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Category:Decommissioning Funding Plan DKTs 30
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-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-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 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 ML1001202412010-01-11011 January 2010 Submittal of Braidwood Station Site-Specific Safstor Decommissioning Cost Estimate ML0921201652009-07-29029 July 2009 Decommissioning Funding Assurance Plan RS-09-095, Decommissioning Funding Assurance Plan2009-07-29029 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-06-176, Site-Specific Decommissioning Cost Estimates2006-12-18018 December 2006 Site-Specific Decommissioning Cost Estimates 2023-03-23
[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:50
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-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-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 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 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-06-176, Site-Specific Decommissioning Cost Estimates2006-12-18018 December 2006 Site-Specific Decommissioning Cost Estimates 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:Letter type:RS
MONTHYEARRS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval2024-09-13013 September 2024 Relief Requests Associated with the Fifth Inservice Inspection Interval RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-118, Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-10-31031 October 2022 Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . 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 2024-09-13
[Table view] |
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4300 Winfielcl Rozicl Warrenville. IL 60555 Exelon Generation 630 657 2000 Office RS-16-040 10 CFR 50. 75(f) 10 CFR 72.30(b)
February 4, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456. STN 50-457. and 72-73 Byron Station, Unit 2 Renewed Facility Operating License No. NPF-66 NRC Docket Nos. STN 50-455 and 72-68
Subject:
Report on Status of Decommissioning Funding for Braidwood Station, Units 1 and 2 and Byron Station, Unit 2
References:
- 1. Letter from Patrick R. Simpson (Exelon Generation Company, LLC) to U.
S. NRC, "Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations," dated March 31, 2015
- 2. Letter from U. S. NRC to Patrick R. Simpson (Exelon Generation Company, LLC), "Braidwood Station Units 1 and 2, and Byron Station, Units 1 and 2 U.S. Nuclear Regulatory Commission Analysis of Exelon Generation's Decommissioning Funding Status Report," dated January 20,2016 In Reference 1, Exelon Generation Company, LLC (EGC) identified that Braidwood Station, Units 1 and 2 and Byron Station, Unit 2, did not meet the minimum funding assurance criteria under 10 CFR 50. 75, "Reporting and recordkeeping for decommissioning planning,"
as of December 31, 2014. In Reference 2, the NRC acknowledged that EGC had not provided decommissioning assurance as required in the regulations at 10 CFR 50.75 for Braidwood Station, Units 1 and 2 and Byron Station, Unit 2. The NRC instructed EGC to correct any decommissioning funding shortfalls in a timely manner and report compliance to the NRC on or before March 31, 2017. The purpose of this letter is to advise the NRC that the funding shortfalls for Braidwood Station, Units 1 and 2, and Byron Station, Unit 2, have been resolved and to report compliance with the funding assurance requirements of 10 CFR 50.75 as of January 31, 2016.
Subsequent to identification of the funding shortfalls referenced in References 1 and 2, the NRC approved the renewed facility operating licenses for Braidwood Station, Units 1 and 2 effective January 27, 2016 and for Byron Station, Unit 2 effective November 19, 2015.
When the renewed license operating periods are credited in the decommissioning funding
February 4, 2016 U.S. Nuclear Regulatory Commission Page 2 assurance calculations for Braidwood Station, Units 1 and 2, and Byron Station, Unit 2, the minimum funding assurance criteria in 10 CFR 50. 75 are met.
Attachments 2, 3, and 4 contain the updated funding status reports for Braidwood Station, Units 1 and 2 and Byron Station, Unit 2, respectively. This information shows that Braidwood Station, Units 1 and 2 and Byron Station, Unit 2 meet decommissioning funding assurance requirements using the NRC formula cost amount. The calculation of the NRC formula cost amounts provided in Attachments 2, 3, and 4 assumes the labor, energy, and burial factors described in Attachment 1.
In addition to reporting the updated status of decommissioning funding assurance for these reactors in accordance with 10 CFR 50. 75, Attachments 2, 3, and 4 report the updated status of decommissioning funding assurance for the Braidwood Station, Units 1 and 2 and Byron Station, Unit 2 independent spent fuel storage installation (ISFSI) in accordance with 10 CFR 72.30, "Financial assurance and recordkeeping for decommissioning." With respect to the other information required by 10 CFR 72.30(b) and (c), there has been no change from the information provided in Reference 1.
EGC uses the formula cost amount or the site-specific decommissioning cost estimates to demonstrate adequacy of funding to meet regulatory requirements. EGC has not made a final decision as to which decommissioning option to pursue and recognizes that the chosen option must meet NRC requirements for decommissioning funding.
There were no disbursements from the decommissioning trust funds other than those for allowed administrative costs and other incidental expenses of the funds in connection with the operation of the funds per 10 CFR 50. 75(h)(1 )(iv).
This letter completes the actions necessary to resolve all shortfalls identified in Reference 1.
There are no regulatory commitments contained within this letter.
If you have any questions concerning this letter, please contact Mr. Timothy A. Byam at (630) 657-2818.
Patrick R. Simpson Manager - Licensing cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Braidwood Station NRC Senior Resident Inspector- Byron Station
February 4, 2016 U. S. Nuclear Regulatory Commission Page 3 Attachments:
- 1. Labor, Energy, and Burial Factors Used in Calculations
- 2. Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 1
- 3. Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 2
- 4. Radiological Decommissioning Funding Assurance Report for Byron Station, Unit 2
ATTACHMENT 1 Labor, Energy, and Burial Factors Used in Calculations
ATTACHMENT 1 Labor, Energy, and Burial Factors Used in Calculations The labor, energy, and burial indexes used are consistent with those described in NUREG-1307, Revision 15, issued January 2013.
The current labor cost index used is obtained from the Employment Cost Index, published by the U.S. Department of Labor, Bureau of Labor Statistics (BLS). Specifically, EGC used the Employment Cost Index for total compensation for private industry workers by region.
The labor adjustment factor was calculated according to Section 3.1 of NUREG-1307, Revision 15, using fourth quarter 2015 data. Table 1 shows the data used for this calculation.
Table 1: Labor Adjustment Factor 4Q2015 Index Base Labor Adjustment Region Series ID Number Lx Factor (Lx)
Midwest CIU2010000000230I 122.5 2.08 2.548 The current energy cost indexes used are obtained from Producer Price Indexes (PPI) -
Commodities, published by the U.S. Department of Labor, BLS. Specifically, EGC used the PPI for industrial electric power (WPU0543) and light fuel oils (WPU0573). The energy adjustment factors were calculated according to Section 3.2 of NUREG-1307, Revision 15, using December 2015 data. Table 2 shows the data used for this calculation.
Table 2: Energy Adjustment Factors WPU0543 - January 1986 (base value) 114.2 WPU0573 - January 1986 (base value) 82.0 WPU0543 - December 2015 (preliminary value) 214.9 WPU0573 - December 2015(preliminary value) 130.4 Industrial electric power adjustment factor - Px 1.882 Light fuel oil adjustment factor - Fx 1.590 Energy Adjustment Factor (PWR) - Ex(PWR) 1.759 The waste burial adjustment factor used is taken from Table 2-1 of NUREG-1307, Revision 15, based on 2012 data. The adjustment factor EGC used assumes a combination of compact-affiliated and non-compact facilities, consistent with current waste disposal practices at EGC and consistent with typical waste disposal practices during decommissioning. Table 3 summarizes the data used for the calculation of the waste adjustment factor.
Table 3: Waste Adjustment Factors Combination of Compact-Affiliated Reactor and Non-Compact Facility Waste LLW Burial Site Type Adjustment Factor (Bx)
Generic LLW Disposal Site PWR 13.885 The calculation methodology used for all adjustment factors is consistent with NUREG-1307, Revision 15.
ATTACHMENT 2 Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 1
ATTACHMENT 2 Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 1 (January 31, 2016 dollars, thousands) 1 Formula cost amount per 10 CFR 50.75(c) $518,659 2 Site-specific cost amount per 10 CFR 50.75(b)(4) N/A 3 Site-specific cost amount per 10 CFR 72.30(b) $4,810 (a) 4 The amount of decommissioning trust funds accumulated as of January 31, 2016 $293,297 (b) 5 Schedule of the annual amounts remaining to be collected. $0 6 Assumptions used regarding rates of escalation, earnings, and other factors used in funding projections 2% (c) 7 There are no contracts relied upon pursuant to 10 CFR 50.75(e)(1)(v).
8 Financial assurance for decommissioning is provided by the prepayment method, coupled with an external trust fund, in accordance with 10 CFR 50.75(e)(1)(i) and 10 CFR 72.30(e)(1).
9 There are no material changes to the trust fund agreements.
(a) This is the site-specific cost estimate for ISFSI radiological decommissioning that was previously provided in a letter from Patrick R. Simpson (EGC) to U. S. NRC, dated March 31, 2015 ("Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations"). The costs have been escalated from 2014 dollars in the letter to January 31, 2016 using a unit specific escalation rate. No other changes have been made to the decommissioning funding plan in the March 31, 2015 letter.
(b) The trust fund amount is the amount allocated for Radiological Decommissioning only. EGC has no past-due tax payments owed on the decommissioning trust fund activities as of January 31, 2016. Periodic payments of estimated income taxes are made by EGC during the year on a quarterly basis, and EGC subsequently obtains reimbursement from the trust funds on a periodic basis, when the funds are sufficient to demonstrate minimum funding assurance. The trust fund amounts comply with the reporting requirements of 10 CFR 50.75(f) in that the amount of funds reported are those that were accumulated as of January 31, 2016.
(c) A 2% annual real rate of return is used as allowed by 10 CFR 50.75(e)(1)(i).
(d) For purposes of this report, permanent termination of operations (shutdown) is expected on October 17, 2046.
ATTACHMENT 3 Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 2
ATTACHMENT 3 Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 2 (January 31, 2016 dollars, thousands) 1 Formula cost amount per 10 CFR 50.75(c) $518,659 2 Site-specific cost amount per 10 CFR 50.75(b)(4) N/A 3 Site-specific cost amount per 10 CFR 72.30(b) $4,816 (a) 4 The amount of decommissioning trust funds accumulated as of January 31, 2016 $316,857 (b) 5 Schedule of the annual amounts remaining to be collected. $0 6 Assumptions used regarding rates of escalation, earnings, and other factors used in funding projections 2% (c) 7 There are no contracts relied upon pursuant to 10 CFR 50.75(e)(1)(v).
8 Financial assurance for decommissioning is provided by the prepayment method, coupled with an external trust fund, in accordance with 10 CFR 50.75(e)(1)(i) and 10 CFR 72.30(e)(1).
9 There are no material changes to the trust fund agreements.
(a) This is the site-specific cost estimate for ISFSI radiological decommissioning that was previously provided in a letter from Patrick R. Simpson (EGC) to U. S. NRC, dated March 31, 2015 ("Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations"). The costs have been escalated from 2014 dollars in the letter to January 31, 2016 using a unit specific escalation rate. No other changes have been made to the decommissioning funding plan in the March 31, 2015 letter.
(b) The trust fund amount is the amount allocated for Radiological Decommissioning only. EGC has no past-due tax payments owed on the decommissioning trust fund activities as of January 31, 2016. Periodic payments of estimated income taxes are made by EGC during the year on a quarterly basis, and EGC subsequently obtains reimbursement from the trust funds on a periodic basis, when the funds are sufficient to demonstrate minimum funding assurance. The trust fund amounts comply with the reporting requirements of 10 CFR 50.75(f) in that the amount of funds reported are those that were accumulated as of January 31, 2016.
(c) A 2% annual real rate of return is used as allowed by 10 CFR 50.75(e)(1)(i).
(d) For purposes of this report, permanent termination of operations (shutdown) is expected on December 18, 2047.
ATTACHMENT 4 Radiological Decommissioning Funding Assurance Report for Byron Station, Unit 2
ATTACHMENT 4 Radiological Decommissioning Funding Assurance Report for Byron Station, Unit 2 (January 31, 2016 dollars, thousands) 1 Formula cost amount per 10 CFR 50.75(c) $518,659 2 Site-specific cost amount per 10 CFR 50.75(b)(4) N/A 3 Site-specific cost amount per 10 CFR 72.30(b) $4,688 (a) 4 The amount of decommissioning trust funds accumulated as of January 31, 2016 $309,864 (b) 5 Schedule of the annual amounts remaining to be collected. $0 6 Assumptions used regarding rates of escalation, earnings, and other factors used in funding projections 2% (c) 7 There are no contracts relied upon pursuant to 10 CFR 50.75(e)(1)(v).
8 Financial assurance for decommissioning is provided by the prepayment method, coupled with an external trust fund, in accordance with 10 CFR 50.75(e)(1)(i) and 10 CFR 72.30(e)(1).
9 There are no material changes to the trust fund agreements.
(a) This is the site-specific cost estimate for ISFSI radiological decommissioning that was previously provided in a letter from Patrick R. Simpson (EGC) to U. S. NRC, dated March 31, 2015 ("Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations"). The costs have been escalated from 2014 dollars in the letter to January 31, 2016 using a unit specific escalation rate. No other changes have been made to the decommissioning funding plan in the March 31, 2015 letter.
(b) The trust fund amount is the amount allocated for Radiological Decommissioning only. EGC has no past-due tax payments owed on the decommissioning trust fund activities as of January 31, 2016. Periodic payments of estimated income taxes are made by EGC during the year on a quarterly basis, and EGC subsequently obtains reimbursement from the trust funds on a periodic basis, when the funds are sufficient to demonstrate minimum funding assurance. The trust fund amounts comply with the reporting requirements of 10 CFR 50.75(f) in that the amount of funds reported are those that were accumulated as of January 31, 2016.
(c) A 2% annual real rate of return is used as allowed by 10 CFR 50.75(e)(1)(i).
(d) For purposes of this report, permanent termination of operations (shutdown) is expected on November 6, 2046.
4300 Winfielcl Rozicl Warrenville. IL 60555 Exelon Generation 630 657 2000 Office RS-16-040 10 CFR 50. 75(f) 10 CFR 72.30(b)
February 4, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456. STN 50-457. and 72-73 Byron Station, Unit 2 Renewed Facility Operating License No. NPF-66 NRC Docket Nos. STN 50-455 and 72-68
Subject:
Report on Status of Decommissioning Funding for Braidwood Station, Units 1 and 2 and Byron Station, Unit 2
References:
- 1. Letter from Patrick R. Simpson (Exelon Generation Company, LLC) to U.
S. NRC, "Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations," dated March 31, 2015
- 2. Letter from U. S. NRC to Patrick R. Simpson (Exelon Generation Company, LLC), "Braidwood Station Units 1 and 2, and Byron Station, Units 1 and 2 U.S. Nuclear Regulatory Commission Analysis of Exelon Generation's Decommissioning Funding Status Report," dated January 20,2016 In Reference 1, Exelon Generation Company, LLC (EGC) identified that Braidwood Station, Units 1 and 2 and Byron Station, Unit 2, did not meet the minimum funding assurance criteria under 10 CFR 50. 75, "Reporting and recordkeeping for decommissioning planning,"
as of December 31, 2014. In Reference 2, the NRC acknowledged that EGC had not provided decommissioning assurance as required in the regulations at 10 CFR 50.75 for Braidwood Station, Units 1 and 2 and Byron Station, Unit 2. The NRC instructed EGC to correct any decommissioning funding shortfalls in a timely manner and report compliance to the NRC on or before March 31, 2017. The purpose of this letter is to advise the NRC that the funding shortfalls for Braidwood Station, Units 1 and 2, and Byron Station, Unit 2, have been resolved and to report compliance with the funding assurance requirements of 10 CFR 50.75 as of January 31, 2016.
Subsequent to identification of the funding shortfalls referenced in References 1 and 2, the NRC approved the renewed facility operating licenses for Braidwood Station, Units 1 and 2 effective January 27, 2016 and for Byron Station, Unit 2 effective November 19, 2015.
When the renewed license operating periods are credited in the decommissioning funding
February 4, 2016 U.S. Nuclear Regulatory Commission Page 2 assurance calculations for Braidwood Station, Units 1 and 2, and Byron Station, Unit 2, the minimum funding assurance criteria in 10 CFR 50. 75 are met.
Attachments 2, 3, and 4 contain the updated funding status reports for Braidwood Station, Units 1 and 2 and Byron Station, Unit 2, respectively. This information shows that Braidwood Station, Units 1 and 2 and Byron Station, Unit 2 meet decommissioning funding assurance requirements using the NRC formula cost amount. The calculation of the NRC formula cost amounts provided in Attachments 2, 3, and 4 assumes the labor, energy, and burial factors described in Attachment 1.
In addition to reporting the updated status of decommissioning funding assurance for these reactors in accordance with 10 CFR 50. 75, Attachments 2, 3, and 4 report the updated status of decommissioning funding assurance for the Braidwood Station, Units 1 and 2 and Byron Station, Unit 2 independent spent fuel storage installation (ISFSI) in accordance with 10 CFR 72.30, "Financial assurance and recordkeeping for decommissioning." With respect to the other information required by 10 CFR 72.30(b) and (c), there has been no change from the information provided in Reference 1.
EGC uses the formula cost amount or the site-specific decommissioning cost estimates to demonstrate adequacy of funding to meet regulatory requirements. EGC has not made a final decision as to which decommissioning option to pursue and recognizes that the chosen option must meet NRC requirements for decommissioning funding.
There were no disbursements from the decommissioning trust funds other than those for allowed administrative costs and other incidental expenses of the funds in connection with the operation of the funds per 10 CFR 50. 75(h)(1 )(iv).
This letter completes the actions necessary to resolve all shortfalls identified in Reference 1.
There are no regulatory commitments contained within this letter.
If you have any questions concerning this letter, please contact Mr. Timothy A. Byam at (630) 657-2818.
Patrick R. Simpson Manager - Licensing cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Braidwood Station NRC Senior Resident Inspector- Byron Station
February 4, 2016 U. S. Nuclear Regulatory Commission Page 3 Attachments:
- 1. Labor, Energy, and Burial Factors Used in Calculations
- 2. Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 1
- 3. Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 2
- 4. Radiological Decommissioning Funding Assurance Report for Byron Station, Unit 2
ATTACHMENT 1 Labor, Energy, and Burial Factors Used in Calculations
ATTACHMENT 1 Labor, Energy, and Burial Factors Used in Calculations The labor, energy, and burial indexes used are consistent with those described in NUREG-1307, Revision 15, issued January 2013.
The current labor cost index used is obtained from the Employment Cost Index, published by the U.S. Department of Labor, Bureau of Labor Statistics (BLS). Specifically, EGC used the Employment Cost Index for total compensation for private industry workers by region.
The labor adjustment factor was calculated according to Section 3.1 of NUREG-1307, Revision 15, using fourth quarter 2015 data. Table 1 shows the data used for this calculation.
Table 1: Labor Adjustment Factor 4Q2015 Index Base Labor Adjustment Region Series ID Number Lx Factor (Lx)
Midwest CIU2010000000230I 122.5 2.08 2.548 The current energy cost indexes used are obtained from Producer Price Indexes (PPI) -
Commodities, published by the U.S. Department of Labor, BLS. Specifically, EGC used the PPI for industrial electric power (WPU0543) and light fuel oils (WPU0573). The energy adjustment factors were calculated according to Section 3.2 of NUREG-1307, Revision 15, using December 2015 data. Table 2 shows the data used for this calculation.
Table 2: Energy Adjustment Factors WPU0543 - January 1986 (base value) 114.2 WPU0573 - January 1986 (base value) 82.0 WPU0543 - December 2015 (preliminary value) 214.9 WPU0573 - December 2015(preliminary value) 130.4 Industrial electric power adjustment factor - Px 1.882 Light fuel oil adjustment factor - Fx 1.590 Energy Adjustment Factor (PWR) - Ex(PWR) 1.759 The waste burial adjustment factor used is taken from Table 2-1 of NUREG-1307, Revision 15, based on 2012 data. The adjustment factor EGC used assumes a combination of compact-affiliated and non-compact facilities, consistent with current waste disposal practices at EGC and consistent with typical waste disposal practices during decommissioning. Table 3 summarizes the data used for the calculation of the waste adjustment factor.
Table 3: Waste Adjustment Factors Combination of Compact-Affiliated Reactor and Non-Compact Facility Waste LLW Burial Site Type Adjustment Factor (Bx)
Generic LLW Disposal Site PWR 13.885 The calculation methodology used for all adjustment factors is consistent with NUREG-1307, Revision 15.
ATTACHMENT 2 Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 1
ATTACHMENT 2 Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 1 (January 31, 2016 dollars, thousands) 1 Formula cost amount per 10 CFR 50.75(c) $518,659 2 Site-specific cost amount per 10 CFR 50.75(b)(4) N/A 3 Site-specific cost amount per 10 CFR 72.30(b) $4,810 (a) 4 The amount of decommissioning trust funds accumulated as of January 31, 2016 $293,297 (b) 5 Schedule of the annual amounts remaining to be collected. $0 6 Assumptions used regarding rates of escalation, earnings, and other factors used in funding projections 2% (c) 7 There are no contracts relied upon pursuant to 10 CFR 50.75(e)(1)(v).
8 Financial assurance for decommissioning is provided by the prepayment method, coupled with an external trust fund, in accordance with 10 CFR 50.75(e)(1)(i) and 10 CFR 72.30(e)(1).
9 There are no material changes to the trust fund agreements.
(a) This is the site-specific cost estimate for ISFSI radiological decommissioning that was previously provided in a letter from Patrick R. Simpson (EGC) to U. S. NRC, dated March 31, 2015 ("Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations"). The costs have been escalated from 2014 dollars in the letter to January 31, 2016 using a unit specific escalation rate. No other changes have been made to the decommissioning funding plan in the March 31, 2015 letter.
(b) The trust fund amount is the amount allocated for Radiological Decommissioning only. EGC has no past-due tax payments owed on the decommissioning trust fund activities as of January 31, 2016. Periodic payments of estimated income taxes are made by EGC during the year on a quarterly basis, and EGC subsequently obtains reimbursement from the trust funds on a periodic basis, when the funds are sufficient to demonstrate minimum funding assurance. The trust fund amounts comply with the reporting requirements of 10 CFR 50.75(f) in that the amount of funds reported are those that were accumulated as of January 31, 2016.
(c) A 2% annual real rate of return is used as allowed by 10 CFR 50.75(e)(1)(i).
(d) For purposes of this report, permanent termination of operations (shutdown) is expected on October 17, 2046.
ATTACHMENT 3 Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 2
ATTACHMENT 3 Radiological Decommissioning Funding Assurance Report for Braidwood Station, Unit 2 (January 31, 2016 dollars, thousands) 1 Formula cost amount per 10 CFR 50.75(c) $518,659 2 Site-specific cost amount per 10 CFR 50.75(b)(4) N/A 3 Site-specific cost amount per 10 CFR 72.30(b) $4,816 (a) 4 The amount of decommissioning trust funds accumulated as of January 31, 2016 $316,857 (b) 5 Schedule of the annual amounts remaining to be collected. $0 6 Assumptions used regarding rates of escalation, earnings, and other factors used in funding projections 2% (c) 7 There are no contracts relied upon pursuant to 10 CFR 50.75(e)(1)(v).
8 Financial assurance for decommissioning is provided by the prepayment method, coupled with an external trust fund, in accordance with 10 CFR 50.75(e)(1)(i) and 10 CFR 72.30(e)(1).
9 There are no material changes to the trust fund agreements.
(a) This is the site-specific cost estimate for ISFSI radiological decommissioning that was previously provided in a letter from Patrick R. Simpson (EGC) to U. S. NRC, dated March 31, 2015 ("Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations"). The costs have been escalated from 2014 dollars in the letter to January 31, 2016 using a unit specific escalation rate. No other changes have been made to the decommissioning funding plan in the March 31, 2015 letter.
(b) The trust fund amount is the amount allocated for Radiological Decommissioning only. EGC has no past-due tax payments owed on the decommissioning trust fund activities as of January 31, 2016. Periodic payments of estimated income taxes are made by EGC during the year on a quarterly basis, and EGC subsequently obtains reimbursement from the trust funds on a periodic basis, when the funds are sufficient to demonstrate minimum funding assurance. The trust fund amounts comply with the reporting requirements of 10 CFR 50.75(f) in that the amount of funds reported are those that were accumulated as of January 31, 2016.
(c) A 2% annual real rate of return is used as allowed by 10 CFR 50.75(e)(1)(i).
(d) For purposes of this report, permanent termination of operations (shutdown) is expected on December 18, 2047.
ATTACHMENT 4 Radiological Decommissioning Funding Assurance Report for Byron Station, Unit 2
ATTACHMENT 4 Radiological Decommissioning Funding Assurance Report for Byron Station, Unit 2 (January 31, 2016 dollars, thousands) 1 Formula cost amount per 10 CFR 50.75(c) $518,659 2 Site-specific cost amount per 10 CFR 50.75(b)(4) N/A 3 Site-specific cost amount per 10 CFR 72.30(b) $4,688 (a) 4 The amount of decommissioning trust funds accumulated as of January 31, 2016 $309,864 (b) 5 Schedule of the annual amounts remaining to be collected. $0 6 Assumptions used regarding rates of escalation, earnings, and other factors used in funding projections 2% (c) 7 There are no contracts relied upon pursuant to 10 CFR 50.75(e)(1)(v).
8 Financial assurance for decommissioning is provided by the prepayment method, coupled with an external trust fund, in accordance with 10 CFR 50.75(e)(1)(i) and 10 CFR 72.30(e)(1).
9 There are no material changes to the trust fund agreements.
(a) This is the site-specific cost estimate for ISFSI radiological decommissioning that was previously provided in a letter from Patrick R. Simpson (EGC) to U. S. NRC, dated March 31, 2015 ("Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations"). The costs have been escalated from 2014 dollars in the letter to January 31, 2016 using a unit specific escalation rate. No other changes have been made to the decommissioning funding plan in the March 31, 2015 letter.
(b) The trust fund amount is the amount allocated for Radiological Decommissioning only. EGC has no past-due tax payments owed on the decommissioning trust fund activities as of January 31, 2016. Periodic payments of estimated income taxes are made by EGC during the year on a quarterly basis, and EGC subsequently obtains reimbursement from the trust funds on a periodic basis, when the funds are sufficient to demonstrate minimum funding assurance. The trust fund amounts comply with the reporting requirements of 10 CFR 50.75(f) in that the amount of funds reported are those that were accumulated as of January 31, 2016.
(c) A 2% annual real rate of return is used as allowed by 10 CFR 50.75(e)(1)(i).
(d) For purposes of this report, permanent termination of operations (shutdown) is expected on November 6, 2046.