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Report, Technical  and Training Manual

Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Lead +  and Silver +

10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.47 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.54#s2ii +, 10 CFR 50.47#b4 +  and 10 CFR 50.47#a4 +

05000280  +, 05000281  +, 05000416  +  and 05000417  +

ML023010480 +, ML023010480 +, ML023010480 +, ML023010480 +, ML023010480 +, ML023010480 +, ML023010480 +, ML023010480 +, ML023010480 +, ML023010480 +  and ML023010480 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 0.0156 d (0.375 hours, 0.00223 weeks, 5.13675e-4 months)  +

NEI 97-03 +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

NUREG/CR-6166 +, NUREG-1526 +, NUREG/CR-6143 +, NUREG/CR-1250, Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

SP +  and Emergency Operating Procedure +

Regulatory Guide 1.160 +  and Regulatory Guide 1.101 +

NEDE-2401 +  and NEDE-24011 +

01l-5 +, C6rbels-that +  and 1m-oI +

Grand Gulf +  and Surry +

Tennessee +  and Texas +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Shield Building +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +, Rod Sequence Control System +...

Safe Shutdown +, Unanalyzed Condition +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Half scram +, Stroke time +, Water Inventory Control +, Safe Shutdown Earthquake +, Hydrostatic +, Probabilistic Risk Assessment +, Abnormal operational transient +, Notice of Violation +, Feedwater Heater +, Scram Discharge Volume +, Loss of Offsite Power +, Excess Flow Check Valve +, Breakaway torque +, Overtravel +, Fuel cladding +, Backfit +, Coast down +, Fatality +, Power Uprate +  and Water hammer +