Letter Sequence Approval |
---|
EPID:L-2019-LLR-0119, Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period (Approved, Closed) |
|
|
|
---|
Category:Code Relief or Alternative
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22242A1602022-08-30030 August 2022 Hardship Relief Request Pilot-Operated Relief Valve Acceptance Review Results ML21306A1592021-11-16016 November 2021 Request to Use Provisions of Later Edition and Addenda of the ASME Code, Section XI (EPID; L-2021-LLR-0048) ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20230A2052020-08-21021 August 2020 Relief Request RA-20-0031, Delay to Update the Code of Record for Inservice Inspection ML19217A3242019-08-14014 August 2019 Relief Request MC-SRV-NC-03, Alternate Testing for Pressurizer Power Operated Relief Valve Block Valve 2NC-35B RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-18-0180, Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 22018-11-12012 November 2018 Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17034A3622017-02-22022 February 2017 Mcguire Nuclear Station, Unit 1 - Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping Relief ML16358A6962017-01-17017 January 2017 Proposed Relief Request MC-SRV-NC-02, Alternate Testing for Pressurizer Power Operated Relief Valve (Porv) Block Valve 2NC-31B ML16266A0262016-10-18018 October 2016 Proposed Relief Request Serial No. 16-MN-003 for Alternate Repair of Nuclear Service Water Piping ML16294A2542016-10-13013 October 2016 Response to Request for Additional Information Regarding Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping ML16225A6542016-08-11011 August 2016 Email - McGuire Unit No. 1: Acceptance REVIEW- Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping. MNS-16-062, Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping2016-08-10010 August 2016 Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping ML16210A0382016-07-28028 July 2016 Draft Relief Request Serial No. 16-MN-003 MNS-16-053, Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping2016-06-23023 June 2016 Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping ML16152A6012016-06-0808 June 2016 Withdrawal of Relief Request ML15232A5432015-08-27027 August 2015 Proposed Relief Request 15-MN-001 ML14188C3482014-07-14014 July 2014 Proposed Relief Request 13-MN-002 ML14013A2422014-01-17017 January 2014 Proposed Relief Request Nos. MC-SRP-KC-01 and MC-SRP-ND-01 (TAC Nos. MF1164, MF1165, MF1166 and MF1167 ML13294A6092013-11-0808 November 2013 Proposed Relief Request 12-MN-004 (TAC Nos. MF0508, MF0514, and MF0515) ML13010A5542013-01-14014 January 2013 Proposed Relief Request 12-MN-002 ML12355A1492012-11-29029 November 2012 Relief Request Serial # 12-MN-004 Limited Weld Examinations ML12264A3382012-09-24024 September 2012 Correction Letter for Approval Letter and Safety Evaluation for Relief Request 11-MN-002 Regarding the Extension of the Inservice Inspection Interval for Reactor Vessel Category B-A and B-D Welds ML12123A1122012-05-0909 May 2012 Request for Relief 12-MN-001, Relief Request for a Alternative Depth Sizing Criteria ML11160A1442011-06-23023 June 2011 Relief 10-MN-002, Extension of Volumetric Inspection of Steam Generator Primary Manway Studs for One Operating Cycle Beyond the Third 10-Year Inservice Inspection Interval End Date ML1015804222010-06-14014 June 2010 Relief 09-MN-005 for Alternative Leakage Testing for Various American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Class 1 Piping and Components During the Third 10-Year Inservice ML1006200182010-03-0404 March 2010 Relief 09-MN-007 for Reactor Vessel Core Flood Nozzle Weld Examinations During the Third 10-Year Inservice Inspection ML0911400662009-05-13013 May 2009 Request for Relief 08-MN-003 for Reactor Vessel Hot Leg Nozzle to Safe End and Safe-End to Pipe Welds Examinations, TAC MD9614 ML0921706582009-05-0404 May 2009 Submittal of Relief Request Serial No. 09-MN-002 ML0814904712008-05-16016 May 2008 Relief Request 08-MN-001 ML0715604162007-06-0808 June 2007 Withdrawal of Relief Requests Associated with Pump Vibration (MD3253 Through MD3290) ML0712102492007-04-19019 April 2007 Relief Request 07-GO-0001. Proposed Alternative Approach Supports Application of Full Structural Weld Overlays on Various Pressurizer Nozzle-to-Safe End Welds ML0626202612006-09-11011 September 2006 Relief Request 06-GO-001 Request for Additional Information ML0615303872006-08-16016 August 2006 Request for Relief 05-MN-01, for Third 10-Year Interval Inservice Inspection Program Plan ML0634903992006-07-27027 July 2006 Relief Request 06-GO-001 ML0524502572005-09-0606 September 2005 Relief Requests for Third 10-Year Pump & Valve Inservice Testing Program ML0514601792005-05-23023 May 2005 Request for Relief, ISI Request for 04-MN-02, 04-MN-03 and 04-MN-04 ML0506105662005-03-18018 March 2005 Review of RR-03-05, Pressurizer Support Skirt Welds ML0506704672005-02-24024 February 2005 Inservice Testing Program Relief Request MC-SRP-NS-01, Request for Additional Information (RAI) ML0434400722004-12-0202 December 2004 Supplement to Relief Request No. 01-003 ML0430602312004-11-17017 November 2004 Relief Request, Use of a Later Edition of the ASME Section XI Code for the Remainder of the Third 10-year Inspection Interval RR-03-001. TAC No MC2767 2023-09-25
[Table view] Category:Letter
MONTHYEARIR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22347A1512022-12-13013 December 2022 William B. Mcguire Nuclear Station Notification of Licensed Operator Initial Examination 05000369/2023301 and 05000370/2023301 ML22340A6662022-12-0808 December 2022 Summary of November 30, 2022, Public Meeting with Duke Energy Carolinas, LLC for McGuire Nuclear Station, Units 1 & 2 Proposed LAR to Adopt TSTF-505, Rev. 2 and 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems ML22290A1012022-11-29029 November 2022 Issuance of Amendment Nos. 326 and 305, Regarding Changes to Technical Specification 3.4.3, Reactor Coolant System Pressure Temperature Limits ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000369/20220032022-10-27027 October 2022 Integrated Inspection Report 05000369/2022003 and 05000370/2022003 IR 05000369/20220112022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000369/2022011 and 05000370/2022011 ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition IR 07200038/20220012022-09-12012 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200038/2022001 ML22230B6132022-09-0101 September 2022 Review of the Draft Environmental Assessment and Finding of No Significant Impact for Brunswick Steam Electric Plant and McGuire Nuclear Station Independent Spent Fuel Storage Installations Decommissioning Funding Plans IR 05000369/20220052022-08-29029 August 2022 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 NRC Inspection Report 05000369/2022005 and 05000370/2022005 IR 05000369/20220022022-07-26026 July 2022 Integrated Inspection Report 05000369/2022002 and 05000370/2022002 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3112022-05-16016 May 2022 Letter Issuing Exemption to McGuire IR 05000369/20224012022-05-12012 May 2022 Cyber Security Inspection Report 05000369/2022401 and 05000370/2022401 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22290A1012022-11-29029 November 2022 Issuance of Amendment Nos. 326 and 305, Regarding Changes to Technical Specification 3.4.3, Reactor Coolant System Pressure Temperature Limits ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 ML21306A1592021-11-16016 November 2021 Request to Use Provisions of Later Edition and Addenda of the ASME Code, Section XI (EPID; L-2021-LLR-0048) ML21155A2132021-08-26026 August 2021 Plant ML21131A0262021-06-23023 June 2021 Issuance of Amendments to Change Technical Specification 3.8.1, to Reduce Emergency Diesel Generator Maximum Voltage ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20230A2052020-08-21021 August 2020 Relief Request RA-20-0031, Delay to Update the Code of Record for Inservice Inspection ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19217A3242019-08-14014 August 2019 Relief Request MC-SRV-NC-03, Alternate Testing for Pressurizer Power Operated Relief Valve Block Valve 2NC-35B ML19184A5852019-08-0808 August 2019 Issuance of Amendment Nos. 316 and 295 to Correct Editorial Error in Technical Specification 3.0 and Remove Expired Footnotes from TS 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11, 3.8.1, and 3.8.4 ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19126A0302019-06-28028 June 2019 Issuance of Amendments to Technical Specification 3.8.1, AC Sources-Operating ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML19091A1942019-04-17017 April 2019 Safety Evaluation Input for License Amendment Request to Revise the Technical Specifications 3.8.1, AC Sources - Operating. ML18355A6102019-01-25025 January 2019 Issuance of Amendments to Revise the Licensing Basis for Protection from Tornado Generated Missiles ML18318A3582019-01-16016 January 2019 Issuance of Amendment Nos. 311 and 290 to Correct Non-Conservative Technical Specification 3.4.11, Pressurizer Power Operated Relief Valves Porvs) ML18277A3222018-11-19019 November 2018 Issuance of Amendments 310 and 289 to Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18009A8422018-01-31031 January 2018 Issuance of Amendments to Extend the Containment Type a Leak Rate Test Frequency to 15 Years and Type C Leak Rate Test Frequency to 75 Months (CAC Nos. MF9020 and MF9021; EPID L-2016-LLA-0032) ML17297A9172018-01-0505 January 2018 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-197-A, Revision 2 (CAC Nos. MF9110 and MF9111; EPID L-2017-LLA-0161) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17277A3132017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-340-A, Revision 3 (CAC Nos. MF9117 and MF9118; EPID L-2017-LLA-0169) ML17269A1982017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 ML17271A0342017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0 (CAC Nos. MF9101 - MF9107) ML17261B2182017-10-25025 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-315-A Revision 0 (CAC Nos. MF9112 and MF9113; EPID L-2017-LLA-0171) ML17269A0552017-10-25025 October 2017 McGuire, Units 1 and 2 - Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-283-A, Revision 3 (CAC NOS. MF9098 and MF9099) ML17244A1022017-09-25025 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF 285-A, Revision 1 ML17240A3542017-09-18018 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-269-A, Revision 2 ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML17060A4812017-03-27027 March 2017 Issuance of Amendments Regarding Change to Technical Specification 3.6.14, & Divider Barrier Integrity; ML17003A0192017-03-0808 March 2017 Issuance of Amendments Regarding Change to Technical Specifications (Ts), Removal of Superseded TS Requirements 2023-09-25
[Table view] |
Text
August 21, 2020 Mr. Thomas D. Ray Site Vice President Duke Energy Carolinas, LLC McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
MCGUIRE NUCLEAR STATION, UNIT 1 - RELIEF REQUEST RA-20-0031, DELAY TO UPDATE THE CODE OF RECORD FOR INSERVICE INSPECTION (EPID L-2019-LLR-0119)
Dear Mr. Ray:
By letter dated December 19, 2019, as superseded by letter dated January 23, 2020, and supplemented by letter dated April 2, 2020, Duke Energy Carolinas, LLC (Duke Energy, the licensee) submitted relief request RA-20-0031 to the U.S. Nuclear Regulatory Commission (NRC) requesting use of an alternative to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, at McGuire Nuclear Station (McGuire), Unit 1.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1), the licensee requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety. The licensee requested to continue to use the 2007 Edition with 2008 Addenda of the ASME Code,Section XI for Class 1, 2, and 3 components and associated supports during the first inspection period of the fifth 10-year inservice inspection (ISI) interval on the basis that the alternative provides an acceptable level of quality and safety.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that Duke Energy has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC staff authorizes the use of relief request RA-20-0031 for the Class 1, 2, and 3 components and associated supports at McGuire, Unit 1, for the first inspection period of the fifth 10-year ISI interval, which is scheduled to start on December 1, 2021.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
T. Ray If you have any questions, please contact the Project Manager, Ed Miller at 301-415-2481 or via e-mail at Ed.Miller@nrc.gov.
Sincerely, Digitally signed by Shawn A. Shawn A. Williams Date: 2020.08.21 Williams 11:23:48 -04'00' Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-369
Enclosure:
Safety Evaluation cc: ListServ
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST RA-20-0031 REGARDING DELAY TO UPDATE THE CODE OF RECORD FOR INSERVICE INSPECTION DUKE ENERGY CAROLINAS MCGUIRE NUCLEAR STATION, UNIT 1 DOCKET NO. 50-369
1.0 INTRODUCTION
By letter dated December 19, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession ML19353C619), as superseded by letter dated January 23, 2020 (ADAMS Accession No. ML20023A272), and supplemented by letter dated April 2, 2020 (ADAMS Accession No. ML20097A026), Duke Energy Carolinas (Duke Energy, the licensee) requested an alternative to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI. In its letter dated January 23, 2020 (RA-20-0031), the licensee proposed to delay updating the inservice inspection (ISI) program code of record for the McGuire Nuclear Station (McGuire), Unit 1, to the latest edition and addenda of the ASME Code,Section XI, that is incorporated by reference into Title 10 of the Code of Federal Regulations (10 CFR) 50.55a until the end of the first inspection period of the fifth 10-year ISI interval.
Specifically, pursuant to 10 CFR 50.55a(z)(1), the licensee proposed to continue to use the 2007 Edition with 2008 Addenda of the ASME Code,Section XI, for Class 1, 2 and 3 components and associated component supports during the first inspection period of the fifth 10-year ISI interval on the basis that the alternative provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(g)(4)(ii), Applicable ISI Code: Successive 120-month interval, states, in part, that Inservice examination of components and system pressure tests conducted during successive 120-month inspection intervals must comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in paragraph (a) of this section 18 months before the start of the 120-month inspection interval (or the optional ASME Code Cases listed in NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1 (ADAMS Accession No. ML19128A244), when Enclosure
using ASME Code,Section XI, or NRC Regulatory Guide 1.192, when using the ASME OM Code, as incorporated by reference in paragraphs (a)(3)(ii) and (iii) of this section), subject to the conditions listed in paragraph (b) of this section. However, a licensee whose ISI interval commences during the 12 through 18-month period after June 3, 2020, may delay the update of their Appendix VIII program by up to 18 months after June 3, 2020. Alternatively, licensees may, at any time in their 120-month ISI interval, elect to use the Appendix VIII in the latest edition and addenda of the ASME Code incorporated by reference in paragraph (a) of this section, subject to any applicable conditions listed in paragraph (b) of this section. Licensees using this option must also use the same edition and addenda of Appendix I, Subarticle I-3200, as Appendix VIII, including any applicable conditions listed in paragraph (b) of this section.
Pursuant to 10 CFR 50.55a(z), alternatives to the requirements of paragraph (b) through (h) of Section 50.55a or portions thereof may be used when authorized by the Director, Office of Nuclear Reactor Regulation. A proposed alternative must be submitted and authorized prior to implementation. The licensee must demonstrate that: (1) the proposed alternative would provide an acceptable level of quality and safety; or (2) compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the NRC to authorize the alternative request by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Background
By letter dated August 30, 2010 (ADAMS Accession No. ML102510186), the NRC approved a similar relief request, 10-MN-001, on March 30, 2011 (ADAMS Accession No. ML110550770),
for McGuire, Unit 1, authorizing the licensee to delay updating the Unit 1 ISI program code of record to the later edition and addenda of the ASME Code,Section XI, that is incorporated by reference into 10 CFR 50.55a until the end of the first inspection period of the fourth 10-year ISI interval. The fourth 10-year ISI interval started on December 1, 2011, and is scheduled to end on November 30, 2021.
3.2 Component Affected ASME Code Class 1, 2, and 3 components and associated component supports are affected.
3.3 Applicable Code Edition and Addenda The code of record for the fourth 10-year ISI interval of McGuire, Unit 1, is the 2007 Edition with 2008 Addenda of the ASME Code. The licensee requested to use the same code of record (i.e., 2007 Edition with 2008 Addenda) during the first inspection period of the fifth 10-year ISI interval.
3.4 Regulatory Requirement Pursuant to 10 CFR 50.55a(g)(4)(ii), the ISI program code of record shall be updated to the latest edition and addenda of the ASME Code,Section XI, incorporated by reference in 10CFR 50.55a 12 months before start of the 120-month ISI interval.
3.5 Duration of Relief Request
The licensee submitted Relief Request RA-20-0031 for the first inspection period of the fifth 10-year ISI interval at McGuire, Unit 1. The fifth 10-year ISI interval is scheduled to commence on December 1, 2021, and is scheduled to end on November 30, 2031.
3.6 Proposed Alternative The licensee proposed to continue to use the 2007 Edition with 2008 Addenda of the ASME Code,Section XI, during its first inspection period of the fifth 10-year ISI interval, and to meet all applicable requirements of 10 CFR 50.55a.
As part of relief request RA-20-0031, the licensee proposed to continue to use certain relief requests approved previously by the NRC for the fourth 10-year ISI interval of McGuire, Unit 1, during the first inspection period of the fifth 10-year ISI interval. The approved relief requests include:
NRC safety evaluation dated July 14, 2014 (ADAMS Accession No. ML14188C348), for Relief Request 13-MN-002 (request dated August 13, 2013, ADAMS Accession No. ML13234A069).
NRC safety evaluation dated December 26, 2017 (ADAMS Accession No. ML17331A086), for Relief Request 17-GO-001 (request dated March 29, 2017, ADAMS Accession No. ML17088A846).
NRC safety evaluation dated June 20, 2019 (ADAMS Accession No. ML19128A326), for Relief Request 18-GO-001 (request dated September 6, 2018, ADAMS Accession No. ML18249A008).
NRC safety evaluation dated September 17, 2019 (ADAMS Accession No. ML19254A620), for Relief Request 19-GO-001 (request dated May 20, 2019, ADAMS Accession No. ML19143A072).
3.7 Basis for Use of Alternative The licensee stated that Relief Request RA-20-0031 would facilitate updating the McGuire ISI program code of record to the latest edition and addenda of the ASME Code that is incorporated by reference in 10 CFR 50.55a at the same date. The ASME Code,Section XI, activities (e.g.,
ISI, repair/replacement, pressure testing, and nondestructive examination) for McGuire, Units 1 and 2, are standardized and administered by a centralized ISI organization at Duke Energy.
Use of a common ASME code of record at both units simplifies program administration, requires fewer programs and procedures than would otherwise be needed to implement requirements of different editions and addenda of the ASME Code. Standardizing these programs using a common code of record also minimizes the risk that errors will occur during program development and implementation.
The licensee stated that the continued use of the previous NRC-approved relief requests listed above during the first inspection period of the fifth 10-year ISI interval provide an acceptable level of quality and safety because:
ASME Code Case N-716-1, Alternative Piping Classification and Examination Requirements,Section XI, superseded ASME Code Case N-716, and has been
incorporated by reference into 10 CFR 50.55a via inclusion in RG 1.147, Revision 19, without conditions. The use of Relief Request 13-MN-002 during the first inspection period of the fifth 10-year ISI interval will continue to provide an acceptable level of quality and safety.
ASME Code Case N-831, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic Pipe Section XI, has been incorporated by reference into 10 CFR 50.55a via inclusion in RG 1.147, Revision 19, with a condition that its use is prohibited in new reactor construction. The use of Relief Request 19-GO-001 during the first inspection period of the fifth 10-year ISI interval will continue to provide an acceptable level of quality and safety.
The stress and flaw tolerance analyses documented in Electric Power Research Institute (EPRI) Technical Report 3002007626, Nondestructive Evaluation: Reactor Pressure Vessel Threads in Flange Examination Requirements, are demonstrated to be bounding for the McGuire, Unit 1, RPV flange, thus the inspection of threads in the flange could safely be eliminated. The use of Relief Request 17-GO-001 during the first inspection period of the fifth 10-year ISI interval will continue to provide an acceptable level of quality and safety.
ASME Code Cases N-695-1, Qualification Requirements for Dissimilar Metal Piping Welds,Section XI, and N-696-1, Qualification Requirements for Mandatory Appendix VIII Piping Examinations Conducted from the Inside Surface,Section XI, have been incorporated by reference into 10 CFR 50.55a via inclusion in RG 1.147, Revision 19, without conditions. The use of Relief Request 18-GO-001 during the first inspection period of the fifth 10-year ISI interval will continue to provide an acceptable level of quality and safety.
3.8 NRC Staff Evaluation The NRC staff evaluated Relief Request RA-20-0031 pursuant to 10 CFR 50.55a(z)(1). The NRC staffs evaluation focused on whether (1) there exists major difference between the licensees proposed edition/addenda and the latest editions/addenda of the ASME Code incorporated by reference in Section 50.55a(a); and (2) applicable conditions in Section 50.55a will be met. The NRC staff finds that if these two criteria are met, the proposed alternative provides an acceptable level of quality and safety.
In evaluating the licensees proposed alternative, the NRC staff confirmed that:
The 2017 Edition of the ASME Code,Section XI, has been incorporated by reference in 10 CFR 50.55a. Use of the 2007 Edition with 2008 Addenda as opposed to the 2017 Edition during the first inspection period of the fifth 10-year ISI interval does not affect the integrity of the components because there are no major differences.
The licensee has acknowledged that it will comply with all applicable provisions in 10 CFR 50.55a.
The licensee identified Relief Requests 13-MN-002, 17-GO-001, 18-GO-001, and 19-GO-001 that were initially approved by the NRC for the fourth 10-year ISI interval of McGuire, Unit 1, for use in the first inspection period of the fifth 10-year ISI interval. The
NRC staffs evaluation of each relief request for use in the proposed inspection period is as follows:
o The NRC staff finds that the continued use of Relief Request 13-MN-002 during the first inspection period of the fifth 10-year ISI interval is as safe as using ASME Code Case N-716-1 which is now incorporated by reference into 10 CFR 50.55a via inclusion in RG 1.147, Revision 19, without exceptions or conditions.
o The NRC staff finds that the continued use of Relief Request 17-GO-001 during the first inspection period of the fifth 10-year ISI interval will provide reasonable assurance of the structural integrity of the RPV flange because the stress and flaw tolerance analyses documented in EPRI TR 3002007626 bound the McGuire, Unit 1, RPV flange and are still valid for the duration of the first period of the fifth 10-year ISI interval.
o The NRC staff finds that the continued use of Relief Request 18-GO-001 during the first inspection period of the fifth 10-year ISI interval is as safe as using ASME Code Cases N-695-1 and N-696-1 directly, and these code cases are now incorporated by reference into 10 CFR 50.55a via inclusion in RG 1.147, Revision 19, without conditions.
o The NRC staff finds that the continued use of Relief Request 19-GO-001 during the first inspection period of the fifth 10-year ISI interval is as safe as using ASME Code Case N-831 directly because this code case is now incorporated by reference into 10 CFR 50.55a via inclusion in RG 1.147, Revision 19, with a condition that its use is prohibited in new reactor construction.
Based on the above, the NRC staff finds that extending the duration of the above four relief requests to the end of the first inspection period of the fifth 10-year ISI interval is acceptable and does not impact safety.
Based on the above, the NRC staff determined that the licensees proposed alternative (i.e., use of the 2007 Edition with 2008 Addenda of the ASME Code and the above four relief requests) in the first inspection period of the fifth 10-year ISI interval is acceptable, and provides reasonable assurance of structural integrity and safety.
4.0 CONCLUSION
As set forth above, the NRC staff concludes that the proposed alternative provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1).
Therefore, the NRC staff authorizes the use of relief request RA-20-0031 for the Class 1, 2, 3 components and associated supports at McGuire, Unit 1, for the first inspection period of the fifth 10-year ISI interval, which is scheduled to start on December 1, 2021.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Michael Farnan, NRR Date: August 21, 2020
ML20230A205 *By Memorandum **By Email OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NAME GCroon EMiller*** KGoldstein**
DATE 8/18/2020 8/18/2020 08/18/2020 OFFICE NRR/DNRL/NPHP/BC NRR/DORL/LPL2-1/ABC NAME MMitchell* MMarkley (SWilliams for)*
DATE 7/21/2020 8/21/2020