ENS 46506

v t e ENS Event
16:50 Dec 23, 2010
Title	Uncomplicated Reactor Trip from 100% Power
Event Description	At 1050 CST on 12/23/2010, Fort Calhoun Station experienced a reactor trip due to an unknown cause. No abnormal indications were present at the time of the trip. [Procedure] "EOP-00, Standard Post Trip Actions, was performed. At 1054 CST, transitioned to [procedure] EOP-01, Reactor Trip Recovery. All Safety Functions of EOP-01 are being satisfied. At 1207 CST, 345KV Backfeed was established to all 4160V buses. The plant is currently stable in Mode 3, and the station continues efforts to determine the cause of the reactor trip. All tripable control rods fully inserted during the reactor trip. No PORVs or safety valves lifted. The steam generators are being fed from the Main Feed Pumps and decay heat is being removed to the main condenser. No Emergency Safety Features actuated during the trip except for the reactor trip. The licensee notified the NRC Resident Inspector.

ENS 46506 +/-
Where
Fort Calhoun Nebraska (NRC Region 4)
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:+-4.17 h-0.174 days <br />-0.0248 weeks <br />-0.00571 months <br />)
Opened:	Nathan Seid 12:40 Dec 23, 2010
NRC Officer:	Mark Abramovitz
Last Updated:	Dec 23, 2010
46506 - NRC Website Loading map...
v • d • e

v t e Emergency Notification System
Fort Calhoun with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2016-06-22T13:41:00 [Table view]
[ENS list for Fort Calhoun]

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