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Boron +, Iodine +, Cesium +, Nitrogen +, Carbon +, Hydrogen +, Chloride +, Lead +  and Silver +

10 CFR 50.73 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.59 +  and 10 CFR 50.47 +

Emergency Preparedness +  and Initiating Events +

U-0643 +, U-603471 +  and U-600940 +

Technical Support Center +  and Emergency Operations Facility +

Reactor Trip +  and Turbine Trip +

GDC 20 +, GDC 54 +, GDC 10 +, GDC 13 +, GDC 2, Design bases for protection against natural phenomena +  and GDC 19, Control room +

NRC Generic Letter 81-32, NUREG-0737, Item II.K.3.44-Evaluation of Anticipated Transients Combined with Single Failure +, NRC Generic Letter 83-05, Safety Evaluation of "Emergency Procedure Guidelines, Revision 2," June 1982 +  and NRC Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs +

ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +, ML22216A218 +...

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

IEEE 323-1974 +  and IEEE 344-1975 +

ML020800179 +, ML20010H747 +, ML20099C742 +, ML20098A392 +, ML20113D349 +, ML20137M239 +, IR 05000461/1985025 +, ML19338C551 +, ML20032A578 +  and ML20066J899 +

General Electric +  and Westinghouse +

NUREG-0835 +, NUREG-0623 +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, 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-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-0853, Forwards Suppl 6 to NUREG-0853, SER Re Operation of Clinton Power Station,Unit 1 +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, 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-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.97 +, Regulatory Guide 1.47 +, Regulatory Guide 1.3 +, Regulatory Guide 1.70 +  and Regulatory Guide 1.101 +

NEDO-24708A +, NEDE-20566P +, NEDE-24988 +, NEDO-24708 +, NEDO-3133 +  and NEDO-24934 +

07-79-05B +  and 07-79-06A +

Manual Scram +  and Automatic Scram +

Tennessee +, Illinois +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +...

Reactor Vessel Water Level +, Grab sample +, Probabilistic Risk Assessment +, Shift Technical Advisor +, Loss of Offsite Power +, Commercial Grade +, Fuel cladding +, Control Room Habitability +  and Basic Component +