ENS 44165
ENS Event | |
|---|---|
07:56 Apr 25, 2008 | |
| Title | Both Emergency Diesel Generators Declared Inoperable |
| Event Description | On 4/24/2008 at 0110 CDT, a concern with the flexible connection alignment between heat exchangers on the 'A' Emergency Diesel Generator was identified. At the time this condition was identified the 'A' Diesel was out of service for outage maintenance activities. During evaluation of this condition, and discussions with the vendor supplier for this flexible connection, additional questions arose and the condition of the identical connections on the 'B' Emergency Diesel Generator was questioned. Inspection of the 'B' Emergency Diesel Generator identified a similar problem, and at 0256 CDT on 4/25/2008, the 'B' Emergency Diesel Generator was declared inoperable, and the Plant entered TS 3.8.2, Condition B, for one required Diesel Generator being inoperable. All required actions regarding TS 3.8.2 have been complied with.
The 'B' Emergency Diesel Generator is still considered to be functional, and remains aligned for automatic start. The 'A' EDG is currently tagged out and work is ongoing to correct the alignment issue. Upon completion of repair to the 'A' EDG it will be restored to operation and the 'B' EDG will be removed from service to correct the alignment issue. The plant is currently in Mode 6, with RCS level greater than 23 feet above the Reactor Vessel Flange, and both required Offsite Power Sources remain operable. The licensee notified the NRC Resident Inspector.
Testing, conducted by the vendor, was performed on the flexible connections in the configuration found at Wolf Creek and in a worst case configuration. The joints were tested, up to design pressure with a joint movement equivalent to a design bases earthquake, without failing. Additionally, the joints were pressurized to burst pressure, which was determined to be greater than 5 times the design pressure of the connection. The testing showed that even though the joints were not installed in accordance with the vendor's recommendation they would have fulfilled their safety function as installed. Therefore, a condition that could have prevented fulfillment of a safety function did not exist. Wolf Creek is retracting the 50.72(b)(3)(v)(B) notification. The licensee notified the NRC Resident Inspector. Notified R4DO (Proulx). |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat | |
| Time - Person (Reporting Time:+2.72 h0.113 days <br />0.0162 weeks <br />0.00373 months <br />) | |
| Opened: | Terry Damashek 10:39 Apr 25, 2008 |
| NRC Officer: | John Knoke |
| Last Updated: | Jun 23, 2008 |
| 44165 - NRC Website
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