Letter Sequence Request |
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EPID:L-2019-LLR-0098, Submittal of Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval (Approved, Closed) |
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Similar Documents at Fermi |
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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:Miscellaneous
MONTHYEARNRC-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 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-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-17-0026, 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 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 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-13-0017, 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 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 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 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 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 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 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 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 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 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 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 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 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 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-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 ML0929604282009-10-23023 October 2009 Independent Spent Fuel Storage Installation Control of Heavy Loads Inspection Document Request NRC-09-0025, Submittal of 2008 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2009-04-17017 April 2009 Submittal of 2008 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML0818304092008-06-30030 June 2008 GE-NE-0000-0047-1716-R1, DTE Energy Enrico Fermi 2, Safer/Gestr Loss-of-Coolant Accident Analysis for GE11 Fuel. ML0818304112008-06-30030 June 2008 GE-NE-0000-0030-6565-R1, DTE Energy, Enrico Fermi 2, Safer/Gestr Loss-of-Coolant Accident Analysis for GE14 Fuel NRC-08-0035, Submittal of 2007 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2008-04-28028 April 2008 Submittal of 2007 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML0723403152007-08-22022 August 2007 Staff Evaluation of BWRVIP Response to Nuclear Regulatory Commission Safety Evaluation of BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (BWRVIP-14-A) NRC-07-0029, Response to Request for Additional Information Regarding License Amendment Request for Extension of Completion Time for an Inoperable Emergency Diesel Generator2007-05-23023 May 2007 Response to Request for Additional Information Regarding License Amendment Request for Extension of Completion Time for an Inoperable Emergency Diesel Generator NRC-06-0058, Groundwater Protection - Data Collection Questionnaire2006-07-28028 July 2006 Groundwater Protection - Data Collection Questionnaire ML0414602392004-05-17017 May 2004 Rev 38 to Tlcomp, Restricted Engineered Components List. ML0626304082004-03-0101 March 2004 PSEG Nuclear, LLC Salem/Hope Creek Safety Culture Assessment ML0318903172003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-For-Duty Enhancements for Nuclear Security Force Personnel for Fermi 2 NRC-03-0018, Submittal of Changes to Emergency Response Data System for Integrated Plant Computer System Replacement2003-03-25025 March 2003 Submittal of Changes to Emergency Response Data System for Integrated Plant Computer System Replacement NRC-02-0013, Annual Report for 20012002-04-16016 April 2002 Annual Report for 2001 2021-05-17
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Peter Dietrich Senior Vice President and Chief Nuclear Officer DTE Energy Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.4153 Fax: 734.586.1431 Email: peter.dietrich@dteenergy.com October 8, 2019 10 CFR 50.55a NRC-19-0067 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:
Submittal of Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval
References:
- 1) DTE Electric Letter to NRC, Submittal of Valve Relief Requests for the Inservice Testing Program Fourth 10-Year Interval, NRC-19-0047, dated June 14, 2019 (ML19165A134)
- 2) NRC Letter to DTE, Supplemental Information Needed for Acceptance of Requested Licensing Action Re: Submittal of Valve Relief Requests for the Inservice Testing Program Fourth 10-Year Interval (EPID L-2019-LLR-0056 and L-2019-LLR 0058), dated July 30, 2019 (ML19197A287)
- 3) DTE Electric Letter to NRC, Withdrawal of the Inservice Testing Program Relief Requests VRR-004 and VRR-007 for the Fourth Ten-Year Interval, NRC-19-0061, dated August 7, 2019 (ML19219A104)
- 4) NRC Letter to DTE, Withdrawal of Requested Licensing Action Re:
Submittal of Valve Relief Requests for the Inservice Testing Program Fourth 10-Year Interval (EPID-L-2019-LLR-0056 and L-2019-LLR-0058),
August 14, 2019 (ML19219A775)
In Reference 1, DTE Electric Company (DTE) submitted relief requests VRR-004 and VRR-007 for the Fermi 2 Inservice Testing (IST) Program fourth 10-year interval. The Fermi 2 IST Program fourth 10-year interval begins on February 17, 2020 and ends on February 16, 2030.
By letter from Ms. Sujata Goetz dated July 30, 2019 (Reference 2), the NRC indicated that additional information was necessary to begin detailed technical review of relief requests VRR-004 and VRR-007. A clarification call was held between DTE and the NRC staff on July 24, 2019 to discuss and clarify the information requested by the NRC staff in Reference 2.
USNRC NRC-19-0067 Page 2 Following the clarification call and feedback from the NRC staff, DTE further reviewed the requirements of ASME OM Code, 2012 Edition, Subsection ISTC-3700, "Position Verification Testing," as well as 10 CFR 50.55a(b)(3)(xi), "OM condition: Valve Position Indication." The testing activities associated with each of the ASME code components (i.e. valves) listed in VRR-004 and VRR-007 were reviewed and DTE has determined that existing activities performed at Fermi 2 would meet the requirements for some of the valves without the need for relief under 10 CFR 50.55a(z). For the subset of valves that remained in scope and where relief was still required, it was determined that additional information would need to be gathered to address the specific NRC requests in Reference 2. For these reasons, DTE submitted a letter to withdraw VRR-004 and VRR-007 (Reference 3) so that a consolidated relief request could be prepared and submitted to the NRC at a later date.
In Reference 4, the NRC acknowledged the DTE request to withdraw VRR-004 and VRR-007.
The NRC also noted that if DTE were to re-submit the requests, the revised relief requests would need to address the items listed in Reference 4, which were the same as those in Reference 2.
DTE has now prepared a revised relief request, VRR-004 Revision 1. The revised relief request consolidates the information previously contained in relief requests VRR-004 and VRR-007, reduces the scope of ASME code components in the relief request, and addresses the information requested by the NRC in References 2 and 4. The revised relief request is enclosed.
DTE requests NRC approval of the relief request VRR-004 Revision 1 by March 16, 2020 to support planned testing during the next refuel outage scheduled in the spring of 2020.
No new commitments are being made in this submittal.
Should you have any questions or require additional information, please contact Mr. Jason R.
Haas, Manager - Nuclear Licensing, at (734) 586-1769.
Sincerely, Paul Fessler, Senior Vice President Nuclear Generation, for Peter Dietrich, Senior Vice President and CNO
Enclosure:
Revised Relief Request VRR-004 for the IST Fourth 10-Year Interval
USNRC NRC-19-0067 Page 3 cc: NRC Project Manager NRC Resident Office Regional Administrator, Region III Michigan Department of Environment, Great Lakes, and Energy
Enclosure 1 to NRC-19-0067 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Revised Relief Request VRR-004 for the IST Fourth 10-Year Interval
Enclosure to NRC-19-0067 Page 1 10 CFR 50.55a Relief Request VRR-004, Revision 1 Relief to Confirm Obturator Position at Seat Leakage Testing Frequency Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1)
Alternative Provides Acceptable Level of Quality and Safety
- 1. ASME Code Component(s) Affected The ASME code components affected by this relief request are the 47 valves listed in Attachment 1 to this Enclosure.
2. Applicable Code Edition and Addenda
ASME OM Code 2012 Edition, No Addenda 10 CFR 50.55a(b)(3)(xi), OM condition: Valve Position Indication.
3. Applicable Code Requirement
10 CFR 50.55a(b)(3)(xi) states:
OM condition: Valve Position Indication. When implementing ASME OM Code, 2012 Edition, Subsection ISTC-3700, Position Verification Testing, licensees shall verify that valve operation is accurately indicated by supplementing valve position indicating lights with other indications, such as flow meters or other suitable instrumentation, to provide assurance of proper obturator position.
ASME OM Code, 2012 Edition, Subsection ISTC-3700, Position Verification Testing, states:
Valves with remote position indicators shall be observed locally at least once every 2 yr to verify that valve operation is accurately indicated. Where practicable, this local position indication observation should be supplemented by other indications such as use of flow meters or other suitable instrumentation to verify obturator position. These observations need not be concurrent. Where local observation is not possible, other indications shall be used for verification of valve operation.
Position verification for active MOVs shall be tested in accordance with Mandatory Appendix III of this Division.
ASME OM Code, 2012 Edition, Mandatory Appendix III, Preservice and Inservice Testing of Active Electric Motor Operated Valve Assemblies in Light-Water Reactor Power Plants, Subsection III-3300, paragraph (e) states:
Enclosure to NRC-19-0067 Page 2 10 CFR 50.55a Relief Request VRR-004, Revision 1 Relief to Confirm Obturator Position at Seat Leakage Testing Frequency Remote position indication shall be verified locally during inservice testing or maintenance activities.
ASME OM Code, 2012 Edition, Mandatory Appendix III, Subsection III-3310 states:
The inservice test interval determination shall include the following:
(a) The inservice test interval shall be determined in accordance with para. III-6440.
(b) If insufficient data exist to determine the inservice test interval in accordance with para. III-6400, then MOV inservice testing shall be conducted every two refueling cycles or 3 yr (whichever is longer) until sufficient data exist, from an applicable MOV or MOV group, to justify a longer inservice test interval.
(c) The maximum inservice test interval shall not exceed 10 yr. MOV inservice tests conducted per para. III-3400 may be used to satisfy this requirement.
4. Reason for Request
Pursuant to 10 CFR 50.55a, Codes and Standards, paragraph (z)(1), relief is requested from the requirements of ASME OM Code Subsections ISTC-3700 and III-3310 and 10 CFR 50.55a(b)(3)(xi), for the subject valves listed in Attachment 1. The proposed alternative is to perform the required verification of obturator position using seat leakage testing at the seat leakage testing frequency interval. The basis of the relief request is that the proposed alternative will provide an acceptable level of quality and safety.
For the purpose of this relief request, DTE will utilize the phrase obturator verification to denote the supplementing of valve position indicating lights with other conditions to confirm proper obturator position as described in ISTC-3700 and 10 CFR 50.55a(b)(3)(xi).
NRC Information Notice (IN) 2012-14, Motor-Operated Valve Inoperable Due to Stem-Disc Separation, (Reference 1) highlighted the need to supplement valve position indicating lights with other indications to provide assurance of proper obturator position. ASME Code, 2012 Edition, included requirements for the use of other indications to supplement position indicating lights in Subsection ISTC-3700 as practicable. At Fermi 2, obturator verification will be performed in both the open and closed directions to comply with 10 CFR 50.55a(b)(3)(xi).
A review of all In-Service Testing (IST) Program valves equipped with remote position indication was performed to identify a method to provide reasonable assurance of proper obturator position. The use of process parameters such as flow or pressure, seat leakage testing, and existing diagnostic testing were all considered as methods. For all the valves listed in Attachment 1, confirmation of obturator position in conjunction with seat leakage testing was identified as the most practical or only method of obturator verification. The seat leakage testing associated with the valves in Attachment 1 is currently performed at a
Enclosure to NRC-19-0067 Page 3 10 CFR 50.55a Relief Request VRR-004, Revision 1 Relief to Confirm Obturator Position at Seat Leakage Testing Frequency frequency that is different than that prescribed in Subsections ISTC-3700 and III-3310.
Combining the obturator verification with the seat leakage testing and performing them together will reduce labor and overall dose while also providing a highly reliable means to demonstrate proper obturator position.
DTE is requesting to perform obturator verification for certain valves as required by ISTC-3700 and 10 CFR 50.55a(b)(3)(xi) at a frequency commensurate with the 10 CFR 50 Appendix J, Option B performance-based leakage testing program at Fermi 2 instead of the two-year frequency required by ISTC-3700. This request applies to all the valves listed in Attachment 1, with two variations as listed below:
- 1) For one set of valves in Attachment 1 (i.e., two valves total), obturator verification as required by ISTC-3700 and 10 CFR 50.55a(b)(3)(xi) will be performed at a frequency commensurate with the seat leakage testing frequency referenced in NEI 13-02, Industry Guidance for Compliance with Order EA-13-109, (Reference 2) instead of the two-year frequency required by ISTC-3700.
- 2) For active motor operated valves in Attachment 1, position indication testing requirements are identified in Mandatory Appendix III as described in ISTC-3700.
Per Subsections III-3300 and III-3310, position indication testing is performed with inservice testing, which itself is performed at a variable frequency. The minimum frequency specified in Subsection III-3310 for inservice testing is every two refueling cycles or 3 years (whichever is longer, although the two options are currently equal for Fermi 2 given the current 18 month refueling cycles). As a result, the requested relief from the code required frequency for obturator verification of active motor operated valves is from the three-year minimum frequency in Mandatory Appendix III Subsection 3310 rather than from the two-year frequency in ISTC-3700. Seat leakage testing, at the Appendix J frequency, will also be utilized as the method for performing obturator verification of these Mandatory Appendix III valves.
- 5. Proposed Alternative and Basis for Use The proposed alternative is to perform the required verification of obturator position using seat leakage testing at the seat leakage testing frequency interval specified by either 10 CFR 50 Appendix J or the guidance in NEI 13-02 as described below.
For most of the valves in Attachment 1, the proposed alternative is to supplement valve position indication to confirm obturator position during the existing seat leakage testing performed in accordance with 10 CFR 50 Appendix J. The frequency of this obturator verification will be aligned to the frequency of the seat leakage testing frequency commensurate with the 10 CFR 50 Appendix J, Option B performance-based leakage testing program at Fermi 2, which incorporates NEI 94-01, Revision 3-A (ADAMS Accession No.
Enclosure to NRC-19-0067 Page 4 10 CFR 50.55a Relief Request VRR-004, Revision 1 Relief to Confirm Obturator Position at Seat Leakage Testing Frequency ML12221A202), and the conditions and limitations specified in NEI 94-01, Revision 2-A (ML100620847).
In 1996, Fermi 2 received approval of License Amendment 108 (ADAMS Accession No. ML020730597) to implement Option B of the 10 CFR 50 Appendix J Program. This program permits the extension of the Appendix J seat leakage testing to a frequency corresponding to the specific valve performance. Valves whose leakage test results indicate good performance may have their interval of testing increased based on these test results.
On March 9, 2017, Fermi 2 received approval of License Amendment No. 205 (ADAMS Accession No. ML16351A460) to implement NEI 94-01, Revision 3-A and the conditions and limitations specified in NEI 94-01, Revision 2-A, to implement the performance-based leakage-testing program in accordance with 10 CFR 50 Appendix J, Option B. This License Amendment increased the containment isolation valves leakage test intervals (i.e., Type C tests) from 60 months to 75 months.
The Fermi 2 program which implements Appendix J, Option B requires individual containment isolation valves to pass three successful seat leakage tests before they can be placed on extended seat leakage testing frequency.
In addition, for one set of valves in Attachment 1 (i.e., two valves total), valve position indication will be supplemented to confirm obturator position by utilizing the existing seat leakage testing performed in accordance with the NEI 13-02, Industry Guidance for Compliance with Order EA-13-109. Valves T4600F420 & T4600F421 are the Torus Hardened Vent Isolation Valves which are credited for compliance with NRC Order EA 109. Section 6.2 of NEI 13-02 identifies that leak rate testing of hardened containment vent system valves should be performed at a frequency of once every three operating cycles.
Consistent with the NEI 13-02 guidance, valves T4600F420 & T4600F421 will be leak tested at a maximum frequency of every three operating cycles. Therefore, the obturator verification of valves T4600F420 & T4600F421 will be performed in conjunction with this seat leakage testing at a maximum frequency of every three operating cycles.
To support the use of seat leakage testing at the Appendix J or NEI 13-02 frequency, Attachment 1 identifies testing or maintenance activities, such as position indication testing, stroke timing, actuator maintenance, and valve diagnostic testing, that will also provide reasonable assurance of overall valve health including indication. Note that this relief request is not proposing to alter the frequency of position indication testing itself, as required by Subsection ISTC-3700 (or Subsection III-3300(e) for active motor operated valves).
Therefore, position indication testing of the valves in Attachment 1 will continue to be performed at a frequency of two years in accordance with ISTC-3700 (or at the frequency in accordance with Subsection III-3310 for active motor operated valves).
Enclosure to NRC-19-0067 Page 5 10 CFR 50.55a Relief Request VRR-004, Revision 1 Relief to Confirm Obturator Position at Seat Leakage Testing Frequency For all the valves in Attachment 1, seat leakage testing is the most practical or only method to validate the obturator is in the proper open or closed position as required. Seat leakage testing would identify problems with obturator integrity. Any identified issues would then be repaired using the Corrective Action Program.
In conclusion, the ability to detect degradation and ensure the operational readiness of the subject valves to perform their intended function is not jeopardized by performing the obturator verification at the same frequency as the seat leakage testing specified by 10 CFR 50 Appendix J or the guidance in NEI 13-02. This frequency of testing provides reasonable assurance of the operational readiness of the subject valves, as well as that the indicating system accurately reflects the valve disc position. Thus, the proposed alternative provides an acceptable level of quality and safety.
- 6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire fourth 10-year interval. The fourth interval begins on February 17, 2020 and ends on February 16, 2030.
- 7. Precedent No precedent was identified for this relief request.
- 8. References
- 1. NRC Information Notice (IN) 2012-14, Motor-Operated Valve Inoperable Due to Stem-Disc Separation, dated July 24, 2012 (ML12150A046).
- 2. NEI 13-02, Industry Guidance for Compliance with Order EA-13-109: BWR Mark I &
II Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, Revision 1, dated April 2015 (ML15120A360).
- 9. Attachments
- 1. Affected Components and Bases for Using Seat Leakage Testing to Confirm Obturator Position [5 pages]
ATTACHMENT 1 TO ENCLOSURE 1 OF NRC-19-0067 (VRR-004, Revision 1)
Affected Components and Bases for Using Seat Leakage Testing to Confirm Obturator Position Valve ID Code OM Valve Valve Actuator IST Program Safety Method of Obturator Verification / Relief Testing /
Valve Description Function of Valve (PIS) Nos. Class Category Type* Type* Classification Direction Requested Maintenance**
Verification of obturator in the open position will be performed using feedwater flow and at a frequency in accordance with the ASME OM code Subsection ISTC-3700 and 10 CFR 50.55a(b)(3)(xi). Therefore, no relief is required These check valves open to allow feedwater flow for the open position.
B2100F076A Feedwater Supply Check to the reactor pressure vessel (RPV) during power 1 A/C CHK AO Active Closed 1, 2, & 4 B2100F076B Air Operated Valves operation. The safety function is to close to There is no practical method to validate valve isolate primary containment. closure other than seat leakage testing.
Verification of obturator in the closed position will be performed during seat leakage testing.
Relief is requested to align the frequency of the closed position verification to the Appendix J seat leakage testing frequency.
Verification of obturator in the open position will be performed during SLC pump testing and at a frequency in accordance with the ASME OM code Subsection ISTC-3700 and 10 CFR 50.55a(b)(3)(xi). Therefore, no relief is required The open safety function of this valve is to open for the open position.
Standby Liquid Control Open / to provide a flow path from the SLC tank to the C4100F006 (SLC) Outboard Check 1 A/C CHK N/A Active 1, 2, & 10 Closed RPV. The closed safety function of this valve is There is no practical method to validate valve Valve to close to isolate primary containment. closure other than seat leakage testing.
Verification of obturator in the closed position will be performed during seat leakage testing.
Relief is requested to align the frequency of the closed position verification to the Appendix J seat leakage testing frequency.
Since the head spray piping is cut and capped, there is no method to use process indicators to The RHR RPV head spray piping has been cut validate obturator position. Seat leakage testing Residual Heat Removal and capped inside the primary containment. This is the only practical method to validate position.
(RHR) RPV Head Spray E1150F022 motor operated valve has a safety function in the Verification of obturator in both the open and Inboard and Outboard 2 A GA MO Passive Closed 1&2 E1150F023 closed position to isolate primary containment. closed positions will be performed during seat Containment Isolation This valve is normally closed and maintained leakage testing. Relief is requested to align the Motor Operated Valves closed for isolation of penetration X-17. frequency of both the open and closed position verification to the Appendix J seat leakage testing frequency.
Page 1
ATTACHMENT 1 TO ENCLOSURE 1 OF NRC-19-0067 (VRR-004, Revision 1)
Affected Components and Bases for Using Seat Leakage Testing to Confirm Obturator Position Valve ID Code OM Valve Valve Actuator IST Program Safety Method of Obturator Verification / Relief Testing /
Valve Description Function of Valve (PIS) Nos. Class Category Type* Type* Classification Direction Requested Maintenance**
Verification of obturator in the open position will be performed during HPCI and RCIC pump testing and at a frequency in accordance with the ASME OM code Subsection ISTC-3700 and 10 High Pressure Coolant CFR 50.55a(b)(3)(xi). Therefore, no relief is Injection (HPCI) and These normally open valves have a safety required for the open position.
E4150F007 Reactor Core Isolation Open / function to allow HPCI and RCIC injection to the 2 A GA MO Active 1, 2, 4, 11, & 12 E5150F012 Cooling (RCIC) Pump Closed RPV. These valves have a closed safety function There is no practical method to validate valve Discharge Isolation Motor to serve as pressure isolation valves. closure other than seat leakage testing.
Operated Valves Verification of obturator in the closed position will be performed during seat leakage testing.
Relief is requested to align the frequency of the closed position verification to the Appendix J seat leakage testing frequency.
Verification of obturator in the open position will be performed during sump pump operation and at a frequency in accordance with the ASME OM code Subsection ISTC-3700 and 10 CFR These valves are normally open to provide a flow 50.55a(b)(3)(xi). Therefore, no relief is required Radwaste Drywell Sump path for water from the drywell sumps to be for the open position.
G1100F003 Pumps Outboard transferred to collector tanks. These air operated 2 A GA AO Active Closed 1, 2, 3, & 7 G1100F019 Containment Isolation Air valves have a safety function in the closed There is no practical method to validate valve Operated Valves position. These valves isolate penetrations X-18 closure other than seat leakage testing.
and X-19 to maintain containment integrity. Verification of obturator in the closed position will be performed during seat leakage testing.
Relief is requested to align the frequency of the closed position verification to the Appendix J seat leakage testing frequency.
These air operated butterfly valves have a safety function in the open position. The function of There is no practical method to use process these normally closed reactor building-to-indicators to validate obturator position.
suppression chamber isolation valves is to relieve Primary Containment Verification of obturator in both the open and the vacuum when primary containment depressurizes T2300F409 Suppression Chamber Open / closed position will be performed during seat 2 A BF AO Active below reactor building pressure. These air 1, 2, 3, & 7 T2300F410 Reactor Building Vacuum Closed leakage testing. Relief is requested to align the operated butterfly valves also have a safety Breaker Valves frequency of both the open and closed position function in the closed position. T2300F409 is the verification to the Appendix J seat leakage testing penetration X-205B containment inboard frequency.
isolation valve. T2300F410 is the penetration X-205A containment inboard isolation valve.
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ATTACHMENT 1 TO ENCLOSURE 1 OF NRC-19-0067 (VRR-004, Revision 1)
Affected Components and Bases for Using Seat Leakage Testing to Confirm Obturator Position Valve ID Code OM Valve Valve Actuator IST Program Safety Method of Obturator Verification / Relief Testing /
Valve Description Function of Valve (PIS) Nos. Class Category Type* Type* Classification Direction Requested Maintenance**
This valve is not routinely operated under system operation where system parameters could be used to validate obturator position. Seat leakage Standby Gas Treatment These air-operated butterfly valves are normally testing is the only practical method to validate System (SGTS) Torus locked closed to maintain the secondary position. Verification of obturator in both the T4600F420 Hardened Vent Secondary Aug. containment boundary for SGTS. The valves can NC BF AO Passive Closed open and the closed position will be performed 1, 2, 7, & 8 T4600F421 Containment Inboard and B be opened for venting primary containment. The during seat leakage testing. Relief is requested to Outboard Isolation Air valves have a safety function to remain closed to align the frequency of both the open and closed Operated Valves maintain secondary containment.
position verification to the seat leakage testing frequency in accordance with NEI 13-02 Industry Guidance for Compliance with Order EA-13-109.
T4800F416 T4800F417 Validation of obturator position using process T4800F418 parameters would require the nitrogen supply to Containment Atmospheric These valves are normally locked closed and T4800F419 be isolated during vacuum breaker testing, which Control (CAC) N2 Inerting remain closed to isolate control N2 to the drywell-T4800F420 could result in equipment risk to the vacuum to Vacuum Breaker Valves to-torus vacuum breaker. These valves close to T4800F421 breakers. Verification of obturator in both the (T2300F400A - 2 A GL AO Passive Closed isolate the applicable penetration to maintain 1, 2, & 7 T4800F422 open and the closed position will be performed T2300F400M) N2 Supply containment integrity and isolate the nitrogen T4800F423 during seat leakage testing. Relief is requested to Isolation Air Operated inerting system and the reactor building from the T4800F424 align the frequency of both the open and closed Valves drywell.
T4800F425 position verification to the Appendix J seat T4800F426 leakage testing frequency.
T4800F427 There is no practical method to use process These valves are normally closed and open to indicators to validate obturator position.
allow inerting of the drywell with N2 gas, purging Verification of obturator in both the open and the T4800F456 CAC N2 Inerting to SGTS for personnel entry into containment, and closed position will be performed during seat T4800F457 N2 Supply Bypass Air 2 A GL AO Active Closed 1, 2, 3, & 7 treatment of the containment atmosphere prior to leakage testing. Relief is requested to align the T4800F458 Operated Valves its release to the environment. The valves close frequency of both the open and closed position to isolate containment penetration X-205D. verification to the Appendix J seat leakage testing frequency.
The hydrogen recombiner Technical T4804F601A Specification requirements were removed by T4804F601B License Amendment 159, dated March 15, 2004.
T4804F602A There is no routine event to run the system which T4804F602B These normally closed valves are opened to would create an opportunity to validate obturator T4804F603A provide a return flow path to the torus when the position using process variables. Seat leakage T4804F603B H2 Recombiner Isolation 2 A BF MO Active Closed hydrogen recombiner is in service. The safety testing is the only practical method to validate 2, 4, & 6 T4804F604A Valves function of these valves is to provide containment closure. Verification of obturator in both the T4804F604B isolation for penetrations. open and the closed position will be performed T4804F605A during seat leakage testing. Relief is requested to T4804F605B align the frequency of both the open and closed T4804F606A position verification to the Appendix J seat T4804F606B leakage testing frequency.
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ATTACHMENT 1 TO ENCLOSURE 1 OF NRC-19-0067 (VRR-004, Revision 1)
Affected Components and Bases for Using Seat Leakage Testing to Confirm Obturator Position Valve ID Code OM Valve Valve Actuator IST Program Safety Method of Obturator Verification / Relief Testing /
Valve Description Function of Valve (PIS) Nos. Class Category Type* Type* Classification Direction Requested Maintenance**
Verification of obturator in the open position will These valves are normally open to supply: control be performed by monitoring pneumatic pressure nitrogen from the Nitrogen Inerting System; or to and at a frequency in accordance with the ASME supply control air from the Non-Interruptible Air OM code Subsection ISTC-3700 and 10 CFR Supply (NIAS) system; or to provide control 50.55a(b)(3)(xi). Therefore, no relief is required nitrogen from the nitrogen back-up bottles. The for the open position.
pneumatic pressure is used for air operated valves Primary Containment (PC) located in the drywell. The valves have a safety T4901F465 Pneumatic Supply Open / Validation of obturator in the closed position 2 A GL AO Active function in the closed direction to isolate primary 1, 2, 7, & 9 T4901F468 Outboard PC Isolation Air Closed using process parameters would result in containment penetrations X-22 and X-36. The Operated Valves pneumatic pressure being lost to the drywell.
valves have a safety function in the open Seat leakage testing is the only practical method direction to allowing for re-opening following to validate closure. Verification of obturator in containment isolation to provide a long-term the closed position will be performed during seat safety-related pneumatic supply to the Automatic leakage testing. Relief is requested to align the Depressurization System (ADS) Safety Relief frequency of the closed position verification to Valves (SRVs) following a design basis accident.
the Appendix J seat leakage testing frequency.
Verification of obturator in the open position will These valves are normally open to supply: control be performed by monitoring pneumatic pressure nitrogen from the Nitrogen Inerting System; or to and at a frequency in accordance with the ASME supply control air from the Non-Interruptible Air OM code Subsection III-3310 and 10 CFR Supply (NIAS) system; or to provide control 50.55a(b)(3)(xi). Therefore, no relief is required nitrogen from the nitrogen back-up bottles. The for the open position.
pneumatic pressure is used for air operated valves PC Pneumatic Supply located in the drywell. The valves have a safety T4901F601 Open / Validation of obturator in the closed position Inboard PC Isolation Motor 2 A GL MO Active function in the closed direction to isolate primary 2, 5, & 6 T4901F602 Closed using process parameters would result in Operated Valves containment penetrations. The valves have a pneumatic pressure being lost to the drywell.
safety function in the open direction to allowing Seat leakage testing is the only practical method for re-opening following containment isolation to to validate closure. Verification of obturator in provide a long-term safety-related pneumatic the closed position will be performed during seat supply to the Automatic Depressurization System leakage testing. Relief is requested to align the (ADS) Safety Relief Valves (SRVs) following a frequency of the closed position verification to design basis accident.
the Appendix J seat leakage testing frequency.
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ATTACHMENT 1 TO ENCLOSURE 1 OF NRC-19-0067 (VRR-004, Revision 1)
Affected Components and Bases for Using Seat Leakage Testing to Confirm Obturator Position Valve ID Code OM Valve Valve Actuator IST Program Safety Method of Obturator Verification / Relief Testing /
Valve Description Function of Valve (PIS) Nos. Class Category Type* Type* Classification Direction Requested Maintenance**
Verification of obturator in the open position will be performed by monitoring drywell pressure and at a frequency in accordance with the ASME OM code Subsection ISTC-3700 and 10 CFR 50.55a(b)(3)(xi). Therefore, no relief is required for the open position.
These valves are normally open to allow Primary Containment monitoring of drywell pressure during normal T5000F420A Atmosphere Monitoring Open / Validation of obturator in the closed position 2 A BA AO Active operations and following a design basis accident. 1, 2, 3, & 7 T5000F420B (PCAM) Outboard Sample Closed using process parameters would require bleed-off The valves are closed to isolate primary Valves of pressure during power operation. Seat leakage containment penetrations.
testing is the only practical method to validate closure. Verification of obturator in the closed position will be performed during seat leakage testing. Relief is requested to align the frequency of the closed position verification to the Appendix J seat leakage testing frequency.
Verification of obturator in the open position will be performed during radiation sample pump operation and at a frequency in accordance with the ASME OM code Subsection ISTC-3700 and 10 CFR 50.55a(b)(3)(xi). Therefore, no relief is required for the open position.
PCAM PC Radiation This valve is normally open to allow radiation Monitor Rack H21P284 monitoring of primary containment atmospheric Validation of obturator in the closed position T5000F455 2 A BA AO Active Closed 1, 2, & 3 Secondary Isolation Air conditions. This valve closes to isolate primary using process parameters would trip the radiation Operated Valves containment penetrations. sample pump. Seat leakage testing is the only practical method to validate closure. Verification of obturator in the closed position will be performed during seat leakage testing. Relief is requested to align the frequency of the closed position verification to the Appendix J seat leakage testing frequency.
- AO = air operated, BA = ball, BF = butterfly, CHK = check, GA = gate, GL = globe, MO = motor operated
- Table footnotes for information regarding testing/maintenance performed on the subject valves:
1: The standard method for performing position indication test will be performed every two years in accordance with the ISTC-3700 frequency requirements.
2: Seat leakage testing is currently performed on the subject valve. Leakage testing for the hardened vent isolation valves T4600F420 & F421 will be performed in accordance with NEI 13-02.
3: Quarterly stroke timing test is to be performed during the 4th IST Interval.
4: Exercise test is to be performed during the 4th IST Interval at two-year (or less) frequency.
5: Two-year exercise and stroke time are to be performed during the 4th IST Interval.
6: MOV Mandatory Appendix III diagnostic and position indication testing is to be performed during the 4th IST Interval.
7: A recurring preventive maintenance (PM) event exists for AOV diagnostic testing / actuator re-build.
8: Stroke timing is to be performed every operating cycle.
9: Stroke timing is to be performed during cold shutdown.
10: Exercise test is to be performed within the Check Valve Condition Monitoring Program.
11: Position indication of these active motor operated valves will follow more restrictive ISTC-3700 frequency requirement (2 year) instead of Mandatory Appendix III due to in-progress valve re-classification.
12: These pressure isolation valves will be aligned with the 10 CFR 50 Appendix J frequency per 4th Interval Fermi 2 Relief Request VRR-003 (ML19149A329).
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