Similar Documents at Byron |
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Category:Letter type:RS
MONTHYEARRS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision RS-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-24-093, 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-24-095, 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-24-088, 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-24-044, 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-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-23-075, 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-23-056, 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-23-049, 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-22-110, 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-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022 Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube. RS-22-057, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-050, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-04-0808 April 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Va 2024-09-13
[Table view] Category:Report
MONTHYEARRS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed BW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood 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-23-056, 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 BYRON 2022-0071, Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment2022-10-13013 October 2022 Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping BYRON 2020-0085, 10 CFR 50.59 Summary Report2020-12-10010 December 2020 10 CFR 50.59 Summary Report BYRON 2020-0084, 10 CFR 72.48 Evaluation Summary Report2020-12-10010 December 2020 10 CFR 72.48 Evaluation Summary Report ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20195B1592020-07-10010 July 2020 Attachment 1 - Description and Assessment ML20195B1622020-06-30030 June 2020 Attachment 11 - SG-SGMP-17-25-NP, Revision 1, Foreign Object Limits Analysis for the Byron and Braidwood Unit 2 Steam Generators June 2020 ML20195B1612020-06-25025 June 2020 Attachment 6 - Intertek Report No. Aim 200510800-2Q-1(NP), Byron Unit 2 Operational Assessment Addressing Deferment of B2R22 Steam Generator Tube Examinations to B2R23, April 2022 ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18192C1522018-07-18018 July 2018 Review of Fall 2017 Steam Generator Tube Inservice Inspection Report ML17355A5612017-12-21021 December 2017 Ltr. 12/21/17 Response to Disputed Non-Cited Violation Documented in Byron Station, Units 1 and 2 - Evaluations of Changes, Tests, and Experiments Baseline Inspection Report 05000454/2017009; 05000455/2017009 (DRS-N.Feliz-Adorno) ML17234A4782017-08-22022 August 2017 Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.4 Path 4: GMRS ≪ 2xSSE RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-04-0707 April 2017 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16344A0062016-12-0909 December 2016 10 CFR 72.48 Evaluation Summary of Biennial Report of Changes, Tests, or Experiments, Performed RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17360A1742016-10-0707 October 2016 Attachment 6: Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations (Non-Proprietary) ML16356A0202016-10-0707 October 2016 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17095A2692016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. RS-16-122, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML16236A2082016-08-23023 August 2016 Report of Backfit Appeal Review Panel ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review RS-16-088, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-07-15015 July 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-03-15015 March 2016 Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds RS-15-267, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-11-30030 November 2015 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-15-072, Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 542015-02-12012 February 2015 Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 54 RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014 Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14128A5562014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14178B2222014-06-24024 June 2014 Technical Review of TIA 2013-02, Single Spurious Assumptions for Braidwood and Byron Stations Safe-Shutdown Methodology ML14085A5332014-05-29029 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14120A0392014-04-24024 April 2014 Units 1 & 2 - License Amendment Request to Install New Low Degraded Voltage Relays & Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses BYRON 2014-0040, Pressure and Temperature Limits Report (PTLR) Revised for Negative Pressure Application During Reactor Coolant System Vacuum Fill2014-03-27027 March 2014 Pressure and Temperature Limits Report (PTLR) Revised for Negative Pressure Application During Reactor Coolant System Vacuum Fill ML14079A4232014-03-12012 March 2014 Enclosure 1, Byron Nuclear Generating Station, Flood Hazard Reevaluation Report, Revision 0 ML14066A4792014-03-0404 March 2014 Clarification of Licensing Basis Assumptions for a Natural Circulation Cooldown Event RS-14-082, ECCS Evaluation Model Error - 10 CFR 50.46 30-Day Report2014-02-27027 February 2014 ECCS Evaluation Model Error - 10 CFR 50.46 30-Day Report BYRON 2014-0003, Pressure and Temperature Limits Report (PTLR) for Measurement Uncertainty Recapture (Mur) Power Uprate2014-02-13013 February 2014 Pressure and Temperature Limits Report (PTLR) for Measurement Uncertainty Recapture (Mur) Power Uprate 2024-05-28
[Table view] Category:Miscellaneous
MONTHYEARRS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood BW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML18192C1522018-07-18018 July 2018 Review of Fall 2017 Steam Generator Tube Inservice Inspection Report ML17355A5612017-12-21021 December 2017 Ltr. 12/21/17 Response to Disputed Non-Cited Violation Documented in Byron Station, Units 1 and 2 - Evaluations of Changes, Tests, and Experiments Baseline Inspection Report 05000454/2017009; 05000455/2017009 (DRS-N.Feliz-Adorno) RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-04-0707 April 2017 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16344A0062016-12-0909 December 2016 10 CFR 72.48 Evaluation Summary of Biennial Report of Changes, Tests, or Experiments, Performed RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17095A2692016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. RS-16-122, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML16236A2082016-08-23023 August 2016 Report of Backfit Appeal Review Panel ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review RS-16-088, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-07-15015 July 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-15-072, Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 542015-02-12012 February 2015 Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 54 RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014 Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application ML14128A5562014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14085A5332014-05-29029 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14120A0392014-04-24024 April 2014 Units 1 & 2 - License Amendment Request to Install New Low Degraded Voltage Relays & Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses ML14066A4792014-03-0404 March 2014 Clarification of Licensing Basis Assumptions for a Natural Circulation Cooldown Event ML13225A5952013-12-17017 December 2013 Interim Staff Evaluation Related to Integrated Plan in Response to Order EA-12-049(Mitigation Strategies) ML13182A0312013-07-0303 July 2013 Transmittal of Final Byron Station, Unit 2, Accident Sequence Precursor Analysis IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee RS-12-162, Company, LLCs 180-Day Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Company, LLCs 180-Day Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RS-12-161, Byron Generation Station, Unit 1, 12Q0108.20-R-002 Rev. 1, Seismic Walkdown Checklist (Swc). Part 2 of 22012-11-0707 November 2012 Byron Generation Station, Unit 1, 12Q0108.20-R-002 Rev. 1, Seismic Walkdown Checklist (Swc). Part 2 of 2 ML12341A1612012-11-0707 November 2012 Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Byron Station, Unit 1, Report No. 12Q0108.20-R-001, Revision 1 RS-12-161, Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 1 of 32012-11-0707 November 2012 Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 1 of 3 RS-12-161, Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 2 of 32012-11-0707 November 2012 Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 2 of 3 RS-12-161, Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 3 of 32012-11-0707 November 2012 Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 3 of 3 RS-12-161, Q0108.20-R-002, Rev. 1, Seismic Walkdown Checklist (Swc). Part 1 of 22012-11-0707 November 2012 Q0108.20-R-002, Rev. 1, Seismic Walkdown Checklist (Swc). Part 1 of 2 ML12341A1662012-11-0707 November 2012 Enclosure 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Byron Station, Unit 2, Report No: 12Q0108.20-R-002, Revision 1 ML12341A1652012-11-0707 November 2012 Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 3 of 3 ML12341A1642012-11-0707 November 2012 Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 2 of 3 2024-05-28
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Michael P. Gallagher Vice President. License Renewal Exelon Nuclear Exelon Generation 200 Exelon Way Kennett Square. PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 RS-15-072 February 12, 2015 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1and2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455
Subject:
Exelon Generation Company, LLC Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 54 Regarding Byron Station, Units 1 and 2
Reference:
- 1) Exelon Generation Company, LLC letter from Michael P. Gallagher to NRC Document Control Desk, "Application for Renewed Operating Licenses", dated May 29, 2013
- 2) Letter from Brian D. Wittick (NRC) to Michael P. Gallagher (Exelon),
"Notice of Availability of the Draft Plant-Specific Supplement 54 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Byron Station, Units 1 and 2", dated December 23, 2014 In the Reference 1 letter, Exelon Generation Company, LLC (Exelon) submitted the License Renewal Application (LRA) for the Byron and Braidwood Stations, Units 1 and 2, which contained combined technical information required by 10 CFR 54.21 for both stations and separate site-specific environmental information required by 10 CFR 54.23 for each station.
In the Reference 2 letter, the U.S. Nuclear Regulatory Commission informed Exelon of the availability of the Draft Plant-Specific Supplement 54 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants (GEIS) Supplement 54 Regarding Byron Station, Units 1 and 2 and requested that comments be provided to the staff by February 20, 2015. A separate plant-specific supplement to the GEIS regarding Braidwood Station, Units 1 and 2 will be issued later.
Exelon has completed its review and is submitting, as an enclosure to this letter, written comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 54 Regarding Byron Station, Units 1 and 2.
U.S. Nuclear Regulatory Commission February 12, 2015 Page2 There are no 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.
Respectfully,
Enclosure:
Exelon Generation Company, LLC Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 54 Regarding Byron Station, Units 1 and 2 cc: Regional Administrator - NRC Region Ill NRC Project Manager (Environmental Review}, NRR-DLR NRC Project Manager (Safety Review), NRR-DLR NRC Project Manager, NRR-DORL Byron Station NRC Senior Resident Inspector, Byron Station Illinois Emergency Management Agency - Division of Nuclear Safety
RS-15-072 Enclosure Page 1 of 8 Exelon Generation Company, LLC Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 54 Regarding Byron Station, Units 1 and 2 NOTE: Where changes to draft text are suggested, proposed inserts are in bolded italic font and proposed deletions are in strikethrough font.
Item DSEIS DSEIS Line # Exelon Comment
- Page Section 1 2-1 30 to 31 2.1 As indicated in section 3.1.1 of the Byron Station, Units 1 and 2 (Byron) License Renewal Environmental Report (ER) (p. 3-4) and in section 3.1 of the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 54 Regarding Byron Station, Units 1 and 2 (DSEIS), Byron Units 1 and 2 entered commercial service on September 16, 1985, and August 21, 1987, respectively, rather than February 1985 and January 1987. Accordingly, change the sentence in lines 30 to 31 on page 2-1 as follows:
Byron is a two-unit, nuclear-powered steam-electric generating facility that began commercial operation in FebruarySeptember 1985 (Unit 1) and JanuaryAugust 1987 (Unit 2).
2 2-1 32 to 33 2.1 Change the sentence in lines 32 to 33 on page 2-1 as follows:
The nuclear reactorreactors for each unit is aboth units are Westinghouse pressurized-water reactorreactors (PWRs), together producing an annual average net output of 2,3702,394 megawatts electric (MWe) for the facility (Exelon 2013a)."
This change is appropriate because, as section 7.1 in the Byron ER stated, it was conservatively assumed throughout the Byron ER that during the license renewal terms Byron Units 1 and 2 will operate with measurement uncertainty recapture (MUR) at an approximate annual average net output of 2,394 MWe.
Exelon Generation acknowledges that some other sections in Chapter 7 of the ER erroneously stated that the approximate annual average net output for Byron (including MUR) would be 2,370 MWe. However, Exelon has confirmed that impacts reported in the Byron ER from the proposed action (i.e., license renewal) as well as from alternatives were calculated using the correct annual average net output of 2,394 MWe for Byron Station.
RS-15-072 Enclosure Page 2 of 8 Item DSEIS DSEIS Line # Exelon Comment
- Page Section 3 2-4 29 2.2.2 The text in line 29 on page 2-4 states that the text box (on page 2-5) contains 17 alternatives. However, only 16 alternatives are listed. The supercritical pulverized coal alternative described in DSEIS Section 2.3.12 is missing from text box and should be added.
4 2-9 Table 2-1 2.2.2 For completeness, Table 2-1 should be revised by adding a column denoting key characteristics for the Purchased Power Alternative.
5 2-9 Table 2-1 2.2.2 Exelon Generation recommends that assumptions be To better specified and standardized in Chapter 2 of the 2-10 DSEIS for all alternatives, and that the assumptions be consistently applied to all impact area analyses in Chapter 4 of the DSEIS. Additional comments below (items 21 to 23) provide examples of specific inconsistencies in assumptions made for certain impact area analyses in Chapter 4.
6 2-11 26 to 47 2.2.2.1 The discussion of the New Nuclear Alternative in lines 28 to 47 on page 2-11 should be revised to clarify that assumptions made for this alternative about reuse of features at an existing power plant site, such as transmission lines, are not unique to the Byron site.
Also, in lines 37 to 40, clarify whether the estimate of "additional land" needed is based on the Byron site. If so, please explain how this assumption relates to existing power plant sites in other states that will necessarily host the New Nuclear Alternative, unless the ban on new nuclear stations in Illinois is reversed.
7 2-15 15 2.2.2.3 In line 15 on page 2-15, change "49 Lpd" as follows: "49 million Lpd" 8 2-20 15 2.3.3 In line 15 on page 2-20, insert theoretically after could as follows:
distances could theoretically function as See FirstEnergy Nuclear Operating Co. (Davis-Besse Nuclear Power Station), CLI-12-08, 75 NRC 393, 401-02 (2012) (explaining that the use of interconnected wind farms for baseload energy generation is theoretical at best).
9 3-1 9 to 10 3.1 As indicated in section 3.1.1 of the Byron ER (p. 3-4) and in section 3.1 of the DSEIS, Byron Units 1 and 2 entered commercial service on September 16, 1985, and August 21, 1987, respectively, rather than February 1985 and January 1987. Accordingly, change the
RS-15-072 Enclosure Page 3 of 8 Item DSEIS DSEIS Line # Exelon Comment
- Page Section sentence in line lines 9 to 10 on page 3-1 as follows:
It began commercial operation in FebruarySeptember 1985 (Unit 1) and JanuaryAugust 1987 (Unit 2).
10 3-5 6 to 7 3.1.1 ComEd does not own the Byron Salvage Yard property.
Owners of property tracts adjacent to the Byron Station site, including the Byron Salvage Yard property, are listed in the Clean Water Act Section 401 Certification Application for Byron, which was provided to the NRC in the Byron ER, Appendix G. The sentence in lines 6 to 7 on page 3-5 should be corrected accordingly.
The sentence in lines 21 to 23 on page 3-5 should be modified as follows:
At 100 percent reactor power, the combined net electrical output from both Byron units is approximately 2,3702,394 megawatts electric (Exelon 2013a).
11 3-5 21 to 23 3.1.2 This change is recommended because, as was noted in a preceding comment (item #2, above, regarding lines 32 to 33 on page 2-1 of the DSEIS), the correct approximate annual average net electrical output (including MUR) for Byron is 2,394 MWe.
12 3-6 Fig 3-4 3.1.3 Figure 3-4 on page 3-6 indicates that steam condensate is recycled to either the reactor or the steam generator.
For clarity, the words, reactor or should be deleted from the figure because at Byron, which is a PWR, the condensate goes only to the steam generator.
13 3-40 18 to 19 3.6.2 On page 3-40, lines 18 to 19, the text states that Table 3-5 lists 55 state-listed plant species in Ogle and Winnebago counties. However, the title of Table 3-5 indicates that only state-listed plants found in Ogle County are included. Also, only 33 (rather than 55) state-listed species are named in Table 3-5, and one of those (Cyclonaias tuberculata purple wartyback) is a mussel, not a plant. Accordingly, the text in lines 18 and 19 on page 3-40 should be corrected by changing the number "55" to "32" in line 18 and by deleting the words "and Winnebago County" in line 19.
14 3-41 Table 3-5 In Table 3-5 (State-Listed Plant Species in Ogle County) on page 3-41, the row containing "Cyclonaias tuberculata," which is a mussel rather than a plant, should be deleted.
RS-15-072 Enclosure Page 4 of 8 Item DSEIS DSEIS Line # Exelon Comment
- Page Section 15 3-46 Table 3-9 In Table 3-9 on page 3-46, the scientific name for Blandings turtle should be changed from Equisetum pretense [sic], which is the scientific name for a plant rather than the turtle, to Emydoidea blandingii.
16 3-80 7 to 8 3.10.5 In lines 7 to 8 on page 3-80, change the phrase "Exelon's last settlement agreement for Byron was signed on November 8, 2008 ..." as follows:
Exelon's last settlement agreement for Byron was signedeffective on November 818, 2008 ...
This change is suggested because the last settlement agreement for Byron was signed on many different days by many parties, and as a result, it became effective on November 18, 2008 rather than on November 8.
17 3-87 14 to 15 3.11.2 For accuracy in lines 14 to 15 on page 3-87, change the sentence "Exelon's Spill Prevention, Control and Countermeasure plan serves as the site's hazardous waste contingency plan" as follows:
Exelon's Spill Prevention, Control and Countermeasure plan The RCRA Facility Plan For Byron Station serves as the site's hazardous waste contingency plan."
18 3-89 12 to 38 3.11.4 As noted in section 3.1.6.5 in the DSEIS (page 3-15),
under the regulations supported by the 2013 Generic Environmental Impact Statement for License Renewal of Nuclear Plants (NUREG-1437, Rev. 1), transmission lines that are within the scope of the NRCs license renewal review for a nuclear power plant are limited to (1) those transmission lines that connect the nuclear plant to the substation where electricity is fed into the regional distribution system and (2) transmission lines that supply power to the nuclear plant from the grid.
As was explained in Exelon Generations response to NRCs post-audit RAIs (HCR-6) (see DSEIS Section 4.18 (References), Exelon 2013b), no offsite Byron transmission lines meet the 2013 regulatory definition for in-scope lines. The electrical connections between the main power transformers and the Byron Switchyard are the only transmission facilities that are in-scope for Byron license renewal under the current regulations.
These facilities are all onsite, and no rights-of-way are maintained specifically for the connections.
Nevertheless, because the Byron ER was written before
RS-15-072 Enclosure Page 5 of 8 Item DSEIS DSEIS Line # Exelon Comment
- Page Section NUREG-1437, Rev. 1 and its accompanying regulations were finalized in 2013, the Byron ER included analyses of induced electric shock potential for offsite transmission lines that were considered in-scope under the 1996 GEIS and its accompanying regulations.
Those analyses are described in Section 3.11.4 in the DSEIS (lines 12 to 38 on p. 3-89), but are no longer relevant under the 2013 regulations and NUREG-1437, Rev. 1.
Considering the above, Exelon Generation recommends:
(1) Modify section 3.11.4 (lines 12 to 32 on page 3-89) to clarify that no offsite transmission lines are within the current scope of the NRCs license renewal review for Byron; and (2) Delete the entire paragraph in lines 33 to 38 on page 3-89 because the information is not relevant to any transmission lines that are in-scope for Byron license renewal under current regulations.
19 3-89 39 to 44 3.11.4 The information in lines 39 to 44 on page 3-89 concerning software and models used to calculate the potential for induced shock effects is not correct for Byron and should be deleted. It is not necessary to correct the information because, as noted in a preceding comment (item # 18, above) regarding lines 12 to 38 on page 3-89, section 3.11.4 should be revised to clarify that no offsite transmission lines are within the current scope of the NRCs license renewal review for Byron.
20 3-90 2 to 3 3.11.5 Delete the sentence in lines 2 to 3 on page 3-90 because section 3.11.5 of the DSEIS addresses only physical occupational hazards and does not address electric shock hazards.
21 4-48 2 to 5 4.9.2 Section 4.9.2 (lines 2 to 5 on page 4-48) states that a separate environmental review would be needed to assess decommissioning impacts on cultural resources for the No Action alternative to Byron license renewal.
Exelon Generation notes that such an environmental review has been completed and recommends that Section 4.9.2 be revised to incorporate by reference the conclusions from NUREG-0586 (NRC 2002, GEIS on Decommissioning of Nuclear Facilities). NUREG-0586 concludes that for all nuclear plant sites at which decommissioning will not require disturbing lands beyond existing site boundaries, impacts to cultural
RS-15-072 Enclosure Page 6 of 8 Item DSEIS DSEIS Line # Exelon Comment
- Page Section resources would be SMALL. For nuclear plants where decommissioning would disturb land beyond existing site boundaries, impacts would have to be assessed on a case-by-case basis and might be SMALL, MODERATE or LARGE. Exelon Generation submits that the existing Byron site is sufficiently large that explicit justification is warranted before concluding in Section 4.9.2 that the generic finding in NUREG-0586 of SMALL impacts to cultural resources from decommissioning would not apply to Byron.
22 4-48 4.9.4 The IGCC impact to cultural resources is characterized and and in Section 4.9.4 as SMALL. The NGCC impact is 4-49 4.9.5 characterized in Section 4.9.5 as SMALL to MODERATE. Each plant is assumed to be sited on the approximately 400 acres of undisturbed land on the Byron site, and the difference between the projects in impacts to cultural resources is attributed to the new gas pipeline that would need to be constructed for the NGCC. However, given that the IGCC alternative requires 2,000 acres and the NGCC alternative requires 94 acres including pipelines (see Table 2-1 on page 2-10), the conclusions are inconsistent. There is not that much difference in the uncertainty of the cultural resource richness of the new pipeline compared to undisturbed area of the existing site, and the IGCC would consume more undisturbed acres than the NGCC.
Therefore, Exelon Generation recommends reconsideration of the impact findings in sections 4.9.4 and 4.9.5 for the IGCC and NGCC alternatives.
23 4-50 6 to 23 4.9.7 The impact from the Purchased Power alternative to cultural resources is described in Section 4.9.7 (page 4-50, lines 6 to 23) as SMALL to LARGE. The description of the activities under this alternative is inconsistent with the description given in Section 2.2.2.5. According to section 2.2.2.5, facilities from which power would be purchased would not likely be constructed solely to replace Byron although [p]urchased power may require new transmission lines. Section 2.2.2.5 further states, Impacts to other resource areas [such as cultural resources] from the operation of existing power plant facilities would likely be less than those for new plants because existing facilities would not require new construction. Given that the New Nuclear alternative, which requires construction of new facilities, was evaluated to have SMALL impacts on cultural resources
RS-15-072 Enclosure Page 7 of 8 Item DSEIS DSEIS Line # Exelon Comment
- Page Section (see section 4.9.3, page 4-48), it is difficult to understand the basis for NRCs conclusion that Purchased Power, for which no construction is likely except possibly transmission lines, would have SMALL to LARGE impacts. Therefore, Exelon Generation recommends reconsideration of the impact findings in section 4.9.7 for the Purchased Power alternative taking into account the probability that new generating facilities would not be needed.
24 4-57 4.10.7 The description of the Purchased Power Alternative in and Section 4.10.7 is different from that in Section 2.2.2.5.
4-58 According to section 2.2.2.5 (page 2-18), facilities from which power would be purchased would not likely be constructed solely to replace Byron. Yet, Section 4.10.7 bases its conclusions about impacts to socioeconomics and transportation resources on the possibility that new electrical power generating facilities would be needed to supply purchased power. Therefore, Exelon Generation recommends reconsideration of the impact findings in section 4.10.7 for the Purchased Power alternative taking into account the probability that new generating facilities would not be needed.
25 4-61 38 to 41 4.11.1.1 The text in lines 38 to 41 on page 4-61 describes the analyses of induced electric shock potential that Exelon Generation performed and included in the Byron ER before NUREG-1437, Rev. 1 and its accompanying regulations were finalized in 2013. Exelon Generation recommends that this information be deleted from page 4-61 because it is no longer relevant.
As the DSEIS notes in section 3.1.6.5 (page 3-15) and Exelon Generation's response to NRC's post-audit RAIs explains (HCR-6) (see DSEIS Section 4.18
[References], Exelon 2013b), no offsite Byron transmission lines meet the 2013 regulatory definition for in-scope lines. The electrical connections between the main power transformers and the Byron switchyard are the only transmission facilities that are in-scope for Byron license renewal under current regulations. These facilities are all onsite, and no rights-of-way are maintained specifically for the connections. Electrical shock hazards are controlled on the Byron site in accordance with applicable industrial safety standards, and potentially affected workers comply with electrical safety procedures when working near energized
RS-15-072 Enclosure Page 8 of 8 Item DSEIS DSEIS Line # Exelon Comment
- Page Section equipment. Accordingly, onsite electrical shock potential is of small significance to public health, and analyses to verify conformance to National Electrical Safety Code criteria are not warranted.
26 4-61 42 to 45 4.11.1.1 The text in lines 42 to 45 on page 4-61 should be modified to reflect appropriate findings regarding the transmission lines for Byron that are currently in-scope, as described in the preceding comment regarding p.
4-61, lines 38 to 41.
27 F-3 Note Table F-1 The Source for the results presented in the Table F-1 is shown as being the Byron ER (Exelon 2013b). While this is true for the Unit 1 values, the Unit 2 values are from Exelon Generations Response (dated February 4, 2014) to NRC requests for additional information (dated January 6, 2014) for the severe accident mitigation alternatives review. Accordingly, the Source should be revised as follows:
Source: Exelon 2013(b) [Unit 1]
Exelon 2014 [Unit 2]
The full citation for Exelon 2014 is listed in Section 4.18 of the DSEIS.
28 F-29 SAMA 1, Table F-5 The text in Table F-5 describing the modeling modeling assumptions for SAMA 1 should be modified to indicate assumptions that a new event was added to the model to represent the diesel-driven SX pump, and it was assigned a failure probability of 1.0E-02, as follows:
Reduce the probability of Add new event representing diesel-driven SX pump with failure toprobability of 1x102.
29 F-30 SAMA 11, Table F-5 The text in Table F-5 describing the modeling modeling assumptions for SAMA 11 should be modified to indicate assumptions that the RCP Seal LOCA probability was also reduced by a factor of 1000 to account for "no-leak" seals.
30 F-32 SAMA 21, Table F-5 The text in Table F-5 describing the modeling modeling assumptions for SAMA 21 should be modified as follows:
assumptions Completely eliminates all risk from the ISLOCA events occurring in the RHR dischargesuction lines.