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ANSI B31.1 +  and ANSI N18.2 +

ASME Section III +  and ASME Section VIII +

Iodine +, Iron +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chloride +, Lead +, Phosphorus +  and Sulfur +

10 CFR 50 Appendix R +, 10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +  and 10 CFR 50 Appendix I +

RS-20-153, Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-1 +  and ND 2311 +

H.2(y) +, P.1(o) +  and P.1(f) +

05000454  +, 05000455  +, 05000456  +, 05000457  +, 07200068  +  and 07200073  +

Turbine Trip +  and Reactor Trip +

05000373/FSAR-10.4 +, 05000373/FSAR-10.2 +, 05000373/FSAR-10.1 +  and Category:05000373/FSAR Chapter 10 +

ML21008A406 +, ML21008A406 +, ML21008A406 +, ML21008A406 +, ML21008A406 +, ML21008A406 +, ML21008A406 +, ML21008A406 +, ML21008A406 +, ML21008A406 +  and ML21008A406 +

5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-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)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG-0876, Advises That Preservice Insp Program,Described in Util 860723,0902,30 & 1016 Ltrs,Acceptable & in Compliance W/ 10CFR50.55a(g)(3).Safety Evaluation Will Be Included in Sser 7 (NUREG-0876) +  and NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +

ES +, IMP +  and Emergency Plan +

108D685-7 +, 108D685-10 +  and 71-1E7-MSLRF-Pl +

Byron +  and Braidwood +

Pennsylvania +  and Illinois +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Turbine +, Residual Heat Removal +, Circulating Water System +, Remote shutdown +, Stator Cooling Water +, Steam Jet Air Ejector +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Electrohydraulic Control +, Moisture Separator Reheater +, Main Condenser +, Control Rod +, Main Steam +, Extraction steam +  and Turbine Gland Sealing System +

05000373/TS-3.7.6 +  and 05000373/TS-3.7.5 +

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

Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Grab sample +, Safe Shutdown Earthquake +, Hydrostatic +, Zebra Mussel +, FLEX +, High Energy Line Break +, Abnormal operational transient +, Feedwater Heater +, Stress corrosion cracking +, Loss of Offsite Power +, Power-Operated Valves +, Turbine Missile +, Power Uprate +, Measurement Uncertainty Recapture +, Overspeed trip +, Overspeed +, Loss of condenser vacuum +  and Water hammer +

Cooling Tower +  and Kankakee River +