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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-2024-004, 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, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals 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 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-2023-118, 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-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes 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 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-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations 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 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) 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-2023-082, 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 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 L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes 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-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 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-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality 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-2022-175, 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-2022-180, 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-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response 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 2024-01-08
[Table view] Category:Report
MONTHYEARL-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update 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) 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-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report ML22227A0532022-08-15015 August 2022 Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant ML22124A0112022-04-30030 April 2022 Scoping Summary Report - Final 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-2022-015, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI2022-01-14014 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI L-2022-011, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld2022-01-12012 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld ML22010A0942022-01-0404 January 2022 Trp 29 St. Lucie SLRA - Tank Breakout L-2021-178, Report of 10 CFR 50.59 Plant Changes2021-11-0808 November 2021 Report of 10 CFR 50.59 Plant Changes 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 ML19252A4002019-09-0909 September 2019 FPL to NRC, Notification of Smalltooth Sawfish Capture at St. Lucie L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds ML18096B3952018-04-0606 April 2018 Exhibit III Estimate of Construction Costs and Exhibit IV Technical Qualifications of Contractors ML18088B1952018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 9, Auxiliary Systems and Chapter 10, Steam and Power Conversion System ML18088B1942018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 11, Radioactive Waste Management System, Chapter 12, Radiation Protection, and Chapter 13, Conduct of Operations ML18088A0942018-03-29029 March 2018 Unit II Plants ECCS Performance Results L-2017-173, Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event2017-09-28028 September 2017 Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event L-2018-081, Kld Engineering, Pc - 2017 Population Update Analysis2017-09-20020 September 2017 Kld Engineering, Pc - 2017 Population Update Analysis L-2017-117, Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-12017-06-20020 June 2017 Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-1 L-2018-015, Plan of Study 316(b) Implementation2017-04-28028 April 2017 Plan of Study 316(b) Implementation L-2017-015, PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee.2016-04-30030 April 2016 PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee. ML16084A6162016-03-24024 March 2016 Submittal of Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant, Units 1 and 2 in St. Lucie County, Florida ML16063A0072016-02-26026 February 2016 Participation in Additional Work Under the Support for Applicant Action Items 1, 2, and 7 from the Final Safety Evaluation on MRP-227, Revision 0 PA-MSC-0983 R2 Cafeteria Task 8 and Acceptance Criteria for Measurement Of.. ML15352A0532016-01-0707 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Revaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights L-2015-297, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan2015-12-10010 December 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan L-2015-300, ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report.2015-11-30030 November 2015 ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report. ML15314A1602015-10-29029 October 2015 St. Lucie, Units 1 and 2 - License Renewal Commitment, Submittal of Pressurizer Surge Line Welds Inspection Program L-2015-221, Report of 10 CFR 50.59 Plant Changes2015-10-16016 October 2015 Report of 10 CFR 50.59 Plant Changes ML15240A1542015-09-0808 September 2015 Staff Observations of Sump Strainer Head Loss Testing at Alden Laboratory for Generic Safety Issue 191 L-2015-206, ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-2062015-07-31031 July 2015 ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-206 L-2015-177, Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 12015-06-30030 June 2015 Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 1 L-2015-143, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2015-05-14014 May 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 20152015-05-0808 May 2015 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 L-2016-052, TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182.2015-03-31031 March 2015 TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182. L-2015-091, ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR2015-03-31031 March 2015 ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR 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 ML15083A2642015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report L-2015-048, St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report2015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 1092015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 109 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-92015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End2015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End ML15083A2652015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 ML15083A2662015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End L-2014-366, ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report2014-12-31031 December 2014 ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report ML14338A5552014-12-0404 December 2014 NRC-2013-TN3079-NRC 2014 St. Lucie License Renewal ML14338A5542014-12-0404 December 2014 NRC-2013- TN2986-NRC 2014 St. Lucie L-2014-125, Report of 10 CFR 50.59 Plant Changes2014-05-0606 May 2014 Report of 10 CFR 50.59 Plant Changes ML13360A2022013-12-12012 December 2013 EPA Echo Report Martin County, Fl 2023-09-28
[Table view] Category:Miscellaneous
MONTHYEARL-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update 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) 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-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report ML22227A0532022-08-15015 August 2022 Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant ML22124A0112022-04-30030 April 2022 Scoping Summary Report - Final ML22010A0942022-01-0404 January 2022 Trp 29 St. Lucie SLRA - Tank Breakout L-2021-178, Report of 10 CFR 50.59 Plant Changes2021-11-0808 November 2021 Report of 10 CFR 50.59 Plant Changes ML19252A4002019-09-0909 September 2019 FPL to NRC, Notification of Smalltooth Sawfish Capture at St. Lucie L-2017-173, Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event2017-09-28028 September 2017 Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event L-2017-117, Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-12017-06-20020 June 2017 Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-1 ML15352A0532016-01-0707 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Revaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights L-2015-297, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan2015-12-10010 December 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan ML15314A1602015-10-29029 October 2015 St. Lucie, Units 1 and 2 - License Renewal Commitment, Submittal of Pressurizer Surge Line Welds Inspection Program L-2015-221, Report of 10 CFR 50.59 Plant Changes2015-10-16016 October 2015 Report of 10 CFR 50.59 Plant Changes ML15240A1542015-09-0808 September 2015 Staff Observations of Sump Strainer Head Loss Testing at Alden Laboratory for Generic Safety Issue 191 L-2015-143, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2015-05-14014 May 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML15083A2642015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report L-2015-048, St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report2015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report ML14338A5552014-12-0404 December 2014 NRC-2013-TN3079-NRC 2014 St. Lucie License Renewal ML14338A5542014-12-0404 December 2014 NRC-2013- TN2986-NRC 2014 St. Lucie L-2014-125, Report of 10 CFR 50.59 Plant Changes2014-05-0606 May 2014 Report of 10 CFR 50.59 Plant Changes ML13360A2022013-12-12012 December 2013 EPA Echo Report Martin County, Fl L-2013-193, Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Acceptance Review Clarification Response2013-06-14014 June 2013 Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Acceptance Review Clarification Response L-2013-175, Report of 10 CFR 50.59 Plant Changes2013-05-23023 May 2013 Report of 10 CFR 50.59 Plant Changes L-2012-437, Standardization of Senior Reactor Operator Fuel Handling Duties2012-12-27027 December 2012 Standardization of Senior Reactor Operator Fuel Handling Duties L-2012-105, Response to Nuclear Performance and Code Review Branch Request for Additional Information Identified During an Audit of Analyses Supporting the Extended Power Uprate License Amendment Request2012-03-15015 March 2012 Response to Nuclear Performance and Code Review Branch Request for Additional Information Identified During an Audit of Analyses Supporting the Extended Power Uprate License Amendment Request ML1026405722010-09-14014 September 2010 E-mail St. Lucie Capture Summary Update for January Through August 2010 ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants L-2010-059, Florida Dept of Environmental Protection - Wastewater Application Form 2CS - Permit to Discharge Process Wastewater from New or Existing Industrial Wastewater Facilities to Surface Water2010-03-18018 March 2010 Florida Dept of Environmental Protection - Wastewater Application Form 2CS - Permit to Discharge Process Wastewater from New or Existing Industrial Wastewater Facilities to Surface Water ML1008304422010-03-18018 March 2010 Florida Dept of Environmental Protection - Wastewater Application Form 2CS - Permit to Discharge Process Wastewater from New or Existing Industrial Wastewater Facilities to Surface Water L-2009-101, Report of 10 CFR 50.59 Plant Changes, for the Period of May 28, 2007 Through November 21, 20082009-04-22022 April 2009 Report of 10 CFR 50.59 Plant Changes, for the Period of May 28, 2007 Through November 21, 2008 L-2008-261, Technical Specification Special Report Inoperable Containment Sump Wide Range Level Channel B2008-12-16016 December 2008 Technical Specification Special Report Inoperable Containment Sump Wide Range Level Channel B ML0807010172008-03-10010 March 2008 EPRI Reports (St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report) L-2008-030, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-02-27027 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors NOC-AE-07002231, Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46)2007-11-0707 November 2007 Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46) L-2007-167, Report of 10 CFR 50.59 Plant Changes During the Period of December 19, 2005 Through May 27, 20072007-10-29029 October 2007 Report of 10 CFR 50.59 Plant Changes During the Period of December 19, 2005 Through May 27, 2007 L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42007-10-29029 October 2007 Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2007-137, Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B2007-08-31031 August 2007 Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B L-2007-029, Semi-Annual Fitness-For-Duty Program Performance Data for the Six-Month Period Ending December 31, 20062007-02-26026 February 2007 Semi-Annual Fitness-For-Duty Program Performance Data for the Six-Month Period Ending December 31, 2006 L-2007-020, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20062007-02-0606 February 2007 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2006 L-2006-078, Proposed License Amendment, Containment Spray Nozzle Surveillance Change2006-10-19019 October 2006 Proposed License Amendment, Containment Spray Nozzle Surveillance Change L-2006-217, Day Post Outage Steam Generator Report Technical Specification 4.4.5.5.c2006-09-20020 September 2006 Day Post Outage Steam Generator Report Technical Specification 4.4.5.5.c L-2006-152, NRC Order EA-03-009 - Reactor Vessel Head and Vessel Head Penetration Nozzle Inspection Results SL2-162006-08-10010 August 2006 NRC Order EA-03-009 - Reactor Vessel Head and Vessel Head Penetration Nozzle Inspection Results SL2-16 L-2006-180, Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire2006-07-31031 July 2006 Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire L-2006-167, Environmental Protection Plan Report Responses to FDEP Comments on FPL Proposal for Information Collection Clean Water Act Section 316(b)2006-07-0606 July 2006 Environmental Protection Plan Report Responses to FDEP Comments on FPL Proposal for Information Collection Clean Water Act Section 316(b) L-2006-139, Report of 10 CFR 50.59 Plant Changes2006-06-16016 June 2006 Report of 10 CFR 50.59 Plant Changes L-2006-063, Technical Specification Special Report, Radwaste Building Exhaust System, Plant Ventilation Stack Particulate Iodine and Noble Gas (Sping) Radiation - Out of Service2006-02-22022 February 2006 Technical Specification Special Report, Radwaste Building Exhaust System, Plant Ventilation Stack Particulate Iodine and Noble Gas (Sping) Radiation - Out of Service L-2006-043, Responses to NRC Requests for Additional Information on WCAP-16208-P, Rev. 0, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions.2006-01-23023 January 2006 Responses to NRC Requests for Additional Information on WCAP-16208-P, Rev. 0, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions. 2023-09-28
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0 Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 October 29, 2007 FPL L-2007-167 10 CFR 50.59(d)
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Report of 10 CFR 50.59 Plant Changes Pursuant to 10 CFR 50.59(d)(2), the attached report contains a brief description of any changes, tests, and experiments, including a summary of the 50.59 evaluation of each which were made on Unit 1 during the period of December 19, 2005 through May 27, 2007. This submittal correlates with the information included in Amendment 22 of the
,Updated Final Safety Analysis Report to be submitted under separate cover.
Please contact us should there by any questions regarding this information.
Very truly yours, orron. J nston Site Vice PrkidentJ St. Lucie PlanI GLJ/tlt Attachment I.
an FPL Group company
St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment ST. LUCIE UNIT 1 DOCKET NUMBER 50-335 CHANGES, TESTS AND EXPERIMENTS MADE AS ALLOWED BY 10 CFR 50.59 FOR THE PERIOD OF DECEMBER 19, 2005 THROUGH MAY 27, 2007 1
St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment INTRODUCTION This report is submitted in accordance with 10 CFR 50.59 (d) (2),
which requires that:
i) changes in the facility as described in the SAR; ii) changes in procedures as described in the SAR; and iii) tests and experiments not described in the SAR.
that are conducted without prior Commission approval be reported to the Commission in accordance with 10 CFR 50.90 and 50.4. This report is intended to meet these requirements for the period of December 19, 2005 through May 27, 2007.
This report is divided into three (3) sections. First, changes to the facility as described in the Updated Final Safety Analysis Report (UFSAR) performed by a Plant Change/Modification (PC/M).
Second, changes to the facility/procedures as described in the UFSAR, or tests/experiments not described in the UFSAR, which are not performed by a PC/M. And third, a summary of any fuel reload 50.59 evaluation.
Each of the documents summarized in Sections 1, 2 and 3 includes a 10 CFR 50.59 evaluation that evaluated the specific change(s).
Each of these 50.59 evaluations concluded that the change does not require a change to the plant technical specifications, and prior NRC approval is not required.
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St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment TABLE OF CONTENTS SECTION 1 PLANT CHANGE/MODIFICATIONS PAGE 04059, R.3 Feedwater Control Replacement - Phase 2 5 SECTION 2 50.59 EVALUATIONS PAGE SENS-07-007, R.0 Roof Ventilator RV-4 for Electrical 8 Equipment Room 1A Exhaust Out of Service for More Than 90 Days.
SENS-07-018, R.1 Operation With the Potential for an ICI 9 Thimble-to-TSP Flange Cap Screw Becoming a Loose Part SECJ-04-064, R.1 Cask Crane Main Hoist Weight Limit 10 Increase to 150 Tons SECTION 3 RELOAD EVALUATION PAGE 05060, R.0 & 1 St. Lucie Unit 1 Cycle 21 Reload 12 3
St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment SECTION 1 PLANT CHANGE / MODIFICATIONS 4
ý--, .. 1 1, St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment PLANT CHANGE/MODIFICATION 04059 REVISION 3 FEEDWATER CONTROL REPLACEMENT - PHASE 2 Summary:
This modification replaces the existing Feedwater Flow and Steam Generator Level Controls, the Reactor Coolant Pump (RCP) monitoring and display system, and the Atmospheric Dump Valve (ADV) controls with new Distributed Control System (DCS) equipment and software. Under PC/M 03068, a DCS, along with a Plant Data Network (PDN), were installed to replace the Digital Data Processing System (DDPS) and the Sequence of Events Recorder (SOER). Therefore, for this modification the existing DCS was expanded to include the FW, ADV and RCP systems. The new DCS equipment will also interface with the installed PDN.
In addition to the controller replacement, the positioner components of the Main Feedwater Regulating Valves (MFRV, FCV-9011 and FCV-9021), the Low Power Feedwater 15% Bypass Control Valves (LCV-9005 and LCV-9006), and the Atmospheric Dump Valves (ADV, HCV-08-2A and HCV-08-25) were replaced with digital positioners by this modification. The Manual/Auto (M/A) stations (FIC-9011/9021, LIC-9005/9006, and PIC-08-lA/IB) for these valves were also replaced. Ten (10) Reactor Turbine Generator Board (RTGB) 102 indicators and four (4) RTGB 102 recorders associated with the Feedwater and ADV System and 52 RCP indicators on RTGB 103 were replaced with Flat Panel Displays (FPDs). Additionally, inputs from the RCP vibration monitoring system on the back of RTGB 104 were brought into the DCS and will be displayed on the FPD on the front of RTGB 103. A Display Driver Cabinet was installed to drive the FPDs. Additionally, the four SG level bypass key lock selector switches located on the front of RTGB 102 were relocated to the inside of RTGB 102 to make room for the FPDs.
The existing power configuration for the FW and the ADV controls was modified slightly, moving the backup power off of the interruptible power supplies, PPI01/102A, onto 125VDC Buses 118 and 119 for Appendix R requirements. Additionally, isolation fuses are required for Appendix R isolation; however there is no additional space to mount a fuse block within the existing PP-119 Isolation Panel. Therefore, an additional fuse isolation panel, PP-119 Isolation Panel #2, was installed.
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St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment The reason for this modification was to reduce the instability (oscillations) of the Feedwater Regulating System (FWRS) and to upgrade this control system, along with the Atmospheric Dump Valve controls and the RCP monitoring and display system, to a DCS. The existing MFRV, Low Power Feedwater 15% Bypass Control Valve, and ADV pneumatic positioners were replaced with digital positioners to enhance tuning and diagnostic capability.
Additionally, the existing DCS was migrated to new software Version 8.0 to improve system performance. Copper blades on zone switches IZOl and 1Z04 were changed to fiber blades to support testing and future expansion of the PDN.
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St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment SECTION 2 50.59 EVALUATIONS 7
St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment EVALUATION SENS-07-007 REVISION 0 ROOF VENTILATOR RV-4 FOR ELECTRICAL EQUIPMENT ROOM 1A EXHAUST OUT OF SERVICE FOR MORE THAN 90 DAYS.
Summary:
In November 2006, the Mechanical Maintenance department was assigned to troubleshoot the rough running fan associated with roof ventilator RV-4. The equipment clearance order (ECO) was executed on November 17, 2006, at 0819 hours0.00948 days <br />0.228 hours <br />0.00135 weeks <br />3.116295e-4 months <br />. When the cover was removed from the fan, extensive damage was found to the fan blades. Two of the four blades completely fractured apart and fell into the cable tray below. The damaged fan assembly was removed and taken to the maintenance shop for disassembly. The two remaining fan blades had linear indications around the blade rivets. In accordance with administrative procedure ADM-09.08, "Operations In-Plant Equipment Clearance Orders," if a 50.59 Screening was not previously performed, the ECO is in place under the expectation that the system alteration would not be in effect for greater than 90 days during at-power operations. Repair of RV-4 was scheduled to begin on February 26, 2007. Section 6.15.1.B.2 of ADM-09.08 requires a 50.59 Screening for those ECOs that have been in place for longer than 60 days. The 50.59 Screening determined that the temporary alteration of the electrical equipment room 1A ventilation exhaust in support of maintenance on RV-4 adversely affected its UFSAR design function.
Therefore, this 10 CFR 50.59 Evaluation was written for the temporary alteration.
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St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment EVALUATION SENS-07-018 REVISION 1 OPERATION WITH THE POTENTIAL FOR AN ICI THIMBLE-TO-TSP FLANGE CAP SCREW BECOMING A LOOSE PART Summary:
During the cutting operation associated with the In-Core Instrumentation (ICI) Thimble Replacement Project (PC/M 04101),
inspection found that twelve (12) thimble tube stubs have a loose ICI Thimble-to-Thimble Support Plate (TSP) joint; i.e., able to be rotated about their centerline or able to be displaced laterally or vertically relative to their installed position.
This condition was determined to be the result of improper seating of the ICI hold-down assemblies to the TSP during the installation of modified hold-down assemblies in the 1978-1990 timeframe. The improper seating resulted in gaps between the hold-down flanges and the TSP, which resulted in the loose thimble-to-TSP joints.'
An evaluation was completed by Westinghouse which evaluated the safety significance of operating Unit 1 with the loose ICI thimbles. The evaluation assessed potential impacts resulting from the loose ICI thimbles and concluded that the only potential impacts of concern were that vibration of the thimble-to-TSP joint could cause the flange cap screws to back out and become a loose part. Vibration could cause thimble or thimble flange failure that could result in the ICI thimble dropping down.
Failure of the ICI thimble could then result in loss of ICI detector assembly operation.
PSL Engineering review of the Westinghouse evaluation concluded that some of the potential consequences of the above issue constituted adverse affects. As a result, PSL Engineering concluded that operation with the potential for a cap screw becoming a loose part involved a change to an SSC which could adversely affect an UFSAR-described design function. Therefore, a 10 CFR 50.59 Evaluation was written to document that prior NRC approval was not required to operate Unit 1 with the potential for an ICI thimble-to-TSP flange cap screw becoming a loose part.
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St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment EVALUATION SECJ-04-064 REVISION 1 CASK CRANE MAIN HOIST WEIGHT LIMIT INCREASE TO 150 TONS Summary:
The cask handling cranes at St. Lucie Units 1 and 2 have been replaced with new single-failure-proof cask cranes of greater capacity. The new cranes have a 150 ton single-failure-proof main hoist and a conventional 25 ton auxiliary hoist. The purposes of this evaluation are to: (a) increase the main hoist (cask crane main hoist, main hook, supporting structures and systems) load limit to the maximum critical load capacity of the new main hoist (150 tons), (b) expand the main hoist safe load path to include all the area that is accessible to the main hoist, and (c) allow the main hoist to place the cask lid on the cask (including lowering the lid onto the cask and/or lifting the lid off the cask) when the cask contains spent fuel.
This is not a change in the capacity of the current (new) cask handling cranes. It replaces the previous (old) crane load limits with the current crane maximum critical load capacity. The load limits for the previous cranes, which were not single-failure-proof, were 25 tons for Unit 1 and 100 tons for Unit 2. The maximum critical load capacity for the new cranes, which are single-failure-proof, is 160 tons.
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St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment SECTION 3 RELOAD EVALUATION 11
St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment PLANT CHANGE/MODIFICATION 05060 REVISIONS 0 & 1 ST. LUCIE UNIT 1 CYCLE 21 RELOAD Summary:
This engineering package (EP) provides the reload core design of St. Lucie Unit 1 Cycle 21 developed by FPL Company and AREVA-NP, Inc. The Cycle 21 core is designed for a nominal cycle length of 12,130 EFPH, based on a nominal Cycle 20 length of 11,100 EFPH.
The Cycle 21 reload design supports an end-of-cycle Tavg coastdown at full power with a maximum reduction in primary coolant temperature of 26°F.
The primary design change to the core for Cycle 21 is the replacement of 73 irradiated fuel assemblies with 72 fresh Region CC fuel assemblies and 1 irradiated fuel assembly (Region 5) currently residing in the spent fuel pool. All assemblies in the Cycle 21 reload core are of the debris-resistant design- The fuel assembly design of Region CC fuel is the same as that of the previous cycle, Region BB fuel design. This fuel design includes the use of high thermal performance (HTP) spacer grids and the use of FuelGuard lower tie plate. The fuel assembly design for Region CC fuel utilizes radial enrichment zoning similar to that used in Region BB fuel. A new 20 Gad pattern is used in Sub-region CC5 (4 assemblies).
The implementation instructions provided in this EP, for core reconfiguration from Cycle 20 to Cycle 21, support a full core offload only. This EP supports offload initiation as early as 145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> after Cycle 20 shutdown if the temperature of the component cooling water (CCW) inlet flow to the spent fuel pool heat exchanger is less than or equal to 95°F. If CCW inlet flow temperature exceeds 95°F, initiation of core offload is restricted to equal to or greater than 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> after shutdown.
The safety analysis for Cycle 21 reload design was performed by AREVA-NP and by FPL using NRC approved methodology. The analyses for Cycle 21 reload support a Departure from Nucleate Boiling Ratio (DNBR) limit at the 95/95 probability/confidence level, consistent with the applicable DNB correlation previously approved by the NRC. The linear heat rate (LHR) corresponding to the fuel centerline melt limit for Cycle 21 is 23.67 kW/ft. All analyses in support of this EP were performed with the assumption of steam generator tube plugging level not to exceed 15% average, and with a maximum asymmetry of +/-7% about the average.
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St. Lucie Unit 1 Docket No. 50-335 L-2007-167 Attachment During the Unit 1 Cycle 20: refueling outage, it was discovered that excore detector #7 was not in its normal operating position.
The as-found position of detector #7 was approximately 10 degree azimuthal and 3 inch radial shift away from its normal operating position. This EP supports the continued operation with linear range detector # 7 in the as-found position. Additionally, this EP supports the replacement of linear range detector #8 with a new shorter design of the same design used in Unit 2 in Cycle 15; and the implementation of new design shorter ICIs and ICI thimbles.
Revision 1 of this EP documents the implementation of the Startup Test Activity Reduction (STAR) program for St. Lucie Unit 1, starting in Cycle 21, to allow an option to eliminate rod worth measurements during zero power physics test, following refueling.
The supporting evaluation for the EP is based on the STAR program approved by the NRC for the participating Combustion Engineering (CE) designed pressurized water reactors. The objective of the STAR program is to reduce startup testing operations while ensuring that the core can be operated as designed, and startup evolution following STAR would use normal operating procedures. Although STAR allows the elimination of rod worth measurements and moderator temperature coefficient (MTC), this revision is only for the elimination of rod worth measurements.
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