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MONTHYEARML12079A1802012-03-16016 March 2012 Response to Information Request Pursuant to 10 CFR 50.54(f) Related to Estimated Effect on Peak Cladding Temperature Resulting from Thermal Conductivity Degradation in Westinghouse-Furnished Realistic.. Project stage: Other ML12110A1942012-04-23023 April 2012 Request for Additional Information - 50.46, 30-Day Report Regarding Thermal Conductivity Degradation in the Westinghouse-Furnished Realistic Emergency Core Cooling Eval Project stage: RAI ML12116A1472012-04-27027 April 2012 Further Request for Additional Information - 50.46, 30-Day Report Regarding Thermal Conductivity Degradation in the Westinghouse-Furnished Realistic Emergency Core Cooling Project stage: RAI ML12151A3692012-05-29029 May 2012 Response to Request for Additional Information - 10 CFR 50.46 30-Day Report Regarding Thermal Conductivity Degradation in the Westinghouse-Furnished Realistic Emergency Core Cooling System Evaluation Project stage: Response to RAI ML12314A0312012-11-16016 November 2012 Closure Evaluation for Report Pursuant to 10 CFR 50.46(a)(3)(ii) Re Significant ECCS Evaluation Model Error Related to Nuclear Fuel Thermal Conductivity Degradation Project stage: Other 2012-04-23
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Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 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 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 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 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 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 IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 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 IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 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) ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) 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 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 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 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 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 IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 2024-02-02
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23271A1792023-09-28028 September 2023 Request for Confirmation License Amendment Application to Revise Control Room Cooling TS 3.7.11 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) ML22336A0692022-11-28028 November 2022 Final 2023 Catawba Nuclear Station (CNS) Commercial Grade Dedication (CGD) Inspection Information Request ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22154A1312022-06-0303 June 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Environmentally-Assisted Fatigue License Renewal Commitment 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 ML22024A1122022-01-24024 January 2022 2022 CNS POV Inspection Information Request 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) ML21335A2252021-12-0101 December 2021 NRR E-mail Capture - Catawba Nuclear Station, Unit 2 - Request for Additional Information Spring 2021 Steam Generator Tube Inspection Report (L-2021-LRO-0043) 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) ML21117A1232021-04-23023 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request Request for Additional Information ML21103A0542021-04-13013 April 2021 NRR E-mail Capture - Extension to Request for Additional Information AMS Topical Report AMS-TR-0720R1 ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 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 ML20338A3932020-12-0303 December 2020 Notification of Inspection and Request for Information 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) ML20244A0462020-08-31031 August 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20216A3512020-08-0303 August 2020 Mcquire U-1 ISI RFI ML20101L3132020-04-10010 April 2020 Notification of Inspection and Request for Information ML20073F3832020-03-13013 March 2020 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station - SG Report (RA-19-0391) - C2R23 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 ML20052E4282020-02-21021 February 2020 Notification of NRC Fire Protection Team Inspection (Fpti) (NRC Inspection Report 05000412/2020013 and 05000414/2020013) and Request for Information ML19354B6372020-01-0707 January 2020 Exemption Request for NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density Request for Additional Information ML20003E5372020-01-0303 January 2020 NRR E-mail Capture - Catawba PT Limits LAR - RAIs ML19032A5842019-01-31031 January 2019 Emergency Preparedness Program Inspection Request for 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) ML19009A5412019-01-0909 January 2019 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Esps LAR 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 ML18068A5052018-03-0909 March 2018 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Nsws Return Pond Header LAR (CACs MG0245 and MG0246, EPID L-2017-LLA-0297) ML18058B2062018-02-27027 February 2018 Notification of Inspection and Request for Information 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) ML17335A0972017-11-29029 November 2017 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Relief Request 17-CN-001 (CACs MF9807 and MF9808, EPID L-2017-LLR-0032) 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) 2023-09-28
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 23, 2012 Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745 Mr. Regis T. Repko Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 (CATAWBA 1 AND 2),
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (MCGUIRE 1 AND 2)
REQUEST FOR ADDITIONAL INFORMATION - 50.46, 30-DAY REPORT REGARDING THERMAL CONDUCTIVITY DEGRADATION IN THE WESTINGHOUSE-FURNISHED REALISTIC EMERGENCY CORE COOLING EVALUATION (TAC NOS. ME8447, ME8448, ME8449, AND ME8450)
Dear Messrs. Morris and Repko:
By letter dated March 16, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12079A180), Duke Energy Carolinas, LLC (the licensee), submitted a response to an NRC staff information request pursuant to Title 10 Code of Federal Regulations (10 CFR), Section 50.54(f) related to the estimated effect on peak cladding temperature resulting from thermal conductivity degradation in the Westinghouse-furnished realistic emergency core cooling evaluation. The licensee also stated that this response served as a 30-day report of a significant emergency core cooling system evaluation model change or error in accordance with requirements of 10 CFR 50.46(a)(3).
In the course of the U.S. Nuclear Regulatory Commission's (NRC's) staff review of the 30-day report submitted in accordance with 10 CFR 50.46(a)(3), it was determined that additional information is necessary for the NRC staff to complete its review. A request for additional information (RAI) was provided to the licensee by email dated March 26,2012 (ADAMS Accession No. ML 1211 OA336), to facilitate discussion between the NRC staff and the licensee and to enable the licensee to respond to the NRC request in a timely manner. Subsequently, the NRC staff conducted an audit at the Westinghouse Electric Company facilities in Cranberry Township, Pennsylvania, to further clarify the RAI and to further delineate the content required to be responsive to the RAI (audit plan at ADAMS Accession No. ML12101A118). As discussed during the audit, the initial RAt has been modified, as reflected in the enclosure, to provide additional clarity. A response from the licensee is requested within 30 days of transmittal of the request to the licensee.
J. Morris and R. Repko -2 If you have any questions on this matter, please contact 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. 50-413, 50-414, 50-369, and 50-370
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING 10 CFR 50.46 30-DA Y REPORT ON THERMAL CONDUCTIVITY DEGRADATION IN THE WESTINGHOUSE-FURNISHED REALISTIC EMERGENCY CORE COOLING EVALUATION CATAWBA NUCLEAR STATION, UNITS 1 AND 2 (CATAWBA 1 AND 2)
DOCKET NOS. 50-413 AND 50-414 MCGUIRE NUCLEAR STATION. UNITS 1 AND 2 (MCGUIRE 1 AND 2)
DOCKET NOS. 50-369 AND 50-370
- 1. Your submittal referenced a March 7,2012, letter sent by Westinghouse Electric Company to the NRC.
- a. The final paragraph on Page 2 of 9 refers to small differences in fuel characteristics that were claimed to be compared. The paragraph also discusses confirmatory evaluations concluding that other operating characteristics were acceptable. Provide the results of this comparison for Catawba Nuclear Station, Units 1 and 2 and McGuire Nuclear Station, Units 1 and 2, including the relevant conclusions and the technical basis supporting those conclusions. For any conclusion that differences in void volume are offset by other conservatisms, list those conservatisms and provide a quantitative estimate of each conservatism, as well as a brief description of the rigor associated with that estimate.
- b. Please provide the values for the coefficients A 1 and A2 used in the PAD 4.0 + TCD U02 thermal conductivity equation.
- c. Please explain any error corrections, code improvements, and miscellaneous code cleanup between the WCOBRAITRAC and HOTSPOT code Versions used in the TCD evaluations and those used in the plant's AOR.
- d. What is the thermal conductivity model impact of code version changes in HOTSPOT?
- e. Explain the differences between the HOTSPOT and PAD thermal conductivity models and the impact of those differences. Provide graphs or other quantified descriptions that aid in explanation.
Enclosure
-2
- f. Please provide additional details concerning the steady-state ASTRUM/CQD initialization process. In particular, please explain what fuel characteristics are adjusted within the applicable models to obtain convergence among HOTSPOT, WCOBRA TRAC, and PAD4.0TCD.
- 2. Please explain how any changed design values will be verified during operation of the plant (Le. TS limits, Surveillances, etc). Also, explain what compensatory actions will be taken if a value is found to be outside of the limits assumed in the analysis.
ML1211OA194
- No significant chan e to input submitted OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRRISRXB/BC* NRR/LPL2-1/BC NRR/LPL2-1/PM NAME JThompson SFigueroa AUlses NSalgado JThompson DATE 04/23/12 04/19/12 04/16/12 04/23/12 04/23/12