Event Notification Report for November 10, 1999

- S/G LEVEL DROPPED TO REACTOR TRIP/AFW AUTO START SETPOINT DURING MAINTENANCE -

At 2220 CST on 11/10/99 with Unit 2 in Mode 5 (Cold Shutdown), priming of the feedwater isolation valves to support maintenance activities was in progress. While priming the 'B' steam generator (S/G) feedwater isolation valve #2FW009B, the valve was opened and water back-flowed from the 'B' S/G into the feedwater piping and the S/G level decreased to the low level 2 reactor trip setpoint of 36.3% which is also the setpoint for the autostart of the auxiliary feedwater (AFW) system. The initial level in the 'B' S/G was 50%. A reactor protection system actuation and engineered safety features actuation occurred and all plant systems responded normally for Mode 5. The reactor trip breakers opened but the control rod drive system was out of service and not capable of control rod withdrawal. The AFW auxiliary lube oil pumps auto started but the AFW pumps were in pull-to-lock due to current plant conditions so the AFW pumps did not start. The cause of the level decrease is due to unfilled feedwater piping following outage restoration. Corrective action is being determined. This event is reportable under the requirements of 10CFR50.72(b)(2)(ii).

The licensee notified the NRC Resident Inspector.

- TWO EMPTY BEER CANS FOUND IN A TRAILER INSIDE THE PLANT PROTECTED AREA -

Plant janitors found two empty beer cans in a shower trailer in a maintenance workers area inside the plant protected area. The licensee is interviewing the janitors and searched the trailer for additional cans; none were found. The licensee sent the cans to the local police for possible identification of fingerprints; results are pending. The licensee searched the hand held items of people exiting the plant protected area; nothing unusual was found. The licensee notified the NRC Resident Inspector and is continuing to investigate this incident.

4 HOUR BULLETIN 91-01 REPORT

On November 11, 1999 at 1020, the Nuclear Criticality Safety (NCS) staff determined that a Nuclear Criticality Safely Approval (NCSA) for X-705 was deficient. The compressor turnover pit located in the equipment disassembly north tear down area, has a sump pump which activates if solution should accumulate above 2.3 inches. NCSA-0705_031.AOO analyzed the turnover pit, assuming a maximum enrichment of 3%. The Nuclear Criticality Safety Evaluation (NCSE) for this operation failed to consider the contingency that the Geometrically Safe Storage (GSS) located overhead, which was analyzed at 100% enrichment, could leak into the compressor turnover pit.

The licensee notified the NRC resident inspector.

AGREEMENT STATE REPORT - STOLEN MOISTURE/DENSITY GAUGE

The state of Louisiana reported that a Campbell moisture/density gauge, model MC3, serial number 6368, was stolen on 11/10/99. The gauge was reported missing at 0700 CST on 11/10/99. The gauge contains 10 mCi of Cs-137 and a 50 mCi AmBe source. The gauge was stolen from the back of a truck at the offices of Moore & Associates. The lock on the gauge had been cut. The theft was reported to the local and state police departments.

FITNESS FOR DUTY REPORT

A supervisory contract employee was found to have used two illegal drugs during a random drug screening.
The NRC resident inspector has been notified.

SECURITY REPORT

UNESCORTED ACCESS GRANTED INAPPROPRIATELY. IMMEDIATE CORRECTIVE ACTIONS TAKEN UPON DISCOVERY. THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. SEE THE HOO LOG FOR ADDITIONAL DETAILS.

* * * RETRACTED AT 1655 EST ON 12/2/1999 BY CHARLES ELBERFELT TO FANGIE JONES * * *

Upon further investigation a determination was made that access was not granted inappropriately, thus the licensee is retracting this event. The licensee informed the NRC Resident Inspector and the NRC Headquarters Operations Officer informed the R2DO (Kenneth Barr).

INTERGRANULAR STRESS CORROSION CRACKING IDENTIFIED ON RECIRCULATION RISER WELD

While performing ultrasonic examination of recirculation riser weld #RRF-F002, nozzle to safe end weld, indications of Intergranular Stress Corrosion Cracking (IGSCC) were identified. Specifically, a 0.3 inch X 13 inch long crack on the nozzle to safe end weld. This nozzle was being inspected as part of an expanded inspection scope as a result of similar indications found on the 'B' recirc riser to safe end weld. To date, indications have been found on the 'B', 'D', and 'F' nozzles with no indications on the 'A' and 'C' nozzles. The 'E', 'G' and 'H' inspections have not been completed.

The licensee notified the NRC resident inspector.

See events #36402 and #36416.