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Event Notification Report for February 15, 2007

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
02/14/2007 - 02/15/2007

EVENT NUMBERS
431674316843169

General Information or Other
Event Number: 43167
Rep Org: MAINE DEPARTMENT OF RADIATION CONTR
Licensee: SAPPI
Region: 1
City: SAWHEGAN   State: ME
County:
License #: 25709
Agreement: Y
Docket:
NRC Notified By: SHAWN SEALY
HQ OPS Officer: JASON KOZAL
Notification Date: 02/15/2007
Notification Time: 11:41 [ET]
Event Date: 02/15/2007
Event Time: 00:00 [EST]
Last Update Date: 02/15/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
JOHN WHITE (R1)
MICHELE BURGESS (FSME)
Event Text
AGREEMENT STATE REPORT - LEAKING SOURCE

The following was provided by the state via facsimile:

"On January 30, 2007 it came to [the licensee's] attention that a radioactive source on Paper Machine #3 is leaking. This source is listed on [the] Materials license (25709) under condition 9 : "Sealed Krypton 85 (85 Kr) sources ". The source is an ABB Industrial Systems Model TG-4, 1 Ci, s/n K-1331-R.

"The source is used as part of a scanning system on the paper machine. It is in a location not readily accessible to employees working in the area. Radiation levels at one foot around the source head are 0.1 mR/hour. The gas is leaking very slowly, as evidenced by a decrease over time in the process variable that it measures. The source has been labeled well with caution tape and a barricade tag is affixed to the tape.

"The plan for remediation is as follows:

" - A replacement source (loaner from ABB) is being shipped (2/1/07) and should arrive by overnight delivery (2/2/07). Upon arrival, [the] shipping department has been instructed to secure the new unit in a designated holding area for radioactive sources. The storage location is a heavy metal cabinet which is locked with a padlock to ensure the safety of the unit and of the workers. The cabinet is in an area not readily accessible to employees, in a building away from production areas.

" - The damaged source will stay in place in its frame on the paper machine until early next week when a specialist from ABB will arrive, repackage it and ship it back to ABB. The replacement source will be installed at that time.

" - A new source is in the process of being purchased. Delivery is expected in 8-12 weeks. At that time, [the state's] department will be notified there is a new source onsite."

ME report number: ME070002


Other Nuclear Material
Event Number: 43168
Rep Org: MCCALLUM TESTING LABORATORY
Licensee: MCCALLUM TESTING LABORATORY
Region: 1
City: CHESAPEAKE   State: VA
County:
License #: 45-15325-01
Agreement: N
Docket:
NRC Notified By: PHIL BERMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 02/15/2007
Notification Time: 14:17 [ET]
Event Date: 02/15/2007
Event Time: 13:50 [EST]
Last Update Date: 06/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
JOHN WHITE (R1)
MICHELE BURGESS (NMSS)
ILTAB (e-mail)
Event Text
LOST TROXLER MOISTURE DENSITY GAUGE

A Troxler Moisture Density Gauge (model 3411, serial number 6957) was lost at a traffic intersection in Chesapeake, VA. The location of the intersection is at Route 17 and George Washington Parkway. The licensee called local police. The radiation safety officer (RSO) is responding to the site to see if the gauge can be found or if any damage to instrument exists.

* * * UPDATE AT 1447 ON 2/15/07 FROM P. BERMAN TO P. SNYDER * * *

The licensee reports that the gauge has been found and taken to the local fire department. The RSO is going to the location to examine the gauge for damage.


* * * UPDATE AT 1147 EDT ON 6/27/07 FROM BERMAN TO HUFFMAN * * *

When the RSO arrived at the fire department on 2/15/07, the gauge was determined to be damaged upon examination. Inspection revealed that the source rod was missing. The pickup truck driven by the city worker that found the gauge was still at the fire department. The truck was examined and the source rod was located loose in the bed of the truck. The RSO picked up the source rod and placed it back into the gauge. The source rod apparently fell out of the gauge while it was being transported to the fire department and was not handled by the individual who found the gauge. The extremity and whole body exposure for the RSO that handled the source rod is estimated to be less than annual limits. Subsequent leak testing of the source rod showed no compromise of the source. R1DO (Powell) and FSME EO (Hackett) notified.


THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.


Power Reactor
Event Number: 43169
Facility: OCONEE
Region: 2     State: SC
Unit: [1] [2] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: ROB MEIXELL
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/15/2007
Notification Time: 19:00 [ET]
Event Date: 02/15/2007
Event Time: 16:54 [EST]
Last Update Date: 02/15/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
PAUL FREDRICKSON (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby
2 A/R Y 100 Power Operation 0 Hot Standby
Event Text
UNIT 1 AND UNIT 2 REACTOR TRIP

"At 1654 EST on 2-15-07, Oconee Units 1 & 2 tripped from 100% power. The cause of the trips is under investigation. Unit 1 experienced a partial loss of 4160 volt power [Non-Safety Related] which resulted in a loss of Main Feedwater. Emergency Feedwater started on Unit 1. Unit 2 remained on Main Feedwater. Reactor Coolant Pump power was not affected by the trip on either Unit. Post trip equipment response on Unit 2 was normal. On Unit 1, a second HPI pump auto-started due to a non-safety low seal flow signal [one normally running for normal RCS makeup].

"Units 1 & 2 have been stabilized in Mode 3. Restoration of 4160 volt loads on Unit 1 is in progress."

All Control rods fully inserted on both units. No PORVs or Safety valves lifted during the event for either unit. Both units are removing decay heat by steaming to the Main Condenser via the Turbine Bypass valves. Both units are in a normal shutdown electrical lineup. Unit 3 was not affected by this event.


The licensee notified the NRC Resident Inspector.