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| Issue date | Title | Topic | |
|---|---|---|---|
| BW230054, Attachment 2: MDMP Deviation Form | 17 November 2023 | Attachment 2: MDMP Deviation Form | |
| 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 | |
| RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 | 29 September 2023 | Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 | Boric Acid VT-2 Finite Element Analysis Liquid penetrant Exclusive Use |
| 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 10 | 20 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 | Non-Destructive Examination Code Reconciliation |
| BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 9 | 20 October 2022 | Pressure and Temperature Limits Report (Ptlr), Revision 9 | Hydrostatic Pressure and Temperature Limits 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 Assignment | 13 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 Suits | 30 June 2022 | Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits | Mururoa |
| 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 |
| BW210065, Pressure and Temperature Limits Report, Revision 8 | 27 October 2021 | Pressure and Temperature Limits Report, Revision 8 | Hydrostatic Pressure and Temperature Limits Report |
| 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 | |
| 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 Sections | 1 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 | Finite Element Analysis Aging Management |
| BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval | 30 June 2021 | ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval | Safe Shutdown |
| RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld | 12 May 2021 | Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld | Hydrostatic VT-2 Finite Element Analysis |
| RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping | 4 January 2021 | Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping | Nondestructive Examination |
| RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections | 16 December 2020 | Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections | Anticipated operational occurrence Pandemic Coronavirus COVID-19 |
| BYRON 2020-0085, 10 CFR 50.59 Summary Report | 10 December 2020 | 10 CFR 50.59 Summary Report | Safe Shutdown Boric Acid Safe Shutdown Earthquake Open Phase Condition Fire Protection Program |
| BYRON 2020-0084, 10 CFR 72.48 Evaluation Summary Report | 10 December 2020 | 10 CFR 72.48 Evaluation Summary Report | |
| ML20303A175 | 23 October 2020 | Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting | |
| ML20195B159 | 10 July 2020 | Attachment 1 - Description and Assessment | Anticipated operational occurrence Pandemic Coronavirus COVID-19 |
| ML20195B162 | 30 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 | |
| ML20195B161 | 25 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 | |
| ML19228A023 | 15 August 2019 | Proposed Alternative to Utilize Code Case N-879 | |
| ML18348A979 | 14 December 2018 | Transmittal of 10 CFR 50.59 Summary Report | Boric Acid Ultimate heat sink Probabilistic Risk Assessment FLEX Earthquake Fuel cladding |
| ML18348A972 | 12 December 2018 | Submittal of Analytical Evaluation in Accordance with ASME Code Section XI | Nondestructive Examination |
| 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 |
| ML17234A478 | 22 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 | High Radiation Area Ultimate heat sink Safe Shutdown Earthquake Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Earthquake Power-Operated Valves Power Operated Valves |
| 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-16-223, 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) | 7 December 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 FLEX Tornado Generated Missile Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Earthquake |
| 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 |
| 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 |
| ML17360A174 | 7 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) | 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 |
| 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 |
| ML16356A020 | 7 October 2016 | 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 |
| ML16250A518 | 30 April 2016 | Technical Evaluation Report Related to the Exelon Generation Company, LLC, License Amendment Request to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink. Docket Nos. Stn 50-456 & 457 | Safe Shutdown Ultimate heat sink Safe Shutdown Earthquake Surveillance Frequency Control Program |
| 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 | |
| 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 Welds | 15 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 | Boric Acid |
| 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 |
| 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) | 30 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) | FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation |