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CORRESPONDENCE-LETTERS, NRC TO PROFESSIONAL/INDUSTRIAL ASSOCIATION  and OUTGOING CORRESPONDENCE

Boron +, Sodium +, Hydrogen +, Chloride +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 5 +, 10 CFR 100 Appendix A +, 10 CFR 507 +, 10 CFR 50.55a +  and 10 CFR 50.55a#h +

05000010  +, 05000029  +, 05000155  +, 05000206  +, 05000213  +, 05000219  +, 05000237  +, 05000244  +, 05000245  +, 05000255  +  and 05000409  +

Eisenhut D +  and Office of Nuclear Reactor Regulation +

GDC 44 +, GDC 34 +, GDC 50 +, GDC 54 +, GDC 35 +, GDC 14 +, GDC 21 +, GDC 13 +, GDC 46 +, GDC 45 +, GDC 37 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +  and GDC 5, Sharing of structures, systems, and components +

ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +, ML20027B595 +  and ML20027B595 +

IEEE 279 +  and IEEE 279-1971 +

General Electric +  and Westinghouse +

NUREG-0691 +, NUREG-0479 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0123, Safety Evaluation Supporting Amend 99 to License DPR-6 +, NUREG/CR-0098, Forwards SEP Position Re Consideration of Inelastic Response Using NUREG/CR-0098 Ductility Factor Approach,Providing Addl Guidance Regarding Application of Ductility Methodology +, NUREG/CR-1582, Forwards Aug 1980 NUREG/CR-1582,Vols 2 & 3, Seismic Hazard Analysis,Solicitation of Expert Opinion, Prepared by Tera Corp.W/O Encl +  and NUREG-0666, 03-17-81 NUREG-0666, a Probabilistic Safety Analysis of DC Power Supply Requirements at Nuclear Power Plants +

Regulatory Guide 1.27 +, Regulatory Guide 1.45 +, Regulatory Guide 1.117 +, Regulatory Guide 1.81 +, Regulatory Guide 1.99 +, Regulatory Guide 1.54 +, Regulatory Guide 1.29 +, Regulatory Guide 1.14 +, Regulatory Guide 1.133 +, Regulatory Guide 1.13 +, Regulatory Guide 1.115 +, Regulatory Guide 1.56 +, Regulatory Guide 1.62 +, Regulatory Guide 1.139 +  and Regulatory Guide 1.96 +

Millstone +, Dresden +, Palisades +, Oyster Creek +, Haddam Neck +, Ginna +, San Onofre +, Yankee Rowe +, La Crosse +  and Big Rock Point +

Wisconsin +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Fuel Pool Cooling and Cleanup +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Containment Spray +  and Low Pressure Coolant Injection +

Denise Edwards +  and ATOMIC INDUSTRIAL FORUM +

Safe Shutdown +, Shutdown Margin +, Ultimate heat sink +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Hydrostatic +, Coatings +, Tornado Generated Missile +, Intergranular Stress Corrosion Cracking +, Feedwater Controller Failure +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Control of Heavy Loads +, Turbine Missile +, Pressure Boundary Leakage +, Backfit +, Overspeed +, Loss of condenser vacuum +  and Control Room Habitability +