Event Notification Report for November 17, 2008

UNUSUAL EVENT DECLARED DUE TO FIRE IN PROTECTED AREA LASTING GREATER THAN 15 MINUTES

Grand Gulf declared an unusual event at 0925 CST based on a fire in the protected area lasting longer than 15 minutes. The fire was discovered at 0911 CST under the B reactor feedwater pump. The fire involved oil accumulated under the feedwater pump. The fire brigade responded and extinguished the fire at 0935 CST. The B reactor feedwater pump was tripped offline and reactor power was reduced to 48% power due to the reduction in feedwater flow. The reactor is stable and there is no ongoing threat from the fire. There is no apparent damage to plant equipment and the cause of the oil leak is unknown at this time. The licensee plans to exit the UE when the licensee confirms there is no concern from fire reflash.

The license has notified the required State and local authorities. The NRC Resident Inspector has been notified.

* * * UPDATE FROM PAT BLUDAU TO JOHN KNOKE AT 1300 EST ON 11/17/08 * * *

"Fire confirmed at 0911 CST in 'B' Reactor Feed Pump Turbine room. Plant power was reduced by Control Room; then "B" Reactor Feed Pump Turbine was tripped in order for the Fire Brigade to combat the fire. Unusual Event declared due to Fire in Protected Area lasting greater than 15 minutes. (HU4). Fire reported out at 0935. No external assistance is needed. Unusual Event terminated at 1134 CST."

Licensee has notified the NRC Resident Inspector, and state and local agencies. Notified R4 RA (Collins), R4 (Cain), NRR (Leeds), NRR (Thorp), IRD (Grant), FEMA (Barden), DHS (Moore).

MANUAL REACTOR SCRAM DUE TO HIGH TURBINE VIBRATION

"At 0551 hours EST, on November 17, 2008, the H. B. Robinson Steam Electric Plant, Unit No. 2, reactor was manually tripped from approximately 78% power due to high vibrations detected on the main turbine. The reactor trip was initiated in accordance with Abnormal Operating Procedure, AOP-006, "Turbine Eccentricity / Vibration." At approximately 0230 hours EST, it was noticed that turbine vibration on the No. 9 bearing was at approximately 10.9 mils and increasing. At 0516 hours EST, the No. 9 bearing was at about 13.5 mils and still increasing. A power reduction from 100% power was commenced in accordance with Operating Procedure, OP-105, "Maneuvering the Plant when Greater than 25% Power." At approximately 0551 hours EST, with power level at approximately 78%, the No. 9 bearing vibrations reached the trip criterion of 14 mils and the reactor was tripped in accordance with AOP-006.

"Path-1, which is the flow chart based on the Westinghouse Owners Group Emergency Response Guideline E-0 for reactor trip response, and Procedures EPP-4, "Reactor Trip Response," and GP-004, "Post Trip Stabilization," were used after initiation of the reactor trip. The auxiliary feedwater system started automatically, as expected, in response to steam generator level changes after the reactor trip. It was also noted that the "B" Main Feedwater Pump had tripped. The cause of the main feedwater pump trip has not been determined and is under investigation. The primary system and steam generator power operated relief valves and safety valves did not actuate during this event. The main feedwater system, main steam system, and condenser remained available during the event and are currently being used for decay heat removal. The normal post-trip electrical configuration is providing power to the required buses and the offsite electrical system is stable at this time. The emergency diesel generators are operable. The unit is currently stable in MODE 3. An estimated restart date has not yet been established.

"This report is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) for reactor protection system actuation and 10 CFR 50.72(b)(3)(iv)(A) for automatic actuation of the auxiliary feedwater system."

The licensee notified the NRC Resident Inspector.