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CONTRACTED REPORT - RTA, QUICK LOOK, ETC. (PERIODIC  and TEXT-PROCUREMENT & CONTRACTS

Boron +, Sodium +  and Lead +

Initiating Events +  and Mitigating Systems +

05000245  +  and 00245  +

Turbine Trip +  and Reactor Trip +

SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY +, Gallagher D +, Amico P +, Atefi B +  and APPLIED RISK TECHNOLOGY CORP. +

ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +, ML20137A629 +  and ML20137A629 +

NUREG/CR-4334 +, NUREG-0993 +, NUREG/CR-2723 +, NUREG/CR-3085 +, NUREG/CR-3010 +, NUREG/CR-2733 +, NUREG-6773 +, NUREG/CR-4155 +, NUREG/CR-2239, Forwards Slides/Handout Used at 821110 Presentation of NUREG/CR-2239 Re Sandia Siting or Consequences Study. Transcript of Meeting in PDR Did Not Include Slides +, NUREG-0880, Transcript of 860619 Commission Meeting in Washington,Dc Re Safety Goals.Pp 1-58.Related Info Encl +, NUREG/CR-2815, Discusses PRA Guidance Documents NUREG/CR-2815 & NUREG/CR-3485.Recasting of Documents in SRP or Reg Guide Formats Recommended Upon Receipt of Public Comments If Documents Reflect Agency Views +, NUREG/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +  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 +

1E-4 +, 1E-3 +, 3E-5 +, 2E-5 +, 7E-7 +, 5E-6 +, 2E-6 +, 2E-3 +, 3E-2 +, 9E-5 +, 9E-6 +, 3E-3 +, 9E-3 +, 8E-6 +, 2E-1 +, 5x10-4 +, 5x10-3 +, 5x10-5 +, 5x10-6 +, 7E-4 +, 5x10-7 +, 3x10-2 +, 2x10-4 +  and 125E-8 +

Manual Scram +  and Automatic Scram +

Washington +  and Virginia +

Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Decay Heat Removal +, Main Condenser +, Control Rod +, Low Pressure Coolant Injection +  and Extraction steam +

Probabilistic Risk Assessment +, Tornado Missile Protection +, Feedwater Heater +, Loss of Offsite Power +, Backfit +  and Control Room Habitability +