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Report  and Technical

ANSI/ANS-51.1-1983 +, ANSI/ANS-52.1-1983 +, ANSI/ANS-59.4-1979 +, ANSI/ANS-58.6-1983 +  and ANSI/ANS-58.11-1983 +

ASME Section III +  and ASME Section IX +

Uranium +, Carbon +, Hydrogen +, Lead +  and Tin +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 50.48 +, 10 CFR 50 +  and 10 CFR 50#45 +

SECY 08-0093 +, SECY-83-269 +, SECY-85-306 +, SECY-93-143 +, SECY-95-034 +, SECY-96-134 +  and SECY-82-267 +

05000259  +, 05000260  +  and 05000296  +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80) +  and NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +

ML091070228 +, ML091070228 +, ML091070228 +, ML091070228 +, ML091070228 +, ML091070228 +, ML091070228 +, ML091070228 +, ML091070228 +  and ML091070228 +

IEEE 380 +  and IEEE 100 +

NEI 02-03 +, NEI 04-06 +, NEI 00-0 +, NEI 04-02, NFPA 805 Transition FAQ 10-0059, Rev 0 +, NEI 04-0 +  and NEI 00-01, Guidance for Post Fire Safe Shutdown Circuit Analysis +

NUREG/CR-6738 +, NUREG/BR-0195 +, NUREG-1824 +, NUREG-0050, Forwards Documents Re 1975 Fire at Plant.Documents Provide Overview of Experience W/Significant Fire That Resulted in Spurious Component Operation,Loss of Control Functions & Erroneous Control Room Instrumentation Readings.W/O Encls +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau +

4.16KV +  and 4.16kV +

Regulatory Guide 1.189 +, Regulatory Guide 1.174 +, Regulatory Guide 1.75 +, Regulatory Guide 1.205 +, Regulatory Guide 1.120 +  and Regulatory Guide 1.17 +

SECY 08-0093 +, SECY-83-269 +, SECY-85-306 +, SECY-93-143 +, SECY-95-034 +, SECY-96-134 +  and SECY-82-267 +

1E-0 +, 1E-6 +, 1E-5 +, 1E-7 +, 1E-07 +, 2E-2 +, 3E-7 +, 9E-7 +, 3E-8 +, 8E-3 +, 1E-2 +, 9E-2 +, 2E-3 +, 3E-2 +, 6E-3 +, 9E-6 +, 4E-2 +, 9E-9 +, 3E-9 +, 8E-2 +, 4E-3 +, 9E-10 +, 9E-4 +, 9E-12 +, 9E-I +, 9E-5iyr +, 9E-10iyr +, 1E-08vr +  and 3Ris-Itforme +

Washington +  and Arizona +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Remote shutdown +, Decay Heat Removal +  and Safety Relief Valve +

TS-7.3.43 +  and TS-7.3.47 +

Hot Short +, Safe Shutdown +, Shutdown Margin +, Fire Barrier +, Probabilistic Risk Assessment +, Coatings +, Operator Manual Action +, Multiple Spurious Operation +, Emergency Lighting +, Significance Determination Process +, Thermoset +, Large early release frequency +, Loss of Offsite Power +, Exemption Request +, Earthquake +, Chernobyl +, Fuel cladding +, Biofouling +  and Fire Protection Program +