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TEXT-SAFETY REPORT, NUREG REPORTS  and SAFETY EVALUATION REPORT--FACILITY

IWC-2500 +, IWB-1220 +, IWC-1220 +, IWC-2520 +  and IWC-1230 +

ASME Section XI +, ASME Section III +  and ASME Section V +

Iodine +, Carbon +  and Lead +

10 CFR 50 +, 10 CFR 50 Appendix E +, 10 CFR 50.55a +, 10 CFR 950.54#s2 +, 10 CFR 50.55a#g +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g2 +, 10 CFR 50.55a#a2 +, 10 CFR 50.55a#a2i +  and 10 CFR 50.55#g +

00373  +, 00374  +, 05000373  +, 05000374  +, 00416  +  and 00417  +

ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +, ML20055B279 +  and ML20055B279 +

ML20010F609 +, ML20050B696 +, ML20054F926 +  and ML20054H785 +

NUREG-519 +, NUREG-0519, Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +  and 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 +

ES +  and ST +

Illinois +, Maryland +, Washington +, New York +  and Mississippi +

Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Automatic Depressurization System +, Emergency Core Cooling System +, Control Rod +  and Main Steam +

Safe Shutdown +, Hydrostatic +, Operating Basis Earthquake +, Nondestructive Examination +, Incorporated by reference +, Scram Discharge Volume +, Stress corrosion cracking +, Loss of Offsite Power +, Control of Heavy Loads +  and Liquid penetrant +