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TEXT-SAFETY REPORT  and COMMISSION PAPER

ASME Section III +  and ASME Section I +

Boron +, Lead +  and Tin +

10 CFR 50 Appendix R +, 10 CFR 50.72 +, 10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.73#a2 +, 10 CFR 50.72#b +, 10 CFR 50.54#a +, 10 CFR 50.34#b6ii +, 10 CFR 50.34#a7 +, 10 CFR 50.109#a3 +, 10 CFR 50.71#e +  and 10 CFR 50#D +

Emergency Preparedness +  and Initiating Events +

SECY-97-168 +, SECY-94-176 +, COMSECY-95-033 +, SECY-95-028 +  and L 21 +

EC-201 +, EC-102 +, EC-184 +, EC-2902 +, EC-187 +, EC-122 +, EC-108 +, EC-234 +, EC-101 +, EC-185 +  and EC-204 +

NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) +  and Callan L +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 80-53, Decay Heat Removal Capability +, NRC Generic Letter 80-42, IEB 80-12 Decay Heat Removal System Operability +, NRC Generic Letter 81-21, Natural Circulation Cooldown +, NRC Generic Letter 85-05, Inadvertent Boron Dilution Events +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +  and NRC Generic Letter 88-17, Loss of Decay Heat Removal +

ML20217K211 +, ML20217K211 +, ML20217K211 +, ML20217K211 +, ML20217K211 +  and ML20217K211 +

0.0347 d (0.833 hours, 0.00496 weeks, 0.00114 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

Westinghouse +  and General Electric +

NUREG-1432 +, NUREG-1431 +, NUREG-1433 +, NUREG-1434 +, NUREG/BR-0058 +, NUREG/CR-6144 +, NUREG-1430 +, NUREG-1269 +, NUREG/BR-0053 +, NUREG/CR-4627 +, NUREG/CR-2723 +, NUREG/CR-2601 +, NUREG-1489 +, NUREG/CR-6218 +, NUREG/CR-6143 +, NUREG/CR-2239, Forwards Slides/Handout Used at 821110 Presentation of NUREG/CR-2239 Re Sandia Siting or Consequences Study. Transcript of Meeting in PDR Did Not Include Slides +, NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +, NUREG-1410, Discusses NRC Concerns Re Operator Diligence While in Shutdown Conditions & Requests Quick & Appropriate Mgt Reactions to Generic Ltr 88-17.Supporting Documentation Encl +  and 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 +

SECY-97-168 +, SECY-94-176 +  and SECY-95-028 +

07-95-601 +, 1E-6 +, 07-97-415 +, 2E-2 +, 2E-6 +, 6E-7 +, 4E-6 +, 07-91-190 +  and 07-95-771 +

Washington +  and Maryland +

Steam Generator +, Reactor Coolant System +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Primary containment +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Condenser +  and Containment Spray +

Safe Shutdown +, Unanalyzed Condition +, Reactor Vessel Water Level +, Ultimate heat sink +, Mission time +, Fire Barrier +, Probabilistic Risk Assessment +, Nondestructive Examination +, Loss of Offsite Power +, License Renewal +, Earthquake +, Fuel cladding +, Fire Protection Program +, Fire Watch +  and Backfit +