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Category:Letter type:L
MONTHYEARL-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements 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-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024 NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report 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-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023 Submittal of Changes to the Technical Specification Bases L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-176, 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-2023-160, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-131, 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-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-107, 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-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-104, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-099, 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-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections 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-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 2024-01-08
[Table view] Category:Report
MONTHYEARML23333A0142023-11-27027 November 2023 Attachment F - Groundwater Tek Inc - Peer Review Study Final-1 ML23333A0172023-11-27027 November 2023 Attachment I - Chin - the Cooling Canal System at the FPL-Turkey-Point Power Station ML24012A0422023-11-16016 November 2023 FAQ 23-03 Turkey Point IE01 Proposed NRC Response L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update ML23265A5512023-09-22022 September 2023 Enclosure 3: WCAP-18830-NP, Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections 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-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report 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-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2022-10-0404 October 2022 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2022-110, License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary)2022-08-26026 August 2022 License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary) L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 ML22227A0532022-08-15015 August 2022 Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-022022-07-29029 July 2022 Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 ML22140A1392022-05-20020 May 2022 Attachment 4 - Cross-Reference of TSTF-505, Revision 2, and Point Beach Proposed Changes ML22140A1332022-05-20020 May 2022 Attachment 1 - Evaluation of the Proposed Changes ML22140A1352022-05-20020 May 2022 RPS Instrumentation ML22140A1362022-05-20020 May 2022 Containment Isolation Valves ML22140A1382022-05-20020 May 2022 Containment Isolation Valves ML22140A1402022-05-20020 May 2022 Attachment 5 - Evaluation of Plant-Specific Variations ML22140A1422022-05-20020 May 2022 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions and Additional Supporting Information ML22140A1412022-05-20020 May 2022 Attachment 6 - Point Beach RICT Program Pre-Implementation Items ML22140A1432022-05-20020 May 2022 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by PRA Models ML22140A1442022-05-20020 May 2022 Enclosure 8 - Attributes of the Configuration Risk Management Model NRC 2022-0007, Enclosure 11 - Monitoring Program2022-05-20020 May 2022 Enclosure 11 - Monitoring Program L-2022-038, Emergency Response Data System (Eros) Changes2022-05-17017 May 2022 Emergency Response Data System (Eros) Changes L-2022-073, Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-05-0303 May 2022 Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 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-2022-022, Updated Conditions of Certification Report2022-02-14014 February 2022 Updated Conditions of Certification Report 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 SBK-L-21106, Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program2021-09-30030 September 2021 Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program L-2021-182, Summary of Commitment Revisions, Emergency Diesel Generator Fuel Oil Storage Tank Cleaning Inspection Commitment Revisions2021-09-16016 September 2021 Summary of Commitment Revisions, Emergency Diesel Generator Fuel Oil Storage Tank Cleaning Inspection Commitment Revisions 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 ML21214A0432021-08-0202 August 2021 SLRA June 30, 2021, Public Meeting Discussion Questions L-2021-069, Commitment Revision Summary Report for Reactor Vessel Head Leakage Detection System (Rvhlds)2021-06-24024 June 2021 Commitment Revision Summary Report for Reactor Vessel Head Leakage Detection System (Rvhlds) ML21126A2392021-05-0606 May 2021 Subsequent License Renewal Application, Aging Management Supplement 2 ML21062A1462021-04-21021 April 2021 Memo to File: Final Ea/Fonsi of 2012 and 2015 Decommissioning Funding Plans for Seabrook Station Unit 1 Independent Spent Fuel Storage Installation (2012 and 2015) ML21040A4852021-02-0909 February 2021 Fws to NRC, Verification Letter for Point Beach SLR Under Programmatic Biological Opinion for Northern Long-eared Bat ML21040A4842021-02-0909 February 2021 Fws to NRC, Point Beach Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location And/Or May Be Affected by Your Project NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report ML21008A0172020-10-25025 October 2020 Revised ANS Design Report IR 05000250/20200112020-07-23023 July 2020 NRC Inspection Report 05000250-2020011 and 05000251-2020011 and Investigation Report 2-2019-011; and Apparent Violation Final 2023-09-28
[Table view] Category:Technical
MONTHYEARML23333A0142023-11-27027 November 2023 Attachment F - Groundwater Tek Inc - Peer Review Study Final-1 ML23333A0172023-11-27027 November 2023 Attachment I - Chin - the Cooling Canal System at the FPL-Turkey-Point Power Station ML23265A5512023-09-22022 September 2023 Enclosure 3: WCAP-18830-NP, Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2022-10-0404 October 2022 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2022-110, License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary)2022-08-26026 August 2022 License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary) L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-022022-07-29029 July 2022 Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 NRC 2022-0007, Enclosure 11 - Monitoring Program2022-05-20020 May 2022 Enclosure 11 - Monitoring Program ML22140A1442022-05-20020 May 2022 Enclosure 8 - Attributes of the Configuration Risk Management Model ML22140A1432022-05-20020 May 2022 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by PRA Models ML22140A1422022-05-20020 May 2022 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions and Additional Supporting Information ML22140A1412022-05-20020 May 2022 Attachment 6 - Point Beach RICT Program Pre-Implementation Items ML22140A1402022-05-20020 May 2022 Attachment 5 - Evaluation of Plant-Specific Variations ML22140A1392022-05-20020 May 2022 Attachment 4 - Cross-Reference of TSTF-505, Revision 2, and Point Beach Proposed Changes ML22140A1382022-05-20020 May 2022 Containment Isolation Valves ML22140A1362022-05-20020 May 2022 Containment Isolation Valves ML22140A1352022-05-20020 May 2022 RPS Instrumentation ML22140A1332022-05-20020 May 2022 Attachment 1 - Evaluation of the Proposed Changes L-2022-073, Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-05-0303 May 2022 Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 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-2022-022, Updated Conditions of Certification Report2022-02-14014 February 2022 Updated Conditions of Certification Report 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 SBK-L-21106, Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program2021-09-30030 September 2021 Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program 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 L-2021-069, Commitment Revision Summary Report for Reactor Vessel Head Leakage Detection System (Rvhlds)2021-06-24024 June 2021 Commitment Revision Summary Report for Reactor Vessel Head Leakage Detection System (Rvhlds) NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report ML21008A0172020-10-25025 October 2020 Revised ANS Design Report L-2020-073, Fifth Ten-Year Inservice Inspection Interval Revised Relief Request No. 6 and Supplemental Information for Train B CCW Return Piping2020-04-13013 April 2020 Fifth Ten-Year Inservice Inspection Interval Revised Relief Request No. 6 and Supplemental Information for Train B CCW Return Piping ML20098F3412020-04-0707 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure2019-08-29029 August 2019 Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure 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 L-2019-054, Baffle-Former Bolts Predictive Evaluations2019-03-13013 March 2019 Baffle-Former Bolts Predictive Evaluations ML19072A1622019-03-0505 March 2019 National Park Service, Southeast Regional Office, Comments Dated March 5, 2019, on Turkey Point Nuclear Generating Units 3 and 4 Preliminary Draft SEIS Regarding Subsequent License Renewal ML18353A8352018-12-31031 December 2018 Biological Assessment for the Turkey Point Units 3 and 4 Proposed Subsequent License Renewal ML18299A1162018-10-15015 October 2018 Structural Integrity Associates Engineering Report No. 1700109.401P, Revision 7 - Redacted, Evaluation of Environmentally-Assisted Fatigue for Turkey Point Units 3 and 4 for Subsequent License Renewal ML18299A1182018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.304, Revision 3, Fatigue Crack Growth Evaluation, October 12, 2018 L-2018-174, Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines2018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines L-2018-169, Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review2018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review L-2018-187, Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation2018-10-0505 October 2018 Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation ML18227B5212018-08-15015 August 2018 Submit Attachment a, Annual Hourly Percent Frequency of Vertical and Horizontal Stability Categories by Wind Direction and Wind Speed ML18227A2902018-08-15015 August 2018 Submit Report Contains Official Summary of Startup Physics Tests, Unit 4 Cycle Iii. the Tests Were Conducted in Accordance with Operating Procedure 0204.5, Startup Sequence After Refueling NRC 2018-0017, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2018-05-0202 May 2018 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2018-098, Annual Report for the AP1000 Standard Plant Design, 2017 Model Year 10 CFR 50.462018-04-18018 April 2018 Annual Report for the AP1000 Standard Plant Design, 2017 Model Year 10 CFR 50.46 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 2023-09-22
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MAR 1_ Q_ 2019 L-2019-010 10 CFR 50.55a ATIN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Re: Florida Power & Light Company St. Lucie Units 1 and 2, Docket Nos. 50-335, 50-389 Turkey Point Units 3 and 4, Docket Nos. 50-250, 50-251 N extEra Energy Seabrook, LLC Seabrook Station, Docket No. 50-443 NextEra Energy Point Beach, LLC Point Beach Unjts 1 and 2, Docket Nos. 50-266,59-301
Subject:
Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds
Reference:
NRC letter "Duane Arnold Energy Center; Point Beach Nuclear Plant, Units 1 and 2; Seabrook Station, Unit No. 1; St. Lucie Plant, Unit Nos. 1 and 2; Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Proposed Alternative to use Encoded Phased Array Ultrasonic examination Techniques (EPID L-2017-LLR-0081)," April 25, 2018 (ADAMS Accession No. ML18106B121)
Pursuant to 10 CFR 50.55a(z)(1), Florida Power & Light Company (FPL), acting on behalf of itself and as agent for NextEra Energy Seabrook, LLC and NextEra Energy Point Beach, LLC requests Nuclear Regulatory Commission (NRC) approval of a proposed alternative to
, radiography performed on construction welds. In the referenced letter, the NRC approved an alternative to radiography for ferritic piping welds during repair and replacement activities. In this request, FPL is requesting approval of a proposed alternative to radiography performed on construction welds in ferritic and austenitic piping. American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel (B&PV) Section III requires that certain ferritic and austenitic circumferential pipe weld joints be examined using radiographic examination techniques to satisfy nondestructive examination requirements. FPL requests approval to use encoded Phased A,rray Ultrasonic Examination Techniques (PAUT) as an alternative to radiographic examination. FPL proposes that the alternative would provide an acceptable level of quality and safety. AD4-7 Florida Power & Light Company tJ~~
700 Universe Boulevard,Juno Beach, FL 33408
L-2019-010 Page 2 of 2 FPL requests approval of the proposed alternative following a one-year review.
The basis for this request is provided in the enclosure to this letter. There are no commitments contained in this submittal.
If you have any questions regarding this submittal, please contact Dale Snyder, Engineering, at 561-904-5489.
Sincerely, William Parks Director, Nuclear Licensing and Regulatory Compliance Florida Power & Light Company
Enclosure:
Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for F erritic and Austenitic
-welds cc: NRC Project Manager - St. Lucie NRC Project Manager - Turkey Point NRC Project Manager - Seabrook NRC Project Manager - Point Beach Regional Administrator - NRC Region 1 Regional Administrator - NRC Region 2 Regional Administrator .: NRC Region 3 NRC Resident Inspector - St. Lucie NRC Resident Inspector - Turkey Point NRC Resident Inspector - Seabrook NRC Resident Inspector - Point Beach
L-2019-010 Enclosure Page 1 of 13 Enclosure to Letter L-2019-010 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic l1,nd Austenitic Welds
L-2019-010 Enclosure Page 2 of 13 RELIEF REQUEST NUMBER FRR-04, REVISION 0 ALTERNATIVE REQUIREMENTS FOR THE USE OF ENCODED PHASED ARRAY ULTRASONIC EXAMINATION TECHNIQUES IN LIEU OF RADIOGRAPHY FOR FERRITIC AND AUSTENITIC WELDS Proposed Alternative In Accordance with 10CFRS0.55a(z)(1)
--Alternative Provides Acceptable Level of Quality and ~afety--
- 1. ASME Code Component(s) Affected American Society of Mechanical Engineers (ASME), Boiler & Pressure Vessel (B&PV) Code, Section XI, ferritic and austenitic piping welds requiring radiography during repair/ replacement activities.
- 2. Applicable Code Edition and Addenda PLANT INTERVAL EDITION START END Point Beach 2007 Edition Nuclear Plant Fifth through 2008 August 1, 2012 July 31, 2022 Units 1 and 2 Addenda St. Lucie 2007 Edition Nuclear Plant Fifth through 2008 February 11, 2018 February 10, 2028 Unit 1 Addenda St. Lucie 2007 Edition Nuclear Plant Fourth through January 20, 2013 January 19, 2023 Unit2 2008 Addenda 2004 Edition Seabrook Station Third August 19, 2010 August 18, 2020 No Addenda Turkey Point 2007 Edition Nuclear Plant Fifth through February 22, 2014 February 21, 2024 Unit3 2008 Addenda Turkey Point 2007 Edition Nuclear Plant Fifth through April 15, 2014 April 14, 2024 Unit 4 2008 Addenda
L-2019-010 Enclosure Page 3 of 13
3. Applicable Code Requirement
The 2004 Edition with No Addenda and the 2007 Edition through the 2008 Addenda of ASME Section XI, paragraph IWA-4221 requires that items used for repair/replacement activities meet the applicable Owner's Requirements and Construction Code requirements when performing repair/ replacement activities. IWA-4520 requires that welded joints made for installation of items be examined in accordance with the Construction Code identified in the Repair/Replacement Plan.
The examination requirements for ASME Section III, Class 1, 2 and 3 circumferential butt welds are contained in the ASME Section III, subarticle NB-5200, NC-5200 and ND-5200 and the acceptance standards for radiographic examination are specified in subarticle NB-5300, NC-5300 and ND-5300.
4. Reason for Request
Replacement of piping is periodically performed in support of the Flow Accelerated Corrosion (FAC) program as well as other repair and replacement activities. The use of encoded Phased Array Ultrasonic Exarpination Techniques (PAUT) in lieu of radiography (RT) to perform the required1examinations of the replaced welds would eliminate the safety risk associated with performing RT, which includes both planned and unplanned radiation exposure to plant workers. PAUT also minimizes the impact on other outage activities normally involved with performing RT, such as limited access to work locations. In addition, encoded PAUT is equivalent or superior to the code-required RT examination for ASME fern.tic and austenitic piping repair/ replacement welds for detecting and sizing critical (planar) flaws, such as cracks and lack of fusion. PAUT provides sizing capabilities for both depth and length dimensions of the flaw, which are required to apply the acceptance criteria of the applicable code case. RT does not provide depth-sizing capabilities.
This proposed alternative is requested to support both planned and unplanned piping repair and replacement activities. The duration of the proposed alternative request is for the remainder of the inservice inspection interval for the plants defined in Section 2 of this request.
- 5. Proposed Alternative and Basis for Use The use of encoded PAUT is proposed in lieu of the code-required RT examination for ASME ferritic and austenitic piping repair/ replacement welds. Similar techniques are being used throughout the nuclear industry for examination of dissimilar metal welds, overlaid welds, as well as other applications including ASME B31.1 piping replacements. This proposed alternative request includes requirements that provide an acceptable level of quality and safety that satisfies the requirements of 10CFRS0.55a(z)(1). The capability of the alternative technique is comparable to the examination methods documented in the ASME Code Sections III, VIII, and IX, and associated code cases (References 8.1, 8.3, 8.6, 8.7, 8.8, 8.9, 8.10, 8.11, 8.12, 8.13, 8.14 and 8.15) using ultrasonic examination techniques for weld acceptance.
L-2019-010 Enclosure Page 4 of 13 The examinations will be performed using personnel and procedures qualified by performance demonstration in accordance with Section 5.1 below.
- 5.1 Proposed Alternative (a) Use of this alternative request is limited to welds made as part of a repair/ replacement activity and is subject to review by the Auth~rized Inspection Agency.
(b) The welds to be examined shall be conditioned such that transducers properly couple with the scanning surface with no more than a 1/32 in. (0.8 tntn) gap between the search unit and the scanning surface.
(c) Ultrasonic examination shall be performed using equipment, procedures, and personnel qualified by performance demonstration as described below.
(d) The examination volume shall include 100% of the weld volume and the weld-to-base metal interface.
(1) Angle beam examination of the complete examination volume for fabrication flaws oriented parallel to the weld joint shall be performed.
(2) Angle beam examination for fabricatioµ flaws oriented transverse to the weld joint shall be performed to the extent practical. Scan restrictions that limit complete coverage shall be documented.
(3) A supplemental straight beam examination shall be performed on the volume of base metal through which the angle beams will travel to locate any reflectors that can limit the ability of the angle beam to examine the weld.
Detected reflectors that may limit the angle beam examination shall be recorded and evaluated for impact on examination coverage. The straight beam examination procedure, or the straight-beam portion of the procedure, is required to be qualified in accordance with ASME Section V, Article 4.
(e) _ All detected flaws from (d)(1) and (d)(2) above shall be considered planar flaws and shall be compared to the preservice acceptance standards for volumetric examination in accordance with Article IWB-3000, IWC-3000, or IWD-3000, as applicable: Analytical evaluation for acceptance of flaws in accordance with IWB-3600, IWC-3600, or IWD-3600 is permitted for flaws that exceed the applicable acceptance standards and are confirmed by surface or volumetric examination to be non-surface-connected.
(£) Flaws exceeding the applicable acceptance standards without an analytical evaluation for acceptance shall be reduced to an acceptable size or removed and repaired, and the location of the repair shall be reexamined using the same ultrasonic examination procedure that detected the flaw.
(g) The ultrasonic examination shall be performed using encoded PAUT technole>gy
L-2019-010 Enclosure Page 5 of 13 that produces an electronic record of the ultrasonic responses indexed to the probe position, permitting off-line analysis of images built from the combined data.
Where component configuration does not allow for effective examination for transverse flaws (e.g., pipe-to-valve, tapered weld transition, weld shrinkage), use of non-encoded UT technology may be used for transverse flaws. The basis for the non-encoded examination shall be documented.
(h) A written ultrasonic examination procedure qualified by performance demonstration shall be used. The qualification shall be applicable to the scope of the procedure, e.g., flaw detection or sizing (length or through-wall height),
encoded or non-encoded, single or dual-side access. The procedure shall:
(1) Contain a statement of scope that specifically defines the limits of procedure applicability (e.g., minimum and maximum thickness, minimum and maximum. diameter, scanning access).
(2) Specify which parameters are considered essential variables, and a single value, a range of values or criteria for selecting each of the essential variables.
(3) List the examination equipment, including manufacturer and model or series.
(4) Define the scanning requirements, such as beam angles, scan patterns, beam direction, maximum scan speed, extent of scanning, and access.
(5) Contain a description of the calibration method (i.e., actions required to ensure that the sensitivity and accuracy of the signal amplitude and time outputs of the examination system, whether displayed, recorded, or automatically processed, are repeated from examination *to examination)
(6) Describe the method and criteria for discrimination of indications (e.g.,
geometric indications versus indications of flaws and surface versus subsurface indications).
1 (7) Describe the surface preparation requirements.
(i)
- Performance demonstration specimens shall conform to the following requirements:
(1) The specimens shall be fabricated from ferritic or austenitic material, similar to the material b~ing examined. Ferritic specimens shall be fabricated with the same inside si;u:face cladding process, if applicable, with the following exceptions:
(i) Demonstration with shielded metal arc weld (SMAW) single-wire cladding is transferable to multiple-wire or strip-cla,d processes.
L-2019-010 Enclosure Page 6 of 13 (ii) Demonstration with a multiple-wire or strip-clad process is considered equivalent but is not transferable to SMAW type cladding processes.
(2) The demonstration specimens shall contain a weld representative of the joint to be ultrasonically examined, including the same welding processes.
(3) The demonstration set shall include specimens not thicker than 0.1 in. (2.5 mm) more than the minimum thickness, nor t:hiruier than 0.50 in. (13 mm) less than the maximum thickness for which the examination procedure is applicable. The demonstration set shall include the minimum, within 1/2 of the nominal outside diameter (OD), and maximum pipe diameters for which the examination procedure is applicable. If the procedure is applicable to piping of 24 in. (610 mm) OD or larger, the specimen set must include at least one specimen 24 in. (610 mm) OD or larger but need not include the maximum diameter.
(4) The demonstration specimen scanning and weld surfaces shall be representative of the surfaces to be examined.
(5) The demonstration specimen set shall include geometric conditions that require discrimination from flaws (e.g., counterbore, weld root conditions, weld crowns) and limited scanning surface conditions for single-side access, when applicable.
(6) The demonstration specimens shall include both planar and volumetric fabrication flaws (e.g., lack of fusion, crack, incomplete penetration, slag inclusions) representative of the welding process or processes of the welds to be examined. The flaws shall be distributed throughout the examination volume.
(7) Specimens shall be divided into flawed and unflawed grading units as follows:
(i) Flawed grading units shall be the actual flaw length, plus a minimum of 0.25 in. (6 mm) on each end of the flaw. Unflawed grading units shall be at least 1 in. (25 mm).
(ii) The number of unflawed grading units shall be at least 1-1/2 times the number of flawed grading units.
(8) Demonstration specimen set flaw distribution shall be as follows:
(i) For thickness greater than 0.50 in. (13 mm); at least 20% of the flaws shall be distributed in the outer third of the specimen wall thickness, at least 20% of the flaws shall be distributed in the middle third of the specimen wall thickness, and at least 40% of the flaws shall be
L-2019-010 Enclosure Page 7 of 13 distributed iri the inner third of the specimen wall thickness. For -
thickness 0.50 in. (13mm) and less, at least 20% of the flaws shall be distributed in the outer half of the specimen wall thickness, an.cl at least 40% of the flaws shall be distributed in the inner half of the specimen wall thickness.
(ii) At least 30% of the flaws shall be classified as surface planar flaws in accordance with IWA-3310. At least 40% of the flaws shall be classified as subsurface planar flaws in accordance with IWA-3320.
(iii) At least 50% of the flaws shall be planar flaws, such as lack of fusion, incomplete penetration, or cracks. At least 20% of the flaws shall be volumetric flaws, such as slag inclusions.
(iv) The flaw through-wall heights shall be based on the applicable acceptance standards for volumetric examination in accordance with IWB-3400, IWC-3400, or Article IWD-3000, as applicable. At least 30% of the flaws shall be classified as acceptable planar flaws, with the smallest flaws being at least 50% of the maxiplum allowable size based on the applicable a/ t aspect ratio for the flaw. Additional smaller flaws may be included in the specimens to assist in establishing a detection threshold, but shall not be counted as a missed detection if not detected. At least 30% of the flaws shall be classified as unacceptable in accordance with the applicable acceptance standards. Welding
- fabrication flaws are typically confined to a height of a single weld pass.
Flaw through-wall height distribution shall range f:t;om approximately one to four weld pass thicknesses, based on the welding process used.
(v) If applicable, at least two flaws, but no more than 30% of the flaws, shall be oriented perpendicular to the weld fusion line, and the remaining flaws shall be circumferentially-oriented.
(vi) For demonstration of single-side-acce~s capabilities, at least 30% of the flaws shall be located on the far side of the weld centerline and at least 30% of the planar flaws shall be located on the near side of the weld centerline. The remaining flaws shall be distributed on either side of the weld.
G) Ultrasonic examination procedures shall be qualified by performance demonstration in accordance with the following requirements.
(1) The procedure shall be demonstrated using either a blind or a non-blind demonstration.
(2) The non-blind performance demonstration is used to assist in optimizing the examination procedure. When applying the non-blind performance
L-2019-010 Enclosure Page 8 of 13 demonstration process, personnel have access to limited knowledge of specimen flaw information during the demonstration process. The non-blind performance demonstration process consists of an initial demonstration without any flaw information, an assessment of the results, and feedback of the performance provided to the qualifying candidate. After an assessment of the initial demonstration results, limited flaw information may be shared with the candidate, as part of the feedback process, to assist in enhancing the examination procedure to improve the procedure performance. To maintain the integrity of the specimens for blind personnel demonstrations, only-generalities of the flaw information may be provided to the candidate.
Procedure modifications or enhancements made to the procedure, based on the feedback process, shall be applied to all applicable specimens, based on the scope of the changes.
(3) Objective evidence of a flaw's detection, length, and through-wall height sizing, in accordance with the procedure requirements, shall be provided to the organization administering the performance demonstration.
(4) The procedure demonstration specimen set shall be representative of the procedure scope and limitations (e.g., thickness range, diameter range, material, access, surface condition).
(5) The demonstration set shall include specimens to represent the minimum and maximum diameter and thickness covered by the procedure. If the procedure spans a range of diameters and thicknesses, additional specimens shall be included in the set to demonstrate the effectiveness of the procedure throughout the entire range.
(6) The procedure demonstration specimen s~t shall include at least 30 flaws and shall meet the requirements of (i) above.
(7) Procedure performance demonstration acceptance criteria (i) To be qualified for flaw detection, all flaws in the demonstration set that are not less than 50% of the maximum allowable size, based on the applicable a/ t aspect ratio for the flaw, shall be detected. In addition, when performing blind procedure demonstrations, no more than 20% of the non-flawed grading units may contain a false call.
Any non-flaw condition (e.g., geometry) reported as a flaw shall be considered a false call.
(ii) To be qualified for flaw length sizing, the root mean square (RMS) error of the flaw lengths estimated by ultrasonic, as compared with the true lengths, shall not exceed 0.25 in. (6 mm) for NPS 6 (DN150) and smaller, and 0.75 in. (18 mm) for larger than NPS 6 (DN150).
L-2019-010 Enclosure Page 9 of 13 (iii) To be qualified for flaw through-wall height sizing, the RMS error of the. flaw through-wall heights estimated by ultrasonic, as compared with the true tju:ough-wall heights, shall not exceed 0.125 in. (3 mm).
(iv) RMS error shall be calculated as follows:
where lnj *= me~s1,1red,. flaw size.
ti = true flaw siZe n = nli.tllbet of .flaws measur~d (8) Essential variables may be changed during successive personnel performance demonstrations. Each examiner need not demonstrate qualification over the entire range of every essential variable.
(9) Expansion of a procedure, demonstrated in accordance with G), to include an additional material type (i.e. ferritic or austenitic) shall meet the following:
(i) The procedure expansion may be performed during successive personnel perf~rmance demonstrations, performed in accordance with (k)(1), with the *exception that all flaws must be detected.
(ii) The examination technique is the same, e.g. wave modes, angles, V-path, access. Any changes to the examination technique shall I be performed in accordance with G)-
(iii) The demonstration set must include the minimum and maximum diameter and thickness range of the new material being demonstrated.
. (iv) Personnel using the expanded procedure shall demonstrate the m
additional material type accordance with (k).
(k) Ultrasonic examination personnel shall be qualified in accordance with IWA- 2300.
In addition, examination personnel shall demonstrate their capability to detect and size flaws by performance demonstration, using the qualified procedure, in accordance with the following requirements:
(1) The personnel performance demonstration shall be conducted in a blind fashion (flaw information is not provided).
L-2019-010 Enclosure Page 10 of 13 (2) The demonstration specimen set shall contain at least 10 flaws and shall meet the flaw distribution requirements of (i) (8) above, with the exception of (i)(8)(v). When applicable, at least one flaw, but no more than 20% of the flaws, shall be oriented perpendicular to the weld fusion line, and the remaining flaws shall be circumferentially oriented.
(3) Personnel performance demonstration acceptance criteria:
(i) To be qualified for fl~w detection, at least 80% of the flaws in the demonstration set shall be detected and no more than 20% of the grading units shall contain a false-call. Any non-flaw condition (e.g.,
geometry) reported as a flaw shall be considered a false call.
(ii) To be qualified for flaw length sizing, the RMS error of the flaw lengths estimated by ultrasonic, as compared with the true lengths, shall not exceed 0.25 in. (6 mm) for NPS 6 (DN150) and smaller, and 0.75 in.
(18 mm) for larger than NPS 6 (DN150).
(iii) To be qualified for flaw through-wall height sizing, the RMS error of the flaw through-wall heights estimated by ultrasonic, as compared with the true through-wall heights, shall not exceed 0.125 in. (3 mm). *
(I) NextEra Energy is responsible for reviewing the procedure and demonstration results to validate that the ranges of the essential variables in the procedure were included in the demonstration.
(m) Documentation of the qualifications of procedures and personnel shall be maintained by NextEra Energy. Documentation shall include identification of personnel, procedures, equipment, and specimens used during qualification, and results of the performance demonstration.
- 5.2 Basis for Use The basis for this proposed alternative is that encoded PAUT is equivalent or superior to RT for detecting and sizing critical (planar) flaws. In this regard, the basis for the proposed alternative was developed from numerous codes, code cases, associated industry experience, articles, and the results of RT and encoded PAUT examinations.
The examination procedure and personnel performing examinations are qualified using representative piping conditions and flaws that demonstrate the ability to detect and size flaws that are both acceptable and unacceptable to the defined acceptance standards.
The demonstrated ability of the examination procedure and personnel to appropriately detect and size flaws provides an acceptable level of quality and safety alternative as allowed by 10CFR50.55a(z)(1).
- 6. Duration of Proposed Alternative This alternative request will be applied for the remainder of the inservice inspection intervals for the plants defined in Section 2 of this relief request.
- 7. Precedents 7.1 Dominion Request for Relief No. RR-04-27 and IR-3-38, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination, dated February 28, 2018 (ML18066A522. NRC approval dated September 17, 2018 (ML18252A003).
7.2 NextEra Energy for R~liefNo. FRR-01, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Techniques, dated July 24, 2017 (ML17208A058). NRC approval dated April 25, 2018 (ML18106B121).
7.3 Oconee Request for Relief No. 2006-0N-001 dated,June 20, 2006; requested relief on butt welds between the Pressurizer Level and Sample Tap nozzles and their respective Safe Ends. The reason for the request was based on the difficulty to perform the code required radiography. The alternative was to perform ultrasonic examination per similar requirements to Code Case N-659-0. (ML061210495).
7.4 Wolf Creek 10 CPR 50.55a Request ET 06-0029, dated September 1, 2006; requested relief on main steam and feedwater piping welds being replaced due to flow assisted corrosion. The reason for the request was based on the acceptability of the proposed ultrasonic examination alternative process, radiation exposure reduction, outage costs and duration, and radiography exposure risk. (ML062500093).
7.5 Palo Verde Nuclear Generating Station Relief Request 48, dated August 1, 2012 ML12229A046). NRC, approval dated April 12, 2013 (ML13091A177).
7.6 Millstone Power Station Unit 2 Alternative Request RR-04-16, dated August 1, 2013(.ML13220A019). NRC approval dated April 4, 2014(.ML14091A973).
7.7 Millstone Power Station Unit 2 Alternative Request RR-04-21, dated October 6, 2014 (ML14283A128). NRC approval dated September 21, 2015 (ML15257A005).
7.8 Millstone Power Station Unit 3 Alternative Request IR-3-25, dated October 6, 2014(.ML14283A128). NRC approval dated September 21, 2015 (ML15257A005).
7.9 Millstone Power Station Unit 2 Alternative Request RR-04-023, dated April 11, 2016 (ML16106A105). NRC approval dated January 23, 2017 (ML16363A089).
7.10 Millstone Power Station Unit 3 Alternative Request IR-3-28, dated April 11, 2016(.ML16106A105). NRC approval dated January 23, 2017 (ML16363A089).
7.11 Millstone Power Station, Units 2 and 3; North Anna Power Station, Units 1 and 2; and Surry Power Station, Units 1 and 2; Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination, dated June 29, 2017 (ML17188A379). NRC approval dated January 24, 2018 (ML18019A195).
L-2019-010 Enclosure Page 12 of 13
- 8. References 8.1 ASME Section III Code Case N-659-2, "Use of Ultrasonic Examination in Lieu of Radiography for Weld Examination Section III, Divisions 1 and 3," dated June 9, 2008.
8.2 Pacific Northwest National Laboratory Report PNNL-19086, "Replacement of Radiography with Ultrasonics for the Nondestructive Inspection of Welds - Evaluation pf Technical Gaps -An Interim Report," dated April 2010.
8.3 ASME B31.1, Case 168, "Use of Ultrasonic Examination in Lieu of Radiography for B31.1 Application," dated June 1997.
8.4 ASME Sections III an~ XI, 2004 Edition, No Addenda.
8.5 ASME Section III and XI, 2007 Edition through the 2008 Addenda.
8.6 ASME Section III, Code Case N-818, "Use of Analytical Evaluation approach for Acceptance of Full Penetration Butt Welds in Lieu of Weld Repair," dated December 6, 2011.
8.7 ASME Code Case 2235-9, 2005; "Use of Ultrasonic Examination in Lieu of Radiography Section I, Section VIII, Divisions 1 and 2, and Section XII," dated October 11, 2005.
8.8 Journal of Pressure Vessel Technology, "Technical Basis for ASME Section VIII Code Case 2235 on Ultrasonic Examination of Welds in Lieu of Radiography;" Rana, Hedden, Cowfer and Boyce, Volume 123, dated August 2001.
8.9 ASME Code Case 2326, "Ultrasonic Examination in Lieu of Radiographic Examination for Welder Qualification Test Coupons Section IX," dated January 20, 2000.
8.10 ASME Code Case 2541, "Use of Manual Phased Array Ultrasonic Examination Section V," dated January 19, 2006.
8.11 ASME Section III, Code Case N-818, "Use of Analytical Evaluation approach for Acceptance of Full Penetration Butt Welds in Lieu of Weld Repair," dated December 6, 2011.
8.12 ASME Code Case 2599, "Use of Linear Phased Array E-Scan Ultrasonic Examination Per Article 4 Section V," dated January 29, 2008.
8.13 ASME Code Case 2600, "Use of Linear Phased Array S-Scan Ultrasonic Examination Per Article 4 Section V," dated January 29, 2008.
8~14 ASME Section XI, Code Case N-713, "Ultrasonic Examination in Lieu of Radiography,"
dated November 10, 2008.
L-2019-010 Enclosure Page 13 of 13 8.15 ASME Section XI, Code Case N-831, "Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic Pipe," dated October 20, 2016.
8.16 US NRC, NUREG/CR-7204, "Applying Ultrasonic Testing in Lieu of Radiography for Volumetric Examination of Carbon Steel Piping" (ML15253A674).
8.17 Technical Basis for Substituting Ultrasonic Testing for Radiographic Testing for New, Repaired, and Replacement Welds for ASME Section XI, Division 1, Stainless Steel Piping. EPRI, Palo Alto, CA: 2017. 3002010297.