Event Notification Report for February 16, 2005

CPN NUCLEAR GAUGE STOLEN FROM THE JOBSITE

An employee of the ALCO Corporation was working at a jobsite on Highway PR837 in Guaynabo, Puerto Rico with a CPN nuclear gauge. About 14:55 on 2/16/05 he had walked 40 feet away from the nuclear gauge and when he returned to the area he noticed the gauge missing. The gauge contain two sources, 50 millicuries Am-241and 10 millicuries of Cs-137. A police report was being taken and that information will be provided as a later update.

No reward for the return of the gauge is being offered at this time.

* * * UPDATE ON 02/17/05 AT 0742 FROM DAVID RHOE TO GERRY WAIG * * *

The following information was received via facsimile from Mr. Rhoe:

"RE: Stolen CPN Nuclear Gauge [Serial number] MD20801021

"On February 16, 2005 the above nuclear gauge was stolen from a [deleted] vehicle. The nuclear gauge was located inside the carrying case and the case was secured by chains/padlock to the vehicle. The chain was cut and the nuclear gauge/case/chains were removed. Mr. [deleted] was inspecting the asphalt and the vehicle was temporarily out of sight due to the blind spots around the corner of the road. The handle of the nuclear gauge inside the case was not locked. The incident occurred between 3:30 to 4:00 pm on RP 837 in Guaynabo at the Barrio Camarones site. The police and NRC were immediately notified. The police report number is 05-7-132-02011.

"The following media stations were notified:
Channel 2 WKAQ TV
Channel 4 WAPA TV
University of Puerto Rico TV

"Today the radio stations and newspaper will be notified. There will be a reward offered for the return of the gauge."

Notified TAS DO, R1DO (Eugene Cobey), NMSS (Sandra Wastler)

DEGRADED CONDITION - REACTOR BUILDING NORMAL SUMP LEVEL INCREASING

The licensee provided the following information via facsimile:

"Event:
"On February 16, 2005 at 1331 hours EST, Operations discovered that the Oconee Unit 3 Reactor Building Normal Sump (RBNS) level was increasing. Chemistry sampled the containment normal sump to determine the water source and could not conclusively rule out Low Pressure Service Water (LPSW). The leak rate into the sump is approximately 1.9 gpm. LPSW is the cooling medium used for the Reactor Cooling Pump (RCP) motor coolers, the Reactor Building Cooling Units (RBCU), and the Reactor Building Auxiliary Cooling Units (RBACU).

"Unit 3 entered Technical Specification 3.6.1.A at 1331. This requires restoring containment to Operable status within 1 hour. The approximately 1.9 gpm leakage is above the leakage allowed in calculation OSC-7005 "LPSW Allowable Leakage Inside Containment". At 1431 Unit 3 entered Technical Specification 3.6.1 B which requires being in mode 3 in 12 hours.

"Initial Safety Significance:
"By limiting the amount of LPSW leakage inside containment then containment operability is ensured. Above the calculated LPSW leakage as stated in OSC-7005, containment operability is in question. The LPSW system pressure could be less than containment LOCA peak pressure. Therefore containment atmosphere has the potential to leak through the LPSW system, during a LOCA, and out the return line resulting in a containment leak path.

"Collective Action(s):
"Additional sampling and process indications suggest that the cause of the Reactor Building Normal Sump rate increase is feedwater or main steam. A power reduction to 18% has been completed and a reactor building entry is in progress to confirm the source of the leakage. If the source is confirmed to be feedwater or main steam, Technical Specification 3.6.1 will be exited."

The turbine is still loaded and the electrical grid was not affected by the power decrease to 18%. All systems functioned as required and other units at Oconee were not affected by this event.

NRC Resident Inspector was notified.


* * * UPDATE ON 2/17/05 @ 0018 BY JOHN COLLINS TO CHAUNCEY GOULD * * * UPDATE

They entered the containment and verified a steam leak off the impulse line for the "3B" steam generator main steam pressure transmitters. They are currently at 18% power and making a decisions on repair options.

The NRC Resident Inspector will be informed. The Reg 2 RDO(Bernhard) was notified.


* * * UPDATE ON 2/17/05 @ 0139 BY JOHN COLLINS TO CHAUNCEY GOULD * * * RETRACTION

At 0012 on February 17, 2005 entry into the Unit 3 reactor building confirmed that the source of leakage into the reactor building normal sump was the Main Steam system. Specifically, the location of the leak appears to be a fitting downstream of an instrument root valve off the 3B Main Steam line. Based on this information, Technical Specification 3.6.1 was exited and this event is not reportable per 10CFR50.72. and therefore being retracted.

A shutdown to MODE 3 will be conducted to facilitate repairing the leak.

The NRC Resident Inspector will be informed. Reg 2 RDO(Bernhard) was notified.

REACTOR TRIP DUE TO TURBINE TRIP AS A RESULT OF FAILED POWER SUPPLY

"Ginna Station received a reactor trip from Turbine Trip at 2112 hrs on 02/16/05. The Turbine Trip signal was generated from the ATWS Mitigation System Actuation Circuitry (AMSAC) related to a failed power supply in the Advanced Digital Feedwater Control System. All control rods inserted on the reactor trip. The plant is currently stable in Mode 3, RCS Pressure 2235 psig, Temperature 540 deg F. AFW [Auxiliary Feed Water] did actuate as designed after the trip.

"For the transient, min & max Temperatures, Pressures & Levels are:
RCS Temperature: Max - 561 deg F Min - 538 deg F
RCS Pressure: Max - 2250 psig Min - 2218 psig
Pressurizer Level: Max - 50% Min - 28%"

The electrical grid is stable. Decay heat is being rejected to the Main Condenser. The licensee notified the NRC Resident Inspector and the State Public Service Commission.

AGREEMENT STATE MEDICAL EVENT

The following information was provided by the State of Wisconsin via facsimile:

"On Thursday, February 17, 2005 at approximately 3:45p.m. [CST], the Wisconsin Radiation Protection Section (RPS) received a telephone call from the Marshfield Clinic, Marshfield, WI (license number 141-01162-001) informing the section of a medical event involving a therapeutic radiation dose from a gamma knife exposing a site outside the intended treatment volume to a level greater than 50% of the expected dose. (HFS 157.72 (1) (a) 3.)

"Preliminary Information From the Licensee:

"On Wednesday, February 16, 2005, the Marshfield Clinic had scheduled a therapeutic radiation treatment of 18 Gray (1800 Rads) using a gamma knife. During the process of manually programming the positioning system, the y and z coordinates were transposed. The error was not noticed during a double check of the treatment coordinates. As a result, a site outside the intended treatment volume received an estimated dose of 5.06 Gray (506 Rads) instead of the originally estimated 0.4 Gray (40 Rads). The volume of the unintended treatment site was 0.7 cubic centimeters. The treatment duration was 2.42 minutes. The prescribed dose of 18 Gray was delivered and the patient treatment was completed.

"The attending neurosurgeon and radiation oncologist believe there will be no medical consequences to the patient from the unintended exposure. The referring physician has been notified.

"[State of Wisconsin] is reporting this event under:

"HFS 157.72 (1) (a) 3. requires a licensee to report an event where there is 'A dose to an organ outside the intended treatment volume that exceeds the expected dose to that organ by 0.5 Sv (50 Rem) where the excess dose is greater than 50% of the expected dose to that organ. . . '

"DHFS, RPS staff have been dispatched on Friday, February 18, 2005 to investigate.

"Wisconsin Incident No: 20"