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NRC TECHNICAL REPORT, NUREG REPORTS  and TEXT-SAFETY REPORT

Boron +, Iodine +, Iron +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Lead +  and Aluminum +

10 CFR 50 +, 10 CFR 50.55 +, 10 CFR 50.44 +, 10 CFR 50.60 +, 10 CFR 50.54 +, 10 CFR 46 +, 10 CFR 50.54#f +, 10 CFR 50.54#F +  and 10 CFR 50.44#C +

SECY-93-048 +, L-93-03 +, L-92-01 +, SECY-92-130 +, L 41 +  and L-89-02 +

Reactor Trip +  and Turbine Trip +

NRC Generic Letter 93-06, Research Results on Generic Safety Issue 106, "Piping and the Use of Highly Combustible Gases in Vital Areas" +, NRC Generic Letter 97-06, Degradation of Steam Generator Internals +, 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 79-58, ECCS Calculations on Fuel Cladding +, NRC Generic Letter 79-43, Reactor Cavity Seal Ring Generic Issue +, NRC Generic Letter 79-36, Adequacy of Station Electric Distribution Systems Voltages +, NRC Generic Letter 79-33, Transmitting NUREG-0576 - Security Training and Qualification Plans +, NRC Generic Letter 79-25, Information Required to Review Corporate Capabilities +, NRC Generic Letter 80-99, Technical Specification Revisions For Snubber Surveillance +, NRC Generic Letter 80-30, Clarification of the Term "Operable" As It Applies to Single Failure Criterion For Safety Systems Required by TS +, NRC Generic Letter 80-14, LWR Primary Coolant System Pressure Isolation Valves +, NRC Generic Letter 80-02, Quality Assurance Requirements Regarding Diesel Generator Fuel Oil +, NRC Generic Letter 81-21, Natural Circulation Cooldown +, NRC Generic Letter 81-14, Seismic Qualifications for Auxiliary Feedwater Systems +, NRC Generic Letter 81-04, Emergency Procedures And Training for Station Blackout Events +, NRC Generic Letter 81-01, Qualification of Inspection, Examination, Testing and Audit Personnel +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-43, Reporting Requirements of 10 CFR 50, Sections 50.72 and 50.73, and Standard Technical Specifications +, NRC Generic Letter 83-20, Integrated Scheduling for Implementation of Plant Modifications +, NRC Generic Letter 83-08, Modification of Vacuum Breakers on Mark I Containments +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 84-13, Technical Specification for Snubbers +, NRC Generic Letter 84-09, Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii) +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +, NRC Generic Letter 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements +, 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 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +...

ML20063H746 +, ML20063H746 +, ML20063H746 +, ML20063H746 +, ML20063H746 +, ML20063H746 +  and ML20063H746 +

TI 2515/119 +  and TI 2515/114 +

L-93-03 +, L-92-01 +, L 41 +  and L-89-02 +

Westinghouse +, General Electric +, B080 +, F075 +  and B058 +

NRC Bulletin 88-04 +, NRC Bulletin 93-03 +, NRC Bulletin 93-02 +, NRC Bulletin 90-01 +  and NRC Bulletin 89-01 +

Information Notice 92-46 +, Information Notice 89-42 +, Information Notice 91-47 +, Information Notice 91-79 +, Information Notice 90-40 +  and Information Notice 88-80 +

NUREG-1435, Forwards Suppl 2 to NUREG-1435 Containing Most Recent Assessment of Licensee Actions & Committments Re TMI Action Plan Requirements.W/O Encl +, NUREG-1342, Discusses New multi-plant Action MPA F-72, SPDS-Response to Generic Ltr 89-06, Initiated to Accurately Reflect Status of SPDS Issue in Sims.Procedures Should Be Followed by Affected Plants as Indicated +, NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +, 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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0567, Comments on NUREG-0567, Proposed Policy & Procedures for Differing Prof Opinions. Procedures Will Lead to Better Interchange of Prof Views & More Complete Basis for Decisionmaking +, NUREG-0510, Responds to 790614 Questions Re Status & Future of Nuclear Power in Mi.Nrc Has Summarized Historical & Economic Data Requested.Forwards NUREG-0510.Cover Sheet Only Encl +, NUREG-1370, Requests That Util Clearly & Specifically Address Compliance W/Requirements of 10CFR50.44 in Individual Plant Exam Submittal +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +  and NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +

ES +, ST +, MP +, SP +  and IMP +

Regulatory Guide 1.97 +  and Regulatory Guide 1.99 +

SECY-93-048 +  and SECY-92-130 +

1Y-RELATED +, 0F-THE +, C00K-1 +, 8L-88-04 +, 8L-88-08 +, 8L-92-01 +, 100l-SHIFT +, 1MPA-F071 +, 8L-88-03 +, 8L-88-07 +, 8L-88-11 +, 8L-92 +, 8L-93-02 +, 8L-93-03 +, T4ElWED-LAG +, 14T-m +, 5F4-8116 +  and 8FA-3118 +

Texas +, Maryland +, Washington +, New York +, Florida +, Arkansas +, Vermont +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Safety Parameter Display System +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +  and Containment Spray +

TS-3.0.4 +, TS-3.0 +  and TS-4.0.2 +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Offsite Dose Calculation Manual +, Fire Barrier +, Probabilistic Risk Assessment +, Anchor Darling +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Stress corrosion cracking +, Hardened vent +, Fuel cladding +  and Backfit +