ENS 40286: Difference between revisions

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| event date = 10/31/2003 19:48 EST
| event date = 10/31/2003 19:48 EST
| last update date = 10/31/2003
| last update date = 10/31/2003
| title = Reactor Trip On Low Steam Generator Water Level
| title = Reactor Trip on Low Steam Generator Water Level
| event text = Automatic Reactor Trip due to low Steam Generator levels.  All systems responded normally.  Plant is stable at NOT/NOP [normal operating temperature and pressure] in Mode 3.  Emergency Feedwater system actuated as designed due to reactor trip.
| event text = Automatic Reactor Trip due to low Steam Generator levels.  All systems responded normally.  Plant is stable at NOT/NOP [normal operating temperature and pressure] in Mode 3.  Emergency Feedwater system actuated as designed due to reactor trip.
Lowest Steam Generator level reached was just below the trip setpoint of 25%.  Low level caused by trip of one of two Main Feed Pumps.  All control rods fully inserted.  No primary or secondary relief valves lifted.  The electrical system is stable and the EDG's remain in standby.  Decay heat is being removed via steam dumps.   
Lowest Steam Generator level reached was just below the trip setpoint of 25%.  Low level caused by trip of one of two Main Feed Pumps.  All control rods fully inserted.  No primary or secondary relief valves lifted.  The electrical system is stable and the EDG's remain in standby.  Decay heat is being removed via steam dumps.   

Latest revision as of 21:24, 1 March 2018

ENS 40286 +/-
Where
Seabrook 
New Hampshire (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: 05000443/LER-2003-002
Regarding Reactor Trip Following the Loss of a Main Feed Pump
Time - Person (Reporting Time:+-3.55 h-0.148 days <br />-0.0211 weeks <br />-0.00486 months <br />)
Opened: Tom Waechter
21:15 Oct 31, 2003
NRC Officer: Mike Ripley
Last Updated: Oct 31, 2003
40286 - NRC Website
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