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IWB-3410 +, IWB-3500 +, IWB-2500 +, IWB-3000 +, IWC-2500 +, IWB-5000 +, IWB-2420 +, IWB-2400 +, IWC-2400 +, IWA-2430 +, IWA-2200 +  and IWA-4000 +

ASME Section XI +, ASME Section III +, ASME Section I +  and ASME Section VIII +

Iodine +, Iron +, Nickel +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chloride +  and Lead +

BWRVIP-75 +, BWRVIP-86 +  and BWRVIP-78 +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.49 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 10.60#a +  and 10 CFR 50.55a#g6i +

ASME Code Case N-640 +  and ASME Code Case N-588 +

05000254  +  and 05000265  +

Drawing 5.1-3 +  and Drawing 5.2-8 +

NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety- Related Power-Operated Gate Valves +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

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 +, 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 +, 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 +, 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 +, 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 +, 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 +, 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 +, 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 +, 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 +  and 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 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

Westinghouse +, Limitorque +, General Electric +  and Target Rock +

NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +

RT +, ISP +  and TOP +

Regulatory Guide 1.45 +, Regulatory Guide 1.70 +, Regulatory Guide 1.26 +, Regulatory Guide 1.190 +, Regulatory Guide 1.99 +, Regulatory Guide 1.50 +, Regulatory Guide 1.44 +  and Regulatory Guide 1.34 +

Tennessee +  and Illinois +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

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 +  and Thermal fatigue +