!!}t INITIALRTNDT = 3'F AT IO EFFECTIVE FULL POWER YEARS ![li "'I :Is((.[
tii'tjj LI ill!
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I!.~Pji :I:;flit". t 1800[...,,.... itol ~ ~ ~ a ltf! :; I) ::,i',! fi!!
I hii}jt}I
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RTNDT AT I/O THICKNESS = 236'F e ~
I ~ Itss
~ w j
--,::j-::;:: RTNDT AT 3/4 THICKNESS = I59 F I" j}jjl'I+ijI iijI i!j::I: " 'I
~ a I!ijjhell i I:I rer }tl!
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1600 ,:-."..'. stile
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; I'jlj s}!I hie eL
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j::::i::g I >> I-':etf e ~ ~ ".'j!
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[lfi ijlli}jj!lit lk i!!.'}ij! } i'd) te tl, l ' tt Itis lttta se I t ti' I Ihl
~
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~ ~ ~
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e a ~ ~ ~
C5 ~ ~ IL tl';jj![:r>>>> >>t::I::::I fii:.)I f."
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a)tt tj!tj tt j! liiijii::!
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r 100 150 200 250 300 =
350 400 450 500 550 50 j ND !GATED TEIL'ERATURE ( F )
FIGURE 3.1-1d TURKEY POINT UNIT 3 REACTOR COOLANT COOLDOWN LtIMITATIONSAPPLICABLE FOR PERIODS .
FROM '5 TO IO Er FECTIVE FULL POWER YEARS.
7
i' 2600 ft<< tI 4l it444 ~ <<4 ti.. T)I I j.i,.f t!:I
'. a.t. I ~ 44 ~ 0 ~ ~ ~ ~ 0 ~
~" ~ .:::I f)SS 4 01
~ le.'jli(;j ~ 0 0~ 'I ~
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tie:I ~ ~ ~ 0~ !!I!jljjjji(t!('Sill' it!!jj;::tj ~tfe),itt) ;!!if j)!if!ji) lit. i.i: !(t) itt. i :)) "ea etc) -:!!IJ!!ri) r'iHI(ir'r'I Rl(jtlti)(I-')FrHsj ttrr) llrI 'rtrr'till!ji!l ) jr.iijf)tl j MATERIAL PROPERTY BASIS t ! ~
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2000 a 180P WELD METALCU = 0.30~ro INITIALRTgIDT = O' AT 5 EFFECTIVE FULL POWER YEARS itft!7 toit i-ij i i!!lllil (ila ftrs iP; I!I)
,;:l jt, i)!t ili!':"::ti'!
141
~
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14
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~
I! I it'I I4 ~ )j':j fj-'! i:!j!j ii!! (!:lit :.1")<<" f( '<<.Sf.:
RTNDT AT 3/4 THICKNESS = I88'F j~f P:I i'jt }4 0
i,tl i:i (iii !l"j Tjlj'j""' lfii i!4 ll~
1600 J ijl t t It(
~
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~
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re BASES FOR LIMITING CONDITIONS FOR OPERATION, REACTOR COOLANT SYSTEM
- 1. 0 erational Com onents The specification requires that a sufficient number of reactor coolant pumps be operating to provide coast down core cooling in the event that a loss oi flow occurs. The flow provided will keep DNBR well above 1,30. When the boron concentration of the Reactor Coolant System is to be reduced the process must be uniform to prevent sudden reactivity changes in the reactor. Mixing of the reactor coolant will be sufficient to maintain a uniform boron concentration if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place.
The residual heat removal pump will circulate the reactor coolant system volume in approximately one half hour.
Hach of the pressurizer safety valves is designed to relieve 293,330 lbs. per hr. of saturated steam at the valve set point,. (1) Below 350 F and 450 psig in the Reactor Coolant Syst: em, the Residual lieat Removal System can remove decay heat and thereby control system temperature and pressure. If no residual heat were removed by any of the means available the amount oi steam which could be generated at safety valve lifting pressure would be less than the capacity of a single valve. Also, two safety valves have capacity greater than the (2) maximum surge rate resulting irom complete loss of load.
- 2. Pressure/Tem erature Limits All components in the Reactor. Coolant System are designed I
to withstand the effects of cyclic loads due to system .
temperature and pressure changes. These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations. The various categories of load cycles used for design purposes are pr6vided in B3.1-1 5/21/76 1
Section 4.1.5 of the PSAR. During startup and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for prevention of brittle fracture.
During heatup, the thermal gradients in the reactor vessel wall produce thermal stresses which vary from compressive at the inner wall to tensile at the outer wall. These thermal induced compressive stresses tend to alleviate the tensile stresses i.nduced by the internal pressure.
Therefore, a pressure-temperature curve based on steady state conditions (i.e., no thermal stresses) represents a lower bound of a11 similar curves for. finite heatup rates when the inner wall of the vessel is treated as the governing location.
The heatup analysis also covers the determination of pressure-temperature limitations for the case in which the outer wall of the vessel becomes the controlling
)
location. The thermal gradients established during heatup produce tensile stresses at the outer wall of the vessel. These stresses are additive to the pressure induced tensile stresses which are already present. The thermal induced stresses at the outer wall of the vessel are tensile and are dependent on both the raj:e of heatup and the time along the heatup ramp; therefore, a lower bound curve similar to that described for the heatup of the inner wall cannot be defined. Subsequently, for the cases in which the outer wall oi the vessel becomes the stress controlling location, each heatup rate of interest must be analyzed on aIi individual basis.
33.1-2 5/21/76
The heatup limit curves are composite curves prepared by determining. the most conservative case, with either the inside or outside wall controlling, for any heatup rate up to 100'P 'per hour. The cooldown limit curves are composite curves which were prepared based upon the same type analysis with the exception that the controlling location is always the inside wall where the cooldown thermal gradients tend to produce tensile stresses while producing compressive stresses at the outside wall. The heatup and cooldown curves were prepared based upon the most limiting value of the predicted adjusted reference tempexature at the end of the service period.
Thc reactor vessel materials have been tested to determine their initial RT , . Adjusted reference temperatures, based upon the fluence and copper content of the material in question, are then determined. The heatup and cooldown limit curves include the shift in RT at the end of the service period shown on the heatup and cooldown curves.
The actual shift in NDTT of the vessel material will be established periodically during operation by removing and evaluating, in accoxdance with ASTM E185-73, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area.
Since the neutron spectra at the irradiation samples has a definite xelationship,to the spectra at the vessel inside radius, the measured transition shift for a sample can be related with confidence to the adjacent section of the reactor vessel. The heatup and cooldown curves must be 83.1-3 5/21/76
recalculated when the bRT D, determined from the surveillance capsule is different from the calculated ARTIST for the equivalent capsule radiation exposure.
The pressure-temperature limit lines shown for reactor criticality and for inservice leak 'and hydrostatic testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10 CPR 50.
The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.2-1 to assure compliance with the requirements of Appendix H to 10 CPR Part 50.
The limitations imposed on pressurizer heatup and cooldown and spray water temperature diiferential are provided to assure that the pressurizer is operated within the design criteria assumed ior the fatigue analysis performed in accordance with the ASMH Code requirements B3.1-4 5/21/76
0.30% COPPER QASE. Q.25$ MELO A%0'OVER 0.25$ COPPER aasE. 0.20$ uELO Q.P.0$ COPPER BISE. O.le WE 200 g~n V f00
- o. gQ 60
- 0. t S8 OOP P ER 3LSE. 0, )OX VE'LO 0-lOg COPPER BASE. 0.05$ tfELO tO'6 Effect of Pluence and Copper Content on Shift of RTNDT for Reactor Vessel Steels Exposed to 550 '1'emperature Figure 33.1-1 5/21/76
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'a SAFETY EVALUATXON Xntroduction Limits for reactor coolant temperature and pressure are given in Turkey Point Technical Specifications 3.1.2. This submittal proposes changes to the specification to bring it into compliance with 10 Appendix G. The changes are based on test results recently CFR'0, obtained from the latest reactor vessel surveillance capsules 'from Unit 3 and 4. P 4 ~
Discussion Since the physical properties of reactor vessel mater'i'als-,can. be affected by neutron irradiation, these materials. are subjec'4".to a surveillance program. Reactor vessels are designed'o ""the accommodate surveillance capsules which contain materials used in rpanuiacture of the vessels. Xrradiated surveillance materials are p'erRodically analyzed and the data used to revise operating pressure-temperature.
limits. Turkey Point FSAR Section 4.4 contains detailed infor-mation on the reactor vessel surveillance program.
Current Technical Specification 3.1.2 provides a method'or revising heatup and cooldown curves based on the radiation exposure of surveillance specimens. However, the Turkey Point, reactor vessels were manufactured before the publication of 10 CFR 50, Appendix G and ASHE Boiler and Pressure Vessel Code, Section Xi~', appendix G:
both of which provide information on reactor vessel design and calculation techniques based on surveillance specimen data. Now that Turkey Point surveillance capsule data have been reviewed and analyzed in accordance with Appendix G and the ASb1E Code, we find it necessary to revise the pressure-temperature curves in the Technical Specifications. The new limit curves for normal heatup and cooldown of the primary reactor coolant system were calculated using the methods discussed in the proposed Bases pages.
Conclusion Based on these considerations, (1) the proposed change does not increase the probability or consequences of accidents or malfunctions of equipment important to safety and does not reduce the margin of safety as defined in the basis for any technical specification, therefor'e, the change does not. involve a significant hazards consideration, (2) there is reasonable assurance that the health the and safety of the public will not be endangered by operation in proposed manner, and (3) such activities will be conducted in com-pliance with the Commission's regulations and the issuancesecurityof this amendment will not be inimical to the common defense and or to the health and safety of the public.
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