| | | Reporting criterion |
|---|
| 05000261/LER-2016-001, Regarding Inoperability of Motor-Driven Auxiliary Feedwater Pumps Due to Insufficient Lube Oil Cooling | Regarding Inoperability of Motor-Driven Auxiliary Feedwater Pumps Due to Insufficient Lube Oil Cooling | |
| 05000261/LER-2016-002, Unit No. 2, Regarding Unanalyzed Condition Related to Main Steam Line Break Inside Containment | Unit No. 2, Regarding Unanalyzed Condition Related to Main Steam Line Break Inside Containment | 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)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
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) |
| 05000261/LER-2016-003, Regarding Failure of Lake Robinson Tainter Gates to Fully Open During Performance of Functionality Testing | Regarding Failure of Lake Robinson Tainter Gates to Fully Open During Performance of Functionality Testing | 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), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i) |
| 05000261/LER-2016-004, Regarding Reactor Trip During the Performance of a Visual Inspection of the Main Turbine Trip Block | Regarding Reactor Trip During the Performance of a Visual Inspection of the Main Turbine Trip Block | 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)(x)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(viii) |
| 05000261/LER-2016-005, Regarding Reactor Trip and Automatic System Actuation Due to Weather-Related Loss of Offsite Power | Regarding Reactor Trip and Automatic System Actuation Due to Weather-Related Loss of Offsite Power | 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)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
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) |
