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The following information, in addition to … The following information, in addition to the phone report, was obtained from the licensee via facsimile:</br>Fort Calhoun Station Unit 1 experienced a reactor trip from 16.1% Reactor Power on a Loss of Turbine Load during a scheduled plant shutdown for a refueling outage.</br>The turbine generator was tripped offline at 2101 per refueling outage schedule. A feedwater transient occurred (cause being investigated) during turbine testing, resulting in power rising rapidly from 12.6% to 16.1% . At which point the reactor tripped on loss of load due to being greater than 15% power with all turbine stop valves closed.</br>All plant equipment functioned as designed. A Reactor Coolant System (RCS) cooldown resulted due to a feedwater transient. Main Feedwater was isolated, which terminated the cooldown. Auxiliary Feedwater (AFW) was established with the diesel driven auxiliary feed pump. Emergency Boration was manually initiated due to the RCS cooldown and secured after shutdown margin verification. Plant is currently stable in mode 3.</br>This report is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) for an event that resulted in an event that resulted in an unplanned RPS actuation while the reactor was critical.</br>All rods fully inserted, no ECCS actuation and no relief valves lifted. Steam generators are being used for heat sink.</br>The NRC resident Inspector was notifiedk.
The NRC resident Inspector was notified +
03:34:00, 27 February 2005 +
41,446 +
01:26:00, 27 February 2005 +
03:34:00, 27 February 2005 +
The following information, in addition to … The following information, in addition to the phone report, was obtained from the licensee via facsimile:</br>Fort Calhoun Station Unit 1 experienced a reactor trip from 16.1% Reactor Power on a Loss of Turbine Load during a scheduled plant shutdown for a refueling outage.</br>The turbine generator was tripped offline at 2101 per refueling outage schedule. A feedwater transient occurred (cause being investigated) during turbine testing, resulting in power rising rapidly from 12.6% to 16.1% . At which point the reactor tripped on loss of load due to being greater than 15% power with all turbine stop valves closed.</br>All plant equipment functioned as designed. A Reactor Coolant System (RCS) cooldown resulted due to a feedwater transient. Main Feedwater was isolated, which terminated the cooldown. Auxiliary Feedwater (AFW) was established with the diesel driven auxiliary feed pump. Emergency Boration was manually initiated due to the RCS cooldown and secured after shutdown margin verification. Plant is currently stable in mode 3.</br>This report is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) for an event that resulted in an event that resulted in an unplanned RPS actuation while the reactor was critical.</br>All rods fully inserted, no ECCS actuation and no relief valves lifted. Steam generators are being used for heat sink.</br>The NRC resident Inspector was notifiedk.
The NRC resident Inspector was notified +
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