Letter Sequence Response to RAI |
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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:Response to Request for Additional Information (RAI)
MONTHYEARRS-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-23-056, 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-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-21-015, 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-20-147, 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 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-18-094, 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-18-095, 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-18-097, 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 RS-17-085, Response to Request for Additional Information Regarding Amendments to Remove Obsolete License and Technical Specification Items2017-06-29029 June 2017 Response to Request for Additional Information Regarding Amendments to Remove Obsolete License and Technical Specification Items ML17178A0762017-06-26026 June 2017 Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 15; Supplemental Information Letter RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-16-213, Response to Request for Additional Information Regarding Relief Request 13R-17 to Extend the Reactor Pressure Vessel Inservice Inspection Interval2016-11-21021 November 2016 Response to Request for Additional Information Regarding Relief Request 13R-17 to Extend the Reactor Pressure Vessel Inservice Inspection Interval RS-16-231, Revised Response to Request for Additional Information for License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair2016-11-14014 November 2016 Revised Response to Request for Additional Information for License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair RS-16-222, Response to Request for Additional Information Related to License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair2016-10-28028 October 2016 Response to Request for Additional Information Related to License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair RS-16-218, Response to Request for Additional Information License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time to Support 2A SX Pump Repair2016-10-26026 October 2016 Response to Request for Additional Information License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time to Support 2A SX Pump Repair RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure RS-16-112, Response to Request for Additional Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink.2016-04-29029 April 2016 Response to Request for Additional Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink. RS-16-079, Response to Request for Additional Information Regarding the Request for Exemption from 10 CFR 50.55a, Codes and Standards, Paragraph (h)(2), Protection Systems, Including Change to Request NRC Approval Under 10 CFR 50.55a..2016-04-11011 April 2016 Response to Request for Additional Information Regarding the Request for Exemption from 10 CFR 50.55a, Codes and Standards, Paragraph (h)(2), Protection Systems, Including Change to Request NRC Approval Under 10 CFR 50.55a.. RS-16-078, Clarification to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-04-0404 April 2016 Clarification to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds 2023-04-20
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40() Wit it ('1(1 Romi Wir riivill, Awomw ExeLon G (/ ?OO() Off RS-1 5-266 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. 50-456 and 50-457
Subject:
Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units I 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 I 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 RAIs 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 I and 2, Technical Specification 3.7.9, "Ultimate Heat Sink," dated March 31, 2015 (ML15090A604)
- 4) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC)
Preliminary Containment and Ventilation Branch RAI5 for Braidwood UHS LAR, dated March 9, 2015 (ML15069A004)
- 5) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC)
Revised Preliminary RAIs for LAR Regarding Braidwood Station Technical Specification, "Ultimate Heat Sink," dated March 24, 2015 (MI-1 5084A01 8)
- 6) 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 I and 2, Technical Specification 3.7.9, "Ultimate Heat Sink," dated April 30, 2015 (ML15120A396)
October 9, 2015 U.S. Nuclear Regulatory Commission Page 2
- 7) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC)
Additional RAI Regarding Containment Analysis for Braidwood UHS LAR (MF4671 and M174672), dated July 22, 2015
- 8) 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 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 I 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. In Reference 2, the U. S. Nuclear Regulatory Commission (NRC) requested additional information related to its review of Reference 1. In Reference 3, EGC provided the requested information. In Reference 4, the NRC provided additional preliminary RAIs from the Containment and Ventilation Branch. In Reference 5, the NRC clarified the questions provided in Reference 4 and indicated that certain questions originally transmitted in Reference 4 had been eliminated and no longer required a response (i.e., RAIs 2, 3 and 4). Reference 6 provided a response to the Reference 4 and Reference 5 RAI5.
Reference 7 and Reference 8 requested additional information related to the Reference I submittal and Reference 6 follow-up response. Attachment I provides the response to the Reference 7 and Reference 8 requested information.
EGC has reviewed the information supporting a finding of no significant hazards consideration that was previously provided to the NRC in Attachment I 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.
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.
October 9, 2015 U.S. Nuclear Regulatory Commission Page 3 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:
Response to Request for Additional Information cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector, Braidwood Station Illinois Emergency Management Agency Division of Nuclear Safety
Response to Request for Additional Information ATTACHMENT Response to Request for Additional 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 I 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 °F to a maximum UHS temperature of 102°F. In Reference 2, the U. S. Nuclear Regulatory Commission (NRC) requested additional information related to its review of Reference 1. In Reference 3, EGC provided the requested information. In Reference 4, the NRC provided additional preliminary RAIs from the Containment and Ventilation Branch. In Reference 5, the NRC clarified the questions provided in Reference 4 and indicated that certain questions originally transmitted in Reference 4 had been eliminated and no longer required a response (i.e., RAls 2, 3 and 4). Reference 6 provided a response to the Reference 4 and Reference 5 RAIs.
Reference 7 and Reference 8 requested additional information related to the Reference I submittal and Reference 6 follow-up response. This attachment provides the response to the Reference 7 and Reference 8 requested information.
SCVB-RAI-1I SCVB-RAI-1 I The NRC staff is aware of Westinghouse's InfoGram lG-14-1, dated November 5, 2014, which states that the loss-of-coolant accident (LOCA) containment mass and energy (M&E) release analysis methodology was found to use the reactor coolant system (RCS) stainless steel volumetric heat capacity value lower than the ASME values. The staff has received information which indicates that the impact on the LOCA peak containment pressure in the current licensing basis would be significant if the analysis would use ASME values for the RCS metal volumetric heat capacity. Provide an update to your application dated August 19, 2014 (ADAMS Accession Number ML14231A902), that contains the results of the containment pressure, containment temperature, sump temperature responses and net positive suction head (NPSH) analysis using the ASME published volumetric heat capacity for the RCS metal. In your supplement dated April 30, 2015 (ADAMS Accession No. ML15128A186) you stated that, "All issues related to the subject Nuclear Safety Advisory Letters (NSALs) (NSAL-06-6, NSAL-1 1-5, and NSAL-14-2) were explicitly addressed (and subsequent corrections in the loss-of-coolant (LOCA) mass and energy (M&E) release analysis were made) in support of the Ultimate Heat Sink (UHS) analysis." Confirm, in your update, that these NSALs continue to be addressed in the requested updated analysis.
SCVB-RAI-I I Response:
Exelon has reviewed the above RAI and will be providing a response in a future transmittal.
SCVB-RAI-I 2:
Exelon letter dated April 30, 2015, response to SCVB-RAI-1 (a), third paragraph states:
"Braidwood Unit I specific analysis of this event models the hydraulics of the affected systems using RELAP5 up to the point of void collapse and determines the resulting flow and pressures, Page 1 of 5
ATTACHMENT Response to Request for Additional Information and then calculates water hammer forces using either the EPRI methodology or a method of characteristics-based program, such as HYTRAN."
Provide a description of the EPRI methodology and the program HYTRAN that was used for the analysis and, if possible, a reference to NRC approval of the methodology.
SCVB-RAI-12 ResDonse:
As discussed in Reference 6, the Braidwood Station Unit I and Unit 2 analysis utilized EPRI methodology and the program HYTRAN to calculate water hammer forces for evaluations performed in support of Generic Letter (GL) 96-06. The Braidwood Station application of EPRI methodology was described in various submittals, as outlined in "Byron Station, Units I and 2, and Braidwood Station, Units I and 2, Generic Letter 96-06, 'Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions," dated February 24, 2004 (Reference 9). As documented in Reference 9, the NRC reviewed the various Braidwood Station submittals and indicated satisfactory resolution of GL 96-06 requested actions, including water hammer and two-phase flow conditions and thermally-induced overpresurrization. The Reference 9 letter includes reference to the NRC approval of EPRI methodology (ML020940132).
The GL 96-06 calculations were revised for Braidwood Station in support of the Measurement Uncertainties Recapture (MUR) project. In the revised analyses, RELAP continues to be used to determine the locations where the vapor voids would collapse, along with the corresponding fluid velocities of the two water slugs. As described in Reference 6, the Braidwood methodology includes calculating water hammer loads using either the EPRI methodology or a Method of Characteristics (MOC) based program, HYTRAN. The EPRI methodology has limitation of applicability based on voids closure velocity. The RELAP results for Braidwood show closure velocities above the EPRI applicability criteria, therefore, HYTRAN was used to calculate the forces from the void collapses.
HYTRAN is a PC based program that implements MOC to perform the waterhammer analysis.
It computes time-dependent forces on, and pressures and flow velocities in, the legs of a liquid filled piping system. Output gives pressures and flow velocities at the end nodes of each leg, and the internal nodes if desired, and also gives the unbalanced force on the leg.
The HYTRAN model is used to match pre-collapse steady state flows in the RELAP analysis, match flows just prior to the steam bubble collapse, collapse the steam bubble in the predicted time, and return to steady state flow after collapse. Loads from the collapsing voids are determined along each piping leg. The HYTRAN results are then post-processed to generate time-history files containing flow velocities, pressures and leg forces. The flows before and after the void collapse were matched to the RELAP flows for the HYTRAN results to be valid.
Furthermore, the HYTRAN results were ensured to be conservative by verifying that the rate of change of the velocity (i.e., slope of the velocity trace) in the HYTRAN analysis is greater than or equal to the rate of change of the velocity in the RELAP analysis.
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ATTACHMENT Response to Request for Additional Information The HYTRAN computer program is part of the original licensing basis for Braidwood Station and is described in UFSAR, Appendix D, Section D.8.6 and referenced in UFSAR section 3.9.1.2, "Computer Programs Used in Analyses":
HYTRAN (Hydraulic Transient Analysis) calculates pressures, velocities and force transients in a liquid filled piping network due to transients that are initiated by valve closure, pump trip, or by pressure changes at a piping terminal. HYTRAN was validated by comparison of sample problem results to results given in published documents.
The use of HYTRAN for this application has been validated by other utilities in support of GL 96-06 related analyses. A submittal (Reference 10) for Palisades Nuclear Power Plant compared HYTRAN results to results from the EPRI Rigid Body method (RBM). The report concluded that the RBM and HYTRAN/MOC loads correlate well, and the HYTRAN/MOC loads are almost always higher than the RBM method loads. The conservatism with using the HYTRAN program when compared to the EPRI RBM method was acknowledged by the NRC in the SER for the Palisade Plant GL 96-06 submittals (Reference 11).
SCVB-RAI-1 3 Exelon letter dated April 30, 2015, response to SCVB-RAI-1(a), last paragraph states:
"The RCFC Unit 2 piping analyses are based on the Unit I RCFC piping analytical models, with unit specific differences reconciled during original construction. Unit specific RCFC piping differences that are applicable to the 96-06 analysis will be reconciled as part of Regulatory Commitment #1 of Reference 1, prior to the implementation of the UHS LAR."
Explain what is implied by reconciliation of unit specific differences (if possible, provide a reference of NRC approval during initial licensing) and how the analysis for Braidwood Unit 2 will be performed using the analysis for Unit I SCVB-RAI-1 3 Resronse:
As described in Reference 6, for Braidwood Unit 2, the original analyses for the piping subsystems that are evaluated for Generic Letter (GL) 96-06 are based on the analyses of the corresponding Unit I piping subsystems.
During original design and construction, the Braidwood Unit 2 analyses documented the review of the as-built piping configurations (piping geometry and support configuration) with respect to the Braidwood Unit I analyzed configuration. Variances were evaluated and reconciled. The analyses document that all piping stresses for the reconciled Braidwood Unit 2 geometry are within code allowable. The results of the Braidwood Unit 2 piping subsystem analyses confirmed compliance with applicable Codes and were reviewed as part of the original Unit 2 licensing. Use of the piping analytical models of the lead Unit (i.e., Unit 1) to the design of the replicate unit (i.e., Unit 2) is common industry practice.
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ATTACHMENT Response to Request for Additional Information The GL 96-06 RELAP model includes the entire flow path from the Ultimate Heat Sink through the Reactor Containment Fan Coolers (RCFCs) and back to the UHS. A simplified model of the flow paths parallel to the RCFCs is included in the analysis. The parallel flowpaths are not modeled in detail as void formation occurs outside these parallel flow paths. Based on similarities between Unit I and Unit 2 Essential Service Water (SX) piping configurations (as documented in the reviews of the as-built piping subsystems), the results of the RELAP model using the Braidwood Unit I configuration are considered representative for both Braidwood Units.
The forces on the piping that were calculated with HYTRAN were reviewed against the structural capacity of the pipe supports. The support loads and configuration were obtained from the stress analyses for the affected Braidwood Unit I piping subsystems. The regulatory commitment is to validate that the structural capacity of the Unit 2 pipe support configuration is equivalent to the capacity of the Unit I pipe support configuration. This commitment will support the conclusion that the Unit 2 pipe supports can accommodate forces developed from void collapses.
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ATTACHMENT Response to Request for Additional Information
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 I 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 I and 2, Technical Specification 3.7.9, "Ultimate Heat Sink," dated March 31, 2015 (MLI 5090A604)
- 4) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC) Preliminary Containment and Ventilation Branch RAls for Braidwood UHS LAR, dated March 9, 2015 (MLI 5069A004)
- 5) Email from J. Wiebe (NRC) to J. Krejcie (Exelon Generation Company, LLC) Revised Preliminary RAls for LAR Regarding Braidwood Station Technical Specification, "Ultimate Heat Sink," dated March 24, 2015 (ML15084A018)
- 6) 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 I and 2, Technical Specification 3.7.9, "Ultimate Heat Sink," dated April 30, 2015 (ML15120A396)
- 7) 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
- 8) 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
- 9) Letter from Mahesh Chawla (U.S. NRC Office of Nuclear Reactor Regulation) to Mr.
Christopher M. Crane, (Exelon Generation Company, LLC), "Byron Station, Units I and 2, and Braidwood Station, Units I and 2, Generic Letter 96-06, 'Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions' (TAC NOS. M96789, M96790, M96782, AND M96783)," dated February 24, 2004 (ML040220400).
10)Letter from Daniel J Malone (Nuclear Management Company, LLC) to U.S. Nuclear Regulatory Commission, "Resolution of Generic Letter (GL) 96-06 Watterhammer Issues revised Response Requested Actions to Address GL-96-06," dated August 18, 2004 (ML042370019) 11)Letter from David H. Jaffe (U.S. NRC Office of Nuclear Reactor Regulation) to Mr. Daniel J. Malone (Nuclear Management Company), "Palisades Plant Generic Letter 96-06 Regarding Piping Thermal Overpressurization, Waterhammer, and Two-Phase Flow Issue (TaG No. M96844), dated January 11, 2005 (ML040560007)
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