The following information was obtained from the licensee via facsimile:
1. SYSTEMS AFFECTED: Reactor trip, Aux feed water actuation.
2. ACTUATIONS AND THEIR INITIATING SIGNALS: Reactor trip - Loss of Load Turbine Trip, Aux Feed Water (AFW) - 21% [on the narrow range indication] in Steam Generators.
3. CAUSES: Reactor tripped due to an undetermined cause in the main generator end of the secondary plant. AFW started as expected on EFAS [Emergency Feedwater Actuation Signal] at 21% from a trip at 100%.
4. EFFECT OF EVENT ON PLANT: Plant is stable at 545F [and] 2250 [psi] hot standby conditions and will remain here until cause determination made as to cause of trip.
5. ACTIONS TAKEN OR PLANNED: Maintain hot standby conditions for post trip review.
CONTINUATION SHEET: 1) Remain in Mode 3 for cause determination post-trip review to provide actual mode required. 2) Estimate restart date pending cause determination and any repairs required. 3) All rods inserted, no primary or secondary reliefs lifted, electrical grid stable, all safety systems performed as expected, no effect on Unit 3. Electrical power supplied from offsite power.
Decay heat removal is via steam dump to condenser.
The licensee has notified the NRC Resident Inspector.
