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.
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MONTHYEARNRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis2023-03-0707 March 2023
[Table view]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 Category:Technical MONTHYEARNRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis2023-03-0707 March 2023
[Table view]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 |