Similar Documents at Fermi |
---|
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] |
Text
William T. O'Connor, Jr.
Vice President, Nuclear Generation Fermi 2 6400 North Dixie Hwy., Newport, Michigan 48166 Tel: 734.586.5201 Fax: 734.586.4172 Detroit Edison
.* A DTE Energy Company 10CFR50.90 February 21, 2002 NRC-02-0002 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001
Reference:
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Proposed License Amendment for the Elimination of the Chlorine Detection Function from the Control Room Heating, Ventilation and Air Conditioning System Pursuant to 10CFR50.90, Detroit Edison hereby requests the NRC approval of a proposed License Amendment to eliminate the chlorine detection function from the Control Room Heating, Ventilation and Air Conditioning (CCHVAC) system. provides a description and an evaluation of the proposed license change. provides an analysis of significant hazards consideration using the standards of 10CFR50.92.
Detroit Edison has reviewed the proposed license change against the criteria of 10CFR51.22 for categorical exclusion of environmental review. 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 change does not significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, Detroit Edison concludes that the proposed license change meets the criteria provided in 10CFR5 1.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement or an Environmental Assessment.
Detroit Edison has recently completed a study to evaluate the need for the chlorine detection system. The study included a survey to determine all chlorine sources in the vicinity of the plant. A probabilistic approach was utilized to evaluate the risk of
USNRC NRC-02-0002 Page 2 incapacitating the control room operators from a chlorine release accident. The study concluded that the probability of a chlorine release having the potential to result in a significant concentration in the control room is below the threshold specified in Regulatory Guide 1.78, Revision 1, for considering chemical hazards in the evaluation of control room habitability. Therefore, the chlorine detection system and automatic isolation function are no longer necessary at Fermi 2.
This License Amendment involves changes to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) and Technical Requirements Manual (TRM) which is incorporated by reference in the UFSAR. Changes to the UFSAR are subject to the requirements of 10CFR50.59; however, these changes are being submitted for NRC review and approval since they involve the elimination of an automatic action.
Nuclear Energy Institute (NEI) guidance document 96-07, Revision 1, indicates that NRC approval would be required for changes involving the permanent elimination of automatic actions for performing UFSAR-described design functions. Therefore, Detroit Edison believes this change cannot be performed under 10CFR50.59.
In recent years, the chlorine detection system reliability has been degrading. The chlorine detectors have frequently failed response time testing, and have been placed on an increased surveillance test frequency. The detectors have required extensive maintenance, and frequently required replacement or re-calibration. In addition, obsolescence issues made procurement of replacement or alternate parts very difficult. Similar problems have been experienced with chlorine detectors at other nuclear facilities.
Detroit Edison requests NRC approval of this License Amendment by May 24, 2002, with an implementation period of within 60 days following NRC approval.
Should you have any questions or require additional information, please contact Mr. Norman K. Peterson of my staff at (734) 586-4258.
Sincerely, Enclosures cc: T. J. Kim M. A. Ring NRC Resident Office Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission
USNRC NRC-02-0002 Page 3 I, WILLIAM T. O'CONNOR, JR., 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.
WILLIAM T. O'CO&INOR, Jh.
- Vice President - Nuclear Generatio-'
On this day of 2002 before me personally appeared William T. O'Connor, Jr., being first duly sworn and says that he executed the foregoing as his free act and deed.
-A Notdry Public K'-N M.REED Nri. : orroe County, MI My -ires 09/02/205
ENCLOSURE 1 TO NRC-02-0002 FERMI 2 NRC DOCKET NO. 50-341 OPERATING LICENSE NO. NPF-43 REQUEST FOR LICENSE AMENDMENT:
ELIMINATION OF THE CHLORINE DETECTION FUNCTION FROM THE CONTROL ROOM HEATING, VENTILATION AND AIR CONDITIONING SYSTEM DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGE to NRC-02-0002 Page 1 DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGE DESCRIPTION Fermi 2 Technical Requirements Manual (TRM) currently includes Specification No. TR 3.3.10 for the operability requirements of two redundant chlorine detectors located in the normal ventilation air intake of the Control Center Heating, Ventilation and Air Conditioning (CCHVAC) system. Upon detection of chlorine gas, with CCHVAC operating in the Normal Mode, the detectors automatically place the system in the Chlorine Mode. In this mode of operation, all outside air intake and exhaust dampers are closed to prevent ingress of toxic gas into the Control Center. The TRM specification is applicable at all times, except when the Control Room Emergency Filtration (CREF) system is operating in the Recirculation Mode.
Operation in the Recirculation Mode will not result in toxic chlorine levels since all air is passed through the Emergency Make-up and Recirculation filters before being discharged in the Control Center.
In the original plant design, it was assumed that a chlorine railroad tank car would be located on site for use in water treatment. Therefore, a chlorine detection system was added to the design of the CCHVAC system. The chlorine detection system was designed to protect the control room operators from toxic chlorine gas originating from a postulated chlorine leak. Instead of using a railroad tank car, twelve chlorine cylinders (1-ton each), located at the Circulating Water Pump House about 1000 feet from the control room, were used for on site chlorine storage. In 1992, the use of chlorine was discontinued. Since that time chlorine has not been stored at the Fermi site. The nearest significant source of an accidental chlorine release is from a postulated rupture of a 90-ton railroad tank car about 3.4 miles away from the plant. A re-evaluation of the need for the chlorine detection system has not been performed since the plant was originally licensed to operate.
Original plant operating license included Technical Specification (TS) 3.3.7.8, "Instrumentation
- Chlorine Detection System" until it was relocated to the TRM per License Amendment No.
115, implemented on June 11, 1998. The basis for the relocation was NRC Generic Letter 95-10, "Relocation of Selected Technical Specifications Requirements Related to Instrumentation."
The chlorine detection system was evaluated against the criteria in 10CFR50.36(c)(2)(ii) and it was determined that it did not meet this criteria for inclusion in the TS. The Fermi 2 TRM is incorporated by reference in the Updated Final Safety Analysis Report (UFSAR). A description of the chlorine detectors' automatic function and the abnormal operating procedures for the isolation of the control room, use of breathing apparatus and other protective measures, is included in UFSAR Sections 6.4, 7.3.5, 9.4.1, 12.2.2.1 and A.1.95. UFSAR Section A.1.95 states that the nearest source of an accidental chlorine release would be from the rupture of a 90 ton tank car on the railroad northwest of the plant.
to NRC-02-0002 Page 2 In recent years, the chlorine detection system reliability has been degrading. The chlorine detectors have frequently failed response time testing, and have been placed on an increased surveillance test frequency. The detectors have required extensive maintenance, and frequently required replacement or re-calibration. In addition, obsolescence issues made procurement of replacement or alternate parts very difficult. Similar problems have been experienced with chlorine detectors at other nuclear facilities.
As a result, Detroit Edison has recently completed a new study to evaluate the need for the chlorine detection system. The study included a survey to determine all chlorine sources in the vicinity of the plant. A probabilistic approach was utilized to evaluate the risk of incapacitating the control room operators from a chlorine release accident. The study concluded that the probability of a chlorine release having the potential to result in a significant concentration in the control room is below the threshold specified in Regulatory Guide 1.78, Revision 1, for considering chemical hazards in the evaluation of control room habitability. Therefore, the chlorine detection system and automatic isolation function are no longer necessary at Fermi 2.
This License Amendment requests the NRC review and approval of the elimination of the chlorine detection system and associated automatic function. The chlorine mode of the CCHVAC system will remain available for use by the operators; however, it will no longer be initiated automatically by the chlorine detectors. The new chlorine accident evaluation demonstrates that the probability of control room chlorine concentration reaching toxic limits, assuming no automatic or manual action, is below the acceptable level of risk specified in RG 1.78, Revision 1. The Abnormal Operating Procedures for isolating the control room to minimize the ingress of toxic fumes, use of emergency breathing air system, evacuation of non essential personnel, and orderly plant shutdown will remain in place.
The change described in this License Amendment complies with the Regulatory Positions in RG 1.78, Revision 1; however, it is being submitted to the NRC for approval because it involves the elimination of an automatic action. Nuclear Energy Institute (NEI) document 96-07, Revision 1, "Guidelines for 10CFR50.59 Implementation" indicates that NRC approval would be required for changes involving the permanent elimination of automatic actions for performing UFSAR described design functions. NEI 96-07, Revision 1, has been endorsed by the NRC in RG 1.187.
The NRC approved similar probabilistic evaluations for the deletion of chlorine detection systems from the Technical Specifications for several nuclear facilities including Prairie Island Nuclear Generating Plant, Units 1 and 2 (TAC No. M82518 and M82519) and Shearon Harris Nuclear Power Plant, Unit 1 (TAC No. 71858). Other similar amendments have been approved for Grand Gulf Nuclear Station, Unit 1 (December 3, 1986) and Braidwood Station, Units 1 and 2 (March 4, 1987).
Upon NRC approval of this amendment, Detroit Edison will delete the chlorine detection specification from the TRM and follow up with a plant modification and an update of the UFSAR to reflect the change in plant design.
to NRC-02-0002 Page 3 EVALUATION OF THE PROPOSED CHANGE Detroit Edison has recently performed a survey of the site and nearby industrial, commercial and transportation facilities in the vicinity of the Fermi 2 plant to determine stationary and mobile sources of chlorine. It was determined that no chlorine is stored on site and no significant amounts are stored in facilities within 5 miles of the site. The Berlin Wastewater Treatment facility near Trombly Road is the primary chlorine user within the 5-mile radius. This facility is located about 2 miles north of the Fermi 2 site. It receives and stores insignificant amount of chlorine in the form of up to four 150-pound cylinders. This amount of chlorine is easily screened out from further consideration based on the screening criteria in Regulatory Position 1.1 of Regulatory Guide (RG) 1.78, Revision 1.
The nearest railroad track to the Fermi site is the Canadian National Shore Line Subdivision (previously called Detroit and Toledo Shore Line Railroad) which passes approximately 3.4 miles from the plant at the closest point. Two other railroad tracks operated by the Norfolk Southern Railway (formerly Conrail or Penn Central Railroad) pass approximately 3.5 and 3.8 miles from the plant at their closest points. Liquid chlorine shipments typically involve about 485 railcars per year on the Canadian National Shore Line Subdivision railway, and about 350 railcars per year on the Norfolk Southern railways. The chlorine shipments utilize 90-ton railroad tank cars.
There is one chlorine packaging plant in Michigan, JCI Jones Chemicals, Inc. located in the city of Riverview about 12 miles north of the Fermi 2 site. It packages chlorine in 150-pound cylinders or one-ton containers. An accidental release of a one-ton container at the closest point of the nearby 1-75 Interstate Highway (about 4.1 miles from the site) is easily screened out from further consideration based on the screening criteria in Regulatory Position 1.2 of RG 1.78, Revision 1.
There is no barge traffic within 5 miles of the plant on Lake Erie. The United States Coast Guard confirmed that cargo shipping lanes are more than 5 miles away from the plant.
Based on the results of the survey, the only viable risk of reaching toxic chlorine levels in the Fermi 2 control room is from an accident involving a 90-ton railroad car which results in the release a significant amount of chlorine and is carried over to the control center HVAC air intake by prevailing winds blowing toward the site. RG 1.78, Revision 1, encourages licensees to use risk evaluations for cases where hazardous chemical releases do not meet the screening criteria in the RG. A risk evaluation was performed to calculate the probability of significant control room chlorine concentrations as a result of this postulated railroad tank car accident.
NUREG/CR-6624, "Recommendations for Revision of Regulatory Guide 1.78" provides the railcar accident probability based on the most recent statistics as 6.OE-07 per railcar-mile. It also provides a conditional release (spill) probability of 0.15 for rail cars. The NUREG further states to NRC-02-0002 Page 4 that accidents involving a spill of less than 10 percent of the cargo would not represent a significant hazard to control room operators and recommends a probability of 0.5 for spills of at least 10 percent of the cargo. Based on these estimates, the probability of a significant spill was determined by combining the probability of a railcar accident with the conditional release probability and the probability for a spill of at least 10 percent of the cargo. This resulted in a probability of 4.5E-08 per railcar-mile.
In order for the Fermi 2 control room to be impacted, the winds must be blowing toward the site and airborne chlorine concentrations must be sufficient, upon arrival of the chlorine plume at the CCHVAC air intake, to cause toxic levels in the control room.
Meteorological data from the years 1997 to 2000 was used to determine wind speeds and directions. It was assumed that all chlorine rail traffic occurs on the closest railroad track. The railroad track length within the 5-mile radius of the Fermi site was divided into segments corresponding to the applicable 16 wind direction sectors. Using an average ambient air temperature of 90-degrees Fahrenheit at the time of the assumed release, it was determined that a maximum of 21.77 percent of the liquid chlorine in the 90-ton rail car would immediately flash to vapor. The 90-degree temperature is a very conservative estimate of the 95t" percentile maximum area temperature. The diffusion equation for instantaneous puff release was used to calculate the chlorine concentrations at the Fermi 2 control room air intake. For conservatism, the air intake was assumed to be at ground level.
The probability of an adverse control room impact was determined by combining the probability of certain wind speed and direction in a sector, adjusted for plume width, with the probability of a railcar chlorine spill multiplied by the railroad segment length and the annual traffic. This was integrated over all railroad segments, wind sectors, wind speeds, wind directions and atmospheric stability classes E, F and G.
The total overall probability of a chlorine railcar accident and spill resulting in a control room toxic concentration of 10 parts per million, as defined in RG 1.78, Revision 1, was calculated to be 8.4E-07 per year. The RG states that a release that has the potential to result in a significant concentration in the control room need not be considered for further detailed evaluation if the release is of low frequency of 1.OE-06 per year or less. Therefore, the railcar accident risk evaluation meets this criterion in Regulatory Position 2 of the RG.
In summary, the proposed modification is acceptable because the postulated chlorine accident has such a low probability of occurrence that it is not considered to be a credible event. This evaluation is based on several conservative assumptions and does not take credit for manual operator action to isolate the control room upon detecting chlorine odor or upon offsite notification. It also takes no credit for use of the emergency breathing air system by the operators in the control room.
ENCLOSURE 2 TO NRC-02-0002 FERMI 2 NRC DOCKET NO. 50-341 NRC LICENSE NO. NPF-43 REQUEST FOR LICENSE AMENDMENT:
ELIMINATION OF THE CHLORINE DETECTION FUNCTION FROM THE CONTROL ROOM HEATING, VENTILATION AND AIR CONDITIONING SYSTEM 10CFR50.92 SIGNIFICANT HAZARDS CONSIDERATION to NRC-02-0002 Page 1 10CFR50.92 SIGNIFICANT HAZARDS CONSIDERATION In accordance with 10CFR50.92, Detroit Edison has made a determination that the proposed change of eliminating the chlorine detection function from the Control Room Heating, Ventilation and Air Conditioning (CCHVAC) system involves no significant hazards consideration. This change does not involve a significant hazards consideration for the following reasons:
- 1. The change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The chlorine detection system was originally added to the plant design when it was assumed that a chlorine rail car would be located on site for use in water treatment purposes; however, one-ton chlorine cylinders were used instead. In 1992, the use of chlorine for on site water treatment was discontinued. There is no chlorine stored on site and no significant amounts are stored at any other facility within the 5-mile radius of the plant. The only credible accident involving a chlorine release that could be carried into the control room is from a chlorine rail car accident on the three railroad tracks 3.4 to 3.8-miles away from the site. The probability of a rail car accident and spill of chlorine is not affected by the removal of the chlorine detectors located in the normal air intake for the CCHVAC system; therefore, only the consequences of the event must be addressed as a result of the proposed change.
The chlorine detectors in the control room ventilation air intake are intended to provide protection to the control room occupants in the event of an accidental offsite chlorine release.
Detroit Edison has performed a probabilistic risk assessment to determine the probability of reaching toxic chlorine concentration levels of 10 parts per million in the control room as a result of a chlorine railcar accident and spill within 5 miles of the plant. The probability analysis took no credit for any automatic or manual action to isolate the control room. The results of the analysis show that the total probability of 8.4E-07 per year is below the 1.OE-06 threshold specified in Regulatory Guide (RG) 1.78, Revision 1. Therefore, since the probability analysis results meet the RG criteria, the elimination of the chlorine detection function will not significantly increase the consequences of an offsite chlorine release.
- 2. The change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The probabilistic risk assessment evaluation demonstrates that the likelihood of creating hazardous conditions in the control room as a result of a chlorine accident is very small. RG 1.78, Revision 1, states that events of such low frequencies do not need to be considered in the plant design because the resultant low levels of radiological risk are considered acceptable. The probabilistic assessment assumed no automatic or manual action to isolate the control room or to filter outside air before it is discharged in the control room. The to NRC-02-0002 Page 2 evaluation did not rely on any structure, system or component to perform a specific function; therefore, the elimination of the chlorine detection system does not create the potential for a new or different kind of accident from any accident previously evaluated.
- 3. The change does not involve a significant reduction in the margin of safety.
The elimination of the chlorine detection system will not affect the protection of the control room operators from the hazard of an offsite chlorine release. No significant amounts of chlorine are stored within 5 miles of the plant and the only chlorine accident risk is from. a railroad car accident over 3 miles away. The probabilistic evaluation demonstrates the low risk associated with a chlorine accident that would incapacitate the operators such that their functions in mitigating a radiological event are impacted. Since the Regulatory Positions in RG 1.78, Revision 1 are satisfied, deletion of the chlorine detection system will not result in a significant reduction in the margin of safety.