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INDEXES  and TEXT-BIBLIOGRAPHIC & CATALOGS & INDEXES

Atomic Energy Act of 1954 +, Endangered Species Act +  and Clean Air Act +

Environmental Protection Agency +, Illinois Department of Nuclear Safety +  and Federal Emergency Management Agency +

Boron +, Uranium +, Radium +, Krypton +, Oxygen +, Sodium +, Hydrogen +, Radon +, Lead +, Helium +, Magnesium +, Titanium +  and Tin +

10 CFR 21 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 72 +, 10 CFR 52 +, 10 CFR 50.2 +, 10 CFR 1 +, 10 CFR 2 +, 10 CFR 40 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 60 +, 10 CFR 61 +, 10 CFR 19.20 +, 10 CFR 50.34 +, 10 CFR 50.47 +, 10 CFR 50.70 +, 10 CFR 50.75 +, 10 CFR 50 Appendix F +, 10 CFR 50.36a +, 10 CFR 50.34a +, 10 CFR 20.106 +, 10 CFR 50.55a#h +  and 10 CFR 52#54 +

Advisory Committee on Reactor Safeguards +  and Advisory Committee on the Medical Uses of Isotopes +

SECY-93-223 +, SECY-93-032 +, SECY-93-049 +, SECY-93-113 +, SECY-93-097 +, SECY-92-200 +, SECY-93-244 +, SECY-91-306 +, CY-1992 +  and SECY 049 +

00114  +, 00130  +, 00133  +, 00171  +, 00206  +, 00267  +, 00312  +, 00320  +, 00322  +, 00344  +  and 00409  +

July 1, 1993  +, March 9, 1993  +, August 23, 1990  +  and January 27, 1992  +

51 FR 30028 +, 52 FR 34884 +, 50 FR 32138 +, 58 FR 41108 +  and 58 FR 44610 +

NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) +  and Meador S +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +  and NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f) +

ML20057F133 +, ML20057F133 +, ML20057F133 +, ML20057F133 +, ML20057F133 +, ML20057F133 +  and ML20057F133 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

Westinghouse +  and General Electric +

NRC Bulletin 93-03 +, NRC Bulletin 92-01 +  and NRC Bulletin 90-01 +

Information Notice 92-54 +, Information Notice 92-46 +, Information Notice 89-42 +, Information Notice 91-47 +, Information Notice 91-79 +, Information Notice 92-55 +, Information Notice 92-82 +, Information Notice 93-40 +, Information Notice 93-41 +  and Information Notice 93-27 +

NUREG-1444 +, NUREG/CR-2850 +, NUREG-1368, Informs Commission of Intent to Publish Final Version of NUREG-1368, Preapplication SER for Power Reactor Innovative Small Module Lmr +, 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-1422 +, NUREG-2907 +, NUREG-1477, Discusses Technical Concerns W/Changes to Draft NUREG-1477 Re Probability of Leakage Curves +, NUREG-1303, Forwards Revs to Incident Investigation manual,NUREG-1303, Deemed Necessary in Order to Effectively Implement Actions Identified in App 4 Coordination Plan +, NUREG-1251, Forwards NUREG-1251, Implications of Accident at Chernobyl for Safety Regulation of Commercial Nuclear Plants in Us. W/O 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-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-0837, Discusses Data Suggesting That Factors Other than Operation of & Releases from Facility Affecting Results of Environ Monitoring Program Re Resin Release in June 1982.Higher Dose Readings & 1982 Release Coincidental.Related Info Encl +, NUREG-2850 +  and DD-87-21, Directors Decision DD-87-21 Denying Addl Relief Requested by Petitioners That Commission Order Immediate Implementation of Relief Noted in 860506 Petition Re Suspension of Further Licensing of Nuclear Plants in Us +

Joseph Holonich +  and Steven West +

Nedo-nes11W +  and Nedo-nalLLW +

SECY-93-223 +, SECY-93-032 +, SECY-93-049 +, SECY-93-113 +, SECY-93-097 +, SECY-92-200 +, SECY-93-244 +, SECY-91-306 +  and SECY 049 +

Texas +, Ohio +, Tennessee +, Pennsylvania +, Connecticut +, Utah +, Arizona +, Georgia +, Illinois +, Colorado +, Minnesota +, Maryland +, North Carolina +, Washington +, California +, Massachusetts +, Alabama +, New Jersey +, South Carolina +, Idaho +, New York +, Michigan +, Wisconsin +, Indiana +, Nebraska +, New Hampshire +, Vermont +, New Mexico +, Oregon +, North Dakota +...

Steam Generator +, Reactor Coolant System +, Primary Containment Isolation System +, Emergency Response Data System +, Shutdown Cooling +, Reactor Pressure Vessel +, Automatic Depressurization System +, Remote shutdown +, Decay Heat Removal +  and Control Rod +

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Fire Barrier +, Probabilistic Risk Assessment +, Decommissioning Funding Plan +, Aging Management +, Annual Radioactive Effluent Release Report +, Notice of Violation +, Stress corrosion cracking +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, License Renewal +, Earthquake +, Chernobyl +, Fuel cladding +, Fire Protection Program +, Brachytherapy +  and Fatality +