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NRC TECHNICAL REPORT, NUREG REPORTS  and TEXT-SAFETY REPORT

Boron +, Uranium +, Carbon +, Sodium +, Hydrogen +, Radon +  and Lead +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 35 +, 10 CFR 72 +, 10 CFR 52 +, 10 CFR 60 +, 10 CFR 61 +, 10 CFR 62 +, 10 CFR 73 +, 10 CFR 150 +, 10 CFR 50.62 +, 10 CFR 70#72 +  and 10 CFR 50.62#c4 +

Emergency Preparedness +  and Physical Protection +

SECY-89-183 +  and SECY-89-017 +

52 FR 34884 +  and 50 FR 32138 +

NRC Generic Letter 88-17, Loss of Decay Heat Removal +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-11, Resolution of Generic Issue 101 "Boiling Water Reactor Water Level Redundancy" +, NRC Generic Letter 89-09, ASME Section III Component Replacements +, NRC Generic Letter 89-06, Task Action Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54 (f) +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML20042E914 +, ML20042E914 +, ML20042E914 +, ML20042E914 +, ML20042E914 +  and ML20042E914 +

9.259259e-4 d (0.0222 hours, 1.322751e-4 weeks, 3.044e-5 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

NUREG/CR-4330 +, NUREG/CR-5275 +, NUREG/CR-1161 +, NUREG/CR-5250 +, NUREG/CR-3480 +, NUREG-1369 +, NUREG/CR-4234 +, NUREG/CR-5000 +, NUREG/CR-5193 +, NUREG-1384 +, NUREG-1368, Informs Commission of Intent to Publish Final Version of NUREG-1368, Preapplication SER for Power Reactor Innovative Small Module Lmr +, NUREG/CR-4618 +, NUREG/CR-5351 +, NUREG/CR-5332 +, NUREG-1266 +, NUREG/CR-4214, Comments on Quantification of Public Health Risks.Nrc Should Be Encouraged to Use Health Effects Models Noted in NUREG/CR-4214 & SECY-86-8 in Preparation of Environ Assessment & Pra.Addl Comments Provided +, NUREG-1260 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1317, Forwards Correspondence from Listed Utils & Law Firms in Response to Request for Comments on NUREG-1317.W/o Encls +, NUREG-1174, Summary of CRGR Meeting 163 on 890524 Re Proposed Generic Ltr on Emergency Response Data Sys,Usi A-17 on Sys Interactions,Generic Issue A-30 on safety-related Dc Power Sys & USI A-47 on Control Sys +, NUREG-1229, Forwards Revised Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Package Requested to Be Revised to State More Explicitly Proposed Actions Taken by Licensees & by Nrc.Issue Identified as Category 2 Action +, NUREG-1251, Forwards NUREG-1251, Implications of Accident at Chernobyl for Safety Regulation of Commercial Nuclear Plants in Us. W/O Encl +, NUREG-1335, Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Associated Guidance, NUREG-1335 +, NUREG-1338, Responds to Ltr to Wd Travers, Re Small,Modular, pebble-bed Reactor Design.Some Background Info & Guidance on Licensing gas-cooled Reactor Designs Can Be Found in NRC Staff repts;NUREG-1226,NUREG-1338 & NUREG-1512 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG/CR-5100 +, NUREG-1217, Forwards NRC Resolution of USI A-47, Safety Implications of Control Sys, for Info.Resolution Consists of NUREG-1217, Evaluation of Safety Implications...Technical Findings Re USI A-47 & NUREG-1218, Regulatory Analysis.... W/O Encls +, NUREG-1370, Requests That Util Clearly & Specifically Address Compliance W/Requirements of 10CFR50.44 in Individual Plant Exam Submittal +, NUREG/CR-4884, Advises That Assessing Intakes of Radioactive Matl Using Bioassay Data Should Be Based on Best Data & Models Available.Licensee May Use Improved & Accepted Methodology Provided in Recent Icrp Publications & NUREG/CR-4884 +, NUREG-1218, Disapproves 900320 Response to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs +...

AM +, CH +, Emergency Operating Procedure +, SP-90 +, ST-1 +  and ISP-24 +

Regulatory Guide 1.9 +, Regulatory Guide 1.86 +, Regulatory Guide 1.114 +, Regulatory Guide 3.61 +, Regulatory Guide 3.62 +, Regulatory Guide 3.44 +  and Regulatory Guide 3.64 +

SECY-89-183 +  and SECY-89-017 +

Ohio +, Tennessee +, Kansas +, Arizona +, Georgia +, Illinois +, Maryland +, Washington +, California +, Massachusetts +, Virginia +, South Carolina +, Idaho +, New York +, Oklahoma +, Indiana +, Nebraska +, New Mexico +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, Standby Liquid Control +  and Control Rod +

High winds +, Ultimate heat sink +, Weld Overlay +, Hydrostatic +, Probabilistic Risk Assessment +, Nondestructive Examination +, Aging Management +, Abnormal operational transient +, Stress corrosion cracking +, Loss of Offsite Power +, License Renewal +, Earthquake +, Hardened vent +, Chernobyl +, Fuel cladding +, Backfit +, Overexposure +, Failure to Scram +  and Leak-Before-Break +