ENS 40596
ENS Event | |
|---|---|
20:57 Mar 17, 2004 | |
| Title | Switchgear Rooms Flooding Analysis Concerns |
| Event Description | {{#Wiki_filter:At 1457 on 3-17-2004, Wolf Creek Generating Station Fire Protection Engineering submitted information to the Control Room that there was a flooding analysis concern in the Engineered Safety Features Switchgear (NB) Rooms regarding the 2 � inch fire protection header that is located in the rooms. The capability of the floor drain system in the room is indeterminate in regards to draining all the water that could be expected to accumulate in the rooms if the fire main were to rupture during a seismic event.
Compensatory actions have been put in place in the form of additional fire suppression equipment and administrative isolation of the fire protection header that is located in the NB switchgear rooms. Investigation continues into the assumptions used in the flooding and seismic analysis. The Senior Resident Inspector has been notified.
On March 17, 2004, at 2125 EST, Wolf Creek Nuclear Operating Corporation (WCNOC) made an event notification regarding a flooding analysis concern related to a 2 1/2 Inch fire protection header located in the Engineered Safety Features Switchgear (NB) Rooms (EN40596). This notification identified that the analysis with regards to draining all the water from the room in the event that the fire protection header pipe were to rupture during a seismic event was indeterminate. Subsequent evaluation has determined that the fire protection header piping located in the subject NB switchgear rooms is built to seismic Il/I requirements, and is therefore not subject to a pipe rupture in the event of a seismic event. Therefore, WCNOC is retracting the March 17, 2004 event notification. The NRC Senior Resident Inspector has been notified. Notified R4DO (L. Smith). }} |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+0.47 h0.0196 days <br />0.0028 weeks <br />6.43806e-4 months <br />) | |
| Opened: | Dave Dees 21:25 Mar 17, 2004 |
| NRC Officer: | Mike Ripley |
| Last Updated: | May 11, 2004 |
| 40596 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |