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	Issue date	Title	Topic
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

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