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Category:Graphics incl Charts and Tables
MONTHYEARML22013A3172022-01-12012 January 2022 Trp 030 - St. Lucie SLRA Breakout Questions_Fuel Oil ML22013A3162022-01-12012 January 2022 Trp 020 - St. Lucie SLRA Breakout Questions_Occw ML22013A3342022-01-11011 January 2022 TRP16 - St. Lucie SLRA Breakout Questions_Pwr Internals ML22012A3912022-01-11011 January 2022 Scoping and Screening 2.3.3.2 & 2.3.3.4 St. Lucie SLRA - Breakout Questions ML22013A3072022-01-11011 January 2022 Trp 084 St Lucie SLRA - Ssnial Scclombreakoutq ML22012A2632022-01-10010 January 2022 Trp 3 - St. Lucie Psl SLRA Breakout Question Reactor Head Closure Stud Bolting ML22010A0972022-01-0707 January 2022 Trp 038 Psl Internal Surfaces Breakout Questions - Allik ML22010A1002022-01-0707 January 2022 Trp 033 Psl Selective Leaching Breakout Questions - Allik ML21356A5772021-12-22022 December 2021 Slar Breakout Questions - Fire Protection Scoping and Screening ML22013A3052021-12-21021 December 2021 Trp 143.4 St Lucie SLRA - Breakout Questions HELB ML22013A3042021-12-21021 December 2021 Trp 143.3 St Lucie SLRA - Breakout Questions EAF ML22013A3032021-12-21021 December 2021 Trp 143.2 St Lucie SLRA - Breakout Questions Non-Class 1 Fatigue ML22013A3022021-12-21021 December 2021 Trp 143.1 St Lucie SLRA - Breakout Questions Class 1 Fatigue ML22013A3012021-12-21021 December 2021 TRP60 St. Lucie SLRA - Breakout Questions Fatigue Monitoring ML22013A2972021-12-21021 December 2021 Trp 77 St. Lucie SLRA - Breakout Questions Corrosion Structural ML22013A2962021-12-21021 December 2021 Trp 74 St. Lucie SLRA - Breakout Questions ML22013A2952021-12-21021 December 2021 Trp 47 St. Lucie SLRA - Breakout Questions ML22013A2942021-12-21021 December 2021 Trp 46 St. Lucie SLRA - Breakout Questions Structures Monitoring ML22013A2922021-12-21021 December 2021 Trp 41 St. Lucie SLRA - Breakout Questions ML22013A2882021-12-21021 December 2021 Trp 23 & 147.8 St. Lucie SLRA - Breakout Questions Cranes AMP-TLAA ML22013A2842021-12-21021 December 2021 Trp 18 St. Lucie SLRA - Breakout Questions Bolting Integrity ML22013A2822021-12-21021 December 2021 SLRA - Breakoutt Questions Corrosion OE ML21354A8372021-12-20020 December 2021 Trp 11 St. Lucie SLRA Breakout Questions ML21351A2382021-12-17017 December 2021 Trp 148.1 St. Lucie SLRA - Breakout Questions for TLAA Section 4.7.1 Rev. 1 ML21351A2412021-12-17017 December 2021 Trp 15 St. Lucie SLRA - Internal Coatings Breakout Questions - Allik ML21351A2392021-12-17017 December 2021 Trp 14 St. Lucie SLRA - Buried Pipe Breakout Questions - Allik.Docx L-2021-137, GL 2004-02 Debris Transport Calculation Non-Conservatism2021-07-23023 July 2021 GL 2004-02 Debris Transport Calculation Non-Conservatism 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 ML15224B4492015-09-0303 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15236A0762015-09-0303 September 2015 Enclosure, Revised St Lucie Tables-LQ-W ML15231A4122015-08-21021 August 2015 FPL St. Lucie Capture Summary 2015 ML15231A4172015-08-21021 August 2015 Power Plant Causal Turtles L-2015-093, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2015-03-24024 March 2015 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2014-340, RAI Reply - Fourth Ten-Year Interval Unit 2 Relief Request No. 42014-11-0606 November 2014 RAI Reply - Fourth Ten-Year Interval Unit 2 Relief Request No. 4 L-2013-067, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20122013-02-14014 February 2013 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2012 ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML12073A1512012-03-0606 March 2012 NRR E-mail Capture - St. Lucie Discharge Headwall Project L-2010-096, Extended Power Uprate Data for NRC Confirmatory EPU Analyses2010-06-0404 June 2010 Extended Power Uprate Data for NRC Confirmatory EPU Analyses L-2009-078, Extended Power Uprate Data for NRC Confirmatory EPU Analyses2009-04-0202 April 2009 Extended Power Uprate Data for NRC Confirmatory EPU Analyses L-2008-236, Extended Power Uprate, Data for NRC Confirmatory EPU Analyses2008-10-29029 October 2008 Extended Power Uprate, Data for NRC Confirmatory EPU Analyses L-2008-178, Fourth Ten-Year Interval In-Service-Test Program Submittal RAI Reply to Relief Request PR-042008-08-0505 August 2008 Fourth Ten-Year Interval In-Service-Test Program Submittal RAI Reply to Relief Request PR-04 ML0810502642008-03-19019 March 2008 NDE Report, on PSL-1 Pressurizer Nozzles, Attachment 2 ML0808506472008-03-19019 March 2008 NDE Report on PSL-1 Pressurizer Nozzles L-2008-018, Transmittal of Pressurized Butt Weld Alloy Report, and Mitigation Status and Swol Inspection Results2008-02-21021 February 2008 Transmittal of Pressurized Butt Weld Alloy Report, and Mitigation Status and Swol Inspection Results 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 ML0526603212005-09-21021 September 2005 Tech Spec Pages for Amendment No. 196, Extension of the Reactor Coolant System Pressure/Temperature Curve Limits L-2004-293, Third 10-Year Inservice Inspection Interval Relief Request No. 2 Supplemental Information2004-12-28028 December 2004 Third 10-Year Inservice Inspection Interval Relief Request No. 2 Supplemental Information 2022-01-07
[Table view] Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-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) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump 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-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 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, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 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 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request 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) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 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-2023-071, 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 IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 ML23275A1142023-10-0202 October 2023 Improved Technical Specifications Conversion, Chapter 2.0, Safety Limits, Revision 1 - Volume 4 L-2023-126, Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal2023-10-0202 October 2023 Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal ML23275A1262023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 5.0, Administrative Controls, Revision 2 - Volume 16 ML23275A1252023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 4.0, Design Features, Revision 2 - Volume 15 ML23275A1242023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2 - Volume 14 ML23275A1232023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.8, Electrical Systems, Revision 2 - Volume 13 ML23275A1222023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.7, Plant Systems, Revision 2 - Volume 12 ML23275A1212023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.6, Containment Systems, Revision 2 - Volume 11 ML23275A1192023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 2 - Volume 9 ML23275A1202023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 - Volume 10 ML23275A1182023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 2 - Volume 8 ML23275A1162023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6 ML23275A1172023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 - Volume 7 ML23275A1152023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.0, LCO and SR Applicability, Revision 2 - Volume 5 ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 ML23275A1112023-10-0202 October 2023 Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16 ML23275A1122023-10-0202 October 2023 Improved Technical Specifications Conversion License Amendment Request Self-Identified Administrative Changes - Volume 2 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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-2022-154, Subsequent License Renewal Application Revision 1, Supplement 42022-09-22022 September 2022 Subsequent License Renewal Application Revision 1, Supplement 4 L-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022 Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-043, Subsequent License Renewal Application Revision 1 - Supplement 12022-04-0707 April 2022 Subsequent License Renewal Application Revision 1 - Supplement 1 ML22010A0962022-01-0505 January 2022 Trp 010 St Lucie SLRA - Boricacidcorrbreakoutq - Makar ML21285A1072021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1 ML21285A1082021-10-12012 October 2021 Enclosure 1: St. Lucie Nuclear Plant, Units 1 and 2, Subsequent Licensee Renewal Application, Revision 1 ML21285A1112021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report2021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 ML21215A3152021-08-0303 August 2021 Application for Subsequent Renewed Facility Operating Licenses ML21215A3162021-08-0303 August 2021 Enclosure 1: Subsequent License Renewal Application Enclosures Summary ML21215A3192021-08-0303 August 2021 Appendix E - Applicant'S Environmental Report for St. Lucie L-2021-192, Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-05-26026 May 2021 Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 L-2020-164, License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2020-12-21021 December 2020 License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2020-020, License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years2020-02-18018 February 2020 License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2019-10-0909 October 2019 License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019 Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG L-2018-161, License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2018-12-20020 December 2018 License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2018-182, License Amendment Request Iodine Removal System Elimination2018-11-0909 November 2018 License Amendment Request Iodine Removal System Elimination L-2018-201, Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-0909 November 2018 Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-147, Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications2018-08-0202 August 2018 Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications L-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies2018-06-29029 June 2018 License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-120, License Amendment Request to Remove the Site Area Map from the Technical Specifications2018-06-25025 June 2018 License Amendment Request to Remove the Site Area Map from the Technical Specifications L-2018-111, Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-06-0707 June 2018 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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-2018-031, License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme2018-01-31031 January 2018 License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2017-12-19019 December 2017 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors L-2017-139, License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2017-09-14014 September 2017 License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply 2023-06-14
[Table view] Category:Safety Evaluation
MONTHYEARML23219A0032023-09-0101 September 2023 SLRA SER Rev 1 ML23200A1462023-07-21021 July 2023 Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1 and 2 ML22255A1022022-09-21021 September 2022 Authorization and Safety Evaluation for Alternative Relief Request No. 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety ML22038A1872022-02-0909 February 2022 Authorization and Safety Evaluation for Relief Request No. 19 (RR19) - the Use of an Alternative to ASME Code Case N-729-6 for Replacement Reactor Vessel Closure Head Penetration Nozzle 85 ML21342A2092022-01-14014 January 2022 Issuance of Amendment Nos. 252 and 207 to Allow Risk-Informed Completion Times (RICT) for the 120-Volt Alternating Current (AC) Instrument Bus Requirements ML21236A1312021-09-30030 September 2021 Authorization of RR 15 Regarding Extension of ASME Requirements Related to Reactor Pressure Vessel Weld Examinations from 10 to 20 Years ML21022A2192021-02-26026 February 2021 Issuance of Amendment No. 206 to Replace the Current Time-Limited Reactor Coolant System Pressure/Temperature Limit Curves and LTOP Setpoints with Curves and Setpoints That Will Remain Effective for 55 Effective Full Power Years ML21027A2262021-02-17017 February 2021 Approval of Alternative to ASME Code, Section XI to Use an Alternative Inservice Inspection Schedule for the Reaction Vessel Closure Head Bolting ML20329A4022021-02-0303 February 2021 Approval of Alternative to Use ASME Code Case N-513-4 for Alternative Repair of Intake Cooling Water System ML20259A2982020-11-18018 November 2020 Issuance of Amendment No. 205 Regarding Modification of the Reactor Coolant Pump Flywheel Inspection Program ML20237F2572020-10-30030 October 2020 Issuance of Amendment Nos. 251 and 204 Regarding Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Development of Emergency Action Levels for Non-Passive Reactors ML20099A3482020-06-25025 June 2020 Safety Evaluation for Relief Request for Fifth Ten-Year Inservice Inspection (ISI) Interval - Alternative Risk-Informed Inservice Inspection Program for Class 1 and 2 Piping Welds ML20023B3782020-02-19019 February 2020 Safety Evaluation for Relief Request RR-16, Alternate Repair of 2B Boric Acid Makeup Pump Revision for the Fourth 10-Year Inservice Inspection Interval ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19266A0722020-01-27027 January 2020 Issuance of Amendment Nos. 250 and 202 Regarding Technical Specification Changes to Allow the Performance of Selected Emergency Diesel Generator Surveillance Requirements During Power Operation ML19254B5332019-09-30030 September 2019 Safety Evaluation for Relief Request RR#15, Revision 0, Regarding Limited Piping Examinations 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 ML19203A1662019-07-26026 July 2019 Issuance of Exigent Amendment No. 248 Technical Specification 3/4.8.1 Change to Allow for a One-Time Extension of the Allowed Outage Time for One Emergency Diesel Generator ML19115A2812019-05-31031 May 2019 Safety Evaluation for Relief Request No. 6 for the Fifth 10 Year Inservice Inspection Interval ML19058A4922019-04-23023 April 2019 Issuance of Amendment 198 Regarding Technical Specification Changes to Reduce the Number of Control Element Assemblies ML18274A2242018-11-0202 November 2018 Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map ML18256A0982018-10-30030 October 2018 Safety Evaluation for Relief Request No.5 for the Fifth 10-Year Inservice Inspection Interval ML18129A1492018-07-0909 July 2018 Issuance of Amendments Regarding Technical Specification Changes Related to the Auxiliary Feedwater System (CAC Nos. MG0237 and MG0238; EPID L-2017-LLA-0296) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18046A7122018-03-26026 March 2018 Issuance of Amendments Regarding the Unusual Event Fire Related Emergency Action Level Scheme ML18018A0332018-01-26026 January 2018 Safety Evaluation of Relief Requests for the Fifth 10-Year Inservice Testing Program (EPID L-2017-LLR-0113; L-2017-LLR-0017, L-2017-LLR-0018, L-2017-LLR-0119, L-2017-LLR-0120, L-2017-LLR-0121, and L-2017-LLR-0122) ML17334A9362018-01-0404 January 2018 Relief from the Requirements of the ASME Code Regarding Relief Request No. 17, Revision 0, for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9826; EPID L-2017-LLR-0043) ML17341A4422018-01-0404 January 2018 Relief from the Requirements of the ASME Code Relief Request No. 3 for the Fifth 10-Year Inservice Inspection Interval (CAC No. MF9288; EPID L-2017-LLR-0003) ML17257A0152017-10-31031 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to the Reactor Protection System and Limiting Condition for Operation 3.0.5 ML17263A1202017-10-27027 October 2017 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 16 (CAC No. MF9827; EPID L-2017-LLR-0044) ML17248A3792017-10-23023 October 2017 Issuance of Amendments to Revise the Renewed Facility Operating Licenses Fire Protection License Conditions (CAC Nos. MF9681 and MF9682; EPID L-2017-LLA-0230) ML17235A5652017-10-0505 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to Component Cyclic or Transient Limits ML17219A1742017-08-31031 August 2017 Relief from the Requirements of the ASME Code Regarding Relief Request 12 for the Fourth 10-Year Inservice Inspection Interval ML17195A2912017-08-14014 August 2017 Issuance of Amendments Regarding Relocation of Radiation Monitor Requirements from Technical Specifications to Licensee-Controlled Documents ML17132A1672017-07-10010 July 2017 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 13 ML17110A2702017-05-10010 May 2017 Inservice Inspection Plan Fourth 10-year Interval Relief Request No. 14 Rev 0 - ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17038A2252017-03-29029 March 2017 Issuance of Amendment No. 188 Regarding Emergency Diesel Generator Day Tank Volume 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) ML16251A1282016-12-0505 December 2016 Issuance of Amendments to Update Appendix B to the Renewed Facility Operating License to Incorporate the 2016 Biological Opinion ML16292A7612016-11-0202 November 2016 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 11 ML16166A4242016-10-0505 October 2016 St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding the Use of a New Computer Code to Model the Containment Vacuum Analyses ML16183A1382016-09-19019 September 2016 Issuance of Amendments Regarding Technical Specification Change to Eliminate the Moderator Temperature Coefficient Surveillance Test at the End of Cycle ML16210A3742016-08-30030 August 2016 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2 ML16103A3972016-07-28028 July 2016 Issuance of Amendments Regarding Removal of Technical Specification for Cleaning Fuel Oil Storage Tank Sediment and Relocating Procedures to Licensee Controlled Documents ML16167A4732016-07-0505 July 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16139A5882016-05-27027 May 2016 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 10, Revision 0 ML16124A3832016-05-25025 May 2016 St. Lucie Plant, Unit No. 1 - Issuance of Amendment Regarding Changes to the Snubber Surveillance Requirements (CAC No. MF6490) ML16063A1212016-04-19019 April 2016 Redacted - Issuance of Amendment Regarding License Amendment Request for the Transitioning to Areva Fuel ML15344A3462016-03-31031 March 2016 Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) (CAC Nos. MF1373 & MF1374) 2023-09-01
[Table view] |
Text
U.S. NUCLEAR REGULATORY CC, SSION DOCKET NLIMOER NR C Fo AM 195" (2-7aI 5d 334 FILE NUMOER Ngg DlSTR lBUTlON ron PART 60 DOCKET MATERIAL FROM: DATE OF DOCUMENT Florida Power & Light.,Company 3/17/77 Mr. Victor Stello Miami, Florida OATE RECEIVED Robert E. Uhrig 3/21/77 IgLETTE R QNOTORI2ED PROP INPUT FORM NUMBER OF COPIES RECEIVED ABORIGINAL 'ILEIUNCLASSIFIE D Q.COP Y DESCRIPTION ENCLOSURE Ltr. re our 2/15/77 ltr....trans the following: Amdt- to ol/notorized 3/17/77. .change to
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tech specs.'.to revise pressure-temperature limits for the first,two effective years ACKNOWLEDGED of full power operation., ~ .
.DO1lOrpREMOVS W.nc.r PLANT NAtfE: ( go C,'~ S St. Lucie Unit No. 1 (2-P)
(9-P)'JL FOR ACTION/INFORiVIATION ASSXGNED AD:
RRQQMH a.~~ C5 BRANC1LC1 ROJL'CT MA1LG PROJECT MANAGER' g LXC ASST LIC ASST ~
INTERNAl DIST RIBUTION REG FXLE SYSTEMS SAFETY PLANT SYSTEMS S MESA~~
HEXNEl!AN TEDEQgO M52XRO.~1 SCHROEDER REISE. YS'EHlQKAM OELD GOSSXCK 6; STAFF ENGINEERXNG IPPOLIgO F,riEi'1+~KH MXPC ERNST CASE HOSii',LXK HALLARD HANAUER SXHHEIL OPERATING REACTORS YOUNGBLOOD 11ARLESS ~PAWL CK STELLO SXTE TECH PROJECT MANAGEIKNT REACTOR SAFE OPERATXNG TECH GAMIfILL BOYD ROSS EXSEN11UT STEPP PE COLLXNS NOVAK gj+0 HULlfAN llOUSTON ROSZTOCZY ME PETERSON CHECK H+EY.E SITE ANALYSIS MELT7. VOLLHER HELTElfES AT& I HUNCH SKOVHOLT SALTZl'fAN J COLLINS RUTHFRG KREGER EXTERNAL DISTRIBUTION 6M'QQKUMKtLMT CONTROI NUMBER LPDS Fk Pr ~ .~~e NAT ~ LAB'EG
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'I FLORIDA POWER 8( LIGHT COMPANY migs)f 9'gIH g,k Mm L-77-82 17, 1977
'arch Director of Nuclear Peactor Regulation Attention: Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Stello:
Be: St. Lucie Unit 1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 A letter from your staff dated February 15, 1977 requested that, we revise our pressure-temperature limits for the first 2 effective years of full power operation (Technical Specification Figure 3.4-2a) to provide additional margin to assure compliance with Appendix G to 10 CFR Part 50. We have studied several references (SRP 5.3.2, BTP MTEB No. 5-2, and Appendix G to 10 CFR Part. 50) dealing with fracture toughness requirements and have developed a new curve with which to replace Figure 3.4-2a. Our new curve conservatively depicts operating conditions for up to 5 effective years of full power operation. We propose that our new curve be approved for use in place of the current Figure 3.4-2a.
Xn accordance with 10 CFR 50.30, we hereby submit three (3) signed originals and forty (40) copies of our request, to amend Appendix A of Facility Operating License DPR-67. The changes are described below and shown on the accompanying Technical.
Specification'pages bearing the date of this letter in the lower right hand corner.
Pa e 3/4 4-23a A new Figure 3.4-2a is provided entitled "Reactor Coolant System Pressure Temperature Limitations for up to 5 years of Full Power Operation".
Page 3/4 4-23b The title of Figure 3.4-2b is revised to read "Reactor for Coolant System Pressure Temperature Limitations up to 10 Years of Pull Power Operation".
~7+'QIQ/42 PEOPLE... SERVING PEOPLE
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Director of Nuclear Reactor Regulation March 17, 1977 Page Two Page Pa e 3/4 4-23c The title of Figure 3.4;2c is revised to read "Reactor Coolant System Pressure Temperature Limitations for up to 40 Years of Full Power Operation".
The proposed changes have been reviewed by the St. Lucie Facility Review Group and the Florida Power & Light Company Nuclear Review Board. They have concluded that safety question. A it does not involve an unreviewed safety evaluation is attached.
Very truly yours, Robert E. Uhrig Vice President REU/MAS/cpc Attachment cc: Mr. Norman C. Moseley, Region Robert Lowenstein, Esquire II
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0 0 100 200 300 400 500 INDICATED REACTOR COOLANT TEMPERATURE T~ F FIGURE 3A-2c Reaetar Caalaat System pressure Temperature Llmltatlaas for up to 40 Years of Ful I Power Operation ST. LUCIE - UijIT 1 3/4 4-23c 3/17/77
SAFETY EVALUATION 1.0 Introduction This evaluation supports proposed changes to the St. Lucie Unit 1 Pressure-Temperature curves (Figures 3.4-2a, 3.4-2b, and 3.4-2c).
2.0 Discussion 2.1 Figure 3.4-2a Criteria presented in paragraph 2.2.2 of Branch Technical Position 5-2 (Fracture Toughness Require-ments) lead to the following equation:
RTNDT z.nitial) + RTNDT (shift due to service)
>RTNDT (maximum from remaining pressure boundaries) + 50'F This relationship has been used to develop a new Technical Specification Figure 3.4-2a. The new curve is applicable for up to 5 years of full power operation.
A minimum RT shift of 95'F is necessary to satisfy Equation (1). A 95'F shift is midway between the 55'F shift of the current Figure 3.4-2a and the 135'F shift of Figure 3.4-2b. To develop a new Figure 3.4-2a that will satisfy Equation40'F(1), the 10-year curves of Figureis 3.4-2b were shifted to the left. This technique justified based on paragraph 3c of section III to Standard Review Plan 5.3.2 (Pressure-Temperature Limits).
Information from Chapter 5 of the FSAR was used to determine the service time for which a 95'F shift will be applicable.
a) The pertinent chemical composition of the weld in the beltline region was obtained from Table 5.2-4A on page 5.2-14:
.23 weight 8 Cu
.013 weight 0 P b) The end-of-life RTNDT shift and the end-of-life fluence were obtainect.
from Sections 5.2.3.5.5 (page 5. 2-18) and 5. 4. 4 (page 5. 4-8):
end-of-life RTNDT shift = 225'F end-of-life fluence = 1.91x10 19 n/cm 2
SAFETY EVALUATION (Continued) c) An equation relating RT D , chemical composition, and fluence was obtainecPErom Regulatory Guide 1.99 (Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials):
RT DT (shif t) = [40
+ 5000
+ 1000 (8 Cu-0. 08)
(SP-0.008) ) 't 1019
]
1/2 or, ( NDT 215 ) z 10 19 = f (n/cm 2
)
RTNDT ( F) f (n/cm 2 ) time (yrs. )
225 1.9lxlO 40 135 3.94xlo 10 95 1.95xlo 55 0.65xlO The attached figures show the pressure-temperature curves for RTNDT=95'F and a semi-logarithmic plot of fluence vs. service life. The service life plot shows that, after 5-1/2 years of full power operation, the vyisel surface has been exposed to a fluence of 1.95xlO n/cm Thus, the new pressure-temperature curves conservatively depict operating conditions for up to 5 years of full power. operation.
2.2 Fi ures 3.4-2b and 3.4-2c
'Since the pressure temperature curves represent an upper boundary on service life, the titles are revised to read "up to 10 Years" and "up to 40 Years" instead of "2 to 10 Years" and "10 to 40 Years", respectively.
3.0 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
SAFETY EVALUATION (Continued) 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 will 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 will not be inimical to the common defense and security or to the health and safety of the public.
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STATE OF FLORIDA )
) ss COUNTY OF DADE )
ADOPT , being first duly sworn, deposes and says:
That he is Executive Vice Presi n ~
of Florida Power Light Company, the Lz.censee 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.
E. A. Adomat
,,<<q ub's'ex~bed and sworn to before me this TARY<~- UBLIC, in and for the County of Dade, re S h~ate"".'o
<lrIIIÃ4"~""
f Florida NOTARY PUBLIC STAG Of fLORIDA A1 LARQ MY COMMISSION EXPIRES NOV. 30 1979 My commission expires: BoIeEo THRU a~ERAL INS. UNDERwRIIERS
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