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TEXT-SAFETY REPORT  and NRC TECHNICAL REPORT

Carbon +, Hydrogen +  and Lead +

Office of Nuclear Reactor Regulation +  and Serkiz A +

ML20205D994 +, ML20205D994 +, ML20205D994 +, ML20205D994 +, ML20205D994 +, ML20205D994 +  and ML20205D994 +

3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +

NUREG/CR-1363 +, NUREG/CR-3653 +, NUREG/CR-2552 +, NUREG/CP-0072 +, NUREG/CR-2800 +, NUREG-0483 +, NUREG-0618 +, NUREG/CR-1496 +, NUREG/CR-4594 +, NUREG/CR-2378 +, NUREG/CP-0033 +, NUREG-459 +, NUREG-11509 +, NUREG-31940 +, NUREG-1363 +, NUREG-0869, Forwards CRGR Review of Proposed Resolution of Unresolved Safety Issue A-43, Containment Emergency Sump Performance. Draft NUREG-0869 & NUREG-0897 Re Unresolved Safety Issue A-43 Also Encl +, NUREG/CR-4050, Forwards NUREG/CR-4050,NRC Review of Facility PRA Study & Evaluation of Unisolated LOCA Outside Drywell in Shoreham Nuclear Power Station. No Safety Issue Identified Needing Immediate Action +, NUREG/CR-31940 +, NUREG/CR-3726 +, NUREG/CR-0033 +, NUREG/CR-0933 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1037, Requests Support in Development & Implementation of New Accident Source Term Info to Improve Regulations & Related Regulatory & Staff Practices,Per 860326 Presentation of SECY-86-76 +, NUREG-1079, Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR +, NUREG/CR-0255, Forwards NUREG/CR-0255 Re Contempt Program for Predicting Containment Pressure & Temp response,NUREG/CR-0009,TID-14844 & ORNL-TM-2412,in Response to Request for Info on Containment Analysis.W/O Encls +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +, 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-0366, Response to 790102 Request Providing Tables & Individual Plant Summaries from Draft NUREG-0366 Nuclear Power Plant Operating Experience for 1977 +...

NEDE-21864 +, NEDE-25100 +, NEDE-24757 +  and NEDO-24951 +

1x10-6 +, 2x10-8 +, 4x10-5 +  and 3x10-5 +

Illinois +, Maryland +, Washington +, New York +, Mississippi +  and Vermont +

Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +

Probabilistic Risk Assessment +, Stress corrosion cracking +, Earthquake +, Backfit +  and Water hammer +