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

ASME Section XI +  and ASME Section III +

Boron +, Iodine +, Uranium +, Iron +, Potassium +, Nitrogen +, Carbon +, Hydrogen +, Xenon +, Molybdenum +, Thorium +, 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 20 +, 10 CFR 50 +, 10 CFR 30.50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 34.20 +, 10 CFR 71 +, 10 CFR 31 +, 10 CFR 61 +, 10 CFR 40.22 +, 10 CFR 50.7 +, 10 CFR 50.49 +, 10 CFR 50.120 +, 10 CFR 73.21 +, 10 CFR 73.55 +, 10 CFR 73.57 +, 10 CFR 20.302 +, 10 CFR 35.23 +, 10 CFR 20.303 +, 10 CFR 20.408 +, 10 CFR 55.250 +, 10 CFR 50.54#f +, 10 CFR 50.54#p +, 10 CFR 73.40#d +...

Control rod 96-01 +, Control rod 93-04 +, Control rod 85-15 +, Control rod 89-32 +, Control rod 82-29 +  and Control rod 81-16 +

Physical Protection +  and Emergency Preparedness +

SECY 82-111 +, L 80-13 +, L 84-29 +, CY 1983 +, L 62 +, L 177 +, L 195 +, L 159 +  and NRC 83-12 +

S.2(o) +, S.1(a) +, S.2(a) +, S.4(t) +, S.1(i) +, S.1(o) +  and S.1(e) +

Reactor Trip +  and Turbine Trip +

WESTINGHOUSE ELECTRIC COMPANY +, DIV OF CBS CORP. +, Mcintyre B +  and Lindgren D +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 80-45, Fire Protection Rule +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 85-05, Inadvertent Boron Dilution Events +, NRC Generic Letter 86-06, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +, NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-02, Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products +, NRC Generic Letter 93-04, Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) +, NRC Generic Letter 93-03, Verification of Plant Records +, NRC Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes +, NRC Generic Letter 69-10 +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +, NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification +  and NRC Generic Letter 1981-38, Storage of Low-Level Radioactive Wastes at Power Reactor Sites +

ML20217L762 +, ML20217L762 +, ML20217L762 +, ML20217L762 +, ML20217L762 +, ML20217L762 +, ML20217L762 +, ML20217L762 +, ML20217L762 +, ML20217L762 +, ML20217L762 +  and ML20217L762 +

Strontium-90 +, Iodine-125 +, Cesium-137 +, Iridium-192 +, Americium-241 +, Kr-85 +, Iodine-131 +  and Cobalt-60 +

L 80-13 +, L 84-29 +, L 62 +, L 177 +, L 195 +  and L 159 +

Westinghouse +, Foxboro +, Honeywell +, 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 88-09 +, NRC Bulletin 93-02 +, NRC Bulletin 80-06 +, NRC Bulletin 87-01 +, 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 80-21 +, NRC Bulletin 80-12 +, NRC Bulletin 80-17 +, NRC Bulletin 80-03 +, NRC Bulletin 80-09 +, NRC Bulletin 80-23 +, NRC Bulletin 80-08 +, NRC Bulletin 80-19 +, NRC Bulletin 80-16 +, NRC Bulletin 80-05 +  and NRC Bulletin 86-01 +

Information Notice 92-54 +, Information Notice 83-70 +, Information Notice 92-06 +, Information Notice 87-43 +, Information Notice 88-86 +, Information Notice 84-74 +, Information Notice 93-34 +, Information Notice 90-69 +, Information Notice 93-35 +, Information Notice 93-36 +, Information Notice 93-71 +, Information Notice 94-43 +, Information Notice 83-68 +, Information Notice 95-14 +  and Information Notice 81-02 +

NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301 +, NUREG-0916, Notice of Issuance & Availability of Amend 51 to License DPR-18 +, NUREG-127 +, 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-0965, Forwards marked-up Copy of Section 3.2 of NUREG-0965, NRC Inventory of Dams, & Corrected Pages for App C & App E +, NUREG-1477, Discusses Technical Concerns W/Changes to Draft NUREG-1477 Re Probability of Leakage Curves +, 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-1262, Discusses Review of Plant Simulation Facility Development Plan,Submitted on 880526.Overall Approach of Plan Acceptable Due to Reliance on Util Simulation Facility Group Baseline Document.Issues Requiring Resolution Stated +, NUREG-1169, Notification of 870902 Meeting W/Util in Bethesda,Md to Discuss MSIV Leakage Control Sys & NUREG-1169 Applicability. Proposed Agenda 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-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-1358, Forwards NRC Info Notice 92-076, Issuance of Suppl 1 to NUREG-1358, Lessions Learned from Special Insp Program for EOPs (Conducted Oct 1988-Sept 1991). W/O Encl +, 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-0626, 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-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 +, 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 +

SP +, CP +, ESP +  and Emergency Operating Procedure +

Regulatory Guide 1.137 +, Regulatory Guide 1.108 +, Regulatory Guide 1.58 +, Regulatory Guide 1.118 +, Regulatory Guide 1.152 +  and Regulatory Guide 1.150 +

07-86-110 +, 07-83-10c +, 07-88-100 +, 07-80-007 +, 07-85-100 +, 07-86-108 +, 07-86-106 +, 07-86-103 +, 07-80-106 +, 07-83-10a +, 07-83-10b +, 07-80-060 +, 07-80-101 +, 07-83-10d +, 07-80-028 +, 07-80-021 +, 07-80-039 +, 07-80-086 +, 07-80-034 +, 07-80-031 +, 07-80-038 +, 07-80-022 +, 07-80-048 +, 07-80-058 +, 07-80-080 +, 8S-03 +, 07-80-033 +, 07-83-10e +, 07-80-070 +, 07-80-006 +...

Texas +, Connecticut +, Illinois +, Washington +, New Jersey +, New York +, Arkansas +, Vermont +  and Maine +

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

TS-3.7.1 +, TS-3.4.16 +, TS-3.5 +  and TS-3.4.2 +

Safe Shutdown +, Boric Acid +, Fitness for Duty +, Health Physics Network +, Shutdown Margin +, Reactor Vessel Water Level +, Loop seal +, High Radiation Area +, Offsite Dose Calculation Manual +, Fire Barrier +, Internal Flooding +, Coatings +, Anchor Darling +, Temporary Modification +, 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 +, Tone Alert Radio +, Safeguards Contingency Plan +, Overtravel +, Earthquake +, Commercial Grade +, Control of Heavy Loads +, Biofouling +...

WCAP-12945 +, WCAP-13383 +, WCAP-13054 +  and WCAP-13559 +

WCAP-12945 +, WCAP-13383 +, WCAP-13054 +  and WCAP-13559 +