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| | issue date = 03/29/2012 | | | issue date = 03/29/2012 |
| | title = Response to Request for Additional Information Regarding Relief Request Serial #11-MN-002 | | | title = Response to Request for Additional Information Regarding Relief Request Serial #11-MN-002 |
| | author name = Repko R T | | | author name = Repko R |
| | author affiliation = Duke Energy Carolinas, LLC | | | author affiliation = Duke Energy Carolinas, LLC |
| | addressee name = | | | addressee name = |
Revision as of 00:53, 29 June 2019
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MONTHYEARML12102A0142012-03-29029 March 2012 Response to Request for Additional Information Regarding Relief Request Serial #11-MN-002 Project stage: Response to RAI ML12249A1752012-09-0606 September 2012 Mcguire Nuclear Station, Unit 2, Relief 10-MN-002 to Extend the Inspection Interval for Reactor Vessel Category B-A and B-D Welds Project stage: Other 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 Project stage: Approval 2012-09-24
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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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REGIS T. REPKO Vice President L ,-,-:"Energy, McGuire Nuclear Station Duke Energy MG01 VP / 12700 Hagers Ferry Rd.Huntersville, NC 28078 980-875-4111 980-875-4809 fax regis. repko@duke-energy.
com I./March 29, 2012 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)McGuire Nuclear Station, Unit 2 Docket No. 50-370 Relief Request Serial #11-MN-002 Response to Request for Additional Information By letter dated October 3, 2011, Duke Energy submitted Relief Request (RR) 11 -MN-002 to request authorization to extend the inservice inspection (ISI) interval for the McGuire 2 reactor vessel Category B-A and B-D welds from 10 years to 20 years so that the third 10-year ISI interval examinations can be deferred until calendar year 2024.On March 6, 2012, the Nuclear Regulatory Commission (NRC) staff electronically requested additional information regarding this RR. The attachment to this letter contains Duke Energy's response to the NRC questions.
Duke Energy requests NRC approval of this relief request by September 1, 2012.If you have any questions or require additional information, please contact P.T. Vu at (980) 875-4302.Sincerely, Regis T. Repko Attachment www. duke-energy comr U. S. Nuclear Regulatory commission March 29, 2012 Page 2 xc: V. M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 J. H. Thompson, Project Manager U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852-2738 J. Zeiler NRC Senior Resident Inspector McGuire Nuclear Station ATTACHMENT Relief Request 11-MN-002 Response to NRC Request for Additional Information Relief Request 11 -MN-002, Response to NRC Request for Additional Information Attachment, Page 2 of 2 Question 1: Table 2 states that three indications were identified in the RV beltline region during the most recent/SI.a. Please identify the RV beltline forging and/or weld materials where the three beltline indications were discovered.
- b. Please state whether additional recordable indications were discovered in any of the subject Examination Category B-A or B-D (beltline and non-beltline) components, other than those reported in Table 2, even if the indications were found to be acceptable based on the ASME Code, Section Xl, IWB-3500 acceptance standards.
Response: la. All three of the noted beltline indications are located in the Intermediate Shell Forging (Item 2 in Table 3 of Relief Request 11-MN-002).
1 b. During the most recent examination, a total of 76 recorded indications were identified during the performance of Examination Category B-A and B-D examinations, including the three indications stated in Table 2. All of the recorded indications were determined to be acceptable per IWB-3500, Table IWB-3510-1 of the ASME Code Section XI, 1989 Edition, with no further evaluation required.Question 2: Please state whether any of the SA-508, Class 2 RV forgings at McGuire 2 are susceptible to intergranular separations (underclad cracking), based on the criteria specified in Regulatory Guide (RG) 1.43, "Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components," Revision 1, March 2011.Response: It was assumed in the calculation of the McGuire Unit 2 RV through-wall cracking frequencies (TWCF), that the SA-508, Class 2 RV forgings are susceptible to intergranular separations (underclad cracking).
This assumption was considered to be conservative and an evaluation was not performed to determine whether the SA-508, Class 2 RV forgings at McGuire Unit 2 meet the criteria specified in Regulatory Guide 1.43, Revision 1.Question 3: ASME Code Case (CC) N-648-1, "Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles, Section X1, Division 1," is listed as "Conditionally Acceptable" in Table 2 of RG 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1,," Revision 16, October 2010. Please state whether the previous examinations of the Examination Category B-D, Nozzle Inside Radius Sections, which utilized the visual examination methods of CC N-648-1, in lieu of volumetric examination methods, met the condition specified in Table 2 of RG 1.147.Response: The visual examination methods of CC N-648-1 (in lieu of volumetric examination methods) used to inspect the Category B-D, Nozzle Inside Radius Sections, met the condition specified in Table 2 of RG 1.147.