ENS 45790
ENS Event | |
|---|---|
15:28 Mar 25, 2010 | |
| Title | High Pressure Safety Injection Inoperable Due to Voids Identified in Suction Piping |
| Event Description | At 1028 CDT today 3/25/2010, a rejectable void was found in one of the suction lines (cooled suction line) to the B HPSI [High Pressure Safety Injection] pump. The main suction line is water filled. The piping was declared inoperable and the appropriate technical specification was entered. At 1357 CDT the void was cleared from the cooled suction line and the piping was declared operable. Subsequently, at 1409 CDT a similar rejectable void was discovered in the other cooled suction line for HPSI pumps A and C. The piping was declared inoperable. The appropriate technical specification was entered. At 1447 CDT the void was cleared and the piping was declared operable. Due to the close proximity of these occurrences the station is conservatively reporting this as a safety system functional failure as it appears that both trains of HPSI cooled suction were inoperable at the same time.
The licensee notified the NRC Resident Inspector.
Subsequent to making this event notification a detailed analysis of the event was performed by FAUSKE / Westinghouse Engineering. This evaluation determined the quantity of gas voiding in the piping, the duration of time the pump(s) would be subjected to gas voiding and potential effects on the piping support design loading. The hydraulic data was then reviewed by the HPSI pump manufacturer (Sulzer) to determine the effect on pump performance. Based on these evaluations, it has been determined that the HPSI pumps were not degraded, and that they were capable of performing their design basis function at all times and were operable. Therefore, this event does not meet the 10 CFR 50.72 reporting criteria and the notification is being retracted. The licensee notified the NRC Resident Inspector. Notified the R4DO (Shannon). |
| Where | |
|---|---|
Fort Calhoun  Nebraska (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat | |
| Time - Person (Reporting Time:+3.42 h0.143 days <br />0.0204 weeks <br />0.00468 months <br />) | |
| Opened: | Erick Matzke 18:53 Mar 25, 2010 |
| NRC Officer: | Vince Klco |
| Last Updated: | May 24, 2010 |
| 45790 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |