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Category:Letter type:L
MONTHYEARL-2024-085, Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results2024-10-15015 October 2024 Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results L-2024-165, Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made2024-10-14014 October 2024 Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-155, Subsequent License Renewal Application, Third Annual Update2024-09-27027 September 2024 Subsequent License Renewal Application, Third Annual Update L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-117, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review L-2024-104, Response to Request for Additional Information, St. Luce 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 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce 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 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-011, 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 Applications2024-03-13013 March 2024 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-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-027, Safety Injection Tank Vent Through Wall Leakage2024-02-29029 February 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules 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) 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-2023-175, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, 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 2024-09-09
[Table view] Category:Report
MONTHYEARL-2024-085, Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results2024-10-15015 October 2024 Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results L-2024-165, Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made2024-10-14014 October 2024 Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion L-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. 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-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 2024-09-11
[Table view] Category:Miscellaneous
MONTHYEARL-2024-165, Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made2024-10-14014 October 2024 Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion L-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 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-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 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-2007-168, 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-2007-167, 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-2007-137, 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) 2024-07-29
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September 28, 2023 L-2023-131 10 CFR 54.17 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11545 Rockville Pike One White Flint North Rockville, I:vID 20852-2746 St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 Facility Operating Licenses DPR-67 and NPF-16 SUBSEQUENT LICENSE RENEWAL APPLICATION - SECOND ANNUAL UPDATE
References:
- 1. Florida Power & Light Company (FPL) letter L-2021-192, Subsequent License Renewal Application -
Revision 1, October 12, 2021 (ADAJvIS Package Accession No. I\t1L21285A106)
- 2. FPL Letter L-2022-163 dated September 28, 2022, Subsequent License Renewal Application - First Annual Update (ADAMS Accession No. Iv1L22271A399)
- 3. FPL letter L-2022-043, Subsequent License Renewal Application Revision 1 - Supplement 1, April 7, 2022 (ADAMS Accession No. Iv1L22097A202)
- 4. FPL letter L-2022-143, Subsequent License Renewal Application Revision 1 - Aging Management Requests for Additional Information (RAI) Set lA Response (ADAMS Accession No. I\t1L22251A202)
FPL, the owner and licensee for St. Lucie Nuclear Plant (PSL) Units 1 and 2, has submitted a revised subsequent license renewal application (SLRA) for the Facility Operating Licenses for PSL Units 1 and 2 (Reference 1) and the first annual update (Reference 2) . The License Renewal Rule, 10 CFR 54.21(6),
requires that each year following submittal of an LRA, and at least 3 months before scheduled completion of the NRC review, an update to the LRA must be submitted that identifies any change to the current licensing basis (CLB) of the facility that materially affects the content of the LRA including the Updated Final Safety Analysis Report Supplement.
In accordance with the License Renewal Rule, FPL has performed the second annual review of PSL Units 1 and 2 CLB changes since SLRA submittal to dete1111ine whether any sections of the SLRA were materially affected by these changes. As a result of this annual review, FPL identified one change to the PSL Units 1 and 2 CLB materially affecting SLRA content. A description of these changes and the corresponding affected SLRA content revisions are provided in Attachments 1 and 2 to this letter, respectively. Note that SLRA pages 3.3-93 and 3.4-72 were previously revised by references 3 and 4, respectively.
For ease of reference, the index of attached information is provided on page 3 of this letter. Attachment 2 includes associated revisions to the SLRA (Enclosure 3 Attachment 1 of Reference 1) denoted by strikethrough (deletion) and/ or bold red underline (insertion) text. Previous SLRA revisions are denoted by bold black text. SLRA table revisions are included as excerpts from each affected table.
Florida Power & Light Company 15430 Endeavor Drive, Jupiter, FL 33478
St. Lucie Nuclear Plant Units 1 and 2 L-2023-131 Dockets 50-335 and 50-389 Page 2 of3 Should you have any questions regarding this submittal, please contact Mt. Michael Davis, Fleet Licensing Projects Manager at (319) 851-7032. I declare under penalty of perjU1y that the foregoing is true and correct.
I declare under penalty of perjury that the foregoing is 1:1.ue and correct.
Executed on the 28 th day of September 2023.
Sincerely, Dianne Strand Dianne Strand General Manager Regulato1y Affairs Florida Power & Light Company Attachments (2) cc: Regional Administrator, USNRC, Region II Senior Resident Inspector, USNRC, St. Lucie Plant Chief, USNRC, Division of New and Renewed Licenses Senior Project Manager, USNRC, Division of New and Renewed Licenses Chief, Bureau of Radiation Control, Florida Department of Health
St. Lucie Nuclear Plant Units 1 and 2 L-2023-131 Dockets 50-335 and 50-389 Page 3 of 3 Attachment Subject No.
1 Current Licensing Basis (CLB) Changes Affecting the SLRA 2 Affected SLRA Content Revisions
St. Lucie Nuclear Plant Units 1 and 2 L-2023-131 Dockets 50-335 and 50-389 Attachment 1 Page. 1 of 1 CURRENT LICENSING BASIS (CLB) CHANGES AFFECTING THE SLRA PSL 1 and 2 CLB Change Screening / Aging SLRA Sections Affected Management Review/
Program (AMR /AMP)
Documents Affected A Winterization Protection Modification NEESL0000S-REPT-011 Section 3.2, Table 3.2.2-2 installed heat tracing and insulation on NEESL0000S-REPT-015 Section 3.3, Table 3.3.2-1 Unit 1 & 2 auxiliary feedwater and con-densate, chemical volume and control, NEESL0000S-REPT-017 Section 3.3, Table 3.3.2-3 containment spray, and demineralized NEESL0000S-REPT-032 Section 3.4, Table 3.4.2-3 makeup water system piping and valves.
The new component type / material /
environment combinations affect SLRA chapter 3 summary of aging manage-ment evaluation tables and boundary drawings for these systems.
St. Lucie Nuclear Plant Units 1 and 2 L-2023-131 Dockets 50-335 and 50-389 Attachment 2 Page 1 of7 Affected SLRA Content Revisions SLRA Section 3.2 (Table 3.2.2-2), page 3.2-59 is revised as follows:
Table 3.2.2-2: Containment Sorav - Summarv of Aaina Manaaement Evaluation Component Type Intended Material Environment Aging Effect Aging Management NUREG-2191 Table Notes Function Requiring Program Item 1 Item Manaaement Piping Pressure Stainless steel Wastewater Loss of material Inspection of Internal VI I. E5.AP-278 3.3-1 , A boundary (int) Flow blockage Surfaces in Miscellaneous 095 Piping and Ducting Comoonents (B.2.3.24)
Piping Pressure Stainless steel Wastewater Wall thinning - Inspection of Internal VII.C1 .A-409 3.3-1, E, 1 boundary (int) erosion Surfaces in Miscellaneous 126 Piping and Ducting Comoonents (B.2.3.24)
PiQing {insulated} Pressure Stainless Air - outdoor Cracking External Surfaces Monitoring V.E.E-451c 3.2-1, A boundary steel {ext} of Mechanical Comgonents 108 fB.2.3.23)
PiQing {insulated} Pressure Stainless Air - outdoor Loss of material External Surfaces Monitoring V.E.E-450c 3.2-1, A boundary steel {ext} of Mechanical Comgonents 107 18.2.3.23\
Piping and piping Structural Stainless steel Air- indoor Cracking External Surfaces Monitoring V.A.EP-103c 3.2-1, A components integrity uncontrolled of Mechanical Components 007 (attached) (ext) (B.2.3.23)
Piping and piping Structural Stainless steel Air- indoor Loss of material External Surfaces Monitoring V.D1 .EP-107b 3.2-1 , A components integrity uncontrolled of Mechanical Components 004 (attached) (ext) (B.2.3.23)
Piping and piping Structural Stainless steel Air- indoor Cracking Inspection of Internal V.A.EP-103d 3.2-1, A components integrity uncontrolled Surfaces in Miscellaneous 007 (attached) (int) Piping and Ducting Components (B.2.3.24)
St. Lucie Nuclear Plant Units 1 and 2 L-2023-131 Dockets 50-335 and 50-389 Attachment 2 Page 2 of7 Affected SLRA Content Revisions SLRA Section 3.2 (Table 3.2.2-2), pages 3.2-65 is revised as follows:
Table 3.2.2-2: Containment Sprav - Summary of Aging Management Evaluation Component Type Intended Material Environment Aging Effect Aging Management Program NUREG-2191 Table 1 Notes Function Requiring Item Item Management Valve body Pressure Stainless steel Air- outdoor Loss of material External Surfaces Monitoring V.D1.EP-107b 3.2-1 , A boundary (ext) of Mechanical Components 004 (B.2.3.23)
Valve body Pressure Stainless steel Treated borated Loss of material Water Chemistry (B.2.3.2) V.A.EP-41 3.2-1 , A boundary water (int) One-Time Inspection 022 (B.2.3.20)
Valve body Pressure Stainless steel Treated water Loss of material Water Chemistry (B.2.3.2) V.C.EP-63 3.2-1 , A boundary (int) One-Time Inspection 022 (B.2.3.20)
Valve body Pressure Stainless steel Wastewater Loss of material Inspection of Internal VII.E5.AP-278 3.3-1, A boundary (int) Flow blockage Surfaces in Miscellaneous 095 Piping and Ducting Components (B.2.3.24)
Valve body Pressure Stainless steel Wastewater Wall thinning - Inspection of Internal VI I. C 1.A-409 3.3-1, E, 1 boundary (int) erosion Surfaces in Miscellaneous 126 Piping and Ducting Components (B.2.3.24)
Valve bod~ Pressure Stainless Air - outdoor Cracking External Surfaces V.E.E-451c 3.2-1, ~
{insulated) boundarv steel {ext} Monitoring of Mechanical 108 Comoonents (B.2.3.23\
Valve bod~ Pressure Stainless Air - outdoor Loss of material External Surfaces V.E.E-450c 3.2-1, ~
{insulated) bounda!Y steel {ext) Monitoring of Mechanical 107 Comoonents (B.2.3.23\
St. Lucie Nuclear Plant Units 1 and 2 L-2023-131 Dockets 50-335 and 50-389 Attachment 2 Page 3 of7 Affected SLRA Content Revisions SLRA Section 3.3 (Table 3.3.2-1), page 3.3-87 is revised as follows:
Table 3.3.2-1: Chemical and Volume Control - Summary of Aging Management Evaluation Component Type Intended Material Environment Aging Effect Aging Management Program NUREG- Table 1 Notes Function Requiring 2191 Item Management Item Piping (insulated) Pressure Stainless Air- indoor Cracking External Surfaces Monitoring of VII.I.A-734c 3.3-1 , A boundary steel uncontrolled Mechanical Components 205 (ext) (B.2.3.23)
Piping (insulated) Pressure Stainless Air- indoor Loss of material External Surfaces Monitoring of Vll.1.A-761c 3.3-1 , A boundary steel uncontrolled Mechanical Components 232 (ext) (B.2.3.23)
PiQing {insulated} Pressure Stainless Air - outdoor Cracking External Surfaces Monitoring Vll.1.A-734c 3.3-1, A bounda!Y steel {ext} of Mechanical ComQonents 205 (B.2.3.23)
PiQing {insulated} Pressure Stainless Air - outdoor Loss of material External Surfaces Monitoring VII.I.A-761c 3.3-1, A boundarv steel {ext} of Mechanical ComQonents 232 (B.2.3.23\
Piping and piping Pressure Stainless Treated borated Cumulative TLAA - Section 4.3.2, Metal VII.E1.A-57 3.3-1 , A components boundary steel water (int) fatigue damage Fatigue of Non-Class 1 002 Components Piping and piping Structural Stainless Air - dry (int) Loss of material Compressed Air Monitoring VII.D.A-764 3.3-1 , A components integrity steel (B.2.3.14) 235 (attached)
Piping and piping Structural Stainless Air- indoor Cracking External Surfaces Monitoring of VII.E1 .AP-209b 3.3-1 , A components integrity steel uncontrolled (ext) Mechanical Components 004 (attached) (B.2.3.23)
Piping and piping Structural Stainless Air- indoor Loss of material External Surfaces Monitoring of VII.E1.AP-221b 3.3-1 , A components integrity steel uncontrolled (ext) Mechanical Components 006 (attached) (B.2.3.23)
Piping and piping Structural Stainless Treated borated Loss of material Water Chemistry (B.2.3.2) VII.E1 .AP-79 3.3-1 , A components integrity steel water (int) One-Time Inspection 125 (attached) (B.2.3.20)
St. Lucie Nuclear Plant Units 1 and 2 L-2023-131 Dockets 50-335 and 50-389 Attachment 2 Page 4 of7 Affected SLRA Content Revisions SLRA Section 3.3 (Table 3.3.2-1), page 3.3-93 is revised as follows:
Table 3.3.2-1: Chemical and Volume Control - Summary of Aging Management Evaluation Component Type Intended Material Environment Aging Effect Aging Management NUREG-2191 Table 1 Notes Function Requiring Program Item Item Management Valve body Pressure Stainless steel Treated borated Cracking Water Chemistry VII.E1 .AP-82 3.3-1, 028 A boundary water >140°F (int) (B.2.3.2)
One-Time Inspection (B.2.3.20)
Valve bod)l Pressure Stainless Air - outdoor Cracking External Surfaces VII.I.A-734c 3.3-1, 205 ~
(insulated) boundary steel (ext) Monitoring of Mechanical ComQonents
{B.2.3.23)
Valve bod)l Pressure Stainless Air - outdoor Loss of material External Surfaces VII.I.A-761 c 3.3-1, 232 ~
(insulated) boundary steel (ext) Monitoring of Mechanical ComQonents
{B.2.3.23)
General Notes A. Consistent with component, material, environment, aging effect, and AMP listed for NUREG-2191 line item. AMP is consistent with NUREG-2191 AMP description.
B. Consistent with component, material, environment, aging effect, and AMP listed for NUREG-2191 line item. AMP has exceptions to NUREG-2191 AMP description.
C. Component is different, but consistent with material, environment, aging effect, and AMP listed for NUREG-2191 line item. AMP is consistent with NUREG-2191 AMP description.
Plant Specific Notes None.
St. Lucie Nuclear Plant Units 1 and 2 L-2023-131 Dockets 50-335 and 50-389 Attachment 2 Page5of7 Affected SLRA Content Revisions SLRA Section 3.3 (Table 3.3.2-3), page 3.3-107 is revised as follows:
Table 3.3.2-3: Demineralized Makeuo Water - Summarv of Aaina Manaaement Evaluation Component Type Intended Material Environment Aging Effect Aging NUREG-2191 Table 1 Notes Function Requiring Management Program Item Item Manaaement PiQing {insulated} Leakage Stainless Air - outdoor Cracking External Surfaces Monitoring Vll.1.A-734c 3.3-1, A boundarv steel {ext} of Mechanical ComQonents 205
{sQatial} (8.2.3.23)
PiQing {insulated} Leakage Stainless Air - outdoor Loss of material External Surfaces Monitoring VII.I.A-761 c 3.3-1, A boundart steel {ext} of Mechanical ComQonents 232
{sQatial} (8.2.3.23)
Steel components Leakage Carbon Airwith borated Loss of material Boric Acid Corrosion (B.2.3.4) VII.I.A-79 3.3-1 , A boundary steel water leakage 009 (spatial)
Valve body Leakage Stainless Air- indoor Cracking External Surfaces Monitoring of VII.C1 .AP-209b 3.3-1 , A boundary steel uncontrolled Mechanical Components 004 (spatial) (ext) (B.2.3.23)
Valve body Leakage Stainless Air- indoor Loss of material External Surfaces Monitoring of VI I. C 1.AP-221 b 3.3-1 , A boundary steel uncontrolled Mechanical Components 006 (spatial) (ext) (B.2.3.23)
Valve body Leakage Stainless Treated Loss of material Water Chemistry (B.2.3.2) VIII.B1 .SP-87 3.4-1 , A boundary steel water (int) One-Time Inspection (B.2.3.20) 085 (spatial)
Valve bod~ Leakage Stainless Air - outdoor Cracking External Surfaces Monitoring Vll.1.A-734c 3.3-1, A
{insulated} boundarv steel {ext} of Mechanical ComQonents 205
{sQatial} l8.2.3.23)
Valve bod~ Leakage Stainless Air - outdoor Loss of material External Surfaces Monitoring Vll.1.A-761 c 3.3-1, A
{insulated} boundart steel {ext} of Mechanical ComQonents 232
{sQatial} {8.2.3.23}
General Notes A. Consistent with component, material, environment, aging effect, and AMP listed for NUREG-2191 line item . AMP is consistent with NUREG-2191 AMP description.
St. Lucie N uclear Plant Units 1 and 2 L-2023-131 D ockets 50-335 and 50-389 Attachment 2 Page 6 of7 Affected SLRA Content Revisions SLRA Section 3.4 (Table 3.4.2-3) , page 3.4-72 is revised as follows:
Table 3.4.2-3: Auxiliary Feedwater and Condensate - Summary of Aging Management Evaluation Component Type Intended Material Environment Aging Effect Aging Management Program NUREG-2191 Table Notes Function Requiring Item 1 Item Manaqement Piping Pressure Stainless Concrete (ext) Cracking Buried and Underground Piping VIII.H .S-420 3.4-1 , 8 boundarv steel and Tanks (B.2.3.27) 072 Piping Pressure Stainless Concrete (ext) Loss of material Buried and Underground Piping VIII.H.SP-145 3.4-1 , 8 boundarv steel and Tanks (B.2.3.27) 047 Piping Pressure Stainless Soil (ext) Cracking Buried and Underground Piping VIII.H .S-420 3.4-1 , 8 boundarv steel and Tanks (B.2.3.27) 072 Piping Pressure Stainless Soil (ext) Loss of material Buried and Underground Piping VIII.H .SP-145 3.4-1 , 8 boundarv steel and Tanks (B.2.3.27) 047 Piping Pressure Stainless Treated Loss of material Water Chemistry (B.2.3.2) VIII.G.SP-87 3.4-1 , A boundarv steel water (int) One-Time Inspection (B.2.3.20) 085 Piping Pressure Stainless Treated Wall thinning - Flow-Accelerated Corrosion VIII.G.S-408 3.4-1 , A boundarv steel water (int) erosion (B.2.3.8) 060 Piping Pressure Stainless Treated water Cracking Water Chemistry (B.2.3.2) VIII.G.SP-88 3.4-1 , A boundarv steel >140°F (int) One-Time Inspection (B.2.3.20) 011 Pi~ing {insulated} Pressure Carbon Air- outdoor Loss of material External Surfaces Monitoring of VIII.H.S-402a 3.4-1, A bounda!Y steel {ext} Mechanical Com~onents 063
{B.2.3.23}
Piping (insulated) Pressure Stainless Air-outdoor Cracking External Surfaces Monitoring of VIII.H.S-452c 3.41 , A boundary steel (ext) Mechanical Components 104 (B.2.3.23)
Piping (insulated) Pressure Stainless Air- outdoor Loss of material External Surfaces Monitoring of VIII.H .S-451c 3.4-1 , A boundary steel (ext) Mechanical Components 103 (B.2.3.23)
Piping (insulated) Leakage Carbon Air- outdoor Loss of material External Surfaces Monitoring of VI 11.H.S-402a 3.4-1 , A (Unit 1 only) boundary steel (ext) Mechanical Components 063 (spatial) (B.2.3.23)
Piping (Unit 1 only) Leakage Carbon Air- outdoor Loss of material External Surfaces Monitoring of VIII.H.S-29 3.4-1 , A boundary steel (ext) Mechanical Components 034 (spatial) (B.2.3.23)
St. Lucie Nuclear Plant Units 1 and 2 L-2023-131 Dockets 50-335 and 50-389 Attachment 2 Page 7 of7 Affected SLRA Content Revisions SLRA Section 3.4 (Table 3.4.2-3), page 3.4-78 is revised as follows:
rrable 3.4.2-3: Auxiliary Feedwater and Condensate - Summary of AQinQ Ma:naQement Evaluation Component Type Intended Material Environment Aging Effect Aging Management Program NUREG-2191 Table Notes Function Requiring Item 1 Item ManaQement Valve body Pressure Stainless Treated water Cracking Water Chemistry (B.2.3.2) VIII.G.SP-88 3.4-1 , A boundary steel >140°F (int) One-Time Inspection (B.2.3.20) 011 Valve bod)l Pressure Carbon Air- outdoor Loss of material External Surfaces Monitoring of VIII.H.S-402a 3.4-1. 8.
{insulated} boundarv steel {ext} Mechanical ComRonents 063 (B.2.3.23)
Valve Pressure Stainless Air- outdoor Cracking External Surfaces Monitoring of VIII.H.S-452c 3.4-1, A body boundary steel (ext) Mechanical Components 104 (insulated) (B.2.3.23)
Valve Pressure Stainless Air - outdoor Loss of material External Surfaces Monitoring of VIII.H .S-451c 3.4-1, A body boundary steel (ext) Mechanical Components 103 (insulated) (B.2.3.23)
Valve body Leakage Carbon Air- outdoor Loss of material External Surfaces Monitoring of VIII.H.S-402a 3.4-1, A (insulated) (Unit 1 boundary steel (ext) Mechanical Components 063 only) (spatial) (B.2.3.23)
Valve body (Unit 1 Leakage Carbon Air- outdoor Loss of material External Surfaces Monitoring of VIII.H .S-29 3.4-1, A only) boundary steel (ext) Mechanical Components 034 (spatial) (B.2.3.23)
Valve body (Unit 1 Leakage Carbon Treated Loss of material Water Chemistry (B.2.3.2) VIII.G.SP-74 3.4-1 , A only) boundary steel water (int) One-Time Inspection (B.2.3.20) 014 (spatial)
Valve body (Unit 1 Leakage Carbon Treated Wall thinning- Flow-Accelerated Corrosion VIII.G.S-408 3.4-1, A only) boundary steel water (int) erosion (B.2.3.8) 060 (spatial)
Valve body (Unit 1 Leakage Carbon Treated Wall thinning - Flow-Accelerated Corrosion VIII.G.S-16 3.4-1 , A only) boundary steel water (int) FAC (B.2.3.8) 005 (spatial)