Browse wiki

Strontium +, Iodine +, Cesium +, Hydrogen +, Lead +, Ruthenium +, Tellurium +, Barium +  and Cerium +

10 CFR 50.67 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +  and 10 CFR 100 +

EC-119 +, EC-121 +  and EC-463 +

ML040500297 +, ML040500297 +, ML040500297 +, ML040500297 +, ML040500297 +, ML040500297 +, ML040500297 +, ML040500297 +, ML040500297 +  and ML040500297 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-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)  +  and 7.986111e-4 d (0.0192 hours, 1.140873e-4 weeks, 2.62545e-5 months)  +

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

NUREG/CR-6604 +, NUREG/CR-6189 +, NUREG/CR-5966 +, NUREG/CR-0009 +, NUREG-6189 +, NUREG-0989, Safety Evaluation Supporting Proposed Turbine Maint Program. Proposal Satisfies Licensee Commitment Prescribed in Sser 5. Commitment Acceptable Resolution of Turbine Maint Issue +, 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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

ST +  and SP +

Regulatory Guide 1.183 +, Regulatory Guide 1.3 +, Regulatory Guide 1.52 +  and Regulatory Guide 1.49 +

SR-3.6.1.3 +, SR-3.6.1.3.9 +  and SR-0.00 +

1E-5 +  and 1E-4 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary containment +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Standby Gas Treatment System +, Shield Building +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +

TS-3.6.1.3 +  and TS-5.5.7.c +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Stroke time +, Safe Shutdown Earthquake +, Loss of Offsite Power +, Deep Dose Equivalent +, Fuel cladding +  and Power Uprate +