| | | Reporting criterion |
|---|
| 05000335/LER-2019-001-01, 1 for St. Lucie Unit 1, Regarding Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load | 1 for St. Lucie Unit 1, Regarding Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load | |
| 05000335/LER-2019-001, Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load | Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) |
| 05000335/LER-2019-002, Reactor Coolant Pump Motor Ground Results in Reactor Coolant Pump Trip and Subsequent Automatic Reactor Trip | Reactor Coolant Pump Motor Ground Results in Reactor Coolant Pump Trip and Subsequent Automatic Reactor Trip | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A) |
| 05000335/LER-2019-003, Inoperability of Emergency Diesel Generator Due to Cracked Crankshaft | Inoperability of Emergency Diesel Generator Due to Cracked Crankshaft | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) |
