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

Iodine +, Carbon +, Oxygen +  and Lead +

05000267  +  and 00267  +

NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) +, Farrell R +, Jaudon J +, Skow M +  and Michaud P +

NRC Generic Letter 86-01, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, NRC Generic Letter 85-20, Resolution of Generic Issue 69: High Pressure Injection/Make-up Nozzle Cracking in Babcock And Wilcox Plants +, NRC Generic Letter 85-19, Reporting Requirements on Primary Coolant Iodine Spikes +, NRC Generic Letter 85-18, Operator Licensing Examinations +, NRC Generic Letter 85-17, Availability of Supplements 2 and 3 to NUREG-0933, "A Prioritization of Generic Safety Issues" +, 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 86-06, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" +, 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 86-03, Applications for License Amendments +  and NRC Generic Letter 86-02, Technical Resolution of Generic Issue B-19 - Thermal Hydraulic Stability +

ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +, ML20207S352 +  and ML20207S352 +

Westinghouse +, Foxboro +, Limitorque +  and Valcor +

NRC Bulletin 84-02 +, NRC Bulletin 85-02 +, NRC Bulletin 85-01 +, NRC Bulletin 86-03 +, NRC Bulletin 86-01 +  and NRC Bulletin 86-04 +

Information Notice 86-72 +  and Information Notice 86-07 +

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 +  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 +

Texas +, Colorado +, Virginia +, Michigan +  and Indiana +

Feedwater +, Emergency Diesel Generator +  and Auxiliary Feedwater +

Water hammer +  and Feedwater Heater +