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MONTHYEARRS-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. Project stage: Request 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 Project stage: Response to RAI ML23150A1432022-12-0808 December 2022 Form 2.3-1 Exam Outline Quality Checklist Project stage: Request ML22305A6992022-12-28028 December 2022 Issuance of Amendment Nos. 231 and 231 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 Project stage: Approval ML23191A0592023-07-21021 July 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 Project stage: Approval ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 Project stage: Approval ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 Project stage: Approval 2022-08-10
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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-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-118, 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-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-118, Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-10-31031 October 2022 Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0606 June 2022 Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022 Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube. RS-22-057, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-017, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions for Calvert Cliffs2022-04-20020 April 2022 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions for Calvert Cliffs 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-22-050, 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-22-047, 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-22-049, 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-22-027, 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-22-023, 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 2024-01-11
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information 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 ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23241A8432023-08-29029 August 2023 Enclosure 3 - Response to Request for Additional Information - Non-Proprietary Version ML23166A1052023-06-15015 June 2023 Response to Request for Additional Information Related to the License Amendment Request to Modify the Long-Term Coupon Surveillance Program ML23155A0012023-06-0404 June 2023 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request - One-Time Extension of the Control Room Emergency Ventilation System (C BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0606 June 2022 Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . ML22118B1432022-04-28028 April 2022 Supplemental Information No. 2 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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 ML21334A3422021-11-30030 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request 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 ML21320A0542021-11-15015 November 2021 R. E. Ginna Nuclear Power Plant - Response to Request for Additional Information - Request for Exemption from the Biennial Emergency Preparedness Exercise Requirements in 10 CFR 50, Appendix E, Section IV.F.2.c ML21308A5072021-11-0404 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request ML21298A0432021-10-25025 October 2021 Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request 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 ML21208A0072021-07-26026 July 2021 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-567 Rev 1, Add Containment Sump TS to Address GSI-191 Issues 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 ML21078A0022021-03-19019 March 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of R. E. Ginna Nuclear Power Plant, License Amendment Request to Modify the Steam Generator Tube Inspection Frequency RS-21-024, Response to Request for Additional Information (RAI) Regarding Byron Station, Units 1 and 2, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2021-03-16016 March 2021 Response to Request for Additional Information (RAI) Regarding Byron Station, Units 1 and 2, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-21-029, Response to RAI Re License Amendment Request - Proposed Changes to Byron & Dresden Stations Emergency Plan for Post-Shutdown and Permanently Defueled Condition2021-03-15015 March 2021 Response to RAI Re License Amendment Request - Proposed Changes to Byron & Dresden Stations Emergency Plan for Post-Shutdown and Permanently Defueled Condition RS-21-015, Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-182021-02-10010 February 2021 Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-18 RS-21-019, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections2021-02-0909 February 2021 Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections RS-20-017, Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-8852021-02-0101 February 2021 Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-885 RS-20-150, Response to Request for Additional Information Related to Subsequent Exemption from Part 26 Requirements2020-12-0101 December 2020 Response to Request for Additional Information Related to Subsequent Exemption from Part 26 Requirements RS-20-147, Response to Request for Additional Information Related to Exemption from Part 26 Requirements2020-11-23023 November 2020 Response to Request for Additional Information Related to Exemption from Part 26 Requirements RS-20-143, Response to Request for Additional Information Regarding Application to Revise Technical Specifications 3.8.1, AC Sources- Operating2020-11-20020 November 2020 Response to Request for Additional Information Regarding Application to Revise Technical Specifications 3.8.1, AC Sources- Operating ML20317A1122020-11-12012 November 2020 Final Response and Close-out to Generic Letter 2004-02 ML20280A5132020-10-0606 October 2020 Response to Request for Additional Information - End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval ML20248H3882020-09-0404 September 2020 Response to Request for Additional Information - License Amendment Request for Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System. RS-20-100, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections2020-08-19019 August 2020 Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20182A1102020-06-30030 June 2020 Response to Request for Additional Information to License Amendment Request - Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements Voltage ML20107F7652020-04-16016 April 2020 Response to Request for Additional Information to License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program 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 ML20080N8892020-03-20020 March 2020 R. E. Ginna Nuclear Power Plant, Supplemental Information Associated with the License Amendment Request to Add a One-Time Note for Use of Alternate Residual Heat Removal Methods 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 ML19282B7182019-10-0909 October 2019 Revised Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 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. ML19277D1032019-10-0303 October 2019 Response to Request for Additional Information Revised - Final Response to Generic Letter 2004-02 2023-08-29
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4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-22-123 10 CFR 50.90 December 7, 2022 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244
Subject:
Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, "Revised Frequencies for Steam Generator Tube Inspections"
References:
- 1. Letter from K. Lueshen (Constellation Energy Generation, LLC) to U.S. Nuclear Regulatory Commission, "Application to Revise Technical Specifications to Adopt TSTF-577, 'Revised Frequencies for Steam Generator Tube Inspections'," dated August 10, 2022 (ADAMS Accession No. ML22222A068)
- 2. Email from J. Wiebe (U.S. Nuclear Regulatory Commission) to L. Simpson (Constellation Energy Generation), "Draft RAI for Adoption of TSTF-577,"
dated November 4, 2022 In Reference 1, Constellation Energy Generation, LLC (CEG) requested amendments to Renewed Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2 (Braidwood); Renewed Facility Operating License Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron); Renewed Facility Operating License Nos. DPR-53 and DPR-69 for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs); and Renewed Facility Operating License No. DPR-18 for R.E. Ginna Nuclear Power Plant (Ginna).
December 7, 2022 U.S. Nuclear Regulatory Commission Page 2 The proposed changes would revise the "Steam Generator (SG) Program" and the "Steam Generator Tube Inspection Report" Technical Specifications (TS) based on Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, "Revised Frequencies for Steam Generator Tube Inspections" (TSTF-577) (ML21060B434), and the associated NRC safety evaluation (SE) (ML21098A188).
In Reference 2, the U.S. Nuclear Regulatory Commission (NRC) requested additional information that is needed to complete review of the proposed changes specific to Braidwood, Calvert Cliffs, and Ginna. Attachment 1 provides the additional information. The request for additional information is not applicable to Byron; however, Attachment 1 provides an administrative clarification regarding dates provided for Byron in Section 2.1 of Reference 1.
CEG has reviewed the information supporting the finding of no significant hazards consideration, and the environmental consideration that were previously provided to the NRC in Reference 1.
The additional 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 addition, the information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
There are no regulatory commitments included in this letter.
CEG is notifying the State of Illinois, the State of Maryland, and State of New York of this supplement to a previous application for a change to the operating license by sending a copy of this letter and its attachments to the designated Illinois, Maryland, and New York Officials in accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b).
If you should have any questions regarding this letter, please contact Ms. Lisa Simpson at (630) 657-2815.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 7th day of December 2022.
Respectfully, Lueshen, Digitally signed by Lueshen, Kevin Kevin Date: 2022.12.07 15:09:45
-06'00' Kevin Lueshen Sr. Manager - Licensing Constellation Energy Generation, LLC
Attachment:
Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, "Revised Frequencies for Steam Generator Tube Inspections"
December 7, 2022 U.S. Nuclear Regulatory Commission Page 3 cc: NRC Project Manager - NRR - Braidwood / Byron NRC Project Manager - NRR - Calvert Cliffs NRC Project Manager - NRR - Ginna NRC Regional Administrator, Region I NRC Regional Administrator, Region III NRC Senior Resident Inspector, Braidwood Station NRC Senior Resident Inspector, Byron Station NRC Senior Resident Inspector, Calvert Cliffs NRC Senior Resident Inspector, Ginna Illinois Emergency Management Agency - Division of Nuclear Safety A. L. Peterson, NYSERDA S. Seaman, State of Maryland
ATTACHMENT 1 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, "Revised Frequencies for Steam Generator Tube Inspections" In letter dated August 10, 2022 (Reference 1), Constellation Energy Generation, LLC (CEG) requested amendments to Renewed Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2 (Braidwood); Renewed Facility Operating License Nos.
NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron); Renewed Facility Operating License Nos. DPR-53 and DPR-69 for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs); and Renewed Facility Operating License No. DPR-18 for R.E. Ginna Nuclear Power Plant (Ginna).
By email dated November 4, 2022 (Reference 2), the U.S. Nuclear Regulatory Commission (NRC) requested additional information to complete review of the proposed changes. This Attachment provides the additional information.
NRC REQUEST FOR ADDITIONAL INFORMATION Introduction By license amendment request (application) dated August 10, 2022 (Agencywide Documents Access and Management System Accession No. ML22222A068), Constellation Energy Generation, LLC (the licensee) requested changes to the technical specifications (TS) for Braidwood Station, Units 1 and 2 (Braidwood); Byron Station Units 1 and 2 (Byron); Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs); and R.E. Ginna Nuclear Power Plant (Ginna). Note that this request for additional information is not applicable to Byron. The licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the "Steam Generator (SG) Program" and the "Steam Generator Tube Inspection Report" TS based on Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, "Revised Frequencies for Steam Generator Tube Inspections" (TSTF-577) (ML21060B434), and the associated NRC staff safety evaluation (SE)
(ML21098A188).
The tubes within a steam generator (SG) function as an integral part of the reactor coolant pressure boundary and, in addition, isolate fission products in the primary coolant from the secondary coolant and the environment. SG tube integrity means that the tubes are capable of performing this safety function in accordance with the plant design and licensing basis.
The NRC staff has determined that additional information is needed to complete its review, as described below.
Regulatory Basis The regulation in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36(c)(5),
"Administrative Controls," states in part, that "Administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner." All pressurized water reactors have TS according to 10 CFR 50.36 that include a SG Program with specific criteria for the structural and leakage integrity, repair, and inspection of SG tubes. At Constellation, programs 1 of 5
ATTACHMENT 1 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, "Revised Frequencies for Steam Generator Tube Inspections" established by the licensee, including the SG Program, are listed in the administrative controls section of the TS to operate the facility in a safe manner.
Request for Additional Information To complete its evaluation of whether the proposed changes meet the SG Program requirements described above, the NRC staff requests the following information.
Traveler TSTF-577 in part, revises the standard technical specifications related to SG tube inspections to extend the inspection interval for thermally treated Alloy 600 (Alloy 600TT) and thermally treated Alloy 690 (Alloy 690TT) SG tubing. By letter dated August 10, 2022 (ML22222A068), the licensee applied to adopt TSTF-577 for Braidwood, Byron, Calvert Cliffs, and Ginna. According to TSTF-577, the new SG TS inspection period would start after a 100 percent inspection of all SG tubes performed during a single outage. In the application to adopt TSTF-577, Braidwood, Calvert Cliffs, and Ginna provided SG TS markups that reflect the new SG TS tube inspection provisions however, these units have not yet completed, or do not credit completion of, the required inspection. As described in the application, these units plan to complete the required inspection in future outages, after the adoption of TSTF-577. To address this situation (i.e., adopting TSTF-577 prior to completing the required inspection) the licensee proposed a license condition. The license condition would restrict the use of the extended inspection interval until after completion of the 100% inspection of all tubes in a single outage.
In general, the proposed license condition for each applicable unit states, "[t]he extended inspection interval of TS 5.5.9 will not be permitted following implementation of the TSTF-577 amendment until after performance of a 100% inspection of all tubes in a single outage." Based on the preceding information, the NRC staff requests additional information to better understand the proposed approach.
- 1. The application described plans to complete the required inspection in future outages, after the adoption of TSTF-577. Upon implementing the amendment, which allows an extended inspection interval, each applicable units proposed license condition specifies that the extended inspection interval of TS 5.5.9 (typical) will not be permitted until after performance of the required inspection (emphasis added). However, it does not state the inspection requirements that will be in effect and how they are controlled before performance of the required inspection (emphasis added). Based on the approach described in the application and summarized above, the NRC staff requests that the licensee describe what inspection requirements and interval will be in effect and how they are controlled prior to the performance of a 100% inspection of all SG tubes in a single outage and implementation of TSTF-577. As part of the response, explain how the proposed approach supports the TS administrative controls necessary to assure operation of the facility in a safe manner.
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ATTACHMENT 1 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, "Revised Frequencies for Steam Generator Tube Inspections" CEG Response to RAI The CEG application dated August 10, 2022 (Agencywide Documents Access and Management System Accession No. ML22222A068) (Reference 1) described plans to complete the required inspection in future outages, after the adoption of TSTF-577. However, as discussed during the NRC clarification call on November 9, 2022, CEG now intends to credit a 100% SG tube inspection performed during a single refueling outage for each unit prior to approval of the amendments; consequently, no change to inspection requirements and/or intervals is required to be in effect prior to the performance of a 100% inspection of all SG tubes in a single outage and implementation of TSTF-577. Furthermore, there will be no need for additional or different TS administrative controls to assure operation of the facilities in a safe manner. Once the amendments for Braidwood, Units 1 and 2, Calvert Cliffs, Units 1 and 2, and Ginna are approved, the TS will be implemented within 120 days.
As some of the outages to complete the 100% SG tube inspections have not yet transpired, CEG intends to submit a supplement following the completion of the inspections described in the SG Program for the Braidwood Unit 2 spring refueling outage (A2R23) and the Ginna spring refueling outage (G1R44) planned for submittal in May 2023. The May 2023 supplement will also eliminate the proposed license conditions from Reference 1 for Braidwood, Calvert Cliffs, and Ginna as they will no longer be applicable.
The specific details for each applicable unit of Reference 1 are provided below.
Braidwood, Unit 1:
The initial inspection period described in the SG Program, paragraph d.2, began October 18, 2022, for Braidwood, Unit 1. CEG will submit a SG Tube Inspection Report meeting the revised TS 5.6.9 requirements within 60 days after implementation of the license amendment.
Braidwood, Unit 2:
The initial inspection period described in the SG Program, paragraph d.3, is scheduled to begin in spring 2023 for Braidwood, Unit 2. The May 2023 supplement will provide the date of the 100% SG tube inspection performed during the A2R23 spring 2023 refueling outage (i.e., date of entering MODE 4 at the end of the refueling outage). CEG will submit a SG Tube Inspection Report meeting the revised TS 5.6.9 requirements within 60 days after implementation of the license amendment.
Calvert Cliffs, Unit 1*:
The initial inspection period described in the SG Program, paragraph d.2, began March 9, 2020, for Calvert Cliffs, Unit 1. CEG will submit a SG Tube Inspection Report meeting the revised TS 5.6.9 requirements within 60 days after implementation of the license amendment.
Calvert Cliffs, Unit 2*:
The initial inspection period described in the SG Program, paragraph d.2, began March 14, 2019, for Calvert Cliffs, Unit 2. CEG will submit a SG Tube Inspection Report meeting the revised TS 5.6.9 requirements within 60 days after implementation of the license amendment.
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ATTACHMENT 1 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, "Revised Frequencies for Steam Generator Tube Inspections"
- Note: For Calvert Cliffs, Units 1 and 2, the dates provided in Reference 1 credited future outages in 2026 and 2025, respectively. In this letter, Calvert Cliffs, Units 1 and 2, credit a 100% SG tube inspection performed during a single refueling outage for each unit prior to approval of the amendments.
Ginna:
The initial inspection period described in the SG Program, paragraph d.2, is scheduled to begin in spring 2023 for Ginna. The May 2023 supplement will provide the date of the 100% SG tube inspection performed during the G1R44 spring 2023 refueling outage (i.e., date of entering MODE 4 at the end of the refueling outage). CEG will submit a SG Tube Inspection Report meeting the revised TS 5.6.7 requirements within 60 days after implementation of the license amendment.
Variation As discussed during the NRC clarification call on November 9, 2022, one additional Variation is added to the Variations from Reference 1:
Reference 1 included a time period for when CEG would submit a SG Tube Inspection Report meeting the revised TS requirements (i.e., within 30 days after implementation of the license amendment). This time period, based on the TSTF-577 Model Application, will be extended such that CEG will submit SG Tube Inspection Reports meeting the revised Braidwood TS 5.6.9, Calvert Cliffs TS 5.6.9, and Ginna TS 5.6.7 requirements within 60 days after implementation of the license amendments. This extension from 30 to 60 days is to allow for a staggered implementation for these CEG units. This difference from the TSTF-577 Model Application is administrative and does not affect the applicability of TSTF-577 to the Braidwood, Calvert Cliffs, and Ginna TS.
Administrative Clarification - Byron Dates As part of the review of information provided in CEG application dated August 10, 2022 (Reference 1), it was identified that the dates provided of the 100% SG tube inspections performed during Byron, Units 1 and 2, prior to approval of the amendments were inaccurate.
Based on a consistent CEG fleet approach of using the date for entry into MODE 4 at the end of the refueling outage, the dates are corrected and are applicable for Byron, Units 1 and 2, in the following paragraph from Section 2.1 of Reference 1:
Byron, Units 1 and 2:
The initial inspection period described in the SG Program, paragraph d.2, began March 24, 2020, for Byron, Unit 1, and the initial inspection period described in the SG Program, paragraph d.3, began May 10, 2022, for Byron Unit 2. CEG will submit a SG Tube Inspection Report meeting the revised TS 5.6.9 requirements within 30 days after implementation of the license amendment at Byron.
Note: As the request for additional information (Reference 2) is not applicable to Byron, the additional Variation included above will not apply to Byron, Units 1 and 2 (i.e., CEG will submit a SG Tube Inspection Report meeting the revised TS 5.6.9 requirements within 30 days after implementation of the license amendment at Byron, as stated in Reference 1).
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ATTACHMENT 1 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, "Revised Frequencies for Steam Generator Tube Inspections" REFERENCES
- 1. Letter from K. Lueshen (Constellation Energy Generation, LLC) to U.S. Nuclear Regulatory Commission, "Application to Revise Technical Specifications to Adopt TSTF-577, 'Revised Frequencies for Steam Generator Tube Inspections'," dated August 10, 2022 (ADAMS Accession No. ML22222A068)
- 2. Email from J. Wiebe (U.S. Nuclear Regulatory Commission) to L. Simpson (Constellation Energy Generation), "Draft RAI for Adoption of TSTF-577," dated November 4, 2022 5 of 5