Event Notification Report for November 07, 2001

AUTOMATIC REACTOR SCRAM

Reactor power level was at 8% after coming out of a refueling outage when a 1/2 scram signal was received. Approximately 2 minutes after receiving the 1/2 scram signal, while investigating the cause of the 1/2 scram signal, another 1/2 scram signal was received which initiated a fully reactor scram from 8% reactor power. All rods fully inserted into the core. The initial shrink of reactor vessel water level from plus 30 inches to plus 10 inches was due to the reactor scram. Group 2, drywell isolation valves, and Group 3, reactor water cleanup, isolations were caused by reactor vessel water level decreasing. Main Steam Isolation Valves were closed to maintain control of reactor vessel pressure, very little decay heat in the core. Reactor pressure is currently 562psi and reactor feed pumps are maintaining proper reactor vessel water level. All emergency core cooling systems are fully operable if needed. The emergency diesel generators are fully operable if needed and the electrical grid is stable. The licensee at this time does not know what signal initiated the 1/2 scram signals. Investigation is in progress.

The NRC Resident Inspector will be notified by the licensee of this event.

NOTIFICATION OF THE RECOVERY OF A DEAD GREEN TURTLE FROM THE PLANT'S INTAKE CANAL

A dead green turtle was recovered from the plants intake canal where it apparently drowned near the 5" barrier net. The licensee notified the Florida Department of Environmental Protection as required by the plant's sea turtle permit.

The NRC Resident Inspector was notified.

THE STATE OF ILLINOIS REPORTED A SOURCE BEING FOUND AT A SCRAPYARD

The source of the elevated readings was traced to a metallic right circular cylinder, approximately 1 inch long and 1/8 inch in diameter. There were no visible markings, color codings, or other identifications on this object. Measured exposure rates were 110 mR/hour at 3" and 13 mR/hour at 12". The object was placed into the finger of a nitrile glove and further surveys were performed. Mr. Labkon's(the individual who recovered the scrap metal) hands and gloves were surveyed and were found to be free of contamination. The Styrofoam cup which had held the source and the storage room were also surveyed and found to be free of contamination.

A gamma spectrum was obtained using the Microspec-2 portable multichannel analyzer, serial number 94006. The spectrum showed no discernible photopeak. Spectral data are included with this report.

The source/nitrile glove finger were placed into a Syncor threaded pig. The exposure rate at near contact with the pig was measured at 25 µRem/hour.

Based on the data available, this source would be either a strong beta emitter, or a very low energy gamma emitter, such as 241-Am. In order to determine whether this source may have been manufactured as a neutron source, a neutron measurement was performed on November 1, 2001. Using a Health Physics Instruments Model REM 500 neutron meter, serial number 00203, and taking a standard one minute count for each determination, the following readings were obtained:











Configuration Reading (mRem/hour) Reading(neutrons/minute)

Background 0.000 0


4" from
unshielded
source 3.21 330


at near contact
with the stainless
steel shield with
the source inside 0.448 2

Based on the available data, considering the possibilities of an 241-Am-Be source, a 239-Pu-Be source, or a 226-Ra-Be source, the most likely possibility is an 241-Am-Be source, with a calculated activity of 4 mCi.

The source was returned to a safe shielded position and locked within their source storage room. Pending satisfactory disposal of this source, this matter may be considered closed.

HEAD LOSS CHARACTERISTICS OF CHECK VALVES GREATER THAN PREVIOUSLY ASSUMED.

On November 7, 2001, at approximately 1414 hours, with the plant in mode 5 (cold shutdown), evaluation of preliminary results from mock-up testing of containment sump check valves determined that the head loss characteristics of the check valves are greater than previously assumed by calculations that support the safety analyses. The result of increased head loss through the containment sump check valves is reduced available net positive suction head (NPSH) for the safety injection and containment spray pumps during recirculation mode following a loss of coolant accident (LOCA). The reduced available NPSH may have effected the ability of the pumps to satisfy their required design safety function during previous periods of plant operation. Recirculation mode operation of these pumps is required by Technical Specifications in Mode 3 (hot standby) and above. Therefore, this condition has no adverse implications for the present plant condition at Mode 5. Evaluation of test results is continuing.

The NRC Resident Inspector was notified of this event by the licensee.

* * * RETRACTED AT 1450 EST ON 03/04/02 BY DAN MALONE TO GERRY WAIG* * *

"Subsequent evaluation of the past operability of the pumps with the reduced NPSH condition was concluded that the pumps were nonconforming but operable. This conclusion was reached by crediting containment overpressure and actual plant parameters, which increase available NPSH above that required for all pumps considering the most limiting postulated conditions.

"Since a determination of nonconforming but operable was reached for past operating conditions, there was no loss of a required safety function and no significant impact on plant safety this condition was originally discovered and reported with the plant in Mode 5; and was corrected prior to plant restart by modifying plant equipment and procedures without further reliance on crediting containment overpressure."

Licensee notified the NRC Resident Inspector. Notified R3DO (John Madera).

AGREEMENT STATE REPORT

"A truck caught fire and burned. A S.P.E.C. camera, serial # 98, source serial # HS1210 containing Ir-192 was on board. The source remained intact and was not leaking. The device and source were returned to the manufacturer.

"We have no additional information. We have contacted the Licensee to obtain more details."

Texas Incident No.: I-7848