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Boron +, Iodine +, Cesium +, Uranium +, Carbon +, Sodium +, Hydrogen +, Xenon +, Lead +, Tin +, Tellurium +, Cerium +  and Samarium +

10 CFR 50.67 +, 10 CFR 21 +, 10 CFR 20 +, 10 CFR 50 Appendix K +, 10 CFR 100 +  and 10 CFR 50 +

RS-11-159, Updated Final Safety Analysis Report, Revision 11 +  and ND-147 +

05000254  +, 05000265  +, 00237  +, 00245  +, 00254  +  and 00265  +

Turbine Trip +  and Reactor Trip +

GDC 10 +  and GDC 19, Control room +

RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses +  and RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 1.736111e-4 d (0.00417 hours, 2.480159e-5 weeks, 5.7075e-6 months)  +

Am-241 +, Co-60 +, Cs-137 +, Sr-90 +, Y-90 +, Kr-85 +, I-131 +, N-16 +  and Mo-99 +

Westinghouse +  and General Electric +

NUREG/CR-6604 +, NUREG-0373 +, NUREG/CR-009 +, NUREG/CR-6331, Discusses 970627 Meeting Between W & NRC Re Assessment of Atmospheric Dispersion Re W AP600 Control Room Habitability. Believes W Should Consider Use of Alternative Methodology, Described in Rev 1 to NUREG/CR-6331 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

AM-241 +  and Emergency Operating Procedure +

Regulatory Guide 1.183 +, Regulatory Guide 1.25 +, Regulatory Guide 1.194 +, Regulatory Guide 1.3 +, Regulatory Guide 1.49 +, Regulatory Guide 1.145 +, Regulatory Guide 1.77 +  and Regulatory Guide 1.5 +

NEDO-32465 +, NEDO-31960 +, NEDC-32424P +, NEDO-21231 +, NEDO-31400A +, NEDC-32868P +, NEDO-33091 +, NEDO-10958 +, NEDC-32961P +, NEDO-24807 +, NEDE-25026 +  and NEDE-31152 +

Tennessee +, Colorado +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +, Main Steam Safety Valve +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Shutdown Margin +, Reactor Vessel Water Level +, Stroke time +, Anticipated operational occurrence +, Hydrostatic +, Feedwater Heater +, Scram Discharge Volume +, Feedwater Controller Failure +, MELLLA +, Loss of Offsite Power +, Fast acting solenoid valve +, Main Steam Line Radiation Monitor +, Overtravel +, Deep Dose Equivalent +, Fuel cladding +, Power Uprate +, Overspeed +, Loss of condenser vacuum +, Potassium iodide +  and Control Room Habitability +

Turbine bypass valve +  and Main Turbine Control Valve +