05000220/LER-2009-003 | Manual Scram and High Pressure Coolant Injection Following a Loss of Feedwater Level Control Due to Firmware Deficiency | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000298/LER-2009-003 | Isolation of Residual Heat Removal Shutdown Cooling | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
05000263/LER-2009-004 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000397/LER-2009-004 | 6.9 kV Non-Segregated Electrical Bus Failure | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
05000286/LER-2009-004 | Automatic Reactor Trip During Single Feedwater Pump Operation Due to a High 32 Steam Generator Water Level Caused by Inadequate 31 Main Feedwater Pump Governor Valve Setting | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
05000395/LER-2009-004 | Manual reactor trip due to main steam dump system fault 05000 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000483/LER-2009-004 | Failure to Comply with Technical Specification 3.8.1 Required Action A.1 for One Offsite Circuit Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000325/LER-2009-004 | Technical Specification Required Shutdown Due To Emergency Diesel Generator 4 Inoperability | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
05000354/LER-2009-004 | Multiple Control Rod Drifts Resulting in a Reactor Scram | |
05000305/LER-2009-004 | Failed Backdraft Damper Renders Containment Fan Coil Unit Inoperable | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000237/LER-2009-004 | Unit 2 Shutdown Cooling System Isolation during Cooldown due to Temperature Instrumentation Failure | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
05000334/LER-2009-004 | Two Ultrasonic Indications Found in Reactor Coolant System Drain Pipe | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded |
05000382/LER-2009-004 | Condition prohibited by Technical Specification with Log Power Channel Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000361/LER-2009-004 | Both Trains of Spent Fuel Pool Cooling Inoperable Results in a Loss of Safety Function | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
05000366/LER-2009-004 | Turbine Trip On High Reactor Water Level Due To Failed Circuit Board Results in Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000298/LER-2009-005 | Cooper Nuclear Station 05000298 1Dof 5 | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
05000321/LER-2009-005 | Inadequate Procedure results in a Group 1 Isolation and Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000237/LER-2009-005 | Unit 2 Reactor Recirculation Drain Line Pressure Boundary Leakage | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded |
05000482/LER-2009-005 | Loss of both Diesel Generators with all fuel in the Spent Fuel Pool | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
05000382/LER-2009-005 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
05000263/LER-2009-005 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
05000361/LER-2009-005 | Wiring Error in Diesel Generator Circuit Results in Loss of Fire Isolation Capability | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
05000282/LER-2009-005 | Reactor Trip Due to 12 Circulating Water Pump Trip Caused by Electrical Ground Fault | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000354/LER-2009-005 | Missed EDG Surveillance Check | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000382/LER-2009-006 | Degraded Hydraulic Fluid Causes Both Main Feedwater Isolation Valves to Fail Inservice Test Stroke | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000354/LER-2009-006 | Post-fire Safe Shutdown Analysis Error | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
05000278/LER-2009-007 | Oil Leak from Main Steam Isolation Valve Dashpot Results in Short Valve Stroke Time | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |