Letter Sequence Other |
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CAC:MF8416, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B (Open) |
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MONTHYEARML16291A0152016-10-13013 October 2016 NRR E-mail Capture - McGuire Unit No. 2: Acceptance REVIEW- Relief Request Alternative Testing Approval for Two PORV Block Valves Project stage: Acceptance Review ML16294A1112016-10-18018 October 2016 Email Attachment McGuire Nuclear Station, Unit 2 - Acceptance Review - Relief Request Alternative Testing Approval for Two PORV Block Valves Project stage: Request ML16294A1102016-10-18018 October 2016 Email - McGuire Nuclear Station, Unit 2 - Acceptance Review - Relief Request Alternative Testing Approval for Two PORV Block Valves Project stage: Request ML16291A3032016-10-20020 October 2016 Relief Request MC-SRV-NC-01, Regarding Alternate Testing for Pressurizer Power Operated Relief Valve Block Valves Inservice Testing Project stage: Other 2016-10-18
[Table View] |
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Category:Code Relief or Alternative
MONTHYEARML24207A0862024-07-24024 July 2024 Relief Request Acceptance Review Results - McGuire Units 1 and 2 Alternatives Component Cooling Pumps, RHR Pumps ML23256A0882023-09-25025 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 2024-07-24
[Table view] Category:Letter
MONTHYEARIR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, “Provide Risk-Informed Extended Completion Times - Ritstf IR 05000369/20244032024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, “Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000369/20240102024-03-13013 March 2024 Comprehensive Engineering Team Inspection Report 05000369/2024010 and 05000370/2024010 IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 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 05000369/20230102023-10-13013 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 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 ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report 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 2024-08-01
[Table view] Category:Safety Evaluation
MONTHYEARML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, “Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML23256A0882023-09-25025 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 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) ML17269A1982017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 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) 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) 2024-07-12
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 20, 2016 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNIT 2 - RELIEF REQUEST MC-SRV-NC-01 REGARDING ALTERNATE TESTING FOR PRESSURIZER POWER OPERATED RELIEF VALVE BLOCK VALVES INSERVICE TESTING (CAC NO. MF8416)
Dear Mr. Capps:
By letter dated September 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16274A066), Duke Energy Carolinas, LLC (the licensee) submitted Relief Request MC-SRV-NC-01 regarding alternate testing for pressurizer power operated relief valve block valves inservice testing (IST). The licensee requested an alternative test plan in lieu of certain IST requirements of the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the IST program at the McGuire Nuclear Station (MNS), Unit 2, during the fourth 10-year IST program interval. The licensee requested relief pursuant to Title 10 of the Code of Federal Regulations 50.55a(z)(2). The request was made on the basis that compliance with the specified ASME requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety at MNS, Unit 2.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, it is acceptable to maintain the valve current configuration with Valve 2NC-35B in its closed position and Valve 2NC-33A in the open back seated position, with power on and capable of isolating on an automatic close signal configuration maintained, until maintenance can be performed at the next refueling outage.
Therefore, the NRC staff authorizes the proposed alternative in Relief Request MC-SRV-NC-01, for MNS, Unit 2, until the next refueling outage, which is scheduled to begin on March 30, 2017.
During a telephone call on October 13, 2016, your staff confirmed that an evaluation was performed using the Surveillance Frequency Control Program (SFCP), and the results met the criteria in Nuclear Energy Institute (NEI) 04-10, Revision 1, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies, Industry Guidance Document," April 2007 (ADAMS Accession No. ML071360456), such that an associated license amendment for this relief request was not needed. By electronic mail dated October 18, 2016 (ADAMS Package Accession No. ML16294A119), the licensee provided additional information concerning the SFCP and valve testing. This matter is being referred to NRC Region II for followup via the inspection program.
S. Capps All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject relief request remain applicable, including the third party review by the Authorized Nuclear lnservice Inspector.
If you have any questions, please contact the project managers, V. Sreenivas at 301-415-2597 or V.Sreenivas@nrc.gov, or G. Edward Miller at 301-415-2481 or Ed.Miller@nrc.gov.
Sincerely, Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-370
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST MC-SRV-NC-01 RELATED TO ALTERNATIVE TESTING FOR PRESSURIZER POWER OPERATED RELIEF VALVE BLOCK VALVES INSERVICE TESTING PROGRAM FOURTH 10-YEAR INTERVAL DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNIT 2 DOCKET NO. 50-370
1.0 INTRODUCTION
By letter dated September 29, 2016 (Agencywide Documents Access and Management System Accession No. ML16274A066), Duke Energy Carolinas, LLC (the licensee), submitted proposed Relief Request MC-SRV-NC-01 to the U.S. Nuclear Regulatory Commission (NRC or the Commission). The licensee requested an alternative test plan in lieu of certain inservice testing (IST) requirements of the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the IST program at the McGuire Nuclear Station (MNS), Unit 2, during the fourth 10-year IST program interval.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee requested to use proposed alternatives, since complying with the current ASME OM Code requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(f), "lnservice testing requirements," require, in part, that IST of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized, pursuant to paragraph 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2).
In proposing an alternative, a licensee must demonstrate that the proposed alternative provides an acceptable level of quality and safety (10 CFR 50.55a(z)(1 )) or that compliance would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety (10 CFR 50.55a(z)(2)).
Enclosure
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to authorize the alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1.1 Licensee's Relief Request MC-SRV-NC-01 ASME OM Code Requirements ISTC-3510, "Exercising Test Frequency," states, in part, that, "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, ISTC-3550, ISTC-3570, ISTC-5221, and ISTC-5222."
Alternative testing is requested for the following valves:
Table 1 Valve ID System Cat Class 2NC-33A Pressurizer Block Valve B 1 2NC-35B Pressurizer Block Valve B 1 In its letter dated September 29, 2016, the licensee stated the following:
Reason for Request
Nuclear Condition Report (NCR) 02043441 was initiated by systems engineering due to an increase in identified reactor coolant system (RCS) leakage during performance of RCS system leakage calculation on July 4, 2016. Subsequent calculations yielded repeatable results at or near 0.148 GPM [gallons per minute],
a significant change from previous results of approximately 0.038 GPM. Technical Specification (TS) 3.4.13 limits RCS identified leakage to a maximum of 10 GPM.
Initial troubleshooting identified 2NC-33A packing leakage as the source of RCS leakage. Following additional troubleshooting of all Unit 2 pressurizer PORV
[power operated relief valve] block valves, NCR 02048025 identified 2NC-35B as a source of RCS identified leakage due to high temperatures observed on the valve packing leak off line.
Stroking the valves can create a hardship as further packing degradation may result, reducing operational RCS leakage margin. Current RCS leakage values are stable with 2NC-33A administratively open on backseat and 2NC-35B administratively closed. Both valves remain operable with emergency power available. Based on current plant conditions and as described in the proposed alternative basis, the licensee is requesting relief from ASME Code quarterly valve surveillances to prevent quarterly valve cycles until valve repair can be made during the next Unit 2 refueling outage (2EOC24).
Repair of 2NC-33A and 2NC-35B would require entry into containment and RCS depressurization for isolation purposes. Personal safety and ALARA [as low as reasonably achievable] practices are maximized during a scheduled refueling outage. Additionally, maneuvering the reactor to a mode outside of TS applicability and depressurizing the RCS involves inherent risk and increases nuclear safety risk due to cycling plant equipment.
Proposed Alternative and Basis for Use:
As an alternative to performing quarterly surveillance testing on 2NC-33A and 2NC-35B, the licensee is requesting to perform exercise and valve stroke timing testing during cold shutdown. In the event of PORV block valve packing leakage, stroking the respective valve creates a hardship because of the increased potential for packing leakage. Increased leakage reduces the margin for acceptable reactor coolant system identified leakage (Reference TS 3.4.13, Operational Leakage). If RCS identified leakage exceeds its allowable limit, the required action is plant shutdown. For non-leaking PORV block valves, the valves will continue to be stroked quarterly per applicable ASME code requirements.
As stated in Section 5, to control stem packing leakage on 2NC-33A, the licensee manually positioned the valve open on backseat with power available. Operational valve stroke timing testing was conducted from the open backseat configuration and re-opened the valve with satisfactory results. This testing demonstrates the valve is fully operational ready in the current configuration. Continued stroking of 2NC-33A represents a hardship with respect to manually positioning the valve on backseat following each quarterly exercise and valve stroke timing test.
When the valves are closed due to valve packing leakage, the valve is administratively maintained closed with power available. If required to be opened to perform its intended safety function, the valve is opened by the control room operator. Opening the valve with a packing leak during normal plant operation may cause further stem packing damage, resulting in increased RCS leakage.
When the valves are open due to valve packing leakage, the valve is administratively maintained open with the valve stem on backseat with power available. If required to be closed to perform its intended safety function, the valve is closed by the control room operator. Closing the valve with a packing leak during normal plant operation may cause further stem packing damage, resulting in increased RCS leakage.
The subject valves have established preventative maintenance activities. The valves have maintained consistent performance with no adverse trends or abnormalities noted during Motor Operated Valve diagnostic testing. The valve actuator general and lubrication condition is of sufficient quality to support continued reliability with the relief of quarterly exercise and stroke timing activities until scheduled repairs in 2EOC24.
IST performance history of McGuire Unit 2 PORV block valves has been excellent with no valve stroke timing or position indication testing failures from reviewed data January 1, 2009 to present. 2NC-33A and 2NC-35B valve stroke timing performance (open and closed directions) has been consistently between 5.5 and 6.5 seconds, demonstrating acceptable margin to the maximum limit of 10 seconds.
Duration of Proposed Alternative:
This condition is only intended to permit McGuire Unit 2 operation for a limited period of time not to exceed restart from the next refueling outage. 2NC-33A and 2NC-35B repair is planned for the next McGuire Unit 2 refueling outage 2EOC24 scheduled to begin on March 30, 2017. Following the refueling outage, the licensee will resume quarterly testing of 2NC-33A and 2NC-35B per applicable ASME Code requirements.
3.1.2 NRC Staff Evaluation ASME OM Code requirement ISTC-3510 requires that active Category A and B valves be exercised nominally every 3 months. In addition, the ASME OM Code specifies that if the exercise tests are not practicable to perform during power operation, the test may be deferred to either cold shutdowns or refueling outages.
The licensee stated that it has been exercise testing the valves noted in Table 1 above nominally every 3 months and that IST performance history has been excellent with no issues.
Recently, there has been a noted increase in RCS leakage due to faulty packing of the pressurizer block Valves 2NC-33A and 2NC35B. Continued operation of the faulty valves in the normally open position could challenge TS RCS operational leakage limit of 10 gallons per minute (gpm) for identified leakage. To avoid an unnecessary RCS depressurization, 2NC-33A was back-seated to seal off the packing area, operationally tested from this configuration, and re-seated into the back seat. Valve 2NC-35B was placed into the closed position. RCS leakage was confirmed to return to acceptable levels. Continuation with the quarterly exercise stroke testing could result in an increase in packing degradation and lead to a plant shutdown. The NRC staff concludes that this would constitute a hardship or unusual difficulty, without a compensating increase in the level of quality or safety.
The licensee proposes to maintain the valve current configuration with Valve 2NC-35B in its closed position and Valve 2NC-33A in the open back seated position, with power on and capable of isolating on an automatic close signal. This configuration will be maintained until maintenance can be performed at the next refueling outage currently scheduled for spring of 2017. The NRC staff concludes that the proposed alternative provides reasonable assurance that the components are operationally ready.
4.0 CONCLUSION
As set forth above, the NRC staff determined that the proposed alternatives provide reasonable assurance that the affected components are operationally ready. Accordingly, the NRC staff
concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(z)(2).
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject relief request remain applicable.
Therefore, the NRC staff authorizes MSN, Unit 2, Relief Request MC-SRV-NC-01 alternative until the valves in Table 1 above are repaired during the next refueling outage, which is currently scheduled to begin March 30, 2017.
Principal Contributor: M. Farnan Dated: October 20, 2016
S. Capps All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject relief request remain applicable, including the third party review by the Authorized Nuclear lnservice Inspector.
If you have any questions, please contact the project managers, V. Sreenivas at 301-415-2597 or V.Sreenivas@nrc.gov, or G. Edward Miller at 301-415-2481 or Ed.Miller@nrc.gov.
Sincerely,
/RA/
Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-370
Enclosure:
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