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NRC TECHNICAL REPORT, NUREG REPORTS  and TEXT-SAFETY REPORT

Strontium +, Iodine +, Cobalt +, Cesium +, Uranium +, Krypton +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Zirconium +, Lead +, Helium +, Lithium +, Beryllium +, Magnesium +, Aluminum +, Ruthenium +, Tellurium +  and Plutonium +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 51 +, 10 CFR 50 Appendix E +, 10 CFR 100.11 +  and 10 CFR 5#0 +

Emergency Preparedness +  and Mitigating Systems +

NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) +, Office of Nuclear Reactor Regulation +, Pasedag W +, Jankowski M +  and Blond R +

ML20005A692 +, ML20005A692 +, ML20005A692 +, ML20005A692 +, ML20005A692 +, ML20005A692 +, ML20005A692 +, ML20005A692 +, ML20005A692 +  and ML20005A692 +

3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

Strontium-90 +, Cs-137 +, U-235 +, Sr-90 +, Cesium-137 +, Americium-241 +, I-131 +, Iodine-131 +, C-14 +, Yttrium-90 +, Krypton-85 +  and Cobalt-60 +

General Electric +  and Westinghouse +

NUREG/CR-1711 +, NUREG-0112 +, NUREG-0107 +, NUREG-771 +, NUREG-0396, Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs +, 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-0715, Forwards NUREG-0715 in Response to 811228 Request.W/O Encl +, NUREG-0771, Transcript of 810521 Public Meeting Re Briefing on SECY-81- 240,draft NUREG-0771 & 0772 Re Accident Source Term Assumptions,In Washington,Dc.Pp 1-67.Meeting Outline & Viewgraphs Encl +, NUREG-0772, Contract: Evaluate NUREG-0772, Technical Bases for Estimating Fission Product Behavior During LWR Accidents, Awarded to Jl Kelly +, NUREG-0409, Discusses NUREG-0409 Iodine Behavior in PWR Cooling Sys Following Postulated Steam Generator Tube Rupture Accident +, 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 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Maryland +, Washington +, California +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Core Spray +, Standby Gas Treatment System +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +

Probabilistic Risk Assessment +, Fuel cladding +, Operational leakage +  and Potassium iodide +