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Category:Letter type:RS
MONTHYEARRS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, 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-22-037, 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-22-057, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision 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 2024-06-04
[Table view] Category:License-Application for (Amend/Renewal/New) for DKT 30
MONTHYEARRS-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-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-19-022, License Amendment Request - Clarifying Changes for Certain Emergency Action Levels Based on Emergency Preparedness Program Frequently Asked Questions (Epfaqs)2019-03-0101 March 2019 License Amendment Request - Clarifying Changes for Certain Emergency Action Levels Based on Emergency Preparedness Program Frequently Asked Questions (Epfaqs) RS-16-197, License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair2016-09-30030 September 2016 License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair ML13161A2232013-06-0303 June 2013 Byron and Braidwood, Units 1 and 2 - License Renewal Application ML1206604942012-03-30030 March 2012 Issuance of Amendments Revision of Technical Specifications (TS) 3.3.1, Reactor Trip System Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation (TAC ME5836... RS-08-036, License Amendment Request to Revise Containment Tendon Surveillance Program2008-04-0909 April 2008 License Amendment Request to Revise Containment Tendon Surveillance Program RS-02-045, Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles2002-04-19019 April 2002 Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles ML0208801152002-03-19019 March 2002 Request for a License Amendment to Modify the Method of Controlling Unfavorable Exposure Time Related to an Anticipated Transient Without Scram Event for Byron and Braidwood Station 2022-03-24
[Table view] Category:40
MONTHYEARRS-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-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-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-032, Amended Decommissioning Trust Agreements2021-02-25025 February 2021 Amended Decommissioning Trust Agreements RS-21-030, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-02-24024 February 2021 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 RS-19-045, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2019-04-0101 April 2019 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-19-022, License Amendment Request - Clarifying Changes for Certain Emergency Action Levels Based on Emergency Preparedness Program Frequently Asked Questions (Epfaqs)2019-03-0101 March 2019 License Amendment Request - Clarifying Changes for Certain Emergency Action Levels Based on Emergency Preparedness Program Frequently Asked Questions (Epfaqs) RS-16-197, License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair2016-09-30030 September 2016 License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair RS-16-040, Report on Status of Decommissioning Funding2016-02-0404 February 2016 Report on Status of Decommissioning Funding ML16008A1172016-01-20020 January 2016 U.S. Nuclear Regulatory Commission Analysis of Excelon Generation'S Decommissioning Funding Status Report RS-15-094, (EGC) - Submittal of Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2015-03-31031 March 2015 (EGC) - Submittal of Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-15-077, Submittal of Updated Site Specific Safstor Decommissioning Cost Estimates for Braidwood, Byron and LaSalle Stations2015-02-19019 February 2015 Submittal of Updated Site Specific Safstor Decommissioning Cost Estimates for Braidwood, Byron and LaSalle Stations ML13161A2232013-06-0303 June 2013 Byron and Braidwood, Units 1 and 2 - License Renewal Application RS-13-106, (EGC) Amended 2011 Report on Status of Decommissioning Funding for Reactors and Correction to July 27, 2011 RAI Response2013-04-12012 April 2013 (EGC) Amended 2011 Report on Status of Decommissioning Funding for Reactors and Correction to July 27, 2011 RAI Response RS-13-100, Report on Status of Decommissioning Funding for Reactors2013-04-0101 April 2013 Report on Status of Decommissioning Funding for Reactors ML1206604942012-03-30030 March 2012 Issuance of Amendments Revision of Technical Specifications (TS) 3.3.1, Reactor Trip System Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation (TAC ME5836... ML1001202412010-01-11011 January 2010 Submittal of Braidwood Station Site-Specific Safstor Decommissioning Cost Estimate RS-09-157, Submittal of Site-Specific Safstor Decommissioning Cost Estimate2009-11-16016 November 2009 Submittal of Site-Specific Safstor Decommissioning Cost Estimate RS-09-095, Decommissioning Funding Assurance Plan2009-07-29029 July 2009 Decommissioning Funding Assurance Plan ML0921201652009-07-29029 July 2009 Decommissioning Funding Assurance Plan RS-09-041, Submittal of Exelon Generation Company, LLC, Report on Status of Decommissioning Funding for Reactors Owned by EGC2009-03-31031 March 2009 Submittal of Exelon Generation Company, LLC, Report on Status of Decommissioning Funding for Reactors Owned by EGC RS-08-036, License Amendment Request to Revise Containment Tendon Surveillance Program2008-04-0909 April 2008 License Amendment Request to Revise Containment Tendon Surveillance Program RS-06-176, Site-Specific Decommissioning Cost Estimates2006-12-18018 December 2006 Site-Specific Decommissioning Cost Estimates RS-02-045, Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles2002-04-19019 April 2002 Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles ML0208801152002-03-19019 March 2002 Request for a License Amendment to Modify the Method of Controlling Unfavorable Exposure Time Related to an Anticipated Transient Without Scram Event for Byron and Braidwood Station 2023-03-23
[Table view] Category:70
MONTHYEARRS-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-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-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-032, Amended Decommissioning Trust Agreements2021-02-25025 February 2021 Amended Decommissioning Trust Agreements RS-21-030, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-02-24024 February 2021 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 RS-19-045, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2019-04-0101 April 2019 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-19-022, License Amendment Request - Clarifying Changes for Certain Emergency Action Levels Based on Emergency Preparedness Program Frequently Asked Questions (Epfaqs)2019-03-0101 March 2019 License Amendment Request - Clarifying Changes for Certain Emergency Action Levels Based on Emergency Preparedness Program Frequently Asked Questions (Epfaqs) RS-16-197, License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair2016-09-30030 September 2016 License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair RS-16-040, Report on Status of Decommissioning Funding2016-02-0404 February 2016 Report on Status of Decommissioning Funding ML16008A1172016-01-20020 January 2016 U.S. Nuclear Regulatory Commission Analysis of Excelon Generation'S Decommissioning Funding Status Report RS-15-094, (EGC) - Submittal of Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2015-03-31031 March 2015 (EGC) - Submittal of Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-15-077, Submittal of Updated Site Specific Safstor Decommissioning Cost Estimates for Braidwood, Byron and LaSalle Stations2015-02-19019 February 2015 Submittal of Updated Site Specific Safstor Decommissioning Cost Estimates for Braidwood, Byron and LaSalle Stations ML13161A2232013-06-0303 June 2013 Byron and Braidwood, Units 1 and 2 - License Renewal Application RS-13-106, (EGC) Amended 2011 Report on Status of Decommissioning Funding for Reactors and Correction to July 27, 2011 RAI Response2013-04-12012 April 2013 (EGC) Amended 2011 Report on Status of Decommissioning Funding for Reactors and Correction to July 27, 2011 RAI Response RS-13-100, Report on Status of Decommissioning Funding for Reactors2013-04-0101 April 2013 Report on Status of Decommissioning Funding for Reactors ML1206604942012-03-30030 March 2012 Issuance of Amendments Revision of Technical Specifications (TS) 3.3.1, Reactor Trip System Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation (TAC ME5836... ML1001202412010-01-11011 January 2010 Submittal of Braidwood Station Site-Specific Safstor Decommissioning Cost Estimate RS-09-157, Submittal of Site-Specific Safstor Decommissioning Cost Estimate2009-11-16016 November 2009 Submittal of Site-Specific Safstor Decommissioning Cost Estimate RS-09-095, Decommissioning Funding Assurance Plan2009-07-29029 July 2009 Decommissioning Funding Assurance Plan ML0921201652009-07-29029 July 2009 Decommissioning Funding Assurance Plan RS-09-041, Submittal of Exelon Generation Company, LLC, Report on Status of Decommissioning Funding for Reactors Owned by EGC2009-03-31031 March 2009 Submittal of Exelon Generation Company, LLC, Report on Status of Decommissioning Funding for Reactors Owned by EGC RS-08-036, License Amendment Request to Revise Containment Tendon Surveillance Program2008-04-0909 April 2008 License Amendment Request to Revise Containment Tendon Surveillance Program RS-06-176, Site-Specific Decommissioning Cost Estimates2006-12-18018 December 2006 Site-Specific Decommissioning Cost Estimates RS-02-045, Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles2002-04-19019 April 2002 Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles ML0208801152002-03-19019 March 2002 Request for a License Amendment to Modify the Method of Controlling Unfavorable Exposure Time Related to an Anticipated Transient Without Scram Event for Byron and Braidwood Station 2023-03-23
[Table view] Category:Technical Specifications
MONTHYEARRS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink 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 ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position 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 ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21154A0462021-07-13013 July 2021 Issuance of Amendments Nos. 222 and 222 Revision of Technical Specifications for the Ultimate Heat Sink ML21060B2812021-04-0202 April 2021 Issuance of Amendments Nos. 221, 221, 224, and 224 Regarding Technical Specifications 3.8.1, AC Sources-Operating ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20317A0012020-12-28028 December 2020 Non-Proprietary, Issuance of Amendment Nos. 219, 219, 223, and 223, Revise Loss-of-Coolant Accident Methodology in TS 5.6.5, Core Operating Limits Report (COLR) ML21008A4052020-12-17017 December 2020 Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections ML20246G8652020-09-21021 September 2020 Issuance of Amendment Nos. 222 and 222 One-Time Extension of Unit No. 2 Steam Generator Inspections (COVID-19) ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20118C4292020-06-0909 June 2020 Issuance of Amendments Revision of Technical Specifications for the Ultimate Heat Sink ML20086M2882020-04-0202 April 2020 Correction of Amendments Nos. for Amendments Revising Instrument Testing and Calibration Definitions RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML19190A0812019-08-28028 August 2019 Issuance of Amendments Regarding Limiting Condition of Operation for Inoperability of Snubbers RS-19-018, Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times2019-02-14014 February 2019 Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times RS-18-102, License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.22018-08-10010 August 2018 License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.2 ML18067A1812018-06-0404 June 2018 Correction to Technical Specification Amendment Identification Format ML16180A2512016-08-0101 August 2016 Issuance of Amendments Regarding Use of Optimized Zirlo as Fuel Cladding Material ML16133A4382016-07-26026 July 2016 Issuance of Amendments Ultimate Heat Sink Temperature Increase RS-16-034, License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding2016-02-23023 February 2016 License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding ML15336A7312016-01-27027 January 2016 TS 50456-Bwd-AppsABC ML15307A7762015-12-21021 December 2015 Braidwood - Issuance of Amendments Regarding Installation of New Low Degraded Voltage Relays and Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses (CAC Nos. MF4051 - MF4054) ML15341A3162015-12-14014 December 2015 Correction of Technical Specifications Related to Amendment 145 ML15286A2762015-11-19019 November 2015 Technical Specifications ML15232A4412015-10-28028 October 2015 Issuance of Amendments to Utilize WCAP-16143-P, Revision 1 Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Byron/Braidwood Units 1 and 2, Dated October 2014 ML15268A4862015-10-0606 October 2015 Correction of Amendments Adopting Technical Specification Task Force Traveler TSTF-523 (TAC Nos. MF4436-MF4446) ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training RS-14-337, Units 1 & 2 - License Amendment Request for Diesel Generator Load Rejection Surveillance Requirement2014-12-18018 December 2014 Units 1 & 2 - License Amendment Request for Diesel Generator Load Rejection Surveillance Requirement ML14239A4272014-12-0707 December 2014 Issuance of Amendments to Clarify Technical Specification 3.3.1, Reactor Trip System Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation RS-14-285, License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink(Uhs)2014-11-24024 November 2014 License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink(Uhs) ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements ML13311B4812014-07-21021 July 2014 Issuance of Amendments to Revise Technical Specifications Section 3.5.3 ML14069A3372014-04-0202 April 2014 Final Response to Task Interface Agreement 2012-13, Braidwood Station Technical Specification 3.6.3 Compliance with One or More Main Steam Isolation Valves Inoperable ML13326A1072014-03-13013 March 2014 Issuance of Amendments to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program ML13281A0002014-02-0707 February 2014 Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate RS-13-240, License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program.2013-10-10010 October 2013 License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program. RS-13-137, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-09-0303 September 2013 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process RS-13-175, Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs).2013-08-21021 August 2013 Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs). RS-12-009, License Amendment Request - Diesel Generator Steady State Maximum Frequency and Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel2012-05-0101 May 2012 License Amendment Request - Diesel Generator Steady State Maximum Frequency and Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel RS-12-028, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.2012-03-22022 March 2012 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. RS-12-023, License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria2012-03-20020 March 2012 License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria 2024-05-28
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Exelon Generation www.exeloncorp.com Exelon 43oo Winfield Road Nuclear Warrenville, IL 6o555 10 CFR 50 .90 RS-08-036 April 9, 2008 U . S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 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 Facility Operating License Nos . NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
License Amendment Request to Revise Containment Tendon Surveillance Program In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) requests an amendment to Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, and Facility Operating License Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2 . The proposed change revises Technical Specifications (TS) Section 5.5.6, "Pre-Stressed Concrete Containment Tendon Surveillance Program," and Section 5.6.8, "Tendon Surveillance Report," for consistency with the requirements of 10 CFR 50 .55a, "Codes and standards," paragraph (g)(4) for components classified as Code Class CC. Specifically, the proposed changes replace or delete the reference to the specific ASME Code year for the tendon surveillance program with a requirement to use the applicable ASME Code and addenda as required by 10 CFR 50.55a(g)(4) .
This request is subdivided as follows.
" Attachment 1 provides a description and evaluation of the proposed change.
" Attachment 2 provides a markup of the affected TS pages for Braidwood Station .
" Attachment 3 provides a markup of the affected TS pages for Byron Station.
" Attachments 4 and 5 provide a markup of the affected TS Bases pages for Braidwood Station and Byron Station, respectively . The TS Bases pages are provided for information only and do not require NRC approval .
April 9, 2008 U . S . Nuclear Regulatory Commission Page 2 The proposed change has been reviewed by the Plant Operations Review Committees at each of the stations and approved by the Nuclear Safety Review Board in accordance with the requirements of the EGC Quality Assurance Program .
EGC requests approval of the proposed change by April 9, 2009. Once approved, the amendment will be implemented within 60 days . This implementation period will provide adequate time for the affected station documents to be revised using the appropriate change control mechanisms .
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), EGC is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official .
There are no regulatory commitments contained in this letter . If you have any questions concerning this letter, please contact Ms. Tricia Mattson at (630) 657-2813 .
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 9th day of April 2008.
Respectfully, P6 Patrick R. Simpson Manager - Licensing Attachments:
- 1. Evaluation of Proposed Change
- 2. Markup of Proposed Technical Specifications Pages for Braidwood Station
- 3. Markup of Proposed Technical Specifications Pages for Byron Station
- 4. Markup of Proposed Technical Specifications Bases Pages for Braidwood Station
- 5. Markup of Proposed Technical Specifications Bases Pages for Byron Station
ATTACHMENT 1 Evaluation of Proposed Change 1 .0 DESCRIPTION
2.0 PROPOSED CHANGE
3.0 BACKGROUND
4.0 TECHNICAL ANALYSIS
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria
6.0 ENVIRONMENTAL CONSIDERATION
7.0 REFERENCES
ATTACHMENT 1 Evaluation of Proposed Change 1 .0 DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit,"
Exelon Generation Company, LLC (EGC) requests an amendment to the Technical Specifications (TS) of Facility Operating License Nos. NPF-72, NPF-77, NPF 37, and NPF-66 for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, respectively .
The proposed change revises TS Section 5.5 .6 "Pre-Stressed Concrete Containment Tendon Surveillance Program," and Section 5.6.8, "Tendon Surveillance Report," for consistency with the requirements of 10 CFR 50.55a, "Codes and standards," paragraph (g)(4) for components classified as Code Class CC. This regulation requires licensees to update their 10-year containment inservice inspection interval to comply with the latest edition and addenda of the Code incorporated by reference in paragraph (b) of 10 CFR 50 .55a .
This proposed change is a conforming administrative amendment in that it revises TS Section 5.5.6 and 5.5.8 to remove the reference to the specific ASME Code edition and addenda, since 10 CFR 50.55a(g)(4) provides the regulatory requirement to update this for each 10-year interval .
2 .0 PROPOSED CHANGE The proposed change revises TS Section 5.5.6 to read :
" . . .The Containment Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC ."
Additionally, the note stating the provisions of Surveillance Requirement (SR) 3.0.2 is applicable to the frequency of the SR is being deleted from these specifications .
TS Section 5.6.8 is revised to delete the reference to the dated edition and addenda.
3.0 BACKGROUND
On January 7, 1994, the NRC published a proposed amendment to the regulations to incorporate by reference the 1992 Edition with the 1992 Addenda of Subsections IWE and IWL of Section XI, Division I of the ASME Boiler and Pressure Vessel Code (the Code). The final rule, 10 CFR 50.55a(g)(6)(ii)(B), became effective on September 9, 1996, and requires licensees to implement Subsections IWE and IWL, with specified modifications and limitations, by September 9, 2001 .
For Braidwood, the next 10-year containment inservice inspection interval for Unit 1 and Unit 2 is scheduled to begin on July 29, 2008 and October 17, 2008, respectively . For Byron, the current 10-year containment inservice inspection interval for Unit 1 and Unit 2 began on January 16, 2006, as outlined in Reference 1 .
ATTACHMENT 1 Evaluation of Proposed Change The containment consists of a pre-stressed, reinforced concrete, cylindrical structure with a hemispherical dome . The post-tensioning system used for the shell and dome of the containment employs tendons. Each tendon consists of high strength steel wires and anchoring components. The pre-stressing load is transferred, by cold formed button heads on the ends of the individual wires through stressing washers, to steel bearing plates embedded in the structure. The unbonded tendons are installed in tendon ducts and tensioned in a predetermined sequence .
4.0 TECHNICAL ANALYSIS
TS Section 5.5.6, states in part, "The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in conformance with requirements of 10 CFR 50 .55a(b)(2)(vi),
10 CFR 50 .55a(b)(2)(ix), ASME Boiler and Pressure Vessel Code Subsection IWL, 1992 Edition with the 1992 Addenda and Regulatory Guide 1 .35 .1, July 1990 ." TS Section 5.6.8, states in part, "Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50.55a and ASME Section XI, 1992 Edition with the 1992 Addenda ." As identified above, 10 CFR 50 .55a(g)(4) requires licensees to update their containment inservice inspection requirements in accordance with Subsections IWE and IWL of Section XI, Division I of the ASME Boiler and Pressure Vessel Code as limited by 10 CFR 50.55a(b)(2)(vi) and modified by 10 CFR 50 .55a(b)(2)(viii) and 10 CFR 50.55a(b)(2)(ix) . The requirements in 10 CFR 50.55a(g)(4) and ASME Code Section XI, Subsection IWL, do not reference the 1992 Edition with the 1992 Addenda or Regulatory Guide 1 .35.1 . Rather, 10 CFR 50.55a(g)(4) requires the latest edition and addenda of the ASME Code incorporated by reference in paragraph (b) of 10 CFR 50.55a, to be used for containment inservice inspections . As such, the TS are inconsistent with the requirements of 10 CFR 50.55a and should be updated to refer to the most updated edition of the ASME Code as specified in 10 CFR 50.55a and to remove the reference to Regulatory Guide 1 .35.1 .
Additionally, since the tendon inspection frequencies will be in accordance with ASME Section XI, Subsection IWL, the provisions of SR 3.0.2 are no longer applicable and are deleted from Technical Specification 5 .5.6. As discussed in the TS Bases for SR 3.0.2, the regulations take precedence over the TS . As such, 10 CFR 50 .55a requires the implementation of ASME Section XI, Subsection IWL, and specifies the requirements for extending inspection frequencies.
The proposed change adopts wording that is identical to NUREG-1431 (i .e., Reference 2) for the containment tendon surveillance program.
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration In accordance with 10 CFR 50 .90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) requests an amendment to Technical Specifications (TS) Section 5.5.6 and Section 5 .6.8 of Facility Operating License Nos. NPF-72, NPF-77, NPF 37, and NPF-66 for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, respectively .
ATTACHMENT 1 Evaluation of Proposed Change The proposed amendment revises the TS Section 5 .5 .6 "Pre-Stressed Concrete Containment Tendon Surveillance Program," and Section 5.6.8 "Tendon Surveillance Report," for consistency with the requirements of 10 CFR 50 .55a, "Codes and standards," paragraph (g)(4) for components classified as Code Class CC . Additionally, the note stating the provisions of Surveillance Requirement (SR) 3 .0 .2 is applicable to the frequency of the SR is being deleted from these specifications .
According to 10 CFR 50 .92, "Issuance of amendment," paragraph (c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
1 . Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2 . Create the possibility of anew or different kind of accident from any accident previously evaluated; or 3 . Involve a significant reduction in a margin of safety.
In support of this determination, an evaluation of each of the three criteria set forth in 10 CFR 50.92 is provided below regarding the proposed license amendment .
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response : No The proposed change revises the TS administrative controls program for consistency with the requirements of 10 CFR 50.55a(g)(4) for components classified as Code Class CC .
The revised requirements do not affect the function of the containment post-tensioning system components. The post-tensioning systems are passive components whose failure modes could not act as accident initiators or precursors . The proposed change does not impact the physical configuration or function of plant structures, systems, or components (SSCs) or the manner in which SSCs are operated, maintained, modified, tested, or inspected . The proposed change does not impact the initiators or assumptions of analyzed events, nor does it impact the mitigation of accidents or transient events .
The proposed change does not impact any accident initiators or analyzed events or assumed mitigation of accident or transient events . It does not involve the addition or removal of any equipment, or any design changes to the facility .
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated .
ATTACHMENT 1 Evaluation of Proposed Change
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response : No The proposed change revises the TS administrative controls program for consistency with the requirements of 10 CFR 50.55a(g)(4) for components classified as Code Class CC .
The function of the containment post-tensioning system components is not altered by this change. The proposed change does not involve a modification to the physical configuration of the plant (i .e., no new equipment will be installed) or change in the methods governing normal plant operation . The proposed change will not impose any new or different requirements or introduce a new accident initiator, accident precursor, or malfunction mechanism. Additionally, there is no change in the types or increases in the amounts of any effluent that may be released off-site and there is no increase in individual or cumulative occupational exposure .
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response : No The proposed change revises the TS administrative controls program requirements for consistency with the requirements of 10 CFR 50.55a(g)(4) for components classified as Code Class CC.
The function of the containment post-tensioning system components are not altered by this change. The change is conforming and administrative in nature in that it will allow the TS to be updated to refer to the most recently approved edition of the ASME Boiler and Pressure Vessel Code Subsection IWL. The safety function of the containment as a fission product barrier will be maintained .
Therefore, the proposed change does not involve a significant reduction in a margin of safety .
Based upon the above, EGC concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified .
5.2 Applicable Regulatory Requirements/Criteria 10 CFR 50.55a(g)(4) requires that for each successive 10-year inservice inspection interval, licensees adopt the latest edition and addenda of the ASME Code Section XI, incorporated by
ATTACHMENT 1 Evaluation of Proposed Change reference in 10 CFR 50 .55a(b). The proposed amendment revises TS Section 5 .5.6 and Section 5.6.8 for consistency with the requirements of 10 CFR 50.55a(g)(4) for components classified as Code Class CC.
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public .
6.0 ENVIRONMENTAL CONSIDERATION
EGC has evaluated this proposed license amendment and determined that the proposed change would change a requirement with respect to installation or use of a facility component located within the restricted areas, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure . Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51 .22 "Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review" paragraph (c)(9) . Therefore, pursuant to 10 CFR 51 .22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.
7.0 REFERENCES
- 1. Letter from D. Hoots (EGC) to U . S. NRC, "Byron Station, Units 1 and 2, Transmittal of Inservice Inspection Program Plan for Third Ten year Inspection Interval," dated February 14, 2006
- 2. NUREG-1431, "Standard Technical Specifications Westinghouse Plants," Volume 1, Revision 3, dated March 2004
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages for Braidwood Station Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 REVISED TECHNICAL SPECIFICATIONS PAGES 5.5-5 5.6-6
Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .6 Pre-Stressed Con crete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity . The program shall include baseline measurements prior to initial operations . The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in C R!! ith P ~i pements ef accordance The provisions of SR 3 .9 .2 ap~ SR 3 .0 .3 are applicable to the Tendon Surveillance Program inspection frequencies .
5 .5 .7 Reactor Coolant Pub Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c .4 .b of Regulatory Guide 1 .14, Revision 1, August 1975 .
In lieu of Regulatory Position c .4 .b(1) and c .4 .b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI .
Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55x, except where an alternative, exemption, or relief has been authorized by the NRC .
BRAIDWOOD - UNITS 1 & 2 5 .5 - 5 Amendment 118
Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .8 Tendon Surveillance Resort Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50 .55a and ASME Section XI; 5 .6 .9 Steam Generator (SG) Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 5 .5 .9, Steam Generator (SG) Program .
The report shall include :
- a. The scope of inspections performed on each SG,
- b. Active degradation mechanisms found,
- c. Nondestructive examination techniques utilized for each degradation mechanism,
- d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
- e. Number of tubes plugged or repaired during the inspection outage for each active degradation mechanism,
- f. Total number and percentage of tubes plugged or repaired to date,
- g. The results of condition monitoring, including the results of tube pulls and in-situ testing,
- h. The effective plugging percentage for all plugging and tube repairs in each SG, and i . Repair method utilized and the number of tubes repaired by each repair method .
BRAIDWOOD - UNITS 1 & 2 5 .6 - 6 Amendment 144
ATTACHMENT 3 Markup of Proposed Technical Specifications Pages for Byron Station Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 REVISED TECHNICAL SPEC IFICATIONS PAGES 5.5-5 5.6-6
Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .6 Pre-Stressed Concrete Containment Tendon_ .Surveillance Progra m This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity . The program shall include baseline measurements prior to initial operations . The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be i n r=eH¬ePH ;aHGeF~i th n+c n~
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/Addenda alld Regul atepy (_Hide 1-25 .1, 99v_ accordance The provisions of S ~~2a- SR 3 .0 .3 are applicable to the Tendon Surveillance Program inspection frequencies .
5 .5 .7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c .4 .b of Regulatory Guide 1 .14, Revision 1, August 1975 .
In lieu of Regulatory Position c .4 .b(1) and c .4 .b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI .
Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55a, except where an alternative, exemption, or relief has been authorized by the NRC .
BYRON - UNITS 1 & 2 5 .5 - 5 Amendment 123
Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .8 Tendon Surveillance Report Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50 .55a and ASME Section XI, 92 Ed# i GH w 4-th the 1992 AddeHda .
5 .6 .9 Steam Generator (SG) Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 5 .5 .9, Steam Generator (SG) Program .
The report shall include :
- a. The scope of inspections performed on each SG,
- b. Active degradation mechanisms found,
- c. Nondestructive examination techniques utilized for each degradation mechanism,
- d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
- e. Number of tubes plugged or repaired during the inspection outage for each active degradation mechanism,
- f. Total number and percentage of tubes plugged or repaired to date,
- 9. The results of condition monitoring, including the results of tube pulls and in-situ testing,
- h. The effective plugging percentage for all plugging and tube repairs in each SG, and i . Repair method utilized and the number of tubes repaired by each repair method .
For Unit 2, following completion of an inspection performed in Refueling Outage 13 (and any inspections performed in the subsequent operating cycle), the number of indications and location, size, orientation, and whether initiated on primary or secondary side for each indication detected in the upper 17-inches of the tubesheet thickness .
BYRON - UNITS 1 & 2 5 .6 - 6 Amendment 150
ATTACHMENT 4 Markup of Technical Specifications Bases Pages for Braidwood Station Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.6.1 - 3 B 3.6.1 - 6 B 3.6.1 - 7
Containment B 3 .6 .1 BASES APPLICABLE SAFETY ANALYSES (continued)
The DBAs that result in a challenge to containment OPERABILITY from high pressures and temperatures are a LOCA and a steam line break (Ref . 2) . In addition, release of significant fission product radioactivity within containment can occur from a LOCA, secondary system pipe break, or fuel handling accident (Ref . 3) . In the DBA analyses, it is assumed that the containment is OPERABLE such that, for the DBAs involving release of fission product radioactivity, release to the environment is controlled by the rate of containment leakage . The containment leakage rate, used to evaluate doses resulting from accidents, is defined in 10 CFR 50, Appendix J, Option B (Ref . 1), as La : the maximum allowable containment leakage rate at the calculated peak containment internal pressure (P ) resulting from the limiting design basis LOCA .
The allowable leakage rate represented by La forms the basis for the acceptance criteria imposed on all containment leakage rate testing . L is assumed to be 0 .20% per day in the safety analysis at = 42 .8 psig for Unit 1 and Pa = 38 .4 psig for Unit (Ref . 3) .
The radiological dose assessments performed for the design basis LOCA assume a maximum allowable containment leakage rate of 0 .20% per day . In this case, the dose limits of 10 CFR 50 .6 7 (Ref . ;) are not exceeded .
6 Satisfactory leakage rate test results are a requirement for the establishment of containment OPERABILITY .
The containment satisfies Criterion 3 of 10 CFR 50 .36(c)(2)(ii) .
LCO Containment OPERABILITY is maintained by limiting leakage to
<_ 1 .0 La , except prior to the first startup after performing a required Containment Leakage Rate Testing Program leakage test . At this time, applicable leakage limits must be met .
Compliance with this LCO will ensure a containment configuration, including the equi pment hatch, that is structurally sound and that will limit leakage to those leakage rates assumed in the safety analysis .
BRAIDWOOD - UNITS 1 & 2 B 3 .6 .1 - 3 Revision 61
Containment B 3 .6 . 1 BASES SURVEILLANCE SR 3 .6 .1 .1 REQUIREMENTS Maintaining the containment OPERABLE requires compliance with the visual examinations and leakage rate test requirements of the Containment Leakage Rate Testing Program . Failure to meet air lock and purge valve leakage limits specified in LCO 3 .6 .2 and LCO 3 .6 .3 does not invalidate the acceptability of these overall leakage determinations unless their contribution to overall Type A, B, and C leakage causes that to exceed limits . As left leakage prior to the first startup after performing a required leakage test is required to be < 0 .6 L a for combined Type B and C leakage and < 0 .75 La for overall Type A leakage . At all other times between required leakage rate tests, the acceptance criteria is based on an overall Type A leakage limit of <_ 1 .0 La . At <_ 1 .0 La the dose consequences are bounded by the assumptions of the safety analysis . SR Frequencies are as required by the Containment Leakage Rate Testing Program . These periodic testing requirements verify that the containment leakage rate does not exceed the leakage rate assumed in the safety analysis .
SR 3 .6 .1 .2 This SR ensures that the structural integrity of the containment will be maintained in accordance with the provisions of the Containment Tendon Surveillance Program .
Testing and Frequency are consistent with the requi. rements of 10 CFR50 .55a OT!WI, SE9TT9N XTT" (Ref .
-!WE aRd SHbseGti nn !WI, SHbse G~GTI'1 (I DDF(1 GF~(hl(`J1(ivl "EXamiRat4GR ofr aRdSe ccmrrrcrT-G ra cr GeRGnete-Ee 48i-amen " , P4 . ~ .R Predicted tendon lift off forces will be determined GR 4eRt with ,e Te epda e 1 .35 .1, (Ref .
"Codes and standards" in accordance with the ASME Code,Section XI, Subsection IWL (Ref . 5), and applicable addenda as required by 10 CFR 50 .55a .
BRAIDWOOD - UNITS 1 & 2 B 3 .6 .1 - 6 Revision 61
Containment B 3 .6 .1 BASES REFERENCES 1. 10 CCFR 50, Appendix J, Opt on B .
- 2. UFSAR, Chapter 15 .
- 3. UFSAR, Section 6 .2 .
- 4. 10 CFR50 .55a,(b)( ' " ¬- 4 E ' d AddeRda P^ avid SHbco ! . i'LSECTIONNY1 ."
"Codes and seGt4gR !WE v-standards ." 1 (1 (`DDF(1 GF~ 1,~~2~~~ , ~~ ~
~m GGY1~ e
- 5. rav-iron
- 6. RegH1 atery (_Hide l .
fTC'gRT '
'2G l
.T~
10 CFR 50 .67 .
ASME Code,Section XI, Subsection IWL BRAIDWOOD - UNITS 1 & 2 B 3 .6 .1 - 7 Revision 61
ATTACHMENT 5 Markup of Technical Specifications Bases Pages for Byron Station Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 2.6.1 - 3 B 3 .6.1 - 5 B 3 .6.1 - 6
Containment B 3 .6 .1 BASES APPLICABLE SAFETY ANALYSES (continued)
The DBAs that result in a challenge to containment OPERABILITY from high pressures and temperatures are a LOCA and a steam line break (Ref . 2) . In addition, release of significant fission product radioactivity within containment can occur from a LOCA, secondary system pipe break, or fuel handling accident (Ref . 3) . In the DBA analyses, it is assumed that the containment is OPERABLE such that, for the DBAs involving release of fission product radioactivity, release to the environment is controlled by the rate of containment leakage . The containment leakage rate, used to evaluate doses resulting from accidents, is defined in 10 CFR 50, Appendix J, Option B (Ref . 1), as La : the maximum allowable containment leakage rate at the calculated peak containment internal pressure (P ) resulting from the limiting design basis LOCA .
The allowable leakage rate represented by La forms the basis for the acceptance criteria imposed on all containment leakage rate testing . La is assumed to be 0 .20% per day in the safety analysis at P = 42 .8 psig for Unit 1 and Pa = 38 .4 psig for Unit 2 (Ref . 3) .
The radiological dose assessments performed for the design basis LOCA assume a maximum allowable containment leakage rate of 0 .20% per day . In this case, the dose limits of 10 CFR 50 .67 (Ref .,,-7 ) are not exceeded .
6 Satisfactory leakage rate test results are a requirement for the establishment of containment OPERABILITY .
The containment satisfies Criterion 3 of 10 CFR 50 .36(c)(2)(ii) .
LCO Containment OPERABILITY is maintained by limiting leakage to
<_ 1 .0 La , except prior to the first startup after performing a required Containment Leakage Rate Testing Program leakage test . At this time, applicable leakage limits must be met .
Compliance with this LCO will ensure a containment configuration, including the equipment hatch, that is structurally sound and that will limit leakage to those leakage rates assumed in the safety analysis .
BYRON - UNITS 1 & 2 B 3 .6 .1 - 3 Revision 55
Containment B 3 .6 . 1 BASES SURVEILLANCE SR 3 .6 .1 .1 REQUIREMENTS Maintaining the containment OPERABLE requires compliance with the visual examinations and leakage rate test requirements of the Containment Leakage Rate Testing Program . Failure to meet air lock and purge valve leakage limits specified in LCO 3 .6 .2 and LCO 3 .6 .3 does not invalidate the acceptability of these overall leakage determinations unless their contribution to overall Type A, B, and C leakage causes that to exceed limits . As left leakage prior to the first startup after performing a required leakage test is required to be < 0 .6 La for combined Type B and C leakage and < 0 .75 La for overall Type A leakage . At all other times between required leakage rate tests, the acceptance criteria is based on an overall Type A leakage limit of <_ 1 .0 La . At <_ 1 .0 La the dose consequences are bounded by the assumptions of the safety analysis . SR Frequencies are as required by the Containment Leakage Rate Testing Program . These periodic testing requirements verify that the containment leakage rate does not exceed the leakage rate assumed in the safety analysis .
SR 3 .6 .1 .2 This SR ensures that the structural integrity of the containment will be maintained in accordance with the provisions of the Containment Tendon Surveillance Program .
Testing and Frequency are consistent with the requirements of 10 CFR50 .55a-(b)-( -" ¬4eE ' Edi+4^n and nddeRd~ n-F bsecti-eH--h 14- a - .
S1-, eGti-eR-IWL, SEG IION-X1!' (Ref . 4),
"Codes and GGRGnete-Ee Rtai-emeRts (Ref . 5 } . Predicted tendon lift off forces will be determined GeRsisteRt with the standards" PeGeweRd at4-en-s-e; Reg Hlat ^ny (_wide 1 .36 .1, (Ref . 6) .
in accordance with the ASME Code,Section XI, Subsection IWL (Ref . 5), and applicable addenda as required by 10 CFR 50 .55a .
BYRON - UNITS 1 & 2 B 3 .6 .1 - 5 Revision 55
Containment B 3 .6 .1 BASES REFERENCES 1. 10 CFR 50, Appendix J, Option B .
- 2. UFSAR, Chapter 15 .
- 3. UFSAR, Section 6 .2 .
- 4. 10 CFR50 . 55a-(b)( 2 ' ( -cf rfcGtive Edi t i eR alld Addenda o SHbSeG iGR 1WIE Swb-S eGtiF-!WL . SECTION X111 .
f r?1(ivl~
1(1 (~GDFfI FF~(hlT "Examination of Gnnrncte-
"Codes and cvrnrca 4 HrReHts "
standards ."
- 6. rcm°.qarutGny GHi de 1 .35 .1, lHl y 14
~
7 10 CFR 50 .67 .
ASME Code,Section XI, Subsection IWL BYRON - UNITS 1 & 2 B 3 .6 .1 - 6 Revision 55