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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-Operating (New/Renewal/Amendments) DKT 50
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 ML23249A2412023-09-25025 September 2023 Regulatory Audit Summary for the Review of License Amendment Request to Revise the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23082A0402023-04-0505 April 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment Nos. 260 and 255 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 ML22098A0902022-04-13013 April 2022 Nextera/Fpl Non-Proprietary Presentation for April 13, 2022 Public Meeting Re Planned Turkey Point Digital Instrumentation and Controls License Amendment Request (EPID L-2021-LRM-0007) (Slides) ML22020A4032022-02-0707 February 2022 Summary of November 17, 2021, Meeting with Florida Power and Light/Nextera on Improved Technical Specification Conversion License Amendment Requests (EPIDs L-2021-LLI-0000 and L-2021-LLI-0002) ML21279A0432021-10-15015 October 2021 Summary of Pre-Application Meetings with Florida Power and Light Concerning a Proposed Digital Instrumentation and Control Upgrade for Turkey Point, Units 3 and 4 ML21119A3552021-05-26026 May 2021 Correction to Amendment Concerning Extension of Containment Leak Rate Testing Frequency Amendments 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) 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 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 ML19310D7772019-12-0404 December 2019 Florida Power & Light Company - Turkey Point Nuclear Generating Unit 3 Subsequent Renewed Facility Operating License ML19305C8792019-12-0404 December 2019 LTR - Issuance of Subsequent Renewed Facility Operating License Nos. DPR-31 and DPR-41 for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML19310D7782019-12-0404 December 2019 Florida Power & Light Company - Turkey Point Nuclear Generating Unit 4 Subsequent Renewed Facility Operating License 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 L-2019-088, Subsequent License Renewal Application FPL Comments Regarding the NRC Biological Assessment2019-04-18018 April 2019 Subsequent License Renewal Application FPL Comments Regarding the NRC Biological Assessment 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 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 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) ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17004A2922017-02-0909 February 2017 Issuance of Amendments Regarding Technical Specifications for Snubbers 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 ML16008B0722016-02-25025 February 2016 Issuance of Amendments Regarding Technical Specifications for Facility Staff Qualifications for Licensed Operators ML15294A4432015-11-0909 November 2015 Issuance of Amendments Regarding Emergency Core Cooling System Technical Specifications ML15233A3792015-09-28028 September 2015 Issuance of Amendments Regarding Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15205A1742015-08-14014 August 2015 Issuance of Amendments Regarding Removal of Reactor Coolant System Chemistry Requirements from the Technical Specifications and Relocation of Requirements in Licensee-Controlled Documents ML15181A1792015-07-27027 July 2015 Issuance of Amendments Regarding Adoption of Technical Specification Task Force Traveler 523 (TSTF-523), Revision 2 ML13329A0922014-06-13013 June 2014 Issuance of Amendments Regarding Operating License Conditions and Technical Specifications ML13329A1392014-02-21021 February 2014 Issuance of Amendments Regarding the Use of Optimized Zirlo Fuel Rod Cladding Material ML13207A0952013-09-10010 September 2013 Issuance of Amendment No. 258 Regarding a One-Time Extension of Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d ML13059A2242013-04-0202 April 2013 Issuance of Amendments Regarding the Recirculation Ph Control System and Sodium Tetraborate Basket Loading ML12339A1122012-12-17017 December 2012 Issuance of Amendments Regarding Revision of Cyber Security ML12297A2402012-11-0606 November 2012 Issuance of Amendments Regarding Adoption of TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection ML12291A7302012-11-0505 November 2012 Issuance of Amendments Regarding Revision to Technical Specifications 3.7.5 Control Room Emergency Ventilation System ML12292A3422012-11-0505 November 2012 Issuance of Amendments Regarding Permanent Alternate Repair Criteria for Steam Generator Tubes ML12208A2982012-08-0808 August 2012 Issuance of Amendments Regarding Change to Direct Current Source Surveillance Requirements ML12130A0892012-06-21021 June 2012 Issuance of Amendments Regarding Section 5.0 Design Features 2024-01-22
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MRC FORM 195 U.S. NUCLEAR REGULATORY CO'ION DOCKET NUMBER (2. 76) 50-250 FILE NRC DISTRIBUTION FQR PART 50 DOCKET MATERIAL NUMBER'O:
Mr>>-V>> Stell o FROM: FPL DATE OF DOCUMENT 12;21>>76
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Miami, Fla, 33101 R>>E, Uhrig DATE F C 6 I V6 D RLETTER RlNOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED CI ORIGINAL K UNC LASS IF I ED Q COPY
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3 sigped 37 CC DEBCBIr TIDN Ltr notarized 12-21 76 requesing for Revised & addi pages to OL/Tech Specs Amdt to OL/Tech Specs ~ >>,trans the following pertaining to ECCS cooling performance ~ ~ ~
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.PLANT NAME: Turkey Pt, Unit 3 SAFETY FOR 'ACTION/INFORMATION DHL 12>>
ASSXGNED AD:
0 EC MANA PROJECT MANAGER L C ASST LIC ASST INTERNAL DISTRIBUTION REG FIL SAFETY PLANT SYSTEMS S SAFE NRC PDR HEINEMAN TEDESCO I"&' 'SCHROEDER 0 em OELD GOSSXCK & STAFF ENGINEERXNG IPPOLXTO MIPC ERNST CASE KNXGHT BALLARD SIHWEIL OPERATING REACTORS SPANGLER HARLESS PAWL'K STELLO SITE TECH ASLB'YSTEMS PROJECT MANAGEMENT BOYD REACTOR SAFE ROSS OPERATING TECH EISENHUT GAMMILL STEPP PE COLLINS NOVAK HULMAN HOUSTON ROSZTOCZY PETERSON CHECK SXTE ANALYSIS MELTZ VOLLMER HELTEMES AT & I BUNCH SKOVHOLT SALTZMAN J ~ COLLINS RUTBERG KREGER EXTERNAL DISTRIBUTION CO/IT OL NUMBER LPDR Miami Fla>>.. NAT LAB B TIC: REG V.IE ULR KSON OR NSIC LA PDR 12999 )+F,"
CONS TANTS fI NRC FORM 196 {2 76)
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.ag j POWER & LIGHT COMPANY ylr December 21, 1976 L-76-429
,.'Hegulati>ji Oo(:kej Fjf>8'ffice of Nucleai,Reactor Regulation Attention: Mr.'ictor Stello, Director @COfto Division of Operating Reactors SSc SN U. S. Nuclear Regulatory Commis'sion Washington, D. C. 20555 O,S.~~IA' ~
Dear Mr. Stello:
Re: Turkey Point Unit 3 Docket No. 50-250 Proposed Amendment to Facility 0 eratin License DPR-31 In accordance with 10 CFR 50.30 Florida Power 6 Light Company hereby submits three (3) signed originals and forty (40) copies of a request. to amend Appendix A of Facility Operating License DPR-31.
This proposal is being submitted as a result of a re-evaluation of ECCS cooling performance calculated in accordance with an approved Westinghouse Evaluation Model. The ECCS re-evaluation was forwarded to you on December 9, 1976 under our cover letter L-76-419. The proposed changes are described below and shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner. NRC approval of the proposed amendment is requested prior to the end of the current refueling outage, however, the amendment is not necessary for the conduct of the'efueling, or return to operation following completion of refueling.
Page 3.2-3 Page 3.2-3 is designated applicable to Unit 3 only. The page contains a revision to Specification 3.2.6.a such that the limit on Heat Flux Hot Channel Factor (Fq) for Unit 3 is reduced from 2.32 to 2.24.
Page 3.2-3a Page 3.2-3a is designated applicable to Unit 4 only.
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Office of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Page Two Pa es B3.2-4 and B3.2-6 Pages B3.2-4 and B3.2-6 are designated applicable to Unit 3 only. These pages present the basis for the revised Unit 3 F< limit.
Pa es B3.2-4a and B3.2-6a Pages B3.2-4a and B3.2-6a are designated applicable to Unit 4 only.
Page 3.4-1 Page 3.4-1 is designated applicable to Unit 3 only. The accumulator water volume in Specification 3.4.1.3 is revised from 825-841 ft~ to 875-891 ft.
Page 3.4-1a Page 3.4-la is designated applicable to Unit 4 only.
The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 6 Light Company Nuclear Review Board. They have concluded that, it does not involve an unreviewed safety question. A safety evaluation is attached.
Very truly yours, Robert E. Uhrig Vice President REU/MAS/cpc Attachments cc: Mr. Norman C. Moseley Robert Lowenstein, Esquire
STATE OF FLORIDA )
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COUNTY OF DADE )
Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert E. Uhrig Subscribed and sworn to before me this day of NOTARY PUB IC, in and for the County of Dade, State of lorida >PY Pll RV STATE OP Fl.ORIDA AV l ~n~e lAY CONhtlSS(OlII EXPIRES JAM.
26, l970 VPO@THKU GE
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UNIT 3 reactivity insertion upon ejection greater than 0.3% A k/k at rated power. Inoperable rod worth shall be determined within 4 weeks.
- b. A control rod shall be considered inoperable if (a) the rod cannot be moved by the CRDH, or (b) the rod is misaligned from its 5@ggy~more O>IL$0 than 15 inches, or ~~!!!Ml-'> t Wgl1 (c) the rod drop time de oot met. P~".g,gp~yot<~~@
- c. If a control rod cannot be moved by the
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boron addition to compensate for the withdrawn worth of the inoperable xod.
- 5. CONTROL ROD POSITION INDXCATXON If either the power range channel deviation alarm or the rod deviation monitor alarm are not operable rod positions shall be logged once per shift and after a load change greater than 10% of rated power. If both alarms axe inoperable for two hours or more, the nuclear overpower trip shall be reset to 93% of rated power.
- 6. ONER DISTRIBUTION LIMITS
- a. At all times except during low power physics tests, the hot channel factors defined in the basis must meet the following limits:
Fq(Z) < (2.24/P) x K(Z) for P > .5 Fq(Z) < (4.48) x K(Z) for P-< .5 FgH < 1.55 [1 + 0.2 (1-P) 3 where P is the fraction of design power at which the core is operating. K(Z) is the function given in Figure 3.2-3 and Z is the core height location.oE Fq.
- b. Following initial loading before the reactor is .
operated above /5% of rated power and at regulax-effective full rated power monthly intexvals thereafter, powex distribution maps, using the movable detector system shall be made, to conform that the hot channel factor limits of the specifi.ca-tion are satisfied. For the purpose of this comparison, 3~2 3 12/21/76
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UNIT 4 reactivity insertion upon ejection greater than 0.3% 6 k/k at rated power. Inoperable rod worth shall be dete ined within 4 weeks.
- b. A control rod shall be considered inoperable if (a) the rod can..ot be moved by the CRD~f, or (b) the rod is misaligned from its bank by more than 15 inches, or (c) the rod drop time is not met..
- c. If a control rod cannot be moved by the drive mechanism, shutdown nargin, shall be increased by boron addition to compensate for the withdrawn worth of the inoperable rod.
- 5. CONTROL ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation monitor alarm are not operable rod positions shall be logged once per shift and after a load change greater than 10% of rated power. If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93% of rated power.
- 6. POLAR DISTRIBUTION LLitITS
- a. At all times except during low power physics tests, the hot channel factors defined in the basis must meet the following limits:
Fq(Z) < (2.32/P) x K(Z) for P ) .5 Fq(Z) < (4.64) x K(Z) for P < .5 FN < 1.55 [1 + 0.2 (1-P)]
where P is the fraction of design power at which the core is operating. K(Z) is the function oiven in Figure 3.2-3 and Z is the core height location of'q.
b.. Following initial loading before the reactor is operated above 75% of rated powex and at regular
.effective full rated power monthly intervals thereafter, power distribution maps~ using the movable detec ox system shall be made, to conform that the hot channel factor limits of the specifica-tion are satisfied. For the purpose of this comparison, 30 2 3a 12/21/76
0 UNIT 3 3.4 ENGINEERED SAFETY FEATURES Applies to the operating sta-us of the Engineered Safety Features.
Ob jeer='= To define-those limiti"g co ditions for operation that are necessary: (1) to re=ove decay heat from'he core in emergency or normal shutdown situations, (2) to re-move heat from conta n=ent in normal operating and emergency situations, and (3) to remove a$ .rborne iodine from the containment atmosphere in the event of a Ifaximum Hypothetical Accident.
- l. SAFETY INJECTION ='~1') RES~MUAL HEAT RENOVAL SYSTPiiS
- a. The" reactor shall not be made crier.ca1, except for low power physics tests, unless the following 1., The refueling water tank shall. contain not less than 320,000 gal. of water with a boron con-centration of at least 1950 ppa.
- 2. The boro" i jection tank shall contain not less than 900 ga". o= a 20,000 to 22,500 ppm boron solution. The solution in the tank, and in isolated portio"s of the inlet and outlet piping, sha' be -aintained at a temperature of at lees" 145:-. T40 channels of heat tracing shall be opera"'e for the flow path.
- 3. E'ach accu=ulator shall be pressurized to at least 600 psig and contain 875-891 Ift I 3 of water witn a bc=on concentration of at least 1950 pp..., and j-.=-ll not be iso3.ated.
- 4. FOUR safety in-.ection pumps shall be operabl
- 3. '-1 UNIT 3 12/21/7b
0 UNIT 4 3.4 ENGINEERED SAFETY FEATURES Features.
~Ob'ective: To define those limiting conditions for operation that are necessary: (1) to remove decay heat from the core in emergency or normal shutdown situations, (2) to re-move- heat from containment in normal operating and emergency situations, and (3) 'to remove airborne iodine from the containment atmosphere in the event. of a Maximum Hypothetical Accident.
- 1. SAFETY INJECTION AND RESIDUAL HEAT ~i OVAL SYSTEMS'.
The reactor shall not be made critical, except for-low power physics tests, unless the following conditions are met:
l.~ The refueling water tank shall contain not less than 320,000 gal. of water with a boron con-centration of at least 1950 ppm.,
- 2. The boron injection tank shall contain not less than 900 gal. of a 20,000 to 22,500 ppm boron solution. The solution in the tank, and in isolated portions of the inlet and outlet piping, shall be maintained at a temperature of at least 145F. TtlO channels of heaL tracing shall be operable for the flow path.
- 3. Each accumulator shall be pressurized to at least 600 psig and contain 825-841 ft3 of water with a boron concentration of at least 1950 ppm, and shall not be isolated.
- 4. FOUR safety injection pumps shall be operablee 3e4-1 a 12/21/76 I
An upper bound envelope of 2.24 times the normalized peaking factor axial dependence of Figure 3.2-3 has been determined to be consistent with the technical. specifications on power distribution control as given in Section 3.2.
When an F measurement is taken, both experimental error and manufacturing '
tolerance must be allowed for. Five percent is the appropriate experimenta1-uncertainty allowance for a full'ore map taken with the movable incore detector flux mapping system and three percent is the appropriate allowance for manufactuzing tolerance.
In thh specified limit of F , there is an 8 percent allowance for uncertain-ties which means that normal operation of the core is expected to result in
<1.55/1.08. The logic behind the larger uncertainty zn this case ia that, F hEE (a) " normal perturbations in the radial power shape (e.g., zod misalign-ment) affect F>H, in most cases without necessarily affecting F ,(b) the operator has a direct influence on F through movement of rods, and can limit it to the desired value, he has no direct control over F8 and (c) an error in the predictions for radial power shape, which may be detected during startup physics tests can be compensated for in F by tighter axial control, but compensation for F is less readily available. When a measurement of v
F bH is taken, experimental error must be allowed for and 4/ is the appro-priate allowance for a full coze map taken with the movaole incore detector flux mapping system.
Measurements of the hot channel factors are required as part of start-up physics tests, at least once each full rated power month of'peration, and whenever abnormal power distribution conditions require a r duction of core power to a level based on measured hot channel factors. The incore map taken following initial Roading provides confirmation o the basic nuc1ear UNIT 3
- 83. 2-4 12/21/76
UNIT 4 M upper bound envelope of 2.32 ti es tna nox alized peak.ing factor axiaL c'apendanca of Figure 3.2-3 has been Eat 'nad (from extansive analyses at design power considering all opera'g ma"auvers) to ba consistent with tna technical specifications on power distr bution control as given in Section 3.2. The results of the loss of coo>>~t accident analys~ based on this upper 'bound envelope indicate a peak cl-d. temperature of 2150't design power, corresponding to a 50 P marg~ to the 2200 P FAC 3.imit 0
xnan an F measuremant is taken, bo~ experimental error and manufacturing tolerance must be allowed for. Piva percent is the apprapriate experimentaL
'ncertainty allowance for a full cora map taken with the. znovable incore detector flux mapping system and tare pe-cent is the ap~ropriate allowance for manufacturing tolerance.
La the specified limit of P, there is an 8 percent allo~ance for uncertain-wnich means that normal oparat on of tha core is a:~ected to result in bH'ies
<1.55/1.08. Tne logic behind tne larger uncertainty an this case is that (a) normal perturbatiors in the red al ".ower.supe (e.~., rod misalign- ~
affect P, in most cases without necessarily affecting P,(b) the .'ant) operator has a direct influence on = 6 tnrough movement oE rods, and can linjt H
it to the desired value, ha has no c=ract control. over F H and-(c) an erro-in tha predictions for radial powa" shape, which may b cRetectad during stzrtuo physics tests can be compensa ad =or in Fq by tip>ter'xial control bu" conpensation for P> is less raa ily available. E'en a measurement of
~~H is taken, experimental error rust ba allowed for and l~% is. the appro-"-
pria"a allowance 'for a full core r-p take" A.th the movable"incore detector ~
flux mapping system. '
Zaasuremants of the hot channel facto s a"a required as part of start-up physics tests, at least orce each fuU. ra-ed power month of operation, and v,.",anavar abnormal power distribution co;.=itiors require a rad ction of core po=-ar to a level based on measured ~ot channel factors Th rcore map taken following in "ial 3:oading pro .=des confirmation o th basic nuclear
') / a UNIT 4 12/21)7r,
UNIT 3 Flux Difference (Llg) and a reference value which corresponds to the full design power equilibrium value of Axis~ Of set (Axial Offset = A4/fractional power). The reference value of flux difference varies with power level and burnup but expressed as axi 1 offset it varies only with burnup.
The technical specifications on power distribution control. assure that tne F upper bound envelope of 2.24 times Figur 3.2-3 is not exceed d and xenon distributions are not developed which at a later time, would cause greater local power peaking even though the flux difference is then witnin the limits speciried by the procedure.
The target (or reference) value of flux difference is determined as 'follows.
At any time that equilibrium xenon conditions have been established, the in-dicated flux difference is noted with part length rods withdrawn from the core and with tne full length rod control rod bank more than 190 steps withdrawn (i.e., normal rated power operating position appropriate for the time in life.
Control rods are usually withdrawn fart". r as burnup proceeds). This value, divided by th- fraction of design power at which the core 'was operating is tne design power value of the target flux difference. Values for all other core power levels are obtained oy multiply=-ng tne design power value by the fractional power. Since the indicated equilibrium valu was noted, no allowances for ezcore detector error ar necessary and indicated deviation of
+5/ 61 are permitted from the indicated reference value. During peri'ods where extensive load following is. required, it may be impractical to establish the required core conditions for measuring tne target flux difference every rated power month. For this reason, methods are permitted by Item 6c of Section 3.2 for updating the target flux differences. Fipuxe B3.2-1 shows a typical construction of the target flux dif=erence band at 'BOL*and Figure B'3.2-2 shows the typical variation of the fuM> power value with buxnup.
Strict control of the flux difference (and rod position) is not as necessary during part power operation. This is because xenon distribution control at part power is not as significant as tne control at full power and allowance has been made in pr dieting the heat "lux peaking factors for less strict co=
trol at part power. Strict control of the ux difference is not possible
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during certain physics tests or during tne quired, periodic excore calibra-UNIT 3 '3.2-6 12/21/76
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UNIT 4 Flux Dizference {Ag) and a reference -alue which corresponds to tne full desim power equilibrium value of A~~ Of=set (Axial Offset ~ <0/fractional po"er). The reference value of flux izzer nce varies with power level and burnup but expressed as azi 1 offset "t varies only with burnup.
inc technical specifications on pow r distribution control assure that tne P upper bound envelope of 2.32 times Pigur 3.2-3 is not exceed d and. xenon dzstrxbutzons are not developed whicn at a latez time, would cause greater local power peaking -even though the flux di=ference is then within the limits specified by the procedure.
The target (or reference) value of fizz differ'ence is determined as fo1lows.
At any time that equilibrium xenon conditions have been established, the. in-dicated flux di fference is noted witn par t length rods withdrawn from. the core and with tne full length zod control =od ba"k more than 190 steps withdrawn (i.e., normal rated power operating positio" appropriate for the time in life..
Control rods are usually withdrawn faith r as burnup proceeds). This. value, divided by tha fraction of design power at -hich the core was operating is tne.
design power value of the target f1m cizfe"ence. Values Sor aU ot'hez. core power levels are obtained by multiplymg the design power value by the fract.onal power. Since the indicate: equilibrium valu was noted, no allo =-aces for excore detector error ar necessary and indicated deviation of
+5K LI are permitted from the indicatM re= rence value. During periods where extensive load following is required, it may be impractical, to establish the required core conditions fo m asuring -he target flux difzerence every rated power month. Por this reason, ~ thocs are permitted by Item 6c of Section 3 2 for updating the target f~uz di=ferences. Figure B3.2-1 shows a
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typical construction of the target fl w dif=erence band at EOL and Piguge B3.2-2 snows tne typical variation of the fuH~ po r value with burnup.
Strict control of the flux difference {and od position) is not as necessary during part power operation. This is be"a se xenon distribution control. at part power is not as significant as the co=trol at full power and allowan'ce h s b=-en made in predicti.".g the heat = ux "=-aking factors for less trict co=;
trol at part power. Strict control of t..e =:ux difference xs no possible duri-..= certain physics tests or du ig ne = -uir d, per odi.c excore ca1i'ora-UNIT 4 B3.2-5 a 12/21/76 I
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SAFETY EVALUATXQ'8 1.0 introduction This safety evaluation supports the ollowing proposed changes to the Unit 3 Technical Specifications:
The maximum allowable nuclear peaking'actor (Pq) is decreased from 2.32 to 2.24.
The limits on Safety ejection accumulator water volume are increased from 825-841 875-891 ft3.. ft3 to
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2.0 Discussion ECCS Re-evaluation A re-evaluation of ECCS cooling. performance calculated
.-: in accordance with an approved 'Plestinghouse Evaluation Model has been performed. The re-evaluation shows that for breaks up to and including the douhle ended
'everence of a reactor coolant pipe, the ECCS vill.
meet, the Acceptance Criteria presented in 10 CFR 50.46.
The detailed re-evaluation is contained in PPL letter
.. L-76-419 of December 9, 1976, and shows that, at a core power level of 102% o~ 2192 Nwt and a minimum water volume of 875 ft. per accumulator, 'ccumulator the maximum allowable nuclear peaking factor. is 2.25.
'owever, since the Technical Specifications allow a maximum core power level o 2200 Mwt, the re-evaluation.
is being revised using the higher power level. The revised calculation is expected to yield a maximum F<
of 2.24.
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'I3.0 Conclusions 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, therefore, the change does not involve a significant hazards consideration, (2) there is reasonable assurance 'that the health .and safety of the public vill not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment. wilJ not be inimical to t:he common defense and security or to the health and safety of the public.
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