Similar Documents at Fermi |
---|
Category:Legal-Affidavit
[Table view] Category:Letter type:NRC
MONTHYEARNRC-24-0007, Report of Changes to Quality Assurance Program for Radioactive Material Packages2024-01-12012 January 2024 Report of Changes to Quality Assurance Program for Radioactive Material Packages NRC-24-0002, Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122024-01-12012 January 2024 Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0079, Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 222023-12-14014 December 2023 Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 22 NRC-23-0077, Submittal of Revision 50 to the Fermi 2 Radiological Emergency Response Preparedness Plan2023-12-0404 December 2023 Submittal of Revision 50 to the Fermi 2 Radiological Emergency Response Preparedness Plan NRC-23-0073, Guarantee of Payment of Deferred Premiums2023-11-29029 November 2023 Guarantee of Payment of Deferred Premiums NRC-23-0071, Response to Request for Additional Information (RAI) for Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating2023-10-13013 October 2023 Response to Request for Additional Information (RAI) for Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating NRC-23-0062, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122023-10-12012 October 2023 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0068, Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating2023-09-28028 September 2023 Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating NRC-23-0064, Additional Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-09-11011 September 2023 Additional Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0057, Independent Spent Fuel Storage Installation Cask Registration2023-08-31031 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0054, Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30 20232023-08-31031 August 2023 Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30 2023 NRC-23-0056, Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval2023-08-31031 August 2023 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval NRC-23-0061, Clarification for NRC-23-0059, Response to Request for Additional Information for Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water..2023-08-30030 August 2023 Clarification for NRC-23-0059, Response to Request for Additional Information for Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water.. NRC-23-0059, Response to Request for Additional Information Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-25025 August 2023 Response to Request for Additional Information Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0060, Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-25025 August 2023 Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0053, Independent Spent Fuel Storage Installation Cask Registration2023-08-23023 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0050, Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-10010 August 2023 Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0048, Independent Spent Fuel Storage Installation Cask Registration2023-08-0101 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0049, Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-07-24024 July 2023 Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0043, Independent Spent Fuel Storage Installation, Cask Registration2023-06-27027 June 2023 Independent Spent Fuel Storage Installation, Cask Registration NRC-23-0020, License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance2023-06-13013 June 2023 License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance NRC-23-0039, Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-06-0606 June 2023 Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0030, Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval2023-06-0505 June 2023 Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval NRC-23-0029, Snubber Program for the Fourth 10-Year Testing Interval2023-06-0505 June 2023 Snubber Program for the Fourth 10-Year Testing Interval NRC-23-0037, 56542-EN 56542 - Fermi2023-05-26026 May 2023 56542-EN 56542 - Fermi NRC-23-0031, Response to NRC Request from Audit of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources -Operating,' Emergency Diesel Generator Voltage and Frequency Surveillance Requirements2023-05-16016 May 2023 Response to NRC Request from Audit of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources -Operating,' Emergency Diesel Generator Voltage and Frequency Surveillance Requirements NRC-23-0002, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122023-05-0505 May 2023 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0010, License Amendment Request to Correct Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage2023-05-0505 May 2023 License Amendment Request to Correct Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage NRC-23-0017, Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report2023-04-28028 April 2023 Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report NRC-23-0025, Submittal of 2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2023-04-28028 April 2023 Submittal of 2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-23-0018, Annual Non-Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Non-Radiological Environmental Operating Report NRC-23-0024, Levels and Sources of Property Insurance Coverage2023-04-0303 April 2023 Levels and Sources of Property Insurance Coverage NRC-23-0021, ISFSI, Decommissioning Funding Plan Update2023-03-30030 March 2023 ISFSI, Decommissioning Funding Plan Update NRC-23-0016, Decommissioning Funding Status Report2023-03-30030 March 2023 Decommissioning Funding Status Report NRC-23-0015, Decommissioning Funding Status Report for Fermi 12023-03-30030 March 2023 Decommissioning Funding Status Report for Fermi 1 NRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis2023-03-0707 March 2023 License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis NRC-22-0026, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements2022-12-16016 December 2022 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements NRC-22-0051, DTE Electric Company - Guarantee of Payment of Deferred Premiums2022-11-29029 November 2022 DTE Electric Company - Guarantee of Payment of Deferred Premiums NRC-22-0052, Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 20222022-11-17017 November 2022 Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 2022 NRC-22-0046, Submittal of Biennial Review of the Fermi 1 Safety Analysis Report2022-11-14014 November 2022 Submittal of Biennial Review of the Fermi 1 Safety Analysis Report NRC-22-0041, Evacuation Time Estimate Report2022-10-0505 October 2022 Evacuation Time Estimate Report NRC-22-0033, Enrico Fermi Atomic Power Plant, Unit 1 - Annual Report for Period Ending June 30, 20222022-08-29029 August 2022 Enrico Fermi Atomic Power Plant, Unit 1 - Annual Report for Period Ending June 30, 2022 NRC-22-0030, Inservice Inspection Summary Report2022-08-10010 August 2022 Inservice Inspection Summary Report NRC-22-0023, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2022-08-0404 August 2022 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements NRC-22-0022, Annual Non-Radiological Environmental Operating Report2022-04-29029 April 2022 Annual Non-Radiological Environmental Operating Report NRC-22-0021, Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report2022-04-29029 April 2022 Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report NRC-22-0020, Enrico Fermi Atomic Power Plant, Unit No. 1 & Fermi 2 Power Plant - 10 CFR 20.2206 Report of Individual Monitoring2022-04-28028 April 2022 Enrico Fermi Atomic Power Plant, Unit No. 1 & Fermi 2 Power Plant - 10 CFR 20.2206 Report of Individual Monitoring NRC-22-0003, Submittal of 2021 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2022-04-26026 April 2022 Submittal of 2021 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-22-0019, Submittal of the National Pollutant Discharge Elimination System Permit Application for Reissuance2022-04-0404 April 2022 Submittal of the National Pollutant Discharge Elimination System Permit Application for Reissuance NRC-22-0011, Enrico Fermi Atomic Power Plant, Unit No. 1 - Decommissioning Funding Status Report2022-03-31031 March 2022 Enrico Fermi Atomic Power Plant, Unit No. 1 - Decommissioning Funding Status Report 2024-01-12
[Table view] Category:Report
MONTHYEARNRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis2023-03-0707 March 2023 License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis NRC-21-0031, Request for Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2021-05-17017 May 2021 Request for Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic ML21055A3852021-02-0202 February 2021 3 to Updated Final Safety Analysis Report - GE Document 209A4756, Logic Symbols NRC-19-0067, Submittal of Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval2019-10-0808 October 2019 Submittal of Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval NRC-19-0018, Submittal of 2018 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2019-04-18018 April 2019 Submittal of 2018 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-18-0054, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)2018-12-14014 December 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109) NRC-18-0022, Submittal of 2017 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2018-04-19019 April 2018 Submittal of 2017 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML17305A0382017-10-16016 October 2017 Enclosures 1-6: 10CFR50.59 Evaluation Summary Report, Commitment Management Report, Revisions to Technical Requirements Manual and Technical Specifications Bases NRC-17-0052, High Frequency Seismic Confirmation Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-08-30030 August 2017 High Frequency Seismic Confirmation Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident NRC-17-0026, Submittal of 2016 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2017-04-0606 April 2017 Submittal of 2016 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML16231A4432016-08-30030 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) NRC-16-0026, Submittal of 2015 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2016-04-27027 April 2016 Submittal of 2015 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML16057A7592016-02-25025 February 2016 Comments on Advance Notice of Proposed Rulemaking on Regulatory Improvements for Decommissioning Power Reactors NRC-16-0014, Comments on the Nrc'S Safety Evaluation Report with Open Items Related to the License Renewal2016-02-25025 February 2016 Comments on the Nrc'S Safety Evaluation Report with Open Items Related to the License Renewal NRC-15-0085, Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask2015-08-19019 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask NRC-15-0043, Submittal of 2014 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2015-04-28028 April 2015 Submittal of 2014 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-14-0058, 10 CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the TN-RAM Cask Due to As-Built Discrepancies Identified by Cask Certificate Holder2014-08-13013 August 2014 10 CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the TN-RAM Cask Due to As-Built Discrepancies Identified by Cask Certificate Holder NRC-14-0061, Post Accident Monitoring Report Regarding Inoperable Instrumentation2014-08-0707 August 2014 Post Accident Monitoring Report Regarding Inoperable Instrumentation ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14093A7662014-05-0606 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 NRC-14-0030, Submittal of 2013 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2014-04-28028 April 2014 Submittal of 2013 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML13317A8942013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Fermi Unit 2, TAC No.: MF0770 NRC-13-0052, CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time2013-09-0909 September 2013 CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time NRC-13-0026, Response to Request for Additional Info Re Proposed License Amendment to Relocate Pressure and Temperature Curves to Pressure & Temperature Limits Report2013-07-0909 July 2013 Response to Request for Additional Info Re Proposed License Amendment to Relocate Pressure and Temperature Curves to Pressure & Temperature Limits Report NRC-13-0017, Submittal of 2012 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2013-04-26026 April 2013 Submittal of 2012 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-13-0013, DTE Electric Submittal of Flooding Hazard Reevaluation Report in Response to March 12, 2012 Information Request Regarding Flood Protection Evaluations2013-03-0808 March 2013 DTE Electric Submittal of Flooding Hazard Reevaluation Report in Response to March 12, 2012 Information Request Regarding Flood Protection Evaluations NRC-13-0004, Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization.2013-01-31031 January 2013 Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization. ML13043A6552013-01-31031 January 2013 Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization. NRC-12-0076, Detroit Edison'S Response to March 12, 2012 Information Request Regarding Flood Protection Walkdowns2012-11-26026 November 2012 Detroit Edison'S Response to March 12, 2012 Information Request Regarding Flood Protection Walkdowns ML12341A3642012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-43 Through C-149 ML12341A3632012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Cover Through Appendix C, Page C-42 ML12341A3612012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-336 Through C-426 ML12341A3582012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-247 Through C-335 ML12341A3652012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-150 Through C-246 ML12341A3662012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-427 Through C-529 ML12341A3672012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-530 Through C-628 ML12341A3682012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-629 Through Appendix D, Page D-7 ML12341A3692012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-8 Through Page D-108 ML12341A3702012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-109 Through Page D-211 NRC-12-0075, TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-212 Through End2012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-212 Through End NRC-12-0067, Fermi 2, Submittal of Revision 18 to the Updated Final Safety Analysis Report, 10 CFR 50.59 Evaluation Summary Report, Commitment Management Report and Revision to the Technical Requirements Manual and the Technical Specifications Bases2012-11-0505 November 2012 Fermi 2, Submittal of Revision 18 to the Updated Final Safety Analysis Report, 10 CFR 50.59 Evaluation Summary Report, Commitment Management Report and Revision to the Technical Requirements Manual and the Technical Specifications Bases ML13004A1352012-10-31031 October 2012 Enclosure 5 to NRC-12-0037, NEDO-33785, Rev 0, DTE Energy/Enrico Fermi Power Plant 2 Pressure and Temperature Limits Report Up to 24 and 32 Effective Full-Power Years. ML1203704612012-01-30030 January 2012 Theodore Smith Ltr Revised Final Report No. 1: Independent Confirmatory Survey Summary and Results for the Enrico Fermi Atomic Power Plant, Unit 1, Newport, Michigan ML1131111732011-10-27027 October 2011 Revised Final Report No. 2, Fermi Independent Confirmatory Survey Summary and Results ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants NRC-11-0036, Enrico Fermi Atomic Power Plant, Unit 1 - License Termination Plan, Revision 42011-06-29029 June 2011 Enrico Fermi Atomic Power Plant, Unit 1 - License Termination Plan, Revision 4 NRC-11-0018, Enrico Fermi Atomic Power Plant, Unit 1 - Fermi 1 Groundwater Site Conceptual Model2011-06-29029 June 2011 Enrico Fermi Atomic Power Plant, Unit 1 - Fermi 1 Groundwater Site Conceptual Model ML1029401782010-10-13013 October 2010 B. Watson Ltr. Report No. 1: Independent Confirmatory Survey Summary and Results for the Enrico Fermi: Atomic Power Plant, Unit 1, Newport, Michigan ML1011004632010-04-0707 April 2010 Technical Requirements Manual, Vol. 1, Revision 97 NRC-09-0080, Impact of Revised Unsaturated Zone Thickness on Fermi 1 Soil Dcgl Values2009-11-30030 November 2009 Impact of Revised Unsaturated Zone Thickness on Fermi 1 Soil Dcgl Values 2023-03-07
[Table view] Category:Technical
MONTHYEARNRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis2023-03-0707 March 2023 License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis ML21055A3852021-02-0202 February 2021 3 to Updated Final Safety Analysis Report - GE Document 209A4756, Logic Symbols NRC-19-0018, Submittal of 2018 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2019-04-18018 April 2019 Submittal of 2018 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-17-0052, High Frequency Seismic Confirmation Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-08-30030 August 2017 High Frequency Seismic Confirmation Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML13317A8942013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Fermi Unit 2, TAC No.: MF0770 NRC-13-0026, Response to Request for Additional Info Re Proposed License Amendment to Relocate Pressure and Temperature Curves to Pressure & Temperature Limits Report2013-07-0909 July 2013 Response to Request for Additional Info Re Proposed License Amendment to Relocate Pressure and Temperature Curves to Pressure & Temperature Limits Report ML13043A6552013-01-31031 January 2013 Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization. NRC-13-0004, Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization.2013-01-31031 January 2013 Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization. NRC-12-0076, Detroit Edison'S Response to March 12, 2012 Information Request Regarding Flood Protection Walkdowns2012-11-26026 November 2012 Detroit Edison'S Response to March 12, 2012 Information Request Regarding Flood Protection Walkdowns ML13004A1352012-10-31031 October 2012 Enclosure 5 to NRC-12-0037, NEDO-33785, Rev 0, DTE Energy/Enrico Fermi Power Plant 2 Pressure and Temperature Limits Report Up to 24 and 32 Effective Full-Power Years. ML1203704612012-01-30030 January 2012 Theodore Smith Ltr Revised Final Report No. 1: Independent Confirmatory Survey Summary and Results for the Enrico Fermi Atomic Power Plant, Unit 1, Newport, Michigan ML1131111732011-10-27027 October 2011 Revised Final Report No. 2, Fermi Independent Confirmatory Survey Summary and Results NRC-11-0018, Enrico Fermi Atomic Power Plant, Unit 1 - Fermi 1 Groundwater Site Conceptual Model2011-06-29029 June 2011 Enrico Fermi Atomic Power Plant, Unit 1 - Fermi 1 Groundwater Site Conceptual Model ML1029401782010-10-13013 October 2010 B. Watson Ltr. Report No. 1: Independent Confirmatory Survey Summary and Results for the Enrico Fermi: Atomic Power Plant, Unit 1, Newport, Michigan ML1011004632010-04-0707 April 2010 Technical Requirements Manual, Vol. 1, Revision 97 NRC-09-0064, Submittal of the Inservice Testing Program Relief Requests for Pumps and Valves - Third Ten-Year Interval2009-11-0303 November 2009 Submittal of the Inservice Testing Program Relief Requests for Pumps and Valves - Third Ten-Year Interval ML0912701872009-04-27027 April 2009 Technical Requirements Manual - Volume I ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0615903572006-05-26026 May 2006 Technical Requirements Manual - Vol. I, Revision 82 ML0512304432005-02-28028 February 2005 GE-NE-0000-0031-6254-R1-NP, DTE Energy Fermi-2 Energy Center Neutron Flux Evaluation. ML0802902312004-02-12012 February 2004 Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 NRC-03-0051, ECCS Cooling Performance Evaluation Model Report2003-05-30030 May 2003 ECCS Cooling Performance Evaluation Model Report NRC-03-0019, Additional Information Regarding Proposed License Amendment for a One - Time Deferral of Primary Containment Integrated Leak Rate Test2003-02-27027 February 2003 Additional Information Regarding Proposed License Amendment for a One - Time Deferral of Primary Containment Integrated Leak Rate Test NRC-87-0137, Submittal of Safety/Relief Valve In-Plant Testing Results1987-09-11011 September 1987 Submittal of Safety/Relief Valve In-Plant Testing Results ML19227A0771984-08-31031 August 1984 Report No. DECO-12-2191, Revision 2, Enrico Fermi Atomic Power Plant, Unit 2, Evaluation of Containment Coatings. 2023-03-07
[Table view] |
Text
Peter Dietrich Senior Vice President and Chief Nuclear Officer DTE Electric Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.6515 Email: peter.dietrich@dteenergy.com DTE March 7, 2023 10 CFR 54 NRC-23-0011 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Fermi 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Fermi 2 License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis
References:
- 1) DTE Electric Company Letter to NRC, Response to the NRC Request for Additional Information for the review of the Fermi 2 License Renewal Application - Sets 27, 28, 29, and 31, NRC-15-0044, dated April 27, 2015 (ML15118A557)
- 2) NRC Letter to EPRI, Final Proprietary Safety Evaluation for BWRVIP-25, Revision 1: BWR Vessel and Internals Project, BWR Core Plate Inspection and Flaw Evaluation Guidelines (CAC NO. MF4887; EPID L-2014-TOP-0008),
dated March 23, 2020 (ML19290G703)
- 3) NRC Letter to DTE Electric Company, FERMI 2 - REVISED RELIEF REQUEST RR-A39 FOR THE FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL (EPID L-2020-LLR-0161), dated October 15, 2021 (ML21253A010)
In accordance with Reference 1, the Fermi 2 Updated Final Safety Analysis Report (UFSAR) was revised to incorporate the updated License Renewal commitments related to Core Plate Hold-Down Bolt examinations required by the Boiling Water Reactor Vessel & Internals project (BWRVIP). In Reference 2, the NRC staff confirmed that Revision 1 of BWRVIP-25 is acceptable for referencing in licensing applications. BWRVIP-25, Revision 1 provides plant-specific criteria that must be met for applicability of a bounding analysis that justifies no core plate hold-down bolt examinations are required.
In Reference 3, the NRC accepted BWRVIP-25 Revision 1-A for use at Fermi.
Option (b) of Fermi 2 License Renewal Commitment 7c requires that for a plant-specific analysis justifying no inspections of core plate hold-down bolts, the analysis will be submitted to the NRC two years prior to the period of extended operation. The Fermi 2 plant-specific analysis is provided in . contains proprietary information as defined by 10 CFR 2.390. As the owners of the proprietary information, GE-Hitachi (GEH) and the Electric Power Research Institute (EPRI) have executed the affidavits in Enclosure 1, which identify that the enclosed proprietary information has been
USNRC NRC-23-0011 Page 2 handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure. A non-proprietary version of the documentation in Enclosure 2 is provided in .
No new commitments are made in this letter.
Should you have any questions or require additional information, please contact Mr. Eric Frank, Manager - Nuclear Licensing, at (734) 586-4772.
Sincerely, Peter Dietrich Senior Vice President and Chief Nuclear Officer
Enclosures:
- 1) GEH and EPRI Affidavits for 007N5355P
- 2) 007N5355P, Revision 0 - PROPRIETARY
- 3) 007N5355NP, Revision 0 - NON-PROPRIETARY cc:
NRC Project Manager NRC Resident Office Regional Administrator, Region III
Enclosure 1 to NRC-23-0011 Fermi NRC Docket No. 50-341 Operating License No. NPF-43 GEH and EPRI Affidavits for 007N5355P
GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, Kent E. Halac, state as follows:
(1) I am a Senior Engineer, GE-Hitachi Nuclear Energy Americas LLC (GEH), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in GEH proprietary report 007N5355P, Fermi 2 Power Plant Core Plate Bolt BWRVIP-25 Appendix I Evaluation, Revision 0, dated January 13, 2023. GEH proprietary information in 007N5355P Revision 1 is identified by a dotted underline inside double square brackets. ((This sentence is an example.{3})). GEH proprietary information in figures and large objects is identified by double square brackets before and after the object. In each case, the superscript notation {3}
refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 U.S.C. §552(b)(4), and the Trade Secrets Act, 18 U.S.C.
§1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F.2d 871 (D.C. Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F.2d 1280 (D.C. Cir. 1983).
(4) The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a and (4)b. Some examples of categories of information that fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without a license from GEH constitutes a competitive economic advantage over other companies;
- b. Information that, if used by a competitor, would reduce its expenditure of resources or improve its competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
- c. Information that reveals aspects of past, present, or future GEH customer-funded development plans and programs, resulting in potential products to GEH;
- d. Information that discloses trade secret or potentially patentable subject matter for which it may be desirable to obtain patent protection.
007N5355P Revision 0 Affidavit Page 1 of 3
GE-Hitachi Nuclear Energy Americas LLC (5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GEH, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions for proprietary or confidentiality agreements or both that provide for maintaining the information in confidence. The initial designation of this information as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in the following paragraphs (6) and (7).
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or who is the person most likely to be subject to the terms under which it was licensed to GEH.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary and/or confidentiality agreements.
(8) The information identified in paragraph (2) is classified as proprietary because it contains the detailed GEH methodology for pressure-temperature curve analysis for the GEH Boiling Water Reactor (BWR). These methods, techniques, and data along with their application to the design, modification, and analyses associated with the pressure-temperature curves were achieved at a significant cost to GEH.
The development of the evaluation processes along with the interpretation and application of the analytical results is derived from the extensive experience databases that constitute a major GEH asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GEH's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
007N5355P Revision 0 Affidavit Page 2 of 3
GE-Hitachi Nuclear Energy Americas LLC The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GEH. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. GEH's competitive advantage will be lost if its competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GEH would be lost if the information were disclosed to the public. Making such information available to competitors without there having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on this 13th day of January 2023.
Kent E. Halac Senior Engineer GE-Hitachi Nuclear Energy Americas, LLC 3901 Castle Hayne Road Wilmington, NC 28401 kent.halac@ge.com 007N5355P Revision 0 Affidavit Page 3 of 3
BWRVIP 2023-003, Attachment 1 EPf21 STEVE SWILLEY Vice President and Deputy Chief Nuclear Officer Ref. EPRI Docket No. 99902016 January 10, 2023 Document Control Desk Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Request for Withholding of the following Proprietary Information Included in:
Fermi 2 Power Plant Core Plate Bolt BWRVIP-25 Appendix I Evaluation GE Hitachi Nuclear Energy 007N5355, Revision OJanuary 2023 To Whom It May Concern:
This is a request under 10 C.F.R. §2.390(a)(4) that the U.S. Nuclear Regulatory Commission ("NRC") withhold from public disclosure the information identified in the enclosed Affidavit consisting of the proprietary information owned by Electric Power Research Institute, Inc. ("EPRI") identified above in the attached report. Proprietary and non-proprietary versions of the Report and the Affidavit in support of this request are enclosed.
EPRI desires to disclose the Proprietary Information in confidence to assist the NRC review of the enclosed submittal to the NRC by DTE Energy. The Proprietary Information is not to be divulged to anyone outside of the NRC or to any of its contractors, nor shall any copies be made of the Proprietary Information provided herein. EPRI welcomes any discussions and/or questions relating to the information enclosed. In case the NRC rejects this affidavit for protection for any reason, EPRI requests that the NRC contact the EPRI project manager and EPRI Order Center (vvaughn@epri.com) with an offer of an opportunity for EPRI to withdraw this submittal.
If you have any questions about the legal aspects of this request for withholding, please do not hesitate to contact me.
Questions on the content of the Report should be directed to Nathan Palm of EPRI at (724) 288-4043.
Sincerely, Attachment(s)
Together ... Shaping the Future of Energy 1300 West W.T. Harris Boulevard, Charlotte, NC 28262-8550 USA
AFFIDAVIT
Subject:
Request for Withholding of the Following Proprietary Information Included In:
Fermi 2 Power Plant Core Plate Bolt BWRVIP-25 Appendix I Evaluation GE Hitachi Nuclear Energy 007N5355, Revision OJanuary 2023 I, Steven Swilley, being duly sworn, depose and state as follows:
I am the Vice President and Deputy Chief Nuclear Officer at Electric Power Research Institute, Inc., whose principal office is located at 3420 Hillview Avenue, Palo Alto, California ("EPRI"), and I have been specifically delegated responsibility for the above-listed Report which contains EPRI Proprietary Information that is sought under this Affidavit to be withheld "Proprietary Information". I am authorized to apply to the U.S. Nuclear Regulatory Commission C'NRC")
for the withholding of the Proprietary information on behalf of EPRI.
EPRI Proprietary Information is identified in the above referenced report with text inside double brackets.
Examples of such identification is as follows:
((This sentence is an example{El))
Tables containing EPRI Proprietary Information are identified with double brackets before and after the object.
In each case the superscript notation [El refers to this affidavit and all the bases included below, which provide the reasons for the proprietary determination.
EPRI requests that the Proprietary Information be withheld from the public on the following bases:
Withholding Based Upon Privileged and Confidential Trade Secrets or Commercial or Financial Information (see e.g. 10 C.F.R. §2.390(a){4)):
- a. The Proprietary Information is owned by EPRI and has been held in confidence by EPRI. All entities accepting copies of the Proprietary Information do so subject to written agreements imposing an obligation upon the recipient to maintain the confidentiality of the Proprietary Information. The Proprietary Information is disclosed only to parties who agree, in writing, to preserve the confidentiality thereof.
- b. EPRI considers the Proprietary Information contained therein to constitute trade secrets of EPRI. As such, EPRI holds the information in confidence, and disclosure thereof is strictly limited to individuals and entities who have agreed, in writing, to maintain the confidentiality of the Information. EPRI made a substantial economic investment to develop the Proprietary Information, and, by prohibiting public disclosure, EPRI derives an economic benefit in the form of licensing royalties and other additional fees from the confidential nature of the Proprietary Information. If the Proprietary Information were publicly available to consultants and/or other businesses providing services in the electric and/or nuclear power industry, they would be able to use the Proprietary Information for their own commercial benefit
and profit and without expending substantial economic resources required of EPRI to develop the Proprietary information.
- c. EPRl's classification of the Proprietary Information as trade secrets is justified by the Uniform Trade Secrets Act. which California adopted in 1984 and a version of which has been adopted by over forty states. The California Uniform Trade Secrets Act, California Civil Code §§3426 - 3426.11, defines a "trade secret" as follows:
'Trade secret' means information, including a formula, pattern, compilation, program device, method, technique, or process, that:
(1) Derives independent economic value, actual or potential, from not being generally known to the public or to other persons who can obtain economic value from its disclosure or use; and
- 2) Is the subject of efforts that are reasonable under the circumstances to maintain its secrecy."
- d. The Proprietary Information contained therein are not generally known or available to the public. EPRI developed the Information only after making a determination that the Proprietary Information was not available from public sources. EPRI made a substantial investment of both money and employee hours in the development of the Proprietary Information. EPRI was required to devote these resources and effort to derive the Proprietary Information.
As a result of such effort and cost, both in terms of dollars spent and dedicated employee time, the Proprietar1 Information is highly valuable to EPRI.
- e. A public disclosure of the Proprietary Information would be highly likely to cause substantial harm to EPRl's competitive position and the ability of EPRI to license the Proprietary Information both domestically and internationally.
The Proprietary Information and Report can only be acquired and/or duplicated by others using an equivalent investment of time and effort.
I have read the foregoing, and the matters stated herein are true and correct to the best of my knowledge, information, and belief. I make this affidavit under penalty of perjury under the laws of the United States of America and the laws of the State of North Carolina.
Executed at 1300 W WT Harris Blvd, Charlotte, NC being the premises and place of business of Electric Power Research Institute, Inc.
Date: _*_5_c_,"' __\_\~I-~~--()_;i_s _ _ _ _ __
/ __,_ .---?*
Steven Swilley
(State of North Carolina)
(County of Mecklenburg)
Enclosure 3 to NRC-23-0011 Fermi NRC Docket No. 50-341 Operating License No. NPF-43 007N5355NP, Revision 0 - NON-PROPRIETARY
e HITACHI GE Hitachi Nuclear Energy 007N5355NP Revision 0 January 2023 Non-Proprietary Information Fermi 2 Power Plant Core Plate Bolt BWRVIP-25 Appendix I Evaluation Copyright 2023 GE-Hitachi Nuclear Energy Americas LLC, All Rights Reserved
INFORMATION NOTICE This is a non-proprietary version of the document 007N5355P Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( )).
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT Please Read Carefully The design, engineering, and other information contained in this document are in accordance with the contract between DTE Energy Electric Company and GEH, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone other than DTE Energy Electric Company or for any purpose other than that for which it is furnished by GEH is not authorized; and with respect to any unauthorized use, GEH makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.
2
007N5355NP Revision 0 Non-Proprieta1y Infonnation REVISION
SUMMARY
Revision Revision Summary 0 Initial Release 3
007N5355NP Revision 0 Non-Proprietary Information TABLE OF CONTENTS
1.0 INTRODUCTION
.............................................................................................................................. 5 2.0 BWRVIP-25 APPENDIX I METHODOLOGY FOR CORE PLATE BOLTS ................................. 6 3.0 FERMI 2 CORE PLATE BOLT EVALUATION.............................................................................. 7 3.1 Fermi 2 Core Plate Design and Load Combination ................................................................. 7 3.2 SC 11-05 Considerations ......................................................................................................... 7 3.3 Fermi 2 Core Plate Vertical Loads ........................................................................................... 7 3.4 Fermi 2 Core Plate Horizontal Load and Required Number of Core Plate Bolts .................... 8
4.0 CONCLUSION
S ................................................................................................................................ 9 5.0 ACRONYMS ................................................................................................................................... 10
6.0 REFERENCES
................................................................................................................................. 11 LIST OF TABLES Table 1 Fermi 2 Vertical Loads vs. Those Analyzed in BWRVIP-25 Appendix I Table 8-3 ........7 4
007N5355NP Revision 0 Non-Proprietary Information
1.0 INTRODUCTION
Fermi 2 core plate bolts are evaluated for eliminating or reducing the inspection requirements using the methodology in the BWRVIP-25 Appendix I (Reference 1). The current licensed operating conditions analyzed in the Thermal Power Optimization Safety Analysis Report (Reference 2) are applied with GNF3 fuel and 24 month fuel cycle in the evaluation. The fluence for 60 years of plant life is considered in the analysis. Consistent with GNF3 RPV internals evaluations, Safety Communication (SC) 11-07 (Reference 3) is not considered for the core plate bolt evaluation.
5
007N5355NP Revision 0 Non-Proprietary Information 2.0 BWRVIP-25 APPENDIX I METHODOLOGY FOR CORE PLATE BOLTS The analysis in BWRVIP-25 Appendix I (Reference 1) was based on the Service Level D (Faulted condition) loading and allowable limits because of the dominating effect of horizontal SSE (a Faulted condition seismic load) on the displacement and ASME Code stress limits. In BWRVIP-25 Appendix I analysis for each category of core plate/bolt design, several horizontal loads were evaluated to determine the corresponding required number of bolts with fixed vertical loads, which are intended to be bounding. These fixed vertical loads are listed in Table 8-3 of BWRVIP-25 Appendix I. In order to apply the results in BWRVIP-25 Appendix I to a specific plant, the plant specific vertical loads and accumulated neutron fluence need to be bounded by those in Table 8-3. Otherwise, the BWRVIP-25 Appendix I results should not be used and additional plant-specific analysis for the core plate bolts should be considered. In addition, the conditions of SC 11-05 (Reference 5) are met.
6
007N5355NP Revision 0 Non-Proprietary Information 3.0 FERMI 2 CORE PLATE BOLT EVALUATION 3.1 Fermi 2 Core Plate Design and Load Combination Fermi 2 is a BWR/4 Mark I containment plant. Fermi 2 core plate design is classified as Category 1 with 34 core plate bolts as listed in BWRVIP-25 Appendix I (Reference 1). Fermi 2 is one of the Mark I Exception plants (Reference 4) which is not a New Loads or Old Loads plant. The applicable dynamic loads for the core plate include Annulus Pressurization (AP) and Fuel Lift in addition to the seismic. The limiting load combination for Fermi 2 core plate in Service Level D is (Table 13-5 of Reference 4) as follows.
(( ))
The (( )) are vertical loads. SSE has both vertical and horizontal components.
AP is a horizontal load. Thermal stresses of core plate are insignificant because there are no thermal gradients on the core plate. Furthermore, it is not required to include the thermal stress in Faulted condition for the ASME code evaluation. Therefore, thermal stresses are not included in BWRVIP-25 Appendix I and design basis calculations in Faulted condition.
3.2 SC 11-05 Considerations BWRVIP-25 Appendix I set the acceptable core plate horizontal displacement limit to ((
)) inch with the considerations of conditions identified in SC 11-05 (Reference 5). This displacement limit accounts for additional control-blade-to-fuel-channel friction due to the possibility of existing channel bow, monitored by SC 11-05. For Fermi 2, one of the plants that SC 11-05 is applicable, the conditions of SC 11-05 are met for the core plate bolt evaluation because SC 11-05 has been considered in the displacement limit and the channel bow is monitored.
3.3 Fermi 2 Core Plate Vertical Loads The vertical loads are summarized in the following table. Fermi 2 specific vertical loads are found to be within the analyzed conditions of BWRVIP-25 Appendix I. The Fermi 2 fluence in the table is the maximum value at the top of the core plate bolts among all azimuthal locations. The Fermi 2 fluence and core plate bolt torque also meet the analyzed limits. Therefore, the Preload Final Multiplier of (( )) in Table 6-1 of BWRVIP-25 Appendix I applies to Fermi 2.
Table 1 Fermi 2 Vertical Loads vs. Those Analyzed in BWRVIP-25 Appendix I Table 8-3 Combined Vertical Core Plate DP Core Plate Bolt Fluence*
Plant Load (kips) (psid) Torque (n/cm2)
(With Fuel Lift) (With Fuel Lift) (ft-lbf)
BWRVIP-25 (( ))
Fermi 2 (( ))
(*) Fermi 2 peak fluence for 60 years of plant life (52 Effective Full Power Year) is with GNF3 fuel and 24 month fuel cycle. The methodology of fluence calculation is documented in the New Fuel Introduction (NFI) Report.
7
007N5355NP Revision 0 Non-Proprietary Information 3.4 Fermi 2 Core Plate Horizontal Load and Required Number of Core Plate Bolts The combined horizontal load on Fermi 2 core plate is (( )) kips. Per the Table 9-2 of BWRVIP-25 Appendix I, (( )) bolts are needed if the horizontal load is (( )) kips. The load of 455 kips is the minimum combined horizontal load analyzed in BWRVIP-25 Appendix I for category 1 core plate plants with FLL in their design bases. With (( )) kips of horizontal load for Fermi 2 core plate, the number of core plate bolts needed are less than (( ))
out of the total of 34 bolts. However, the exact number of bolts needed cannot be determined because interpolation or extrapolation of the results is not allowed as stated in Section 9 of BWRVIP-25 Appendix I (Reference 1). There is considerable margin in terms of number of core plate bolts needed versus available number of bolts for the horizontal load of (( )) kips.
Following the Figure 9-9 Applicability Flow Chart in BWRVIP-25 Appendix I, this evaluation justifies no additional inspections of core plate bolts for Fermi 2.
8
007N5355NP Revision 0 Non-Proprietary Information
4.0 CONCLUSION
S Fermi 2 core plate design is category 1 with 34 core plate bolts as analyzed in BWRVIP-25 Appendix I with FLL considered in the design basis.
- The loads and conditions for Fermi 2 core plate with licensed/analyzed operating conditions, including GNF3 fuel and 24 month fuel cycle, are bounded by those analyzed in BWRVIP-25 Appendix I.
- Therefore, the results of BWRVIP-25 Appendix I can be applied to Fermi 2 core plate bolts.
- The number of core plate bolts needed for Fermi 2 are less than (( )) out of total of 34 bolts.
- Following the Figure 9-9 Applicability Flow Chart in BWRVIP-25 Appendix I, this evaluation justifies no additional inspections of core plate bolts for Fermi 2.
9
007N5355NP Revision 0 Non-Proprietary Information 5.0 ACRONYMS Acronym Explanation AP Faulted P AP Annulus Pressurization ASME American Society of Mechanical Engineers BWRVIP Boiling Water Reactor Vessel and Internals Project P Delta Pressure EPRI Electric Power Research Institute FLL Fuel Lift Load kips Kilo pounds NL Normal load (such as Dead Weight)
RPV Reactor Pressure Vessel SC Safety Communication SSE Safe Shutdown Earthquake THF Thermal Load at Faulted Condition 10
007N5355NP Revision 0 Non-Proprietary Information
6.0 REFERENCES
- 1. BWRVIP-25, Revision 1-A: BWR Vessel and Internals Project, BWR Core Plate Inspection and Flaw Evaluation Guidelines, EPRI, September 2020.
- 2. NEDC-33578P, Safety Analysis Report for Fermi Generating Station Unit-2 Thermal Power Optimization, January 2013.
- 3. SC 11-07 Rev.0, Impact of Inertial Loading and Potential New Load Combination fromRecirculation Suction Line Break Acoustic Loads, June 2013.
- 4. BWRVIP-303, Revision 0: BWR Vessel and Internals Project, Load Definitions and Combinations for Use in BWR Internals Repair/Replacement and Flaw Evaluations, EPRI, January 2019.
- 5. SC 11-05 Revision 2, Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance, December 2013.
11