ENS 42013
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ENS Event | |
|---|---|
19:10 Sep 25, 2005 | |
| Title | Degradation in Fire Barrier Discovered During an Inspection |
| Event Description | During an inspection of structural steel in the Emergency Filtration Train (EFT) building, it was determined that a portion of the steel did not have adequate fire retardant material protecting the steel. This condition would have compromised the 3 hour-fire barrier between the 2 divisions of the Emergency Service Water (ESW) System, impacting # 11 Emergency Diesel Generator ESW Pumps, # 13 and # 14 ESW Pumps. This condition could have resulted in the inability to establish and maintain cold shutdown conditions in the event of a fire in this area. A fire impairment was entered and an hourly fire watch was established to address this condition. All ESW divisions are presently operable.
The NRC Resident Inspector will be notified of this event by the licensee.
Monticello is retracting the event notification based on further investigation of the issue. The station has completed calculations that confirm the affected steel beams are not required to maintain fire barrier integrity. Further, the fire severity in the zone will not cause the steel beams to fail. Therefore, the ability of the station to establish and maintain cold shutdown conditions in the event of a fire in this area was not impacted. Based on this information, Monticello has determined there was no unanalyzed condition as reported in Event Notification 42013. The degraded fire retardant material has been replaced. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
| Monticello Minnesota (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+0.65 h0.0271 days <br />0.00387 weeks <br />8.9037e-4 months <br />) | |
| Opened: | Curt Arndt 19:49 Sep 25, 2005 |
| NRC Officer: | John Mackinnon |
| Last Updated: | Nov 11, 2005 |
| 42013 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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