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	Issue date	Title	Topic
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

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