ENS 50607: Difference between revisions

v t e ENS Event
20:48 Nov 12, 2014
Title	Manual Reactor Trip Due to Lowering Steam Generator Water Level
Event Description	On November 12, 2014 at 1548 [EST], Unit 2 was manually tripped due to a lowering 2B steam generator level caused by the spurious (slow) closure of 2B Main Feedwater Isolation Valve, HCV-09-2B. All CEAs [control element assemblies] fully inserted into the core. All safety systems responded as expected with the 2B Auxiliary Feedwater Actuation System Channel 2 (AFAS 2) actuating on low 2B steam generator level. Decay heat removal is from main feedwater to the 2A steam generator and manual control of auxiliary feedwater to the 2B steam generator, with steam bypass to the main condenser. This event is reportable pursuant to 10 CFR 50.72(b)(2)(iv)(B) for the reactor trip and 10 CFR 50.72(b)(3)(iv)(A) for the AFAS 2 actuation. During the transient, no relief or safety valves lifted. The grid is stable and the plant is in its normal shutdown electrical lineup at normal operating pressure and temperature. The cause of the feedwater isolation valve malfunction is under investigation. There was no effect on Unit 1. The licensee has notified the NRC Resident Inspector.

ENS 50607 +/-
Where
Saint Lucie Florida (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:+-2.28 h-0.095 days <br />-0.0136 weeks <br />-0.00312 months <br />)
Opened:	Fred Pollak 18:31 Nov 12, 2014
NRC Officer:	Howie Crouch
Last Updated:	Nov 12, 2014
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v • d • e

v t e Emergency Notification System
Saint Lucie with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2024-07-28T22:37:00 [Table view]
[ENS list for Saint Lucie]

@@ Line 16: / Line 16: @@
 | event date = 11/12/2014 15:48 EST
 | last update date = 11/12/2014
-| title = Manual Reactor Trip Due To Lowering Steam Generator Water Level
+| title = Manual Reactor Trip Due to Lowering Steam Generator Water Level
 | event text = On November 12, 2014 at 1548 [EST], Unit 2 was manually tripped due to a lowering 2B steam generator level caused by the spurious (slow) closure of 2B Main Feedwater Isolation Valve, HCV-09-2B.
 All CEAs [control element assemblies] fully inserted into the core. All safety systems responded as expected with the 2B Auxiliary Feedwater Actuation System Channel 2 (AFAS 2) actuating on low 2B steam generator level. Decay heat removal is from main feedwater to the 2A steam generator and manual control of auxiliary feedwater to the 2B steam generator, with steam bypass to the main condenser.

Latest revision as of 20:49, 1 March 2018