ENS 40591: Difference between revisions

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| event date = 03/15/2004 20:20 EST
| event date = 03/15/2004 20:20 EST
| last update date = 03/15/2004
| last update date = 03/15/2004
| title = Automatic Reactor Trip At Millstone 2 Due To Spurious Loss Of One Main Feed Pump
| title = Automatic Reactor Trip at Millstone 2 Due to Spurious Loss of One Main Feed Pump
| event text = The licensee reported that an automatic reactor trip occurred on 3/15/04 at 2020 EST due to the spurious trip of one main feed pump which caused a low steam generator water level trip signal. The plant has two main feed pumps. Operators reset the tripped main feed pump but steam generator levels didn't recover in time. The lowest level observed was in the "B" steam generator at 15% level as compared to the normal level of 65%. The trip setpoint is at 50% level. All control rods properly inserted into the core. The auxiliary feed water system automatically initiated as designed and expected. The plant remains stable in mode 3 while the licensee commenced the post trip review to determine the cause of the main feed pump trip. Decay heat removal was established using the AFW system to feed steam generators and bleed steam to the main condenser through the condenser dump valves.  
| event text = The licensee reported that an automatic reactor trip occurred on 3/15/04 at 2020 EST due to the spurious trip of one main feed pump which caused a low steam generator water level trip signal. The plant has two main feed pumps. Operators reset the tripped main feed pump but steam generator levels didn't recover in time. The lowest level observed was in the "B" steam generator at 15% level as compared to the normal level of 65%. The trip setpoint is at 50% level. All control rods properly inserted into the core. The auxiliary feed water system automatically initiated as designed and expected. The plant remains stable in mode 3 while the licensee commenced the post trip review to determine the cause of the main feed pump trip. Decay heat removal was established using the AFW system to feed steam generators and bleed steam to the main condenser through the condenser dump valves.  
The licensee notified the NRC Resident Inspector.
The licensee notified the NRC Resident Inspector.

Latest revision as of 22:23, 1 March 2018

ENS 40591 +/-
Where
Millstone Dominion icon.png
Connecticut (NRC Region 1)
Reporting
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation

10 CFR 50.72(b)(3)(iv)(A), System Actuation
LER: 05000336/LER-2004-002
Time - Person (Reporting Time:+-4.38 h-0.183 days <br />-0.0261 weeks <br />-0.006 months <br />)
Opened: Sunyoung Kwon
20:57 Mar 15, 2004
NRC Officer: Rich Laura
Last Updated: Mar 15, 2004
40591 - NRC Website
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