ENS 43932: Difference between revisions

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| event date = 01/24/2008 16:04 EST
| event date = 01/24/2008 16:04 EST
| last update date = 01/24/2008
| last update date = 01/24/2008
| title = Manual Reactor Trip Due To Failure Of The "C" Feedwater Flow Control Valve
| title = Manual Reactor Trip Due to Failure of the "C" Feedwater Flow Control Valve
| event text = At 1604 [EST], VC Summer Nuclear Station was manually tripped due to rapidly decreasing level in 'C' Steam Generator. The decreasing Steam Generator level was due to a failure of the 'C' Feedwater Flow Control Valve.  All systems responded as required.  All Emergency Feedwater Pumps automatically started on Lo-Lo Steam Generator level.  The Steam Generator levels recovered quickly.  The Pressurizer Level Control System cycling resulted in lifting the Letdown System Relief Valve due to high temperature and pressure.  The Letdown Relief Valve reseated with no further problems. One Moisture Separator Reheater Relief Valve lifted momentarily and reseated.
| event text = At 1604 [EST], VC Summer Nuclear Station was manually tripped due to rapidly decreasing level in 'C' Steam Generator. The decreasing Steam Generator level was due to a failure of the 'C' Feedwater Flow Control Valve.  All systems responded as required.  All Emergency Feedwater Pumps automatically started on Lo-Lo Steam Generator level.  The Steam Generator levels recovered quickly.  The Pressurizer Level Control System cycling resulted in lifting the Letdown System Relief Valve due to high temperature and pressure.  The Letdown Relief Valve reseated with no further problems. One Moisture Separator Reheater Relief Valve lifted momentarily and reseated.
Presently, the plant is in Mode 3 with normal RCS pressure and temperature.  Decay heat is being removed by dumping steam to the condenser. The plant will remain in  Mode 3 until repairs are completed on the 'C' Feedwater Flow Control Valve.
Presently, the plant is in Mode 3 with normal RCS pressure and temperature.  Decay heat is being removed by dumping steam to the condenser. The plant will remain in  Mode 3 until repairs are completed on the 'C' Feedwater Flow Control Valve.

Latest revision as of 21:15, 1 March 2018

ENS 43932 +/-
Where
Summer South Carolina Electric & Gas Company icon.png
South Carolina (NRC Region 2)
Reporting
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation

10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+-2.08 h-0.0867 days <br />-0.0124 weeks <br />-0.00285 months <br />)
Opened: Arnie Cribb
18:59 Jan 24, 2008
NRC Officer: Howie Crouch
Last Updated: Jan 24, 2008
43932 - NRC Website
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