Category:Letter type:BYRON
MONTHYEARBYRON 2024-0046, Cycle 27 Core Operating Limits Report2024-09-19019 September 2024 Cycle 27 Core Operating Limits Report BYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024 Annual Radiological Environmental Operating Report (AREOR) BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024 2023 Regulatory Commitment Change Summary Report BYRON 2024-0020, Annual Dose Report for 20232024-04-18018 April 2024 Annual Dose Report for 2023 BYRON 2024-0021, Registration of Use of Cask to Store Spent Fuel2024-04-11011 April 2024 Registration of Use of Cask to Store Spent Fuel BYRON 2024-0019, Registration of Use of Cask to Store Spent Fuel2024-03-28028 March 2024 Registration of Use of Cask to Store Spent Fuel BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023 Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements BYRON 2023-0022, 2022 Annual Radiological Environmental Operating Report (AREOR)2023-05-0404 May 2023 2022 Annual Radiological Environmental Operating Report (AREOR) BYRON 2023-0002, Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2023-04-0606 April 2023 Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements BYRON 2023-0012, Cycle 26 Core Operating Limits Report2023-03-16016 March 2023 Cycle 26 Core Operating Limits Report BYRON 2022-0081, CFR72.48 Evaluation Summary Report2022-12-0909 December 2022 CFR72.48 Evaluation Summary Report BYRON 2022-0072, Steam Generator Tube Inspection Report for Refueling Outage 232022-10-27027 October 2022 Steam Generator Tube Inspection Report for Refueling Outage 23 BYRON 2022-0069, 2021 Regulatory Commitment Change Summary Report2022-10-13013 October 2022 2021 Regulatory Commitment Change Summary Report 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 BYRON 2022-0065, Registration of Use of Cask to Store Spent Fuel2022-10-13013 October 2022 Registration of Use of Cask to Store Spent Fuel BYRON 2022-0063, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report for September 9, 2021 to September 8, 20222022-09-29029 September 2022 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report for September 9, 2021 to September 8, 2022 BYRON 2022-0064, Letter 2022-0064 Submittal of Byron Integrated Initial License Training Examination Materials(Signed)2022-09-28028 September 2022 Letter 2022-0064 Submittal of Byron Integrated Initial License Training Examination Materials(Signed) BYRON 2022-0059, Registration of Use of Cask to Store Spent Fuel2022-09-15015 September 2022 Registration of Use of Cask to Store Spent Fuel BYRON 2022-0045, Day Inservice Inspection Report for Interval 4, Period 2, (B2R23)2022-07-15015 July 2022 Day Inservice Inspection Report for Interval 4, Period 2, (B2R23) BYRON 2022-0026, Annual Radiological Environmental Operating Report2022-05-0505 May 2022 Annual Radiological Environmental Operating Report BYRON 2022-0030, Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Report2022-05-0303 May 2022 Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Report BYRON 2022-0028, Cycle 24 Core Operating Limits Report2022-04-28028 April 2022 Cycle 24 Core Operating Limits Report BYRON 2022-0016, Annual Dose Report for 20212022-04-0707 April 2022 Annual Dose Report for 2021 BYRON 2021-0033, Submittal on Initial Operator Licensing Examination Outline2021-10-28028 October 2021 Submittal on Initial Operator Licensing Examination Outline BYRON 2021-0072, Post Exam Submittal Letter2021-10-28028 October 2021 Post Exam Submittal Letter BYRON 2021-0063, Reactor Coolant System Pressure and Temperature Limits Report2021-09-28028 September 2021 Reactor Coolant System Pressure and Temperature Limits Report BYRON 2021-0064, Cycle 25 Core Operating Limits Report2021-09-28028 September 2021 Cycle 25 Core Operating Limits Report BYRON 2021-0032, 2020 Annual Radiological Environmental Operating Report (AREOR)2021-05-0606 May 2021 2020 Annual Radiological Environmental Operating Report (AREOR) BYRON 2021-0031, 2020 Annual Radioactive Effluent Release Report2021-04-21021 April 2021 2020 Annual Radioactive Effluent Release Report BYRON 2021-0027, Annual Dose Report for 20202021-03-30030 March 2021 Annual Dose Report for 2020 BYRON 2021-0023, Registration of Use of Cask to Store Spent Fuel2021-03-25025 March 2021 Registration of Use of Cask to Store Spent Fuel BYRON 2021-0024, 2020 Regulatory Commitment Change Summary Report2021-03-19019 March 2021 2020 Regulatory Commitment Change Summary Report BYRON 2021-0001, Day Inservice Inspection Report for Interval 4, Period 2, (B2R22)2021-01-13013 January 2021 Day Inservice Inspection Report for Interval 4, Period 2, (B2R22) BYRON 2020-0087, National Pollutant Discharge Elimination System (NPDES) Permit No. IL00483132020-12-16016 December 2020 National Pollutant Discharge Elimination System (NPDES) Permit No. IL0048313 BYRON 2020-0084, 10 CFR 72.48 Evaluation Summary Report2020-12-10010 December 2020 10 CFR 72.48 Evaluation Summary Report BYRON 2020-0085, 10 CFR 50.59 Summary Report2020-12-10010 December 2020 10 CFR 50.59 Summary Report BYRON 2020-0067, Cycle 22 Core Operating Limits Report2020-10-20020 October 2020 Cycle 22 Core Operating Limits Report BYRON 2020-0063, Independent Spent Fuel Storage Installation - Transmittal of Annual Radioactive Effluent Release Repo2020-10-0101 October 2020 Independent Spent Fuel Storage Installation - Transmittal of Annual Radioactive Effluent Release Repo BYRON 2020-0053, Steam Generator Tube Inspection Report for Refueling Outage 232020-09-10010 September 2020 Steam Generator Tube Inspection Report for Refueling Outage 23 BYRON 2020-0025, Annual Dose Report 20192020-03-24024 March 2020 Annual Dose Report 2019 BYRON 2020-0015, Cycle 24 Core Operating Limits Report2020-03-17017 March 2020 Cycle 24 Core Operating Limits Report BYRON 2020-0010, Revision to Byron Station Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 172020-02-13013 February 2020 Revision to Byron Station Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 17 BYRON 2020-0008, 2019 Regulatory Commitment Change Summary Report2020-02-0707 February 2020 2019 Regulatory Commitment Change Summary Report BYRON 2019-0105, Post Examination Submittal Letter2019-11-26026 November 2019 Post Examination Submittal Letter BYRON 2019-0095, Registration of Use of Cask to Store Spent Fuel2019-10-10010 October 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0090, Registration of Use of Cask to Store Spent Fuel2019-09-18018 September 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0078, Registration of Use of Cask to Store Spent Fuel2019-08-22022 August 2019 Registration of Use of Cask to Store Spent Fuel 2024-09-19
[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
[Table view] |