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INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

ASME Section XI +  and ASME Section III +

Iodine +, Uranium +, Hydrogen +  and Lead +

10 CFR 20 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.82 +, 10 CFR 50 Appendix I +  and 10 CFR 50.5a#a +

Hanauer S +  and Office of Nuclear Reactor Regulation +

GDC 17, Electric power systems +  and GDC 53 +

ML20041D085 +, ML20041D085 +, ML20041D085 +, ML20041D085 +, ML20041D085 +, ML20041D085 +, ML20041D085 +, ML20041D085 +  and ML20041D085 +

Westinghouse +, General Electric +  and Target Rock +

NRC Bulletin 78-03 +  and NRC Bulletin 79-07 +

NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG-0471, Responds to 781113 Request & Encl Generic Task Problem Descriptions(NUREG-0471)& NRC Prog for Resolution of Generic Issues Related to Nuc Pwr Plants(NUREG-0410). W/O Encl +, NUREG-0318, Final Response to FOIA Request.Forwards App a Document.App B Documents Withheld (Ref FOIA Exemption 5) +, 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-0772, Contract: Evaluate NUREG-0772, Technical Bases for Estimating Fission Product Behavior During LWR Accidents, Awarded to Jl Kelly +, NUREG-0317 +, NUREG/CR-0660, Forwards Sample Ltr to Applicants,Cp Holders & Licensees of LWRs Transmitting NUREG/CR-0660 Enhancement of Onsite Emergency Diesel Generator Reliability +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl +, NUREG-0666, 03-17-81 NUREG-0666, a Probabilistic Safety Analysis of DC Power Supply Requirements at Nuclear Power Plants +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Mike King +  and George Thomas +

ES +, CP +  and IMP +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 8.8 +, Regulatory Guide 1.86 +, Regulatory Guide 1.133 +, Regulatory Guide 1.20 +, Regulatory Guide 4.2 +, Regulatory Guide 1.139 +  and Regulatory Guide 1.96 +

Idaho +, Vermont +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +

Eisenhut D +, Vollmer R +, Office of Nuclear Reactor Regulation +  and Mattson R +

Ultimate heat sink +, Tornado Missile +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Process Control Program +, Stress corrosion cracking +, Earthquake +, Control of Heavy Loads +, Power Operated Valves +, Turbine Missile +, Fuel cladding +, Backfit +, Overspeed +, Simmer margin +, Thermal fatigue +, Water hammer +  and Control Room Habitability +