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MONTHYEARML13310B9292013-12-0606 December 2013 Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During ... Project stage: Meeting RS-15-091, Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2015-03-31031 March 2015 Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink Project stage: Response to RAI ML15232A5892015-09-14014 September 2015 Regulatory Audit Report for the June 11, 2015 Audit in Support of the Ultimate Heat Sink License Amendment Request Project stage: Other RS-15-266, Response to Request for Additional Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink.2015-10-0909 October 2015 Response to Request for Additional Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink. Project stage: Response to RAI ML15299A0132015-10-21021 October 2015 NRR E-mail Capture - (External_Sender) 1 of 2: Final Report: Five Year Post-construction Monitoring of the Unionid Community Near Braidwood Station Kankakee River Discharge Project stage: Request ML15322A3172015-11-18018 November 2015 Record of Decision Project stage: Request ML15314A8142015-11-30030 November 2015 NUREG-1437, Suppl 55, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Braidwood Station, Units 1 and 2 Final Report. Project stage: Acceptance Review RS-16-049, Supplemental Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink.2016-02-12012 February 2016 Supplemental Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink. Project stage: Supplement ML16181A0072016-07-18018 July 2016 Environmental Assessment and Finding of No Significant Impact Related to Ultimate Heat Sink Modification Project stage: Other 2015-11-30
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Category:Letter type:RS
MONTHYEARRS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-114, 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-23-097, 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-23-083, 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-23-040, 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-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0606 June 2022 Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022 Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube. RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-050, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-04-0808 April 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-014, Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time2022-03-24024 March 2022 Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time RS-22-041, Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes2022-03-22022 March 2022 Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes RS-22-036, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-03-10010 March 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-22-008, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin2022-01-24024 January 2022 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-117, Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d)2021-12-0909 December 2021 Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d) RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections 2024-01-11
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-117, Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d)2021-12-0909 December 2021 Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d) ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink2021-08-0202 August 2021 License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-057, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2021-05-27027 May 2021 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-20-089, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2020-07-15015 July 2020 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-20-068, Application to Revise Technical Specifications 3.8.1, AC Sources-Operating2020-06-26026 June 2020 Application to Revise Technical Specifications 3.8.1, AC Sources-Operating RS-20-058, Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-16016 April 2020 Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections RS-20-044, Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-0606 April 2020 Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections ML20063L2822020-02-28028 February 2020 Application of Westinghouse Full Spectrum LOCA Evaluation Model RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2020-02-28028 February 2020 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues2020-02-0606 February 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions2019-12-0909 December 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions RS-19-078, License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies.2019-09-24024 September 2019 License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies. RS-19-082, License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS)2019-09-11011 September 2019 License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS) RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) RS-19-081, Supplement to Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2019-08-0909 August 2019 Supplement to Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements RS-19-018, Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times2019-02-14014 February 2019 Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times RS-19-008, Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2019-01-31031 January 2019 Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RS-18-129, Supplement to License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies2018-10-19019 October 2018 Supplement to License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies RS-18-035, 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-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) RS-18-016, License Amendment Request to Utilize the TORMIS Computer Code Methodology2018-02-0101 February 2018 License Amendment Request to Utilize the TORMIS Computer Code Methodology 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 ML18053A1662018-01-31031 January 2018 Attachment 1B - Braidwood Station Units 1 & 2 - Clean 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 ML18053A1652018-01-31031 January 2018 Attachment 1A - Braidwood Station Units 1 & 2 - Mark-up Emergency Plan EP-AA-1000 Pages ML18053A1792018-01-31031 January 2018 Enclosure 1 - Braidwood Station, Units 1 & 2 - Evaluation of Proposed Changes 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 2023-09-29
[Table view] |
Text
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RS-16-049 10 CFR 50.90 February 12, 2016 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50-457
Subject:
Supplemental Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, "Ultimate Heat Sink"
References:
- 1) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"
dated August 19, 2014 (ML14231A902)
- 2) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC)
Preliminary RAls for LAR Regarding Braidwood Station Technical Specification, "Ultimate Heat Sink," dated February 5, 2015 (ML15036A431)
- 3) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"' dated March 31, 2015 (ML151090A604)
- 4) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"' dated April 30, 2015 (ML15120A396)
- 5) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC)
Additional RAI Regarding Containment Analysis for Braidwood UHS LAR (MF4671 and MF4672), dated July 22, 2015
- 6) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC)
Need Clarification Conference Call Regarding Your April 30, 2015 Response to SCVB-RAI-1(a), dated August 12, 2015 (ML1522413548)
February 12, 2016 U.S. Nuclear Regulatory Commission Page 2
- 7) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC)
Additional RAls Regarding Braidwood Ultimate Heat Sink Temperature Amendment, dated September 29, 2015
- 8) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"' dated October 9, 2015
- 9) Letter D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"' dated October 30, 2015 10)Letter D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"' dated November 9, 2015 11)Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC)
Preliminary Balance of Plant RAls for Braidwood Ultimate Heat Sink LAR, dated October 26, 2015 12)Letter Glen T. Kaegi (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"' dated December 16, 2015 In Reference 1, Exelon Generation Company, LLC, (EGC) requested an amendment to the Technical Specifications (TS) of Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2. The proposed amendment would modify TS 3.7.9, "Ultimate Heat Sink (UHS)," by changing the maximum allowable temperature of the UHS from 100 OF to a maximum UHS temperature of 102°F.
The U. S. Nuclear Regulatory Commission (NRC) requested additional information related to its review of Reference 1 in References 2, 5, 6, 7 and 11. In response to the requested information, EGC responded in References 3, 4, 8, 9, 10 and 12.
As part of Reference 12, EGC indicated in the response to SBPB RAI-1 0 that design calculations in accordance with 10 CFR Appendix B would be revised and completed for the equipment that is cooled by the Ultimate Heat Sink via the Essential Service Water System and that Section 3.5 of the UHS LAR (Reference 1) would be revised based on the results of the design calculations. Revised design calculations have been completed and the Attachment 1
February 12, 2016 U.S. Nuclear Regulatory Commission Page 3 response provides a revision to the affected sections of Section 3.5 of Reference 1. Sections 3.5.6.3, 3.5.8 and 3.5.10 remain as stated in Reference 1.
Additionally, during a teleconference that was held with NRC technical reviewers on February 3, 2016, the NRC staff requested clarification on the EGC response to SBPB RAI-7 that was provided in Reference 12. Clarification is provided in Attachment 1.
EGC has reviewed the information supporting a finding of no significant hazards consideration that was previously provided to the NRC in Attachment 1 of Reference 1. The information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration.
There are no regulatory commitments contained within this letter.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b), a copy of this letter and its attachment is being provided to the designated State of Illinois official.
Should you have any questions concerning this letter, please contact Ms. Jessica Krejcie at (630) 657-2816.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 16th day of February 2016.
Respectfully, David M. Gullott Manager - Licensing Exelon Generation Company, LLC : Supplemental Information cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Braidwood Station Illinois Emergency Management Agency Division of Nuclear Safety
Attachment 1 Supplemental Information
Attachment 1 Supplemental Information In Reference 1, Exelon Generation Company, LLC, (EGC) requested an amendment to the Technical Specifications (TS) of Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2. The proposed amendment would modify TS 3.7.9, "Ultimate Heat Sink (UHS)," by changing the maximum allowable temperature of the UHS from 100 OF to a maximum UHS temperature of 102°F.
The U. S. Nuclear Regulatory Commission (NRC) requested additional information related to its review of Reference 1 in References 2, 5, 6, 7 and 11. In response to the requested information, EGC responded in References 3, 4, 8, 9, 10 and 12.
As part of Reference 12, EGC indicated in the response to SBPB RAI-10 that design calculations in accordance with 10 CFR Appendix B would be revised and completed for the equipment that is cooled by the Ultimate Heat Sink via the Essential Service Water System and that Section 3.5 of the UHS LAR (Reference 1) would be revised based on the results of the design calculations. Revised design calculations have been completed and the below response provides a revision to the affected sections of Section 3.5 of Reference 1. Sections 3.5.6.3, 3.5.8 and 3.5.10 remain as stated in Reference 1.
Additionally, during a teleconference that was held with NRC technical reviewers on February 3, 2016, the NRC staff requested clarification on the EGC response to SBPB RAI-7 that was provided in Reference 12. Clarification is provided below.
Revised Reference 1 Section 3.5, "Evaluation of Equipment" Revised engineering calculations have been completed to review the impact of the increase in the UHS maximum temperature of 102°F and the increase in the maximum post-accident SX inlet temperature of 105.2°F. For conservatism, a temperature of 106°F was used for the maximum post-accident temperature.
The heat load on the UHS is determined based on one unit undergoing a LOCA with a LOOP and the other unit going through a normal shutdown from maximum power. Heat loads for the UHS DBA event are shown in UFSAR Table 9.2-1 and were evaluated for the components listed in sections 3.5.1 through 3.5.5 with the exception of the Positive Displacement (PD)
Charging Pump Cubicle Cooler since the PD Charging pumps are not operated at Braidwood Station. While SX flow to the PD Charging Pump Room Cubicle Cooler is not isolated, the heat load in the room is insignificant with the pump idle. Note, the heat load for the Spent Fuel Pit Heat Exchanger includes the Spent Fuel Pool background heat load due to Spent Fuel Assemblies that are stored in the pool.
Note, all equipment that is cooled by the SX system is within the scope of the Generic Letter (GL) 89-13, "Service Water System Problems Affecting Safety-Related Equipment" program.
The information below describes the revised engineering calculations that have been performed to ensure that required plant equipment can continue to perform their design function at the elevated UHS temperature.
3.5.1 Pump Room Cubicle Coolers Pump room cubicle coolers are required to remove equipment heat from rooms with operating pumps. Revised design calculation demonstrated that all cubicle coolers cooled by SX have adequate margin between the heat removed and the design heat load at design SX cooling flow rates:
Page 1 of 9
Auachment 1 Supplemental Information
- Essential Service Water (SX) Pump Cubicle Coolers
- Residual Heat Removal (RHR) Pump Cubicle Coolers
- Safety Injection (SI) Pump Cubicle Coolers
- Charging (CV) Pump Cubicle Coolers
- Spent Fuel Pit Pump Room Cubicle Coolers
- Diesel Driven Auxiliary Feedwater (AF) Pump Room Cubicle Coolers
- Containment Spray (CS) Pump Room Cubicle Coolers These margins were calculated under design conditions for a conservative maximum post-accident SX inlet temperature of 106°F which bounds the maximum calculated SX inlet temperature of 105.2°F. The calculations were performed to determine the maximum number of tubes plugged allowable with the increased UHS temperature. All coolers (with the exception of the CS Pump room cubicle coolers and spent fuel pit pump cubicle cooler) showed considerable margin (i.e., greater than 10% to the required heat load) while maximizing the analyzed number of tube plugged which provides margin in the tube plugging limits. All current actual tube plugging values are less than the calculated maximum number of tubes plugged allowable at the increased UHS temperature.
The CS Pump room cubicle coolers and spent fuel pit pump cubicle cooler calculations were performed in the same manner to maximize allowable tube plugging limits while maintaining margin. With no tubes plugged, the CS Pump room cubicle coolers have 7.2% margin and with 16 of 160 tubes plugged, there is approximately 1.5% margin to the required capacity. The current CS Pump room cubicle coolers have no more than 8 tubes plugged per cooler. The spent fuel pit pump room cubicle coolers calculation showed 7.9% margin with no tubes plugged and approximately 1.4% margin with 15 tubes plugged. There are currently a maximum of 8 tubes plugged in any cooler.
3.5.2 Oil Coolers The SX system provides cooling water to oil coolers for safety related pumps. The lube oil coolers for safety related pumps are small heat exchangers that are periodically cleaned and inspected in accordance with GL 89-13. The oil cooler margins were evaluated under design conditions for a conservative maximum post-accident SX inlet temperature of 106°F which bounds the maximum calculated SX inlet temperature of 105.2°F. Oil cooler calculations were performed to determine the maximum number of tubes plugged allowable with the increased UHS temperature. All coolers showed margin in heat load removal while maximizing the analyzed number of tube plugged, allowing for margin in the tube plugging limits. All current actual tube plugging values are less than the calculated maximum number of tubes plugged allowable with the increased UHS temperature. The oil coolers evaluated are:
- SX Pump Oil Coolers
- SI Pump Oil Coolers
- Diesel Driven AF Pump Gear Oil Cooler
- CV Centrifugal Pump Gear Oil Coolers
- Motor and Diesel Driven AF Pump Oil Coolers
- Diesel Driven AF Pump Right Angle Gear Lube Oil Cooler
- CV Centrifugal Pump Oil Coolers Page 2 of 9
Attachment 1 The SX system provides cooling water to diesel engine cooling systems. Revised design calculation demonstrated that all engine coolers cooled by SX have adequate margin between the heat removed and the design heat load at design values. The revised calculations utilized a post-accident SX inlet temperature of 106°F at design flow conditions to confirm that the maximum shell side temperature remains below the maximum temperature alarm setpoint. All engine coolers cooled by the SX system have been evaluated and demonstrate margin at the increased SX temperature. Evaluations of both the engine coolers identified below determined margin available to their respective high jacket water temperature alarm setpoints:
- Diesel Driven AF Pump Engine Closed Cycle Heat Exchanger
- Emergency Diesel Generator (EDG) Jacket Water Coolers For the Diesel Driven AF pump engine closed cycle heat exchanger, the UHS temperature increase was evaluated using the design SX cooling flow rate of 250 gpm and 1 tube plugged and demonstrated that the resultant shell inlet temperature was 194°F which is below the alarm setpoint of 195°F. There are currently 0 tubes plugged on Unit 1 and 1 tube plugged on Unit 2.
A case was analyzed using a SX cooling flow rate of 350 gpm and determined 27 tubes could be plugged to remain below the alarm setpoint of 195°F. Flow modeling and surveillance test results support use of a higher flow rate.
The EDG Jacket Water Coolers calculation was performed at the design SX cooling flow rate and assumed 54 tubes plugged. The resultant temperature was 189.5°F which remains below the alarm setpoint of 190°F. Currently, the most number of tubes plugged for any cooler on either unit is 30 tubes. Therefore, adequate margin exists to the allowable tubes plugged limit for the increased SX temperature. Additional detailed information on the evaluation of the diesel driven AF pump is contained in the response to SBPB RAI-12 in Reference 12.
3.5.4 Main Control Room Chiller Condenser The SX system provides cooling water to the Main Control Room (MCR) chiller condensers, which remove sensible and latent heat from the control room to ensure equipment operability and personnel occupancy. A revision to the design analysis calculation was performed to assess an increase in UHS temperature up to 106°F using design heat loads and design SX cooling flow rates and to determine limits on tube plugging values. The results show that the MCR chiller condenser is able to remove the required heat load with up to 24 tubes plugged for the Main Control Room Chiller evaporator and up to 84 total for the Main Control Room Chiller condenser. The current maximum tubes plugged for the main control room chiller evaporator is 11 tubes and 1 tube for the main control room condenser. Additional detailed information on the evaluation of the main control room chiller condenser is contained in the response to SBPB RAI-11 from Reference 12.
3.5.5 CC Heat Exchangers The CC system rejects heat to the UHS during normal plant operation and during accident conditions. Five different operating scenarios were evaluated to model the different plant configurations where the CC system is designed to operate (e.g., two units operating at power, one unit operating at power with the other unit shutdown, normal unit shutdown with other unit experiencing a LOCA, etc.). The CC heat exchangers were evaluated for increased normal operating UHS temperature of 102°F and increased post-DBA UHS temperature of 106°F using Page 3 of 9
Attachment 1 Supplemental Information existing tube plugging values. The design basis scenario for the UHS DBA results in a margin of 30% for the CC heat exchangers.
Of the five operating scenarios evaluated, normal operating scenarios are more limiting than the design basis scenario described above. Normal operating scenarios are the limiting configurations with respect to CC heat exchanger performance since the allowed maximum CC temperature for normal operations is 105°F which is lower than the allowed maximum CC temperature of 120°F for the normal shutdown unit and 128°F for the other unit during post-L OCA operations. The limiting CC heat exchanger scenario has the following margins:
Table 1: CC Heat Exchanger Mar ins CC HX Margin U-0 CC HX 43%
U-1 CC HX 7%
U-2 CC HX 84%
The margins are based on actual fouling factors from recent thermal performance testing.
Additional detailed information on the evaluation of the CC Heat Exchangers is contained in the EGC response to RAI-1 in Reference 3.
3.5.6 Net Positive Suction Head (NPSH) Evaluations The NPSH for all safety related pumps which take suction from the UHS has been evaluated and found to remain acceptable for the higher UHS temperature. Sections 3.5.6.1 through 3.5.6.3 describe the revision to the design analyses of NPSH.
3.5.6.1 SX Pump The analysis has been revised to incorporate a maximum SX temperature of 106 OF. The new NPSH Available (NPSHA) has been calculated to be 42 feet which has significant margin above the NPSH Required (NPSHR) value of 36 feet at 28,000 gpm per pump.
3.5.6.2 SX Booster Pumps The SX booster pumps provide flow to various coolers associated with the diesel driven AF pumps. Normally, suction for the pumps is supplied by the SX pumps with more than adequate NPSHA.
The SX booster pump analysis calculates a limiting NPSHA for a Station Blackout event initial configuration when the SX pumps are not running. The Braidwood Station licensing basis does not postulate a Station Blackout concurrent with a UHS Design Basis Event. Therefore, assuming a maximum SX inlet temperature of 102°F, a minimum margin of 10.3 feet was calculated based on an NPSHA of 28 feet with an NPSHR of 17.7 feet. When considering the increase in SX temperature for the recirculation case (refer to Section 3.5.7), the NPSH margin decreases by less than 2.5 feet (difference in water vapor pressure between the initial temperature of 102°F, 1.00789 psia, and the final temperature of 126 OF, 1.9959 psia) and remains acceptable.
Page 4 of 9
A.&&
Auachment 1 Pill 1~1 1 1 1 1~
The Braidwood AFW system is capable of supplying the required flow to the steam generators independent of any AC power source for a duration of two hours. This condition is more limiting than a SBO scenario because during a SBO one SX pump is available from the non-blackout Unit after the Unit SX supply cross-tie isolation valves are opened.
In the event of a complete loss of onsite AC electrical power; the Diesel Driven AF pump (i.e.,
the 'B'AF pump) is credited for steam generator inventory makeup. The Braidwood Station licensing basis does not postulate a simultaneous UHS DBA. Therefore, water temperature experienced by the 'B' AF pump and its associated diesel driven SX booster pump at the start of the event is limited to the proposed TS maximum temperature of 102°F.
During a Loss of All AC Power scenario, the SX booster pump operates to provide cooling water to the 'B'AF pump's heat exchangers and coolers. Flow recirculates through the different heat exchangers and coolers back to the SX booster pump suction, resulting in isolation of the cooling water heat sinks and heat-up of the isolated SX booster pump cooling loop during the Braidwood Station coping time of two hours. The final calculated SX temperature is 126°F. The analysis shows that the AF diesel engine is able to operate during the transient without exceeding its jacket water high temperature trip setpoint.
The NPSHA analysis for the recirculation mode during this scenario is discussed in section 3.5.6.2 above.
3.5.9 Spent Fuel Pool Cooling The spent fuel pool cooling heat exchanger is cooled by the CC system. Since the CC Heat Exchangers have been evaluated to be capable of removing the required heat load at the increased UHS temperature of 102°F during normal operation (see section 3.5.5), the spent fuel pool heat exchanger will continue to be able to perform its required design function. During a UHS DBA, the CC Heat Exchanger is also analyzed at 106°F and is capable of removing the required spent fuel pool heat exchanger heat load. Thus, the spent fuel pool cooling heat exchanger will remain capable of removing the required heat load ensuring the maximum pool bulk temperature is below the bounds of the design analysis.
3.5.11 Conclusions Revised analyses have been completed in accordance with Regulatory Commitment #1 of Reference 1. Revised analyses have confirmed that margins in the design analyses are present to address the increased SX temperature.
Clarification to EGC Response to SBPB RAII-7 from Reference 12 The heat load tables from calculation ATD-01 09 Attachment C(Attachment 5 of Reference 1) were recalculated using 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time intervals in response to SBPB RAI-7. The following table (Table 2) presents the equivalent of Table C1 from calculation ATD-01 09 Attachment C performed for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> intervals. These 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> average heat loads were converted to Plant Temperature Rise and displayed on Figure 2 of the previously submitted response (page 18 of 28 of Reference 12). The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Plant Temperature Rise is then used as an input to the LAKET-PC computer program. The results of the LAKET-PC case runs (for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Page 5 of 9
Attachment 1 Supplemental Information heat loads) are presented on Figures 3 and 4 of the previously submitted response (pages 19 and 21 of 28 Reference 12).
Table 2: Determination of 1 hr Average Heat Loads for First 24 Hours Total Heat Time Trapezoidal Sum of Average Load (hours) Rule Previous Heat Time to the UHS Integration Column Load (seconds) (Worst Case Over Over Time Over from ATD-Previous Interval Time 0063, page Time Step (Btu- Interval E9, Table 13 (Btu-sec/hr) sec/hr) (Btu/hr)
(Btu/Hq 0.00 0.0000E+00 0 0.00 1.0000E+01 8.30E+07 4.15E+08 0.01 2.0000E+01 8.30E+07 8.30E+08 0.01 2.1000E+01 5.85E+08 3.34E+08 0.01 3.3000E+01 5.75E+08 6.96E+09 0.01 5.0000E+01 5.68E+08 9.72E+09 0.03 1.0200E+02 5.54E+08 2.92E+10 0.04 1.3100 E+02 5.47E+08 1.60E+1 0 0.06 1.9900E+02 5.33E+08 3.67E+10 0.08 2.8900E+02 5.22E+08 4.75E+10 0.10 3.4900E+02 5.17E+08 3.12E+10 0.13 4.5900E+02 5.08E+08 5.64E+10 0.17 5.9900E+02 4.99E+08 7.05 E+ 10 0.19 6.9500E+02 4.94E+08 4.77E+10 0.19 6.9500E+02 7.87E+08 7.69E+05 0.25 8.9900E+02 7.93E+08 1.61 E+11 0.28 9.9900E+02 7.96E+08 7.95E+10 0.31 1.0990E+03 7.95E+08 7.96E+10 0.33 1.1990E+03 7.86E+08 7.91 E+10 0.36 1.2990E+03 7.77E+08 7.82E+10 0.39 1.3990E+03 7.68E+08 7.73 E+ 10 0.49 1.7640E+03 7.34E+08 2.74E+11 0.64 2.2990E+03 6.35E+08 3.66E+11 0.81 2.8990E+03 5.60E+08 3.59E+11 1.00 3.5990E+03 5.19E+08 3.78E+11 2.28E+12 6.35E+08 1.39 4.9990E+03 4.58E+08 6.84E+11 1.94 6.9990E+03 3.79E+08 8.37E+11 2.00 7.2000E+03 3.76E+08 7.59E+10 1.60E+12 4.44E+08 2.78 9.9990E+03 3.32E+08 9.91 E+11 3.00 1.0800E+04 3.27E+08 2.64E+11 1.25E+12 3.48E+08 4.00 1.4400E+04 3.03E+08 1.13E+12 1.13E+12 3.15E+08 5.00 1.8000E+04 2.80E+08 1.05E+1 1.05E+12 2.92E+08 5.56 1.9999E+04 2.67E+08 5.47E+11 6 2.1600E+04 2.67E+08 4.27E+11 9.74E+11 2.71 E+08 I
Attachment 1 Supplemental Information Total Heat Trapezoidal Sum of Average Load Rule Previous Heat Time to the UHS, Time Integration Column Load (seconds) (Worst Case (hours) Over Over Time Over from ATD-Previous Interval Time 0063, page Time Step (Btu- Interval E9, Table 13 )
(Btu-sec/hr) sec/hr) (Btu/hr)
(Btu/Hr) 7.00 2.5200E+04 2.67E+08 9.61 E+11 9.61 E+11 2.67E+08 8.00 2.8800E+04 2.67E+08 9.61 E+11 9.61 E+11 2.67E+08 8.33 2.9998E+04 2.67E+08 3.20E+11 8.33 2.9999E+04 5.51 E+08 4.09E+08 9 3.2400E+04 5.34E+08 1.30E+12 1.62E+12 4.51 E+08 10 3.6000E+04 5.08E+08 1.88E+12 1.88E+12 5.21 E+08 11 3.9600E+04 4.83E+08 1.78E+12 1.78E+12 4.96E+08 11.11 3.9999E+04 4.80E+08 1.92E+11 12 4.3200E+04 4.34E+08 1.46E+12 1.65E+12 4.60E+08 13 4.6800E+04 3.82E+08 1.47E+12 1.47E+12 4.08E+08 13.89 4.9999E+04 3.36E+08 1.15E+12 14.00 5.0400E+04 3.36E+08 1.35E+11 1.28E+12 3.57E+08 15 5.4000E+04 3.33E+08 1.20E+12 1.20E+12 3.34E+08 16 5.7600E+04 3.30E+08 1.19E+12 1.19E+12 3.31 E+08 16.67 5.9999E+04 3.28E+08 7.89E+11 17.00 6.1200E+04 3.27E+08 3.93E+11 1.18E+12 3.28E+08 18 6.4800E+04 3.24E+08 1.17E+12 1.17E+12 3.26E+08 19 6.8400E+04 3.21 E+08 1.16E+12 1.16E+12 3.23E+08 20 7.2000E+04 3.18E+08 1.15E+12 1.15E+12 3.20E+08 21 7.5600E+04 3.16E+08 1.14E+12 1.14E+12 3.17E+08 22 7.9200E+04 3.13E+08 1.13E+12 1.13E+12 3.14E+08 22.22 7.9999E+04 3.12E+08 2.50E+11 23.00 8.2800E+04 3.10E+08 8.71 E+11 1.12E+12 3.11 E+08 24 8.6400E+04 3.07E+08 1.11E+12 1.11E+12 3.08E+08 24-End of Transient 8.9999E+04 3.04E+08 1.10E+12 Page 7 of 9
Attachment 1
References:
- 1) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"' dated August 19, 2014 (ML14231A902)
- 2) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC) Preliminary RAls for LAR Regarding Braidwood Station Technical Specification, "Ultimate Heat Sink,"
dated February 5, 2015 (MI-1 5036A431)
- 3) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"' dated March 31, 2015 (ML151090A604)
- 4) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"' dated April 30, 2015 (ML15120A396)
- 5) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC) Additional RAI Regarding Containment Analysis for Braidwood UHS LAR (MF4671 and MF4672),
dated July 22, 2015
- 6) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC) Need Clarification Conference Call Regarding Your April 30, 2015 Response to SCVB-RAI-1 (a), dated August 12, 2015 (MI-1 522413548)
- 7) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC) Additional RAls Regarding Braidwood Ultimate Heat Sink Temperature Amendment, dated September 29, 2015
- 8) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, 'Ultimate Heat Sink,"' dated October 9, 2015
- 9) Letter D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9,
'Ultimate Heat Sink,"' dated October 30, 2015 10)Letter D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9,
'Ultimate Heat Sink,"' dated November 9, 2015 11)Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC) Preliminary Balance of Plant RAls for Braidwood Ultimate Heat Sink LAR, dated October 26, 2015
Attachment 1 Response to Request for Additional Information
- 12) Letter Glen T. Kaegi (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9,
'Ultimate Heat Sink,"' dated December 16, 2015 Page 9 of 9