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CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE  and NRC TO RESEARCH INSTITUTION/LABORATORY

Hydrogen +, Chloride +, Lead +  and Tin +

10 CFR 50 Appendix R +, 10 CFR 50.73 +  and 10 CFR 21 +

00528  +, 00220  +, 00346  +, 00395  +, 00285  +, 00413  +, 00335  +, 00298  +, 00458  +, 00237  +, 00304  +  and 00382  +

Turbine Trip +  and Reactor Trip +

NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) +  and Heltemes C +

ML20207B087 +, ML20207B087 +, ML20207B087 +, ML20207B087 +, ML20207B087 +, ML20207B087 +, ML20207B087 +, ML20207B087 +  and ML20207B087 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.430556e-4 d (0.00583 hours, 3.472222e-5 weeks, 7.9905e-6 months)  +, 0.00694 d (0.167 hours, 9.920635e-4 weeks, 2.283e-4 months)  +, 0.00718 d (0.172 hours, 0.00103 weeks, 2.3591e-4 months)  +, 0.0081 d (0.194 hours, 0.00116 weeks, 2.6635e-4 months)  +, 0.00839 d (0.201 hours, 0.0012 weeks, 2.758625e-4 months)  +, 0.0121 d (0.29 hours, 0.00173 weeks, 3.976225e-4 months)  +, 0.00851 d (0.204 hours, 0.00122 weeks, 2.796675e-4 months)  +, 0.0209 d (0.502 hours, 0.00299 weeks, 6.87944e-4 months)  +, 0.00978 d (0.235 hours, 0.0014 weeks, 3.215225e-4 months)  +, 0.0156 d (0.374 hours, 0.00222 weeks, 5.117725e-4 months)  +, 0.0162 d (0.389 hours, 0.00231 weeks, 5.327e-4 months)  +, 0.0177 d (0.424 hours, 0.00252 weeks, 5.80643e-4 months)  +, 0.0188 d (0.45 hours, 0.00268 weeks, 6.1641e-4 months)  +, 0.0174 d (0.417 hours, 0.00248 weeks, 5.7075e-4 months)  +, 0.0175 d (0.421 hours, 0.0025 weeks, 5.764575e-4 months)  +, 0.0186 d (0.447 hours, 0.00266 weeks, 6.12605e-4 months)  +, 0.0197 d (0.472 hours, 0.00281 weeks, 6.4685e-4 months)  +, 0.00382 d (0.0917 hours, 5.456349e-4 weeks, 1.25565e-4 months)  +, 0.00647 d (0.155 hours, 9.242725e-4 weeks, 2.126995e-4 months)  +, 0.00706 d (0.169 hours, 0.00101 weeks, 2.32105e-4 months)  +, 0.00492 d (0.118 hours, 7.027116e-4 weeks, 1.617125e-4 months)  +, 0.0236 d (0.567 hours, 0.00338 weeks, 7.76981e-4 months)  +, 0.0119 d (0.286 hours, 0.0017 weeks, 3.91915e-4 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 0.0132 d (0.318 hours, 0.00189 weeks, 4.349115e-4 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 0.0106 d (0.254 hours, 0.00151 weeks, 3.473965e-4 months)  +

IEEE 383 +  and IEEE 323-1974 +

Westinghouse +, General Electric +  and Electro-Motive +

NUREG/CR-2000 +, NUREG-0304 +, NUREG-1190, Transcript of Commission 860122 Briefing in Washington,Dc Re San Onofre & Status of Rancho Seco.Pp 1-105.Supporting Documentation & NUREG-1190, Loss of Power & Water Hammer Event at San Onofre,Unit 1 on 851121 Encl +, NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco +, NUREG-0900, Informs Commission of Status of Staff Reassessment of Source Terms & Related Severe Accident Research Activities,For Use in Implementing Commission Severe Accident Policy Statement. NEA Mar 1986 Rept, Nuclear Reactor...Source Terms, Encl +, NUREG-0540, Notifies of Issuance of NUREG-0568, Title List of Publicly Available Documents on Tmi,Docket 50-320. Suppl Will Be Published.All New Entries Will Be in NUREG-0540,Title List Journal,Issued Monthly +  and NUREG-0090, SECY-25-0016: Enclosure 1 - NUREG-0090, Volume 47, Report to Congress on Abnormal Occurrences: Fiscal Year 2024 +

24V +  and 345kV +

AOP +, ES +, SP +  and ST-26 +

07-85-101 +, 07-85-100 +, 1E31-PDIN084 +, 1E31-PDTN084 +  and 2FIC-4488 +

Texas +, Ohio +, Pennsylvania +, Arizona +, Georgia +, Washington +, California +, South Carolina +, New York +  and Nebraska +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Residual Heat Removal +, Steam Bypass Control System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Steam +  and Containment Spray +

TS-3.0.3 +, TS-3.7.4.1 +, TS-3.9.B +  and TS-3.4.5.6 +

NUCLEAR SAFETY ANALYSIS CENTER +  and Layman W +

Safe Shutdown +, Fire Barrier +, Stroke time +, Shift Technical Advisor +, Loss of Offsite Power +, Continuous fire watch +, Brachytherapy +, Overexposure +, Overspeed +  and Water hammer +