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TEXT-SAFETY REPORT  and Probabilistic Risk Assessment

Boron +, Iodine +, Cesium +, Oxygen +, Hydrogen +, Zirconium +, Lead +  and Tellurium +

Initiating Events +  and Mitigating Systems +

05000352  +, 05000353  +, 00352  +, 00247  +  and 00286  +

Exelon +  and (FORMERLY PHILADELPHIA ELECTRIC +

ML20054E969 +, ML20054E969 +, ML20054E969 +, ML20054E969 +, ML20054E969 +, ML20054E969 +, ML20054E969 +, ML20054E969 +, ML20054E969 +  and ML20054E969 +

2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 8.101852e-4 d (0.0194 hours, 1.157407e-4 weeks, 2.6635e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +  and 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +

Co-60 +, Cs-137 +  and Sr-90 +

General Electric +  and Target Rock +

NUREG/CR-2300 +, NUREG/CR-1362 +, NUREG/CR-1131 +, NUREG/CR-0460 +, NUREG/CR-1205, Lists LERs Re HPCI & RCIC Sys Failures,Not Included in NUREG/CR-1205 on LERs Related to Pumps.Probabilistic Analysis Branch Should Correct Classification Deficiencies +, NUREG-0772, Contract: Evaluate NUREG-0772, Technical Bases for Estimating Fission Product Behavior During LWR Accidents, Awarded to Jl Kelly +, NUREG/CR-0400, Forwards NRC Policy Statement Re Reactor Safety Study,Review by the Lewis Committee (NUREG/CR-0400) & Survey of NRC Uses of WASH-1400.All Documents Have Been Furnished to ASLB & Aslab Panel Members.W/O Encl +, 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-0460 +

NEDO-24708 +  and NEDO-25420 +

1E-4 +, 2E-5 +, 1x10-5 +, 2x10-3 +, 5x10-3 +, 1o-8 +, 1x10-3 +, 1x10-z +, 7x10-3 +, 2x10-5 +, 3x10-5 +, 9E-4 +, 8E-5 +, 2x10-a +, 2x10-s +  and 3to-I +

Ohio +, Pennsylvania +, Connecticut +, North Carolina +, Washington +, California +, Massachusetts +, Virginia +, New Jersey +, Idaho +, New York +, Kentucky +, Michigan +  and Delaware +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Steam Jet Air Ejector +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Rod Sequence Control System +, Main Condenser +, Control Rod +, Containment Spray +  and Low Pressure Coolant Injection +

Safe Shutdown +, Probabilistic Risk Assessment +, Finite Element Analysis +, Loss of Offsite Power +, Liquid penetrant +, Fatality +, Failure to Scram +, Loss of condenser vacuum +, Leak-Before-Break +  and Leak Before Break +