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Revision as of 21:25, 17 May 2018
| ML18109A164 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/19/2018 |
| From: | Maglio S A DTE Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC-18-0022 | |
| Download: ML18109A164 (8) | |
Similar Documents at Fermi | |
|---|---|
Category:Letter
MONTHYEARIR 05000341/20240122024-11-0101 November 2024
[Table view]Commercial Grade Dedication Inspection Report 05000341/2024012 IR 05000341/20245012024-10-0808 October 2024 – Emergency Preparedness Inspection Report 05000341/2024501 ML24276A2032024-10-0303 October 2024 FEMA Level 1 Finding Transmittal Letter ML24268A0992024-10-0101 October 2024 Power Plant – Audit Summary for License Amendment Request and Regulatory Exemptions for a Risk Informed Approach to Address ECCS Strainer Performance IR 05000341/20240132024-09-30030 September 2024 Phase 2 Post Approval License Renewal Report 05000341/2024013 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24257A1652024-09-13013 September 2024 FEMA Region 5 Fermi 2 Nuclear Power Plant Level 1 Finding September 2024 ML24254A3562024-09-0909 September 2024 FEMA Level 1 Finding for Fermi 2024 Biennial Exercise ML24240A3532024-08-27027 August 2024 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval Update IR 05000341/20240052024-08-22022 August 2024 Updated Inspection Plan for Fermi Power Plant, Unit 2 (Report 05000341/2024005) IR 05000341/20244042024-08-21021 August 2024 Public-Fermi Power Plant, Unit 2 - Material Control and Accounting Program Inspection Report 05000341/2024404 IR 05000341/20240022024-08-14014 August 2024 Integrated Inspection Report 05000341/2024002 ML24199A2182024-07-25025 July 2024 Enrico Fermi Atomic Power Plant, Unit 1 - NRC Position on Continuation of Possession-Only License No. DPR-9 Past the Current Expiration Date (Docket No. 50-016) ML24169A4092024-07-18018 July 2024 Relief Request RR-A25, Alternative to Reactor Vessel Circumferential Shell Weld Examination IR 05000341/20243022024-07-0909 July 2024 NRC Initial License Reexamination Report 05000341/2024302 ML24173A1012024-06-14014 June 2024 Retake Exam Post-Exam Cover Letter & Comments ML24155A0852024-06-11011 June 2024 Operator Licensing Reexamination Approval Letter - Fermi Power Plant, June 2024 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000341/20244022024-05-30030 May 2024 Security Baseline Inspection Report 05000341/2024402 ML24143A1852024-05-29029 May 2024 – Regulatory Audit in Support of LAR to Adopt TSTF-505, Rev. 2, TSTF-439, Rev. 2, and TSTF-591, Rev. 0 ML24141A2072024-05-20020 May 2024 Plant—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 05000341/LER-2024-002, Primary Containment Isolation Valve Declared Inoperable for a Period Prohibited by Technical Specifications2024-05-16016 May 2024 Primary Containment Isolation Valve Declared Inoperable for a Period Prohibited by Technical Specifications 05000341/LER-2024-001, Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-222024-05-15015 May 2024 Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-22 IR 05000341/20240102024-05-0606 May 2024 NRC Inspection Report 05000341/2024010 ML24052A2772024-04-30030 April 2024 Issuance of Amendment No. 229 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 IR 05000341/20240012024-04-30030 April 2024 Integrated Inspection Report 05000341/2024001 ML24107B1372024-04-18018 April 2024 Confirmation of Initial License Reexamination June 2024 ML24101A3732024-04-11011 April 2024 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000341/2024012 ML24100A8422024-04-0909 April 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection: Inspection Report 05000341/2024013 IR 05000341/20234022024-04-0808 April 2024 Reissue - Fermi Power Plant, Unit 2 - Cyber Security Inspection Report 05000341/2023402 (Public) ML24088A2162024-04-0404 April 2024 Change in Estimated Review Schedule and Level of Effort for License Amendment Request for Risk Informed Approach to ECCS Strainer Performance ML24086A5732024-04-0101 April 2024 Response to Disputed Non-Cited Violation Documents in Fermi Power Plant, Unit 2 - Cyber Security Inspection Report 05000341/2023402-01 Withdrawal of Non-Cited Violation (Public) IR 05000341/20243012024-04-0101 April 2024 NRC Initial License Examination Report 05000341/2024301 IR 05000341/20244012024-03-22022 March 2024 – Security Baseline Inspection Report 05000341/2024401 (Public) IR 05000341/20240112024-03-0808 March 2024 Nbsp;Safety Conscious Work Environment Issue of Concern Follow-up Inspection Report 05000341/2024011 ML24002B1812024-03-0404 March 2024 Issuance of Amendment No. 228 Regarding Revision of Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage IR 05000341/20230062024-02-28028 February 2024 Annual Assessment Letter for Fermi Power Plant, Unit 2 (Report 05000341/2023006) ML24019A1842024-02-16016 February 2024 Exemption from Select Requirements of 10 CFR Part 73 Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24045A1602024-02-14014 February 2024 Operator Licensing Examination Approval - Fermi Power Plant, February 2024 IR 05000341/20230042024-02-0505 February 2024 Integrated Inspection Report 05000341/2023004 IR 05000341/20230102023-12-0808 December 2023 Nbsp;Biennial Problem Identification and Resolution Inspection Report 05000341/2023010 ML23341A1852023-12-0808 December 2023 Acknowledgement of Response to NRC Inspection Report 05000341/2023402 and Disputed Non-Cited Violation ML23310A1492023-12-0808 December 2023 Issuance of Amendment No. 227 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements ML23334A1902023-12-0101 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000341/2024010 ML23335A0062023-12-0101 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000341/2024002 IR 05000016/20230012023-12-0101 December 2023 NRC Inspection Report No. 050-00016/2023-001 (Drss) - Enrico Fermi Atomic Power Plant, Unit 1 IR 05000341/20230032023-11-0707 November 2023 Integrated Inspection Report 05000341/2023003 and 07200071/2023001 ML23297A0512023-10-30030 October 2023 Issuance of Amendment No. 226 Regarding Revision of Technical Specifications 3.8.1, AC Sources - Operating (Exigent Circumstances) ML23311A3482023-10-20020 October 2023 DTE Electric Company (DTE) - Submittal of the Renewed Fermi 3 Michigan Department of Environmental, Great Lakes, and Energy (EGLE) National Pollutant Discharge Elimination System (NPDES) Permit No. MI0058892 ML23272A1552023-10-10010 October 2023 – Letter to Licensee and Federal Register Notification of Amendment to Renewed Facility Operating License and Proposed No Significant Hazards Consideration Determination (Exigent Circumstances) (EPID L-2023-LLA-0134) (Letter) 2024-09-09 Category:Report 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: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
[Table view]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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