Event Notification Report for June 14, 2002

MANUAL REACTOR TRIP FOLLOWING CLOSURE OF A FEEDWATER ISOLATION VALVE DURING SURVEILLANCE TESTING

The following text is a portion of a facsimile received from the licensee:

"At 04:35 [CDT] on 06/14/2002, operators manually tripped the reactor following closure of feedwater isolation valve 2C during surveillance testing. The cause of the feedwater isolation valve failure is unknown at this time. Also, both source range nuclear instruments failed to energize following the reactor trip, but both extended range nuclear instruments are available. The auxiliary feedwater system actuated as expected on steam generator low-low level."

"Did the rods fully insert? yes
Did steam bypass to the condenser or to atmosphere? condenser
Did any primary/secondary relief valves lift? no
Any electrical bus transfer problems? no
State normal operating temperature and pressure (NOT/NOP)[:] 590 degrees 2235 psig
Any significant TS LCOs entered? no"

The licensee stated that there was nothing unusual or misunderstood with the exception of the cause of the feedwater isolation valve failure and the cause of the failure of both source range nuclear instruments to energize following the reactor trip. All systems functioned as required with the same exceptions.

The licensee also stated that the unit is currently stable in Mode 3 (Hot Standby). Normal charging and letdown, pressurizer heaters and sprays, and the reactor coolant pumps are currently being utilized for primary system level, pressure, and transport control. Secondary steam is being dumped to the condenser, and auxiliary feedwater is supplying water to the steam generators. Operators are in the process of transferring from auxiliary feedwater to main feedwater. All engineered safety feature equipment and emergency core cooling systems are operable and available if needed.

The licensee notified the NRC resident inspector.

* * * UPDATE ON 6/14/02 @ 2243 BY REDDIX TO GOULD * * *

Licensee reported that after further investigation it was determined that both source range instruments did energize as expected, however, after indicating some counts erratically, they decayed away to zero. Both source range detectors are inoperable at this time.

The NRC Resident Inspector was notified.

Notified Reg 4 RDO(Gody)

REACTOR MANUALLY TRIPPED FROM 88% POWER DUE TO LOSS OF THE EAST MAIN FEED PUMP ON LOW CONDENSER VACUUM

At 1443 the unit one reactor was manually tripped from 88% reactor power due to the loss of the East Main Feedwater pump on low condenser vacuum. Loss of East Main Feedwater Pump Condenser Vacuum occurred during the start of #13 Main Circulating Water Pump. It is believed that this was caused by high differential pressure across the feed pump condenser and it appeared that the circulating water pump transferred some debris from the forebay into the condenser resulting in the loss of condenser vacuum, but this incident is still under investigation.

All rods fully inserted, no ECCS injection and no safety relief valves lifted.

Plant is currently stable in Mode 3. All plant equipment functioned as designed. Event Investigation is currently in progress.

The NRC Resident Inspector was notified.

LOSS OF A CHEMICAL AGENT DETECTOR DURING A FIELD TRAINING EXERCISE IN WIESBADEN, GERMANY

A chemical agent detector (model M43A1) was lost by an Army unit during a field training exercise in Wiesbaden, Germany. It was discovered to be missing at approximately 0200 on 06/07/02. The missing chemical agent detector contained 300 microcuries of americium-241. Aberdeen was notified of this incident via email at 0355 on 06/14/02.

(Call the NRC operations officer for a licensee contact telephone number.)