ENS 44831: Difference between revisions
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| event date = 02/05/2009 15:24 CST | | event date = 02/05/2009 15:24 CST | ||
| last update date = 02/05/2009 | | last update date = 02/05/2009 | ||
| title = Unit 1 Manually Tripped Due | | title = Unit 1 Manually Tripped Due to Control Rod Drive Motor High Temperatures | ||
| event text = Arkansas Nuclear One Unit 1 was manually tripped from 61% power due to Control Rod Drive motor (CRD) high temperatures due to a loss of cooling water flow from Non-Nuclear Intermediate Cooling Water (ICW). No significant equipment issues were observed. No primary safeties lifted. Secondary safeties lifted for ~18 seconds. Emergency feedwater did not actuate and was not needed. Post trip response was normal and the plant is stable in mode 3. Post transient review is in progress. | | event text = Arkansas Nuclear One Unit 1 was manually tripped from 61% power due to Control Rod Drive motor (CRD) high temperatures due to a loss of cooling water flow from Non-Nuclear Intermediate Cooling Water (ICW). No significant equipment issues were observed. No primary safeties lifted. Secondary safeties lifted for ~18 seconds. Emergency feedwater did not actuate and was not needed. Post trip response was normal and the plant is stable in mode 3. Post transient review is in progress. | ||
All control rods fully inserted into the core. There is no known primary-secondary steam generator tube leakage. The offsite electrical grid is stable. The loss of ICW flow is attributed to the mechanical failure of service air compressor C-3A. Decay heat removal is via main feedwater to the steam generator and steam to the main condenser. | All control rods fully inserted into the core. There is no known primary-secondary steam generator tube leakage. The offsite electrical grid is stable. The loss of ICW flow is attributed to the mechanical failure of service air compressor C-3A. Decay heat removal is via main feedwater to the steam generator and steam to the main condenser. |
Latest revision as of 22:12, 1 March 2018
Where | |
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Arkansas Nuclear Arkansas (NRC Region 4) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
Time - Person (Reporting Time:+-2.07 h-0.0863 days <br />-0.0123 weeks <br />-0.00284 months <br />) | |
Opened: | Bob Fowler 19:20 Feb 5, 2009 |
NRC Officer: | Steve Sandin |
Last Updated: | Feb 5, 2009 |
44831 - NRC Website
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