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 | |