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	Issue date	Title	Topic
RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds	1 November 2023	Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds	Hydrostatic VT-2 Finite Element Analysis Flow Accelerated Corrosion Stress corrosion cracking License Renewal Thermal fatigue
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles	11 October 2023	Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles	Finite Element Analysis Aging Management Flow Accelerated Corrosion Stress corrosion cracking License Renewal Subsequent License Renewal Power Uprate
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections	10 October 2023	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 Subsequent License Renewal
ML23255A104	11 August 2023	Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout	Subsequent License Renewal
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
RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators	21 February 2023	Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators
ML22307A246	10 November 2022	Proposed Alternative to the Requirements of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code (EPIDs L-2021-LLR-0035 and L-2021-LLR-0036)	Probabilistic Risk Assessment Incorporated by reference
RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.	20 September 2022	Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.	Non-Destructive Examination Scaffolding
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
ML22105A072	15 April 2022	NRR E-mail Capture - Braidwood/Byron Verbal Authorization for Proposed Alternative I4R-15/I4R-21
RS-22-050, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds	8 April 2022	Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds
ML21194A027	31 December 2020	Westinghouse, WCAP-18596-NP Revision 0, Braidwood Unit 1 Reactor Vessel Closure Head Dome-to-Ring Weld ASME Section XI Evaluation of As-Found Indications	Hydrostatic Finite Element Analysis Affidavit
ML21008A397	17 December 2020	Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Appendix F, Updated Final Safety Analysis Report Supplement (License Renewal)	Boric Acid Ultimate heat sink Non-Destructive Examination Fire Barrier Hydrostatic Coatings High Energy Line Break Aging Management Flow Accelerated Corrosion Stress corrosion cracking Eddy Current Testing Moisture barrier License Renewal Liquid penetrant Through-Wall Leakage Overspeed trip Thermography Thermal fatigue Water hammer
ML19136A386	5 June 2019	Relief from the Requirements of the American Society of Mechanical Engineers Code	Nondestructive Examination Finite Element Analysis Stress corrosion cracking Liquid penetrant
ML18348A972	12 December 2018	Submittal of Analytical Evaluation in Accordance with ASME Code Section XI	Non-Destructive Examination Affidavit
RS-18-124, Relief Request Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval	4 October 2018	Relief Request Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval	Nondestructive Examination Finite Element Analysis Stress corrosion cracking License Renewal Liquid penetrant
RS-18-083, Response to Request for Additional Information Regarding Braidwood Station Fourth Inservice Inspection Interval Relief Request 14R-05	22 June 2018	Response to Request for Additional Information Regarding Braidwood Station Fourth Inservice Inspection Interval Relief Request 14R-05	Aging Management License Renewal
RS-18-030, Relief Requests Associated with the Fourth Inservice Inspection Interval	19 March 2018	Relief Requests Associated with the Fourth Inservice Inspection Interval	Weld Overlay Internal Flooding Hydrostatic Probabilistic Risk Assessment Nondestructive Examination VT-2 Incorporated by reference Finite Element Analysis FLEX Flow Accelerated Corrosion Stress corrosion cracking Operability Determination Liquid penetrant Through-Wall Leak Through-Wall Leakage Dissimilar Metal Weld Scaffolding Weak link Thermal fatigue
RS-16-142, Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange	31 October 2016	Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange	Finite Element Analysis Stress corrosion cracking Weak link
ML16109A337	27 April 2016	Relief from the Requirements of the ASME Code (CAC Nos. MF6715, MF6716, MF6717, and MF6718)	Boric Acid Nondestructive Examination Incorporated by reference Finite Element Analysis Stress corrosion cracking License Renewal
ML15350A041	31 December 2015	NUREG-2190 V2 - Safety Evaluation Report, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2.	Boric Acid Ultimate heat sink Fire Barrier Anticipated operational occurrence Safe Shutdown Earthquake Weld Overlay Coatings Operating Basis Earthquake Nondestructive Examination VT-2 Incorporated by reference Finite Element Analysis B.5.b Aging Management Pressure and Temperature Limits Report Flow Accelerated Corrosion Stress corrosion cracking Integrated leak rate test Eddy Current Testing Moisture barrier License Renewal Earthquake Control of Heavy Loads Liquid penetrant Flow Induced Vibration Power Uprate Measurement Uncertainty Recapture Thermal fatigue
ML15259A049	11 September 2015	Units 1 and 2 - Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds	Nondestructive Examination Finite Element Analysis Stress corrosion cracking License Renewal Liquid penetrant Affidavit
RS-15-236, Braidwood Station, Units 1 and 2 & Byron Station, Units 1 and 2 - Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds	11 September 2015	Braidwood Station, Units 1 and 2 & Byron Station, Units 1 and 2 - Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds	Nondestructive Examination Finite Element Analysis Stress corrosion cracking License Renewal Liquid penetrant Affidavit
RS-15-035, Update to Report the Completion of Commitment 47, Related to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, License Renewal Application	23 January 2015	Update to Report the Completion of Commitment 47, Related to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, License Renewal Application	Hydrostatic VT-2 Aging Management License Renewal
RS-14-084, Responses to NRC Requests for Additional Information, Set 10, Dated February 26, 2014 Related to the License Renewal Application	28 March 2014	Responses to NRC Requests for Additional Information, Set 10, Dated February 26, 2014 Related to the License Renewal Application	Loop seal Safe Shutdown Earthquake VT-2 Aging Management Flow Accelerated Corrosion Stress corrosion cracking License Renewal Earthquake Flow Induced Vibration Affidavit
RS-13-285, Bryon, Units 1 and 2, Updated Responses to Two NRC Requests for Additional Information from Set 1, Dated October 7, 2013, Related to the License Renewal Application	19 December 2013	Bryon, Units 1 and 2, Updated Responses to Two NRC Requests for Additional Information from Set 1, Dated October 7, 2013, Related to the License Renewal Application	Boric Acid Hydrostatic VT-2 Aging Management Intergranular Stress Corrosion Cracking Stress corrosion cracking License Renewal
RS-11-050, Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside.	11 April 2011	Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside.	Stress corrosion cracking Dissimilar Metal Weld DM weld
ML072760048	8 November 2007	Relief Request (12R-49), Regarding Inservice Inspection Program Alternative Method	Nondestructive Examination Incorporated by reference Dissimilar Metal Weld DM weld
ML20212A744	10 September 1999	Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety	Hydrostatic VT-2 Incorporated by reference Finite Element Analysis Liquid penetrant
ML20217K633	20 April 1998	Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code
ML20217K623	20 April 1998	Forwards SE Accepting Licensee 971015 Submittal Re Evaluation of Flaw in Nozzle Shell to Intermediate Shell Weld of Braidwood,Unit 2,reactor Pressure Vessel
ML20198J565	15 October 1997	Forwards Proprietery Rev 1 to WCAP-12045 & non-proprietary WCAP-12046,which Both Demonstrate That Indication Detected in Nozzle Shell-to-Intermediate Shell Weld Is Acceptable to Continue Svc.Proprietary Rept Withheld,Per 10CFR2.790(a)4	Affidavit
ML20141B555	13 May 1997	SE Accepting First 10-yr Interval Inservice Insp Program Plan Request for Relief NR-29 for Braidwood Station,Units 1 & 2	Incorporated by reference
ML20135C778	25 February 1997	Forwards Response to Request for Addl Info Re First 10-yr ISI Relief Request NR-29
ML20082L545	18 April 1995	Rev 3 to ISI Plan for Braidwood Nuclear Generating Station Units 1 & 2 1st Insp Interval	Boric Acid Non-Destructive Examination Hydrostatic Nondestructive Examination VT-2 Intergranular Stress Corrosion Cracking Liquid penetrant Scaffolding Thermal fatigue
ML20078E606	23 January 1995	Transmits Results of Last ASME Section XI ISI of Plant Unit 1 RHR Nozzle to Vessel Welds,Per 950120 Request
ML20086B541	13 November 1991	Transmits Info Re Flaws in Both Nozzles on Both Heat Exchangers Which Require Fracture Mechanics Evaluation & Forwards MMDT-SMT-193, Fracture Mechanics Evaluation, Braidwood,Unit 2 Residual Heat Exchanger Tube Side..
ML031140549	7 November 1991	Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability	Safe Shutdown Unanalyzed Condition Fitness for Duty Probabilistic Risk Assessment Condition Adverse to Quality Missed surveillance Operability Determination Exemption Request Pressure Boundary Leakage Backfit Operational leakage
IR 05000456/1988019	19 July 1988	Safety Insp Repts 50-456/88-19 & 50-457/88-19 on 880529- 0709.No Violations Noted.Major Areas Inspected:Licensee Action on Previously Identified Items,Emergency Preparedness,Followup on TMI Action Items & Events	Unanalyzed Condition Boric Acid High Radiation Area Stress corrosion cracking Fire Watch
ML20196H110	30 June 1988	Safety Evaluation Report Related to the Operation of Braidwood Station,Units 1 and 2.Docket Nos. 50-456 and 50-457.(Commonwealth Edison Company)	Safe Shutdown Non-Destructive Examination Nondestructive Examination Process Control Program Stress corrosion cracking Exemption Request Turbine Missile Fire Protection Program
ML20147F470	23 February 1988	Forwards Relief Request 2NR15 & Interim Rept, Evaluation of Indication in Unit 2 Loop 1 Elbow to Valve Weld Region, for Review & Acceptance in Conjunction W/Review of Sc Hunsader to TE Murley on Preservice Insp Program
ML20154D433	28 February 1986	Forwards Results of Preservice Insp of Steam Generators & Pressurizer Vessels.Repairs Involve Risk of Reducing Vessel Integrity & Unwarranted.Nrc Concurrence Requested

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