ENS 45931: Difference between revisions

Latest revision as of 22:09, 1 March 2018

v t e ENS Event
14:17 May 17, 2010
Title	Automatic Reactor Trip Due to Low Steam Generator Water Level
Event Description	System Affected: RPS actuation and reactor trip. Actuation Initiation Signals: AFW auto initiation. Cause: Low level 'C' steam generator. Effect of event on Plant: Reactor and turbine trip. Actions taken or Planned: Standard post trip actions. Additional information: Plant stabilized at NOP/NOT. The licensee experienced a feedwater transient which initiated the event. All safety systems are available. All control rods fully inserted. The electrical lineup is normal. The decay heat path is through the condenser steam dumps. There were no relief valve or safety valve lifted during the transient. Primary plant temperature is 555 degrees Fahrenheit, and primary plant pressure is 2250 psig. The licensee is investigating the cause of the feed transient. The licensee notified the NRC Resident Inspector, the Waterford Dispatch, and the State Department of Environmental Protection,

ENS 45931 +/-
Where
Millstone 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
Time - Person (Reporting Time:+-1.83 h-0.0763 days <br />-0.0109 weeks <br />-0.00251 months <br />)
Opened:	Bob Kastner 12:27 May 17, 2010
NRC Officer:	Joe O'Hara
Last Updated:	May 17, 2010
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v • d • e

v t e Emergency Notification System
Millstone with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2023-05-30T08:46:00 [Table view]
[ENS list for Millstone]

@@ Line 16: / Line 16: @@
 | event date = 05/17/2010 10:17 EDT
 | last update date = 05/17/2010
-| title = Automatic Reactor Trip Due To Low Steam Generator Water Level
+| title = Automatic Reactor Trip Due to Low Steam Generator Water Level
 | event text = System Affected: RPS actuation and reactor trip.  Actuation Initiation Signals:  AFW auto initiation.  Cause: Low level 'C' steam generator.  Effect of event on Plant: Reactor and turbine trip. Actions taken or Planned: Standard post trip actions.  Additional information: Plant stabilized at NOP/NOT.
 The licensee experienced a feedwater transient which initiated the event.  All safety systems are available.  All control rods fully inserted.  The electrical lineup is normal. The decay heat path is through the condenser steam dumps.  There were no relief valve or safety valve lifted during the transient.  Primary plant temperature is 555 degrees Fahrenheit, and primary plant pressure is 2250 psig.  The licensee is investigating the cause of the feed transient.

Latest revision as of 22:09, 1 March 2018