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INDEXES  and TEXT-BIBLIOGRAPHIC & CATALOGS & INDEXES

Boron +, Iodine +, Uranium +, Carbon +, Hydrogen +, Chlorine +  and Tin +

10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.4 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 20.302 +, 10 CFR 6 +, 10 CFR 53.62 +, 10 CFR 50.46t#A +, 10 CFR 5#b +  and 10 CFR 50.46#A +

05000327  +, 05000328  +, 00327  +, 00328  +, 00329  +  and 00323  +

ENS 23 +, ENS 201 +, ENS 220 +, ENS 207 +, ENS 235 +, ENS 231 +, ENS 230 +, ENS 223 +, ENS 229 +, ENS 224 +, ENS 222 +, ENS 215 +, ENS 213 +, ENS 205 +, ENS 204 +, ENS 203 +, ENS 241 +, ENS 232 +, ENS 237 +, ENS 226 +, ENS 239 +  and ENS 221 +

Reactor Trip +  and Turbine Trip +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 80-24, Transmittal of Information on NRC "Nuclear Data Link Specifications" +, NRC Generic Letter 81-21, Natural Circulation Cooldown +, NRC Generic Letter 81-04, Emergency Procedures And Training for Station Blackout Events +, NRC Generic Letter 83-43, Reporting Requirements of 10 CFR 50, Sections 50.72 and 50.73, and Standard Technical Specifications +, NRC Generic Letter 83-36, NUREG-0737 Technical Specifications +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-02, NUREG-0737 Technical Specifications +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +, NRC Generic Letter 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 88-06, Removal of Organization Charts from Technical Specification Administrative Control Requirements +, NRC Generic Letter 88-03, Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps" +, 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 89-09, ASME Section III Component Replacements +, NRC Generic Letter 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs +, NRC Generic Letter 89-06, Task Action Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54 (f) +, NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +, NRC Generic Letter 90-03, Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2, "Vendor Interface for Safety-Related Components" +, NRC Generic Letter 90-02, Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, NRC Generic Letter 38-05 +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML20029A809 +, ML20029A809 +, ML20029A809 +, ML20029A809 +, ML20029A809 +, ML20029A809 +, ML20029A809 +, ML20029A809 +, ML20029A809 +  and ML20029A809 +

Westinghouse +, Valcor +, B080 +  and F075 +

NRC Bulletin 89-02 +  and NRC Bulletin 90-01 +

Information Notice 88-03 +  and Information Notice 88-02 +

NUREG-073 +, NUREG-6737 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

AM +, ES +, ST +, CH +, MP +, SP +, RT +, TP +, CP +, IMP +, Emergency Plan +, JF +, CP-1 +  and SP-I +

SR-4.6.5 +, SR-4.6.5.I.6 +  and SR-4.4.11.A +

8L-79-07 +, 0VER-TORQUE +, 8FC-R00108 +  and F8f-M75752 +

Steam Generator +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, HVAC +, Decay Heat Removal +  and Control Rod +

TS-3.9.2 +, TS-3.6 +, TS-3.0.4 +, TS-3.4.1.4 +, TS-3.9 +  and TS-6.9.1.4 +

Boric Acid +, Shutdown Margin +, Hydrostatic +, Anchor Darling +, FLEX +, Feedwater Heater +, Shift Technical Advisor +, Exemption Request +, Control of Heavy Loads +, Water hammer +, Control Room Habitability +  and Spent fuel rack +