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Category:Letter type:RS
MONTHYEARRS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision RS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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-24-088, 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-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink 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-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-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-23-094, 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-23-093, 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-23-091, 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 . 2024-09-13
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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 ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for 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-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-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to 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 BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements 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-23-038, 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-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-22-084, 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-22-074, 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-22-027, 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 ML21320A2422021-11-16016 November 2021 Stations - Response to Request for Additional Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments ML21225A0062021-08-13013 August 2021 Response to Request for Additional Information Regarding License Amendment Request to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 0 NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting RS-21-024, Response to Request for Additional Information (RAI) Regarding Byron Station, Units 1 and 2, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2021-03-16016 March 2021 Response to Request for Additional Information (RAI) Regarding Byron Station, Units 1 and 2, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-21-029, Response to RAI Re License Amendment Request - Proposed Changes to Byron & Dresden Stations Emergency Plan for Post-Shutdown and Permanently Defueled Condition2021-03-15015 March 2021 Response to RAI Re License Amendment Request - Proposed Changes to Byron & Dresden Stations Emergency Plan for Post-Shutdown and Permanently Defueled Condition RS-21-015, Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-182021-02-10010 February 2021 Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-18 RS-21-019, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections2021-02-0909 February 2021 Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections RS-20-017, Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-8852021-02-0101 February 2021 Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-885 RS-20-150, Response to Request for Additional Information Related to Subsequent Exemption from Part 26 Requirements2020-12-0101 December 2020 Response to Request for Additional Information Related to Subsequent Exemption from Part 26 Requirements RS-20-147, Response to Request for Additional Information Related to Exemption from Part 26 Requirements2020-11-23023 November 2020 Response to Request for Additional Information Related to Exemption from Part 26 Requirements RS-20-143, Response to Request for Additional Information Regarding Application to Revise Technical Specifications 3.8.1, AC Sources- Operating2020-11-20020 November 2020 Response to Request for Additional Information Regarding Application to Revise Technical Specifications 3.8.1, AC Sources- Operating RS-20-100, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections2020-08-19019 August 2020 Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information RS-20-057, Response to Request for Additional Information Regarding Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-13013 April 2020 Response to Request for Additional Information Regarding Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections RS-20-012, Response to Request for Additional Information Regarding Relief Request Associated with the Third Ten-Year Inservice Inspection Program Interval2020-01-29029 January 2020 Response to Request for Additional Information Regarding Relief Request Associated with the Third Ten-Year Inservice Inspection Program Interval NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 RS-19-100, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended.2019-10-0707 October 2019 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended. RS-19-088, Response to Request for Additional Information Regarding Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed...2019-09-0505 September 2019 Response to Request for Additional Information Regarding Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed... JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 RS-19-051, Response to Request for Additional Information for the License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies2019-05-30030 May 2019 Response to Request for Additional Information for the License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements RS-18-095, Response to Request for Additional Information Regarding Braidwood Station Fourth Lnservice Inspection Interval Relief Request 14R-032018-07-31031 July 2018 Response to Request for Additional Information Regarding Braidwood Station Fourth Lnservice Inspection Interval Relief Request 14R-03 RS-18-094, Response to Request for Additional Information Regarding Braidwood Station Fourth Lnservice Inspection Interval Relief Request 14R-062018-07-31031 July 2018 Response to Request for Additional Information Regarding Braidwood Station Fourth Lnservice Inspection Interval Relief Request 14R-06 RS-18-097, Response to Request for Additional Information and Supplemental Information-License Amendment.2018-07-27027 July 2018 Response to Request for Additional Information and Supplemental Information-License Amendment. RS-18-084, Response to Request for Additional Information Regarding Braidwood TORMIS Amendment Request2018-07-0909 July 2018 Response to Request for Additional Information Regarding Braidwood TORMIS Amendment Request RS-18-083, Response to Request for Additional Information Regarding Braidwood Station Fourth Inservice Inspection Interval Relief Request 14R-052018-06-22022 June 2018 Response to Request for Additional Information Regarding Braidwood Station Fourth Inservice Inspection Interval Relief Request 14R-05 RS-18-072, Response to Request for Additional Information Regarding 50.69 Amendment2018-06-13013 June 2018 Response to Request for Additional Information Regarding 50.69 Amendment RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) RS-18-041, Response to Request for Additional Information Regarding Request for Relief (I4R-07) for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ...2018-04-12012 April 2018 Response to Request for Additional Information Regarding Request for Relief (I4R-07) for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ... RS-17-138, Stations - Response to Request for Additional Information Related to License Amendment Request to Incorporate Changes Supported by TSTF-547, Clarification of Rod Position Requirements'2017-10-25025 October 2017 Stations - Response to Request for Additional Information Related to License Amendment Request to Incorporate Changes Supported by TSTF-547, Clarification of Rod Position Requirements' RS-17-084, Response to Request for Additional Information for Byron Station and Braidwood Station Post Peening Relief Requests2017-07-14014 July 2017 Response to Request for Additional Information for Byron Station and Braidwood Station Post Peening Relief Requests 2024-08-09
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RS-1 5-264 10 CFR 50.90 October 9, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units I and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units I and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Response to Request for Additional Information Regarding the License Amendment Request to Install New Low Degraded Voltage Relays and Timers on the 4.16 kV Engineered Safety Features (ESF) Buses
References:
(1) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. NRC, "License Amendment Request to Install New Low Degraded Voltage Relays and Timers on the 4.16 kV Engineered Safety Features (ESF) Buses," dated April 24, 2014 (2) Email from J. S. Wiebe (U. S. NRC) to J. A. Bauer (Exelon Generation Company, LLC), "Preliminary Request for Additional Information Regarding Braidwood and Byron New Low Degraded Voltage Relays and Timers (MF4051, MF4052, M174053, and MF4054)," dated October 23, 2014 (3) Email from J. S. Wiebe (U. S. NRC) to J. A. Bauer (Exelon Generation Company, LLC), "Preliminary Request (2nd Set) for Additional Information Regarding Braidwood and Byron New Low Degraded Voltage Relays and Timers (MF4051, MF4052, M174053, and MF4054)," dated November 10, 2014 (4) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. NRC, "Supplement and Response to Request for Additional Information Regarding the License Amendment Request to Install New Low Degraded Voltage Relays and Timers on the 4.16 kV Engineered Safety Features (ESF) Buses,"
dated April 30, 2015 (5) Email from J. S. Wiebe (U. S. NRC) to J. A. Bauer (Exelon Generation Company, LLC), "Preliminary Follow Up RAls Regarding LAR to Install New Degraded Voltage Relays and Timers," dated August 12, 2015
October 9, 2015 U. S. Nuclear Regulatory Commission Page 2 In Reference 1, Exelon Generation Company, LLC, (EGC) requested an amendment to Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units I and 2, and Facility Operating License Nos. NPF-37 and NPF-66 for Byron Station, Units I and 2. This amendment request proposed to revise Technical Specifications (TS) 3.3.5, "Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation." Specifically, LCO 3.3.5 would be revised to add a new "low degraded voltage" Function. In addition, the associated Surveillance Requirement (SR) 3.3.5.2 would be revised to add a CHANNEL CALIBRATION to verify the specified values for the new low degraded voltage Allowable Value and time delay setting.
In References 2 and 3, the NRC requested that EGC provide additional information to support their review of the subject License Amendment Request (i.e., Reference 1). The response to these requests was provided in Reference 4. In Reference 5, the NRC requested additional information related to the responses provided in Reference 4. During a follow-up clarification call to discuss the information requested in Reference 5, one minor revision was made to Question 1.
It was also agreed that EGC would provide the requested information to the NRC on or before October 9, 2015. The subject response is provided in Attachment 1.
EGC has reviewed the information supporting the No Significant Hazards Consideration and the Environmental Consideration that was previously provided to the NRC in Reference 1. The additional information provided in this submittal does not affect the conclusion that the proposed license amendment does not involve a significant hazards consideration. This additional information also does not affect the conclusion that neither an environmental impact statement nor an environmental assessment need be prepared in support of the proposed amendment.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b),
EGC is notifying the State of Illinois of this additional information by transmitting a copy of this letter and its attachment to the designated State Official.
This letter contains no new regulatory commitments. If you have any questions concerning this letter, please contact Joseph A. Bauer at (630) 657-2804.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 9th day of October 2015.
Respectfully, David M. Gullott Manager Licensing Exelon Generation Company, LLC Attachment 1: Response to Request for Additional Information cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector, Braidwood Station NRC Senior Resident Inspector, Byron Station Illinois Emergency Management Agency Division of Nuclear Safety
ATTACHMENT I Response to Request for Additional Information In Reference 1, Exelon Generation Company, LLC, (EGC) requested an amendment to Facility Operating License Nos NPF-72 and NPF-77 for Braidwood Station, Units I and 2 and Facility Operating License Nos. NPF-37 and NPF-66 for Byron Station, Units I and 2. This amendment request proposed to revise Technical Specifications (TS) 3.3.5, "Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation." Specifically, LCO 3.3.5 would be revised to add a new "low degraded voltage" Function. In addition, the associated Surveillance Requirement (SR) 3.3.5.2 would be revised to add a CHANNEL CALIBRATION to verify the specified values for the new low degraded voltage Allowable Value and time delay setting.
In References 2 and 3, the NRC requested that EGC provide additional information to support their review of the subject License Amendment Request (i.e., Reference I). The response to these requests was provided in Reference 4. In Reference 5, the NRC requested additional information related to the responses provided in Reference 4. During a follow-up clarification call to discuss the information requested in Reference 5, one minor revision was made to Question 1. The requested information is provided below.
Electrical Engineering Branch (EEB)
Request for Additional Information (RAI)
During normal plant operation, the Class I safety-related buses should automatically separate from the power supply within a short interval if sustained degraded voltage conditions are detected. The time delay chosen should be optimized to ensure that permanently connected Class IE loads are not damaged under sustained degraded voltage conditions (such as a sustained degraded voltage below the DVR [Degraded Voltage Relay] voltage setting(s) for the duration of the time delay setting).
RAIl In response to the NRC staff's RAI Question No. 2 concerning safety-related loads to start and run without damaging and actuating their protective devices, your response dated April 30, 2015, stated the following in Section F.
BTP PSB-1, "Adequacy of Station Electric Distribution System Voltages," Section B. 1.b.2 states in part, "The second time delay should be of a limited duration such that the permanently connected Class I E loads will not be damaged." The BTP does not specifically require that loads be capable of starting under low degraded voltage conditions; therefore, the Byron Station and Braidwood Station low degraded voltage evaluations did not specifically analyze the potential starting of loads under low degraded voltage conditions.
To complete its review of Exelon's application dated April 24, 2015, the NRC staff requires information that addresses the capability of safety-related loads to start under degraded voltage conditions. The staff position is that for a time delay period of 340 seconds, for Byron and Braidwood Stations, the licensee must demonstrate that safety-related loads will have adequate voltage to start and run without damaging or actuating protective devices that can disable safety related equipment. The staff position and requirements have been further clarified in Regulatory Issue Summary 2011-12 "Adequacy of Station Electric Distribution System Voltages,"
Revision 1. Therefore the staff requests that the licensee provide a summary of the analysis to show that all safety-related loads can start and run without actuating their protective devices, including control circuit fuses, and none of the safety-related loads will be degraded with the proposed degraded voltage relay setpoints (voltage and time delay).
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ATTACHMENT I Response to Request for Additional Information Response to RAI I The original degraded voltage logic was developed in accordance with the guidance provided by BTP PS B-1. The existing Degraded Voltage Relay (DVR) setpoint was developed to provide protection (i.e., to ensure voltage requirements are met) for Class 1 safety-related buses and components from sustained degraded voltage conditions on the offsite power system coincident with an accident as well as during non-accident conditions. The Class 1 E buses will separate from the offsite power system immediately if an accident occurs coincident with sustained degraded voltage conditions (i.e., degraded voltage condition exists for at least 10 seconds) below the DVR setpoint. The development of the setpoint is consistent with the discussion of DVR Setting Design Calculations provided in RIS 2011-12, Revision 1. Specifically, division specific degraded voltage analyses were performed for each Byron Station and Braidwood Station safety-related distribution system to determine the existing DVR setpoint and analytically demonstrate that adequate voltage exists for starting and running all safety-related equipment at or above the DVR setpoint value.
The plant changes to install the new Low Degraded Voltage Relay (LDVR) and the associated License Amendment Request (LAR) to include the LDVR setpoint in the Technical Specifications (TS) do not impact the existing DVR function, setpoints, or analysis as described above.
Prior to the installation of the LDVR and associated TS setpoints, EGC could not demonstrate that the permanently connected loads to the Class I E buses would operate without actuation of protective devices if subjected to a degraded voltage condition below the DVR setpoint, all the way down to the loss of power (LOP) setpoint, for the entire 340 second time delay. Therefore, as described in the LAR (Reference 1), the LDVRs and the associated setpoints are analyzed to limit the degree of undervoltage during the 340 second time delay to ensure that permanently connected Class I E loads are not damaged under the sustained degraded voltage conditions.
As stated in RIS 2011-12, Revision 1, this is a sustained degraded voltage below the DVR voltage setting for the duration of the time delay setting.
The intent of our previous RAI response was to clarify that analyses for the permanently connected loads have been performed down to the LDVR setpoint. However, consistent with the requirements of BTP PSB-1 and RIS 2011-12, Revision 1, analyses of the startup and operation of non-permanently connected loads during the time delay is not postulated or analyzed.
Therefore, the analyses performed to support the LDVR setpoints demonstrate that any permanently connected load (i.e., any load that would be expected to be operating at the start of a degraded voltage condition) would continue to operate throughout the 340 second time delay without sustaining damage or actuating protective devices that would prevent the component from performing its intended safety function.
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ATTACHMENT I Response to Request for Additional Information RAI2 In response to the NRC staff's RAI Question No. 3.c concerning evaluations to show that a momentary voltage dip lasting approximately 3 seconds to a value marginally above the loss of voltage relay setpoint, with a recover,' to the reset point of the LDVR [Low Degraded Voltage Relay] will not adversely impact any important to safety equipment which may be required to operate for more than 5 minutes, in its response dated April 30, 2015, the licensee stated the following:
Valves were not evaluated because they are not continuous loads and are not expected to operate during a degraded voltage condition. Therefore, valves were considered outside the scope of the BTP PSB-1 requirements.
To complete its review of Exelon's application dated April 24, 2015, the NRC staff requires information regarding the evaluation of valves for the degraded voltage condition. In accordance with the guidance delineated in Generic Letter No. 89-10: "Safety Related Motor-Operated Valve Testing and Surveillance, "licensees demonstrated that all safety-related motor operated valves (MOV) can perform key safety functions at the degraded voltage relay setpoint.
The response to RAI 3.c indicates that voltages at MOV terminals may drop below the LDVR setpoint for approximately 3 seconds. Provide a summary of the evaluation for the motor operated valves including any impact due to momentary voltage dips lasting 3 seconds.
Resoonse to RAI 2 Consistent with the guidance delineated in Generic Letter No. 89-10 "Safety Related Motor-Operated Valve Testing and Surveillance," Byron Station and Braidwood Station MOV motor terminal voltage calculations were performed to demonstrate that all safety-related MOVs can perform key safety functions at the existing Degraded Voltage Relay (DVR) setpoint. The response provided to RAI Question 3.c was related to the position that MOVs are not considered permanently connected loads and, as such, were not included in the analyzes performed to show that running motors were not damaged by sustained operation below the DVR setpoint for the maximum time period (i.e., 340 seconds) allowed by the DVR logic.
Consistent with the requirements in BTP PSB-1, the Byron Station and Braidwood Station DVR logic consists of two time delay periods. The first time delay is 10 seconds and confirms the existence of a sustained degraded voltage condition (i.e., a period longer than a motor-starting transient). During the first time delay period, an external grid event is postulated to occur resulting in the degraded Class I E bus voltage. An additional, independent plant transient or accident occurring within the short duration of the first time delay is not, and has historically not been, an event required to be analyzed. During the subsequent second time delay (i.e. after the 10 second initial time delay) the BTP PS B-1 guidance explicitly postulates the occurrence of a safety injection (SI) actuation signal. The SI actuation signal results in the immediate separation of the Class I E safety-related buses from the offsite power system.
The guidance provided in BTP PSB-I and RIS 2011-12, Revision 1 did not require analysis of other abnormal operational occurrence or accident loads during the second time delay.
Therefore, since MOVs are not normally connected loads and are started only in response to a plant accident or transient, evaluation of the MOVs below the DVR setting, including any impact due to momentary voltage dips below the LDVR lasting 3 seconds, is considered outside the design guidance and requirements.
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ATTACHMENT I Response to Request for Additional Information REFERENCES
- 1. Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. NRC, "License Amendment Request to Install New Low Degraded Voltage Relays and Timers on the 4.16 kV Engineered Safety Features (ESF) Buses," dated April 24, 2014
- 2. Email from J. S. Wiebe (U. S. NRC) to J. A. Bauer (Exelon Generation Company, LLC),
"Preliminary Request for Additional Information Regarding Braidwood and Byron New Low Degraded Voltage Relays and Timers (MF4051, MF4052, MF4053, and MF4054)," dated October 23, 2014
- 3. Email from J. S. Wiebe (U. S. NRC) to J. A. Bauer (Exelon Generation Company, LLC),
"Preliminary Request (2nd Set) for Additional Information Regarding Braidwood and Byron New Low Degraded Voltage Relays and Timers (MF4051, MF4052, MF4053, and MF4054)," dated November 10, 2014
- 4. Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. NRC, "Supplement and Response to Request for Additional Information Regarding the License Amendment Request to Install New Low Degraded Voltage Relays and Timers on the 4.16 kV Engineered Safety Features (ESF) Buses," dated April 30, 2015
- 5. Email from J. S. Wiebe (U. S. NRC) to J. A. Bauer (Exelon Generation Company, LLC),
"Preliminary Follow Up RAIs Regarding LAR to Install New Degraded Voltage Relays and Timers," dated August 12, 2015 Page 4 of 4