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Inspection Report, TEXT-INSPECTION & AUDIT & I&E CIRCULARS, NRC-GENERATED  and UTILITY

Iodine +, Nitrogen +, Sodium +, Lead +  and Tin +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 2 Appendix C +, 10 CFR 50.7 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 73.55 +, 10 CFR 73.57 +  and 10 CFR 50.6 +

05000237  +, 05000249  +, 00237  +  and 00249  +

Ring M +  and NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 86-17, Availability of NUREG-1169, "Technical Findings Related to Generic Issue C-8, BWR MSIC Leakage and Treatment Methods" +, 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 86-14, Operator Licensing Examinations +, NRC Generic Letter 86-09, Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs +, NRC Generic Letter 86-08, Availability of Supplement 4 to NUREG-0933, "A Prioritization of Generic Safety Issues" +, NRC Generic Letter 86-07, Transmittal of NUREG-1190 Regarding the San Onofre Unit 1 Loss of Power and Water Hammer Event +, NRC Generic Letter 86-05, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" +, NRC Generic Letter 86-04, Policy Statement On Engineering Expertise on Shift +, NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +, NRC Generic Letter 87-08, Implementation of 10 CFR 73.55 Miscellaneous Amendments and Search Requirements +, NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves +, NRC Generic Letter 87-05, Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells +, NRC Generic Letter 87-04, Temporary Exemption From Provisions of the FBI Criminal History Rule for Temporary Workers +, NRC Generic Letter 87-03, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +  and NRC Generic Letter 87-01, Public Availability of the NRC Operator Licensing Examination Question Bank +

IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +, IR 05000237/1988011 +...

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-1169, Notification of 870902 Meeting W/Util in Bethesda,Md to Discuss MSIV Leakage Control Sys & NUREG-1169 Applicability. Proposed Agenda Encl +  and 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 +

SP +  and ST +

IR 05000237/1988011 +  and IR 05000237/1988011 +

TAC:47096 +  and TAC:49083 +

Regulatory Guide 1.6 +  and Regulatory Guide 1.1 +

3D-1501-4 +  and 11as-built +

DPR-19 +  and DPR-25 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Reactor Building Ventilation +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Main Steam Safety Valve +, Main Steam Line +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

TS-3.7.C +, TS-3.2.A +, TS-4.7.C +  and TS-6.6.A +

Shutdown Margin +, Half scram +, Missed surveillance +, Notice of Violation +, Scram Discharge Volume +, Fire Watch +, Siren +  and Water hammer +