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COMMISSION PAPER  and TEXT-SAFETY REPORT

ASME Section III +, ASME Section I +  and ASME Section II +

Boron +, Iodine +, Cesium +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Lead +  and Chromium +

10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 52.47 +, 10 CFR 50.54#f +, 10 CFR 50.34#f2viii +, 10 CFR 50.34#f +, 10 CFR 50.34#f2xvii +, 10 CFR 50.34#f2ix +  and 10 CFR 52.47#aii +

Initiating Events +  and Emergency Preparedness +

SECY-77-439 +, SECY-93-087 +, SECY-90-377 +, SECY-90-016 +, SECY-92-053 +, SECY-90-241 +, SECY-91-178 +, SECY-91-210 +, SECY-92-196 +, SECY-92-214 +, SECY-92-287 +, SECY-92-294 +, SECY-92-299 +, SECY-92-327 +, SECY-88-147 +, SECY-91-229 +, SECY-91-273 +, SECY-92-127 +, SECY-92-219 +, SECY-92-037 +, SECY-91-262 +, SECY-91-272 +, SECY-91-292 +, SECY-91-078 +, SECY-90-341 +, SECY-93-87 +, SECY-89-012 +, SECY-89-013 +, SECY-91-074 +, SECY-92-092 +...

52 FR 41288 +, 50 FR 32138 +  and 53 FR 11311 +

Taylor J +  and NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) +

GDC 34 +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +  and GDC 4, Environmental and dynamic effects design bases +

ML20035D387 +, ML20035D387 +, ML20035D387 +, ML20035D387 +, ML20035D387 +, ML20035D387 +  and ML20035D387 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

IEEE 384 +, IEEE 344 +  and IEEE 279 +

Westinghouse +  and General Electric +

NUREG/CR-5250 +, NUREG/CR-4885 +, NUREG/CR-4905 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, 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-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-1410, Discusses NRC Concerns Re Operator Diligence While in Shutdown Conditions & Requests Quick & Appropriate Mgt Reactions to Generic Ltr 88-17.Supporting Documentation Encl +, NUREG/CR-4661, Forwards Written Comments & Suggested Changes to Draft NUREG/CR-4661, Closeout of IE Bulletin 85-003: Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings +  and NUREG-0493, Notification of 790830 Meeting W/Westinghouse in Bethesda,Md to Discuss Westinghouse Response to NUREG-0493, Progress of Westinghouse Verification & Validation Program on RESAR-414 & Results of NRC Review Effort +

Regulatory Guide 1.97 +, Regulatory Guide 1.155 +, Regulatory Guide 1.76 +, Regulatory Guide 1.100 +, Regulatory Guide 1.29 +, Regulatory Guide 1.152 +, Regulatory Guide 1.62 +, Regulatory Guide 1.124 +, Regulatory Guide 1.139 +  and Regulatory Guide 1.96 +

SECY-77-439 +, SECY-93-087 +, SECY-90-377 +, SECY-90-016 +, SECY-92-053 +, SECY-90-241 +, SECY-91-178 +, SECY-91-210 +, SECY-92-196 +, SECY-92-214 +, SECY-92-287 +, SECY-92-294 +, SECY-92-299 +, SECY-92-327 +, SECY-88-147 +, SECY-91-229 +, SECY-91-273 +, SECY-92-127 +, SECY-92-219 +, SECY-92-037 +, SECY-91-262 +, SECY-91-272 +, SECY-91-292 +, SECY-91-078 +, SECY-90-341 +, SECY-93-87 +, SECY-89-012 +, SECY-89-013 +, SECY-91-074 +, SECY-92-092 +...

07-90-016 +, 07-89-153 +, 07-89-228 +, 07-92-196 +, 07-91-135 +, 07-92-133 +, 07-91-229 +, 07-91-273 +, 07-92-214 +, 5ECY-90-016 +, 4UREG-0800 +  and 07-90-406 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, HVAC +, Residual Heat Removal +, Reactor Water Cleanup +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Reactor Vessel Water Level +, Ultimate heat sink +, Fire Barrier +, Internal Flooding +, Probabilistic Risk Assessment +, Seismically rugged +, Scram Discharge Volume +, License Renewal +, Earthquake +, Fuel cladding +, Offsite Circuit +, Grace period +, Core Exit Thermocouple +, Water hammer +, Control Room Habitability +  and Leak-Before-Break +