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TEXT-SAFETY REPORT  and REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)

Boron +, Americium +, Uranium +, Iron +, Potassium +, Nitrogen +, Carbon +, Hydrogen +, Xenon +, Molybdenum +, Chloride +, Lead +, Helium +, Aluminum +, Silicon +, Mercury +, Silver +, Tin +  and Hafnium +

10 CFR 50 Appendix R +, 10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 21 +, 10 CFR 26 +, 10 CFR 50 +, 10 CFR 30.50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 31 +, 10 CFR 61 +, 10 CFR 35.24 +, 10 CFR 50.7 +, 10 CFR 50.49 +, 10 CFR 55.25 +, 10 CFR 73.5 +, 10 CFR 73.55 +, 10 CFR 20.303 +, 10 CFR 20.408 +, 10 CFR 50.54f#f +, 10 CFR 50.54#f +, 10 CFR 50.54#0 +  and 10 CFR 50.55#e +

Control rod 85-15 +, Control rod 89-32 +, Control rod 82-29 +  and Control rod 81-16 +

Emergency Preparedness +  and Physical Protection +

SECY 82-111 +  and CY 1983 +

S.1(e) +  and S.1(o) +

Turbine Trip +  and Reactor Trip +

WESTINGHOUSE ELECTRIC COMPANY +  and DIV OF CBS CORP. +

NRC Generic Letter 80-45, Fire Protection Rule +, NRC Generic Letter 81-07, Control of Heavy Loads +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML20125D593 +, ML20125D593 +, ML20125D593 +, ML20125D593 +, ML20125D593 +, ML20125D593 +, ML20125D593 +, ML20125D593 +, ML20125D593 +  and ML20125D593 +

Strontium-90 +, Cesium-137 +, Americium-241 +, Iridium 192 +, Kr-85 +  and Cobalt-60 +

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

NRC Bulletin 80-04 +, NRC Bulletin 80-24 +, NRC Bulletin 80-14 +, NRC Bulletin 80-10 +, NRC Bulletin 80-11 +, NRC Bulletin 80-06 +, NRC Bulletin 80-13 +, NRC Bulletin 80-07 +, NRC Bulletin 80-20 +, NRC Bulletin 80-25 +, NRC Bulletin 80-01 +, NRC Bulletin 80-15 +, NRC Bulletin 80-18 +, NRC Bulletin 80-12 +, NRC Bulletin 80-17 +, NRC Bulletin 80-03 +, NRC Bulletin 80-09 +, NRC Bulletin 80-02 +, NRC Bulletin 80-23 +, NRC Bulletin 80-08 +, NRC Bulletin 80-16 +  and NRC Bulletin 80-05 +

Information Notice 83-70 +  and Information Notice 85-59 +

NUREG/CR-2980 +, NUREG-0916, Notice of Issuance & Availability of Amend 51 to License DPR-18 +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG-4626 +, NUREG-0965, Forwards marked-up Copy of Section 3.2 of NUREG-0965, NRC Inventory of Dams, & Corrected Pages for App C & App E +, NUREG-1190, Transcript of Commission 860122 Briefing in Washington,Dc Re San Onofre & Status of Rancho Seco.Pp 1-105.Supporting Documentation & NUREG-1190, Loss of Power & Water Hammer Event at San Onofre,Unit 1 on 851121 Encl +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, 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 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, 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-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0909, Forwards NRC Rept on 820125 Steam Generator Tube Rupture, Re Ginna Nuclear Power Plant, (NUREG-0909).W/o Encl +, NUREG-0744, Notice of Issuance & Availability of NUREG-0744, Resolution of Reactor Vessel Matls Toughness Safety Issue. Final Rept Will Provide Resoultion of Unresolved Safety Issue A-11 +, NUREG-0645, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +, NUREG/CR-0095, Research Info Ltr 50:summarizes & Comments on Result of Study Published as NUREG/CR-0095, Nuclear Safety Guide, TID-7016,Revision 2 +, NUREG-0977, Requests Util Review of NUREG-0977 Re ATWS Events to Identify & Explain Apparent Inconsistencies Based on Latest Available Info & Provide Basis for Relevance of New Info +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +, NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +, NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

4.16KV +  and 4kV +

ST +, SP +  and Emergency Operating Procedure +

Regulatory Guide 1.137 +  and Regulatory Guide 1.108 +

1A-A +, 07-80-005 +, 07-83-10c +, 07-80-007 +, 07-85-100 +, 07-86-108 +, 07-86-106 +, 07-86-103 +, 07-80-106 +, 07-83-10b +, 07-80-060 +, 07-80-101 +, 07-80-012 +, 07-83-10d +, 07-80-003 +, 07-80-112 +, 07-80-008 +, 07-80-035 +, 07-80-021 +, 07-80-039 +, 07-80-059 +, 07-80-105 +, 07-80-066 +, 07-80-034 +, 07-80-045 +, 07-80-048 +, 07-80-080 +, 07-80-053 +, 07-80-026 +, 07-80-011 +...

Texas +, Pennsylvania +, Connecticut +, Illinois +, New Jersey +, Arkansas +, Vermont +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Main Turbine +, Emergency Response Data System +, Shutdown Cooling +, Safety Parameter Display System +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Main Steam Safety Valve +, Remote shutdown +, Residual Heat Removal Service Water +, Spray Pond +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +...

Safe Shutdown +, Boric Acid +, Fitness for Duty +, Reactor Vessel Water Level +, Loop seal +, High Radiation Area +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Fire Barrier +, Internal Flooding +, Coatings +, Anchor Darling +, Zebra Mussel +, High Energy Line Break +, Main transformer failure +, Scram Discharge Volume +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Safeguards Contingency Plan +, Overtravel +, Commercial Grade +, Control of Heavy Loads +, Chernobyl +, Biofouling +, Brachytherapy +, Dissimilar Metal Weld +, Stolen +...