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MONTHYEARRS-10-114, License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal2010-06-29029 June 2010 License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal Project stage: Request ML1021401282010-08-0505 August 2010 Unit Nos.1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action Low Temperature Overpessure Protection Project stage: Acceptance Review RS-10-137, Supplemental Information Supporting License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal2010-08-24024 August 2010 Supplemental Information Supporting License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal Project stage: Supplement ML1024204702010-09-0303 September 2010 Acceptance Review of License Amendment Request Low Temperature Overpressure Protection Project stage: Acceptance Review RS-11-006, Additional Information Supporting Request for License Amendment Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal2011-01-13013 January 2011 Additional Information Supporting Request for License Amendment Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal Project stage: Request ML11132A1292011-03-17017 March 2011 Transmittal of Ihpb Safety Evaluation, Byron, Units 1 and 2, Braidwood, Units 1 and 2, License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal Project stage: Approval ML1108406572011-06-29029 June 2011 Issuance of Amendments 167, 167, 174 & 174 Low Temperature Overpressure Protection and Loss of Decay Heat Removal Project stage: Approval 2010-09-03
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Category:Letter type:RS
MONTHYEARRS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-118, Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-10-31031 October 2022 Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0606 June 2022 Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022 Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube. RS-22-057, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-050, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-04-0808 April 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-014, Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time2022-03-24024 March 2022 Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time RS-22-041, Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes2022-03-22022 March 2022 Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes RS-22-036, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-03-10010 March 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC 2024-01-11
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-117, Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d)2021-12-0909 December 2021 Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d) ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink2021-08-0202 August 2021 License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-057, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2021-05-27027 May 2021 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-20-130, License Amendment Request - Proposed Changes to Byron Emergency Plan for Post-Shutdown and Permanently Defueled Condition2020-11-0202 November 2020 License Amendment Request - Proposed Changes to Byron Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML20303A3252020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 2 of 5 ML20303A3272020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 4 of 5 ML20303A3262020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 3 of 5 ML20303A3232020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 1 of 5 RS-20-129, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 52020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 5 RS-20-114, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2020-09-24024 September 2020 License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition RS-20-089, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2020-07-15015 July 2020 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-20-068, Application to Revise Technical Specifications 3.8.1, AC Sources-Operating2020-06-26026 June 2020 Application to Revise Technical Specifications 3.8.1, AC Sources-Operating RS-20-058, Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-16016 April 2020 Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections RS-20-044, Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-0606 April 2020 Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections ML20063L2822020-02-28028 February 2020 Application of Westinghouse Full Spectrum LOCA Evaluation Model RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2020-02-28028 February 2020 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues2020-02-0606 February 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions2019-12-0909 December 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions RS-19-078, License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies.2019-09-24024 September 2019 License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies. RS-19-082, License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS)2019-09-11011 September 2019 License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS) RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) RS-19-081, Supplement to Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2019-08-0909 August 2019 Supplement to Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements RS-19-018, Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times2019-02-14014 February 2019 Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times RS-19-008, Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2019-01-31031 January 2019 Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process RS-18-149, Supplemental Information Related to License Amendment Request for a One-Time Extension to Technical Specification 3.8. 1, AC Sources-Operating, Required Action A.22018-12-21021 December 2018 Supplemental Information Related to License Amendment Request for a One-Time Extension to Technical Specification 3.8. 1, AC Sources-Operating, Required Action A.2 RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RS-18-129, Supplement to License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies2018-10-19019 October 2018 Supplement to License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies RS-18-102, License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.22018-08-10010 August 2018 License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.2 RS-18-035, License Amendment Request to Revise Technical Specification 3.2.3, Axial Flux Difference2018-04-0202 April 2018 License Amendment Request to Revise Technical Specification 3.2.3, Axial Flux Difference RS-18-027, License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies2018-03-0808 March 2018 License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies 2023-09-29
[Table view] Category:Technical Specifications
MONTHYEARML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21154A0462021-07-13013 July 2021 Issuance of Amendments Nos. 222 and 222 Revision of Technical Specifications for the Ultimate Heat Sink ML21060B2812021-04-0202 April 2021 Issuance of Amendments Nos. 221, 221, 224, and 224 Regarding Technical Specifications 3.8.1, AC Sources-Operating ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20317A0012020-12-28028 December 2020 Non-Proprietary, Issuance of Amendment Nos. 219, 219, 223, and 223, Revise Loss-of-Coolant Accident Methodology in TS 5.6.5, Core Operating Limits Report (COLR) ML21008A4052020-12-17017 December 2020 Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections ML20246G8652020-09-21021 September 2020 Issuance of Amendment Nos. 222 and 222 One-Time Extension of Unit No. 2 Steam Generator Inspections (COVID-19) ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20118C4292020-06-0909 June 2020 Issuance of Amendments Revision of Technical Specifications for the Ultimate Heat Sink ML20086M2882020-04-0202 April 2020 Correction of Amendments Nos. for Amendments Revising Instrument Testing and Calibration Definitions RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML19190A0812019-08-28028 August 2019 Issuance of Amendments Regarding Limiting Condition of Operation for Inoperability of Snubbers RS-19-018, Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times2019-02-14014 February 2019 Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times RS-18-102, License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.22018-08-10010 August 2018 License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.2 ML18067A1812018-06-0404 June 2018 Correction to Technical Specification Amendment Identification Format ML16180A2512016-08-0101 August 2016 Issuance of Amendments Regarding Use of Optimized Zirlo as Fuel Cladding Material ML16133A4382016-07-26026 July 2016 Issuance of Amendments Ultimate Heat Sink Temperature Increase RS-16-034, License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding2016-02-23023 February 2016 License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding ML15336A7312016-01-27027 January 2016 TS 50456-Bwd-AppsABC ML15307A7762015-12-21021 December 2015 Braidwood - Issuance of Amendments Regarding Installation of New Low Degraded Voltage Relays and Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses (CAC Nos. MF4051 - MF4054) ML15341A3162015-12-14014 December 2015 Correction of Technical Specifications Related to Amendment 145 ML15286A2762015-11-19019 November 2015 Technical Specifications ML15232A4412015-10-28028 October 2015 Issuance of Amendments to Utilize WCAP-16143-P, Revision 1 Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Byron/Braidwood Units 1 and 2, Dated October 2014 ML15268A4862015-10-0606 October 2015 Correction of Amendments Adopting Technical Specification Task Force Traveler TSTF-523 (TAC Nos. MF4436-MF4446) ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training RS-14-337, Units 1 & 2 - License Amendment Request for Diesel Generator Load Rejection Surveillance Requirement2014-12-18018 December 2014 Units 1 & 2 - License Amendment Request for Diesel Generator Load Rejection Surveillance Requirement ML14239A4272014-12-0707 December 2014 Issuance of Amendments to Clarify Technical Specification 3.3.1, Reactor Trip System Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation RS-14-285, License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink(Uhs)2014-11-24024 November 2014 License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink(Uhs) ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements ML13311B4812014-07-21021 July 2014 Issuance of Amendments to Revise Technical Specifications Section 3.5.3 ML14069A3372014-04-0202 April 2014 Final Response to Task Interface Agreement 2012-13, Braidwood Station Technical Specification 3.6.3 Compliance with One or More Main Steam Isolation Valves Inoperable ML13326A1072014-03-13013 March 2014 Issuance of Amendments to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program ML13281A0002014-02-0707 February 2014 Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate RS-13-240, License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program.2013-10-10010 October 2013 License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program. RS-13-137, 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 Process2013-09-0303 September 2013 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 RS-13-175, Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs).2013-08-21021 August 2013 Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs). RS-12-009, License Amendment Request - Diesel Generator Steady State Maximum Frequency and Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel2012-05-0101 May 2012 License Amendment Request - Diesel Generator Steady State Maximum Frequency and Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel RS-12-028, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.2012-03-22022 March 2012 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. RS-12-023, License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria2012-03-20020 March 2012 License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria RS-11-136, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications (TS) 3.3.12011-09-0202 September 2011 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications (TS) 3.3.1 ML1117900312011-06-23023 June 2011 Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate, Attachment 2A, Markup of Proposed Operating License and Technical Specifications Pages 2023-07-20
[Table view] |
Text
Exelon Generation Company, LL(_www.exeloncorp.com 4300 Winfield Road Warrenville, I! 6o Exekrn.Nuclear RS-10-11410 CFR 50.90 June 29, 2010 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50
-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF
-37 and NPF-66 NRC Docket Nos. STN 50
-454 and STN 50-455
Subject:
License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal
References:
1.NRC Generic Letter 88
-17, "Loss of Decay Heat Removal," dated October 17, 1988 2.Letter from G. Stanley and K. Graesser (Commonwealth Edison Company) to U.S. NRC, "Application for Amendment to Appendix A, Technical Specifications - Conversion to the Improved Standard Technical Specifications," dated December 13, 1996 3.Letter from R. R. Assa (U.S. NRC) to O. D. Kingsley (Commonwealth Edison Company), "Issuance of Amendments (TAC NOS. M97546, M97547, M97548 and M97549)," dated December 22, 1998 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC)requests an amendment to Facility Operating License Nos. NPF-72 and NPF
-77 for Braidwood Station, Units 1 and 2, and Facility Operating License Nos. NPF
-37 and NPF
-66 for Byron Station, Units 1 and 2. The proposed change revises Technical Specifications (TS) 3.4.12, "Low Temperature Overpressure Protection (LTOP)System," to correct an inconsistency between the TS, and implementation of procedures and administrative controls for Safety Injection (SI) pumps required to mitigate a postulated loss of decay heat removal during mid
-loop operation as discussed in NRC Generic Letter (GL) 88
-17, "Loss of Decay Heat Removal," (i.e., Reference 1). Specifically, the proposed change adds a note to TS Limiting Condition for Operation (LCO) 3.4.12 that states:
June 29, 2010 U.S. Nuclear Regulatory Commission Page 2"For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is < 5 percent." The proposed change corrects an oversight introduced during the conversion of the Braidwood Station and Byron Station TS to the Improved Technical Specifications (i.e., References 2 and 3).This request is subdivided as follows.Attachment 1 provides a description and evaluation of the proposed change.Attachment 2 provides a markup of the affected TS page for Braidwood Station.Attachment 3 provides a markup of the affected TS page for Byron Station.Attachments 4 and 5 provide a markup of the affected TS Bases page for Braidwood Station and Byron Station, respectively.
The TS Bases pages are provided for information only and do not require NRC approval.
The proposed change has been reviewed by the Braidwood Station and Byron Station Plant Operations Review Committees and approved by the Nuclear Safety Review Board in accordance with the requirements of the EGC Quality Assurance Program.
EGC requests approval of the proposed change by June 29, 2011. Once approved, the amendment will be implemented within 60 days. This implementation period will provide adequate time for the affected station documents to be revised using the appropriate change control mechanisms.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b), EGC is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 65 7-2803.I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of June 2010.
JeffreyDL. lonsen Manager -Licensing June 29, 2010 U.S. Nuclear Regulatory Commission
Page 3 Attachments: 1. Evaluation of Proposed Change
- 2. Markup of Proposed Technical Specifications Page for Braidwood Station 3. Markup of Proposed Technical Specifications Page for Byron Station 4. Markup of Proposed Technical Specifications Bases Page for Braidwood Station
- 5. Markup of Proposed Technical Specifications Bases Page for Byron Station
cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector - Braidwood Station NRC Senior Resident Inspector - Byron Station Illinois Emergency Management Agency - Division of Nuclear Safety ATTACHMENT 1 Evaluation of Proposed Change Page 1 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable
Regulatory Requirements/Criteria 4.2 No Significant Hazards Consideration
4.3 Conclusions
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
ATTACHMENT 1 Evaluation of Proposed Change Page 2 1.0
SUMMARY
DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) requests an amendment to Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, and Facility Operating License Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2. The proposed change revises Technical Specifications (TS) 3.4.12, "Low Temperature Overpressure Protection (LTOP) System," to correct an inconsistency between the TS, and implementation of procedures and administrative controls for Safety Injection (SI) pumps required to mitigate a postulated loss of decay heat removal during mid-loop operation as discussed in NRC Generic Letter (GL) 88-17, "Loss of Decay Heat Removal," (i.e., Reference 1). Specifically, the proposed change adds a note to TS Limiting Condition for Operation (LCO) 3.4.12 that states:
"For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is < 5 percent." The proposed change corrects an oversight introduced during the conversion of the Braidwood Station and Byron Station TS to the Improved Technical Specifications (ITS) (i.e., Reference 2 and Reference 3). 2.0 DETAILED DESCRIPTION LCO 3.4.12 requires, in part, an LTOP system to be operable with no SI pumps capable of injecting into the Reactor Coolant System (RCS). The proposed change adds a new Note to LCO 3.4.12 which states: 2. For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is < 5 percent. The existing LCO 3.4.12 Note is numbered as Note 1.
3.0 TECHNICAL EVALUATION
On October 17, 1988, the NRC issued GL 88-17 to request licensees to take actions to address concerns with a potential loss of decay heat removal. In response to GL 88-17, a review was performed to identify TS changes, for Braidwood Station and Byron Station, which might prevent or mitigate the consequences of a loss of decay heat removal event. The review concluded that a TS change was necessary to allow one or more SI pumps to be available for injection purposes if normal heat removal capability was lost. Commonwealth Edison (ComEd) submitted a license amendment request in Refe rence 4 to add this allowance, and the NRC approved the license amendment request in Reference 5. The allowance for one or more SI pumps to be available for injection purposes if normal heat removal capability was lost was incorporated into Braidwood Station and Byron Station TS 3.5.4.2, and remained part of TS 3.5.4.2 until conversion of the Braidwood Station and Byron Station TS to the Improved Technical Specifications (ITS). Specifically, prior to conversion to the ITS, Current Technical Specifications (CTS) 3.5.4.1 required all SI pumps to be inoperable in Mode 5 with pressurizer level greater than 5 percent, and in Mode 6 with pressurizer level ATTACHMENT 1 Evaluation of Proposed Change Page 3 greater than 5 percent and the reactor vessel head resting on the reactor vessel flange. In addition, prior to the conversion to the ITS, CTS 3.5.4.2 required at least one SI pump and flowpath to be available in Modes 5 and 6 with pressurizer level less than or equal to 5 percent. The CTS requirements discussed above were evaluated and issued by the NRC in a safety evaluation dated August 31, 1990 (i.e., Reference 5). Section 2.2 of the Safety Evaluation
states: The availability of a Safety Injection (SI) pump provides for the mitigation of the effects of a loss of decay heat removal event during mid-loop operations. Operation of at least one SI pump is required in some cases to prevent core uncovery. The licensee proposes to have an SI pump available in Modes 5 and 6. The potential for low temperature overpressurization has been analyzed and accounted for in the Specification by requiring pressurizer level to be less than 5 percent if the SI pump is available. It is the licensee's intention that during RCS reduced inventory conditions, the safety injection pump motor circuit breakers will be racked in and the pump secured by placing the Control Room handswitch in the Pull-to-Lock position. This will prevent the safety injection pump from being inadvertently started by a signal, but will allow the operators to start the pump from the Control Room if needed to mitigate a loss of decay heat removal. This modification is consistent with Generic letter 88-17 and is acceptable. SI pump capability to inject into the RCS in Mode 5 with pressurizer level < 5 percent and in Mode 6 when the reactor vessel head is on and pressurizer level is < 5 percent is controlled in accordance with existing plant procedures. As discussed in Reference 4, 5 percent pressurizer level was used as the reference water level to ensure that the necessary surge volume in the pressurizer while minimizing the burden on Operations personnel. The availability of one or more SI pumps in Mode 5 and Mode 6, with pressurizer level < 5 percent, mitigates the consequences of a loss of decay heat removal event during mid-loop operations. The availability of one or more SI pumps under these circumstances does not present a concern for cold overpressure protection since sufficient air volume exists which allows Operations personnel time to mitigate the transient. This is in contrast to the analyzed cold overpressure transients, in which the RCS is assumed to be water solid at the onset of the event. During the conversion of the Braidwood Station and Byron Station TS to the ITS (i.e., References 2 and 3), the requirements of CTS 3.5.4.1 were incorporated in TS 3.4.12.
However, the Applicability dependence on pressurizer level was not incorporated in TS 3.4.12.
Based on a review of the "Discussion of Changes to CTS," for ITS Section 3.4, "Reactor Coolant System," it was determined that although the more restrictive aspects of the ITS Completion Time were discussed with respect to CTS 3.5.4.1, the more restrictive aspects of the ITS Applicability were not similarly discussed. The ITS conversion resulted in an unintended more restrictive change to the Mode of Applicability for the SI pump capability to inject in Mode 5 and Mode 6 when the reactor vessel head is on. This resulted in a conflict with the recommendations and guidance of GL 88-17 regarding mitigation of loss of decay heat removal during mid-loop operations.
ATTACHMENT 1 Evaluation of Proposed Change Page 4 The potential for vessel overpressurization is most acute when the RCS is water solid, occurring only while shutdown; a pressure fluctuation can occur more quickly than an operator can react to relieve the condition. To limit the coolant input capability, LCO 3.4.12 requires, in part, that no SI pumps be capable of injecting into the RCS. The proposed note allows one or more SI pumps to be capable of injecting into the RCS only when pressurizer level is < 5 percent in Mode 5 and Mode 6 when the reactor vessel head is on. This provides protection to limit coolant input capacity during shutdown in which a pressure fluctuation due to coolant input from the SI pumps could occur more quickly than an operator could react, while providing an allowance for one or more SI pumps to be capable of injecting into the RCS during conditions in which a loss of decay heat removal could result in rapid core uncovery. The proposed change is acceptable because: (1) it resolves a conflict between LTOP requirements and mitigation of a postulated loss of decay heat removal during mid-loop operation, (2) it is consistent with the Braidwood Station and Byron Station licensing bases that existed prior to the introduction of an unintended more restrictive change, and (3) it is consistent with GL 88-17.
4.0 REGULATORY EVALUATION
4.1 Applicable
Regulatory Requirements/Criteria Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TS as part of the license. The Commission's regulatory requirements related to the content of the TS are contained in 10 CFR 50.36, "Technical specifications." The TS requirements in 10 CFR 50.36 include the following categories:
(1) safety limits, limiting safety systems settings and control settings, (2) limiting conditions for operation (LCO), (3) surveillance requirements, (4) design features, and
(5) administrative controls. The LTOP system controls RCS pressure at low temperatures so the integrity of the Reactor Coolant Pressure Boundary is not compromised by violating the pressure and temperature limits of 10 CFR 50, Appendix G, "Fracture Toughness Requirements." In GL 88-17, the NRC requested licensees to take actions to address concerns with a potential loss of decay heat removal. In Reference 5, the NRC approved TS changes for Braidwood Station and Byron Station to allow one or more SI pumps to be available for injection purposes if normal heat removal capability was lost. The NRC concluded that the TS changes were acceptable and consistent with GL 88-17. The proposed change corrects an inconsistency between the Braidwood Station and Byron Station TS for the LTOP system, and actions that are necessary to mitigate a postulated loss of decay heat removal during mid-loop operation as discussed in GL 88-17. The proposed change maintains compliance with the regulatory requirements discussed above.
ATTACHMENT 1 Evaluation of Proposed Change Page 5 4.2 No Significant Hazards Consideration In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) requests an amendment to Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, and Facility Operating License Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2. The proposed change revises Technical Specifications (TS) 3.4.12, "Low Temperature Overpressure Protection (LTOP) System," to correct an inconsistency between the TS, and implementation of procedures and administrative controls for Safety Injection (SI) pumps required to mitigate a postulated loss of decay heat removal during mid-loop operation as discussed in NRC Generic Letter (GL) 88-17, "Loss of Decay Heat Removal." Specifically, the proposed change adds a note to TS Limiting Condition for Operation (LCO) 3.4.12 that states: "For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is < 5 percent." The proposed change corrects an oversight introduced during the conversion of the Braidwood Station and Byron Station TS to the Improved Technical Specifications (ITS). According to 10 CFR 50.92, "Issuance of amendment," paragraph (c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1) Involve a significant increase in the probability or consequences of any accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety. EGC has evaluated the proposed change, using the criteria in 10 CFR 50.92, and has determined that the proposed change does not involve a significant hazards consideration. The following information is provided to support a finding of no significant hazards consideration. 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No The proposed change does not result in any physical changes to safety related structures, systems, or components. The proposed change revises TS 3.4.12 to correct an inconsistency between the TS, and implementation of procedures and administrative controls for SI pumps required to mitigate a postulated loss of decay heat removal during mid-loop operation as discussed in GL 88-17. Specifically, the proposed change adds a note to TS LCO 3.4.12 that states:
"For the purpose of protecting the decay heat removal function, one or more SI ATTACHMENT 1 Evaluation of Proposed Change Page 6 pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is < 5 percent." The proposed change corrects an oversight introduced during the conversion of the Braidwood Station and Byron Station TS to the ITS. The probability of occurrence of an accident is not increased since the proposed change will continue to require that no SI pumps are capable of injecting into the RCS in Modes 5 and 6 with pressurizer level greater than 5 percent. The NRC has previously evaluated the allowance for one or more SI pumps to be capable of injecting into the RCS in Mode 5 or Mode 6 when the reactor vessel head is on provided pressurizer level is < 5 percent for the Braidwood Station and Byron Station. In a safety evaluation dated August 31, 1990, related to Braidwood Station, Units 1 and 2, Amendment 25, and Byron Station, Units 1 and 2, Amendment 38, the NRC concluded that allowing SI pump capability to inject into the RCS in Mode 5 or Mode 6 when the reactor vessel head is on provided pressurizer level is < 5 percent was acceptable. The availability of SI pumps under these circumstances does not present a concern regarding cold overpressure protection since sufficient air volume exists which allows Operations personnel time to mitigate the transient. This is in contrast to the analyzed cold overpressure transients, in which the RCS is assumed to be water solid at the onset of the event. 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 kind of accident from any accident previously evaluated? Response: No The proposed change revises TS 3.4.12 to correct an inconsistency between the TS, and implementation of procedures and administrative controls for SI pumps required to mitigate a postulated loss of decay heat removal during mid-loop operation as discussed in GL 88-17. Specifically, the proposed change adds a note to TS LCO 3.4.12 that states: "For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is < 5 percent." The proposed change corrects an oversight introduced during the conversion of the Braidwood Station and Byron Station TS
to the ITS. The proposed change is necessary for the purpose of mitigating the consequences of a loss of decay heat removal during mid-loop operations. Operation of at least one SI pump is required in some cases to prevent the core from uncovering. The only new configuration allowed by the proposed change is the potential of having one or more SI pumps available in Modes 5 and 6 with pressurizer level < 5 percent. The potential overpressurization accident has ATTACHMENT 1 Evaluation of Proposed Change Page 7 been analyzed and accounted for by requiring pressurizer level to be <
5 percent if one or more SI pumps are available. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No The proposed change revises TS 3.4.12 to correct an inconsistency between the TS, and implementation of procedures and administrative controls for SI pumps required to mitigate a postulated loss of decay heat removal during mid-loop operation as discussed in GL 88-17. Specifically, the proposed change adds a note to TS LCO 3.4.12 that states: "For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is < 5 percent." The proposed change corrects an oversight introduced during the conversion of the Braidwood Station and Byron Station TS to the ITS. The proposed note allows one or more SI pumps to be capable of injecting into the RCS only when pressurizer level is < 5 percent in Mode 5 and Mode 6 when the reactor vessel head is on. This provides protection to limit coolant input capacity during shutdown in which a pressure fluctuation due to coolant input from the SI pumps could occur more quickly than an operator could react, while providing an allowance for one or more SI pumps to be capable of injecting into the RCS during conditions in which a loss of decay heat removal could result in rapid core uncovery. Therefore, the proposed change does not involve a significant reduction in a margin of safety. Based on the above evaluation, EGC concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92, paragraph (c), and accordingly, a finding of no significant hazards consideration is
justified.
4.3 Conclusions
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 be inimical to the common defense and security or the health and safety of the public.
ATTACHMENT 1 Evaluation of Proposed Change Page 8
5.0 ENVIRONMENTAL CONSIDERATION
EGC has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, "Standards for Protection Against Radiation." However, the proposed amendment does not involve: (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22, "Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review," paragraph (c)(9). Therefore, pursuant to 10 CFR 51.22, paragraph (b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.
6.0 REFERENCES
- 1. NRC Generic Letter 88-17, "Loss of Decay Heat Removal," dated October 17, 1988 2. Letter from G. Stanley and K. Graesser (Commonwealth Edison Company) to U.S. NRC, "Application for Amendment to Appendix A, Technical Specifications - Conversion to the Improved Standard Technical Specifications," dated December 13, 1996 3. Letter from R. R. Assa (U.S. NRC) to O. D. Kingsley (Commonwealth Edison Company), "Issuance of Amendments (TAC NOS. M97546, M97547, M97548 and M97549)," dated December 22, 1998 4. Letter from T. K. Schuster (Commonwealth Edison Company) to T. E. Murley (U.S. NRC), "Application for Amendment to Facility Operating Licenses NPF-37/66 &
NPF-72/77 - Implementation of Generic Letter 88-17," dated January 31, 1990 5. Letter from S. P. Sands (U.S. NRC) to T. J. Kovach (Commonwealth Edison Company), "Issuance of Amendments (TAC NOS. 76715, 76716, 76717 and 76718)," dated August 31, 1990 ATTACHMENT 2 Markup of Proposed Technical Specifications Page for Braidwood Station Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 REVISED TECHNICAL SPECIFICATIONS PAGE 3.4.12-1 LTOP System 3.4.12 BRAIDWOOD - UNITS 1 & 2 3.4.12 - 1 Amendment 98
3.4 REACTOR
COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System
LCO 3.4.12 An LTOP System shall be OPERABLE with:
- a. A maximum of one charging pump (centrifugal) capable of injecting into the RCS;
- b. No Safety Injection (SI) pumps capable of injecting into the RCS; c. Each SI accumulator isolated, whose pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T
limit curves provided in the PTLR; and
- d. One of the following pressure relief capabilities:
- 1. Two Power Operated Relief Valves (PORVs) with lift settings within the limits specified in the PTLR,
- 2. Two Residual Heat Removal (RHR) suction relief valves with setpoints 450 psig, 3. One PORV with a lift setting within the limits specified in the PTLR and one RHR suction relief
valve with a setpoint 450 psig, or
- 4. The RCS depressurized and an RCS vent of 2.0 square inches.
NOTE----------------------------
Operation in MODE 4 with all SI pumps and charging pumps
capable of injecting into the RCS is allowed when all RCS cold legs exceed 330
°F. ------------------------------------------------------------
APPLICABILITY: MODES 4 and 5, MODE 6 when the reactor vessel head is on.
- 2. For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is < 5 percent.
- 1. S ATTACHMENT 3 Markup of Proposed Technical Specifications Page for Byron Station Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 REVISED TECHNICAL SPECIFICATIONS PAGE 3.4.12-1 LTOP System 3.4.12 BYRON - UNITS 1 & 2 3.4.12 - 1 Amendment 106
3.4 REACTOR
COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System
LCO 3.4.12 An LTOP System shall be OPERABLE with:
- a. A maximum of one charging pump (centrifugal) capable of injecting into the RCS;
- b. No Safety Injection (SI) pumps capable of injecting into the RCS; c. Each SI accumulator isolated, whose pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T
limit curves provided in the PTLR; and
- d. One of the following pressure relief capabilities:
- 1. Two Power Operated Relief Valves (PORVs) with lift settings within the limits specified in the PTLR,
- 2. Two Residual Heat Removal (RHR) suction relief valves with setpoints 450 psig, 3. One PORV with a lift setting within the limits specified in the PTLR and one RHR suction relief
valve with a setpoint 450 psig, or
- 4. The RCS depressurized and an RCS vent of 2.0 square inches.
NOTE----------------------------
Operation in MODE 4 with all SI pumps and charging pumps
capable of injecting into the RCS is allowed when all RCS cold legs exceed 330
°F. ------------------------------------------------------------
APPLICABILITY: MODES 4 and 5, MODE 6 when the reactor vessel head is on.
- 2. For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is < 5 percent.
- 1. S ATTACHMENT 4 Markup of Proposed Technical Specifications Bases Page for Braidwood Station Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 REVISED TECHNICAL SPECIFICATIONS BASES PAGE B 3.4.12-9 LTOP System B 3.4.12 BRAIDWOOD - UNITS 1 & 2 B 3.4.12 - 9 Revision 0 BASES LCO This LCO requires that the LTOP System is OPERABLE. The LTOP System is OPERABLE when the minimum coolant input and pressure relief capabilities are OPERABLE. Violation of this LCO could lead to the loss of low temperature
overpressure mitigation capability and violation of the Reference 1 limits as a result of an operational transient.
To limit the coolant input capability, the LCO requires no SI pumps and a maximum of one charging pump (centrifugal) be capable of injecting into the RCS, and all accumulator discharge isolation valves be closed and de-energized (when
accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed in the PTLR).
The LCO is modified by a note that permits the operation in MODE 4 with all SI pumps and charging pumps capable of RCS injection whenever all RCS cold legs exceed 330
°F. This is necessary to allow transition between MODES 3 and 4.
The elements of the LCO that provide low temperature overpressure mitigation through pressure relief are:
- a. Two OPERABLE PORVs;
- b. Two OPERABLE RHR suction relief valves;
- c. One OPERABLE PORV and one OPERABLE RHR suction relief valve; or
- d. A depressurized RCS and an OPERABLE RCS vent.
A PORV is OPERABLE for LTOP when its block valve is open, its lift setpoint is set to the limit required by the PTLR and testing proves its ability to open at this setpoint, and
motive power is available to the two valves and their control circuits.
An RHR suction relief valve is OPERABLE for LTOP when its RHR suction isolation valves are open, its setpoint is 450 psig, and testing has proven its ability to open at this setpoint. two notes. Note 1Note 2 permits operation in MODE 5 and in MODE 6 when the reactor vessel head is on with one or more SI pumps capable of RCS injection whenever pressurizer level is < 5 percent. This is necessary to provide for the mitigation of the effects of a loss of decay heat removal cooling event during mid-loop operations. Operation of at least one SI pump is required in some instances to prevent core uncovery.
ATTACHMENT 5 Markup of Proposed Technical Specifications Bases Page for Byron Station Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 REVISED TECHNICAL SPECIFICATIONS BASES PAGE B 3.4.12-9 LTOP System B 3.4.12 BYRON - UNITS 1 & 2 B 3.4.12 - 9 Revision 0 BASES LCO This LCO requires that the LTOP System is OPERABLE. The LTOP System is OPERABLE when the minimum coolant input and pressure relief capabilities are OPERABLE. Violation of this LCO could lead to the loss of low temperature
overpressure mitigation capability and violation of the Reference 1 limits as a result of an operational transient.
To limit the coolant input capability, the LCO requires no SI pumps and a maximum of one charging pump (centrifugal) be capable of injecting into the RCS, and all accumulator discharge isolation valves be closed and de-energized (when
accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed in the PTLR).
The LCO is modified by a note that permits the operation in MODE 4 with all SI pumps and charging pumps capable of RCS injection whenever all RCS cold legs exceed 330
°F. This is necessary to allow transition between MODES 3 and 4.
The elements of the LCO that provide low temperature overpressure mitigation through pressure relief are:
- a. Two OPERABLE PORVs;
- b. Two OPERABLE RHR suction relief valves;
- c. One OPERABLE PORV and one OPERABLE RHR suction relief valve; or
- d. A depressurized RCS and an OPERABLE RCS vent.
A PORV is OPERABLE for LTOP when its block valve is open, its lift setpoint is set to the limit required by the PTLR and testing proves its ability to open at this setpoint, and
motive power is available to the two valves and their control circuits.
An RHR suction relief valve is OPERABLE for LTOP when its RHR suction isolation valves are open, its setpoint is 450 psig, and testing has proven its ability to open at this setpoint. two notes. Note 1Note 2 permits operation in MODE 5 and in MODE 6 when the reactor vessel head is on with one or more SI pumps capable of RCS injection whenever pressurizer level is < 5 percent. This is necessary to provide for the mitigation of the effects of a loss of decay heat removal cooling event during mid-loop operations. Operation of at least one SI pump is required in some instances to prevent core uncovery.