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Issue date | Title | Topic | |
---|---|---|---|
ML20217A993 | 30 September 1999 | NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data | |
ML20196H862 | 30 June 1999 | NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept | High Radiation Area Power change |
ML20205C567 | 19 March 1999 | Simulator Four-Yr Certification Rept | Safe Shutdown |
ML20205D131 | 31 December 1998 | 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 | |
ML20196C873 | 30 November 1998 | Rev 0 to GE-NE-B13-01980-30-1, Fracture Mechanics Evaluation on Observed Indications at Two Welds in Recirculation Piping of Quad Cities,Unit 1 Station | Weld Overlay |
ML20196C839 | 30 November 1998 | Rev 0 to GE-NE-B13-01980-030-2, Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1 | |
ML20216C056 | 30 April 1998 | Safe Shutdown Rept for Quad Cities Station,Units 1 & 2, Vols 1 & 2.W/22 Oversize Figures | Hot Short Safe Shutdown Fire Barrier Emergency Lighting Exemption Request Fire Protection Program |
ML20217G395 | 8 April 1998 | TS 3/4.8.F Snubber Functional Testing Scope Quad Cities Unit 2 TS (Safety-Related) Snubber Population 129 Snubbers | |
ML20217G364 | 9 March 1998 | TS 3/4.8.F Snubber Functional Testing Scope Quad Cities Unit 1 TS (Safety-Related) Snubber Population 118 Snubbers | |
ML20113C913 | 28 June 1996 | NRC USI A-46 Resolution Seismic Evaluation Rept Quad Cities Nuclear Station Units 1 & 2 | Safe Shutdown Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Code Reconciliation Earthquake |
ML20113C922 | 28 June 1996 | A-46 Relay Evaluation Rept for Quad Cites Nuclear Power Station Units 1 & 2 | Safe Shutdown Design basis earthquake Battery sizing Earthquake |
ML20101P098 | 28 March 1996 | Core Spray Flaw Evaluation Rept | Safe Shutdown Earthquake Finite Element Analysis Earthquake Fuel cladding Flow Induced Vibration |
B130172, Safety Evaluation for Quad Cities Unit 1 Core Spray Line Repair | 31 January 1996 | Safety Evaluation for Quad Cities Unit 1 Core Spray Line Repair | Safe Shutdown Abnormal operational transient Flow Induced Vibration |
ML20083L531 | 4 May 1995 | Evaluation of Acceptability of Fddr 1E6AR-FDDR-001 for Shroud Repair Program at Quad Cities Unit 2 | Earthquake |
ML20083K932 | 10 April 1995 | Core Shroud Repair,Design Reliant Structures Insp Requirements & Acceptance Criteria | Nondestructive Examination Finite Element Analysis |
ML20081C289 | 31 March 1995 | Simulator Four Yr Certification Rept,Mar 1995 | Safe Shutdown |
ML20081A746 | 31 March 1995 | First Quad Cities Station Course of Action Progress Rept | |
ML20078S284 | 14 February 1995 | Flaw Tolerance Evaluation Quad Cities Units 1 & 2 Feedwater Nozzles, | |
ML20078D853 | 7 January 1995 | Shroud Stabilizer | |
ML20078D840 | 7 January 1995 | Shroud Stabilizer Hardware | Design basis earthquake Earthquake Liquid penetrant |
ML20078D843 | 7 January 1995 | Reactor Pressure Vessel | Design basis earthquake |
ML20078D851 | 6 January 1995 | Fabrication of Shroud Stabilizer | Nondestructive Examination Liquid penetrant |
ML20086A300 | 31 October 1994 | Reactor Bldg Crane & Cask Yoke Assembly Mods | |
ML20078C613 | 21 October 1994 | Foreign Matl Exclusion Program Deficiencies Level 2 Investigation PIF 94-1837 | Foreign Material Exclusion |
ML20065L222 | 14 April 1994 | Course of Action | High Radiation Area Offsite Dose Calculation Manual FLEX Foreign Material Exclusion Systematic Assessment of Licensee Performance Scaffolding |
ML20155A688 | 30 September 1993 | Evaluation of Min Post-LOCA Heat Removal Requirements to Assure Adequate NPSH for Core Spray & Lpci/Containment Cooling Pumps | Operability Assessment |
ML20056F889 | 23 August 1993 | Rev 1 to COE-301-200, Evaluation & Disposition of IGSCC- Susceptible Welding at Quad Cities Nuclear Power Station Unit 2 1993 Outage | |
ML20082A693 | 31 March 1991 | Structural Evaluation of Com Ed BWR Reactor Pressure Vessel Head Stud Cracking | Hydrostatic |
ML20073A228 | 31 March 1991 | Rev 0 to Evaluation of Quad Cities Penetration Bellows Assemblies Leakage Rates | |
ML20073A214 | 31 March 1991 | Bellows Expansion Joint Design Evaluation Drywell Penetration X-25,Quad Cities Nuclear Power Station,Unit 1 | |
ML20070S890 | 19 March 1991 | Simulator Initial Certification Rept,Mar 1991, Vols 1 & 2 | |
ML20029A059 | 21 November 1990 | Feedwater Line Thermal Hydraulic Behavior During LOCA Conditions for Quad-Cities Nuclear Power Station. | Loop seal |
ML20083A083 | 31 March 1990 | Draft 137-0010,rev 2 to Vessel Fatigue Evaluation Considering Revised Thermal Cycles for Quad Cities Nuclear Station Units 1 & 2 | |
ML17347B462 | 31 December 1989 | App a to USI A-46 & Generic Ltr 87-02. | Safe Shutdown Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Backfit |
ML19332E670 | 26 October 1989 | Rev 1 to Vessel Fatigue Evaluation Considering Revised Thermal Cycles for Quad Cities Nuclear Station,Units 1 & 2. | Finite Element Analysis |
ML20246D687 | 14 August 1989 | Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks | |
ML19327B401 | 31 July 1989 | Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. | |
ML18008A031 | 31 July 1989 | NTH-TR-01 Decrease in Heat Removal by Secondary Sys. | Safe Shutdown Rod Drop Event |
ML20245E801 | 13 July 1989 | Applicability of Pipelocks as Remedy for IGSCC in Bwrs | Weld Overlay |
ML20247H071 | 30 June 1989 | Description & Verification Summary of Computer Program, Gappipe | Earthquake |
ML20246D671 | 30 June 1989 | Criticality Analysis of Byron/Braidwood Fresh Fuel Racks | |
ML20247H079 | 22 June 1989 | App to Description & Verification Summary of Computer Program,Gappipe | |
ML20247N062 | 31 May 1989 | Production Training Dept,Braidwood,Malfunctions & Initial Conditions | |
ML20247L184 | 12 May 1989 | Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 | Packing leak Safe Shutdown Earthquake Liquid penetrant Flow Induced Vibration |
ML20247K301 | 12 May 1989 | Leak-Before-Break Evaluation for Carbon Steel Piping | Safe Shutdown Earthquake Hydrostatic Finite Element Analysis Earthquake Flow Induced Vibration |
ML18094A355 | 30 April 1989 | Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. | Safe Shutdown Earthquake |
ML20245E797 | 31 March 1989 | Rev 1 to Hydrogen Water Chemistry Installation Compliance W/Epri Guidelines for Permanent BWR Hydrogen Water Chemistry Installations Sept 1987 Rev | Tornado Missile Design basis earthquake Fuel cladding |
ML20247F132 | 23 March 1989 | Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment | |
ML20246F637 | 3 March 1989 | Rev 1 to Hydrogen Water Chemistry Installation Rept for Amend to Facility Ol | |
ML20005G421 | 28 February 1989 | Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation. | Hydrostatic |