Letter Sequence Response to RAI |
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Results
Other: ML13212A367, ML14050A304, ML14071A620, ML14072A369, ML14092A346, ML14177A430, ML14238A691, ML15098A181, ML15106A736, RS-14-183, Updated Responses to NRC Set 14 Requests for Additional Information, Related License Renewal Application, RS-14-249, Results of Detailed Review Performed in Response to Request 1 of NRC RAI B.2.1.7-7 from Set 17, Related to License Renewal Application
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MONTHYEARML13212A3672013-08-12012 August 2013 Plan for the Aging Management Program Regulatory Audits Regarding the Byron and Braidwood Nuclear Stations License Renewal Application Review (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: Other ML13281A5742013-11-25025 November 2013 Requests for Additional Information for the Review of the Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, License Renewal Application - Aging Management, Set 3 (TAC Nos. MF1879, MF1880, MF1881, and MF1882 Project stage: RAI ML13303B4632013-11-25025 November 2013 Summary of Telephone Conference Call Held on October 22, 2013, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning RAI Set 3 for the Byron-Braidwood LRA Project stage: RAI ML13281A5692013-12-12012 December 2013 Request for Additional Information for the Review of the Byron Nuclear Station Units 1 and 2, and the Braidwood Nuclear Station Units 1 and 2, LRA - Aging Management, Set 4 Project stage: RAI ML13282A3692013-12-13013 December 2013 Requests for Additional Information for the Review of the Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, License Renewal Application - Aging Management, Set 2 (TAC Nos. MF1879, MF1880, MF1881, and MF1882 Project stage: RAI RS-13-273, Responses to NRC Requests for Additional Information, Set 3, Dated November 25, 2013, Related to the License Renewal Application2013-12-17017 December 2013 Responses to NRC Requests for Additional Information, Set 3, Dated November 25, 2013, Related to the License Renewal Application Project stage: Response to RAI RS-13-274, Response to NRC Requests for Additional Information, Set 5, Dated November 22, 2013, Related to License Renewal Application2013-12-19019 December 2013 Response to NRC Requests for Additional Information, Set 5, Dated November 22, 2013, Related to License Renewal Application Project stage: Response to RAI ML13317A0752014-01-13013 January 2014 Requests for Additional Information for Review of Byron, Units 1 & 2, and Braidwood, Units 1 & 2, License Renewal Applications, Set 6 Project stage: RAI RS-14-003, Bryon, Units 1 and 2, Response to NRC Requests for Additional Information, Set 2, Dated December 13, 2013, Related to the License Renewal Application2014-01-13013 January 2014 Bryon, Units 1 and 2, Response to NRC Requests for Additional Information, Set 2, Dated December 13, 2013, Related to the License Renewal Application Project stage: Response to RAI ML14007A6582014-01-22022 January 2014 Requests for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 9 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML13309A9322014-01-23023 January 2014 Summary of Telephone Conference Call Held on October 31, 2013, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Byron Station and Braid Project stage: Draft RAI RS-14-030, Response to NRC Requests for Additional Information, Set 6, Dated January 13, 2014, Related to License Renewal Application2014-02-0404 February 2014 Response to NRC Requests for Additional Information, Set 6, Dated January 13, 2014, Related to License Renewal Application Project stage: Response to RAI ML14006A0212014-02-0606 February 2014 Requests for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application- Aging Management, Set 8 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14023A5642014-02-0707 February 2014 RAI for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 13 (TAC MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14030A5962014-02-10010 February 2014 Requests for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 12 (TAC MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14007A6032014-02-18018 February 2014 Request for Additional Information for the Review of the Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, LRA - Aging Management - Set 17 Project stage: RAI ML14035A1892014-02-20020 February 2014 Summary of Telephone Conference Call Held on January 30, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Draft Request for Additional Information Pertaining to the Byron Station and Braidw Project stage: Draft RAI ML14035A5342014-02-20020 February 2014 January 22, 2014, Summary of Telephone Conference Call Held Between NRC and Exelon Generation Company, Llc., Concerning Draft Requests for Additional Information Pertaining to the Byron Station and Braidwood Station, License Renewal Applica Project stage: Draft RAI RS-14-051, Response to NRC Requests for Additional Information, Set 8, Dated February 6, 2014 Related to the License Renewal Application2014-02-27027 February 2014 Response to NRC Requests for Additional Information, Set 8, Dated February 6, 2014 Related to the License Renewal Application Project stage: Response to RAI ML14063A4952014-03-0404 March 2014 Units 1 & 2, Response to NRC Requests for Additional Information, Set 13, Dated February 7, 2014 Re License Renewal Application Project stage: Response to RAI ML14050A1672014-03-0404 March 2014 Summary of Telephone Conference Call on January 23, 2014, Between U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning RAI Set 11, for Byron-Braidwood License Renewal Application (TAC Nos. MF1879, MF1880, MF1881 Project stage: RAI ML14036A3102014-03-0404 March 2014 Summary of Telephone Conference Call Held on January 28, 2014, Between NRC and Exelon, Concerning RAI Set 10, for the Byron and Braidwood Station, LRA Project stage: RAI ML14051A4312014-03-0404 March 2014 Summary of Telephone Conferene Call Held on January 29, 2014, Between the NRC and Exelon Generating Company, Llc., Concerning RAI Set 10, for the Byron and Braidwood Station License Renewal Application (TAC Nos. MF1879, MF1880, MF1881, and Project stage: RAI ML14051A4282014-03-0606 March 2014 January 13, 2014, Summary of Telephone Conference Call Held Between the NRC and Exelon RAI Set 8, for the Byron and Braidwood Station LRA Project stage: RAI ML14050A0812014-03-0707 March 2014 Correction to Request for Additional Information B.2.1.10-1, Letter Dated February 7, 2014, for the Review of the Byron Station and Braidwood Station, Units 1 and 2, LRA Set 13 Project stage: RAI ML14058B1802014-03-11011 March 2014 Summary of Telephone Conference Call on February 18, 2014, Between U.S. Nuclear Regulatory Commission & Exelon Generation Company, LLC Concerning Draft Request for Additional Information Regarding Byron & Braidwood Stations, License Renewal Project stage: Draft RAI ML14064A4032014-03-11011 March 2014 Summary of Telephone Conference Call on February 27, 2014, Between U.S. Nuclear Regulatory Commission & Exelon Generation Company, LLC Concerning Draft Request for Additional Information Re Byron Station & Braidwood Station License Renewal Project stage: Draft RAI ML14064A3912014-03-11011 March 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 15 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14071A6202014-03-13013 March 2014 Aging Management Programs Audit Report Regarding the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (Tac Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: Other ML14072A3692014-03-13013 March 2014 AMP Audit Enclosure (3) Project stage: Other ML14050A3042014-03-14014 March 2014 Scoping and Screening Methodology Audit Report Regarding the Byron Station, and Braidwood Station, Units 1 and 2, LRA Project stage: Other ML14058B1822014-03-18018 March 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 14 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14051A5032014-03-20020 March 2014 Request for Additional Information for the Review of the Byron Nuclear Station Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, License Renewal Application - Set 17 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI RS-14-084, Responses to NRC Requests for Additional Information, Set 10, Dated February 26, 2014 Related to the License Renewal Application2014-03-28028 March 2014 Responses to NRC Requests for Additional Information, Set 10, Dated February 26, 2014 Related to the License Renewal Application Project stage: Response to RAI ML14084A3352014-04-0303 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 16 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14073A7052014-04-0303 April 2014 Summary of Telephone Conference Call Held on February 12, 2014, Between the NRC and Exelon, Concerning Drais Pertaining to the Byron and Braidwood Station, LRA Project stage: RAI ML14092A3462014-04-0707 April 2014 Project Manager Change for the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: Other ML14092A2612014-04-0707 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 20 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14084A4882014-04-0707 April 2014 03/04/2014 Summary of Telephone Conference Call Held Between NRC and Exelon Generation Company, LLC, Concerning Draft Request for Additional Information Pertaining to the Byron and Braidwood License Renewal Application Set 16 Project stage: Draft RAI ML14094A3662014-04-0808 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 19 Project stage: RAI ML14093B2472014-04-10010 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 18 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14099A4852014-04-17017 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 & 2, and Braidwood Station, Units 1 & 2, License Renewal Application, Set 21, (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14099A4932014-04-22022 April 2014 April 03, 2014 Summary of Telephone Conference Call Held Between NRC and Exelon Generation Co., LLC, Concerning Draft Request for Additional Information, Set 21, Pertaining to Byron, Units 1 & 2, Braidwood, Units 1 & 2, License Renewal Appl Project stage: Draft RAI ML14111A1182014-04-24024 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 22 Project stage: RAI ML14107A0772014-04-25025 April 2014 Summary of Telephone Conference Call Held on April 9, 2014, Between the U.S. Nuclear Regulatory Commission & Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 23, Pertaining to the Byron Station & Braid Project stage: Draft RAI ML14107A2262014-05-14014 May 2014 Summary of Telephone Conference Call Held on March 26, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 21, Pertaining to the Byron Station and Project stage: Draft RAI ML14092A4402014-05-14014 May 2014 Summary of Telephone Conference Call Held on March 19, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 18, Pertaining to the Byron Station and Project stage: Draft RAI ML14112A4182014-05-14014 May 2014 Summary of Telephone Conference Call Held on April 10, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 22, Pertaining to the Byron Station and Project stage: Draft RAI ML14094A4252014-05-14014 May 2014 Summary of Telephone Conference Call Held on April 1, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 19, Pertaining to the Byron Station and B Project stage: Draft RAI ML14129A3392014-05-14014 May 2014 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance 2014-03-11
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Category:Letter type:RS
MONTHYEARRS-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 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 2024-09-13
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-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 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition 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-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-097, 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-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-117, Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d)2021-12-0909 December 2021 Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d) ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink2021-08-0202 August 2021 License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-057, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2021-05-27027 May 2021 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-20-130, License Amendment Request - Proposed Changes to Byron Emergency Plan for Post-Shutdown and Permanently Defueled Condition2020-11-0202 November 2020 License Amendment Request - Proposed Changes to Byron Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML20303A3252020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 2 of 5 ML20303A3272020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 4 of 5 ML20303A3262020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 3 of 5 ML20303A3232020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 1 of 5 RS-20-129, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 52020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 5 RS-20-114, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2020-09-24024 September 2020 License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition RS-20-089, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2020-07-15015 July 2020 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-20-068, Application to Revise Technical Specifications 3.8.1, AC Sources-Operating2020-06-26026 June 2020 Application to Revise Technical Specifications 3.8.1, AC Sources-Operating RS-20-058, Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-16016 April 2020 Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections RS-20-044, Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-0606 April 2020 Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections ML20063L2822020-02-28028 February 2020 Application of Westinghouse Full Spectrum LOCA Evaluation Model RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2020-02-28028 February 2020 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues2020-02-0606 February 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions2019-12-0909 December 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions RS-19-078, License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies.2019-09-24024 September 2019 License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies. RS-19-082, License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS)2019-09-11011 September 2019 License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS) RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) RS-19-081, Supplement to Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2019-08-0909 August 2019 Supplement to Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements RS-19-018, Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times2019-02-14014 February 2019 Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times RS-19-008, Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2019-01-31031 January 2019 Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process RS-18-149, Supplemental Information Related to License Amendment Request for a One-Time Extension to Technical Specification 3.8. 1, AC Sources-Operating, Required Action A.22018-12-21021 December 2018 Supplemental Information Related to License Amendment Request for a One-Time Extension to Technical Specification 3.8. 1, AC Sources-Operating, Required Action A.2 RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO 2024-06-04
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A lMichael R Gallagher Gen ratonVice President. License Renewal LA o G n r to Exelon Nuclear 200 Exelon Way Kennett Square. PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.coni rnichaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 RS-14-336 November 22, 2014 U. S. Nuclear Regulatory Commission Attention: 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:
Supplemental Commitment related to the October 31, 2014 Response to NRC Request for Additional Information, Set 42, dated October 10, 2014, related to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, License Renewal Application
References:
- 1. Letter from Michael P. Gallagher, Exelon Generation Company LLC (Exelon) to NRC Document Control Desk, dated May 29, 2013, "Application for Renewed Operating Licenses"
- 2. Letter from Lindsay R. Robinson, US NRC to Michael P. Gallagher, Exelon, dated October 10, 2014, "Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 42 (TAC NOS. MF1 879, MF1 880, MF1 881, and MF1882)"
- 3. Letter from Michael P. Gallagher, Exelon to US NRC, dated October 31, 2014, "Response to NRC Request for Additional Information, Set 42, dated October 10, 2014, related to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, License Renewal Application In Reference 1, Exelon Generation Company, LLC (Exelon) submitted the License Renewal Application (LRA) for the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (BBS). In Reference 2, the NRC requested additional information (RAI) to support staff review of the LRA. In Reference 3, Exelon responded to the Reference 2, Set 42 RAI.
November 22, 2014 U.S. Nuclear Regulatory Commission Page 2 Based on NRC feedback resulting from staff review of the Reference 3 response, Exelon is supplementing the earlier Set 42 response with two additional commitments, for Braidwood only, related to the Flux Thimble Tube Inspection aging management program.
Enclosure A contains a description of and basis for the Flux Thimble Tube Inspection aging management program supplemental commitments.
Enclosure B contains updates to sections of the LRA (except for the License Renewal Commitment List) affected by the response.
Enclosure C provides an update to the License Renewal Commitment List (LRA Appendix A, Section A.5). There are no other new or revised regulatory commitments contained in this letter.
If you have any questions, please contact Mr. Al Fulvio, Manager, Exelon License Renewal, at 610-765-5936.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on / 2-i. "20P" Respectfully, Michael P. Gallagher Vice President - License Renewal Projects Exelon Generation Company, LLC
Enclosures:
A. Supplemental Commitments Related to Request for Additional Information RAI B.2.1.24-1a B. Update to Affected LRA Sections C. License Renewal Commitment List Changes cc: Regional Administrator - NRC Region III NRC Project Manager (Safety Review), NRR-DLR NRC Project Manager (Environmental Review), NRR-DLR NRC Senior Resident Inspector, Braidwood Station NRC Senior Resident Inspector, Byron Station NRC Project Manager, NRR-DORL-Braidwood and Byron Stations Illinois Emergency Management Agency - Division of Nuclear Safety
RS-14-336 Enclosure A Page 1 of 6 Enclosure A Byron and Braidwood (BBS), Units 1 and 2 License Renewal Application Supplemental Commitment Related to Request for Additional Information RAI B.2.1.24-1 a
RS-14-336 Enclosure A Page 2 of 6
==
Introduction:==
During recent refueling outages at Braidwood Station, Units 1 and 2, difficulties in obtaining eddy current testing data as required by the Flux Thimble Tube Inspection program have been experienced. This issue has been entered into the corrective action program for resolution. To address this issue a multi-discipline team has been established to determine the cause of the issue and has developed actions to prevent future recurrence. A summary of the planned corrective actions to address this issue was provided in the response to RAI B.2.1.24-1 a. Based on these corrective actions there is confidence that the issue will be resolved and the required data obtained. Furthermore, the program currently accounts for situations when eddy current testing data cannot be obtained by replacing or removing from service flux thimble tubes which cannot be shown by analysis to be satisfactory for continued service. This is consistent with the recommendations in GALL Report AMP XI.M37, Element 7.
To provide further assurance that the intended function of the flux thimble tubes (i.e., reactor coolant pressure boundary) will be maintained if future difficulties in obtaining eddy current testing data are encountered at Braidwood Station, the Flux Thimble Tube Inspection (B.2.1.24) aging management program will be enhanced as follows:
- 1. For Braidwood Unit 1:
- a. The 17 Braidwood Station, Unit 1 flux thimble tubes that exhibited indications of wear during eddy current testing performed during Al R15 Refueling Outage (Fall 2010),
will be replaced or removed from service during Al R18 Refueling Outage (Spring 2015), unless eddy current data is obtained as required by the Flux Thimble Tube Inspection program. (Flux thimble tubes 1 (J-8), 8 (K-6), 9 (H-1 1), 12 (E-9), 14 (H-4),
18 (L-11), 19 (L-5), 21 (E-11), 23 (D-10), 36 (J-14), 37 (P-9), 41 (N-4), 44 (R-8), 45 (N-13), 48 (P-4), 54 (A-11), 55 (N-14))
- b. The remaining Braidwood Station, Unit 1 flux thimble tubes, not replaced during Al R1 8, will be replaced or removed from service during Al R1 9 Refueling Outage (Fall 2016), unless eddy current data is obtained as required by the Flux Thimble Inspection Tube program.
- c. Following Al R19, any Braidwood Station, Unit 1 flux thimble tube will be replaced every three (3) refueling outages or removed from service if eddy current data is not obtained in accordance with the Flux Thimble Tube Inspection program.
- 2. For Braidwood Unit 2:
- a. The 29 Braidwood Station, Unit 2 flux thimble tubes that exhibited indications of wear during eddy current testing performed during A2R1 5 Refueling Outage (Spring 2011) and not replaced during A2R17 Refueling Outage (Spring 2014), will be replaced or removed from service during A2R18 Refueling Outage (Fall 2015), unless eddy current data is obtained as required by the Flux Thimble Tube Inspection program.
(Flux thimble tubes 1 (J-8), 4 (H-6), 5 (F-8), 6 (J-10), 7 (F-7), 9 (H-1 1), 10 (L-8), 11 (G-5), 18 (L-11), 22 (K-12), 23 (D-10), 24 (H-13), 25 (N-8), 26 (H-3), 27 (C-8), 29 (N-6), 32 (L-13), 33 (C-5), 34 (H-2), 36 (J-14), 37 (P-9), 40 (F-14), 41 (N-4), 42 (D-3), 45 (N-13), 46 (J-l), 50 (R-6), 52 (L-15), 56 (N-2))
RS-1 4-336 Enclosure A Page 3 of 6
- b. The remaining Braidwood Station, Unit 2 flux thimble tubes, not replaced during A2R17 or A2R18, will be replaced or removed from service during A2R19 Refueling Outage (Spring 2017), unless eddy current data is obtained as required by the Flux Thimble Inspection Tube program.
- c. Following A2R1 9, any Braidwood Station, Unit 2 flux thimble tube will be replaced every three (3) refueling outages or removed from service if eddy current data is not obtained in accordance with the Flux Thimble Tube Inspection program.
The enhancement for both Braidwood Unit 1 and Braidwood Unit 2 will ensure that the currently installed flux thimble tubes will be conservatively replaced or removed from service if eddy current testing data is not obtained for the individual tubes as required by the program. In addition, part (c) of the enhancements ensures that if difficulties in obtaining eddy current testing data are encountered in the future, then the tubes for which eddy current testing data is not obtained will be replaced such that the intended function of the flux thimble tubes is maintained.
The following discussion provides the basis for the replacement frequency for flux thimble tubes if eddy current testing data is not obtained as required by the program. In addition, a summary of the basis for continued operation of the currently installed flux thimble tubes to the next refueling outage (for tubes that had indications of wear in Al R15 or A2R15) or to the subsequent refueling outage (for tubes that did not have indications of wear in Al R1 5 or A2R15) is provided.
Justification for Replacement Frequency:
The response to RAI B.2.1.24-1a is supplemented to enhance the Flux Thimble Tube Inspection (B.2.1.24) aging management program. The enhancement to the program will require any Braidwood Station flux thimble tube be replaced every three (3) refueling outages or removed from service if eddy current data is not obtained in accordance with the Flux Thimble Tube Inspection program. To determine the appropriate replacement frequency, the historic eddy current testing data over the first 15 refueling cycles for both units, when eddy current testing data was successfully obtained in accordance with the program requirements, was reviewed. Based on this review, none of the 116 flux thimble tubes at Braidwood Units 1 and 2 were required to be replaced due to age-related degradation (i.e., wear due to flow induced vibration) in less than four (4) refueling cycles and in fact, the majority of the original flux thimble tubes have remained in service through the first 15 refueling cycles. Therefore, it is concluded that replacements of flux thimble tubes on a three (3) refueling cycle frequency, if eddy current testing data is not obtained in accordance with the Flux Thimble Tube Inspection program, is very conservative and will ensure that flux thimble tubes are replaced well before age-related degradation challenges the intended function of the flux thimble tubes.
During recent refueling outages, indications of "higher than expected wear" have been entered into the corrective action program. The issue of higher than expected wear was addressed in the response to RAI B.2.1.24-1, request 1, in Exelon letter RS-14-165, dated June 9, 2014. As explained in the response, the higher than expected wear was measured after a flux thimble tube had been in service for only one (1) cycle of operation. Although
RS-14-336 Enclosure A Page 4 of 6 this issue was characterized as "higher than expected wear," as described in WCAP-1 2866, Bottom Mounted InstrumentationFlux Thimble Tube Wear, the highest wear rates are experienced during the first cycle of operation and, therefore, higher wear rates during the initial cycle of a newly installed flux thimble tube are expected. The operating experience evaluated in WCAP-1 2866 indicates that the wear rate decreases substantially with continued service.
In each case where flux thimble tube locations were identified as having higher than expected wear after only one (1) cycle of operation, the previously installed flux thimble tube had remained in service for 13 cycles before being replaced. Subsequent eddy current data (second cycle data) was obtained on some of these and confirmed that wear had stabilized and the wear rate had decreased significantly, consistent with the operating experience evaluated in WCAP-12866. Therefore, a replacement frequency of three (3) refueling outages is sufficient to ensure flux thimble tube integrity is maintained. In one instance, a flux thimble tube experienced a one-time increase in wear, greater than its normal wear.
The increased wear rate (11 % per cycle) was not excessive and subsequent eddy current data confirmed the wear rate returned to normal. In addition, this flux thimble tube remained in service for 16 cycles until replacement was required. Therefore, a replacement frequency of three (3) refueling outages is sufficient to ensure flux thimble tube integrity is maintained.
In conclusion, a three (3) refueling cycle replacement frequency is conservative even when the evaluation accounts for instances of "higher than expected wear" that have been experienced at Braidwood Station.
Tube Replacements to be Performed Next Refueling Outaqe (Unit 1 - Spring 2015; Unit 2 Fall 2015) if ECT Data is not Obtained:
To address the flux thimble tubes that are currently in service, the program is enhanced to require that tubes that exhibited indications of wear during eddy current testing performed during the 15 1h refueling outage at both Unit 1 and Unit 2, will be replaced or removed from service during the next scheduled refueling outage, unless eddy current data is obtained as required by the Flux Thimble Tube Inspection program. For Unit 1, 17 flux thimble tubes exhibited indications of wear between 17% to 42% during eddy current testing performed during the 15 1h refueling outage (Fall 2010). These flux thimble tubes will be replaced or removed from service in the Spring 2015 refueling outage unless eddy current data is obtained as required by the Flux Thimble Tube Inspection program. For Unit 2, 29 flux thimble tubes exhibited indications of wear between 12% to 44% during eddy current testing performed during the 15 th refueling outage (Spring 2011). These flux thimble tubes will be replaced or removed from service in the Fall 2015 refueling outage unless eddy current data is obtained as required by the Flux Thimble Tube Inspection program. Five (5) other flux thimble tubes at Unit 2 also exhibited indications of wear during eddy current testing performed during the 15 1h refueling outage and have subsequently been replaced, as described below. Since existing analysis has determined that a flux thimble tube is capable of performing its intended function with up to 85% wall loss, the indications of wear on the flux thimble tubes that remain in service (between 17% and 42% on Unit 1 and between 12% and 44% on Unit 2) are well within acceptable parameters.
During the most recent refueling outages for both Unit 1 and Unit 2, an evaluation was completed to determine if the installed flux thimble tubes could be shown to be satisfactory for continued operation based on conservative projections utilizing historic testing data. Flux thimble tubes that could not be analytically shown to be satisfactory for continued service
RS-14-336 Enclosure A Page 5 of 6 were replaced or removed from service. At Braidwood Unit 1, two (2) flux thimble tubes were removed from service by capping during the most recent refueling outage. These two (2) flux thimble tubes will be replaced during the upcoming Spring 2015 refueling outage. At Braidwood Unit 2, seven (7) flux thimble tubes were replaced during the most recent refueling outage (Spring 2014). Although five (5) of these seven (7) flux thimble tubes exhibited indications of wear during eddy current testing performed during the 15 th refueling outage, these five (5) tubes will not be replaced or removed from service in the upcoming Fall 2015 refueling outage since, as discussed above, a review of operating experience demonstrates that newly installed flux thimble tubes can remain in service more than three (3) refueling outages. These five (5) flux thimble tubes will be replaced during the Fall 2018 refueling outage if eddy current data is not obtained in accordance with a three (3) refueling cycle replacement frequency specified in part (c) of the enhancements.
Tube Replacements to be Performed in Subsequent Refueling Outages (Unit 1 - Fall 2016; Unit 2 - Spring 2017 or Fall 2018) if ECT Data is not Obtained:
To address the remaining flux thimble tubes that did not exhibit indications of wear during eddy current testing performed during the 15 th refueling outage at both Unit 1 and Unit 2, the program will require tube replacement in subsequent refueling outages (Fall 2016 for Unit 1 and Spring 2017 for Unit 2) unless eddy current data is obtained as required by the Flux Thimble Tube Inspection program.
At Braidwood Unit 1, the remaining 41 flux thimble tubes that did not exhibit indications of wear in A1R15 refueling outage (Fall 2010) will be replaced or removed from service in the subsequent refueling outage (Fall 2016) unless eddy current data is obtained as required by the Flux Thimble Tube Inspection program. Of these 41 flux thimble tubes, 37 had each been in service for six (6) or more refueling cycles when eddy current testing was performed in the 15 1h refueling outage. There is reasonable assurance that the intended function of these tubes will be maintained through the Fall 2016 refueling outage since these tubes exhibited no indications of wear after being in service for six (6) or more refueling cycles.
The remaining four (4) flux thimble tubes had been replaced in the prior outage due to issues other than wear. The operating experience for these four (4) flux thimble tubes indicates that significant wear has not occurred at these locations prior to the replacement of the tube. Based on this it is concluded that the 41 flux thimble tubes that will not be replaced or removed from service in the upcoming Spring 2015 refueling outage are satisfactory for continued service until the following refueling outage.
At Braidwood Unit 2, the remaining 29 flux thimble tubes will be replaced or removed from service in subsequent refueling outages (Spring 2017 or Fall 2018) unless eddy current data is obtained as required by the Flux Thimble Tube Inspection program. Of these 29 flux thimble tubes, seven (7) were replaced in the most recent refueling outage (Spring 2014).
As discussed above, a review of operating experience demonstrates that newly installed flux thimble tubes remain satisfactory for continued service for more than three (3) refueling outages and, therefore, these seven (7) flux thimble tubes will be replaced in the Fall 2018 refueling outage in accordance with part (c) of the enhancements. The remaining 22 flux thimble tubes had each been in service for six (6) or more refueling cycles when eddy current testing was performed in the 15 1h refueling outage. There is reasonable assurance that the intended function of these tubes will be maintained to the Spring 2017 refueling outage since these tubes exhibited no indications of wear after being in service for six (6) or more refueling cycles.
RS-14-336 Enclosure A Page 6 of 6
==
Conclusion:==
In conclusion, with the enhancements to the Flux Thimble Tube Inspection (B.2.1.24) aging management program contained in this submittal, there is reasonable assurance that the intended function of Braidwood Station, Units 1 and 2 flux thimble tubes will be maintained if future difficulties in obtaining eddy current testing data is experienced. Replacement of flux thimble tubes when eddy current testing data is not obtained is consistent with the guidance provided in GALL Report AMP XI.M37.
RS-14-336 Enclosure B Page 1 of 5 Enclosure B Byron and Braidwood Stations, Units 1 and 2 License Renewal Application (LRA) Updates Note: To facilitate understanding, portions of the original LRA have been repeated in this Enclosure, with revisions indicated. Existing LRA text is shown in normal font. Changes are highlighted with bolded italicsfor inserted text.
RS-14-336 Enclosure B Page 2 of 5 As a result of the response provided in Enclosure A of this letter, LRA Appendix A, Section A. 1.1, page A-6 and A.2.1.24, page A-28, are revised as shown below. Additions are indicated with bolded italics.
A.1.1 NUREG-1801 Chapter XI Aging Management Programs The Byron and Braidwood NUREG-1801 Chapter XI Aging Management Programs (AMPs) are described in this section. The AMPs are either existing, existing with enhancements (enhanced) or new.
The following list reflects the status of these programs at the time of the License Renewal Application (LRA) submittal. Commitments for program additions and enhancements are identified in the Appendix A.5 License Renewal Commitment List.
- 24. Flux Thimble Tube Inspection (Section A.2.1.24) [Existing - Requires Enhancement]
A.2.1.24 Flux Thimble Tube Inspection The Flux Thimble Tube Inspection aging management program is an existing condition monitoring program that manages the loss of material in flux thimble tubes due to wear (i.e., wall thinning). Flux thimble tubes, which provide a path for the in-core neutron flux monitoring system detectors, establish part of the reactor coolant pressure boundary and are subject to flow-induced fretting which causes wear. The program uses the non-destructive examination methodology of eddy current testing to periodically inspect the full length of all flux thimble tubes, which encompasses the path from the reactor vessel instrument nozzle to the fuel assembly instrument guide.
The results of the periodic eddy current testing are evaluated and trended to determine if corrective actions are required or if the inspection frequency needs to be changed to ensure reactor coolant pressure boundary integrity is maintained. Corrective actions include flux thimble tube limited repositioning (one-time), replacement, or isolation (removal from service).
The Flux Thimble Tube Inspection program implements the recommendations of NRC IE Bulletin 88-09, "Thimble Tube Thinning in Westinghouse Reactors." This existing aging management program will continue to be implemented during the period of extended operation.
The Flux Thimble Tube Inspection aging managementprogram will be enhanced as follows:
- 1. For Braidwood Unit 1:
- a. The 17 Braidwood Station, Unit 1 flux thimble tubes that exhibited indicationsof wear during eddy current testing performed during A 1R15 Refueling Outage (Fall2010), will be replaced or removed from
RS-14-336 Enclosure B Page 3 of 5 service during A 1R18 Refueling Outage (Spring2015), unless eddy current datais obtainedas requiredby the Flux Thimble Tube Inspection program. (Flux thimble tubes 1 (J-8), 8 (K-6), 9 (H-11), 12 (E-9), 14 (H-4), 18 (L- 11), 19 (L-5), 21 (E- 11), 23 (D-10), 36 (J-14), 37 (P-9), 41 (N-4), 44 (R-8), 45 (N-13), 48 (P-4), 54 (A- 11), 55 (N-14))
- b. The remainingBraidwood Station, Unit 1 flux thimble tubes, not replacedduring A 1R18, will be replaced or removed from service duringA 1R19 Refueling Outage (Fail2016), unless eddy currentdata is obtainedas requiredby the Flux Thimble Inspection Tube program.
- c. Following A 1R19, any Braidwood Station, Unit 1 flux thimble tube will be replacedevery three (3) refueling outages or removed from service if eddy currentdata is not obtainedin accordancewith the Flux Thimble Tube Inspection program.
- 2. For Braidwood Unit 2:
- a. The 29 BraidwoodStation, Unit 2 flux thimble tubes that exhibited indicationsof wear during eddy currenttesting performed during A2R15 Refueling Outage (Spring 2011) and not replaced during A2R17 Refueling Outage (Spring2014), will be replaced or removed from service during A2R18 Refueling Outage (Fail2015), unless eddy current data is obtainedas requiredby the Flux Thimble Tube Inspection program. (Flux thimble tubes 1 (J-8), 4 (H-6), 5 (F-8), 6 (J-10), 7(F-7), 9(H-11), 10(L-8), 11 (G-5), 18(L-11), 22(K-12), 23(D-10),
24 (H-13), 25 (N-8), 26 (H-3), 27 (C-8), 29 (N-6), 32 (L-13), 33 (C-5), 34 (H-2), 36 (J-14), 37 (P-9), 40 (F-14), 41 (N-4), 42 (D-3), 45 (N-13), 46 (J-1), 50 (R-6), 52 (L- 15), 56 (N-2))
- b. The remaining BraidwoodStation, Unit 2 flux thimble tubes, not replaced duringA2R17 or A2R18, will be replacedor removed from service during A2R19 Refueling Outage (Spring 2017), unless eddy current data is obtainedas requiredby the Flux Thimble Inspection Tube program.
- c. Following A2R19, any Braidwood Station, Unit 2 flux thimble tube will be replaced every three (3) refueling outages or removed from service if eddy current data is not obtainedin accordance with the Flux Thimble Tube Inspection program.
These enhancements will be implemented in accordance with the schedule specified in the enhancement.
RS-14-336 Enclosure B Page 4 of 5 As a result of the response provided in Enclosure A of this letter, LRA Appendix B, Sections B.1.5, page B-10 and B.2.1.24, page B-153, are revised as shown below. Additions are indicated with bolded italics; deletions are shown with stiketlweughs.
B.1.5 NUREG-1801 CHAPTER XI AGING MANAGEMENT PROGRAMS The following NUREG-1801 Chapter Xl AMPs are described in Section B.2 of this appendix as indicated. Programs are identified as either existing or new to Byron and Braidwood. All programs are or will be consistent with programs discussed in NUREG-1801.
- 24. Flux Thimble Tube Inspection (Section B.2.1.24) [Existing - Requires Enhancement]
B.2.1.24 Flux Thimble Tube Inspection Enhancements Nee.
The following enhancements will be implemented in the following program elements:
- 1. For Braidwood Unit 1:
- a. The 17 Braidwood Station, Unit 1 flux thimble tubes that exhibited indicationsof wear during eddy current testing performed during A 1R15 Refueling Outage (Fall2010), will be replaced or removed from service during A 1R18 Refueling Outage (Spring 2015), unless eddy current data is obtained as requiredby the Flux Thimble Tube Inspection program. (Flux thimble tubes 1 (J-8), 8 (K-6), 9 (H-11), 12 (E-9), 14 (H-4), 18 (L- 11), 19 (L-5), 21 (E-11), 23 (D-10), 36 (J-14), 37 (P-9), 41 (N-4), 44 (R-8), 45 (N-13), 48 (P-4), 54 (A-11), 55 (N- 14))
- b. The remaining BraidwoodStation, Unit 1 flux thimble tubes, not replacedduring A 1R18, will be replaced or removed from service during A 1R19 Refueling Outage (Fall2016), unless eddy currentdata is obtainedas requiredby the Flux Thimble Inspection Tube program.
- c. Following A 1R19, any Braidwood Station, Unit 1 flux thimble tube will be replaced every three (3) refueling outages or removed from service if eddy currentdata is not obtainedin accordancewith the Flux Thimble Tube Inspection program.
ProgramElement Affected: CorrectiveActions (Element 7)
RS-14-336 Enclosure B Page 5 of 5
- 2. For Braidwood Unit 2:
- a. The 29 BraidwoodStation, Unit 2 flux thimble tubes that exhibited indicationsof wear during eddy current testing performed during A2R15 Refueling Outage (Spring 2011) and not replaced during A2R17 Refueling Outage (Spring2014), will be replaced or removed from service during A2R18 Refueling Outage (Fall 2015), unless eddy current data is obtainedas requiredby the Flux Thimble Tube Inspection program. (Flux thimble tubes 1 (J-8), 4 (H-6), 5 (F-8), 6 (J-10), 7(F-7), 9 (H-11), 10 (L-8), 11 (G-5), 18 (L-11), 22 (K-12), 23 (D-10),
24 (H-13), 25 (N-8), 26 (H-3), 27 (C-8), 29 (N-6), 32 (L-13), 33 (C-5), 34 (H-2), 36 (J-14), 37 (P-9), 40 (F-14), 41 (N-4), 42 (D-3), 45 (N-13), 46 (J-1),
50 (R-6), 52 (L-15), 56 (N-2))
- b. The remainingBraidwood Station, Unit 2 flux thimble tubes, not replacedduring A2R17 or A2R 18, will be replacedor removed from service during A2R19 Refueling Outage (Spring 2017), unless eddy current data is obtainedas requiredby the Flux Thimble Inspection Tube program.
- c. Following A2R19, any Braidwood Station, Unit 2 flux thimble tube will be replaced every three (3) refueling outages or removed from service if eddy current data is not obtained in accordance with the Flux Thimble Tube Inspection program.
ProgramElement Affected: CorrectiveActions (Element 7)
RS-14-336 Enclosure C Page 1 of 3 Enclosure C Byron and Braidwood Stations (BBS) Units 1 and 2 License Renewal Commitment List Changes This Enclosure identifies commitments made in this document and is an update to the Byron and Braidwood Station (BBS) LRA Appendix A, Table A.5, License Renewal Commitment List.
Any other actions discussed in the submittal represent intended or planned actions and are described to the NRC for the NRC's information and are not regulatory commitments. Changes to the BBS LRA Appendix A, Table A.5 License Renewal Commitment List are as a result of this submittal.
Notes:
" To facilitate understanding, portions of the original License Renewal Commitment List have been repeated in this Enclosure, with revisions indicated.
" Existing LRA text is shown in normal font. Changes are highlighted with bold italics for inserted text and 64ikethweughs for deleted text.
RS-14-336 Enclosure C Page 2 of 3 As a result of the response provided in Enclosure A of this letter, LRA Appendix A, Table A.5 License Renewal Commitment List, Item 24 on page A-80, is revised as shown below. The correspondence that led to this commitment modification is listed in the "SOURCE" column. Any other actions described in this submittal represent intended or planned actions. They are described for the NRC's information and are not regulatory commitments. Additions are indicated with bolded italics; deletions are shown with 6',t ÷ ,*e,-ughs.
NO. PROGRAM OR COMMITMENT IMPLEMENTATION SOURCE TOPIC COMMITMENTSCHEDULE ____
24 Flux Thimble Tube Existing prog.rm is;creditod. Ongoing Section A.2.1.24 Inspection Flux Thimble Tube Inspection is an existing programthat will be Schedule for flux thimble Exelon letter enhanced as follows: tube replacement activities RS-14-336 identified in commitment. 11/22/2014
- 1. ForBraidwood Unit I (Note 3):
- a. The 17 Braidwood Station, Unit 1 flux thimble tubes that exhibited indicationsof wear during eddy current testing performed during A 1R15 Refueling Outage (Fall 2010), will be replaced or removed from service during A iR18 Refueling Outage (Spring2015), unless eddy current datais obtainedas requiredby the Flux Thimble Tube Inspection program. (Flux thimble tubes 1 (J-8), 8 (K-6), 9 (H-11), 12 (E-9), 14 (H-4), 18 (L- 11), 19 (L-5), 21 (E-1 1), 23 (D-10), 36 (J-14), 37 (P-9), 41 (N-4), 44 (R-8), 45 (N-13), 48 (P-4), 54 (A- 11), 55 (N-14))
- b. The remaining BraidwoodStation, Unit 1 flux thimble tubes, not replaced during A 11R18, will be replaced or removed from service during A 1R19 Refueling Outage (Fall2016), unless eddy current data is obtained as requiredby the Flux Thimble Inspection Tube program.
- c. Following A 1R19, any BraidwoodStation, Unit 1 flux thimble tube will be replacedevery three (3) refueling outages or removed from service if eddy currentdata is not obtainedin accordancewith the Flux Thimble Tube Inspection program.
RS-14-336 Enclosure C Page 3 of 3 NO. PROGRAM OR COMMITMENT IMPLEMENTATION SOURCE TOPIC SCHEDULE
- 2. For Braidwood Unit 2 (Note3):
- a. The 29 Braidwood Station, Unit 2 flux thimble tubes that exhibited indications of wear during eddy current testing performed during A2R15 Refueling Outage (Spring 2011) and not replaced during A2R17 Refueling Outage (Spring 2014), will be replaced or removed from service during A2R18 Refueling Outage (Fall2015),
unless eddy current data is obtainedas requiredby the Flux Thimble Tube Inspection program. (Flux thimble tubes 1 (J-8), 4 (H-6), 5 (F-8), 6 (J-10), 7 (F-7), 9 (H-1 1), 10 (L-8), 11 (G-5), 18 (L-11), 22 (K-12), 23 (D-10), 24 (H-13),
25 (N-8), 26 (H-3), 27 (C-8), 29 (N-6), 32 (L-13), 33 (C-5), 34 (H-2), 36 (J-14), 37 (P-9), 40 (F-14), 41 (N-4), 42 (D-3), 45 (N-13), 46 (J-1), 50 (R-6), 52 (L-15), 56 (N-2))
- b. The remaining Braidwood Station, Unit 2 flux thimble tubes, not replacedduring A2R17 or A2R18, will be replaced or removed from service during A2R19 Refueling Outage (Spring 2017), unless eddy current data is obtainedas requiredby the Flux Thimble Inspection Tube program.
C. Following A2R19, any Braidwood Station, Unit 2 flux thimble tube will be replaced every three (3) refueling outages or removed from service if eddy current data is not obtainedin accordancewith the Flux Thimble Tube Inspection program.