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Boron +, Strontium +, Iodine +, Cesium +, Uranium +, Krypton +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Chloride +, Lead +, Tellurium +, Barium +  and Cerium +

10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 50.62 +, 10 CFR 50.100, Revocation, Suspension, Modification of Licenses, Permits, and Approvals for Cause +, 10 CFR 50 Appendix I +, 10 CFR 50.67#a +  and 10 CFR 50.71#e +

NRC-16-0034, 0 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System +  and NRC 0102 +

05000341  +  and 07200071  +

Turbine Trip +  and Reactor Trip +

GDC 44 +  and GDC 19, Control room +

NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15 +, NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15 +, NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15 +, NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15 +, NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15 +, NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15 +, NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15 +, NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15 +, NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15 +  and NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 0.00175 d (0.0419 hours, 2.496693e-4 weeks, 5.74555e-5 months)  +

Tritium +, Am-241 +, Co-60 +, Cs-137 +, Sr-90 +, Fe-55 +, Y-90 +, Ni-63 +, Kr-85 +, I-131 +, Cu-64 +, N-16 +, Iodine-131 +, H-3 +, Mo-99 +, Mn-54 +, Pu-238 +  and Pu-239 +

NRC-16-0034, 0 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System +  and NRC 0102 +

NUREG/CR-6604 +, NUREG/CR-5009, Forwards NUREG/CR-5009, Assessment of Use of Extended Burnup Fuel in Lwrs. Rept Concludes That Environmentally, Burnup Increase Would Have No Significant Impact Over That of Normal Burnup.W/O Encl +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

TAC:MF0650 +, TAC:MA0720 +, TAC:69074 +, TAC:67098 +, TAC:M82102 +  and TAC:77676 +

Regulatory Guide 1.183 +, Regulatory Guide 1.25 +, Regulatory Guide 1.3 +, Regulatory Guide 1.49 +, Regulatory Guide 1.70 +, Regulatory Guide 1.143 +, Regulatory Guide 1.109 +, Regulatory Guide 1.29 +, Regulatory Guide 1.5 +  and Regulatory Guide 1.98 +

NEDO-24708A +, NEDO-10527 +, NEDC-32938P +, NEDO-10585 +, NEDO-21231 +, NEDC-31897P +, NEDC-32868P +, NEDE-31152P +, NEDC-31984P +, NEDO-21143 +, NEDO-21142 +, NEDO-20360 +, NEDC-32313P +, NEDO-23842 +, NEDC-31843P +, NEDC-32963A +  and NEDO-12154 +

15A-1 +, 07-96-720 +, 15A-2 +, 15A-3 +, 050E-02 +  and 15A-2a +

Fermi +  and 07200071 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +, Moisture Separator Reheater +, Main Condenser +...

Office of Nuclear Material Safety and Safeguards +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Safety Limit Minimum Critical Power Ratio +, Stroke time +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Abnormal operational transient +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Feedwater Controller Failure +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Earthquake +, Fuel cladding +, Recently irradiated fuel +, Fire Protection Program +, Power change +, Power Uprate +, Measurement Uncertainty Recapture +, Failure to Scram +, Overspeed +, Loss of condenser vacuum +  and Basic Component +

Turbine bypass valve +  and Main Turbine Control Valve +