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CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and VENDOR/MANUFACTURER TO NRC

ASME Section III +  and ASME Section XI +

Boron +, Uranium +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Xenon +  and Chloride +

10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +  and 10 CFR 50.62 +

P.3(t) +  and P.3(b) +

05000605  +  and 00605  +

Turbine Trip +  and Reactor Trip +

GENERAL ELECTRIC CO. +  and Marriott P +

GDC 37 +, GDC 27 +  and GDC 17, Electric power systems +

ML20245A571 +, ML20245A571 +, ML20245A571 +, ML20245A571 +, ML20245A571 +, ML20245A571 +, ML20245A571 +, ML20245A571 +, ML20245A571 +, ML20245A571 +, ML20245A571 +, ML20245A571 +, ML20245A571 +  and ML20245A571 +

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)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +

IEEE 279 +  and IEEE 308 +

NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and 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 +

Regulatory Guide 1.1 +, Regulatory Guide 1.45 +  and Regulatory Guide 1.68 +

5A-10 +  and 1A3-1 +

Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, High Pressure Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Chris Miller +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Ultimate heat sink +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Hydrostatic +, Scram Discharge Volume +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Power change +, Coast down +, Unidentified leakage +, Unidentified leak +, Overspeed +  and Water hammer +