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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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Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 0 August 10, 2006 F=PL L-2006-152 10 CFR 50.4 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: St. Lucie Unit 2 Docket No. 50-389 NRC Order EA-03-009 - Reactor Vessel Head and Vessel Head Penetration Nozzle Inspection Results SL2-16 In April 2006, St. Lucie Unit 2 commenced refueling outage SL2-16. Based on the results of the visual examinations, UT examinations, supplemental OD NDE and leak path assessments (including ECT of the vent), FPL concludes that the RVHP nozzles are not degraded and no wastage has occurred of the RPV head.
In accordance with Section IV.E of the NRC Order (EA-03-009), the attachment submits the FPL inspection results for St. Lucie Unit 2 for the spring 2006 refueling outage (SL2-16).
Please contact Ken Frehafer at (772) 467-7748 if there are any questions about this submittal.
Very truly yours, GLJ/KWF Attachment Alo(
an FPL Group company
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 1 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 FIRST REVISED NRC ORDER EA-03-009:
REACTOR PRESSURE VESSEL HEAD AND VESSEL HEAD PENETRATION NOZZLE POST REFUELING OUTAGE INSPECTION RESULTS FOR ST. LUCIE UNIT 2 - Spring 2006 The First Revised NRC Order EA-03-009 [i] was issued on February 20, 2004, establishing interim inspection requirements for reactor pressure vessel heads of pressurized water reactors.
In Section IV.E. of the NRC Order, the NRC required that the results of the inspection be provided within 60 days of the plant being returned to operation. Florida Power and Light Company (FPL) hereby submits the inspection results for St. Lucie Unit 2 (PSL-2) for the spring 2006 (SL2-16) refueling outage (RFO).
St. Lucie Unit 2 Spring 2006 (SL2-16) Post Outage Reactor Vessel Upper Head Inspection Results:
- 1. Plant Susceptibility Category:
The St. Lucie Unit 2 reactor pressure vessel (RPV) closure head had approximately 16.3 effective degradation years (EDY) at the start of the Spring 2006 refueling outage. The inspection category identified in the Order is High. The corresponding inspection method for the High Category is specified in Section IV.C.(1) of the NRC Order.
- 2. Inspection Scope and Method:
2.a. RPV Bare Metal Head Surface Visual: A bare metal visual inspection (VT) of the RPV head top surface, including 3600 around each RPV head penetration nozzle, was performed in accordance with section IV.C.(5)(a) of the NRC Order and supplemented by Relaxation Request Number 4 ["1 approved by the NRC on December 27, 2004 and January 10, 2005.
[".." [Iv] The VT was performed under the insulation by delivering a video probe under the shroud support ring after removal of flashing panels. Limitations to the bare metal visual inspection were identified in the Relaxation Request. ["I These limitations included a partial area under 32 insulation support feet (<118 square inches) and the inaccessible areas under the -2 1/4" wide vertical leg of the reflective metal insulation that contacts the twelve 6-inch wide shroud lugs. In addition, the areas inside the 54 RV stud holes were limited. The total area of limitation is less than 1% of the total reactor vessel head surface area available for inspection.
2.b. RPV Head Penetration Non Visual Inspection: The ultrasonic (UT) examination technique option, identified in section IV.C.(5)(b)(i) of the First Revised NRC Order, was performed on all of the 102 reactor vessel head penetration (RVHP) nozzles, including the vent line. The examination area was planned to meet the NRC Order required area for the ICI, vent and previously repaired CEDM penetrations. For the 86 CEDMs with the original threaded guide cone configuration, the inspection was planned to include the nozzle base material 2 inches above the J-groove weld to the bottom of the weld. However, below the weld the UT
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 2 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 examination was planned to the maximum extent possible. If the area below the weld coverage was less than 0.50 inches, non visual NDE from the outside diameter (OD) would be used to extend the coverage to the maximum extent possible, but not less than 0.50 inches below the weld toe. The methods used for the OD NDE were automated UT and manual PT. The limitations associated with the threaded guide funnels in the original CEDM penetrations were the subject of Relaxation Request Number 3 [ii] and corresponding NRC approval [iii&iv] of the relaxation.
As part of the UT examinations, the 101 RVHPs with interference fits were assessed to determine if leakage had occurred into the interference fit zone (annulus between the RPV head and the penetration above the pressure boundary weld). This assessment used the Areva/Framatome-ANP proprietary "leak path" technique, which was described in the post outage inspection report for a previous FPL St. Lucie Unit 1 RPV head inspection. [v)
The UT inspection procedure and essential variables used on the 101 RVHPs with interference fits has been demonstrated as part of the industry demonstration program conducted by the EPRI NDE Center. The personnel qualification requirements that were described in Reference [vi remain unchanged.
An eddy current examination (ECT) was performed on the vent nozzle weld surface to ensure weld integrity in lieu of the UT method to assess if leakage has occurred into the clearance fit annulus between the vent nozzle and RPV head steel. The ECT procedure had been successfully demonstrated on RVHP J-groove attachment welds as part of the industry demonstration program conducted by the EPRI NDE Center. All essential variables (Examination Technique Specification sheets, ETSS) and procedural requirements used during the vent nozzle weld examination remained essentially the same as those previously demonstrated.
- 3. Inspection Results Summary:
3.a. RPV Head Visual Results: The overall condition of the St. Lucie Unit 2 RPV head surface was clean with no evidence of leakage occurring from the RV head to penetration interface of the 102 RVHPs. No wastage or boric acid buildup was observed on the reactor vessel head surface.
Some thin film boric acid stains were observed on the vertical surfaces and insulation overhead of penetrations #2, 13, 49, 51, 74, and 83, and in-core instrument (ICI) column # 97. The thin film nature of the stains and lack of buildup is indicative of non operational leakage. The source of the stains was attributed to CEDM venting and past ICI column leakage prior to startup.
There was no degradation of the RPV head surface associated with the boric acid stains. These conditions were addressed as part of our boric acid corrosion control program and the corrective action program.
3.b. RPV Head Penetration Non Visual Inspection Results: There were no relevant indications identified by the ID UT in any of the 102 RVHPs in the St. Lucie Unit 2 RPV head.
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 3 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 Supplemental OD NDE was required on 17 CEDM nozzles to obtain the required examination area of 0.50 inches below the weld. The OD NDE method included UT and manual dye penetrant (PT). A limitation was experienced on 15 CEDM nozzles, where the OD UT was utilized to extend the coverage below the weld toe. These limitations were caused by lift off at the funnel plug weld on the high hillside of the nozzle. The small lift off limitations were > 3.80 inches below the weld toe. The supplemental OD NDE (UT and PT) did not reveal any relevant indications. The details of the ID coverage, supplemental OD coverage, and limitations associated with the funnel plug weld are described in Tables 1 and 2 and Figure 1.
An assessment to determine if leakage has occurred into the interference fit zone was performed for the 101 interference fit RVHPs. There was no evidence of a "leak path" signature for any of the 101 interference fit RVHPs examined. The "leak path" assessment is performed using the Areva/Framatome-ANP demonstrated method that utilizes UT in the interference fit zone above the pressure boundary weld. The assessment results are confirmed by the results of the bare metal visual examination. Since the vent line is a clearance fit nozzle, the clean visual examination provides a direct determination that no leakage has occurred into the annulus.
However, as an added conservatism, the flush pressure boundary surface inside of the RPV head associated with the vent line (the head vent line, alloy 600 attachment weld, and a portion of the adjacent stainless steel clad weld) was examined using a surface eddy current examination (ECT) method. The reporting criteria utilized for the ECT examination was to report all indications.
The acceptance criteria utilized for this ECT examination was "no identified flaws or degradation." There were no flaws or degradation detected by the ECT technique in the inspected area of the weld associated with the head vent nozzle. This examination provides additional confirmation for the assessment that the vent nozzle has no leakage into the annulus.
- 4. Corrective Actions:
With no indications of cracking in the penetrations and no evidence of boric acid buildup associated with pressure boundary leakage, no corrective actions were required to address the integrity of the reactor vessel upper head and penetrations.
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 4 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 5.
Conclusion:
FPL has met the requirements of the First Revised NRC Order (EA-03-009) as modified by NRC approved relaxation requests [iii&iv] for the St. Lucie Unit 2 Spring 2006 refueling outage by performing the required RPV head inspection.
Based on the results of the visual examinations, UT examinations, supplemental OD NDE, leak path assessments (including ECT of the vent), FPL concludes that the RVHP nozzles are not degraded, and no wastage has occurred of the RPV head.
i US NRC Letter EA-09-009, "Issuance Of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements For Reactor Pressure Vessel Heads At Pressurized Water Reactors," from William Borchardt (NRC) to all Pressurized Water Reactor Licensees, Dated February 20, 2004.
" FPL letter L-2004-095, "St. Lucie Unit 2, Docket No. 50-389, Order (EA-03-009) Relaxation Requests 3 and 4, Examination Coverage of Reactor Pressure Vessel Head Penetration Nozzles," W. Jcfferson to NRC, May 6, 2004.
6"US NRC Letter (Adams Accession No. ML043430268), "St. Lucie Plant, Unit 2, First Revised Order EA-03-009 Relaxation Requests No. 3 Regarding Examination Coverage of Reactor Pressure Vessel Hlead Penetration Nozzles, and Relaxation Request No. 4 Regarding Examination Coverage of Reactor Pressure Vessel Head Bare Metal Visual Examination, (TAC Nos. MC3107 and MC3 108)," E. M. Hlackett (NRC) to J.A.
Stall, December 27, 2004.
V US NRC Letter (Adams Accession No. ML050070085), "St. Lucie Plant, Unit 2, Correction to NRC Safety Evaluation for First Revised Order EA-03-009 Relaxation Requests No. 3 Regarding Examination Coverage of Reactor Pressure Vessel Hlead Penetration Nozzles, (TAC No.
MC3107)," E. M. Hackett (NRC) to J.A. Stall, January 10, 2005.
V FPL letter L.-2002-233, "St. Lucie Units I and 2, Docket Nos. 50-335, 50-389, Reactor Pressure Vessel [lead (RPVH Inspection, NRC Bulletin 2002-02 Supplemental Response," D. E. Jernigan to NRC, November 21, 2002.
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 5 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 "A"R B"Coverage Limitations Due to Funnel Plug Weld C > 0 E o > ID ID ID 0 0 Coverage Coverage Coverage Q '4 I
'a 3: below below above -- . 0 0 0." weld on weld on weld on X M
" M. downhill uphill uphill a.) 0 0 side of side of side of Axial weld weld weld Angular Extent Extent Comments (in.) (in.) (In.) (deg.) Min Max Total (in.)
CEDM 1 0.5 1.02 1.02 4.44 360 n/a n/a n/a n/a NO NRI YES CEDM 2 0.5 1.08 1.79 4.31 360 n/a n/a n/a n/a NO NRI YES CEDM 3 0.5 1.09 1.85 4.09 360 n/a n/a n/a n/a NO NRI YES CEDM 4 0.5 0.91 2.02 4.07 360 n/a n/a n/a n/a NO NRI YES CEDM 5 0.5 0.90 1.97 4.36 360 n/a n/a n/a n/a NO NRI YES CEDM 6 0.5 1.02 2.20 4.23 360 n/a n/a n/a n/a NO NRI YES CEDM 7 0.5 0.91 2.15 4.09 360 n/a n/a n/a n/a NO NRI YES CEDM 8 0.5 0.79 2.21 3.40 360 n/a n/a n/a n/a NO NRI YES CEDM 9 0.5 0.90 2.44 2.92 360 n/a n/a n/a n/a NO NRI YES CEDM 10 0.5 0.91 2.44 3.86 360 n/a n/a n/a n/a NO NRI YES CEDM 11 0.5 0.78 2.26 3.74 360 n/a n/a n/a n/a NO NRI YES CEDM 12 0.5 0.91 2.55 4.00 360 n/a n/a n/a n/a NO NRI YES CEDM 13 0.5 1.10 2.67 3.90 360 n/a n/a n/a n/a NO NRI YES CEDM 14 0.5 0.90 2.38 3.14 360 n/a n/a n/a n/a NO NRI YES CEDM 15 0.5 1.02 2.55 4.12 360 n/a n/a n/a n/a NO NRI YES CEDM 16 0.5 0.91 2.62 4.19 360 n/a n/a n/a n/a NO NRI YES CEDM 17 0.5 1.03 2.56 4.05 360 n/a n/a n/a n/a NO NRI YES CEDM 18 0.5 6.10 6.10 6.40 360 n/a n/a n/a n/a NO NRI YES Previous IDTB Repair CEDM 19 0.5 1.08 2.20 4.17 360 n/a n/a n/a n/a NO NRI YES CEDM 20 0.5 0.84 2.91 3.30 360 n/a n/a n/a n/a NO NRI YES CEDM 21 0.5 0.95 2.91 2.81 360 n/a n/a n/a n/a NO NRI YES
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 6 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 A" foci@ Coverage Limitations Due to
""Bv. ."Funnel Plug Weld
.E >
" o ID ID ID 0 £ o0 0 Coverage Coverage Coverage ' 7U
- *o - below below above - 0. 40 0 0 weld on weld on weld on
. M. downhill uphill uphill . :
M 0 side of side of side of Axial weld weld weld Annular Extent Extent Comments (in.) (in.) (in.) (deg.) Mmn Max Total (in.)
CEDM 22 0.5 0.96 3.02 3.54 360 n/a n/a n/a n/a NO NRI YES CEDM 23 0.5 0.67 2.85 3.69 360 n/a n/a n/a n/a NO NRI YES CEDM 24 0.5 0.79 2.79 3.36 360 n/a n/a n/a n/a NO NRI YES CEDM 25 0.5 0.83 2.97 3.00 360 n/a n/a n/a n/a NO NRI YES CEDM 26 0.5 0.75 2.85 3.91 360 n/a n/a n/a n/a NO NRI YES CEDM 27 0.5 6.10 6.10 8.30 360 n/a n/a n/a n/a NO NRI YES Previous IDTB Repair CEDM 28 0.5 0.85 3.15 3.41 360 n/a n/a n/a n/a NO NRI YES CEDM 29 0.5 0.91 3.03 3.24 360 n/a n/a n/a n/a NO NRI YES CEDM 30 0.5 0.90 3.20 3.00 360 n/a n/a n/a n/a NO NRI YES CEDM 31 0.5 1.02 3.21 3.90 360 n/a n/a n/a n/a NO NRI YES CEDM 32 0.5 5.10 5.10 6.02 360 n/a n/a n/a n/a NO NRI YES Previous IDTB Repair CEDM 33 0.5 0.85 3.09 3.96 360 n/a n/a n/a n/a NO NRI YES CEDM 34 0.5 0.84 3.08 3.98 360 n/a n/a n/a n/a NO NRI YES CEDM 35 0.5 0.79 3.03 3.83 360 n/a n/a n/a n/a NO NRI YES CEDM 36 0.5 0.67 3.32 3.02 360 n/a n/a n/a n/a NO NRI YES CEDM 37 0.5 0.85 3.56 2.70 360 n/a n/a n/a n/a NO NRI YES CEDM 38 0.5 0.90 3.44 2.40 360 n/a nfa n/a n/a NO NRI YES CEDM 39 0.5 0.85 3.50 2.99 360 n/a n/a n/a n/a NO NRI YES CEDM 40 0.5 0.90 3.56 3.60 360 n/a n/a n/a n/a NO NRI YES CEDM 41 0.5 0.50 3.27 3.38 360 n/a n/a n/a n/a NO NRI YES CEDM 42 0.5 0.73 3.44 3,49 360 n/a n/a n/a n/a NO NRI YES
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 7 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 Coverage Limitations Due to "A "B" "C" Funnel Plug Weld
> "o ID ID ID o U E0 0 Coverage Coverage Coverage 0 3:0 below weld on below weld on above weld on I-L c.
t5
- 5co downhill uphill uphill .
- side of side of side of Axial n, weld weld weld Angular Extent Extent Comments (in.) (in.) (In.) (deg.) MIn Max Total (In.)
CEDM 43 0.5 0.73 3.32 3.30 360 n/a n/a n/a n/a NO NRI YES CEDM 44 0.5 0.80 3.79 2.70 360 n/a n/a n/a n/a NO NRI YES CEDM 45 0.5 0.84 3.97 5.96 360 n/a n/a n/a n/a NO NRI YES CEDM 46 0.5 0.60 3.67 3.16 360 n/a n/a n/a n/a NO NRI YES CEDM 47 0.5 0.62 3.79 3.57 360 n/a n/a n/a n/a NO NRI YES CEDM 48 0.5 0.62 3.73 3.04 360 n/a n/a n/a n/a NO NRI YES CEDM 49 0.5 0.70 3.91 2.90 360 n/a n/a n/a n/a NO NRI YES CEDM 50 0.5 0.62 3.86 5.33 360 n/a n/a n/a n/a NO NRI YES CEDM 51 0.5 0.73 4.09 5.80 360 n/a n/a n/a n/a NO NRI YES CEDM 52 0.5 0.55 4.03 3.79 360 n/a n/a n/a n/a NO NRI YES CEDM 53 0.5 0.50 3.79 3.80 360 n/a n/a n/a n/a NO NRI YES CEDM 54 0.5 0.43 3.91 4.10 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 144 207 63 0.07 n/a NRI OD UT Scan, See Table 2 for details CEDM 55 0.5 0.67 3.80 3.11 360 n/a n/a n/a n/a NO NRI YES CEDM 56 0.5 7.30 7.30 7.00 360 n/a n/a n/a n/a NO NRI YES Previous IDTB Repair CEDM 57 0.5 0.91 3.97 2.83 360 n/a n/a n/a n/a NO NRI YES CEDM 58 0.5 0.85 4.26 3.47 360 n/a n/a n/a n/a NO NRI YES CEDM 59 0.5 0.32 3.80 3.79 360 n/a n/a n/a n/a NO NRI YES IDUT to be Supplemented by OD UT n/a n/a n/a n/a 169 229 60 0.18 n/a NRI OD UT Scan, See Table 2 for details CEDM 60 0.5 0.73 4.21 2.85 360 n/a n/a n/a n/a NO NRI YES CEDM 61 0.5 0.60 4.14 2.46 360 n/a n/a n/a n/a NO NRI YES
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 8 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 Coverage Limitations Due to
""~ "B" "C" Funnel Plug Weld V M "E D 00 D I >
S o
- 0 Coverage Coverage Coverage 0 V below below above -. 0 ,
C 0 0 weld on weld on weld on I. z 2-6 to downhill 1.
uphill uphill 0 M side of side of side of Axial weld weld weld An ular Extent Extent Comments (in.) (In.) (In.) (deg.) Min Max Total (In.)
CEDM 62 0.5 0.68 4.44 5.25 360 n/a n/a n/a n/a NO NRI YES CEDM 63 0.5 0.79 4.32 3.38 360 n/a n/a n/a n/a NO NRI YES CEDM 64 0.5 0.96 4.38 3.25 360 n/a n/a n/a n/a NO NRI YES CEDM 65 0.5 0.61 4.38 3.54 360 n/a n/a n/a n/a NO NRI YES CEDM 66 0.5 0.44 4.08 3.68 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 166 220 54 0.06 n/a NRI OD UT Scan, See Table 2 for details CEDM 67 0.5 0.73 4.20 3.00 360 n/a n/a n/a n/a NO NRI YES CEDM 68 0.5 0.70 4.98 2.97 360 n/a n/a n/a n/a NO NRI YES CEDM 69 0.5 0.56 4.80 3.40 360 n/a n/a n/a n/a NO NRI YES CEDM 70 0.5 0.43 4.68 4.80 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 146 207 61 0.07 n/a NRI OD UT Scan, See Table 2 for details CEDM 71 0.5 0.67 4.85 4.62 360 n/a n/a n/a n/a NO NRI YES CEDM 72 0.5 3.66 3.66 3.71 360 n/a n/a n/a n/a NO NRI YES Previous IDTB Repair CEDM 73 0.5 0.56 4.97 3.80 360 n/a n/a n/a n/a NO NRI YES CEDM 74 0.5 0.61 5.09 3.31 360 n/a n/a n/a n/a NO NRI YES CEDM 75 0.5 0.43 4.26 3.70 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 157 208 51 0.07 n/a NRI OD UT Scan, See Table 2 for details CEDM 76 0.5 0.61 5.20 3.87 360 n/a n/a n/a n/a NO NRI YES CEDM 77 0.5 0.43 4.97 3.82 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 138 192 54 0.07 n/a NRI OD UT Scan, See Table 2 for details CEDM 78 0.5 0.56 4.85 3.71 360 n/a n/a n/a n/a NO NRI YES
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 9 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16
.1A"1 BCoverage Limitations Due to "B" Funnel Plug Weld "V E'o > 4)E 0 f ID ID ID 0 Eo Coverage Coverage Coverage 13 4)~ O~ below below above d0. 4) 0 04)E weld on weld on weld on d -, U)
U
. *.m downhill uphill uphill .
4 side of side of side of Axial weld weld weld An ular Extent Extent Comments (in.) (in.) (In.) (deg.) Min Max Total (in.)
CEDM 79 0.5 0.43 4.68 3.40 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 117 211 94 0.07 n/a NRI OD UT Scan, See Table 2 for details CEDM 80 0.5 0.44 4.80 3.50 360 n/a n/a n/a n/a NO NRI YES IDUT to be Supplemented by OD UT n/a n/a n/a n/a 161 220 59 0.06 n/a NRI OD UT Scan, See Table 2 for details CEDM 81 0.5 0.48 4.62 3.30 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 150 208 58 0.02 n/a NRI OD UT Scan, See Table 2 for details CEDM 82 0.5 0.50 5.21 2.82 360 n/a n/a n/a n/a NO NRI YES CEDM 83 0.5 0.43 4.91 3.14 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 156 212 56 0.07 n/a NRI OD UT Scan, See Table 2 for details.
CEDM 84 0.5 0.61 5.20 3.19 360 n/a n/a n/a n/a NO NRI YES CEDM 85 0.5 0.45 4.97 3.58 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 139 197 58 0.05 n/a NRI OD UT Scan, See Table 2 for details CEDM 86 0.5 0.40 4.86 3.19 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 151 206 55 0.10 n/a NRI OD UT Scan, See Table 2 for details CEDM 87 0.5 0.34 4.91 3.10 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 149 200 51 0.16 n/a NRI OD UT Scan, See Table 2 for details CEDM 88 0.5 0.32 5.80 3.00 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 145 209 64 0.18 n/a NRI OD UT Scan, See Table 2 for details CEDM 89 0.5 0.20 5.62 2.56 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 135 188 53 0.30 n/a NRI OD UT Scan, See Table 2 for details CEDM 90 0.5 0.49 6.33 3.34 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 10 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 Coverage Limitations Due to "B" (D Funnel Plug Weld 0 = > ID ID ID o E
.2 °0 Coverage Coverage Coverage W o
0 : below below above -
S 0 00 weld on weld on weld on I z .-
- m j;'U6 downhill uphill uphill .
side of side of side of Axial weld weld weld Angular Extent Extent Comments (In.) (in.) (In.) (deg.) Min Max Total (in.)
n/a n/a n/a n/a 159 213 54 0.01 n/a NRI OD UT Scan, See Table 2 for details CEDM 91 0.5 0.32 5.51 3.28 360 n/a n/a n/a n/a NO NRI YES IDUT to be Supplemented by OD UT I n/a n/a n/a n/a 169 223 54 0.18 n/a NRI OD UT Scan, See Table 2 for details ICI 92 N/A n/a n/a 4.78 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 93 N/A n/a n/a 3.40 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 94 N/A n/a n/a 4.15 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 9 N/A n/a n/a 3.90 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head
____ N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 96 N/A n/a n/a 4.80 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 97 N/A n/a n/a 5.60 360 n/a n/a n/a n/a NO NRI YE eds Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI ___Single Element Head Supplemental Scan ICI 98 N/A n/a n/a 5.37 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head
____ N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI ___Single Element Head Supplemental Scan ICI 99 N/A n/a n/a 4.42 360 n/a n/a n/a n/a NO NRi YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 100 N/A n/a n/a 4.53 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 11 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 Coverage Limitations Due to "A" "B"' Funnel Plug Weld V
> E 0 ID ID ID Qo o
.- 0 ý: Coverage Coverage Coverage m , 0
- S3: below below above - (. :
0 2--Z weld on weld on weld on C" 'Sc downhill uphill uphill to side of side of side of Axial weld weld weld Angular Extent Extent Comments (in.) (in.) (in.) (deg.) Min Max Total (in.)
N/A n/a n/a 4.40 360 n/a n/a n/a n/a NO YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan Vent 102 N/A n/a n/a 2.97 360 n/a n/a n/a n/a n/a NRI YES UT of bore performed N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI YES ET performed on J-Groove Weld NRI - No Recordable Indications IND - Indications
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 12 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 2: Coveracie Assessment for Nozzles Examined with Cnv~rz~na I imi$atinnc~
ID UT COVERAGE OD UT COVERAGE OD UT EXCLUSION ZONE "A" "B.. .C D"$ _....
ID ID Coverage Coverage shortage ID ID Axial below weld below weld Coverage Coverage OD height of Required on on below weld above weld Coverage IDOD ID/OD weld plug Coverage downhill downhill on uphill on uphill height Axial Axial Below exclusion side of side of side of side of Circ. ID from end Coverage Coverage Coy Funnel plug weld in 112" Nozzle # Weld weld weld weld weld Coverage of nozzle Overlap Gap Imperage Impacted exclusionzone (deg.) band (in.) (in.) (in.) In. (deg.) (in.) (in.) (in.) ? Min Max Total (in.)
54 0.5 0.43 0.07 3.91 4.10 360 1.10 0.225 None Yes 144 :207 63 0.07 59 0.5 0.32 0.18 3.80 3.79 360 1.08 0.205 None Yes 169 229 60 0.18 66 0.5 0.44 0.06 4.08 3.68 360 1.10 0.225 None Yes 166- -220 54 0.06 70 0.5 0.43 0.07 4.68 4.80 360 1.13 0.255 None Yes 146. .207 .61 0.07 75 0.5 0.43 0.07 4.26 3.70 360 1.11 0.235 None Yes 157 1208 51 0.07 77 0.5 0.43 0.07 4.97 3.82 360 1.06 0.185 None Yes 138- -192 54,--- 0.07 79 0.5 0.43 0.07 4.68 3.40 360 1.04 0.165 None Yes -17. -211 `94 0.07 80 0.5 0.44 0.06 4.80 3.50 360 1.05 0.175 None Yes 161 220 - 0.06 81 0.5 0.48 0.02 4.62 3.30 360 1.18 0.305 None Yes 150 208 58 0.02 83 0.5 0.43 0.07 4.91 3.14 360 1.06 0.185 None Yes 156 212 56 0.07 85 0.5 0.45 0.05 4.97 3.58 360 1.19 0.315 None Yes 139 197 58 0.05 86 0.5 0.40 0.10 4.86 3.19 360 1.10 0.225 None Yes 151 206 55 0.10 87 0.5 0.34 0.16 4.91 3.10 360 1.03 0.155 None Yes 149 200 51 0.16 88 0.5 0.32 0.18 5.80 3.00 360 0.98 0.105 None Yes 145 209 64 0.18 89 0.5 0.20 0.30 5.62 2.56 360 0.75 -0.125 0.125 Yes 135 188 53 0.30 90 0.5 0.49 0.01 6.33 3.34 360 1.20 0.325 None Yes 159 213 54 0.01 91 0.5 0.32 0.18 5.51 3.28 360 1.10 0.225 None Yes 169 223 ..54 0.18
St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 13 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 2: Coverage Assessment for Nozzles Examined with Coverage Limitations Note: Nozzle 79 coverage is limited for 94 degrees in the area of the funnel plug weld due to a mechanical restriction and the funnel plug weld itself that prevents the OD UT tooling from scanning this location. The limitation is due to localized deformation of the funnel that was caused by repair activities of adjacent nozzle 59 during the last refueling outage. The incident that caused the funnel deformation is documented in FPL condition report #2005-2263. Because of this restriction a PT examination was performed on the affected area starting on a plane located approximately 1/16" inch below the low hill J-groove weld toe and progressing to the end of the nozzle. The PT results were free of recordable indications.
Note: Nozzle 89 coverage is limited for 66 degrees centered at the low hill side starting at a position measured 0.2 inches below the downhill toe of the weld and extending for a distance of 0.125" toward the end of the nozzle. The limitation is due an unusually large fillet radius at the low hill side of the nozzle that restricts the OD UT probe travel and prevents the OD UT from obtaining complete coverage in this area. A limitation also exists at the site of the funnel plug weld for the dimensions listed in the table. Because of these restrictions a PT examination was performed on the entire nozzle circumference starting on a plane located approximately 1/16" inch below the low hill J-groove weld toe and progressing to the end of the nozzle. The PT results were free of recordable indications.
Note: The angular coordinate for the OD UT was established visually by placing the transducer module at the uphill side and declaring that position 180 degrees.
Position accuracy is estimated to be + - 20 degrees.
St. Lucie Unit 2 L-2006-152 a Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 14 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 ID UT Coverage Below Weld at r 40.5" Coverage -
Down-hill Side Commitment End of
. Nozzle Figure 1: St. Lucie 2 CEDM Examination Coverage Parameters