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TEXT-SAFETY REPORT  and ANNUAL OPERATING REPORT

Boron +, Iodine +, Cobalt +, Nitrogen +, Carbon +, Sodium +, Hydrogen +, Chlorine +, Lead +, Aluminum +  and Zinc +

Control rod 30-11 +, Control rod 22-35 +, Control rod 30-35 +, Control rod 18-23 +, Control rod 18-15 +, Control rod 18-39 +, Control rod 54-43 +  and Control rod 25-35 +

05000373  +, 05000374  +  and 00373  +

Exelon +  and Ray D +

NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f) +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML20063M003 +, ML20063M003 +, ML20063M003 +, ML20063M003 +, ML20063M003 +, ML20063M003 +, ML20063M003 +, ML20063M003 +, ML20063M003 +, ML20063M003 +, ML20063M003 +  and ML20063M003 +

IEEE 344-1975 +  and IEEE 344-1971 +

Westinghouse +, Limitorque +  and General Electric +

AM +, ESP +, TOP +  and IAP-820-llTA +

1H13-P601 +, 2E12-F042A +, 2E12-F042B +, 1E51-F076 +, 2B21-F010A +, 2B33-F067B +, 1E51-F063 +, 2E51-F008 +, 1E12-F004B +, 2E12-F009 +, 1E12-F004A +, 235Y-2 +, 1E51-F008 +, 1G33-F001 +, 1B21-F028C +, 1B21-F022A +, 1E51-C002 +, 1B21-F067B +, 1E12-F041B +, 1E51-F019 +, 2E51-C001 +, 135Y-2 +, 1E22-S001 +, 1E51-F022 +, 2E51-F059 +, 1E51-F360 +, 2E51-F068 +, 1TR-CM037B +, 2E12-F064B +, 2D18-K751A +...

Illinois +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Residual Heat Removal Service Water +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

TS-3.4.5 +  and TS-3.7.5.3 +

Office of Nuclear Reactor Regulation +  and Office of Information Resources Management +

Safe Shutdown +, Loop seal +, Packing leak +, Grab sample +, Offsite Dose Calculation Manual +, Stroke time +, Hydrostatic +, Anchor Darling +, FLEX +, Local Leak Rate Testing +, Feedwater Heater +, Scram Discharge Volume +, Stress corrosion cracking +, Excess Flow Check Valve +, Integrated leak rate test +, Main Steam Line Radiation Monitor +, Overspeed trip +, Overspeed +  and Spent fuel rack +

Turbine bypass valve +  and Main Turbine Control Valve +