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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
Wlilliam T. O'Connor, Jr.
Vice President, Nuclear Generation Fermi 2 6400 North Dixie llhzy., Newport, Michigan 48166 Tel: 734-586-5201 Fax: 734-5864172 DTE Energy 10 CFR 50.90 March 19, 2004 NRC-04-0006 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 to Revise Technical Specification 3.3.6.1, "Primary Containment Isolation Instrumentation" Pursuant to 10 CFR 50.90, Detroit Edison hereby requests the following amendment.
The proposed change would correct a formatting error introduced during conversion to Improved Technical Specifications by replacing "1 per room" with "2" for the Required Channels Per Trip System for the Reactor Water Cleanup Area Ventilation Differential Temperature - High primary containment isolation instrumentation.
This inaccuracy was introduced during the change to the Improved Standard Technical Specifications (ISTS).
Detroit Edison requests approval of the proposed License Amendment by March 18, 2005, with the amendment being implemented within 90 days following approval. contains an evaluation, including a significant hazards consideration, of the proposed change. Enclosure 2 contains a copy of the existing Technical Specification (TS) page marked up to show the proposed change. Enclosure 3 contains a copy of the proposed revised TS page. Enclosure 4 provides marked up pages of the existing TS Bases showing the proposed changes (for information only).
There are no new regulatory commitments associated with this proposed change.
USNRC NRC-04-0006 Page 2 Detroit Edison has reviewed the proposed change against the criteria of 10 CFR 51.22 for environmental considerations. The proposed amendment is confined to 10 CFR 51.22(c)(1 0)(ii) involving record keeping, reporting, or administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.
In accordance with 10 CFR 50.91, a copy of this application, with enclosures, is being provided to the designated Michigan Official.
If you have any questions regarding this submittal, please contact Norman K.
Peterson at (734) 586-4258.
Sincerely,
Enclosures:
- 1. Fermi 2 Nuclear Power Plant Evaluation for License Amendment Request
- 2. Proposed Technical Specification Changes (Mark-Up)
- 3. Proposed Technical Specification Revised Page
- 4. Enclosure 4 provides marked up pages of the existing TS Bases showing the proposed changes (for information only).
cc: H. K. Chemoff M. A. Ring NRC Resident Office Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission
USNRC NRC-04-0006 Page 3 1, 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'CONNOR(JR.
Vice President - Nuclear Ge tion On this _ _9_ day of _______, 2004 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.
S'\
N - - - -
- x t - -
Noitary Public KARENI M.REED
-N' Fotary Pubffc, L&Mnas Cogaruny. ~'A(l
.. My Commission Expiross 09/02/2005
ENCLOSURE 1 to NRC-04-0006 FERMI 2 NUCLEAR POWER PLANT EVALUATION FOR LICENSE AMENDMENT REQUEST
Enclosure I to NRC-04-0006 Page 1 FERMI 2 NUCLEAR POWER PLANT EVALUATION
SUBJECT:
Revise Technical Specification (TS) 3.3.6.1, Primary Containment Isolation Instrumentation.
- 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
- 7. REFERENCES to NRC-04-0006 Page 2
1.0 DESCRIPTION
The proposed change would replace "1 per room" with "2" for the Required Channels Per Trip System for the Reactor Water Cleanup (RWCU) Area Ventilation Differential Temperature -
High isolation, Function 5.c of Table 3.3.6.1-1 of Technical Specification (TS) 3.3.6.1, Primary Containment Isolation Instrumentation. This formatting error was introduced during TS Amendment No. 134 to implement the Improved Standard Technical Specification (ISTS),
NUREG 1433.
As a result of this formatting error, the actions specified by TS 3.3.6.1, Primary Containment Isolation Instrumentation, are inconsistent with other RWCU isolation instruments listed in Table 3.3.6.1-1. Administrative controls have been placed in the TS Bases using the guidance provided in NRC Administrative Letter 98-10, "Dispositioning Of Technical Specifications That Are Insufficient To Assure Plant Safety". The administrative controls are in place as a conservative measure, to ensure consistent implementation of the TS until implementation of this amendment request.
2.0 PROPOSED CHANGE
The proposed change would restore the pre-Improved Technical Specification (ITS) value of "2" for the Required Channels Per Trip System for the RWCU Area Ventilation Differential Temperature - High on Table 3.3.6.1-1 of TS 3.3.6.1, Primary Containment Isolation Instrumentation. Additionally, an explanatory note is added to Table 3.3.6.1-1 of TS 3.3.6.1, Primary Containment Isolation Instrumentation
3.0 BACKGROUND
The RWCU Area Ventilation Differential Temperature - High primary containment isolation instrumentation is provided to detect a leak from the RWCU system. The isolation signal is redundant to the RWCU Area Temperature - High isolation signal and diverse to the high differential flow instrumentation for the hot portions of the RWCU system. If a small leak were to occur and continue without isolation, offsite dose limits could be reached. Credit for RWCU Area Temperature - High and RWCU Area Ventilation Differential Temperature - High instruments is not taken in any transient or accident analysis in the Updated Final Safety Analysis (UFSAR), since bounding analyses are performed for large breaks such as recirculation or main steam line breaks.
RWCU Area Temperature and Aiea Ventilation Differential Temperature signals are initiated from temperature elements that are located in the area or room that is being monitored. The RWCU Area Temperature instrumentation monitors 6 areas. The RWCU Area Ventilation Differential Temperature instrumentation monitors 4 rooms; the A RWCU Pump room, B RWCU Pump Room, RWCU Heat Exchanger Room, and RWCU Phase Separator Room.
to NRC-04-0006 Page 3 In the conversion to ISTS, the table column for "Minimum Operable Channels Per Trip System" was changed to "Required Channels Per Trip System".
Twelve thermocouples provide input to the RWCU Area Temperature - High Function (two per area). Two channels per area are required to be operable to ensure that no single instrument failure can preclude the isolation function. TS Amendment No. 134 which implemented the ISTS, correctly changed the "6" (Minimum Operable Channels Per Trip System) to "1 per area" (Required Channels Per Trip System) for this function. This change was correct because it ensures at least one channel per area is operable.
Eight thermocouples provide input to the RWCU Area Ventilation Differential Temperature -
High Function. Two thermocouples are required for each channel, one each in the inlet and outlet of the room cooling systems, for a total of four channels (one channel per room). TS Amendment No. 134 which implemented the ISTS, incorrectly formatted the "2" (Minimum Operable Channels Per Trip System) to "1 per room" ( Required Channels Per Trip System) for this function. This change was incorrect because Fermi's accepted design is four channels (one channel per room) for RWCU Area Ventilation Differential Temperature - High. The correct number of Required Channels Per Trip System is two.
4.0 TECHNICAL ANALYSIS
The proposed license amendment restores "2" as the number of Required Channels Per Trip System for the RWCU Area Ventilation Differential Temperature - High isolation, Function 5.c of Table 3.3.6.1-1 of TS 3.3.6.1, Primary Containment Isolation Instrumentation.
This formatting error was introduced during TS Amendment No. 134 which implemented the ISTS (TAC NO. MA1465). In Table A, Administrative Changes to Current Technical Specifications, of the NRC Safety Evaluation (ITS Section 3.3.6.1, A.13), the change from "2" to "1/room" was described as an administrative change to better specify the number of channels for each trip system. This change was made to match the nomenclature used in ISTS and to specify the number of instruments per room.
The Fermi TS bases for the RWCU Area Ventilation Differential Temperature - High isolation Function were reworded from the ISTS bases during conversion to ITS. The changes were made to reflect the plant specific instrumentation at Fermi. The bases acknowledge that there are a total of four Area Differential Temperature - High monitors for RWCU, one per room.
The Fermi design for the RWCU Area Ventilation Differential Temperature - High isolation Function does not match the design used in the ISTS and this change to the number of Required Channels Per Trip System should not have been made. Fermi is designed with one differential temperature monitor per room as opposed to the ISTS design of two differential temperature monitors per room. The Fermi design for the RWCU Area Ventilation Differential Temperature -
Enclosure I to NRC-04-0006 Page 4 High isolation Function is described in a License Amendment Request (Reference 1) dated December 22, 1988, subsequently issued to Fermi as TS Amendment No. 41 (TAC NO. 72759).
In summary, the proposed change to the RWCU Area Ventilation Differential Temperature -
High isolation, Function 5.c of Table 3.3.6.1-1 of TS 3.3.6.1, Primary Containment Isolation Instrumentation, restores the TS to be consistent with the Fermi 2 design.
5.0 REGULATORY SAFETY ANALYSIS:
5.1 No Significant Hazards Consideration Detroit Edison has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as described below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change restores the number of Required Channels Per Trip System of the RWCU Area Ventilation Differential Temperature - High isolation, Function 5.c of Table 3.3.6.1-1 of TS 3.3.6.1, Primary Containment Isolation Instrumentation, to its pre-ITS value and adds an explanatory note. No changes in operating practices or physical plant equipment are created as a result of this change. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated;
- 2. Does the proposed change create the possibility of a new or different type of accident from any accident previously evaluated?
-Response: No.
The proposed change restores the number of Required Channels Per Trip System of the RWCU Area Ventilation Differential Temperature - High isolation, Function 5.c of Table 3.3.6.1-1 of TS 3.3.6.1, Primary Containment Isolation Instrumentation, to its pre-ITS value and adds an explanatory note. No physical change in plant equipment will result from this proposed change. Therefore, the proposed change does not create the possibility of a new or different type of accident from any previously evaluated.
to NRC-04-0006 Page 5
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The proposed change is administrative in nature and only provides a correction to Table 3.3.6.1-1 of TS 3.3.6.1, Primary Containment Isolation Instrumentation, as well as an explanatory note. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
5.2 Applicable Regulatory Requirements / Criteria The technical content of TS 3.3.6.1 will not be changed as a result of this proposed amendment. The proposed change corrects a formatting error introduced during implementation of the ISTS and is judged to have no impact on regulatory requirements or regulatory criteria.
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not adversely affect the common defense and security or the health and safety of the public.
6.0 ENVIRONMENTAL CONSIDERATION
The proposed amendment is confined to 10 CFR 51.22(c)(l 0)(ii) changes involving record keeping, reporting, or administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(l0). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.
7.0 REFERENCES
- 1. Letter to NRC: NRC-88-0279, Proposed Technical Specification Change (License Amendment) - Isolation Actuation Instrumentation (3/4.3.2), dated December 22, 1988.
ENCLOSURE 2 to NRC-04-0006 PROPOSED TECHNICAL SPECIFICATION CHANGE (MARK-UP)
INCLUDED PAGE:
TS 3.3-58
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.61.1 (page 4 of 4)
Primary Containment Isolation Instrunentation APPLICABLE CONDITIONS HODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE SYSTEM ACTION C.1 REOUIREIENTS VALUE
- 5. Reactor Water Cleanup (RWCU) System Isolation
- a. Differential 1.2.3 1 F SR 3.3.6.1.1 . 63.4 gpm Flow - High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 b Aea1.2.3 1 per SR 3.3.6.1.1 s 183PF SR 3.3.6.1.2 2 gh area SR 3.3.6.1.4 SR 3.3.6.1.5
- c. Area Ventilation 1.2.3 - 1per F SR 3.3.6.1.1 s 53-F Differential - 0r-- SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.5
- d. SLC System Initiation 1.2 2 (b) I SR 3.3.6.1.5
- e. Reactor Vessel Water 1.2.3 2 F SR 3.3.6.1.1 r 103.8 inches Level - Low Low. SR 3.3.6.1.2 Level 2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5
- f. Manual Initiation 1.2.3 G SR 3.3.6.1.6 NA
- 6. Shutdown Cooling System Isolation
- a. Reactor Steam Dome 1.2.3 1 F SR 3.3.6.1.1 - 95.5 psig Pressure - High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5
- b. Reactor Vessel Water 3.4.5 2(c) J - SR 3.3.6.1.1 r 171.9 inches Level - Low. Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5
- c. Manual Initiation 1.2.3 1arr G SR 3.3.6.1.6 NA v I ve (b) SLC System Initiation only inputs into one of the two trip systems.
-(c) Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
(d) Fermi design requires only 1 channel per trip system to be I add OPERABLE to maintain isolation capability. 1 FERMI - UNIT 2 3.3 58 Amendment No. 134
ENCLOSURE 3 to NRC-04-0006 PROPOSED TECHNICAL SPECIFICATION REVISED PAGE INCLUDED PAGE:
TS 3.3-58
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 4)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS HODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE
- 5. Reactor Water Cleanup (RWCU) System Isolation
- a. Differential 1.2.3 1 F SR 3.3.6.1.1 s 63.4 gpm Flow- High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5
- b. Area Temperature- 1.2.3 1 per F SR 3.3.6.1.1 s 1830 F High area SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5
- c. Area Ventilation 1.2.3 2 (d) F SR 3.3.6.1.1 s 530 F Differential SR 3.3.6.1.2 I Temperature- High SR 3.3.6.1.4 SR 3.3.6.1.5
- d. SLC System Initiation 1.2 2 (b) I SR 3.3.6.1.5 NA
- e. Reactor Vessel Water 1.2.3 2 F SR 3.3.6.1.1 > 103.8 inches Level - Low Low. SR 3.3.6.1.2 Level 2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5
- f. Manual Initiation 1.2.3 1 lper G' SR 3 .3 .6.1.6 NA va ve
- 6. Shutdown Cooling System Isolation
- a. Reactor Steam Dome 1.2.3 1 F SR 3.3.6.1.1 5 95.5 psig Pressure- High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5
- b. Reactor Vessel Water 3.4.5 2(c) 3 SR 3.3.6.1.1 k 171.9 inches Level - Low. Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5
- c. Manual Initiation 1.2.3 G SR 3.3.6.1.6 NA (b) SLC System Initiation only inputs into one of the two trip systems.
(c) Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
(d) Fermi design requires only 1 channel per trip system to be OPERABLE to maintain isolation capability. I FERMI - UNIT 2 3.3-58 Amendment No. a/
ENCLOSURE 4 to NRC-04-0006 PROPOSED TECHNICAL SPECIFICATION BASES CHANGE (FOR INFORMATION ONLY)
INCLUDED PAGES:
B 3.3.6.1-19 B 3.3.6.1-24 B 3.3.6.1-25 B 3.3.6.1-29 B 3.3.6.1-32
Primary Containment Isolation Instrumentation B 3.3.6.1 BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)
The Differential Flow-High Allowable Value ensures that a break of the RWCU piping is detected.
This Function isolates the RWCU isolation valves.
5.b.. 5.c. Area and Area Ventilation Differential Temperature -High RWCU area and area ventilation differential temperatures are provided to detect a leak from the-RWCU System. The isolation occurs even when very small leaks have occurred and is diverse to the high differential flow instrumentation for the .hot portions of the RWCU System. If the small leak continues without isolation, offsite dose limits may be reached. Credit for these instruments is.not taken in any transient or accident analysis in the UFSAR, since bounding analyses are performed for large breaks such as recirculation or MSL breaks.
Area and area ventilation differential temperature signals are initiated from temperature elements that are located in the area or room that is being monitored. Twelve thermocouples provide input to the Area Temperature -High Function (two per area). Two channels per area are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.
Eight thermocouples provide input to the Area Ventilation Differential Temperature -High Function. The output of these thermocouples is used to determine the differential temperature in four rooms containing RWCU piping and equipment. Each channel consists of a differential temperature instrument that receives inputs from thermocouples that are located in the inlet and outlet of the room cooling system and for a total of four available channels (one per roo One channel per trip system is required to a and Area Ventilation Differential Temperature -High Allowable Values are set low enough to detect a leak be OPERABLE to equivalent to 25 gpm.
maintain isolation These Functions isolate the RWCU isolation valves, as capability appropriate.
FERMI - UNIT 2 B 3.3.6.1 -19 Revision 0
Primary Containment Isolation Instrumentation B 3.3.6.1 BASES ACTIONS (continued)
Condition. However, the Required Actions for inoperable primary containment isolation instrumentation channels provide appropriate compensatory measures for separate inoperable channels. As such, a Note has been provided that allows separate Condition entry for each inoperable primary containment isolation instrumentation channel.
A.1 Because of the diversity of sensors available to provide isolation signals and the redundancy of the isolation design, an allowable out of service time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Funttions 1.f,-2.a, 2.c. and 6.b'and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for-Functions other than Functions 1.f. 2.a. 2.c. and 6.b has been 'shown to be acceptable (Refs. 5 and 6) to permit restoration of any inoperable channel to OPERABLE status. This out of service time is only acceptable provided the associated Function is still maintaining isolation capability (refer to Required Action B.1 Bases). If the inoperable channel cannot be restored to OPERABLE status within the allowable out of service time, the channel must be placed in the' tripped condition per Required Action A.1, Placing the inoperable channel in trip would conservatively compensate for the inoperability, restore capability to accommodate a single failure, and allow operation to continue with no further restrictions. Alternately, if it is not desired to place the channel in .trip (e.g., as in the case where placing the inoperable channel in trip would result in an isolation), Condition C must be entered and its Required Action taken. As an administrative ctrol (fraI c-12)
Temperature-High. iuiL,-i wuelts inoperI able TS 3;3.6.1,
--Codition 1.1 should be entered.
B.1 Required Action B.1 is intended to ensure that appropriate actions are taken if multiple, inoperable. untripped channels within the same Function result in redundant automatic isolation capability being lost for the associated penetration flow path(s). The HSL Isolation Functions are considered to b6 maintaining isolation capability when sufficient channels are OPERABLE or in trip, such that both trip systems will .generate a trip signal .from the given Function on a valid signal. The other isolation functions are considered to be maintaining isolation capability when sufficient channels are OPERABLE or'in trip, such that one Revision 21 B 3.3.6.1-24 FERM1I -
UNIT 2 FERMI - UNIT 2 B 3.3.6.1-24 Revision 21
Primary Containment Isolation Instrumentation B 3.3.6.1 BASES ACTIONS (continued) trip system will generate a trip signal from the given Function on a valid signal.' This ensures that one of the
- two PCIVs in the associated penetration flow path can receive an isolation signal from the given Function. For Functions l.a. lb,1.d, and l.f. this would require both trip systems to have one channel OPERABLE or in trip. For Function l.c. this would require both trip systems to have one channel, associated with each MSL, OPERABLE or in trip.
For Functions 1.e and 1.g, each Function consists of channels that monitor several locations within a given area (e.g., different locations within the main steam tunnel area). Therefore, this would require both trip systems-to have one channel per location OPERABLE or in trip. For Functions 2.a. 2.b. 2.c. 3.b. 3.c. 4.b. 4.c. 5.e. and 6.b, this would require one trip system to have two channels.
each OPERABLE or in trip. For Functions 3.a, 3.d. 4.a. 4.d; 5.a'. 5;.d and.6.a. this would require one trip system to Function 5.c -P have one channel OPERABLE or intrip. >< Function\ 5.b 6ie, czeh mRetiz rconsists of channels that monitor consists of four several different locations. Therefore, this would require h I one pPG canne, ~....
one channel per location to be OPERABLE or in trip (the ,
channels are not required to be in the same trp system).
room, and would The Condition does not include the Manual Initiation Functions (Functions 1.h. 2.d, 3.f.'4.f. 5.f, and 6.c).
require both trip since they are not assumed in any accident or transient systems to have one analysis. Thus. a total loss of manual.initiation capability for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (as allowed by Required Action A.1) channel issllwed A OPERABLE.- Qdto . st be used for an inoperable RWCU Area OPERABLE.enn Differential Temperature-High instrument Is reconizd 1at-R~lcation of Condition B vtn1Enl-chane o RCU re~tdl ati n PifsrflT~empsernatutre~-
-High is inopeal is cons id~nSn this cntext...
However. in the most tive rea Condition B.
isolation ca y. for RWCV Area Venti ati erential Tem r a given room is not maintained
__l7Muel s inprable.
Thg Completion Time is intended to allow the operator time to evaluate and repair any discovered inoperabilities. The.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is acceptable because it minimizes risk while allowing time for'restoration or tripping of channels.
3.36.1-5 Rvisin 2 UNI 2 FERM FERMI - UNIT 2 B 3.3.6.1-25 Revision 21
Primary Containment Isolation Instrumentation B 3.3.'6.1.
BASES SURVEILLANCE REQUIREMENTS (continued)
.(Refs. 5 and 6) assumption of the average time required to perform channel surveillance. That analysis demonstrated that the testing allowance does not significantly reduce the probability that the PCIVs will isolate the penetration flow path(s) when'necessary.'
a ve control'(reference 12 Ventilation Di fre~in1X ^ 4:RX nstrument is allowed to l DpeieTorup to nce testing.
SR 3.3.6.1:1.
Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that.a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels.monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. A CHANNEL CHECK will detect gross channel failure; thus. it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.
Agreement criteria are determined by the plant staff based on a-combination of the channel instrument uncertainties, including indication and readability.- If a channel is outside the criteria, it may began indication that the
'instrument has drifted outside its limit.
The Frequency is based on operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays
- associated with the channels required by the LCO.
SR 3.3.6.1.2 and SR 3.3.6.1.6 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the required contact(s) of a channel relay may be performed by the.
verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL B 3.3.6.1-29 Revision 21 FERMI - UNIT22 FERMI - UNIT B 3.3.6.1-29 Revision 21
Primary Containment Isolation Instrumentation B.3.3.6.1 BASES SLPRVEILLANCE.REQUIREMENTS (continued)
ISOLATION SYSTEM RESPONSE TIME tests are conducted on an 18 month STAGGERED TEST BASIS. The 18 month Frequency is consistent with the typical industry refueling cycle and is based.upon plant operating experience that shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.
- REFERENCES 1. UFSAR. Section 6.3.
- 2. UFSAR, Chapter 15.
- 3. NEDO-31466. 'Technical Specification Screening Criteria Application and Risk Assessment."
Novenber 1987. .
- 4. UFSAR, Section 4.5.2.4.
- 5. NEDC-31677P-A. Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation."
July 1990..
- 6. NEDC-30851P-A Supplement 2, "Technical Specifications
-Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation." March 1989.
- 7. UFSAR. Section 7.3.
- 8. UFSAR. Section 6.2.
- 9. NEDO-31400. 'Safety Evaluation for Eliminating the BWR MSIV Closure Function and Scram Function of the MSL Radiation Monitor.' Licensing Topical Plant Report for
.BROG.
- 10. NEDO-3Z291. .System Analysis for Elimination of Selected Response Time Testing Requirements." January 1994; and Fermi-2 SER for Amendment 111, dated April
- 18. 1997.
- 11. NEDO-32291-A, Supplement 1. 'System Analyses for The
- Elimination of Selected Response Time Testing Requirement. October 1999.' _ __
FERMNIT2
- B .3..1-2 Reisin 2 FERMI - UNIT 2 -B3.3.6.1-32 Revisioh 21'