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TEXT-SAFETY REPORT, GENERAL EXTERNAL TECHNICAL REPORTS  and INDIVIDUAL PLANT EXAM (OF EXTERNAL EVENTS)

Hydrogen +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 50 +  and 10 CFR 50 Appendix B +

Barrier Integrity +  and Initiating Events +

05000315  +, 05000316  +, 00315  +  and 00316  +

Turbine Trip +  and Reactor Trip +

NRC Generic Letter 48-20 +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

ML17332A584 +, ML17332A584 +, ML17332A584 +, ML17332A584 +, ML17332A584 +, ML17332A584 +, ML17332A584 +, ML17332A584 +, ML17332A584 +, ML17332A584 +  and ML17332A584 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 9.837963e-4 d (0.0236 hours, 1.405423e-4 weeks, 3.23425e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 7.523148e-4 d (0.0181 hours, 1.074735e-4 weeks, 2.47325e-5 months)  +

Westinghouse +  and General Electric +

NUREG/CR-2258 +, NUREG/CR-4772 +, NUREG/CR-4566 +, NUREG/CR-4586 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +, NUREG-1335, Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Associated Guidance, NUREG-1335 +, NUREG/CR-5088, Discusses Proposed Actions Re SECY-89-170, Fire Risk Scoping Study:Summary of Results & Proposed Staff Actions, (NUREG/CR-5088).Need for Addl Research Will Be Considered Following Final Definition of fire-related Parts +  and NUREG/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +

600V +  and 4kV +

Emergency Operating Procedure +, ES-1.2 +, ES-12 +, AM-A +, AM-D +  and AM-Dare +

1E-6 +, 1E-7 +, 1E-06 +, 1E-07 +, 4E-7 +, 22E-03 +, 44E-08 +, 130E-01 +, 22E-3 +, 5e-4 +, 1AI-P2 +, 1AU-C4 +, 5AE-2 +, 32E-3 +, 2AE-3 +, 2AE-06 +, 1AZ-C21 +, 1AZ-C64 +, 1AZ-P11 +, 1AZ-C62 +, 1AZ-C27 +, 1AZ-C30 +, 1EI-C23 +, 1EI-C30 +, 1EI-C1 +, 1EI-C54 +, 1EI-C4 +, 1EI-C5 +, 1EM-C6 +, 1CT-P22 +...

Ohio +, Illinois +, Washington +, Michigan +, Indiana +  and New Mexico +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, HVAC +, Residual Heat Removal +, Remote shutdown +, Decay Heat Removal +, Control Rod +, Main Steam +  and Containment Spray +

Hot Short +, Safe Shutdown +, Boric Acid +, Reactor Vessel Water Level +, Mission time +, Fire Barrier +, Probabilistic Risk Assessment +, Design basis earthquake +, Shift Technical Advisor +, Loss of Offsite Power +, Earthquake +, Turbine Missile +, Fire Protection Program +, Fire Watch +  and Scaffolding +