ENS 45098: Difference between revisions

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| event date = 05/28/2009 06:25 EDT
| event date = 05/28/2009 06:25 EDT
| last update date = 05/28/2009
| last update date = 05/28/2009
| title = Automatic Reactor Trip Resulting From A High Steam Generator Level Turbine Trip
| title = Automatic Reactor Trip Resulting from a High Steam Generator Level Turbine Trip
| event text = At 0530 EDT a power reduction commenced due to elevated vibrations on 32 MBFP [Main Boiler Feedwater Pump].  When reactor power reached 60% the team was attempting to stabilize reactor power when a level excursion occurred in 32 steam generator.  When level reached its high level turbine trip set point an automatic reactor trip occurred and all systems responded as expected.  Auxiliary feedwater actuated as expected.  The Unit is currently in mode 3 and stable with auxiliary feed water in service and reactor temperature maintained with the steam dumps to the main condenser. Investigation into the cause of the steam generator level excursion is in progress.  Offsite power is available and supplying safeguard busses.  Unit 2 was unaffected and remains at 100% power.  The [NRC] Resident Inspector has been notified.
| event text = At 0530 EDT a power reduction commenced due to elevated vibrations on 32 MBFP [Main Boiler Feedwater Pump].  When reactor power reached 60% the team was attempting to stabilize reactor power when a level excursion occurred in 32 steam generator.  When level reached its high level turbine trip set point an automatic reactor trip occurred and all systems responded as expected.  Auxiliary feedwater actuated as expected.  The Unit is currently in mode 3 and stable with auxiliary feed water in service and reactor temperature maintained with the steam dumps to the main condenser. Investigation into the cause of the steam generator level excursion is in progress.  Offsite power is available and supplying safeguard busses.  Unit 2 was unaffected and remains at 100% power.  The [NRC] Resident Inspector has been notified.
No safety or relief valves lifted during this event.
No safety or relief valves lifted during this event.

Latest revision as of 21:11, 1 March 2018

ENS 45098 +/-
Where
Indian Point Entergy icon.png
New York (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:+-3.22 h-0.134 days <br />-0.0192 weeks <br />-0.00441 months <br />)
Opened: Dan Lyon
07:12 May 28, 2009
NRC Officer: Mark Abramovitz
Last Updated: May 28, 2009
45098 - NRC Website
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