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 Enclosed | 28 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 | Safe Shutdown Boric Acid Shutdown Margin Anticipated operational occurrence Safe Shutdown Earthquake Operating Basis Earthquake High Energy Line Break Surveillance Frequency Control Program Exemption Request Fuel cladding Accident Tolerant Fuel Exclusive Use Affidavit |
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-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 Stress corrosion cracking Liquid penetrant Exclusive Use Affidavit |
ML23235A172 | 23 August 2023 | Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report | |
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 Stress corrosion cracking Code Reconciliation License Renewal Power Uprate Affidavit |
ML23055A284 | 24 February 2023 | Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping | Fitness for Duty Ultimate heat sink Non-Destructive Examination Safe Shutdown Earthquake Coatings Operating Basis Earthquake Finite Element Analysis Aging Management Foreign Material Exclusion Feedwater Heater Affidavit |
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 |
ML22178A172 | 27 June 2022 | Long Term Coupon Surveillance Program | Aging Management License Renewal |
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 Stress corrosion cracking Code Reconciliation License Renewal Power Uprate |
ML22147A178 | 27 May 2022 | Owner'S Activity Report (Form OAR-1) for the Calvert Cliffs Nuclear Power Plant Unit 1 Spring 2022 Refueling Outage | Boric Acid Integrated leak rate test Moisture barrier |
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 | |
ML21350A114 | 16 December 2021 | Annual Commitment Change Notification | |
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 Unidentified leak Operational leakage Thermal fatigue |
ML21316A051 | 12 November 2021 | Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections | EVT-1 |
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 | |
ML21263A186 | 20 September 2021 | Proposed Alternative Concerning Pressure Testing of ASME Section XI Class 2 Portions of the Auxiliary Feedwater System | Safe Shutdown VT-2 Eddy Current Testing Through-Wall Leakage |
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 Flow Accelerated Corrosion Stress corrosion cracking License Renewal |
ML21210A325 | 30 July 2021 | Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report | License Renewal Subsequent License Renewal Power Uprate Measurement Uncertainty Recapture |
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 Flow Accelerated Corrosion Stress corrosion cracking License Renewal Thermal fatigue |
ML21077A180 | 18 March 2021 | 10 CFR 50.46 Annual Report and 30-day Report for Framatome'S Protect Enhanced Accident Tolerant Fuel (Eatf) Lead Test Assembly (LTA) | Accident Tolerant Fuel |
ML21013A530 | 13 January 2021 | Reactor Vessel Level Monitoring System Special Report | |
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 Flow Accelerated Corrosion Stress corrosion cracking Eddy Current Testing Pandemic Coronavirus COVID-19 Power Uprate Operational leakage |
BYRON 2020-0084, 10 CFR 72.48 Evaluation Summary Report | 10 December 2020 | 10 CFR 72.48 Evaluation Summary Report | |
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 High Energy Line Break Open Phase Condition Fire Protection Program GOTHIC |
ML20303A175 | 23 October 2020 | Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting | |
ML20280A508 | 6 October 2020 | Submittal of Relief Request CISI-03-01 Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements | Incorporated by reference Fuel cladding |
ML20265A198 | 21 September 2020 | R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications for Steam Generator Tube Inspection Frequency | Anticipated operational occurrence Weld Overlay Locked High Radiation Area Flow Accelerated Corrosion Stress corrosion cracking Eddy Current Testing Operability Determination Pandemic COVID-19 Power Uprate Operational leakage |
ML20195B159 | 10 July 2020 | Attachment 1 - Description and Assessment | Anticipated operational occurrence Stress corrosion cracking Pandemic Coronavirus COVID-19 Operational leakage |
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 | |
ML20034E346 | 7 February 2020 | Review of the Spring 2019 Steam Generator Tube Inspection Report | |
ML19347A779 | 12 December 2019 | License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies | Shutdown Margin Anticipated operational occurrence Fuel cladding Accident Tolerant Fuel Exclusive Use Affidavit |
ML19228A023 | 15 August 2019 | Proposed Alternative to Utilize Code Case N-879 | Affidavit |
ML19072A096 | 11 March 2019 | Information Regarding Dissimilar Metal Weld 2-CV-2005-30 Flaw Characteristic and Repair Weld Overlay | Weld Overlay Hydrostatic Design basis earthquake Stress corrosion cracking Earthquake Dissimilar Metal Weld |
ML18348A979 | 14 December 2018 | Transmittal of 10 CFR 50.59 Summary Report | Boric Acid Ultimate heat sink Probabilistic Risk Assessment FLEX High Energy Line Break Local Leak Rate Testing Feedwater Heater Earthquake Fuel cladding Power Uprate Measurement Uncertainty Recapture Water hammer |
ML18348A972 | 12 December 2018 | Submittal of Analytical Evaluation in Accordance with ASME Code Section XI | Non-Destructive Examination Affidavit |
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 |
ML17345A990 | 21 December 2017 | R. E. Ginna Nuclear Power Plant Flood Hazard Mitigation Strategies Assessment | High winds FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Flood Hazard Mitigation Strategies Assessment |
ML17324B369 | 20 December 2017 | Flood Hazard Mitigation Strategies Assessment | Internal Flooding FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Flood Hazard Mitigation Strategies Assessment |
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 Overspeed trip |
ML17214A118 | 27 July 2017 | Transmittal of 2017 Owner'S Activity Report for the Plant | |
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 Feedwater Heater Biofouling Power change Downpower Coast down Overspeed trip Water hammer |