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TEXT-SAFETY REPORT  and Probabilistic Risk Assessment

Boron +, Carbon +, Hydrogen +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 50 +  and 10 CFR 0 +

Emergency Preparedness +  and Initiating Events +

S.1(n) +, P.6(e) +, P.8(i) +, P.6(t) +, S.5(d) +  and P.6(j) +

Turbine Trip +  and Reactor Trip +

PLG +, INC. (FORMERLY PICKARD +, LOWE & GARRICK +, INC.) +, Garrick B +, Iden D +  and Hubbard F +

ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +, ML20155J921 +  and ML20155J921 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +

Westinghouse +  and General Electric +

NUREG/CR-2300 +, NUREG-0880, Transcript of 860619 Commission Meeting in Washington,Dc Re Safety Goals.Pp 1-58.Related Info Encl +, 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 +, 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 +, NUREG-0718, Forwards Final Rule on Licensing Requirements for Pending CP & Mfg License Applications & NUREG-0718,Revision 2.SER Comparison to New Requirements Revealed Util Commitments & CP Conditions Conform to Nureg.W/O NUREG +, NUREG-0020, Responds to Encl Re Spent Fuel Storage Capacity at Plant.Spent Fuel Pool at Plant Has Sufficient Space to Accommodate Addl Fuel Storage Racks of Current Design +, NUREG-0642, Forwards NUREG-0642 in Response to .Final NRC Action Plans Being Prepared & Final Form of Rogovin Rept, Vol II Being Printed.Both Documents Will Be Furnished Upon Issuance.W/O Encl +, 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-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

AM +, RT +, AM-1 +, AM-l +  and AM.GA +

D4I-1 +, 6C-385t +, 7t-Stef +, 8C-F +  and 9C-iii9 +

Pennsylvania +, Washington +, California +, Massachusetts +, Virginia +, New Jersey +, New York +  and Alaska +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, HVAC +, Reactor Building Ventilation +, Circulating Water System +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Electrohydraulic Control +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +, Low Pressure Coolant Injection +  and Emergency Feedwater System +

Boric Acid +, High winds +, Ultimate heat sink +, Mission time +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, High Energy Line Break +, Shift Technical Advisor +, Loss of Offsite Power +, Earthquake +, Turbine Missile +, Overspeed +  and Basic Component +

Susquehanna River +  and Cooling Tower +