Event Notification Report for January 24, 2008

AGREEMENT STATE REPORT - WRONG ISOTOPE ADMINISTERED

"On January 14, [2008], a physician gave a verbal order for a I-123 [Iodine-123] uptake scan. But instead, the patient was given a I-131 uptake scan. On January 16, the physician reviewed the results and realized the wrong isotope had been used. The patient has been notified. No adverse health effects are expected. Florida is investigating."

The amount of I-131 delivered to the patient was 4.7 milliCuries.

This event was assigned Incident Number FL08-012 by the State of Florida.

A 'medical event' indicates potential problems in a medical facility's use of radioactive materials. It does not result in harm to the patient.

CONFIRMED POSITIVE FITNESS FOR DUTY TEST ON A CONTRACT SUPERVISOR

A non-licensed contract employee supervisor had a confirmed positive for illegal drugs during a fitness-for-duty test. The employee's access to the plant has been suspended. Contact the Headquarters Operations Officer for additional details.

MANUAL REACTOR TRIP DUE TO FAILURE OF THE "C" FEEDWATER FLOW CONTROL VALVE

"At 1604 [EST], VC Summer Nuclear Station was manually tripped due to rapidly decreasing level in 'C' Steam Generator. The decreasing Steam Generator level was due to a failure of the 'C' Feedwater Flow Control Valve. All systems responded as required. All Emergency Feedwater Pumps automatically started on Lo-Lo Steam Generator level. The Steam Generator levels recovered quickly. The Pressurizer Level Control System cycling resulted in lifting the Letdown System Relief Valve due to high temperature and pressure. The Letdown Relief Valve reseated with no further problems. One Moisture Separator Reheater Relief Valve lifted momentarily and reseated.

"Presently, the plant is in Mode 3 with normal RCS pressure and temperature. Decay heat is being removed by dumping steam to the condenser. The plant will remain in Mode 3 until repairs are completed on the 'C' Feedwater Flow Control Valve."

During the trip, all control rods fully inserted into the core. The electrical grid is stable and emergency power is being supplied from offsite via the station start-up transformer. There is no known primary to secondary leakage.

The licensee has notified the NRC Resident Inspector and will be notifying State and local agencies.

60 DAY REPORT - INVALID ACTUATION OF THE NUCLEAR SERVICE WATER SYSTEM

"This 60-day optional report as allowed by 10 CFR 50.73(a)(1), is being made under the reporting requirement in 10 CFR 50.73 (a)(2)(iv)(A) to describe an invalid actuation of a specified system, specifically the Nuclear Service Water System (NSWS).

"While performing changeout of a Nuclear Service Water (RN) current module, there was an unexpected auto swap from the normal heat sink (Lake Wylie) to the ultimate heat sink {Standby Nuclear Service Water Pond (SNSWP)} occurred and the system responded as designed. Work was stopped when notified by Operations.

"This event occurred when technicians attempted to isolate power to the module prior to replacing. Unable to do so, they decided to perform a changeout under hot conditions. While tracing power utilizing wire tabs, the technicians did not identify that removing wire from terminal 12 of the module disturbs the power path to other channels. The channel associated with the bad module remained in the trip condition throughout, and when power to other channels was disturbed, the logic for a swap from the normal heat sink to the ultimate heat sink was completed and the automatic swap occurred as designed. This event was entered into the site corrective action program for evaluation."

The licensee will inform local and state agencies and has informed the NRC Resident Inspector.