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MONTHYEARONS-2014-164, Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitment 17T2014-12-19019 December 2014 Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitment 17T Project stage: Request ONS-2015-052, Response to Request for Additional Information Dated March 27, 2015, Related to the Oconee Expedited Seismic Evaluation Process (ESEP) Report2015-04-24024 April 2015 Response to Request for Additional Information Dated March 27, 2015, Related to the Oconee Expedited Seismic Evaluation Process (ESEP) Report Project stage: Response to RAI ML15344A1832016-01-0505 January 2016 Report for the Audit of Duke Energy Carolinas, LLC Interim Evaluations Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation Project stage: Other MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-18018 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Request ML16237A3542016-08-31031 August 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 Project stage: Approval 2016-01-05
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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 IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 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 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 IR 07200038/20220012022-09-12012 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200038/2022001 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition 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
[Table view] Category:Report
MONTHYEARRA-19-0245, of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2021-10-25025 October 2021 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-20-0363, Post Accident Monitoring Report 369-2020-012020-12-0101 December 2020 Post Accident Monitoring Report 369-2020-01 RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 ML19058A4162019-03-0808 March 2019 Staff Evaluation Related to Reactor Vessel Internals Inspection Plan Based on MRP-227-A ML18135A0722018-04-30030 April 2018 ANP-3658, Revision 0, Evaluation of the McGuire Units 1 and 2 Upflow Modification for 60 Years. MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2017-12-13013 December 2017 Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A ML17171A2772017-06-12012 June 2017 Selected Licensee Commitments List of Revised Effected Sections ML16363A3542016-12-0909 December 2016 54003-CALC-01, Evaluation of Risk Significance of Permanent ILRT Extension. ML16293A6662016-10-31031 October 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation (CAC Nos. MF3623 and MF3624) ML16294A2532016-10-12012 October 2016 Issue MNS Technical Specification 5.6 Rev. 2 Amend. 288/267 ML16237A3542016-08-31031 August 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2016-02-0404 February 2016 Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. ML15313A1642015-10-0808 October 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask MNS-15-072, Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days2015-09-10010 September 2015 Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days ML15246A1452015-08-11011 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15219A5662015-07-29029 July 2015 MNS-TS-5,6 - Distribution to Manual Holders - Amendment 278/258 ML15182A0672015-07-20020 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights From.. ML15141A0532015-03-0303 March 2015 Enclosure 5, Revision 0 to EP-EALCALC-MNS-1401, MNS Radiological Effluent EAL Values. MNS-15-014, LTR-PAFM-14-114-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for McGuire, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary)2015-02-28028 February 2015 LTR-PAFM-14-114-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for McGuire, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary) MNS-15-004, Annual Commitment Change Report2015-01-29029 January 2015 Annual Commitment Change Report MNS-14-097, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review.2014-12-17017 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review. ML14156A2872014-06-10010 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14114A3052014-05-0808 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14085A0652014-04-24024 April 2014 NRC Staff Review of the Documentation Provided by Duke Energy Carolinas, LLC, for McGuire Concerning Resolution of Generic LTR 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressuriz MNS-14-029, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The.2014-03-20020 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The. MNS-14-030, Annual Commitment Change Report2014-03-19019 March 2014 Annual Commitment Change Report ML13338A4062014-01-16016 January 2014 William B. McGuire Nuclear Station, Units 1 and 2 - Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13357A3502014-01-10010 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for McGuire Nuclear Station, Units 1 and 2, TAC Nos.: MF1160 and MF1161 CNS-13-005, License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology2013-11-14014 November 2013 License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology ML13338A5772013-09-30030 September 2013 Oig Semiannual Report to Congress - Fall 2013 ML13276A1272013-09-26026 September 2013 Transition to 10 CFR 50.48(c)- NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Cover Through Attachment B ML13276A1282013-09-26026 September 2013 Transition to 10 CFR 50.48(c)- NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Attachment B Through End ML13190A2742013-05-14014 May 2013 Attachment 8, Supplemental Peer Review Summary Reports for Initially Inaccessible Components ML13142A0122013-03-25025 March 2013 Annual Commitment Change Report ML13003A3402012-11-15015 November 2012 Document 1457690101-R-M-00003, Rev. 0, NTTF 2.3 Seismic Peer Review Report, Attachment 6, Unit 1 ML13190A2732012-11-15015 November 2012 Attachment 6, NTTF 2.3 Seismic Peer Review Report ML12151A4142012-05-16016 May 2012 Selected Licensee Commitments (SLC) Loes ML12153A3292012-03-31031 March 2012 Attachment 6 - Duke Energy Methodology Report DPC-NE-1007, Revision 0, Conditional Exemption of the EOC Mtc Measurement Methodology (Non-proprietary) NEI 99-04, McGuire Nuclear Station, Units 1 and 2 - Annual Commitment Change Report2012-03-29029 March 2012 McGuire Nuclear Station, Units 1 and 2 - Annual Commitment Change Report ML11279A0352011-09-21021 September 2011 Relief Request Serial # 11-MN-001, Limited Weld Examinations for Refueling Outages 1EOC20 and 2EOC19 ML11102A1312011-04-0505 April 2011 Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests and Experiments ML1023001682010-08-16016 August 2010 Units 1 & 2 - Supplement 2 to License Amendment Request for Duke Energy Cyber Security Plan ML1019304172010-05-0606 May 2010 Tritium Database Report NEI 99-04, McGuire, Units 1 & 2 - Annual Commitment Change Report2010-03-31031 March 2010 McGuire, Units 1 & 2 - Annual Commitment Change Report ML1010301792010-03-31031 March 2010 Annual Commitment Change Report ML0908202662009-03-16016 March 2009 Submittal of Facility Operating License Revision ML0904007952009-02-0404 February 2009 GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version ML0833701812008-11-0606 November 2008 Independent Spent Fuel Storage Installation (ISFSI) - 10 CFR 72.48 Summary Report ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0809305052008-03-20020 March 2008 License Amendment Request for Full Scope Implementation of the Alternative Source Term 2021-10-25
[Table view] Category:Miscellaneous
MONTHYEARRA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 ML19058A4162019-03-0808 March 2019 Staff Evaluation Related to Reactor Vessel Internals Inspection Plan Based on MRP-227-A MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2017-12-13013 December 2017 Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A ML17171A2772017-06-12012 June 2017 Selected Licensee Commitments List of Revised Effected Sections ML16293A6662016-10-31031 October 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation (CAC Nos. MF3623 and MF3624) ML16294A2532016-10-12012 October 2016 Issue MNS Technical Specification 5.6 Rev. 2 Amend. 288/267 ML16237A3542016-08-31031 August 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 ML15313A1642015-10-0808 October 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask MNS-15-072, Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days2015-09-10010 September 2015 Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days ML15246A1452015-08-11011 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15182A0672015-07-20020 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights From.. ML15141A0532015-03-0303 March 2015 Enclosure 5, Revision 0 to EP-EALCALC-MNS-1401, MNS Radiological Effluent EAL Values. MNS-15-004, Annual Commitment Change Report2015-01-29029 January 2015 Annual Commitment Change Report ML14156A2872014-06-10010 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14114A3052014-05-0808 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14085A0652014-04-24024 April 2014 NRC Staff Review of the Documentation Provided by Duke Energy Carolinas, LLC, for McGuire Concerning Resolution of Generic LTR 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressuriz MNS-14-029, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The.2014-03-20020 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The. MNS-14-030, Annual Commitment Change Report2014-03-19019 March 2014 Annual Commitment Change Report ML13338A5772013-09-30030 September 2013 Oig Semiannual Report to Congress - Fall 2013 ML13142A0122013-03-25025 March 2013 Annual Commitment Change Report ML12151A4142012-05-16016 May 2012 Selected Licensee Commitments (SLC) Loes NEI 99-04, McGuire Nuclear Station, Units 1 and 2 - Annual Commitment Change Report2012-03-29029 March 2012 McGuire Nuclear Station, Units 1 and 2 - Annual Commitment Change Report ML11279A0352011-09-21021 September 2011 Relief Request Serial # 11-MN-001, Limited Weld Examinations for Refueling Outages 1EOC20 and 2EOC19 ML11102A1312011-04-0505 April 2011 Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests and Experiments ML1023001682010-08-16016 August 2010 Units 1 & 2 - Supplement 2 to License Amendment Request for Duke Energy Cyber Security Plan ML1019304172010-05-0606 May 2010 Tritium Database Report NEI 99-04, McGuire, Units 1 & 2 - Annual Commitment Change Report2010-03-31031 March 2010 McGuire, Units 1 & 2 - Annual Commitment Change Report ML1010301792010-03-31031 March 2010 Annual Commitment Change Report ML0908202662009-03-16016 March 2009 Submittal of Facility Operating License Revision ML0833701812008-11-0606 November 2008 Independent Spent Fuel Storage Installation (ISFSI) - 10 CFR 72.48 Summary Report ML0809305052008-03-20020 March 2008 License Amendment Request for Full Scope Implementation of the Alternative Source Term ML0807301312008-02-28028 February 2008 Response to Request for Additional Information on GL-04-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML0731000852007-11-0101 November 2007 Transmittal of DPC-NE-2012-A, Dynamic Rod Worth Measurement Using Casmo/Simulate ML0708005462007-03-13013 March 2007 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML0706504222007-02-27027 February 2007 Fitness-For-Duty Program Performance Data Reports for Period July 1, 2006 Through December 31, 2006 ML0624904272006-08-28028 August 2006 Fitness-For Duty Program Performance Data Reports for Period Covering January 1, 2006 Through June 30, 2006 ML0606601682006-02-21021 February 2006 Fitness-For-Duty Program Performance Data Reports ML0528503312005-09-28028 September 2005 Core Operating Limits Report (COLR) ML0524402932005-08-24024 August 2005 Fitness-For-Duty Program Performance Data Reports ML0517902102005-06-21021 June 2005 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML0506100302005-02-18018 February 2005 Duke Energy Corporation, Fitness-For-Duty Program Performance Data Reports for Period Covering 07/01/2004 Through 12/31/2004 ML0424505372004-08-20020 August 2004 Letter Transmitting Fitness-For-Duty Program Performance Data Reports for Duke Energy Corp Oconee, McGuire and Catawba Nuclear Stations and the General Office ML0324715282003-08-22022 August 2003 Fitness-for-Duty Program Performance Data Reports ML0312100492003-04-24024 April 2003 Duke Energy Topical Report Response to Request for Additional Information Letter Dated April 4, 2003 ML0310504592003-04-0303 April 2003 Submittal of Summary Report of Evaluations Performed at McGuire Nuclear Station ML0306306812003-02-25025 February 2003 Fitness-for-Duty Program, Performance Data Reports ML0226600412002-09-12012 September 2002 Response to Request for Additional Information - Topical Report DPC-NE-1005P, Revision 0, Nuclear Design Methodology Using CASMO/4SIMULATE-3 MOX (Proprietary) ML0234503982002-08-0101 August 2002 Part 2 of 2, McGuire ASME Inservice Testing Program Revision 26 ML0234503402002-08-0101 August 2002 Part 1 of 2, McGuire ASME Inservice Testing Program Revision 26 ML0208104512002-03-15015 March 2002 Response to Requests for Additional Information in Support of Staff Review of Application to Renew Facility Operating Licenses of McGuire & Catawba Nuclear Stations, Units 1 & 2 2019-05-30
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 31, 2016 Mr. Steven D. Capps Vice President - McGuire Site Duke Energy Carolinas, LLC McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - STAFF REVIEW OF SPENT FUEL POOL EVALUATION ASSOCIATED WITH REEVALUATED SEISMIC HAZARD IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION 2.1 (CAC NOS. MF3689 AND MF3690)
Dear Mr. Capps:
The purpose of this letter is to inform Duke Energy Carolinas, LLC (Duke, the licensee) of the results of the U.S. Nuclear Regulatory Commission (NRC) staff's review of the spent fuel pool (SFP) evaluation for McGuire Nuclear Station, Units 1 and 2 (McGuire), which was submitted in response to Item 9 of Enclosure 1 of the NRC's March 12, 2012, request for information (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340), issued under Title 1O of the Code of Federal Regulations Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The NRC staff concludes that the licensee's assessment was performed consistent with the NRC endorsed SFP Evaluation Guidance Report and has provided sufficient information to complete the response to Item 9 of the 50.54(f) letter.
BACKGROUND On March 12, 2012, the NRC issued the 50.54(f) letter. The request was issued as part of implementing lessons learned from the accident at the Fukushima Dai-ichi nuclear power plant. to the 50.54(f) letter requested that licensees reevaluate seismic hazards at their sites using present-day methodologies and guidance. Enclosure 1, Item 4, of the 50.54(f) letter requested that licensees perform a comparison of the ground motion response spectrum (GMRS) and the safe shutdown earthquake (SSE). The staff's assessment of the information provided in response to Items 1-3 and 5-7 of the 50.54(f) letter is provided by letter dated July 20, 2015 (ADAMS Accession No. ML15182A067). Enclosure 1, Item 9, of the 50.54(f) letter requested that, when the GMRS exceeds the SSE in the 1 to 1O Hertz frequency range, a seismic evaluation be made of the SFP. More specifically, plants were asked to consider " ... all seismically induced failures that can lead to draining of the SFP."
S. Capps By letter dated February 23, 2016 (ADAMS Accession No. ML16055A021 ), the Nuclear Energy Institute (NEI) staff submitted Electric Power Research Institute (EPRI) Report No. 3002007148 entitled, "Seismic Evaluation Guidance: Spent Fuel Pool Integrity Evaluation" (SFP Evaluation Guidance Report). The SFP Evaluation Guidance Report provides criteria for evaluating the seismic adequacy of an SFP to the reevaluated GMRS hazard levels. This report supplements the guidance in EPRI Report 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID)" (ADAMS Accession No. ML12333A170) for plants where the GMRS peak spectral acceleration is less than or equal to 0.8g (low GMRS sites). The NRG endorsed the SFP Evaluation Guidance Report by letter dated March 17, 2016 (ADAMS Accession No. ML15350A158), as an acceptable method for licensees to use when responding to Item 9 in Enclosure 1 of the 50.54(f) letter.
By letter dated October 27, 2015 (ADAMS Accession No. ML15194A015), the NRG staff stated that SFP evaluation submittals for low GMRS sites are expected by December 31, 2016.
REVIEW OF LICENSEE SPENT FUEL POOL EVALUATION By letter dated August 18, 2016 (ADAMS Accession No. ML16236A074), Duke submitted its SFP evaluation for McGuire for NRG review. The NRG staff assessed the licensee's implementation of the SFP Evaluation Guidance Report through the completion of a reviewer checklist, which is included in Enclosure 1 to this letter.
TECHNICAL EVALUATION Section 3.0 of the SFP Evaluation Guidance Report develops SFP evaluation criteria for plants with GMRS peak spectral acceleration less than or equal to 0.8g. These criteria address SFP structural elements (e.g., floors, walls, and supports); non-structural elements (e.g.,
penetrations); seismic-induced SFP sloshing; and water loses due to heat-up and boil-off.
Section 3 also provides applicability criteria, which will enable licensees to determine if their site-specific conditions are within the bounds considered in developing the evaluation criteria this report. The staff's review consists of confirming that these SFP site-specific conditions are within the bounds considered for the evaluation criteria specified in the SFP Evaluation Guidance Report.
1.1 Spent Fuel Pool Structural Evaluation Section 3.1 of the SFP Evaluation Guidance Report provides a SFP structural evaluation approach used to demonstrate that the SFP structure is sufficiently robust against the reevaluated seismic hazard. This approach supplements the guidance in Section 7 of the SPID and followed acceptable methods used to assess the seismic capacity of structures, systems, and components (SSCs) for nuclear power plants as documented in EPRI NP-6041 1 . Table 3-2 of the SFP Evaluation Guidance Report (reproduced from Table 2.3 of EPRI NP-6041) provides the structural screening criteria to assess the SFPs and their supporting structures.
The licensee stated that it followed the SFP structural evaluation approach presented in the SFP Evaluation Guidance Report and provided site-specific data to confirm its applicability.
1 A Methodology for Assessment of Nuclear Plant Seismic Margin, Revision 1. EPRI, Palo Alto, CA: 1991. NP-6041-SL.
S. Capps The NRC staff reviewed the structural information provided, which included the requested site-specific data in Section 3.3 of the SFP Evaluation Guidance Report, and confirmed that the evaluation criteria are applicable to the McGuire site. The staff concludes that SFP SSCs were appropriately evaluated and screened based on the seismic capacity criteria in EPRI NP-6041, and that the licensee has demonstrated that the SFP structure is sufficiently robust and can withstand ground motions with peak spectral acceleration less than or equal to 0.8g.
1.2 Spent Fuel Pool Non-Structural Evaluation Section 3.2 of the SFP Evaluation Guidance Report provides criteria for evaluating the non-structural aspects of the SFP, such as piping connections, fuel gates, and anti-siphoning devices, as well as SFP sloshing and heat up and boil-off of SFP water inventory. Specifically, Table 3-4 of the SFP Evaluation Guidance Report provides a summary of the SFP non-structural evaluation criteria derived in Section 3.2, along with applicability criteria to demonstrate that site-specific conditions are suitable for applying the evaluation criteria.
The licensee stated that it followed the SFP non-structural evaluation approach presented in the guidance report and provided site-specific data to confirm its applicability. The staff reviewed the non-structural information provided, which included the requested site-specific data in Table 3-4 of the SFP Evaluation Guidance Report, and confirmed that the evaluation criteria are applicable to the McGuire site. Therefore, the staff concludes that the licensee acceptably evaluated the non-structural considerations for SSCs whose failure could lead to potential drain-down of the SFP due to a seismic event.
CONCLUSION The NRC staff reviewed Duke's SFP evaluation report. Based on its review, the NRC staff concludes that the licensee's implementation of the SFP integrity evaluation met the criteria of the SFP Evaluation Guidance Report for McGuire and therefore, Duke responded appropriately to Item 9 in Enclosure 1 of the NRC's 50.54(f) letter.
S. Capps If you have any questions, please contact me at (301) 415-1617 or via e-mail at Frankie.Vega@nrc.gov.
Sincerely, Frtd!I;: Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
Technical Review Checklist cc w/encl: Distribution via Listserv
TECHNICAL REVIEW CHECKLIST BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO SPENT FUEL POOL EVALUATIONS FOR LOW GROUND MOTION RESPONSE SPECTRUM SITES IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION 2.1 SEISMIC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 BACKGROUND By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340), the U.S. Nuclear Regulatory Commission (NRC) issued a request for information to all power reactor licensees and holders of construction permits in active or deferred status, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR), Section 50.54(f), "Conditions of License" (hereafter referred to as the "50.54(f) letter"). of the 50.54(f) letter requests addressees to reevaluate the seismic hazard at their site using present-day methods and guidance for licensing new nuclear power plants, and identify actions to address or modify, as necessary, plant components affected by the reevaluated seismic hazards. Enclosure 1, Item 4, of the 50.54(f) letter requested that licensees perform a comparison of the ground motion response spectrum (GMRS) with the safe shutdown earthquake (SSE). Enclosure 1, Item 9, requests that, when the GMRS exceeds the SSE in the 1 to 10 Hertz (Hz) frequency range, a seismic evaluation be made of the spent fuel pool (SFP).
More specifically, plants were asked to consider" ... all seismically induced failures that can lead to draining of the SFP."
Additionally, by letter dated February 23, 2016 (ADAMS Accession No. ML16055A021), the Nuclear Energy Institute (NEI) submitted Electric Power Research Institute (EPRI) Report No.
3002007148 entitled, "Seismic Evaluation Guidance: Spent Fuel Pool Integrity Evaluation" (SFP Evaluation Guidance Report). The SFP Evaluation Guidance Report supports the completion of SFP evaluations for sites with reevaluated seismic hazard exceedance in the 1 to 1O Hz frequency range. Specifically, the SFP Evaluation Guidance Report addressed those sites where the GMRS peak spectral acceleration (Sa) is less than or equal to 0.8g (low GMRS sites). The NRC endorsed the SFP Evaluation Guidance Report by letter dated March 17, 2016 (ADAMS Accession No. ML15350A158), as an acceptable method for licensees to use when responding to Item 9 in Enclosure 1 of the 50.54(f) letter. Licensee deviations from the SFP Evaluation Guidance should be discussed in their SFP evaluation submittal.
By letter dated August 18, 2016 (ADAMS Accession No. ML16236A074), Duke Energy Carolinas, LLC (Duke, the licensee) provided an SFP report in a response to Enclosure 1, Item 9, of the 50.54(f) letter, for the McGuire Nuclear Station, Units 1 and 2 (McGuire).
Enclosure
The NRC staff performed its review of the licensee's submittal to assess whether the licensee responded appropriately to Item 9 in Enclosure 1 of the 50.54(f) letter. A multidisciplinary team checked whether the site-specific parameters are within the bounds of the criteria considered in the SFP Evaluation Guidance Report, verified the SFP's seismic adequacy to withstand the reevaluated GMRS hazard levels, and confirmed that the requested information in response to Item 9 of the 50.54(f) letter.
A review checklist was used for consistency and scope. The application of this staff review is limited to the SFP evaluation as part of the seismic review of low GMRS sites as part of the Near-Term Task Force (NTTF) Recommendation 2.1.
NTTF Recommendation 2.1 Spent Fuel Pool Evaluations Technical Review Checklist for McGuire Nuclear Station, Units 1 and 2 (McGuire)
Site Parameters:
I. Site-Specific GMRS The licensee:
- Provided the site-specific GMRS consistent with the information Yes provided in the Seismic Hazard and Screening Report (SHSR), or its update, and evaluated by the staff in its staff assessment.
- Stated that the GMRS peak Sa is less than or equal to 0.8g for any Yes frequency.
Notes from the reviewer:
- 1. The NRC staff confirmed that the site-specific peak Sa= 0.67g (ADAMS Accession No. ML14098A421).
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
The NRC staff concludes:
- The site-specific GMRS peak Sa at any frequency is less than 0.8g . Yes
- The licensee's GMRS used in this evaluation is consistent with the information provided in the SHSR. Yes Structural Parameters:
II. Seismic Design of the SFP Structure The licensee:
- Specified the building housing the SFP. Yes
- Specified the plant's peak ground acceleration (PGA). Yes
- Stated that the building housing the SFP was designed using an SSE with a PGA of at least 0.1g. Yes 3
Notes from the reviewer:
- 1. The NRC staff confirmed that the SFP is housed in the auxiliary building.
- 2. The NRC staff confirmed that the auxiliary building is a Category I structure and was designed to the SSE with PGA of 0.1 Sg (Updated Final Safety Analysis Report (UFSAR Rev. 18, Section 2.5, 3.8.4).
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
The NRC staff concludes that:
- The structure housing the SFP was designed using an SSE with a Yes PGA of at least 0.1g.
Ill. Structural Load Path to the SFP The licensee:
- Provided a description of the structural load path from the Yes foundation to the SFP.
- Performed screening based on EPRI NP-6041 Table 2-3 screening Yes criteria.
Notes from the reviewer:
- 1. The staff verified the structural load path to the SFP.
- 2. The staff confirmed that the SFPs consists of four foot thick concrete shear walls and with an integrated concrete frame located on a four feet thick reinforced concrete slab, based on sound rock. (UFSAR Rev. 18, Section 3.8).
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
The NRC staff concludes that:
- Licensee appropriately described the structural load path to the Yes SFP.
- Structures were appropriately screened based on the screening criteria in EPRI NP-6041. Yes 4
IV. SFP Structure Included in the Civil Inspection Program Performed in Accordance with Maintenance Rule The licensee:
- Stated that the SFP structure is included in the Civil Inspection Yes Program performed in accordance with Maintenance Rule (10 CFR 50.65).
Notes from the reviewer:
None Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
The NRC staff concludes that:
- The SFP structure is included in the Civil Inspection Program Yes performed in accordance with Maintenance Rule (10 CFR 50.65).
Non-Structural Parameters:
V. Applicability of Piping Evaluation The licensee:
- Stated that piping attached to the SFP is evaluated to the SSE. No Notes from the reviewer:
- 1. The staff confirmed that the SFP piping system was designed and evaluated to the SSE (UFSAR Rev. 18 Section 3.1 and UFSAR Rev. 18 Table 3-4).
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
The NRC staff concludes that:
- The piping attached to the SFP is evaluated to the SSE. Yes Yes 5
- Applicability criteria specified in Table 3-4 of SFP evaluation guidance have been met.
VI. Siphoning Evaluation The licensee:
- Stated that anti-siphoning devices are installed on piping systems Yes that could lead to siphoning inventory from the SFP.
- In cases where anti-siphoning devices were not included on the applicable piping, a description documenting the evaluation No performed to determined the seismic adequacy of the piping is provided.
- Stated that the piping of the SFP cooling system cannot lead to rapid No drain down due to siphoning.
- Provided a seismic adequacy evaluation, in accordance with NP- No 6041, for cases where active siphoning devices are attached to 2" or smaller piping with extremely large extended operators.
Yes
- Stated that no anti-siphoning devices are attached to 2" or smaller piping with extremely large extended operators.
Notes from the reviewer:
- 1. UFSAR Rev. 18 Section 9.1.3 states that SFP suction connections enter near the normal level such that it cannot be lowered appreciably by siphoning. In addition, the UFSAR states that the discharge lines to the SFP have vacuum breakers to prevent siphoning.
- 2. Licensee stated that no active anti-siphoning devices are attached to 2" or smaller piping with extremely large extended operator.
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
The NRC staff concludes :
- Piping of the SFP cooling system cannot lead to rapid drain down Yes due to siphoning.
- No active anti-siphoning devices are attached to 2" or smaller piping Yes with extremely large extended operators.
- Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance have been met.
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VII. Sloshing Evaluation The licensee:
- Specified the SFP dimensions (length, width, and depth). Yes
- Specified that the SFP dimensions are bounded by the dimensions Yes specified in the report (i.e. SFP length and width <125ft.; SFP depth >36ft.).
- Stated that the peak Sa in the frequency range less than 0.3 Hz is Yes less than 0.1g.
Notes from the reviewer:
- 1. Verified the SFP dimensions (UFSAR Rev. 18 Section 3.8.4.1 ):
- SFP Length - 67 ft.
- SFP Width - 21.5 ft.
- SFP Depth - 40 ft.
- 2. The staff confirmed in the SHSR that the peak Sa in the frequency range less than 0.3 Hz is less than 0.1g (SHSR).
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
The NRC staff concludes:
- SFP dimensions are bounded by the dimensions specified in the Yes report (i.e. SFP length and width <125ft.; SFP depth >36ft.).
- The peak Sa in the frequency range less than 0.3 Hz is less than Yes 0.1g.
- Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance have been met.
VIII. Evaporation Evaluation The licensee:
- Provided the surface area of the plant's SFP . Yes
- Stated that the surface area of the plant's SFP is greater than Yes 500 ft 2.
- Provided the licensed reactor core thermal power Yes Yes
- Stated that the reactor core thermal power is less than 4,000 MWt per unit.
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Notes from the reviewer:
- 1. Surface area of pool = 1,087.6 ft 2
- 2. Reactor thermal power =3,469 MWt (Unit 1); 3469 MWt (Unit 2) (UFSAR Rev. 18, Section 1.1)
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
The NRC staff concludes:
- The surface area of the plant's SFP is greater than 500 ft 2 Yes
- The reactor core thermal power is less than 4,000 MW1 per unit. Yes
- Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance have been met.
==
Conclusions:==
The NRC staff reviewed Duke's SFP evaluation report. Based on its review, the NRC staff concludes that the licensee's implementation of the SFP integrity evaluation met the criteria of the SFP Evaluation Guidance Report for McGuire and therefore Duke responded appropriately to Item 9 in Enclosure 1 of the 50.54(f) letter.
8
ML16237A354 *via e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA NRR/JLD/JHMB/BC(A)
NAME FVega SLent GBowman (EBowman for)
DATE 08/30/2016 08/30/2016 08/30/2016 OFFICE NRR/JLD/JHMB/PM NAME FVega DATE 08/31/2016