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CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

Boron +, Iodine +, Nitrogen +, Oxygen +, Hydrogen +, Chloride +, Lead +, Helium +  and Silver +

10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +  and 10 CFR 50 +

SECY-80-230 +  and RS 232 +

05000373  +, 05000374  +, 00373  +  and 00374  +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

Exelon +  and L. O. DelGeorge +

GDC 54 +  and GDC 19, Control room +

ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +, ML20008E249 +  and ML20008E249 +

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 4.62963e-4 d (0.0111 hours, 6.613757e-5 weeks, 1.522e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +

IEEE 344 +, IEEE 323 +, IEEE 323-1974 +, IEEE 279 +, IEEE 279-1971 +, IEEE 344-1975 +, IEEE 323-1971 +  and IEEE 324-1974 +

Westinghouse +, General Electric +  and Westronics +

NRC Bulletin 79-08, Events Relevant to Boiling Water Power Reactors Identified During Three Mile Island Incident +  and NRC Bulletin 79-00 +

NUREG-0565, Forwards Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 B&W Owners Group Small Break LOCA Evaluation model,CRAFT2 (Rev 3).Two Confirmatory Issues Identified. Response Requested within 45 Days of Ltr Receipt +, NUREG/CR-1250, Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +, 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-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-0616, Forwards NUREG-0616, Rept of Special Review Group,Ofc of IE on Lessons Learned from Tmi. Also Forwards 791231 Lpdr Document Availability Update +, NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +, NUREG-0625, 02-14-80 NUREG-0625, Report of the Siting Policy Task Force +  and NUREG-0600 +

AM +, ES +, ST +  and RT +

Regulatory Guide 1.3 +, Regulatory Guide 1.101 +  and Regulatory Guide 1.11 +

07-79-06A +, 07-79-06B +  and 07-79-05A +

Illinois +, Washington +  and Virginia +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, High Pressure Coolant Injection +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Main Condenser +, Control Rod +  and Main Steam +

Youngblood B +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Reactor Vessel Water Level +, Grab sample +, Emergency Lighting +, Shift Technical Advisor +, Loss of Offsite Power +, Excess Flow Check Valve +, Potassium iodide +  and Control Room Habitability +