ENS 46877: Difference between revisions

Latest revision as of 22:07, 1 March 2018

v t e ENS Event
16:20 May 24, 2011
Title	Lo-Lo Level in Steam Generator Results in Specified System Actuations
Event Description	At 11:20 [CDT] on 5/24/11, the unit, while in Mode 4, had a reactor trip and Aux Feedwater actuation/Feedwater Isolation Signal due to lo-lo level on 'B' Steam Generator. Reactor Trip breakers were closed to support DRPI [Digital Rod Position Indication] testing. Steam Generator levels were being maintained approximately 30% to support Aux Feedwater pump full flow testing. The trip occurred at 23.5% level in the steam generator. Reactor trip breakers opened and the motor-driven auxiliary feedwater pump fed the steam generators. The feedwater isolation valves fully closed. No other actuations occurred. Operators are in the process of resetting plant conditions to support completion of the testing in progress at the time of the trip. The licensee has notified the NRC Resident Inspector.

ENS 46877 +/-
Where
Wolf Creek Kansas (NRC Region 4)
Reporting

10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+-2.67 h-0.111 days <br />-0.0159 weeks <br />-0.00366 months <br />)
Opened:	Jeremiah Strahm 13:40 May 24, 2011
NRC Officer:	Howie Crouch
Last Updated:	May 24, 2011
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v • d • e

v t e Emergency Notification System
Wolf Creek with 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2022-07-23T00:49:00 [Table view]
[ENS list for Wolf Creek]

@@ Line 16: / Line 16: @@
 | event date = 05/24/2011 11:20 CDT
 | last update date = 05/24/2011
-| title = Lo-Lo Level In Steam Generator Results In Specified System Actuations
+| title = Lo-Lo Level in Steam Generator Results in Specified System Actuations
 | event text = At 11:20 [CDT] on 5/24/11, the unit, while in Mode 4, had a reactor trip and Aux Feedwater actuation/Feedwater Isolation Signal due to lo-lo level on 'B' Steam Generator. Reactor Trip breakers were closed to support DRPI [Digital Rod Position Indication] testing. Steam Generator levels were being maintained approximately 30% to support Aux Feedwater pump full flow testing.
 The trip occurred at 23.5% level in the steam generator. Reactor trip breakers opened and the motor-driven auxiliary feedwater pump fed the steam generators.  The feedwater isolation valves fully closed. No other actuations occurred. Operators are in the process of resetting plant conditions to support completion of the testing in progress at the time of the trip.

Latest revision as of 22:07, 1 March 2018