Letter Sequence Response to RAI |
---|
|
|
|
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] Category:Technical Specifications
MONTHYEARML23310A1492023-12-0808 December 2023 Issuance of Amendment No. 227 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements ML23243A8852023-09-18018 September 2023 Issuance of Amendment No. 225 Regarding Revision of Technical Specifications 3.7.2, Emergency Equipment Cooling Water, Emergency Equipment Service Water and System and Ultimate Heat Sink (Exigent Circumstances) 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 ML23122A2332023-06-26026 June 2023 Issuance of Amendment No. 223 Regarding Revision of Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements 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) ML21335A2802022-04-0707 April 2022 Issuance of Amendment No. 222 Regarding Revision of Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Several Editorial Changes ML22032A1572022-01-19019 January 2022 Technical Requirements Manual - Vol. 1 Revision 130 Dated 01/19/2022 ML21251A1602021-08-17017 August 2021 Technical Requirements Manual - Vol 1 - (Revision 127 Dated 08/17/2021) ML21053A2022021-02-0101 February 2021 Technical Requirements Manual, Vol 1 - Revision 124 Dated 02/01/2021 ML20233A8382020-10-0505 October 2020 Issuance of Amendment No. 216 - Revision to Technical Specification in Response to GE Energy-Nuclear's 10 CFR Part 21 Safety Communication SC05-03 ML18165A2022018-09-13013 September 2018 Issuance of Amendment Regarding the Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities ML16270A5312016-12-15015 December 2016 Fermi, Unit 2, Preoperational Test, Startup Tests and Other Items ML16069A0062016-04-20020 April 2016 Issuance of Amendment Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008-01, Managing Gas Accumulation ML16054A6372016-04-0505 April 2016 Issuance of Amendment to Revise License Amendment Request to Revise Technical Specification Section 3.5.1, Emergency Core Cooling System - Operating Report ML16039A1212016-02-18018 February 2016 Corrections to Amendment No. 201 Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program Based on Technical Specification Task Force (TSTF) Change TSTF-425 ML15233A0842015-09-29029 September 2015 Issuance of Amendment License Amendment Request to Revise the Emergency Action Level Scheme for the Fermi Emergency Plan ML15155B4162015-07-14014 July 2015 Ferm, Uniti 2 - Issuance of Amendment Revise Technical Specifications by Relocating Surveillance Frequencies to Licensee Control in Accordance with Technical Specification Task Force Traveler 425, Revision 3 ML15096A0432015-05-0707 May 2015 Issuance of Amendment Cyber Security Plan Implementation Schedule (Tac No. MF4366) NRC-14-0049, Supplement to License Amendment Request to Revise Technical Specification Surveillance Requirements for Direct Current Batteries2014-06-19019 June 2014 Supplement to License Amendment Request to Revise Technical Specification Surveillance Requirements for Direct Current Batteries ML13364A1312014-02-10010 February 2014 Issuance of Amendment Measurement Uncertainty Recapture Power Uprate ML13346B0672014-02-0404 February 2014 Issuance of Amendment Relocation of Pressure and Temperature Curves to a Pressure Temperature Limits Report ML13112A1422013-05-13013 May 2013 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-522, Using 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-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-12-0037, 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 NRC-12-0071, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2012-11-13013 November 2012 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process NRC-12-0005, Proposed License Amendment to Revise the Residual Heat Removal Suppression Pool Cooling Flow Rate in Technical Specification Surveillance Requirement 3.6.2.3.22012-01-10010 January 2012 Proposed License Amendment to Revise the Residual Heat Removal Suppression Pool Cooling Flow Rate in Technical Specification Surveillance Requirement 3.6.2.3.2 NRC-12-0004, Proposed License Amendment to Modify Technical Specification Surveillance Requirements for Safety Relief Valves2012-01-10010 January 2012 Proposed License Amendment to Modify Technical Specification Surveillance Requirements for Safety Relief Valves 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-11-0030, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2011-08-12012 August 2011 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. 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. ML1013408512010-05-14014 May 2010 Revised Clean TS Pages NRC-10-0003, Proposed License Amendment to Revise the Core Spray Flow Requirement of Technical Specification Surveillance Tests SR 3.5.1.8 and SR 3.5.2.62010-01-0404 January 2010 Proposed License Amendment to Revise the Core Spray Flow Requirement of Technical Specification Surveillance Tests SR 3.5.1.8 and SR 3.5.2.6 NRC-09-0022, Proposed License Amendment to Revise the Degraded Voltage Function Requirements of Technical Specification Table 3.3.8.1-1 to Reflect Undervoltage Backfit Modification2009-06-10010 June 2009 Proposed License Amendment to Revise the Degraded Voltage Function Requirements of Technical Specification Table 3.3.8.1-1 to Reflect Undervoltage Backfit Modification NRC-08-0061, Proposed License Amendment to Remove Statements Related to Nuclear Power Plant Staff Working Hours in Technical Specification2008-09-12012 September 2008 Proposed License Amendment to Remove Statements Related to Nuclear Power Plant Staff Working Hours in Technical Specification ML0812808342008-06-25025 June 2008 Tech Spec Pages for Amendment 180 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 Requirements ML0807900262008-03-17017 March 2008 Issuance of Amendment Technical Specification Change to Emergency Diesel Generator Surveillance Requirements NRC-08-0001, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2008-01-15015 January 2008 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process ML0721404442007-08-0101 August 2007 Tech Spec Pages for Amendment Consolidated Line Item Improvement Process (Cllip) for Technical Specification Change (TSTF-427) to Add Limiting Condition for Operation (LCO) 30.9 Regarding the Unavailability of Barriers ML0721407632007-08-0101 August 2007 Technical Specification 3.8.1 Extension of the Completion Time for an Inoperable Diesel Generator Amendment ML0715002322007-04-12012 April 2007 Technical Specifications, 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-07-0012, Proposed License Amendment to Revise the Minimum Emergency Diesel Generator Voltage in Technical Specification 3.8.1 Surveillance Requirements2007-03-19019 March 2007 Proposed License Amendment to Revise the Minimum Emergency Diesel Generator Voltage in Technical Specification 3.8.1 Surveillance Requirements NRC-07-0001, Application for Technical Specification Change (TSTF-427) to Add LCO 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2007-01-26026 January 2007 Application for Technical Specification Change (TSTF-427) to Add LCO 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process ML0622004402006-08-0707 August 2006 Technical Specifications, Changes to Address Issues Related to an Inconsistency That Was Inadvertently Introduced During Conversion to Improved TSs When 1 Per Room Replaced 2 as the Required Channels Per Trip System NRC-06-0044, Response to Request for Additional Information for Revision to License Amendment Request to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation2006-07-12012 July 2006 Response to Request for Additional Information for Revision to License Amendment Request to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation NRC-06-0040, Proposed License Amendment Request to Extend the Completion Time for Technical Specification 3.8.1 for an Inoperable Emergency Diesel Generator2006-07-12012 July 2006 Proposed License Amendment Request to Extend the Completion Time for Technical Specification 3.8.1 for an Inoperable Emergency Diesel Generator ML0604800392006-02-15015 February 2006 Tech Spec Pages for Amendment 172 Regarding Consolidated Line Item Improvement for Snubbers ML0603704972006-02-0606 February 2006 Tech Spec Pages for Amendment 171 Allowed Outage Time Extension for Emergency Diesel Generator 12 for One Specific Incident 2023-09-18
[Table view] |
Text
Donald K. Cobb Assistant Vice President, Nuclear Generation Fermi 2 6400 North l)ixie lHwy., Newport, MI 48166 Tel: 73.1.586.5201 Fax: 7:34.586.4172 DTE Energy-July 12, 2006 10 CFR 50.90 NRC-06-0044 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001
References:
- 1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
- 2) Detroit Edison Letter to NRC "Proposed License Amendment to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation," NRC-04-0006, dated March 19, 2004.
- 3) Detroit Edison Letter to NRC "Revision to License Amendment Request to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation," NRC-05-0016, dated March 17, 2005.
- 4) Detroit Edison Letter to NRC "Revision to License Amendment Request to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation," NRC-06-0001, dated January 31, 2006.
Subject:
Response to Request for Additional Information for Revision to License Amendment Request to Revise Technical Specification 3.3.6.1, "Primary Containment Isolation Instrumentation" In Reference 4, Detroit Edison requested NRC approval of a proposed license amendment. The proposed change addresses an inconsistency that was inadvertently introduced during conversion to Improved Technical Specifications.
This letter provides revised pages to our request for amendment submittal (Reference
- 4) in response to a Staff request for additional information and clarification, dated May 2, 2006 and telephone calls of June 2, 2006 and June 21, 2006. Enclosure 1 of Reference 4 is revised by Enclosure I of this letter. The attached Enclosures 2, 3, and 4 replace Enclosures 2, 3, and 4 of Reference 4.
-A60o
USNRC NRC-06-0044 Page 2 provides marked up replacement pages for Technical Specification (TS) 3.3.6.1. Enclosure 3 provides revised TS pages. Enclosure 4 provides revised pages for the Technical Specification Bases (for information only). These changes are minor and do not result in any change to the No Significant Hazards Consideration determination.
TS 3.3.6.1 and TS 3.3.6.1 Bases that apply to this amendment request have been reviewed to ensure the use of the terms "area" and "room" are applied consistently and in accordance with Fermi 2 plant nomenclature.
There are no new regulatory commitments associated with this proposed change.
If you have any questions regarding this submittal, please contact Ronald W. Gaston at (734) 586-5197.
Sincerely,
Enclosures:
- 1. Evaluation For License Amendment Request
- 2. Proposed Technical Specification Change (Mark-Up)
- 3. Proposed Technical Specification Change
- 3. Marked up pages of the existing TS Bases showing the proposed changes (for information only) cc: D. H. Jaffe C. A. Lipa NRC Resident Office Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission
USNRC NRC-06-0044 Page 3 I, Donald K. Cobb, do hereby affirm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
D. K. dobb '
Assistant Vice President Nuclear Generation On this /2 day of J -J,2006 before me personally appeared Donald K. Cobb, being first duly sworn and says that he executed the foregoing as his free act and deed.
1'otary Public KAMlNL ItE NOTARY PMUMO. STATEOFM COUMYOF&ROE cOn*CO* TO X S SV2011 ACTNGINOOJNYOF F4au-ýc
ENCLOSURE I to NRC-06-0044 EVALUATION FOR LICENSE AMENDMENT REQUEST
USNRC NRC-06-0044 Page 2 The last paragraph on page 6 of Enclosure I of Reference 4 is revised to read:
Fermi 2 has diversity in its RWCU temperature isolation instrumentation in that Area Ventilation Differential Temperature - High and the RWCU Area Temperature - High monitor for a small leak in the same rooms. The reliability of the RWCU system isolation function remains high even in the presence of single or multiple failures of differential temperature channels because of diversity of the LDS for the RWCU A Pump Room, RWCU B Pump Room, RWCU Phase Separator Room, and RWCU Heat Exchanger Room. A steam leak will cause a coincident trip of both the differential and ambient temperature channels in RWCU A Pump Room, RWCU B Pump Room, RWCU Phase Separator Room, and RWCU Heat Exchanger Room. There is no diversity for the RWCU Open Trench Above Pump Room and RWCU Torus Room areas
ENCLOSURE 2 to NRC-06-0044 PROPOSED TECHNICAL SPECIFICATION CHANGE (MARK-UP)
TS PAGE:
3.3-50 3.3-53 3.3-58
Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.6.1-1.
ACTIONS
................ NOTE ---------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for channels inoperable, trip. Functions 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 l.f. 2.a. 2.c.
and 6.b B. One or e automatic B.1 Restore isolation 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Functions ca th ility capability.
isolation not maintained.
Note- -.-------...
-- (continued)
With a Table 3.3.6.1-1 Function 5.c channel inoperable, isolation capability is considered maintained provided Function 5.b is OPERABLE in the affected room FERMI - UNIT 2 3.3-50 Amendment No. 134
'b.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Function 5 (other than non-redundant circuitry of Primary Containment Isolation Instrumentation 5.a) provided the associated Function maintains isolation capability. 3.3.6.1 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Function 5.c provided Function 5,b is OPERABLE in the affected room; SURVEILLANCE REQUIREMENTS
..................................... NOTES ....................................
- 1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
- 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to:
- a. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for Function 5.a when testing non-redundant circuitry that results in loss of isolation capability associated with this Function. provided Functions 5.b. 5.c. and 5.e are OPERABLE:
c 1.ý 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 1. 2. 5 othes thn nn,redund*an* circitr. "f a and 6. provided the associated Function maintains isolation capability: and d -.- 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for Functions 3 and 4. provided the associated Function maintains isolation capability.
SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.1.3 Verify the trip unit setpoint. 92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 18 months SR 3.3.6.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months i
SR 3.3.6.1.6 Perform CHANNEL FUNCTIONAL TEST. 18 months (continued)
FERMI - UNIT 2 3.3-53 Amendment No. 134
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 4)
Primary Contairmv-nt Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REWIRED SURVEILLANCE ALLOWABLE VALUE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS
- 5. Reactor Water Cleanup (RWCU) System Isolation
- a. Differential 1.2.3 1 F SR 3.3.6.1.1 :s63.4 gpm Flow- High SR 3.3.6.1.2 SR 3.3.6.1.4 SIR 3.3.6.1.5
- b. Area 1.2.3 1 per F SR 3.3.6.1.1 " 1B3"F Temerature - High area (d) SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5
- c. Area Ventilation 1.2.3 e F SR 3.3.6.1.1 " 53"F Differential 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 HA
- e. Reactor Vessel Water 1.2.3 2 F SR 3.3.6.1.1 x 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 varver
- 6. Shutdown Cooling System Isolation
- a. Reactor Steam Dome 1.2.3 I F SR 3.3.6.1.1
- b. Reactor Vessel Water 3.4.5 2(c) J SR 3.3.6.1.1
- 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) For Function 5.c, Reactor Water Cleanup (RWCU) System Isolation, Area Ventilation Differential Temperature - High, the required channels is 1 per room.
FERMI - UNIT 2 3.3-58 Amendment No. 134
ENCLOSURE 3 to NRC-06-0044 PROPOSED TECHNICAL SPECIFICATION CHANGE TS PAGE:
3.3-50 3.3-53 3.3-58
Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.6.1-1.
ACTIONS
..................................... NOTE .....................................
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for channels inoperable, trip. Functions 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
........... NOTE ...........
With a Table 3.3.6.1-1 B.1 Restore isolation 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Function 5.c channel capability.
inoperable, isolation capability is considered maintained provided Function 5.b is OPERABLE in the affected room.
B. One or more automatic Functions with isolation capability not maintained.
(continued)
FERMI - UNIT 2 3.3-50 Amendment No. AýA,
Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS
NOTES ------------------------------------
- 1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
- 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to:
- a. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for Function 5.a when testing non-redundant circuitry that results in loss of isolation capability associated with this Function, provided Functions 5.b, 5.c, and 5.e are OPERABLE;
- b. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Function 5 (other than non-redundant circuitry of 5.a) provided the associated Function maintains isolation capability.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Function 5.c provided Function 5.b is OPERABLE in the affected room;
- c. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 1, 2, and 6, provided the associated Function maintains isolation capability; and
- d. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for Functions 3 and 4, provided the associated Function maintains isolation capability.
SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.1.3 Verify the trip unit setpoint. 92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 18 months SR 3.3.6.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months SR 3.3.6.1.6 Perform CHANNEL FUNCTIONAL TEST. 18 months (continued)
FERMI - UNIT 2 3.3-53 Amendment No. XAý,
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 4)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES 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 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 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 (d) F SR 3.3.6.1.1 : 53°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 2 103.8 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 ýer 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 : 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 ; 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 1 ver G SR 3.3.6.1.6 NA va 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) For Function 5.c. Reactor Water Cleanup (RWCU) System Isolation. Area Ventilation Differential Temperature - High. the required channels is 1 per room. I FERMI - UNIT 2 3.3-58 Amendment No. 2X
ENCLOSURE 4 to NRC-06-0044 PROPOSED REVISED TECHNICAL SPECIFICATION BASES CHANGES (FOR INFORMATION ONLY)
INCLUDED PAGES:
B 3.3.6.1- 1 B 3.3.6.1- 4 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 B 3.3 INSTRUMENTATION B 3.3.6.1 Primary Containment Isolation Instrumentation BASES BACKGROUND The primary containment isolation instrumentation automatically initiates closure of appropriate primary containment Isolation valves (PCIVs). The function of the PCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs). Primary containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a DBA.
The isolation instrumentation Includes the sensors, relays, and switches that are necessary to cause Initiation of primary containment and reactor coolant pressure boundary (RCPB) Isolation. Most channels include electronic equipment (e.g., trip units) that compares measured input signals with pre-established setpoints. When the setpoint is exceeded, the channel output relay actuates, which then outputs a primary containment isolation signal to the isolation logic. Functional diversity is provided by monitoring a wide range of independent parameters. The Input parameters to the isolation logics are (a) reactor vessel water level, (b) area ambient and differential temperatures, (c) main steam line (NSL) flow and radiation, (d) Standby Liquid Control (SLC) System initiation, (e) condenser pressure, (f) main steam line pressure, (g) high pressure coolant injection (HPCI) and reactor core Isolation cooling (RCIC) steam line flow, (h) drywell pressure, (i) HPCI and RCIC steam line pressure, (j) HPCI and RCIC turbine exhaust diaphragm pressure, (k) reactor water cleanup (RWCU) differential flow, and (1) reactor steam dome pressure. Redundant sensor input signals from each parameter are typically provided for initiation of isolation. The only exceptions are SLC System initiationn and RWCU differential flow. In addition, manual isolation of the valves is provided.
Primary containment isolation Instrumentation has inpu to the trip logic of the isolation functions listed bel
, RWCU differential temperature FERMI - UNIT 2 B 3.3.6.1 -1 Revision 0
Primary Containment Isolation Instrumentation B 3.3.6.1 BASES BACKGROUND (continued) and Drywell Pressure -High Functions. These Functions receive inputs from four turbine exhaust diaphragm pressure and four steam supply pressure channels for each system.
The outputs from the turbine exhaust diaphragm pressure and steam supply pressure channels are each connected to two two-out-of-two trip systems. Each trip system isolates one valve per associated penetration.
HPCI and RCIC Functions isolate the HPCI and RCIC isolation valves.
- 5. Reactor Water Cleanup System Isolation The Reactor Vessel Water Level -Low Low, Level 2 Isolation Function receives input from four reactor vessel water level channels. The outputs from the reactor vessel water level channels are connected into two two-out-of-two trip systems.
The Differential Flow-High function is derived from three non-redundant flow transmitters and a non-redundant flow summer. The output of the summer is fed to two trip units, the outputs of which are channeled through relays into two trip systems. One trip system isolates the inboard isolation valve, while the other trip system isolates the two outboard isolation valves.
SLC System Initiation Functions receive input from two channels, with each channel in one trip system using a one-out-of-one logic. Both channels are only input to the trip systems that isolates the outboard isolation valves.
The Area Temperature-High Function receives input from twelve temperature monitors, six to each trip system. The Area Ventilation Differential Temperature -High Function receives input from four differential temperature monitors, two in each trip system. These are configured so that any one input will trip the associated trip system. One of the two trip systems is connected to the inboard valve and the other trip system is connected to the two outboard valves on each RWCU penetration.
Insert 1 - 1 RWCU Functions isolate t RWCU isolation valves.
Either trip system isolates the RWCU system.
FERMI - UNIT 2 B 3.3.6.1- 4 Revision 0
Insert I The Area Temperature-High, and Area Ventilation Differential Temperature-High, Functions act together to provide protection from small leaks in the monitored areas and rooms of the RWCU system.
Primary Containment Isolation Instrumentation B 3.3.6.1 Area Ventilation Differential Temperature-High BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)
The Differential Flow-High Allowable Value ensures hat break of the RWCU piping is detected.
This Function isolates the RWCU isolation valves.
5.b.. S.c. Area and Area Ventilation Differential Temperature - Hi gh RU and aroa we'ntilation diffepronti -teempeecitturzm are Area Temperature-High rovided to detect a leak from the RWCU System. The isolation occurs even when very small leaks have occurred and is diverse to the., ........ ,wn,_,,, instrumentation for the hot portio of the RWCU System. If the small leak continues w isolation, offsite dose limits is not may inbe any taken Credit for these instruments Differential Flow High transient or accident analysis in the UFSAR, since boundin analyses are performed for large breaks such as recirculation or 14SL breaks.
and ae etlte ifenalea 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
,six areas Function (two per arp*). Two channels per area are required tn hp nPFRAeRlZ_4ao sure 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
, four rooms te.-mper.,eP instrument that receives inputs from thermocouples that "e located in the inlet and outlet of the room cooling systsu and for a total of four available channels (one per room).
The Area and Area Ventilation Differential Temperature-High Allowable Values are set low enough to detect a leak equivalent to 25 gpm.
These Functions isolate the RWCU isolation valves, as appropriate.
A note has been added to Table 3.3.6.1-1 for Function 5.c, RWCU Area Differential Temperature - High, clarifiying the required channels per room is one. Function 5.c has only one trip system per room.
FERPI - 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 Functions 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 l.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 i otaken.
! ua m As an ie i ea~i!ll Vent
......*Iie.iat il B-i * -F.r.F-L.
(-- fl i ;--
. l 1.
AMi-z-'t*
)
-Tfmprziture High in"trur*. .*t ii .o..rb- Ts 3,3.641.
CV11I i.shoul d-be antorod.
-B.
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 MSL Isolation Functions are considered to be 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 FERMI -UNIT 2 B 3.3.6.1-24 Revi si on 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. l.b, l.d, and 1.f, this would require both trip systems to have one channel OPERABLE or in trip. For Function I.c, this would require both trip systems to have one channel, associated with each MSL, OPERABLE or in trip.
For Functions 1.e and l.g, each Function consists of rwym)S of-areas channels- that monitor several locations Within a given area (e. ifferent locations within the main steam tunnel area). -refore, this would require both trip systems to r_m ohave one chnel per location OPERABLE or in trip. For r*ov-area *Functions 2.a, .b, 2.c, 3.b, 3.c, 4.b, 4.c. 5.e, and 6.b.
this would requ e one trip system to have two channels, ch OPERABLE or i trip. For Functions 3.a, 3.d, 4.a. 4.d,
- 5. , .d. and 6.a. is would require one trip system to have on hannel OPE LE or in trip. For Functions 5.b Iner2 _and 5.c, ea Functio consists of channels that monitor several differ t 4aea-arti . Therefore, this would require one channel per to be OPERABLE-&r- -- 4pp- (the (channels are not required to be in the same trip system).
The Condition does not include the Manual Initiation Functions (Functions l.h. 2.d, 3.f, 4.f, 5.f, and 6.c),
since they are not assumed in any accident or transient 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) is allowed. -45 am ,, .
'GE d*÷tn P 4 ic f-o hp ,inr fnr an inoper-ble RW.U Ar: -
- r-Egni tsdL dp*l"1jLlt n of Cond4tion BT heR a g;h
..han... .. af .. A,,t
'M*V', inDfferentie! Temperz-*tu Hi1gh 4s 4sp:conseý ývei" in~ this ct~t
.......... in.i r..iva reading 4 CoRd#itin S.
The 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 channel s.
Revision 21 UNIT 2 B 3.3.6.1-25 FERMI - UNIT 2 B 3.3.6.1-25 Revision 21
Insert 2 As noted, with a Table 3.3.6.1-1 Function 5.c channel inoperable, isolation capability is considered maintained provided Function 5.b is OPERABLE in the affected room. There is diversity in the RWCU temperature isolation instrumentation in that Area Ventilation Differential Temperature-High and the Area Temperature-High monitor for a small leak in the same rooms. The reliability of the RWCU system isolation function remains high even in the presence of single or multiple failures of differential temperature channels because a steam leak will cause a coincident trip of both the Area Ventilation Differential Temperature-High and the Area Temperature-High channels in RWCU A Pump Room, RWCU B Pump Room, RWCU Phase Separator Room, and RWCU Heat Exchanger Room. There is no diversity for the RWCU Open Trench Above Pump Room and RWCU Torus Room areas.
Primary Contamient Isolation Inon B 3.3.6.1 BASES SURVEILLANCE REQUIREMENT (continued)
(Refs. 5 and 6) ass--Mtlon of the average time required to perform channel surveillance. That analysis demonstrated that the galloance does not significantly reduce the probability that the PCIVs will isolate the penetration flow path(s) When n s .
Insert 3 SR 3.3.6.1._1 Pet f ance of the CHAMEL CHECK on 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 lnst -- ntton has not occurred. A CHANNEL CHECK is normally a awrison of the paraeter indicated on-one channel to a similar parameter on other channels. It is based on the assmmtion that instriznt channels montoring the same parameter should read ar Mately the same value. Significant deviations the nstruhent channels could be an indication of excessive instruent drift in one of the channels or of something even more serious. A CHANNEL CHECK will detect ross channel failure: thus, it is key to verityIng the stnwuetation continues to operate properly between each CHWUEL CALIBRATIONI.
Agreement criteria are determined by the plant staff based on a combination of the channel instruent uncertainties.
including Indication and readability. If a channel is outside the criteria. It may be an indication that the instrument has drifted outside Its limit.
The Frequency Is based on operating experience that demonstratesichannel 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 LCD.
SR 3.3.6.1.2 and SR 3.3.6.1.6 A ONI!EL FLHCIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. A successful test of the requ"ired contact(s) of a canel r6lay 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 FERNI - hhilT FEIW - 2 UNrr 2 8 3.3.6.1-29 -Revision 27
Insert 3 Note 2.b clarifies that the isolation function is maintained for Function 5.c, RWCU Area Differential Temperature - High, provided Function 5.b, RWCU Area Temperature -
High, is OPERABLE in the affected area.
Primary Containment Isolation Instrunentation B 3.3.6.1 BASE SURVEILLANCE REQUIREMENTS (continued)
ISOLATION SYSTEM RESPOE TIME tests are conducted an an 18 month STANERE 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 failuirs of Instrumentation components causing serious response time degradation, but not channel failure, are Infrequent occurrences.
REFERE1 CES 1. UFSR. Section 6.3.
- 2. UFSAR. Chapter 15.
- 3. NEDO-31466. "Tedmical Specification Screening Criteria Application and Risk Assessment,"
November 1987.
- 4. UFSAR, Section 4.5.2.4.
- 5. NEDC-31677P-A, 'Technical Specification Improvement Analysis for BW Isolation-Actuation Instrumentation,"
July 1990.
- 6. NEDC-30851P-A Supplement 2i "Technical Specificationis 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 BW MSIV Closure Function and Scram Fuction of the KSL Radiation Monitor., Licensing Topical Plant Report for BWR.
- 10. NEDO.32291. "System Analysis for Elimination of Selected Response Time Testing Requirements." January 1994; and Fermi-2 SER for Amendmen i.111, dated April 18, 1997.
- 11. NFD)O-32291-A. Supplement 1, 'System Analyses for The Elimination of Selected Response Time Testing Requirement,' October 1999.'
I
'D~uiafs~ u~
W. Tochnicatl
,,MRl~S
.. ist n,'1- *7 te-P9 Th.
Sao B 3.3.6.1*32 Rei~Ision 21 FEJ~4I
- 1R~IT 2 FERMI - UNIT 2 B 3.3.6.1-32 P,* st on 21