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Letter  and Emergency Preparedness-Emergency Plan Implementing Procedures

Boron +, Iodine +, Carbon +, Hydrogen +  and Lead +

10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 73.71 +, 10 CFR 50 Appendix E +, 10 CFR 50.72#b +  and 10 CFR 50.4#b5iii +

S.2(o) +, H.5(a) +, S.3(o) +, S.6(o) +  and S.5(o) +

05000315  +, 05000316  +  and 00315  +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

Indiana Michigan Power Co +  and Mcintyre B +

ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +, ML032900444 +  and ML032900444 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

I-131 +  and H-3 +

NUREG/CR-4982, Board Notification 87-013:forwards Final NUREG/CR-4982, Severe Accidents in Spent Fuel Pools in Support of Generic Issue 82, Per Commitment of 870327 Board Notification 87-005.W/o Encl +, 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-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 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

AOP +, ES +, Emergency Operating Procedure +  and Emergency Plan +

1O-PRC-002 +  and 07-23-112 +

Manual Scram +  and Automatic Scram +

Washington +, Michigan +  and Indiana +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Emergency Response Data System +, Shutdown Cooling +, Safety Parameter Display System +, Residual Heat Removal +, Main Steam Safety Valve +, Remote shutdown +, Steam Jet Air Ejector +, Decay Heat Removal +, Main Condenser +, Control Rod +, Auxiliary Feed Water +  and Containment Spray +

TS-3.4.8 +, TS-1.1 +  and TS-3.3.1 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Ultimate heat sink +, Grab sample +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Design basis earthquake +, Earthquake +, Fuel cladding +, Pressure Boundary Leakage +, Power change +, Core Exit Thermocouple +, Unidentified leakage +, High range area radiation monitor +  and Spill +