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MONTHYEARHNP-11-065, Supplement Information in Regard to Measurement Uncertainty Recapture Power Uprate License Amendment Request2011-06-23023 June 2011 Supplement Information in Regard to Measurement Uncertainty Recapture Power Uprate License Amendment Request Project stage: Supplement ML12082A2102012-03-0505 March 2012 License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Request ML12117A1752012-04-27027 April 2012 Request for Additional Information Regarding License Amendment Related to Measure Uncertainty Recapture Power Uprate Project stage: RAI ML12138A2672012-05-22022 May 2012 Request for Additional Information Regarding License Amendment Related to Measurement Uncertainty Recapture Power Uprate (TAC Nos. ME8213 and ME8214) Project stage: RAI ML12160A0852012-05-29029 May 2012 Response to Request for Additional Information Regarding License Amendment Related to Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML12158A4812012-06-0606 June 2012 Request for Additional Information Regarding License Amendment Related to Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML12168A0022012-06-15015 June 2012 NRR E-mail Capture - Request for Additional Information for License Amendment Request Dated March 5, 2012 Project stage: RAI ML12187A1742012-06-21021 June 2012 Response to Request for Additional Information Regarding License Amendment Related to Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML1218006502012-07-0303 July 2012 Mcguire Nuclear Station, Units 1 and 2 - Fire Protection Fire Protection Safety Evaluation Input Regarding License Amendment Request Measurement Uncertainty Recapture Power Uprate Project stage: Approval ML12199A0232012-07-0606 July 2012 Response to Request for Additional Information Regarding License Amendment Related to Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML12209A1752012-07-16016 July 2012 Response to Request for Additional Information Regarding License Amendment Related to Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML12215A3302012-08-0101 August 2012 NRR E-mail Capture - Request for Additional Information for License Amendment Request Dated March 5, 2012 Project stage: RAI ML12219A2712012-08-0606 August 2012 NRR E-mail Capture - Request for Additional Information for License Amendment Request Dated March 5, 2012 (TAC Nos. ME8213 and ME8214), RAI Questions 43 and 44 Project stage: RAI ML12250A6222012-08-15015 August 2012 Response to Request for Additional Information Regarding License Amendment Request Related to Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML12254A0182012-08-23023 August 2012 NRR E-mail Capture - Request for Additional Information for License Amendment Request Dated March 5, 2012 (TAC Nos. ME8213 and ME8214), RAI Questions 45 and 46 Project stage: RAI ML12251A0282012-09-13013 September 2012 Request for Withholding Information from Public Disclosure (TAC Nos. ME8213 and ME8214) Project stage: Withholding Request Acceptance ML12251A0242012-09-13013 September 2012 Request for Withholding Information from Public Disclosure (TAC Nos. ME8213 and ME8214 Project stage: Withholding Request Acceptance ML12284A1302012-09-27027 September 2012 Response to Request for Additional Information Regarding License Amendment Request Related to Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML12310A3842012-11-0101 November 2012 Response to Request for Additional Information Regarding License Amendment Request Related to Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML13024A4062013-01-0202 January 2013 Revision to a Response to a Request for Additional Information Regarding License Amendment Request Related to Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML13079A3302013-03-0707 March 2013 Restatement of License Condition Proposed in August 15, 2012 Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML13073A0412013-05-16016 May 2013 Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Approval ML13151A2002013-06-0404 June 2013 Correction Letter to Issuance of Amendment Nos. 269 and 249, Measurement Uncertainty Recapture Power Uprate Project stage: Approval 2012-07-03
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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:Request for Additional Information (RAI)
MONTHYEARML24197A1702024-07-15015 July 2024 Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations 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) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23030B9032023-01-30030 January 2023 Formal Release of RAIs for McGuire Unit 1, Relief Request Impractical RPV Rx Coolant System Welds, Due March 1, 2023 (Email) ML23017A2232023-01-13013 January 2023 Request for Additional Information (RAI) Issuance for McGuire Unit 1 Steam Generator Tube Inspection Report (Email) ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22102A2962022-04-13013 April 2022 Request for Withholding Information from Public Disclosure Response to Request for Additional Information ML22063B1782022-03-0909 March 2022 Request for Additional Information Regarding LAR for Revision to the Conditional Exemption of the End of Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) NON-PROPRIETARY ML22010A0732022-01-0606 January 2022 50.59 Inspection Information Request ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21267A2782021-09-23023 September 2021 50.59 Inspection Information Request ML21252A0532021-09-0808 September 2021 NRR E-mail Capture - Formal Release of Rais, 30 Day Response, Mcguire Relief Request, Ref: Later Edition Addenda ASME Code, Section XI, 50.55a(g)(4)(iv) ML21103A0542021-04-13013 April 2021 NRR E-mail Capture - Extension to Request for Additional Information AMS Topical Report AMS-TR-0720R1 ML21067A6742021-03-0505 March 2021 NRR E-mail Capture - Final Request for Additional Information AMS Topical Report AMS-TR-0720R1 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21020A0682021-01-20020 January 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000369/2021011 and 05000370/2021011) and Request for Information (RFI) ML20346A0212020-12-10010 December 2020 NRR E-mail Capture - Formal Release of RAIs - License Amendment to Change TS 3.8.1 Due Jan. 29, 2021 ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20216A3512020-08-0303 August 2020 Mcquire U-1 ISI RFI ML20101L3132020-04-10010 April 2020 Notification of Inspection and Request for Information ML20071D0962020-03-0505 March 2020 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station Unit 1 Delay in Update of the Code of Record for in Service Inspections ML20050D3382020-02-21021 February 2020 Letter RAI 1 MAGNASTOR-Catawba and McGuire Exemptions with Enclosure ML19354B6372020-01-0707 January 2020 Exemption Request for NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density Request for Additional Information ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18352A8052018-12-18018 December 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - MRP-227 Review ML18306A9372018-11-0202 November 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Esps LAR ML18285A0812018-10-11011 October 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - TORMIS LAR RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML18138A4662018-05-18018 May 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - TORMIS LAR ML18088B2822018-03-29029 March 2018 Requalification Program Inspection - McGuire Nuclear Station ML18057A2182018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to A. Zaremba Request for Additional Information for Review of Duke Energy'S Decommissioning Funding Plan Update) ML17331B1492017-11-21021 November 2017 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Nsws One-Time LAR (CACs MG0242 and MG0243, EPID L-2017-LLA-0299) ML17317B0932017-11-13013 November 2017 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Irlt (CACs MF9020 and MF9021; EPID L-2016-LLA-0032) ML17230A1512017-08-15015 August 2017 Notification of Inspection of Inspection and Request for Information ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17135A0322017-05-12012 May 2017 NRR E-mail Capture - Request for Additional Information - McGuire TSTF-197 ML17114A4992017-04-17017 April 2017 Emergency Preparedness Inspection and Request for Information ML16302A1122016-11-0404 November 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program (CAC Nos. MF2934 and MF2935) MNS-16-077, Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program2016-09-29029 September 2016 Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program ML16228A2612016-08-15015 August 2016 Email - McGuire Unit No. 1: Request for Additional Informati- Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping. ML16194A2862016-07-12012 July 2016 E-Mail - Mcguirai Ice Condenser Door Position Alternate Verification, (ML16089A228) CAC Nos. MF7526 and MF7527 ML16175A0222016-07-12012 July 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program ML16014A6882016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme ML15348A2602015-12-17017 December 2015 Request for Additional Information Regarding License Amendment Request to Use an Alternative Fission Gas Gap Release Fraction ML15320A3862015-11-19019 November 2015 RAI LAR to Adopt TSTF-523 ML15314A3592015-11-10010 November 2015 Duke Energy Draft RAIs Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15314A3562015-11-10010 November 2015 E-mail from J. Whited to A. Zaremba Duke Energy Draft RAIs License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15289A5552015-10-26026 October 2015 Request for Additional Information Regarding License Amendment Request Nuclear Service Water System Allowed Outage Time Extension 2024-07-15
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 22,2012 Mr. Regis T. Repko Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT RELATED TO MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE (TAC NOS. ME8213 AND ME8214)
Dear Mr. Repko:
By letter dated March 5, 2012, Duke Energy Carolinas, LLC (the licensee), submitted a proposed license amendment to change the McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2), Technical Specifications (TSs). The proposed change revises the TSs to implement a measurement uncertainty recapture power uprate for McGuire 1 and 2. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete our review. The enclosed document describes this request for additional information (RAI). Please note that the numbering of the questions in this RAJ does not begin at the number one. A prior RAJ regarding this proposed license amendment was issued to you by letter dated April 27, 2012 (Agencywide Documents Access and Management System Accession No. ML12117A175), with RAI questions numbered one through four. A written response should be provided to the NRC staff within 30 days of the issuance of this letter in order to support our timely review of this application.
Jf you have any questions, please call me at 301-415-1119.
Sincerely, Jon Thompson.
Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
RAI cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING LICENSE AMENDMENT REQUEST RELATED TO THE IMPLEMENTATION OF A MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 By letter dated March 5, 2012 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML12082A210), Duke Energy Carolinas, LLC (Duke Energy, the licensee), submitted a license amendment request (LAR) to change the McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2), Technical Specifications (TSs). The proposed change revises the TSs to implement a measurement uncertainty recapture
[MUR] power uprate for McGuire 1 and 2. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that the following additional information is needed in order to complete our review: In the LAR, Enclosure 2, "Summary of [Regulatory Information Summary] RIS 2002-03 Requested Information," Section VI1.6.A, "Fire Protection Program," states that " ... Additional building heat-up will be minimal such that currently credited fire protection manual actions will not be prevented from being accomplished by their required time ... !! The NRC staff requests the licensee to verify that implementation of the LAR will not require any new operator actions. If implementation of the LAR requires any new operator actions, then please describe them. (AFPB 1) In the LAR, Enclosure 2, Section 47, "Safe Shutdown Fire," states that, " ... For specific site fire area, the Standby Shutdown Facility is the assured method to achieve and maintain the unit in a stable hot shutdown condition.
While the plant is in the hot standby mode, damage control measures can be taken, as necessary, to restore the capability to achieve cold shutdown .... " The NRC staff requests that the licensee describe how McGuire 1 and 2 meet the 72-hour requirements contained in 10 CFR Part 50, Appendix R, Sections III.G.1.b and III.L, with increased decay heat at MUR power uprate conditions. (AFPB 2) Some plants credit aspects of their fire protection system for other than fire protection activities (e.g., utilizing the fire water pumps and water supply as backup cooling or inventory for non-primary reactor systems).
If McGuire 1 and 2 credit its fire protection system in this way, the LAR should identify the specific situations and discuss to what extent, if any, the LAR affects these "non-fire-protection" aspects of the plant fire protection system. If McGuire 1 and 2 do not take such credit, then the NRC staff requests that the licensee verify this as well. Enclosure
-In your response discuss how any non-fire suppression use of fire protection water will impact the ability to meet the fire protection system design demands. (AFPB 3) The LAR takes credit in several instances for administrative controls of the McGuire 1 and 2 "design change process," or "engineering change process." The NRC staff requests that the specific numbers and titles of controlling procedures be provided, along with a reference to the sections that are relevant to identifying impacted procedures, controls, displays, alarms, the Safety Parameter Display System, and other operator interfaces, the simulator, and training, so that the NRC staff can conclude its review." (AHFB 1) Section 3.6.1.2 of the McGuire 1 and 2 updated final safety analysis report (UFSAR) stipulates the criteria used to define moderate energy lines at McGuire 1 and 2. Additionally, Section 3.6.2.2.1 outlines the criteria used to postulate through-wall cracks in moderate energy piping systems. However, the information contained in LAR, Enclosure 2,Section IV, does not include an assessment of the impact of implementation of the LAR on moderate energy piping or the postulation of moderate energy line cracks. Based on the McGuire 1 and 2 UFSAR criteria related to moderate energy piping, state the effects of the proposed MUR power uprate on moderate energy piping, including whether the LAR results in the required postulation of additional moderate energy line cracks. (EMCB 1)Section IV.1.D of RIS 2002-03 stipulates that the content of MUR power uprate LARs should include the codes of record used in the evaluations of structures, systems and components (SSCs) to determine their structural adequacy at MUR conditions.
However, in the LAR, Enclosure 2, Table IV.1.D-1, it does not contain the code of record used in assessing the reactor vessel internals (RVls) or balance-of-plant (BOP) and interfacing piping systems for structural adequacy at the uprated conditions.
Please state the design basis code of record for the RVls, including core support and non-core support structures, BOP piping and interfacing piping systems and confirm that the evaluations performed in support of the LAR were performed consistent with the provisions stipulated by the design basis codes of record for those SSCs identified above. (EMCB 2) In the LAR, Enclosure 2,Section IV.1.A.ii, describes the impact of the proposed LAR on the reactor core support structures and vessel internals (Le., the RVls). The discussion in this section of the LAR indicates that the revised core parameters at the proposed MUR power level are bounded by the values used in the analyses of record (AOR) for the RVls when the analytical uncertainties in the AOR are considered.
Confirm that the AOR related to the structural evaluation of the RVls, including all core support and non-core support structures, did not require a revision to support implementation of the LAR. Additionally, quantify the uncertainty relied upon in the AOR to demonstrate that the calculation tolerance available in the AOR sufficiently bounds the core parameters proposed in the LAR. (EMCB 3) In the LAR, Enclosure 2,Section IV.1.A.v, details the evaluation of the BOP and interfacing piping systems to determine whether these systems will maintain adequate structural integrity at the MUR power level. Please state whether the AOR for any of these
-systems required revision to support the LAR (Le., identify systems which were not bounded by the current AOR). For those systems not bounded by the current AOR, identify whether the revision to the AOR was necessitated based on an increase in temperature, pressure, flow rate, or a combination of any of the three operating parameters. (EMCB 4) In the LAR, Enclosure 2,Section IV.1.A.ix, discusses the review performed to evaluate the effects of the LAR on safety-related valves. The discussion in this section of the LAR focuses on the effects of MUR implementation on the pressurizer overpressure protection valves and other safety-related valves. Please address the following issues related to the safety-related valve evaluation: With respect to the pressurizer overpressure protection valves, the LAR states that the current design basis event analysis is bounding and, as such, there is no adverse impact on the subject valves. Please state whether the review performed for the subject valves considered all MUR operating conditions, including normal operating conditions and abnormal operating conditions.
Additionally, confirm whether the AOR for the subject valves remains bounding at MUR conditions.
If the analyses are not bounded, confirm that the design basis criteria used to structurally qualify the valves remain satisfied at the proposed MUR power level. For the other safety-related valves reviewed in support of MUR implementation, the information in the LAR did not identify which valves were included in this review or whether these valves were found to be structurally adequate at the proposed MUR power level, as evidenced by satisfying their respective design basis criteria.
State whether any of the other safety-related valves reviewed to support MUR implementation were found to be unbounded by their current AOR. If the AOR for these valves was found to be not bounding, confirm that the respective design basis acceptance criteria remain satisfied. (EMCB 5) In the LAR, Enclosure 2,Section IV.1.B.viii, "Jet impingement and thrust forces," only discusses the impact of the LAR on the McGuire 1 and 2 leak-before-break evaluations and does not mention jet impingement nor thrust forces. In Section IV.1.B.vii it states that " ... there is no impact on the [high energy line break] HELB analysis that was originally performed for McGuire Units 1 and 2 ...... and describes the currentAOR regarding HELBs as bounding. Please confirm that the statement in Section IV.1.B.vii applies to jet impingement and thrust forces (or other dynamic effects loadings) resulting from postulated HELBs, such that a conclusion can be made regarding whether the dynamic effects resulting from postulated HELBs remain valid at the proposed MUR power level. (EMCB 6) With regards to the structural evaluations and analyses performed to support the LAR, please confirm that all analyses and evaluations for SSCs which were within the scope of the McGuire 1 and 2 license renewal efforts were done in accordance, and consistent, with the methodologies approved and referenced in NUREG-1772, "Safety Evaluation Report Related to the License Renewal of McGuire Nuclear Station, Units 1 and 2, and Catawba Nuclear Station, Units 1 and 2." Otherwise, please state the changes for all structural evaluations and analyses performed to support the proposed MUR conditions that were not performed in accordance with NUREG-1772.
Justification should also be provided with regards to the acceptability of these changes. (EMCB 7) For McGuire 1, the limiting reference temperature for pressurized thermal shock (RTPTS) reported in the LAR, Enclosure 2,Section IV.1.C.i, is 203 OF for the lower shell longitudinal welds 3-442A, B, and C. The NRC staff has the following questions: The NRC staff found that the limiting RTPTS value for McGuire 1 in this LAR differs from that reported the licensee's license renewal LAR (LRLAR). NUREG-1772 states "Using a limiting fluence of 2.73 x 10 19 n/cm 2 at EOLE [end of life extended], the applicant's revised PTS assessment prOjected the RTPTS values for these welds [the McGuire 1 limiting weld] to be 253 of using all relevant surveillance capsule data for the heat No. 21935/12008, as obtained from docketed information from the Diablo Canyon [Power Plant], [Unit] 2 [Diablo 2] RV [reactor vessel] material surveillance program (inclusive of fracture toughness tests performed on test specimens from Diablo 2 capsules U, X, Y, and V)." The NRC staff used the LAR fluence of 2.13 x 1019 n/cm 2 to reduce the licensee's reported LRLAR RTPTS value from 253 OF to 238 OF, but this value is still far greater than the LAR limiting RTPTS value of 203 oF. Please provide your calculations of the chemistry factors and RTPTS values from the LRLAR (253 OF) and the LAR (203 OF) and resolve this apparent discrepancy.
If the resolution results in a revision of the LAR limiting RTPTS value, then Tables IV.1.C-5, IV.1.C-6, and IV.1.C-9, related to heatup and cooldown curves, need to be revised also because the LAR limiting adjusted reference temperatures (ARTs) will be changed accordingly. Unlike the LRLAR, where the fluence values were different for intermediate shell plate longitudinal welds 2-442A, 2-442B, and 2-442C, the LAR fluence values reported for these welds are identical.
Please confirm that the peak f/uence value for the intermediate shell plate longitudinal welds 2-442A, 2-442B, and 2-442C has been used for all three welds to simplify the classification of these welds in the LAR. Please also confirm that the similar simplification has been applied to the lower shell plate longitudinal welds 3-442A, 3-442B, and 3-442C in the LAR. (EVIB 1) For the upper-shelf energy (USE) evaluation, the LAR, Enclosure 2,Section IV.1.C.v, states that the prOjected EOLE Charpy USE values due to the MUR power uprate fluence at the one quarter RV wall thickness (Y4 T) location were 60.5 ft-Ibs for the intermediate shell longitudinal welds 2-442A, 2-442B, and 2-442C, using surveillance data, and 61.8 ft-Ibs for the bottom head ring 03 for McGuire 2. The limiting USE values reported in the LRLAR are 53 ft-Ibs for the nozzle shell plate B5011-2 for McGuire 1 and 55 ft-Ibs for nozzle shell to intermediate shell weld for McGuire 2. These apparent discrepancies involve a change of limiting materials for both McGuire units. Please explain the following:
-The nozzle shell plate B5011-2 is no longer the limiting USE material for McGuire 1 in the LAR because its fluence at the T location has been revised from 1.83 x 10 19 n/cm 2 (LRLAR) to 0.033 x 10 19 n/cm 2 (LAR). The fluence at the T location for the intermediate shell longitudinal welds 2-442A, 2-442B, and 2-442C of McGuire 1 decreased from 1.63 x 10 19 n/cm 2 (LRLAR) to 1.269 x 10 19 n/cm 2 (LAR) indicating that higher USE value should be expected for the LAR. Instead, the USE value decreased from 72 ft-Ibs (LRLA) to 60.5 ft-Ibs. This appears to be caused by considering additional surveillance data. Please plot all surveillance data in Figure 2 of RG 1.99, Revision 2, to support the USE decrease that was used in estimating the LAR USE value for this material. The nozzle shell to intermediate shell weld is no longer the limiting USE material for McGuire 2 in the LAR because its fluence at the T location has been revised from 1.73 x 10 19 n/cm 2 (LRLAR) to 0.043 x 10 19 n/cm 2 (LAR). Please justify this significant change. Further, the initial USE of ">71" ft-Ibs in Table IV.1.C-12 indicates that the value was not determined based on data from the Certified Materials Test Report (CMTR). Please explain how the initial USE of 71 ft-Ib was determined for the nozzle shell to intermediate shell weld of McGuire 2 and justify use of this initial USE for this weld. If this 71 ft-Ibs value was determined statistically, you must revise this value based on the "mean minus two-sigma" approach. The limiting USE material for McGuire 2 in the LAR is the bottom head ring 03 with an initial USE of ">71" ft-Ibs in Table IV.1.C-12.
Please explain how the initial USE of > 71 ft-Ib was determined for the bottom head ring 03 of McGuire 2 and justify use ofthis initial USE for this ring. If this 71 ft-Ibs value was determined statistically, you must revise this value based on the "mean minus two-sigma" approach. (EVIB 2) For reactor core support structures and vessel internals, the Materials Reliability Program (MRP) Report 1022863 (MRP-227-A), "Pressurized Water Reactor [PWR] Internals Inspection and Evaluation Guidelines
[I&E]," dated December 2011 (ADAMS Accession No. ML12017A194) was issued recently, which contains the NRC staff safety evaluation (SE) for this report. MRP-227 -A provides recommended I&E guidelines, as modified by the NRC staff, for PWR RV internals as a result of the industry effort on this issue for the past few years. The LAR, Enclosure 2,Section IV.1.A.ii, concluded that, "there is no impact, adverse or otherwise, from the McGuire Units 1 and 2 MUR uprate on the plant-specific implementation of the MRP-227 requirements." However,Section IV.1.A.ii did not mention submitting of the plant-specific inspection plan in accordance with MRP-227-A to demonstrate that the degradation of the RV internals will be managed appropriately after the LAR. Please confirm that you plan to submit the plant-specific inspection program consistent with the MRP-227 -A report guidelines, and indicate the approximate date of submittal to support the LAR effectively. (EVIB 3)
-What is the impact of LAR on the air operated valve program for McGuire 1 and 2? (EPTB 1)
May 22,2012 Mr. Regis T. Vice McGuire Nuclear Duke Energy Carolinas, 12700 Hagers Ferry Huntersville, NC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT RELATED TO MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE (TAC NOS. ME8213 AND ME8214)
Dear Mr. Repko:
By letter dated March 5, 2012, Duke Energy Carolinas, LLC (the licensee), submitted a proposed license amendment to change the McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2), Technical Specifications (TSs). The proposed change revises the TSs to implement a measurement uncertainty recapture power uprate for McGuire 1 and 2. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete our review. The enclosed document describes this request for additional information (RAI). Please note that the numbering of the questions in this RAJ does not begin at the number one. A prior RAJ regarding this proposed license amendment was issued to you by letter dated April 27, 2012 (Agencywide Documents Access and Management System Accession No. ML12117A175), with RAJ questions numbered one through four. A written response should be provided to the NRC staff within 30 days of the issuance of this letter in order to support our timely review of this application.
If you have any questions, please call me at 301-415-1119.
Sincerely, IRA! Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
RAI cc w/encl: Distribution via Listserv DISTRIBUTION:
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