Similar Documents at Byron |
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Category:Letter type:RS
MONTHYEARRS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval2024-09-13013 September 2024 Relief Requests Associated with the Fifth Inservice Inspection Interval RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds 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-23-075, 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-23-056, 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-23-049, 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-22-110, 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-22-074, 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 2024-09-13
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition 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-23-075, 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-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-22-037, 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 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-21-076, 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-21-039, 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 ML20303A3232020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 1 of 5 ML20303A3252020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 2 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 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 ML20303A3272020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 4 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-20-068, 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 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-19-044, 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-18-102, 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 ML18053A1672018-01-31031 January 2018 Attachment 2A - Byron Station Units 1 & 2 - Mark-up Emergency Plan EP-AA-1000 Pages RS-18-021, License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements RS-18-021, Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements ML18053A1802018-01-31031 January 2018 Enclosure 2 Byron Station Units 1 & 2 - Evaluation of Proposed Changes ML18053A1682018-01-31031 January 2018 Attachment 2B - Byron Station Units 1 & 2 - Clean Emergency Plan EP-AA-1000 Pages RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors.2017-09-0101 September 2017 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. RS-17-081, License Amendment Request to Revise Control Room Ventilation Temperature Control System Technical Specification2017-06-30030 June 2017 License Amendment Request to Revise Control Room Ventilation Temperature Control System Technical Specification RS-17-058, License Amendment Request to Incorporate Changes Supported by TSTF-547, Clarification of Rod Position Requirements.2017-06-30030 June 2017 License Amendment Request to Incorporate Changes Supported by TSTF-547, Clarification of Rod Position Requirements. RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process 2024-05-28
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Michael P. Gallagher Vice President. License Renewal Exelon Generation Exelon Nuclear 200 Exelon Way Kennett Square. PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 RS-15-174 June 17, 2015 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455
Subject:
Revisions to Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant's Environmental Report, Sections 3.1.3, 3.1 .3.1 and 4.1
References:
Exelon Generation Company, LLC letter from Michael P. Gallagher to NRC Document Control Desk, "Application for Renewed Operating Licenses", dated May 29, 2013 In the referenced letter, Exelon Generation Company, LLC (Exelon Generation) submitted the License Renewal Application (LRA) for the Byron and Braidwood Stations, Units 1 and 2, including Appendix E, Item E-1 to the LRA, which is the Byron Station Applicant's Environmental Report.
The enclosure to this letter provides revised versions of pages from Sections 3.1.3, 3.1.3.1 and 4.1 in the Byron Station Applicant's Environmental Report.
This letter and its enclosure contain no regulatory commitments.
If you have any questions, please contact Ms. Nancy Ranek, Environmental Lead, Exelon Generation License Renewal, at 610-765-5369.
June 17, 2015 U.S. Nuclear Regulatory Commission Page 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on:
Respectfully, Michael P. Gallagher Vice President - License Renewal Projects Exelon Generation Company, LLC Enclosure - Revisions to Byron Station Applicant's Environmental Report, Sections 3.1.3, 3.1 .3.1, and 4.1 cc: Regional Administrator- NRC Region Ill NRC Project Manager (Environmental Review), NRR-DLR NRC Project Manager (Safety Review), NRR-DLR NRC Project Manager, NRR-DORL Byron Station NRC Senior Resident Inspector, Byron Station Illinois Emergency Management Agency- Division of Nuclear Safety
RS-15-174 ENCLOSURE Page 1 of 3 ENCLOSURE Revisions to Byron Station Applicants Environmental Report, Sections 3.1.3, 3.1.3.1, and 4.1
RS-15-174 ENCLOSURE Page 2 of 3 Purpose and Description of Revisions The purpose of revising the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicants Environmental Report (Byron ER), Sections 3.1.3, 3.1.3.1, and 4.1, is to improve consistency with respect to how the Stations maximum potential rate of makeup water withdrawal from the Rock River is characterized in the Byron ER and documentation submitted to other regulatory agencies (e.g., documentation submitted to the Illinois Environmental Protection Agency in accordance with 40 CFR §122.21(r)). The following table summarizes the revisions to the Byron ER. Replacement pages showing these revisions in the Byron ER are also provided in this Enclosure. The replacement pages supersede the pages in the originally filed version of the Byron ER.
ER ER Description of Revision Page # Section #
3-5 3.1.3 Add the number (i.e., two) and rated capacity of the essential service water makeup pumps (i.e., 94.6 L/s or 1,500 gpm) to their description.
Clarify the routing of makeup water from the circulating water makeup pipeline to the mechanical draft cooling tower basin during normal operation and the routing of makeup water from the essential service water makeup pumps to the mechanical draft cooling tower basin.
3-6 3.1.3.1 Change the anticipated maximum gross withdrawal rate from the Rock River to include not only the pumping rate of the CWS makeup water pumps, but also the pumping rate of the two essential service water makeup pumps because, although the essential service water makeup pumps operate only as emergency backup sources of makeup to the essential service water system, they are capable of operating at maximum capacity simultaneously with the two CWS makeup water pumps. Under such circumstances, the maximum gross withdrawal rate from the Rock River could be as high as the sum of the rated capacity of all four pumps (i.e., 3,218 L/s, 113.6 cfs or 51,000 gpm).
4-10 4.1 Add the essential service water system and its associated mechanical draft cooling towers to the description of systems that receive makeup water from the Rock River.
4-11 4.1 Change the anticipated maximum gross withdrawal rate from the Rock River to include not only the pumping rate of the CWS makeup water pumps, but also the pumping rate of the two essential service water makeup pumps because, although the essential service water makeup pumps operate only as emergency backup sources of makeup to the essential service water system, they are capable of operating at maximum capacity simultaneously with the two CWS makeup water pumps. Under such circumstances, the maximum gross withdrawal rate from the Rock River could be as high as the sum of the rated capacity of all four pumps (i.e., 3,218 L/s, 113.6 cfs or 51,000 gpm).
RS-15-174 ENCLOSURE Page 3 of 3 REPLACEMENT PAGES FOR Byron Station Applicants Environmental Report Page Number in Replacement Page Original ER Number 3-5 3-5 3-6 3-6 4-10 4-10 4-11 4-11 NOTE: The replacement pages listed in the table, above, are provided as the last four (unnumbered) pages in this Enclosure to RS-15-174.
Byron Station Environmental Report Section 3.1 General Plant Information Pursuant to the general license issued in 10 CFR 72.210, Exelon Generation operates an ISFSI at the Byron site. The general license allows Exelon Generation, as a reactor licensee under 10 CFR Part 50, to store spent fuel at the ISFSI, provided that such storage occurs in pre-approved casks in accordance with the requirements of 10 CFR Part 72, subpart K (General License for Storage of Spent Fuel at Power Reactor Sites). Spent fuel transfers to the ISFSI began in September, 2010 (Exelon Nuclear 2010f).
The 1996 GEIS (NRC 1999a) noted that 10 CFR 51.23 codifies the NRCs generic determination that storage and disposal of spent fuel during the licensed life for operation of nuclear power plants (which may include the term of a renewed license) can be accomplished safely and without significant environmental impact. In accordance with this determination, the 1996 GEIS concluded that no discussion of environmental impacts of spent fuel storage for the period following the term of a reactor operating license, including a renewed license was required. In 2010, the Commission updated and continued the provisions in 10 CFR 51.23 (referred to as the Waste Confidence Decision Update and Temporary Storage Rule, or WCD Update and Rule) based on experience in the storage of spent nuclear fuel and the increased uncertainty in the siting and construction of a permanent geologic repository for the disposal of spent nuclear fuel (75 FR 81031; December 23, 2010). On June 8, 2012, the D.C. Circuit Court of Appeals vacated and remanded the WCD Update and Rule (New York v. NRC, 681 F.3d 471 (D.C. Cir. 2012)). In response, the NRC Commissioners suspended the issuance of licenses for which the NEPA review would depend on the WCD Update and Rule (NRC 2012b). Because the Commissioners consider responding to the D.C. Circuit Courts concerns to be a generic issue, they further directed the NRC staff to conduct a rulemaking (NRC 2012c). This effort by the NRC staff is ongoing. The updated rule and supporting EIS will provide the NEPA analyses of waste-confidence-related human health and environmental impacts needed to support renewal of the Byron operating license.
3.1.3 Cooling and Auxiliary Water Systems The Byron circulating water system uses two natural draft cooling towers (see Figure 3.1-2), one tower per unit, to dissipate excess heat from condenser cooling water and nonessential service water. Water chemistry in this closed cycle system is controlled by continuous blowdown from the condenser supply water and makeup to an open flume between the two natural draft cooling towers. Makeup water comes from the Rock River and blowdown water is directed back to the Rock River.
In addition to the two natural draft cooling towers, Byron also has two mechanical draft cooling towers to cool essential service water, which removes heat from safety-related equipment, and to serve as the ultimate heat sink for the reactors. Because of their safety function, the mechanical draft cooling towers operate continuously when the reactors are operating, and they also must have a makeup water supply that is capable of supporting 30 days of continuous operation in support of safe shutdown. Normal makeup water to replace evaporation and blowdown from the mechanical draft cooling towers is supplied from the Rock River via a line from the circulating water system makeup water pipeline to the mechanical draft cooling 6/17/15 tower basin. Emergency backup sources of makeup water are also available via: (1) two 12-in. (0.3-m) pipelines, one each from the two essential service water makeup pumps, each of which is rated at 94.6 L/s (1,500 gpm) and located at the Rock River intake structure (river screen house); and (2) two on-site deep wells described in Section 3.1.3.2 (NRC 1982; Exelon Nuclear 2010a). Blowdown from the mechanical draft cooling towers is routed to the flume between the two natural draft cooling towers.
The following subsections describe the water systems at Byron in greater detail.
Byron and Braidwood Stations, Units 1 and 2 Page 3-5 License Renewal Application
Byron Station Environmental Report Section 3.1 General Plant Information 3.1.3.1 Surface Water Byron has an agreement with the Illinois DNR to limit consumption of water from the Rock River for makeup to the Byron cooling systems to no more than 9 percent of total river flow during times when the river flow rate drops below 19,200 L/sec (679 cfs). To maintain compliance, Byron would adjust the CWS makeup and blowdown flows, and if necessary, would reduce the power output from the units. The makeup water required by the essential service water and condenser cooling systems varies seasonally. The maximum gross withdrawal rate capability from the Rock River, which would occur only with two CWS makeup pumps and 6/17/15 both essential service water makeup pumps operating simultaneously at their rated flows, is 3,218 L/sec (113.6 cfs or 51,000 gpm) (Exelon Nuclear 2010a). The average makeup withdrawal rate from the Rock River at 100 percent load is 2,320 L/sec (81.9 cfs or 36,750 gpm), out of which 821 to 1,070 L/sec (29 to 38 cfs or 13,000 to 17,000 gpm) is returned to the river as blowdown (Exelon Nuclear 2005).
Under IAC Title 35, Section 302.102, "a [temperature] mixing zone must not contain more than 25 percent of the cross-sectional area or volume of flow of a stream." In Special Condition 3 of NPDES permit IL0048313, IEPA has determined that Byron meets this criteria as well as the thermal water quality standard in Title 35, Section 302.211. The NPDES Permit requires Byron to monitor and report to IEPA the flow and temperature of its blowdown discharge each month.
(IEPA 2011b).
As specified in Special Condition 12 of NPDES permit IL0048313, Byron must also explicitly demonstrate compliance with the thermal water quality standard on a daily basis during times when the Rock River flow is less than 67,944 L/sec (2,400 cfs), or the temperature difference between the main river temperature and the water quality standard is less than 3°F. (IEPA 2011b).
Blowdown is discharged to the Rock River about 61 m (200 ft) downstream of the river screen house. Blowdown is discharged from the outfall structure via an 84-m (275-ft) rip-rapped channel to the river (Exelon Nuclear 2005).
The surface water drainage system at Byron directs storm water runoff from areas associated with industrial activities in four ways, as described in the Byron Storm Water Pollution Prevention Plan (Exelon Nuclear 2003a). First, general drainage within the immediate vicinity of the protected area is into a large oil separator that discharges to an on-site retention pond referred to as the Construction Runoff Pond (CROP). Water collected in the CROP is normally sampled and pumped to the Unit 2 natural draft cooling tower basin where it mixes with circulating water, but in exceptional circumstances, the CROP can overflow directly to Woodland Creek, a tributary of the Rock River north and east of Byron. Second, runoff from the area collectively designated as the East Area is directed to Woodland Creek through permitted Outfall 003. The East Area includes the area east of the natural draft cooling towers and the mechanical draft essential service water cooling towers as well as areas around the east half of the main site. Third, runoff from the area collectively designated as the West Area is directed to an unnamed tributary of the Rock River through permitted Outfall 004. The West Area, which is mostly outside the protected area, includes the areas around the west portion of the main site and the 345 kV switchyard. Finally, sheet flow drains from a small area north of the protected area into Woodland Creek, and from a small area adjacent to the river screen house directly to the Rock River. All storm water discharge paths are subject to the storm water pollution prevention provisions in Special Condition 16 of NPDES Permit IL0048313 and the Byron Storm Water Pollution Prevention Plan (Exelon Nuclear 2003a).
Byron and Braidwood Stations, Units 1 and 2 Page 3-6 License Renewal Application
Byron Station Environmental Report Section 4.1 Water Use Conflicts (Plants Using Cooling Towers or Cooling Ponds and Withdrawing Makeup Water From A Small River With Low Flow) 4.1. Water Use Conflicts (Plants Using Cooling Towers or Cooling Ponds and Withdrawing Makeup Water From A Small River With Low Flow)
NRC If the applicants plant utilizes cooling towers or cooling ponds and withdraws make-up water from a river whose annual flow rate is less than 3.15x1012 ft3/year (9x1010 m3/year), an assessment of the impact of the proposed action on the flow of the river and related impacts on in-stream and riparian ecological communities must be provided 10 CFR 51.53(c)(3)(ii)(A).
The issue has been a concern at nuclear power plants with cooling ponds and at plants with cooling towers. Impacts on instream and riparian communities near these plants could be of moderate significance in some situations 10 CFR Part 51, Subpart A, Appendix B, Table B-1, Issue 13 The water-use issue associated with operation of cooling towers is the availability of adequate stream flows to provide makeup water, particularly during droughts or in the context of increasing in-stream or off-stream uses (NRC 1996b). Because water use circumstances necessarily vary from site to site, the NRC made surface water use conflicts a Category 2 issue.
According to SECY-12-0063, Enclosure 1, the final rule supported by the updated GEIS will modify this issue by making it applicable to any plant that withdraws make-up water from a river, regardless of the rivers flow rate.
As discussed in Section 3.1.3, the Byron essential service water and circulating water systems use two banks of mechanical draft cooling towers and two closed-cycle natural draft cooling 6/17/15 towers, respectively, that receive their makeup water from the Rock River. The Rock River drains an approximately 28,270 square kilometers (km2) (10,915 square miles [mi2]) area from southeastern Wisconsin through northern Illinois to its confluence with the Mississippi River downstream from Rock Island, Illinois. The drainage area upstream of the plant is approximately 20,700 km2 (8,000 mi2) (NRC 1982).
The U.S. Geological Survey (USGS) maintains a gaging station at Como, Illinois, approximately 74 km (46 mi) downstream of the Byron blowdown discharge at River Mile 62.9 (USGS 2011).
For water years 1935 - 2010, annual mean flow at the Como gaging station averaged 204,023 L/sec (6,012 cfs) (USGS 2011) or 1.89 x1011 ft3/year. Therefore, the Rock River meets the NRC definition of a small river.
Prior to 2006, there were no comprehensive statewide or regional plans for managing the water supply in Illinois. Signed in January 2006, Executive Order (EO) 2006-1 called for a comprehensive program for state and regional water supply planning and management, a strategic plan for the program's implementation, and development of regional water supply plans in two priority water quantity planning areas: east central Illinois and northeastern Illinois (CMAP 2010a). In 2009, funding allowed for the inclusion of the Kaskaskia region as the third Byron and Braidwood Stations, Units 1 and 2 Page 4-10 License Renewal Application
Byron Station Environmental Report Section 4.1 Water Use Conflicts (Plants Using Cooling Towers or Cooling Ponds and Withdrawing Makeup Water From A Small River With Low Flow) priority area for water supply planning efforts (ISWS 2012). Byron is not within any of the three priority planning areas.
Fundamental elements of EO 2006-1 include ensuring that water demand and supply result in equitable availability through drought and non-drought conditions, and protecting water quality and in-stream flows. One planning goal of EO 2006-1 is to manage rivers in Illinois to ensure that river flows remain above the interim 1-day, 10-year low (Q1/10) or 7-day, 10-year low (Q7/10) protected flow level.
Byron has an agreement with the Illinois DNR to limit consumption of water from the Rock River for makeup to the Byron cooling systems to no more than 9 percent of total river flow during times when the river flow rate drops below 19,200 L/sec (679 cfs). Fundamental elements of EO 2006-1 include ensuring that water demand and supply result in equitable availability through drought and non-drought conditions, and protecting water quality and in-stream flows. To maintain compliance, Byron adjusts the CWS makeup and blowdown flows, and if necessary, would reduce the power output from the units.
The maximum gross withdrawal rate capability from the Rock River, which would occur only with two CWS makeup pumps and both essential service water makeup pumps operating 6/17/15 simultaneously, is 3,218 L/sec (113.6 cfs or 51,000 gpm) (Exelon Nuclear 2010a). The average makeup withdrawal rate from the Rock River at 100 percent load factor is 2,320 L/
sec (81.9 cfs or 36,750 gpm), out of which 821 to 1,070 L/sec (29 to 37.9 cfs or 13,000 to 17,000 gpm) is returned to the river as blowdown (Exelon Nuclear 2005).
Based on the Rock Rivers 75-year average annual mean flow at the Como gaging station of 170,241 L/sec (6,012 cfs; see Section 2.2.2), Byrons average makeup withdrawal rate of 2,320 L/sec (81.9 cfs) represents approximately 1.3 percent of the rivers average annual mean flow. However, since 821 to 1,070 L/sec (29 to 37.9 cfs) is returned to the river as blowdown, the net makeup withdrawal from the river ranges from 1,250 to 1,500 L/sec (44 to 53 cfs), which represents 0.73 to 0.88 percent of the average annual mean flow of the river at the intake.
Even at a river flow of 19,200 L/sec (679 cfs), at which point the IDNR agreement prevents withdrawal exceeding 9 percent of total river flow, the plants net makeup withdrawal of 1,250 to 1,500 L/sec (44 to 53 cfs) represents 6.5 to 7.8 percent of the river flow Based on the information presented above, withdrawals of surface water for the operation of Byron during low-flow periods would have a SMALL impact on the availability of fresh water downstream of the site and would not warrant further mitigation.
Hypothetical refurbishment in the form of steam generator replacement would not increase water withdrawals from the Rock River and therefore, would not change this conclusion.
Impact to alluvial aquifers caused by the Byron makeup water withdrawal is addressed in Section 4.6.
Byron and Braidwood Stations, Units 1 and 2 Page 4-11 License Renewal Application