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INDEXES  and TEXT-BIBLIOGRAPHIC & CATALOGS & INDEXES

Iodine +, Carbon +, Hydrogen +  and Lead +

10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 21 +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.54 +, 10 CFR 20.208 +  and 10 CFR 50.54#F +

SECY 81-84 +, SECY 81-494 +, SECY-81-513 +, SECY-81-440 +, SECY-80-107 +, SECY 80-257 +, SECY-80-366 +, SECY-80-331 +, SECY-81-651 +, SECY 80-371 +  and L 27775 +

Reactor Trip +  and Turbine Trip +

Mark King +  and Office of Management and Program Analysis +

ML20054C869 +, ML20054C869 +, ML20054C869 +, ML20054C869 +, ML20054C869 +, ML20054C869 +  and ML20054C869 +

IEEE 566 +  and IEEE 567 +

Tritium +, Co-60 +  and I-131 +

Westinghouse +  and General Electric +

NUREG-0761, Certified Minutes of ACRS Subcommittees on Site Evaluation & on Reactor Radiological Effects 810430 & 0501 Joint Meeting in Washington,Dc Re 10CFR100,10CFR20,radiation Protection Plan (NUREG-0761) & Health Physics Appraisal Plan +, NUREG/CR-1750 +, NUREG/CR-1901 +, NUREG/CR-2147 +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0731, Summary of 860314 Meeting W/Util in Bethesda,Md Re Qualifications of Radiation Protection Manager as Compared to Qualifications Outlined in 1975 Rev 1 to Reg Guide 1.8, Personnel Selection & Training. Viewgraphs Encl +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, 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-0840, Comments Re Peer Group Review of Draft NRC Fuel Testing Task Force rept.In-vessel Core Damage Progression Must Be Experimentally Addressed +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG/CR-153 +, 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-0499, Fed Register Notice of Issuance & Availability of NRC Staff Rept,Gen Considerations & Issues of Significance on the Eval of Alternative Sites for Nuc Generating Stations Under the Natl Environ Act(NUREG-0499,Suppl 1) +, NUREG-0572, Response in Support of Jf Doherty Contention 46 Re Control Rods Leading to Fuel Damage.Contention Involves New Info Appearing in ACRS Review of LERs 1976-78 rept,NUREG-0572. Certificate of Svc Encl +, NUREG-0728, Responds to Re Offsite Emergency Organization Agreements.Rev 1 to NUREG-0728 Assures That NRC Responds to Incidents Having Potential to Threaten Health & Safety of Public or Environ.Summary of NRC Role in Emergency Encl +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Mike King +, Andrew Hon +  and Thomas Scarbrough +

AM +, ES +, ST +, CH +, SP +, CP +, IMP +  and Emergency Plan +

Regulatory Guide 1.97 +, Regulatory Guide 1.52 +, Regulatory Guide 1.33 +, Regulatory Guide 1.109 +, Regulatory Guide 1.8 +, Regulatory Guide 1.141 +, Regulatory Guide 1.111 +  and Regulatory Guide 1.139 +

SECY 81-84 +, SECY 81-494 +, SECY-81-513 +, SECY-81-440 +, SECY-80-107 +, SECY 80-257 +, SECY-80-366 +, SECY-80-331 +, SECY-81-651 +  and SECY 80-371 +

0M-BASED +, H0H-COMPLIA +, H0H-LINEAR +, B8W-DESIGNE +, N0H-SAFETY +, N0H-CONDENS +, H0H-ESF +  and H0H-LEGISLA +

Manual Scram +  and Automatic Scram +

Idaho +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Safety Parameter Display System +, Core Spray +, Automatic Depressurization System +, Emergency Core Cooling System +, Decay Heat Removal +  and Control Rod +

Safe Shutdown +, Reactor Vessel Water Level +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Probabilistic Risk Assessment +, Shift Technical Advisor +, Loss of Offsite Power +, Backfit +  and Control Room Habitability +