ML24109A066 | 2 May 2024 | – Relief Request I5R-26, Revision 0 | VT-2 Incorporated by reference |
ML23206A038 | 21 September 2023 | Proposed Alternative to the Requirements of the ASME Code | Non-Destructive Examination Nondestructive Examination Incorporated by reference Intergranular Stress Corrosion Cracking |
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-22-127, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair | 14 December 2022 | Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair | Non-Destructive Examination Nondestructive Examination Intergranular Stress Corrosion Cracking Stress corrosion cracking Dissimilar Metal Weld |
ML22094A001 | 15 April 2022 | Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) | Nondestructive Examination VT-2 Incorporated by reference Intergranular Stress Corrosion Cracking Stress corrosion cracking Through-Wall Leakage |
ML21300A255 | 21 October 2021 | 6 to Updated Final Safety Analysis Report, Chapter 05 - Reactor Coolant System and Connected Systems | Safe Shutdown Shutdown Margin Reactor Vessel Water Level Non-Destructive Examination Grab sample Safe Shutdown Earthquake Weld Overlay Hydrostatic Operating Basis Earthquake Nondestructive Examination Design basis earthquake Feedwater Heater Intergranular Stress Corrosion Cracking Feedwater Controller Failure Stress corrosion cracking Excess Flow Check Valve Earthquake Liquid penetrant Pressure Boundary Leakage Unidentified leakage Power Uprate Overspeed trip Subsequent actuation Thermal fatigue |
JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs | 12 August 2021 | Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs | Non-Destructive Examination Intergranular Stress Corrosion Cracking Stress corrosion cracking |
ML18022A616 | 24 January 2018 | Approval of Alternatives to the ASME Code Regarding Reactor Vessel Penetration N-11B - Relief Request 15R-11, Revision 3 (CAC No. MF9286; EPID L-2017-LLR-0004) (RS-17-014) | Nondestructive Examination Incorporated by reference Intergranular Stress Corrosion Cracking Stress corrosion cracking |
RS-18-004, Additional Information Supporting Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11 | 4 January 2018 | Additional Information Supporting Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11 | Nondestructive Examination Intergranular Stress Corrosion Cracking Stress corrosion cracking Dissimilar Metal Weld |
ML17298A337 | 19 October 2017 | Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems | Safe Shutdown Shutdown Margin Reactor Vessel Water Level Grab sample Safe Shutdown Earthquake Weld Overlay Hydrostatic Operating Basis Earthquake Nondestructive Examination Design basis earthquake Intergranular Stress Corrosion Cracking Feedwater Controller Failure Stress corrosion cracking Earthquake Liquid penetrant Pressure Boundary Leakage Unidentified leakage Power Uprate Subsequent actuation |
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems | 19 October 2017 | Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems | Safe Shutdown Shutdown Margin Reactor Vessel Water Level Grab sample Safe Shutdown Earthquake Weld Overlay Hydrostatic Operating Basis Earthquake Nondestructive Examination Design basis earthquake Intergranular Stress Corrosion Cracking Feedwater Controller Failure Stress corrosion cracking Earthquake Liquid penetrant Pressure Boundary Leakage Unidentified leakage Power Uprate Subsequent actuation |
RS-17-014, Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11 | 14 February 2017 | Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11 | Nondestructive Examination Intergranular Stress Corrosion Cracking Stress corrosion cracking Dissimilar Metal Weld |
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 |
ML14055A227 | 28 February 2014 | Safety Evaluation in Support of Request for Relief Associated with the Fifth 10 Year Interval Inservice Testing Program MF1462 | Nondestructive Examination VT-2 Incorporated by reference Finite Element Analysis EVT-1 |
RS-13-289, Additional Information Supporting Relief Request I5R-11 Associated with Reactor Pressure Vessel Penetration N-11B Repair | 20 December 2013 | Additional Information Supporting Relief Request I5R-11 Associated with Reactor Pressure Vessel Penetration N-11B Repair | Non-Destructive Examination Hydrostatic Nondestructive Examination Finite Element Analysis Intergranular Stress Corrosion Cracking Stress corrosion cracking Exclusive Use Affidavit |
ML13044A663 | 13 February 2013 | Attachment 1, 10 CFR 50.55a Relief Request I5R-11, Revision 0 | Nondestructive Examination Finite Element Analysis Intergranular Stress Corrosion Cracking Code Reconciliation |
RS-12-064, Relief Request 14R-19 Associated with the Reactor Pressure Vessel Nozzle Repairs | 6 April 2012 | Relief Request 14R-19 Associated with the Reactor Pressure Vessel Nozzle Repairs | Reactor Vessel Water Level Non-Destructive Examination Intergranular Stress Corrosion Cracking Dissimilar Metal Weld |
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 05 - Reactor Coolant System and Connected Systems | 19 October 2011 | Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 05 - Reactor Coolant System and Connected Systems | Safe Shutdown Shutdown Margin Reactor Vessel Water Level Grab sample Safe Shutdown Earthquake Weld Overlay Hydrostatic Operating Basis Earthquake Nondestructive Examination Design basis earthquake Feedwater Heater Intergranular Stress Corrosion Cracking Feedwater Controller Failure Stress corrosion cracking Excess Flow Check Valve Earthquake Liquid penetrant Pressure Boundary Leakage Unidentified leakage Power Uprate Overspeed trip Subsequent actuation Thermal fatigue |
ML11305A054 | 19 October 2011 | Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 05 - Reactor Coolant System and Connected Systems | Safe Shutdown Shutdown Margin Reactor Vessel Water Level Grab sample Safe Shutdown Earthquake Weld Overlay Hydrostatic Operating Basis Earthquake Nondestructive Examination Design basis earthquake Feedwater Heater Intergranular Stress Corrosion Cracking Feedwater Controller Failure Stress corrosion cracking Excess Flow Check Valve Earthquake Liquid penetrant Pressure Boundary Leakage Unidentified leakage Power Uprate Overspeed trip Subsequent actuation Thermal fatigue |
ML20205Q519 | 16 April 1999 | Forwards SER Concluding That Quad Cities Nuclear Power Station,Unit 1 Can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained | Weld Overlay |
ML20205Q529 | 16 April 1999 | SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained | Weld Overlay Stress corrosion cracking |
IR 05000254/1998021 | 5 March 1999 | Insp Repts 50-254/98-21 & 50-265/98-21 on 981112-1218. Violation Noted:Major Areas Inspected:Isi Activities at Plant During Refueling Outage 15 | Non-Destructive Examination Weld Overlay Intergranular Stress Corrosion Cracking Stress corrosion cracking |
SVP-98-353, Forwards Licensee Assessment of Flaw Indications Found in IGSCC Susceptible Welds in Plant Primary Sys Piping,Summary of Weld Overlay Repair Designs & Detailed Evaluations for Flaw Indications That Util Proposes to Leave as-is | 24 November 1998 | Forwards Licensee Assessment of Flaw Indications Found in IGSCC Susceptible Welds in Plant Primary Sys Piping,Summary of Weld Overlay Repair Designs & Detailed Evaluations for Flaw Indications That Util Proposes to Leave as-is | Non-Destructive Examination Weld Overlay Intergranular Stress Corrosion Cracking Scaffolding |
SVP-97-202, Provides RPV Shell Weld Exam Results & Proposed Alternative Exam Requirements | 18 September 1997 | Provides RPV Shell Weld Exam Results & Proposed Alternative Exam Requirements | VT-2 |
ML20135B319 | 25 November 1996 | ISI Post Outage (90 Day) Summary Rept | Weld Overlay Hydrostatic VT-2 Intergranular Stress Corrosion Cracking Stress corrosion cracking Liquid penetrant |
ML20135A284 | 22 November 1996 | Requests Relief from Exam of Certain Reactor Vessel Shell Welds.Results of Augmented Exam of RPV Shell Welds,Encl | VT-2 |
ML20101Q012 | 4 April 1996 | Provides Assessment of Indications Detected in IGSCC Susceptible Stainless Steel Weldments in Reactor Recirculation Piping Sys & Transmits Weld Overlay Repair Designs & Flawed Pipe Evaluations,Per GL 88-01 & Suppl 1 | Weld Overlay Intergranular Stress Corrosion Cracking Stress corrosion cracking |
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 |
ML20064A463 | 28 February 1990 | Technical Evaluation Rept on Response from Comm Ed to Generic Ltr 88-01 Concerning Quad Cities Station,Unit 1 | Packing leak Weld Overlay Intergranular Stress Corrosion Cracking Stress corrosion cracking Pressure Boundary Leakage Unidentified leakage |
ML20093A377 | 27 June 1984 | IGSCC Flaw Disposition Summary | High Radiation Area Weld Overlay Nondestructive Examination |