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TEXT-SAFETY REPORT  and NRC TECHNICAL REPORT

Iron +, Nitrogen +, Chloride +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 21 +, 10 CFR 50.49 +  and 10 CFR 50#54 +

NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) +  and Israel S +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 81-34, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 81-30, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 81-26, Licensing Requirements for Pending Construction Permit and Manufacturing License Applications +, NRC Generic Letter 81-20, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80) +, NRC Generic Letter 81-05, Information Regarding the Program for Environmental Qualification Of Safety-Related Electrical Equipment +, NRC Generic Letter 82-09, Environmental Qualification of Safety Related Electrical Equipment +, NRC Generic Letter 83-41, Fast Cold Starts of Diesel Generators +, NRC Generic Letter 83-30, Deletion of STD. Tech Spec Surveillance Requirement 4.8.1.1.2.d.6 for Diesel Generator Testing +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping +, NRC Generic Letter 84-07, Procedural Guidance for Pipe Replacement at BWRs +, NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +, NRC Generic Letter 85-15, Information on Deadlines for 10CFR50.49, "Environmental Qualification of Electric Equipment Important to Safety at Nuclear Power Plants" +, NRC Generic Letter 86-15, Information Relating to Compliance with 10 CFR 50.49 "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants" +, NRC Generic Letter 86-06, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +, NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture 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 88-15, Electric Power Systems - Inadequate Control Over Design Process +, NRC Generic Letter 88-07, Modified Enforcement Policy Relating to 10 CFR 50.49, "Environmental Qualification of Electrical Equipment Important to Safety" +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +  and NRC Generic Letter 86-61 +

ML20059C668 +, ML20059C668 +, ML20059C668 +, ML20059C668 +, ML20059C668 +, ML20059C668 +  and ML20059C668 +

Westinghouse +, Limitorque +, General Electric +  and Target Rock +

NRC Bulletin 79-14 +, NRC Bulletin 86-02 +, NRC Bulletin 80-13 +, NRC Bulletin 74-03 +, NRC Bulletin 79-07 +, NRC Bulletin 79-17 +, NRC Bulletin 85-03 +, NRC Bulletin 82-03 +, NRC Bulletin 80-12 +, NRC Bulletin 83-02 +, NRC Bulletin 78-02 +, NRC Bulletin 79-23 +, NRC Bulletin 79-06 +, NRC Bulletin 76-04 +, NRC Bulletin 86-01 +, NRC Bulletin 76-01 +, NRC Bulletin 74-16 +, NRC Bulletin 71-03 +  and NRC Bulletin 79-13, Cracking in Feedwater System Piping +

Information Notice 88-30 +, Information Notice 89-52 +, Information Notice 87-44 +, Information Notice 89-07 +, Information Notice 89-26 +, Information Notice 87-59 +, Information Notice 87-50 +, Information Notice 88-56 +, Information Notice 85-24 +, Information Notice 81-29 +, Information Notice 86-87 +, Information Notice 86-76 +, Information Notice 86-29 +, Information Notice 86-70 +, Information Notice 86-05 +, Information Notice 86-47 +, Information Notice 86-01 +, Information Notice 88-08 +, Information Notice 88-80 +, Information Notice 87-36 +, Information Notice 89-36 +, Information Notice 89-57 +, Information Notice 1989-50, Inadequate Emergency Diesel Generator Fuel Supply +, Information Notice 88-01 +, Information Notice 88-05 +, Information Notice 88-61 +, Information Notice 88-68 +, Information Notice 88-75 +, Information Notice 87-23 +, Information Notice 88-81 +...

NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +  and NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Core Spray +, Residual Heat Removal +, Control Room Emergency Ventilation +, Automatic Depressurization System +, Standby Liquid Control +, Main Steam Safety Valve +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Main Steam +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Loop seal +, Ultimate heat sink +, Fire Barrier +, Coatings +, Missed surveillance +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Grace period +, Water hammer +  and Control Room Habitability +