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

Lead +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 100.11 +  and 10 CFR 50.55a#h +

Mitigating Systems +  and Initiating Events +

Reactor Trip +  and Turbine Trip +

SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY +, SANDIA NATIONAL LABORATORIES +, Gallagher D +, Amico P +, Spulak R +  and Stack D +

GDC 44 +, GDC 15 +, GDC 10 +, GDC 18 +, GDC 13 +, GDC 37 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +  and GDC 19, Control room +

ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +, ML20083F796 +  and ML20083F796 +

0.00194 d (0.0467 hours, 2.777778e-4 weeks, 6.3924e-5 months)  +, 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)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

IEEE 279 +, IEEE 279-1971 +  and IEEE 500 +

NUREG-0823, Supplement No. 1, Integrated Plant Safety Assessment, Systematic Evaluation Program +, NUREG/CR-0165 +, NUREG-0822, Safety Evaluation Finding Integrated Plant SAR (NUREG-0822), Section 4.12 Complete W/Exception of Three Issues,Including Evaluation of Drywell for Concrete Subj to High Temps & Thermal Transients +, NUREG/CR-3233 +, 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 +  and NUREG-0666, 03-17-81 NUREG-0666, a Probabilistic Safety Analysis of DC Power Supply Requirements at Nuclear Power Plants +

ES +, ST +, CH +, MP +  and SP +

Regulatory Guide 1.45 +, Regulatory Guide 1.106 +, Regulatory Guide 1.133 +, Regulatory Guide 1.22 +  and Regulatory Guide 1.139 +

22A-1 +, 2A-3NE +, 101AB-1 +, 101AB-2 +, 101AB-3 +, 11UREG-0933 +, 12UI-7 +, 12E-12F +, 12C-12D +, 6AP-1 +  and 1Ryr-1 +

Maryland +, Washington +  and New York +

Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Shutdown Cooling +, Reactor Recirculation Pump +, Core Spray +, Reactor Water Cleanup +, Standby Gas Treatment System +, Emergency Core Cooling System +, Main Steam Line +  and Low Pressure Coolant Injection +

Safe Shutdown +, High Radiation Area +, Ultimate heat sink +, Tornado Missile +, Probabilistic Risk Assessment +, Earthquake +, Turbine Missile +, Pressure Boundary Leakage +, Backfit +, Overspeed +, Loss of condenser vacuum +  and Leak-Before-Break +