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Boron +, Iodine +, Cobalt +, Cesium +, Uranium +, Nickel +, Gadolinium +, Oxygen +, Sodium +, Hydrogen +, Zirconium +, Lead +  and Gold +

10 CFR 50 Appendix R +, 10 CFR 50.67 +, 10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 30 +, 10 CFR 50.59 +, 10 CFR 71 +, 10 CFR 20.1201 +, 10 CFR 20.1301 +, 10 CFR 50.44 +, 10 CFR 50.57 +, 10 CFR 50.62 +, 10 CFR 50.90 +, 10 CFR 50.91 +, 10 CFR 50 Appendix I +, 10 CFR 100.11 +, 10 CFR 20.1101 +, 10 CFR 50.67#b2 +, 10 CFR 50.36#c4 +, 10 CFR 50.62#c4 +, 10 CFR 50.62#c3 +, 10 CFR 20.1101#b +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +

05000354  +  and 00354  +

Regulatory Guide 1.183 +, ML053460347 +, ML072260045 +, ML993140059 +, ML003740166 +, ML062690073 +, ML992870043 +, ML081230540 +, ML011230531 +, ML091340082 +, ML083530224 +, ML070850183 +, ML102230240 +, ML102240335 +, ML071070420 +, ML010660227 +, ML012600176 +, LR-N10-0341, Supplement - License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project) +, LR-N10-0357, Supplement - License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project) +, ML102440026 +, ML101390320 +, ML101390315 +, ML093640193 +, LR-N10-0289, Response to Request for Additional Information - License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project) +, LR-N10-0217, Supplemental Safety Analysis Report Information - License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project) +, LR-N10-0210, Response to Request for Additional Information, License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies +, ML101170113 +, ML100990403 +, ML072290203 +, ML100970126 +...

Turbine Trip +  and Reactor Trip +

ZIRLO +  and Zircaloy +

GDC 10 +  and GDC 19, Control room +

ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +, ML102710156 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +

Union of Concerned Scientists +  and Sierra Club +

Co-60 +, U-235 +, Kr-85 +  and Cobalt-60 +

IR 05000354/2010003 +, LR-N10-0181, Supplement to RAI Responses Submitted in PSEG Letter LR-N10-0181 Dated June 1, 2010, Related to the Severe Accident Mitigation Alternatives Review +, ML101100432 +  and HCH-2009-142, Discharge Monitoring Report, NJPDES Permit NJ0025411 +

NUREG-1433 +, NUREG/CR-5927 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-1455, Forwards AEOD/E93-03, Engineering Evaluation Rept, Electrical Inverter Operating Experience - 1985 to 1992. Findings Show That Inverter Failures Continue to Cause ESF Actuations,Reactor Trips & Turbine Runbacks +

TOP +  and SP-1 +

NEDO-32465 +, NEDO-31960 +, NEDC-32694P +, NEDE-24011 +, NEDC-33173P +, NEDO-24154 +, NEDC-32084P +, NEDC-32851 +, NEDC-33076P +, NEDC-33529P +, NEDO-33529 +  and NEDO-33539 +

L1C-1 +, 3D-Simulat +  and 3D-simulat +

Washington +, California +  and New Jersey +

Reactor Coolant System +, Feedwater +, Secondary containment +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Room Envelope +, Control Rod +, Main Steam +  and Containment Spray +

TS-6.8.4.a +, TS-5.3.1 +, TS-6.16 +  and TS-4.2.1 +

Safe Shutdown +, Shutdown Margin +, Safety Limit Minimum Critical Power Ratio +, Anticipated operational occurrence +, Finite Element Analysis +, Abnormal operational transient +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Feedwater Controller Failure +, MELLLA +, Commercial Grade +, Fuel cladding +, Fire Protection Program +, Power Uprate +, Water rod +, Loss of condenser vacuum +  and Control Room Habitability +