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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNRC-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-23-0055, NRR E-mail Capture - (External Sender) Fermi 2 Power Plant, Emergency Application to Revise Technical Specifications to Adopt TSTF 568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 - Updated Clean Sheet for NRC-23-00552023-08-16016 August 2023 NRR E-mail Capture - (External_Sender) Fermi 2 Power Plant, Emergency Application to Revise Technical Specifications to Adopt TSTF 568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 - Updated Clean Sheet for NRC-23-0055 ML23227A2212023-08-15015 August 2023 Emergency Application to Revise Technical Specifications to Adopt TSTF 568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 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-23-0020, 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-23-0002, 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-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-22-0023, 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 ML22101A0472022-04-0404 April 2022 Submittal of Application for the Renewal of National Pollutant Discharge Elimination System (NPDES) Permit NRC-21-0001, License Amendment Request to Revise Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Miscellaneous Editorial Changes2021-03-31031 March 2021 License Amendment Request to Revise Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Miscellaneous Editorial Changes NRC-20-0038, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2020-10-28028 October 2020 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules NRC-20-0040, Response to NRC Request from Audit of License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2020-06-23023 June 2020 Response to NRC Request from Audit of License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle NRC-20-0032, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2020-06-0505 June 2020 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NRC-19-0075, License Amendment Request - Proposed Revision to Technical Specifications for Secondary Containment Surveillance Requirements2019-12-0606 December 2019 License Amendment Request - Proposed Revision to Technical Specifications for Secondary Containment Surveillance Requirements NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2019-11-0808 November 2019 DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle NRC-19-0028, License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-032019-09-0505 September 2019 License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-03 NRC-19-0001, License Amendment Request to Revise Technical Specification 3.3.5.3, Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation2019-02-27027 February 2019 License Amendment Request to Revise Technical Specification 3.3.5.3, Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation NRC-19-0002, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2019-02-0808 February 2019 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR NRC-17-0063, License Amendment Request for Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities.2017-10-0909 October 2017 License Amendment Request for Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities. NRC-17-0067, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-08-31031 August 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. ML17237A1762017-08-24024 August 2017 License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1 Isolation Functions NRC-17-0056, Supplemental Information Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 32017-08-15015 August 2017 Supplemental Information Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3 NRC-17-0044, License Amendment Request to Revise Technical Specification 5.5.7, Ventilation Filter Testing Program, to Be Consistent with Standard Technical Specifications2017-08-14014 August 2017 License Amendment Request to Revise Technical Specification 5.5.7, Ventilation Filter Testing Program, to Be Consistent with Standard Technical Specifications NRC-17-0025, License Amendment Request to Revise Technical Specification Section 3.7.2 for Emergency Equipment Cooling Water / Emergency Equipment Service Water System and Ultimate Heat Sink2017-07-17017 July 2017 License Amendment Request to Revise Technical Specification Section 3.7.2 for Emergency Equipment Cooling Water / Emergency Equipment Service Water System and Ultimate Heat Sink NRC-17-0010, License Amendment Request to Revise Technical Specifications for Emergency Core Cooling System Instrumentation and Reactor Core Isolation Cooling System Instrumentation2017-02-23023 February 2017 License Amendment Request to Revise Technical Specifications for Emergency Core Cooling System Instrumentation and Reactor Core Isolation Cooling System Instrumentation NRC-16-0036, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, Using the Consolidated Line Item Improvement Pro2016-07-25025 July 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, Using the Consolidated Line Item Improvement Proces NRC-16-0006, License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals2016-03-22022 March 2016 License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals NRC-15-0081, License Renewal Application Update for the Boraflex Monitoring Program2015-09-24024 September 2015 License Renewal Application Update for the Boraflex Monitoring Program NRC-15-0090, License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-09-24024 September 2015 License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process NRC-15-0067, Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 352015-06-18018 June 2015 Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 35 NRC-15-0062, Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 342015-06-0909 June 2015 Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 34 NRC-15-0044, Response to NRC Request for Additional Information for the Review of the License Renewal Application - Sets 27, 28, 29 and 312015-04-27027 April 2015 Response to NRC Request for Additional Information for the Review of the License Renewal Application - Sets 27, 28, 29 and 31 NRC-15-0030, Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 222015-03-19019 March 2015 Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 22 NRC-15-0028, Revision to Response to License Renewal Environmental RAI SSSH-12015-02-18018 February 2015 Revision to Response to License Renewal Environmental RAI SSSH-1 NRC-15-0021, License Renewal Application - Response to LR-ISG-2013-012015-02-0505 February 2015 License Renewal Application - Response to LR-ISG-2013-01 NRC-14-0055, License Amendment Request to Revise the Emergency Action Level Scheme for the Emergency Plan2014-10-21021 October 2014 License Amendment Request to Revise the Emergency Action Level Scheme for the Emergency Plan ML14121A5362014-04-24024 April 2014 Fermi 2, License Renewal Application, Page 3.3-2 Through Appendix C, Page C-13 ML14121A5352014-04-24024 April 2014 Fermi 2, License Renewal Application, Cover Through Page 3.3-1 ML14121A5382014-04-24024 April 2014 Fermi 2, License Renewal Application, Appendix D Through Appendix E, Page 3-169 ML14121A5392014-04-24024 April 2014 Fermi 2, License Renewal Application, Appendix E, Page 3-170 Through Page 9-23 NRC-14-0028, License Renewal Application, Appendix E, Page 10-1 Through End2014-04-24024 April 2014 License Renewal Application, Appendix E, Page 10-1 Through End NRC-13-0012, License Amendment Request to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2013-04-17017 April 2013 License Amendment Request to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process NRC-13-0004, License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate2013-02-0707 February 2013 License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate NRC-13-0001, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line Item Improvement Process2013-01-11011 January 2013 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line Item Improvement Process NRC-13-0002, Proposed License Amendment to Revise the Fermi 2 Licensing Bases for Protection from Tornado-Generated Missiles2013-01-11011 January 2013 Proposed License Amendment to Revise the Fermi 2 Licensing Bases for Protection from Tornado-Generated Missiles NRC-12-0037, Proposed License Amendment to Relocate Pressure and Temperature Curves to a Pressure Temperature Limits Report2012-12-21021 December 2012 Proposed License Amendment to Relocate Pressure and Temperature Curves to a Pressure Temperature Limits Report NRC-12-0087, License Amendment Request to Change Name of Licensee from the Detroit Edison Company to DTE Electric Company2012-12-21021 December 2012 License Amendment Request to Change Name of Licensee from the Detroit Edison Company to DTE Electric Company NRC-12-0083, License Amendment Request to Change Licensee Name on the Operating License2012-12-21021 December 2012 License Amendment Request to Change Licensee Name on the Operating License NRC-12-0037, Fermi 2, Proposed License Amendment to Relocate Pressure and Temperature Curves to a Pressure Temperature Limits Report2012-12-21021 December 2012 Fermi 2, Proposed License Amendment to Relocate Pressure and Temperature Curves to a Pressure Temperature Limits Report 2023-09-28
[Table view] Category:Technical Specification
MONTHYEARNRC-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-23-0002, 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-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-22-0023, 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-21-0001, License Amendment Request to Revise Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Miscellaneous Editorial Changes2021-03-31031 March 2021 License Amendment Request to Revise Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Miscellaneous Editorial Changes NRC-20-0038, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2020-10-28028 October 2020 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML20282A2302020-10-13013 October 2020 Correction to Amendment No. 216 - Revision to Technical Specifications in Response to GE Energy-Nuclear's 10 CFR Part 21 Safety Communication SC05-03 NRC-20-0032, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2020-06-0505 June 2020 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2019-11-0808 November 2019 DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle NRC-19-0028, License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-032019-09-0505 September 2019 License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-03 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-17-0063, License Amendment Request for Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities.2017-10-0909 October 2017 License Amendment Request for Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities. NRC-16-0036, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, Using the Consolidated Line Item Improvement Pro2016-07-25025 July 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, Using the Consolidated Line Item Improvement Proces NRC-15-0091, License Amendment Request to Revise Technical Specification Section 3.5.1, ECCS - Operating.2015-09-24024 September 2015 License Amendment Request to Revise Technical Specification Section 3.5.1, ECCS - Operating. NRC-15-0090, License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-09-24024 September 2015 License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process NRC-14-0055, License Amendment Request to Revise the Emergency Action Level Scheme for the Emergency Plan2014-10-21021 October 2014 License Amendment Request to Revise the Emergency Action Level Scheme for the Emergency Plan NRC-14-0010, License Amendment Request to Revise Technical Specification Surveillance Requirements for Direct Current Batteries2014-04-23023 April 2014 License Amendment Request to Revise Technical Specification Surveillance Requirements for Direct Current Batteries NRC-13-0004, License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate2013-02-0707 February 2013 License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate 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 NRC-11-0049, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration.2011-12-20020 December 2011 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration. NRC-11-0013, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2011-04-0808 April 2011 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. NRC-10-0047, Proposed Emergency License Amendment for a Onetime Extension of the Completion Time in Technical Specification 3.7.3, Control Room Emergency Filtration (CREF) System, Condition B2010-05-14014 May 2010 Proposed Emergency License Amendment for a Onetime Extension of the Completion Time in Technical Specification 3.7.3, Control Room Emergency Filtration (CREF) System, Condition B ML0735506002007-12-18018 December 2007 Tech Spec Pages for Amendment 177 Technical Specification (TS) Change (TSTF-477) to Add an Action Statement for Two Inoperable Control Center Air Conditioning Subsystems to TS 3.7.4 NRC-07-0047, Transmittal of Revised Technical Specifications (TS) Pages for Use with the Application to Add an Action Statement for Two Inoperable Control Center Air Conditioning Subsystems in TS 3.7.42007-09-11011 September 2007 Transmittal of Revised Technical Specifications (TS) Pages for Use with the Application to Add an Action Statement for Two Inoperable Control Center Air Conditioning Subsystems in TS 3.7.4 NRC-07-0036, Proposed License Amendment to Delete the Note Associated with the Performance of Channel Calibration for Primary Containment High Range Radiation Monitor in Technical Specification 3.3.3.1 Surveillance Requirement2007-07-12012 July 2007 Proposed License Amendment to Delete the Note Associated with the Performance of Channel Calibration for Primary Containment High Range Radiation Monitor in Technical Specification 3.3.3.1 Surveillance Requirement NRC-07-0030, Application for Technical Specification Change (TSTF-477) to Add an Action Statement for Two Inoperable Control Center Air Conditioning Subsystems to Technical Specification 3.7.4 Using the Consolidated Line Item Improvement Process2007-06-12012 June 2007 Application for Technical Specification Change (TSTF-477) to Add an Action Statement for Two Inoperable Control Center Air Conditioning Subsystems to Technical Specification 3.7.4 Using the Consolidated Line Item Improvement Process NRC-06-0063, Application for Technical Specification Change TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for the Diesel Fuel Oil Testing Programs Using the Consolidated Line Item Improvement Process2006-11-27027 November 2006 Application for Technical Specification Change TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for the Diesel Fuel Oil Testing Programs Using the Consolidated Line Item Improvement Process NRC-06-0010, Emergency License Amendment Request for One-Time Extension of Allowed Outage Time for the Plant Emergency Diesel Generator 122006-02-0505 February 2006 Emergency License Amendment Request for One-Time Extension of Allowed Outage Time for the Plant Emergency Diesel Generator 12 ML0529900182005-10-25025 October 2005 Technical Specification Page Control Rod Scram Time Testing Frequency ML0433800092004-12-0707 December 2004 Correction to Amendment No. 163 Technical Specification Change Regarding Increased Flexibility in Mode Changes ML0433502482004-11-29029 November 2004 Technical Specifications, Technical Specification Change Regarding Increased Flexibility in Mode Changes NRC-04-0074, Proposed License Amendment Request to Revise Technical Specification 2.1, Safety Limit Minimum Critical Power Ratio2004-10-0707 October 2004 Proposed License Amendment Request to Revise Technical Specification 2.1, Safety Limit Minimum Critical Power Ratio ML0412503642004-04-23023 April 2004 Licensing Document Transmittal Firm 2 Technical Requirements Manual - Vol I, Revision 67, 04/23/2004. NRC-04-0006, Proposed License Amendment to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation.2004-03-19019 March 2004 Proposed License Amendment to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation. ML0407808262004-03-15015 March 2004 Technical Specification Pages for Amendment 159 NRC-04-0004, Proposed Amendment to Revise Technical Specification 3.3.6.2, Secondary Containment Isolation Instrumentation.2004-01-30030 January 2004 Proposed Amendment to Revise Technical Specification 3.3.6.2, Secondary Containment Isolation Instrumentation. ML0402207862004-01-16016 January 2004 Technical Specification Pages for Fermi 2, Amendment No. 158 ML0330903572003-10-30030 October 2003 Tech Spec Pages for License Amendment 157, Revised Action for SCRAM Discharge Volume Vent and Drain Valves NRC-03-0009, Proposed License Amendment for Revision of TS Section 5.5.10, TS Bases Control Program to Be Consistent with Revised 10 CFR 50.592003-02-13013 February 2003 Proposed License Amendment for Revision of TS Section 5.5.10, TS Bases Control Program to Be Consistent with Revised 10 CFR 50.59 2023-09-28
[Table view] Category:Amendment
MONTHYEARNRC-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-23-0002, 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-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-20-0038, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2020-10-28028 October 2020 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML20282A2302020-10-13013 October 2020 Correction to Amendment No. 216 - Revision to Technical Specifications in Response to GE Energy-Nuclear's 10 CFR Part 21 Safety Communication SC05-03 NRC-20-0032, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2020-06-0505 June 2020 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2019-11-0808 November 2019 DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle NRC-19-0028, License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-032019-09-0505 September 2019 License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-03 NRC-16-0036, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, Using the Consolidated Line Item Improvement Pro2016-07-25025 July 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, Using the Consolidated Line Item Improvement Proces NRC-15-0091, License Amendment Request to Revise Technical Specification Section 3.5.1, ECCS - Operating.2015-09-24024 September 2015 License Amendment Request to Revise Technical Specification Section 3.5.1, ECCS - Operating. NRC-14-0010, License Amendment Request to Revise Technical Specification Surveillance Requirements for Direct Current Batteries2014-04-23023 April 2014 License Amendment Request to Revise Technical Specification Surveillance Requirements for Direct Current Batteries NRC-10-0047, Proposed Emergency License Amendment for a Onetime Extension of the Completion Time in Technical Specification 3.7.3, Control Room Emergency Filtration (CREF) System, Condition B2010-05-14014 May 2010 Proposed Emergency License Amendment for a Onetime Extension of the Completion Time in Technical Specification 3.7.3, Control Room Emergency Filtration (CREF) System, Condition B ML0735506002007-12-18018 December 2007 Tech Spec Pages for Amendment 177 Technical Specification (TS) Change (TSTF-477) to Add an Action Statement for Two Inoperable Control Center Air Conditioning Subsystems to TS 3.7.4 NRC-07-0036, Proposed License Amendment to Delete the Note Associated with the Performance of Channel Calibration for Primary Containment High Range Radiation Monitor in Technical Specification 3.3.3.1 Surveillance Requirement2007-07-12012 July 2007 Proposed License Amendment to Delete the Note Associated with the Performance of Channel Calibration for Primary Containment High Range Radiation Monitor in Technical Specification 3.3.3.1 Surveillance Requirement NRC-06-0063, Application for Technical Specification Change TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for the Diesel Fuel Oil Testing Programs Using the Consolidated Line Item Improvement Process2006-11-27027 November 2006 Application for Technical Specification Change TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for the Diesel Fuel Oil Testing Programs Using the Consolidated Line Item Improvement Process NRC-06-0010, Emergency License Amendment Request for One-Time Extension of Allowed Outage Time for the Plant Emergency Diesel Generator 122006-02-0505 February 2006 Emergency License Amendment Request for One-Time Extension of Allowed Outage Time for the Plant Emergency Diesel Generator 12 ML0529900182005-10-25025 October 2005 Technical Specification Page Control Rod Scram Time Testing Frequency ML0433502482004-11-29029 November 2004 Technical Specifications, Technical Specification Change Regarding Increased Flexibility in Mode Changes NRC-04-0074, Proposed License Amendment Request to Revise Technical Specification 2.1, Safety Limit Minimum Critical Power Ratio2004-10-0707 October 2004 Proposed License Amendment Request to Revise Technical Specification 2.1, Safety Limit Minimum Critical Power Ratio ML0412503642004-04-23023 April 2004 Licensing Document Transmittal Firm 2 Technical Requirements Manual - Vol I, Revision 67, 04/23/2004. NRC-04-0006, Proposed License Amendment to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation.2004-03-19019 March 2004 Proposed License Amendment to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation. ML0407808262004-03-15015 March 2004 Technical Specification Pages for Amendment 159 NRC-04-0004, Proposed Amendment to Revise Technical Specification 3.3.6.2, Secondary Containment Isolation Instrumentation.2004-01-30030 January 2004 Proposed Amendment to Revise Technical Specification 3.3.6.2, Secondary Containment Isolation Instrumentation. ML0402207862004-01-16016 January 2004 Technical Specification Pages for Fermi 2, Amendment No. 158 ML0330903572003-10-30030 October 2003 Tech Spec Pages for License Amendment 157, Revised Action for SCRAM Discharge Volume Vent and Drain Valves 2023-09-28
[Table view] |
Text
Donald K. Cobb Assistant Vice President, Nuclear Generation Fermi 2 6400 North Dixie Hwy., Newport, MI 48166 Tel: 734.586.5201 Fax: 734.586.4172 DTE Energy 7
February 5, 2006 10 CFR 50.90 NRC-06-0010 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001
Reference:
Fermi 2 NRC Docket No. 50-34:
NRC License No. NPF-43
Subject:
Emergency License Amendment Request for One-Time Extension of Allowed Outage Time for the Fermi 2 Emergency Diesel Generator 12 Pursuant to 10 CFR 50.90, Detroit Edison hereby requests the following amendment.
Detroit Edison proposes to add a license condition allowing a one-time extension of the allowed outage time for Emergency Diesel Generator (EDG) 12 from seven days to 14 days. The extension would allow continued operation of the unit while repairs, post-maintenance testing and surveillance testing of the EDG are completed. The proposed amendment is being requested on an emergency basis pursuant to 10 CFR 50.91(a)(5).
On January 30, 2006, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, EDG 12 was declared inoperable for a scheduled safety system outage, entering the seven day action statement of Technical Specification (TS) 3.8.1, Condition A. During the outage it was determined that a bearing and a piston needed to be replaced. Following these repairs and the completion of the safety system outage, the following additional unexpected events were experienced:
- EDG 12 tripped on an overvoltage condition during startup for a post-maintenance test run.
- The EDG 12 output breaker failed to open upon completion of a post-maintenance test run.
The EDG 12 output breaker that failed was a refurbished breaker that had been installed during the safety system outage. After failing to open, the breaker was replaced with the original output breaker. Investigation has determined that the refurbished breaker installed in position 12EB-EB3, during this EDG 12 outage, had physical tolerance
USNRC NRC-06-0010 Page 2 differences from the originally installed breaker. This dimensional difference impacted the fit of the refurbished breaker into the EDG output breaker cubicle. EDG 11, 13, and 14 have had refurbished breakers successfully installed and tested. This failure mode is not common to EDG 11, 13, and 14.
The overvoltage failure is not considered to be due to a common cause. The most probable cause for the overvoltage was relaxation of the spring clip that holds the fuse in the voltage regulator sensing circuit. This is supported by the subsequent finding of intermittent discontinuity at one fuse terminal and previous use of the fuse/spring clip as a tagging point for the EDG.
The EDG 12 seven day LCO expires February 6, 2006, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />.
Detroit Edison could not have reasonably foreseen exceeding the seven day Completion Time of TS LCO 3.8.1. The original EDG 12 safety system outage schedule was extended when routine maintenance inspections determined that a bearing and a piston needed to be replaced. Replacement of the bearing and piston was beyond the planned scope of the safety system outage. The time required to replace the bearing and piston did not, by themselves, extend the completion time of the outage, but multiple runs for post-maintenance break-in and testing were required. This extended the outage, originally scheduled for 3 days and 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />, to 4 days and 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />. Additional time has been added to the outage due to the unexpected conditions requiring EDG 12 output breaker replacement and correction of the EDG 12 output overvoltage trip condition.
Completion of repairs, post-maintenance testing and surveillance testing to establish operability will not likely be completed prior to expiration of the seven day allowed outage time. Detroit Edison is requesting a one time extension of this seven day allowed outage time by an additional seven days to assure adequate tirne is available for completion of repairs, post-maintenance testing and surveillance testing of the EDG.
Detroit Edison has determined that the risk of the requested extension does not warrant subjecting the unit to a shutdown transient. This requested extension would be limited to the current period of EDG inoperability. provides a detailed description and safety analysis to support the proposed amendment, including detailed justification for approving the amendment on an emergency basis, an evaluation of significant hazards considerations pursuant to 10 CFR 50.92(c), and an environmental assessment. Enclosure 2 contains a copy of the existing License Condition page marked up to show the proposed change. Enclosure 3 contains a copy of the proposed revised License Condition page.
No previous submittals affect the license pages that are affected by this proposed amendment. If any future submittals affect these license pages, Detroit Edison will
USNRC NRC-06-0010 Page 3 coordinate the changes to the pages wilh the Nuclear Regulatory Commission (NRC)
Project Manager to ensure proper page control when the associated license amendment requests are approved.
Detroit Edison requests approval of the proposed amendment by 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, February 6, 2006, to preclude unnecessary shutdown of Fermi 2. The proposed amendment will be implemented immediately following NRC approval. This letter contains no new regulatory commitments.
If you have any questions regarding this submittal, please contact Ronald W. Gaston at (734) 586-5197.
S cerely\
D. K. Cobb Assistant Vice President Nuclear Generation
Enclosures:
- 1. Fermi 2 Nuclear Power Plant Evaluation for License Amendment Request
- 2. Proposed License Condition Change (Mark-Up)
- 3. Proposed License Condition Revised Page cc: D. H. Jaffe T. J. Kozak NRC Resident Office Regional Administrator, Region II[I Supervisor, Electric Operators, Michigan Public Service Commission
USNRC NRC-06-0010 Page 4 I, Donald K. Cobb, do hereby affirm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
b.b Assistant Vice President Nuclear Generation On this 54h day of t 2006 before me personally appeared Donald K. Cobb, being first duly sworn and says that he executed the foregoing as his free act and deed.
. ........ . .
- - - - - -- - -
Notary Public woq% K. MRMO!'
3o Co),,
rkav PUBICLeo RI W OM&IMON EXPIRES Jul 24, 20Q0
a USNRC NRC-06-0010 Page 5 bcc: G. D. Cerullo D. K. Cobb W. A. Colonnello R. W. Gaston R. W. Libra M. A. Philippon P. W. Smith S. Stasek Electronic Licensing Library (ELL) (200 TAC)
Information Management (140 NOC)
Michigan Department of Enviromnental Quality Radiological Protection and Medical Waste Section NSRG Administrator (200 TAC)
NRR Chron File
ENCLOSURE 1 to NRC-06-0010 FERMI 2 NUCLEAR POWER PLANT EVALUATION FOR LICENSE AMENDMENT REQUEST
FERMI 2 NUCLEAR POWER PLANT EVALUATION
SUBJECT:
Emergency License Amendment Request for One-Time Extension of Allowed Outage Time for the Fermi 2 Emergency Diesel Generator 12
- 1. DESCRIPTION
- 2. PROPOSED CHANGE
- 3. BACKGROUND
- 4. TECHNICAL ANALYSIS
- 5. REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements / Criteria
- 6. ENVIRONMENTAL CONSIDERATION to NRC-06-0010 Page 3
1.0 DESCRIPTION
Pursuant to 10 CFR 50.90, Detroit Edison hereby requests the following amendment.
Detroit Edison proposes to add a license condition allowing a one-time extension of the allowed outage time for Emergency Diesel Generator (EDG) 12. The extension would allow continued operation of the unit while repairs and related testing of the EDG are completed. The proposed amendment is being requested on an emergency basis pursuant to 10 CFR 50.91(a)(5).
On January 30, 2006, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, EDG 12 was declared inoperable for a scheduled safety system outage, entering the seven day action statement of Technical Specification (TS) LCO 3.8.1, Condition A. During the outage, it was determined that a bearing and a piston needed to be replaced. Following these repairs and the completion of the safety system outage, the following three additional unexpected events were experienced:
- February 2, 2006, 0949 hour0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.610945e-4 months <br />s: EDG 12 tripped on overvoltage during a startup for post-maintenance testing. This condition appeared to be resolved. February 3, 2006, 1046 hour0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98003e-4 months <br />s: EDG 12 is started in auto voltage control, output breaker is closed. The overvoltage trip condition did not recurr.
- February 3, 2006, 1154 hour0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.39097e-4 months <br />s: EDG 12 output breaker fails to open upon completion of a post-maintenance test run.
- February 4, 2006, 0641 hour0.00742 days <br />0.178 hours <br />0.00106 weeks <br />2.439005e-4 months <br />s: EDG 12 tripped on overvoltage during a startup for post-maintenance testing. This is a repeat of the February 2 trip condition.
The EDG 12 output breaker that failed was a refurbished breaker that had been installed during the safety system outage. After failing to open, the breaker was replaced with the original output breaker. Investigation has determined that the refurbished breaker installed in position 12EB-EB3, during this EDG 12 outage, had physical tolerance differences from the originally installed breaker.
The overvoltage failure is not considered to be due to a common cause. The most probable cause for the overvoltage was relaxation of the spring clip that holds the fuse in the voltage regulator sensing circuit. This is supported by the subsequent finding of intermittent discontinuity at one fuse terminal and previous use of the fuse/spring clip as a tagging point for the EDG.
The EDG 12 seven day LCO expires February 6, 2006, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />.
Detroit Edison could not have reasonably foreseen exceeding the seven day Completion Time of TS LCO 3.8.1. The original EDG 12 safety system outage schedule was extended when routine maintenance inspections determined that a bearing and a piston needed to be replaced and subsequent electrical problems in voltage regulation and the
Enclosure 1 to NRC-06-0010 Page 4 EDG 12 output breaker. These events are described in more detail in the section discussing why the situation could not have been avoided, Section 3, below.
When the overvoltage condition has been corrected, there remains approximately 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> of post-maintenance testing and surveillance testing prior to declaring EDG 12 operable.
Completion of repairs, post-maintenance testing, and surveillance testing to establish operability will not likely be completed prior to expiration of the seven day allowed outage time. Detroit Edison is requesting a one time extension of this seven day allowed outage time by an additional seven days to assure adequate time is available for completion of repairs, post-maintenance: testing, and surveillance testing of the EDG.
Detroit Edison has determined that the risk of the requested allowed outage time extension does not warrant subjecting the unit to a shutdown transient. This requested extension would be limited to the current period of EDG inoperability.
2.0 PROPOSED CHANGE
The proposed change would add a new License Condition to Section 2.C of the Fermi 2 Facility Operating License. The proposed License Condition is as follows:
The seven day allowed outage time ofTechnical Specification 3.8.1 Condition A, Required Action A.6, which was entered at January 30, 2006, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, may be extended one time by an additional seven days to complete repair and testing of EDG 12.
3.0 BACKGROUND
Description of Events Completion of troubleshooting, repairs, post-maintenance testing, and surveillance testing to establish operability will not be completed prior to expiration of the seven day allowed outage time. TS LCO 3.8.1, Condition C would require that the unit to be placed in Mode 3, Hot Shutdown, within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in Mode 4, Cold Shutdown, within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> of the expiration time of 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on February 6, 2006.
The purpose of this amendment request is to request additional time in order to satisfactorily complete troubleshooting, repairs, post-maintenance testing, and surveillance testing. Detroit Edison has determined that the risk of extending the seven day allowed outage time by an additional seven days does not warrant subjecting the unit to a shutdown transient. Accordingly, DelToit Edison is requesting that the seven day allowed outage time specified by TS LCO 3.8.1, Condition A be extended one time by an
Enclosure 1 to NRC-06-0010 Page 5 additional seven days to allow completion of repairs and retesting of EDG 12. This requested extension would be limited to the current period of EDG inoperability.
With EDG 12 inoperable for greater than seven days, a violation of TS LCO 3.8.1 would occur if action were not taken to initiate a plant shutdown. Thus, a TS amendment is needed to allow continued plant operation, utilizing an extension of the seven day Completion Time specified for one inoperable EDG per Required Action A.6 of TS LCO 3.8.1.
Basis for Current Requirements The operability requirements for the alternating current power sources during plant operation ensures that sufficient power will be available to supply the safety-related equipment required for 1) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant alternating power sources satisfy the requirements of General Design Criteria 17, "Electric Power Systems," of Appendix A to 10 CFR 50.
The TS Action requirements specified for the levels of degradation of the power sources provide restrictions for continued facility operation commensurate with the level of degradation. The operability requirements for the power sources are consistent with the initial condition assumptions of the accident analyses and are based upon maintaining at least one of each of the onsite alternating current power sources and associated distribution systems operable during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite alternating current source.
Reason for Requesting Emergency Amendment Regulation 10 CFR 50.9 1(a)(5) states that where the Nuclear Regulatory Commission (NRC) finds that an emergency situation exists, in that failure to act in a timely manner would result in derating or shutdown of a nuclear power plant, or in prevention of either resumption of operation or of increase in power output up to the plant's licensed power level, it may issue a license amendment involving no significant hazards consideration without prior notice and opportunity for a hearing or for public comment. The regulation also states that the NRC will decline to dispense with notice and comment on the determination of no significant hazards if it determines that the licensee has abused the emergency provision by failing to make t:imely application for the amendment and thus itself creating the emergency. The regulation requires that a licensee requesting an emergency amendment explain why the emergency situation occurred and why the licensee could not avoid the situation. As explained below, an emergency amendment is needed to preclude an unnecessary plant shutdown, and Detroit Edison could not have reasonably avoided the situation or made timely application for an amendment.
to NRC-06-0010 Page 6 Reason Emergency Situation Has Occurred The emergency situation resulted from several unforeseen problems that occurred during this maintenance outage that was originally scheduled to be completed in 91 hours0.00105 days <br />0.0253 hours <br />1.50463e-4 weeks <br />3.46255e-5 months <br />.
Although the problems associated with the bearing replacement, the piston replacement and the output breaker have been resolved and repairs completed, the time required to complete troubleshooting and post maintenance testing associated with these problems is a major contributor to the current emergency situation for which a license amendment is being requested.
The remaining problem involves the unexpected EDG 12 overvoltage condition which was experienced on February 2, 2006 and again on February 4th. Troubleshooting, repair and retesting associated with this problem and the remaining post maintenance runs necessary to restore EDG 12 operability will likely exceed the seven days allowed by TS 3.8.1, Condition A and thus require that the unit be shutdown.
Detroit Edison has determined that the risk of extending the seven day allowed outage time by an additional seven days does not warrant subjecting the unit to a shutdown transient. Neither a routine nor an exigent amendment could be processed within the available time. Therefore, an emergency amendment is needed to preclude an unnecessary shutdown.
Reason the Situation Could Not Have Been Avoided On January 30, 2006, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, EDGi 12 was declared inoperable for a scheduled safety system outage, entering the seven day action statement of Technical Specification (TS) LCO 3.8.1, Condition A. During the outage, it was determined that a bearing and a piston needed to be replaced. Near the completion of the safety system outage, the following three unexpected conditions were experienced:
- February 2, 2006, 0949 hour0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.610945e-4 months <br />s: EDG 12 tripped on overvoltage during a startup for post-maintenance testing. This condition appeared to be resolved. February 3, 2006, 1046 hour0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98003e-4 months <br />s: EDG 12 is started in auto voltage control, output breaker is closed. The overvoltage trip cond ition did not recurr.
- February 3, 2006, 1154 hour0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.39097e-4 months <br />s: EDIG 12 output breaker fails to open upon completion of a post-maintenance test run.
- February 4, 2006, 0641 hour0.00742 days <br />0.178 hours <br />0.00106 weeks <br />2.439005e-4 months <br />s: EDG 12 tripped on overvoltage during a startup for post-maintenance testing. This is a repeat of the February 2, 2006, trip condition.
Enclosure 1 to NRC-06-0010 Page 7 The EDG 12 output breaker had been replaced with a refurbished breaker during the safety system outage. The refurbished EDG 12 output breaker was replaced with the original output breaker. Investigation has determined that the refurbished breaker installed in position 12EB-EB3, during this EDG 12 outage, had physical tolerance differences from the originally installed breaker.
The overvoltage failure is not considered to be due to a common cause. The most probable cause for the overvoltage was relaxation of the spring clip that holds the fuse in the voltage regulator sensing circuit. This is supported by the subsequent finding of intermittent discontinuity at one fuse terminal and previous use of the fuse/spring clip as a tagging point for the EDG.
The EDG 12 seven day LCO expires February 6, 2006, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />.
Detroit Edison could not have reasonably foreseen exceeding the seven day Completion Time of TS LCO 3.8.1. The original EDG 12 safety system outage schedule was extended when routine maintenance inspections determined a bearing and a piston needed to be replaced. Replacement of the bearing and piston was beyond the planned scope of the safety system outage. The time required to replace the bearing and piston did not, by themselves, extend the completion time of the outage, but multiple runs for post-maintenance break-in and testing were required. This extended the outage, originally scheduled for 3 days and 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />, to 4 days and 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />. Additional time has been added to the outage due to the the unexpected conditions requiring EDG 12 output breaker replacement and correction of the EDG 12 output overvoltage trip condition.
When the overvoltage condition has been corrected, there remains approximately 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> of post-maintenance testing and surveillance testing prior to declaring EDG 12 operable.
Completion of repairs, post-maintenance testing, and surveillance testing to establish operability will not likely be completed prior to expiration of the seven day allowed outage time. Detroit Edison is requesting a one time extension of this seven day allowed outage time by an additional seven days to assure adequate time is available for completion of repairs, post-maintenance testing, and surveillance testing of the EDG.
Detroit Edison has determined that the risk of the requested allowed outage time extension does not warrant subjecting the unit to a shutdown transient. This requested extension would be limited to the current period of EDG inoperability.
Detroit Edison therefore considers that the situation could not have been avoided and there is justification for requesting the proposed license amendment on an emergency basis.
Enclosure 1 to NRC-06-0010 Page 8
4.0 TECHNICAL ANALYSIS
The proposed amendment to allow a one-time extension of the allowed outage time for EDG 12 is based on the following considerations.
Risk from Proposed Allowed Outage Time Extension A quantitative Probabilistic Risk Analysis (PRA) for the extended Fermi 2 EDG 12 allowed outage time was produced by comparing the quantified values for Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) with EDG 12 out of service versus the baseline "with maintenance" results.
The evaluation determined that the risk associated with maintaining the unit at power for an additional 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> beyond the present TS allowed outage time with an EDG unavailable falls within the available regulatory guidance. Fermi has concluded that the one-time, single EDG TS allowed outage time change has only a small quantitative impact on plant risk (based upon the guidance provided in Regulatory Guide 1.174 and 1.177).
The evaluation was performed using the ]FermiV6 PRA model. The evaluation used the "with maintenance" PRA model (with nominal equipment unavailability) to compare the results with EDG 12 out-of-service and in-service. The values calculated for ICCDP and ICLERP were determined based on the additional seven-day EDG 12 outage. The numerical analysis is shown below:
ICCDP = (CDFEDG12 - CDFbase)* At Where:
ICCDP = Incremental Conditional Core Damage Probability (per RG 1.177)
CDFEDG12 = Core Damage Frequency with EDG 12 out-of service - 1.23E-5 yr41 CDFbaSe = Core Damage Frequency for the baseline quantification - 4.79E-6 yr 1 At = Change in duration for the proposed one-time AOT extension - 7 days.
ICCDP = (1.23E-5 yf' - 4.79E-6 yr-1 ) * (7 days / (365 days/yr)) = 1.4E-7 And ICLERP = (LERFEDGL2 - LERFbase)* At ICLERP = Incremental Conditional Core Damage Probability (per RG 1.177)
LERFEDGL2 = Large Early Release Frequency with EDG 12 out-of service - 7.07E-7 yr-LERFbase = Large Early Release Frequency for the baseline quantification - 3.27E-7 yr-to NRC-06-0010 Page 9 At = Change in duration for the proposed one-time AOT extension - 7 days.
ICLERP = (7.07E-7 yf ' - 3.27E-7 yrf1) * (7 days / (365 days/yr)) = 7.3E-9 The above calculated values are well below the stringent thresholds required in RG 1.177 (an ICCDP of 5.OE-7 and an ICLERP of '5.OE-8) for a permanent Technical Specification change.
The analysis was completed with the following assumptions:
- 1. The baseline "with maintenance" PRA model, FermiV6 was utilized to perform the assessment. This model represents normal plant operation at full power and includes failure terms for all systems, as well as nominal initiating event frequencies.
- 2. EDG 12 will be returned to service 14 days from the initial LCO entry.
- 3. Equipment failure probabilities are not adjusted to credit restricting access to certain plant equipment required to guarantee the safe shutdown of the plant in the event of a transient.
- 4. No credit was taken for compensatory measures that may be taken to decrease operator or equipment failure rate.
- 5. No credit is taken for the temporary blackstart diesel generator, which allows CTGs 11-2, 11-3, and 11-4 as a source of electrical power in the event of a station blackout.
- 6. No credit is given for the recent periodic testing of the diesel generators (which would reduce their failure probabilities).
- 7. This condition does not increase the contribution to core damage due to other internal and external initiating events.
- 8. A truncation limit of lE-10 was utilized for all quantifications.
In addition to the above analysis, a sensitivity study was performed to account for any potential inclement weather that may occur during the duration of the extended AOT (by increasing the loss of offsite power initiating event frequency by a factor of 2.0). The results of this analysis show that the calculated values are still below the RG 1.177 criteria (ICCDP = 2.OE-7 and ICLERP = 1.7E-8).
to NRC-06-0010 Page 10 Operation and Maintenance Restrictions In accordance with MMR12, the site procedure for risk management, "Equipment Out of Service Risk Management," the plant is currently in a "LOW" risk status and is expected to remain in this category for the extended AOT period. The following equipment protections will be in effect until EDG 12 is restored to an Operable status:
- Elective maintenance will not be performed on EDGs 11, 13, and 14 or CTG 11-1.
- Elective maintenance will not be scheduled within the 120 kV and 345 kV switchyards that would challenge the offsite power connections or offsite power unavailability.
- Elective maintenance will not be performed on equipment in the Standby Feedwater (SBFW) System.
While in the extended EDG 12 completion time period, overall plant risk will be managed by the existing Maintenance Rule (a)(4) program. This program evaluates increases in risk posed by potential combinations of equipment out-of-service and potential increases in initiating event frequency and requires that risk recommendations be implemented as appropriate for a given plant configuration.
Maintenance and testing during the allowed outage time extension will be rescheduled for Fermi 2 as warranted to minimize aggregate risk. This will specifically include:
- Work performed on safety significant systems and their applicable support systems will be reviewed and rescheduled as necessary based upon routine and emergent Maintenance Rule 10CFR65 (a)(4) evaluations.
- No work will be performed that could potentially jeopardize the availability of the remaining on site emergency power sources. This will be ensured by restricting and/or controlling access to this equipment via guidance provided in MOP05 (the site procedure for control of equipment).
The following actions will be taken to provide an increased assurance of grid stability:
- No test or maintenance activities that could reduce switchyard reliability will be performed.
- At four hour intervals, the projected grid voltage following postulated unit trip will be verified to indicate a stable grid. Assuring the grid conditions are expected to remain stable serves to reduce the grid as an initiator for loss of offsite power to the units.
- Fermi 2 will contact the system dispatcher to ensure that no short-term activities adversely affecting grid stability are planned or have transpired.
to NRC-06-0010 Page 11
- Fermi 2 will confirm that the system dispatcher will notify the control room or Shift Manager in the event of severe weather, system degradation, or perturbations do occur so that an appropriate plant response can be determined.
Operations Briefings will be conducted on the use of CTG 11-1 and the utilization of CTG 11-2, CTG 11-3, or CTG 11-4 in conjunction with the auxiliary blackstart diesel to mitigate the consequences of a station blackout or loss of off-site power. These briefings will include review of the associated procedures.
Grid Reliability The following statements from the December 2005 Fermi Grid Adequacy Study demonstrate the stability of the grid near the Fermi plant site.
This study was performed by International Transmission Company (ITC) at the request of DTE Energy. The results show that the Fermi 2 generator and the rest of the system will remain stable for all conditions studied. Fermi and all generators in the study area show a well damped stable response to all faults simulated. Under the conditions studied, the voltage at the Fermi 120kV and 345kV buses, as well as the critical system service 4.16kV buses SS64 and SS65, will be sufficient to prevent the initiation of a trip by the degraded grid relays. Therefore, the grid is capable of supplying the necessary offsite power if the Fermi 2 unit trips off line.
to NRC-06-0010 Page 12
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration Detroit Edison has evaluated whether the proposed amendment involves a significant hazards consideration by addressing the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as described below:
(1) The proposed change does not involve a significant increase in the probability or the consequences of any accident previously evaluated.
The proposed change affects the Completion Time for TS LCO 3.8.1, Required Action A.6. The proposed change allows a one-time extension of the current Completion Time for the inoperable EDG 12 from seven days to 14 days.
The proposed change does not affect the design of the EDGs, the operational characteristics or function of the EDGs, the interfaces between the EDGs and other plant systems, or the reliability of the EDGs.
Required Actions and their associated Completion Times are not considered initiating conditions for any accident previously evaluated, nor are the EDGs considered initiators of any previously evaluated accidents.
The EDGs are provided to mitigate the consequences of previously evaluated accidents, including a loss of offsite power. The consequences of previously evaluated accidents will not be significantly affected by the extended EDG Completion Time because a sufficient number of onsite AC power sources will continue to remain available to perform the accident mitigation functions associated with the EDGs, as assumed in the accident analyses. Thus the consequences of accidents previously evaluated are not affected by the proposed change in Completion Time To fully evaluate the effect of the proposed EDG Completion Time extension, Probabilistic Risk Assessment (PRA) methods and a deterministic analysis were utilized. The results of the analysis show no significant increase in Core Damage Frequency (CDF) or Large Early Release Frequency (LERF). Therefore, the proposed change does not involve a significant increase in the probability or the consequences of any accident previously evaluated.
to NRC-06-0010 Page 13 (2) The proposed change would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change does not involve a change in the design, configuration, or method of operation of the plant. The proposed change will not alter the manner in which equipment operation is initiated, nor will the functional demands on credited equipment be changed. The proposed change allows operation of the unit to continue while EDG 12 is repaired and retested. The proposed extension does not affect the interaction of EDG 12 with any system whose failure or malfunction can initiate an accident. As such, no new failure modes are being introduced.
Therefore, this proposed change does not create the possibility of a new or different kind of accident fErom any accident previously evaluated.
(3) The proposed change will not involve a significant reduction in the margin of safety.
The proposed change does not alter the plant design, nor does it affect the assumptions contained in ihe safety analyses. Specifically, there are no changes being made to the EDG design, including instrument setpoints.
The proposed change has been evaluated both deterministically, and using risk-informed methods. Based upon these evaluations, margins of safety ascribed to EDG availability and to plant risk have been determined to be not significantly reduced. The evaluation has concluded the following with respect to the proposed change:
Applicable regulatory requirements will continue to be met, adequate defense-in-depth will be maintained, sufficient safety margins will be maintained, and any increases in CDF and LERF are small and consistent with the NRC Safety Goal Policy Statement (Federal Register, Vol.5 1, p.
30028 (51 FR 30028), August 4, 1986, as interpreted by NRC Regulatory Guides 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," and 1.177, "An Approach for Plant-Specific Risk-Informed Decision making: Technical Specifications"). Furthermore, increases in risk posed by potential combinations of equipment out of service during the proposed extended EDG Completion Time will be managed under a configuration risk management program consistent with 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," paragraph (a)(4), and as required by Technical Requirements Manual TR 5.1.2.
Enclosure 1 to NRC-06-0010 Page 14 The availability of offsite power coupled with the availability of the other EDGs and the use of on-line risk assessment tools provide adequate compensation for the potential small incremental increase in plant risk associated with the extended EDG Completion Time. The proposed extended EDG Completion Time in conjunction with the availability of the other EDGs, continues to provide adequate assurance of the capability to provide power to the engineered safety features (ESF) buses.
Therefore, implementation of the proposed change will not involve a significant reduction in the margin of safety.
The evaluation provided above shows that the proposed change will not significantly increase the probability or the consequences of any accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in the margin of safety. Therefore, the proposed change meets the criteria of 10 CFR 50.92(c) and no significant hazard consideration is involved.
5.2 Applicable Regulatory Requirements / Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. Detroit Edison has determined that the proposed change does not require any exemptions or relief from regulatory requirements, other than the Technical Specifications (TS), and does not affect conformance with any General Design Criterion (GDC) differently than described in the Safety Analysis Report (SAR).
6.0 ENVIRONMENTAL CONSIDERATION
Detroit Edison has reviewed the proposed change against the criteria of 10 CFR 51.22 for environmental considerations. The proposed change does not involve a significant hazards consideration, nor does it significantly change the types or significantly increase the amounts of effluents that may be released offsite. The proposed change does not significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, Detroit Edison concludes that the proposed change meets the criteria provided in 10 CFR 51 .22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement or an Environmental Assessment.
ENCLOSURE 2 to NRC-06-0010 PROPOSED TECHNICAL SPECIFICATION CHANGE (MARK-UP)
INCLUDED PAGE:
License Conditions page 6
(21) The schedule for performing surveillance requirements (SRs) that are new or revised in Amendment No. 134 shall be as follows:
- For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.
- For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
- For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
- For SRs that edisted prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to the irmlplementation of this amendment.
(22) DECo shall perform an integrated tracer gas test to measure Control Room inleakage using methods described in ASTM E741-00, "Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution." This test will be performed by March 31, 2005.
Further periodic assessments and testing will be performed In accordance with the guidance provided in NRC Regulatory Guide 1.197, (May 2003)
"Demonstrating Control Room Envelope Integrity At Nuclear Power Reactors," Section D, Implementation, using the six year cycle described.
In accordance with the Regulatory Guide, a self assessment will be performed after three years and a periodic test after 6 years.
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(23) The 7 day allowed outage time of Technical Specification 3.8.1 Condition "A",
Required Action A.6, which was entered at January 30, 2006, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, may be extended one time by an additional 7 days to complete repair and testing of EDG 12.
Amendment No. 11, tS+- 162
ENCLOSURE 3 to NRC-06-0010 PROPOSED TECHNICAL SPECIFICATION REVISED PAGE INCLUJDED PAGE License Conditions page 6
(21) The schedule for performing surveillance requirements (SRs) that are new or revised in Amendment No. 134 shall be as follows:
- For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.
- For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
- For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
- For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to the implementation of this amendment.
(22) DECo shall perform an integrated tracer gas test to measure Control Room inleakage using methods described in ASTM E741-00, "Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution." This test will be performed by March 31, 2005.
Further periodic assessments and testing will be performed in accordance with the guidance provided in NRC Regulatory Guide 1.197, (May 2003)
"Demonstrating Control Room Envelope Integrity At Nuclear Power Reactors," Section D, Implementation, using the six year cycle described.
In accordance with the Regulatory Guide, a self assessment will be performed after three years and a periodic test after 6 years.
(23) The 7 day allowed outage time of Technical Specification 3.8.1 Condition "A",
Required Action A.6, which was entered at January 30, 2006, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, may be extended one time by an additional 7 days to complete repair and testing of EDG 12.
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Amendment No. 1l-T, 1-34-,-62