ENS 45377: Difference between revisions
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| event date = 09/22/2009 13:29 CDT | | event date = 09/22/2009 13:29 CDT | ||
| last update date = 09/22/2009 | | last update date = 09/22/2009 | ||
| title = Unanalyzed Condition Resulting | | title = Unanalyzed Condition Resulting from an Unlatched Door Serving as a High Energy Line Break Barrier | ||
| event text = Based on the results of a past operability evaluation completed on 1329 [CDT], 9/22/2009, it appears that an unanalyzed condition existed intermittently for short periods of time in which a door that serves as a High Energy Line Break (HELB) barrier may have been unlatched. With the door not latched, an engineering evaluation concluded that a critical crack (HELB) in the Main Feedwater pipe traversing the south penetration room would force the door (DR-19) open, creating a harsh environment in the adjoining Emergency Feedwater (EFW) pump room. Because the EFW pump room is not evaluated for harsh conditions, it must be conservatively assumed that both pumps may fail to operate following this HELB event. Therefore, this condition is being reported in accordance with 10CFR50.72(b)(3)(ii)(B) as an unanalyzed condition that significantly degrades plant safety. | | event text = Based on the results of a past operability evaluation completed on 1329 [CDT], 9/22/2009, it appears that an unanalyzed condition existed intermittently for short periods of time in which a door that serves as a High Energy Line Break (HELB) barrier may have been unlatched. With the door not latched, an engineering evaluation concluded that a critical crack (HELB) in the Main Feedwater pipe traversing the south penetration room would force the door (DR-19) open, creating a harsh environment in the adjoining Emergency Feedwater (EFW) pump room. Because the EFW pump room is not evaluated for harsh conditions, it must be conservatively assumed that both pumps may fail to operate following this HELB event. Therefore, this condition is being reported in accordance with 10CFR50.72(b)(3)(ii)(B) as an unanalyzed condition that significantly degrades plant safety. | ||
The licensee informed the Arkansas Department of Health. | The licensee informed the Arkansas Department of Health. | ||
Latest revision as of 22:11, 1 March 2018
| Where | |
|---|---|
Arkansas Nuclear  Arkansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+-3.3 h-0.138 days <br />-0.0196 weeks <br />-0.00452 months <br />) | |
| Opened: | Crystal Garbe 15:11 Sep 22, 2009 |
| NRC Officer: | Dong Park |
| Last Updated: | Sep 22, 2009 |
| 45377 - NRC Website
| |