ENS 43358
ENS Event | |
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06:02 Mar 15, 2007 | |
Title | Invalid Eccs and System Actuations |
Event Description | This telephone notification is provided in accordance with 10 CFR 50.73(a)(1), to report an invalid actuation reportable under 10 CFR 50.73(a)(2)(iv)(A).
On March 15, 2007, with Unit 2 in a refueling outage, the reactor vessel was filled to a solid condition and being depressurized following the completion of the vessel hydrostatic test. At 0102 CDST, with pressure indicating approximately 43 psig, the 2B Residual Heat Removal (RHR) pump was started in the shutdown cooling mode. With the vessel solid, the resultant pressure transient caused invalid reactor vessel low-level trip signals and Division 2 and 3 ECCS actuations. The 2C RHR pump auto-started and injected into the vessel. The 2A Diesel Generator (DG) started, and 2B RHR Injection valve (2E12-F042B) auto-opened. The Division 3 ECCS actuation did not result in any equipment starts because the High Pressure Core Spray pump and the 2B DG were properly removed from service at the time of the event. The operators verified that the reactor vessel low-level trips and ECCS actuations were invalid, and shut down the 2C RHR pump and the 2A DG. The 2B RHR Injection Valve was also closed. The cause was determined to be a knowledge deficiency compounded by less than adequate procedural guidance regarding starting shutdown cooling while the reactor vessel is in a solid condition. Corrective actions included reviewing the event with licensed operators, revising the appropriate operating procedures, and developing just-in-time training for future use. The event is reportable under 10 CFR 50.73(a)(2)(iv)(A) as an invalid ECCS actuation and invalid system actuation. The licensee notified the NRC resident inspector. |
Where | |
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Lasalle Illinois (NRC Region 3) | |
Reporting | |
10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
Time - Person (Reporting Time:+1380.57 h57.524 days <br />8.218 weeks <br />1.891 months <br />) | |
Opened: | Todd Granlund 18:36 May 11, 2007 |
NRC Officer: | Gerry Waig |
Last Updated: | May 12, 2007 |
43358 - NRC Website
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Unit 2 | |
---|---|
Reactor critical | Not Critical |
Scram | No |
Before | Cold Shutdown (0 %) |
After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 552402021-03-10T13:15:00010 March 2021 13:15:00
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