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MONTHYEARML21082A4332021-03-30030 March 2021 Completion of License Renewal Commitment No. 11, Aging Management of Environmentally-Assisted Fatigue Project stage: Other 2021-03-30
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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
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March 30, 2021 Mr. Tom Ray Site Vice President Duke Energy Carolinas, LLC McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
WILLIAM B. MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - COMPLETION OF LICENSE RENEWAL COMMITMENT NO. 11, AGING MANAGEMENT OF ENVIRONMENTALLY-ASSISTED FATIGUE (EPID L-2020-LRO-0085)
Dear Mr. Ray:
By letter dated May 17, 2020 (Agency Documents Access and Management System (ADAMS)
Accession No. ML20157A077), Duke Energy Carolinas, LLC (the licensee, Duke Energy),
submitted a document to the U.S. Nuclear Regulatory Commission (NRC) which proposed Duke Energys inspection plan for License Renewal Commitment (LRC) No. 11 (ADAMS Accession No. ML030850237, NUREG-1772, Appendix D). Specifically, the letter documents Duke Energys proposed use of flaw tolerance evaluations and inspections of the pressurizer surge line nozzles and safety injection nozzle welds for McGuire Nuclear Station, Units 1 and 2 to address LRC No. 11 and environmentally-assisted fatigue (EAF) aging management program.
The NRC staff reviewed the submittal and finds that the licensees EAF aging management program, for LRC No. 11 is acceptable.
The NRC staffs review is found in the enclosure of this letter.
If you have any questions, please contact me at (301) 415-3867 or via email at John.Klos@nrc.gov.
Sincerely,
/RA/
John Klos, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 cc: Listserv
NRC STAFF TECHNICAL REVIEW LICENSE RENEWAL COMMITMENT NO. 11, ENVIRONMENTALLY-ASSISTED FATIGUE AGING MANAGEMENT PROGRAM DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 By letter dated May 17, 2020(Agency Documents Access and Management System (ADAMS),
Accession No. ML20157A077), Duke Energy submitted a letter, which documented Duke Energys proposal to meet License Renewal Commitment (LRC) No. 11, by providing an environmentally-assisted fatigue (EAF) aging management program for the pressurizer surge line and safety injection nozzle welds.
Duke Energys submittal stated that the licensee is committed to addressing EAF effects on several fatigue-sensitive locations during the McGuire Nuclear Station (MNS) period of extended operation (PEO). Duke Energy also stated that it determined that the critical locations of concern for fatigue environmentally-adjusted cumulative usage factor (CUFen) for the MNS, during the PEO are the Hot Leg Surge Nozzle, and Safety Injection Nozzle welds. The licensee also stated that the calculated CUFen values for these locations were determined to exceed the American Society of Mechanical Engineers Boiler & Pressure Vessel (ASME) Code,Section III allowable cumulative usage factor (CUF) of 1.0 during the PEO and would, therefore, be subject to future inspection.
Flow Tolerance Evaluation and Staff Finding The licensees letter detailed plant-specific, fatigue flaw tolerance evaluation results for the pressurizer surge line and safety injection nozzle welds. The staff finds the flaw tolerance evaluation the licensee used as the basis for the inspection interval acceptable, because the licensee performed the evaluations for the subject welds using the 2013 Edition of ASME Code,Section XI, Appendix L, Operating Plant Fatigue Assessment. For reference purposes it is noted that the 2013 Edition of ASME Code,Section XI is endorsed by reference in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, and includes Nonmandatory Appendix L without any conditions. Additionally, Appendix L, Subarticle L-1100 states that this Appendix is applicable only in the absence of any flaw at the location of concern, which is larger than allowed by the applicable acceptance standard referenced in ASME Code,Section XI, Table IWB-3410-1.
Pressurizer surge line inspections The licensees flow tolerance evaluation stated that for the pressurizer surge line, the most bounding location was the hot leg nozzle weld where a postulated flaw reached the allowable flaw depth in approximately 11 years of service. The licensee also stated that the plant-specific, pressurizer surge line inspection program will consist of periodic volumetric examinations that will be performed once per interval (not to exceed 10 years) for pressurizer nozzle-to-pipe welds and the hot leg surge nozzle welds for MNS (total of two welds per unit).
Safety injection line inspections The results of the flaw tolerance evaluations indicate that for the safety injection line -- with a postulated surface-connected flaw -- both axial and circumferential flaws remained acceptable for 60 years of operation. The licensee also stated that the plant-specific, safety injection nozzle weld inspection program will consist of periodic volumetric examinations that will be performed once per interval (not to exceed 10 years) for each of the injection line cold leg nozzle welds for MNS (total of four welds per unit).
Staff finding on inspection program For the applicable pressure surge and safety injection line welds, the staff reviewed the proposed inspection program and independently confirmed that it includes volumetric examinations which provide; (a) an effective method of inspection for the detection of flaws due to fatigue, and (b) reasonable assurance of adequate safety, because when unacceptable flaws are detected, replacement, or repair can be implemented such that the intended function and structural integrity of the piping system will be maintained for MNS during its PEO.
Therefore, the staff finds that the licensees proposed EAF aging management inspection program is acceptable.
The NRC staff also noted that the subject welds for MNS were most recently examined using volumetric examinations with satisfactory results in 2017 and 2018.
EAF aging management program Lastly, the staff also noted that the proposed inspection program implements the ten elements criteria for a comprehensive aging management program which is was found acceptable to the staff per NUREG-1801, Generic Aging Lessons Learned (GALL) Report.
Based on the above review, the staff finds that the licensees proposed EAF aging management program and LRC No. 11 is acceptable.
Docket Nos.: 50-369 and 50-370 Primary reviewer: Roger Kalikian
ML21082A433 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME JKlos KGoldstein MMarkley (EMiller for) JKlos DATE 03/22/2021 03/24/2021 03/25/2021 03/29/2021