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TEXT-SAFETY REPORT  and GENERAL EXTERNAL TECHNICAL REPORTS

Hydrogen +, Lead +  and Tin +

10 CFR 55 +  and 10 CFR 55 Appendix A +

Turbine Trip +  and Reactor Trip +

FirstEnergy +, Jason Christensen +, Gardner E +  and Kimel W +

ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +, ML19340D688 +  and ML19340D688 +

0.00231 d (0.0556 hours, 3.306878e-4 weeks, 7.61e-5 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)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 3.703704e-4 d (0.00889 hours, 5.291005e-5 weeks, 1.2176e-5 months)  +, 0.0231 d (0.556 hours, 0.00331 weeks, 7.61e-4 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +  and 4.62963e-4 d (0.0111 hours, 6.613757e-5 weeks, 1.522e-5 months)  +

05000289/LER-1979-015, Forwards LER 79-015/01T-0 +  and ML19305D036 +

Westinghouse +  and General Electric +

NUREG-0573 +, NUREG-0094, Forwards Clarified Portion of Examiner Std That Includes Definition of Significant Re 10CFR55.31(a)(5),requiring Applicants for OLs to Perform Min of Five Significant Control Manipulations,Per NUREG-0094 +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG/CR-1270, Apologizes for Implication That Tx Pirg Was at Fault Re Erroneous Identification of Author as Mi Cotton Instead of I Catton.Nrc Consultant Made Same Error in NUREG/CR-1270,Vol 1,Human Factors Evaluation of Control Room Design & .. +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

AM +  and RT +

1NI-2 +, 1NI-l +  and 31I-2 +

Tennessee +, Pennsylvania +, Georgia +, Washington +, California +, Virginia +, New Jersey +, Florida +, Missouri +  and Iowa +

Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Auxiliary Feedwater +, Decay Heat Removal +, Control Rod +, Main Steam +  and Emergency Feedwater System +

Safe Shutdown +, Ultimate heat sink +, Shift Technical Advisor +  and Fuel cladding +