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| Issue date | Title | Topic | |
|---|---|---|---|
| ML23321A045 | 17 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 Form | 17 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 Welds | 7 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 | Non-Destructive Examination Code Reconciliation |
| RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors | 8 April 2022 | Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors | |
| ML21349A106 | 15 December 2021 | Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 | Non-Destructive Examination Weld Overlay Surveillance Frequency Control Program Through-Wall Leak |
| RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors | 22 October 2021 | Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors | |
| ML20303A175 | 23 October 2020 | Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting | |
| ML18192C152 | 18 July 2018 | Review of Fall 2017 Steam Generator Tube Inservice Inspection Report | |
| ML17355A561 | 21 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) | Probabilistic Risk Assessment Surveillance Frequency Control Program |
| RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors | 7 April 2017 | Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors | |
| ML17024A036 | 31 December 2016 | Operating Data Report for 2016 | Temporary Modification Biofouling Power change Coast down |
| ML16344A006 | 9 December 2016 | 10 CFR 72.48 Evaluation Summary of Biennial Report of Changes, Tests, or Experiments, Performed | Fuel cladding Fire Protection Program |
| RS-16-174, High Frequency Supplement to Seismic Hazard Screening 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... | 3 November 2016 | High Frequency Supplement to Seismic Hazard Screening 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... | Safe Shutdown Earthquake Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Seismically rugged Earthquake |
| ML17095A269 | 7 October 2016 | Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. | Weld Overlay Nondestructive Examination |
| ML17170A147 | 7 October 2016 | Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. | Weld Overlay Nondestructive Examination |
| RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. | 7 October 2016 | Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. | Weld Overlay Nondestructive Examination |
| 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 Accident | 31 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 | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi |
| ML16236A208 | 23 August 2016 | Report of Backfit Appeal Review Panel | Loop seal Packing leak Anticipated operational occurrence License Renewal Backfit Power Uprate Stretch Power Uprate Measurement Uncertainty Recapture |
| ML16214A199 | 11 August 2016 | an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review | Fitness for Duty Probabilistic Risk Assessment Backfit |
| 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) | 15 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) | Boric Acid High winds Shutdown Margin Ultimate heat sink Time to boil Safe Shutdown Earthquake Internal Flooding Hydrostatic Probabilistic Risk Assessment FLEX Tornado Generated Missile Fukushima Dai-Ichi Foreign Material Exclusion Spent Fuel Pool Instrumentation B.5.b Mitigating Strategies Earthquake |
| RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal | 30 June 2016 | Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal | Ultimate heat sink FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Earthquake |
| RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors | 7 April 2016 | Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors | |
| ML16014A188 | 22 January 2016 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review of Insights | Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| ML15344A159 | 10 December 2015 | Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7 | Hydrostatic Pressure and Temperature Limits Report |
| ML15322A317 | 18 November 2015 | Record of Decision | Incorporated by reference License Renewal Environmental Justice |
| ML15237A382 | 15 October 2015 | Pressure and Temperature Limits Report for Measurement Uncertainty Recapture Power Uprate | Anticipated operational occurrence Hydrostatic Pressure and Temperature Limits Report |
| RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015 | 30 April 2015 | Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015 | Ultimate heat sink |
| RS-15-072, Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 54 | 12 February 2015 | Comments on the Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 54 | License Renewal Measurement Uncertainty Recapture |
| ML14349A657 | 15 December 2014 | CFR 50.59 Changes, Tests, and Experiments, Paragraph (d)(2), Summary Report | Safe Shutdown Boric Acid Shutdown Margin Control of Heavy Loads Fuel cladding |
| RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application | 15 December 2014 | Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application | Coatings Aging Management Tornado Generated Missile |
| ML14141A133 | 30 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 | Unanalyzed Condition Internal Flooding Operator Manual Action Fukushima Dai-Ichi Earthquake |
| ML14128A556 | 30 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 | Unanalyzed Condition Ultimate heat sink Internal Flooding Hydrostatic Operator Manual Action Fukushima Dai-Ichi Earthquake |
| ML14101A352 | 4 June 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 | Safe Shutdown Unanalyzed Condition Fukushima Dai-Ichi Earthquake |
| ML14101A445 | 4 June 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 (Tac No. MF0095) | Unanalyzed Condition Fukushima Dai-Ichi Earthquake |
| ML14085A533 | 29 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 | Unanalyzed Condition Fukushima Dai-Ichi Earthquake |
| ML14127A174 | 7 May 2014 | Startup Report for the Measurement Uncertainty Recapture Power Uprate | |
| ML14120A039 | 24 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 | Safe Shutdown Anticipated operational occurrence Operator Manual Action Surveillance Frequency Control Program |
| ML14066A479 | 4 March 2014 | Clarification of Licensing Basis Assumptions for a Natural Circulation Cooldown Event | Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Earthquake Power-Operated Valves |
| ML14059A124 | 28 February 2014 | Pressure and Temperature Limits Reports (Ptlrs) | Hydrostatic Pressure and Temperature Limits Report |
| ML13225A595 | 17 December 2013 | Interim Staff Evaluation Related to Integrated Plan in Response to Order EA-12-049(Mitigation Strategies) | Safe Shutdown Boric Acid High winds Ultimate heat sink Time to boil Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Tornado Generated Missile Fukushima Dai-Ichi Frazil ice Earthquake |
| ML13182A031 | 3 July 2013 | Transmittal of Final Byron Station, Unit 2, Accident Sequence Precursor Analysis | Safe Shutdown Fitness for Duty Functionality Assessment Significance Determination Process |
| IR 05000456/2013202 | 31 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 05000289/2013201 | 31 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 | |
| ML13008A219 | 31 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 05000454/2013202 | 31 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 05000461/2013201 | 31 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 05000237/2013202 | 31 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 05000373/2013201 | 31 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 05000219/2013201 | 31 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 05000272/2013201 | 31 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 |