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Boron +, Iodine +, Uranium +, Oxygen +, Hydrogen +, Zirconium +  and Lead +

10 CFR 50.72 +, 10 CFR 50 +, 10 CFR 73.71 +, 10 CFR 50.2 +, 10 CFR 50.90 +, 10 CFR 73.55 +, 10 CFR 2.39 +, 10 CFR 50.54#q +  and 10 CFR 50.36#c2ii +

Emergency Preparedness +  and Barrier Integrity +

H.2(a) +, S.4(n) +  and H.2(e) +

05000528  +, 05000529  +, 05000530  +  and 07200044  +

ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +, ML17263B249 +  and ML17263B249 +

NEI 03-12 +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

NUREG-1228 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +  and NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +

AOP +, SP +, ESP +  and Emergency Operating Procedure +

40AO-9ZZ12 +, 40EP-9E001 +, 400P-9ZZ05 +, 40AO-9ZZ19 +, 40ST-9RC02 +, 40OP-9ZZ16 +, 40OP-9ZZ23 +, 40ST-9RC01 +, 40AO-9ZZ21 +, 79IS-9SM01 +, 40AO-9ZZ02 +, 74ST-9RC02 +, 40AO-9ZZ22 +, 40EP-9E010 +, 40DP-9AP08 +, 40EP-9E003 +, 400P-9ZZ03 +, 40AL-9RK7C +, 40AO-97721 +, 40AO-9ZZ18 +, 40EP-9E008 +, 40DP-9AP13 +, 40EP-9E009 +, 40ST-9RC05 +, 40ST-9RC08 +, 40EP-9E004 +, 40EP-9E005 +, 40DP-9AP17 +, 40AO-9Z202 +, 40DP-9AP14 +...

Manual Scram +  and Automatic Scram +

Palo Verde +, NPF-51 +  and NPF-74 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Safety Valve +, Remote shutdown +, Qualified Safety Parameter Display System +, Spray Pond +, Emergency Core Cooling System +, Decay Heat Removal +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-1.1 +, TS-3.3.1 +  and TS-3.4.17 +

Office of Nuclear Material Safety and Safeguards +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, High winds +, Reactor Vessel Water Level +, Ultimate heat sink +, Fire Barrier +, Time to boil +, Safe Shutdown Earthquake +, Internal Flooding +, Operating Basis Earthquake +, Operator Manual Action +, Loss of Offsite Power +, Containment high range radiation monitor +, Safeguards Contingency Plan +, Battery sizing +, Earthquake +, Fuel cladding +, Pressure Boundary Leakage +, Power change +, Core Exit Thermocouple +, Unidentified leakage +  and Control Room Habitability +