| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/18/2006 - 08/21/2006 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 42769 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: SVERDRUP CIVIL, INC
Region: 1
City: BOSTON State: MA
County:
License #: 48-0223
Agreement: Y
Docket:
NRC Notified By: MIKE WHALEN
HQ OPS Officer: BILL GOTT | Notification Date: 08/15/2006
Notification Time: 10:01 [ET]
Event Date: 08/07/2002
Event Time: [EDT]
Last Update Date: 08/15/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAYMOND LORSON (R1)
CINDY FLANNERY (NMSS)
| Event Text AGREEMENT STATE REPORT - NUCLEAR GAUGE DAMAGED BY FIRE
The State provided the following information regarding a previously unreported event via facsimile:
"A fire, which started in garage/storage facility, at a golf course construction site near the summit of a former city landfill was allowed to burn for two days by the local fire department. However, during the fire and immediately after the proximity of the device storage shed was disclosed by the licensee to the local authorities, the City of Quincy Fire Department summoned the Agency [MA Radiation Control Program] to the scene. At the scene the Agency representative was able to overview the situation, to take measurements and to advise the fire officials that the radiological device in the nearby stage shed was neither an immediate or imminent health or safety hazard. On the third day, the Agency representative [and] the licensee Radiation Safety Officer (RSO) were allowed by the Fire Chief to enter the separate device shed with instrumentation and to retrieve the device. The device was located with appropriate instrumentation, separated from the rubble and stored securely elsewhere on-site. Surveys were subsequently conducted to release the remains of the storage shed. The manufacturer of the device was engaged by the licensee to come to the job site to confirm recovery of both Cesium-137 and Am-241:Be sealed sources; to conduct appropriate leak testing and leak test analyses; and to package, mark and label the 55 gallon drum for shipment to the manufacturer's headquarters. Leak test results disclosed no apparent leakage of material from either sealed source. These sources were packaged on August 22, 2002, and the shipment was secured on-site in a vault pending completion of attendant paperwork, obtaining the certificate of compliance for the shipping container, and arranging for the transportation pickup of the hauler. Event closed by state." |
| General Information or Other | Event Number: 42770 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: NEN LIFE SCIENCE PRODUCTS
Region: 1
City: BOSTON State: MA
County:
License #: 00-3200
Agreement: Y
Docket:
NRC Notified By: MIKE WHALEN
HQ OPS Officer: BILL GOTT | Notification Date: 08/15/2006
Notification Time: 10:01 [ET]
Event Date: 06/04/2002
Event Time: [EDT]
Last Update Date: 08/15/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAYMOND LORSON (R1)
CINDY FLANNERY (NMSS)
| Event Text AGREEMENT STATE REPORT - DEFECTIVE PACKAGING OF RADIOACTIVE MATERIAL SHIPMENT
The State provided the following information regarding a previously unreported event via facsimile:
"On June 4, 2002, the surface and 1 meter radiation dose rates from a package containing 8 curies of phosphorus-32 (P-32) was found to be 1 R/hr at the surface and 4 milliR/hr at 1 meter. The package had a Yellow II label affixed which has a surface dose rate limit of 50 milliR/hr and a dose rate at 1 meter of 1 milliR/hr per Massachusetts regulation 120.775(A)(1). There was no removable contamination on the package hence the inner container appeared to be intact. However, the inner container appeared to be loose in the packaging rather than in the fixed geometry as evidenced in other similar packages in the same shipment.
"The package dose rate at the surface is greater than 0.2 R/hr but less than 0.01 R/hr at 1 meter hence the package exceeded the requirements of a Yellow III.
"In summary the defective packaging resulted in a radiation field at the surface of the package in excess of the limit for a common carrier and the Yellow II label on the package.
"The licensee has suspended all shipments from this supplier until the investigation of the package failure is complete.
"The root cause investigation of this event by the licensee has been postponed until September with the approval of the Massachusetts Radiation Control program pending decay of the radioactive material and adherence to the Perkin Elmer Life Sciences ALARA policy. A preliminary investigation concluded that persons handling the package during shipment would not have received a significant radiation dose because of the limited area of the package in excess of Yellow Il limits and the limited time of handling package by transportation personnel.
"UPDATE
"Excessive radiation field is due to seepage of radioactive material from cracked glass vial. There is a metal cap used to seal the vial. The metal cap is fastened using a hand operated crank. This tool can be mishandled resulting in over-tightening of the cap and causing the glass to crack. This vial, cap and tool are provided by Perkin Elmer and the firm is familiar with this potential failure mode. Root cause: improper training or supervision of operator of capping tool.
"Licensee informed vendor that supplies the glass vial and have discontinued using this vendor. This event is closed by the state" |
| General Information or Other | Event Number: 42772 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: LEVEL 1, INC
Region: 1
City: ROCKLAND State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MIKE WHALEN
HQ OPS Officer: BILL GOTT | Notification Date: 08/15/2006
Notification Time: 10:01 [ET]
Event Date: 12/15/2002
Event Time: [EDT]
Last Update Date: 08/15/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAYMOND LORSON (R1)
CINDY FLANNERY (NMSS)
ILTAB (Email) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST GENERAL LICENSED DEVICE
The State provided the following information regarding a previously unreported event via facsimile:
"By letter dated 1/28/03, Level 1, Inc. notified the Agency [MA Radiation Control Program] of the loss of a GL device.
"The device was an NRD air deionizer model number P-2021-0101, serial number 109646 which was shipped to the licensee on March 3, 1999. The device was used to de-ionize air during their clean-room assembly process. The device was taken out of service in March of 2002. When units are taken out of service the licensee stated that the devices are stored in a cabinet. The licensee discovered that the device was lost when they sent back all devices (30) in the program that were beyond their usefulness. They had 31 and could not account for one device when they were going to send the devices back. The device was discovered to be lost in December 2002. They have tried unsuccessfully to locate the device. They believe that it may still be in their facility and will continue to locate it.
"In order to prevent future losses, the licensee has implemented a Preventive Maintenance (PM) Program and have included all air deionizers as part of the PM program. The PM program will consist of a computer program that tracks all devices that are to be accounted for in the company for maintenance. The GL devices will be added to the list.
"The devices had 10 millicuries of Po-210 loaded in March of 1999. With the 138.38 day half life of Po-210, the device contains about 6 microCuries at this time. The safety significance is low for this lost device.
"Corrective action
"In order to prevent future losses, the licensee has implemented a Preventive Maintenance Program and have included all air deionizers as part of the PM program. The PM program will consist of a computer program that tracks all devices that are to be accounted for in the company for maintenance. The GL devices will be added to the list. EVENT CLOSED BY STATE."
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. |
| General Information or Other | Event Number: 42773 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: PERKINELMER LIFE SCIENCES
Region: 1
City: BOSTON State: MA
County:
License #: 00-3200
Agreement: Y
Docket:
NRC Notified By: MIKE WHALEN
HQ OPS Officer: BILL GOTT | Notification Date: 08/15/2006
Notification Time: 13:24 [ET]
Event Date: 01/30/2006
Event Time: [EDT]
Last Update Date: 08/15/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAYMOND LORSON (R1)
CINDY FLANNERY (NMSS)
ILTAB (email) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST SULFUR - 35 SHIPMENT
The State provided the following information regarding a previously unreported event via facsimile:
"S-35 (7 mCi) package was shipped via FedEx, from PerkinElmer in Boston, MA on 1/30/06.
"FedEx tracking indicates 1) the package was picked up from PerkinElmer in Boston, MA; 2) the package left the FedEx South Boston station; 3) the package arrived at FedEx Hub in Memphis, TN; 4) the package had an In-transit scan to Montreal on 1/31/06. There were no package scans after that.
"PerkinElmer Canadian Customer Service reported the customer did not receive the package. PerkinElmer asked FedEx several times to locate the package. PerkinElmer receiving department did not receive the package as a return and verified with the customer, again, that the package was not received. FedEx was unable to locate the package.
"PerkinElmer declared the package as lost on February 12, 2006, and reported to the Agency [MA Radiation Control Program] by phone on March 10, 2006. A written report was received to the Agency on April 10, 2006.
"Corrective action: PerkinElmer advised FedEx that all radioactive shipments require a Proof of Delivery; this issue has been escalated to FedEx Dangerous Goods Administrator; and a letter was sent to FedEx explaining the requirements of delivering radioactive packages."
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. |
| General Information or Other | Event Number: 42774 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: BRIGHAM & WOMEN'S HOSPITAL
Region: 1
City: BOSTON State: MA
County:
License #: 44-0004
Agreement: Y
Docket:
NRC Notified By: MIKE WHALEN
HQ OPS Officer: BILL GOTT | Notification Date: 08/15/2006
Notification Time: 13:24 [ET]
Event Date: 05/12/2003
Event Time: [EDT]
Last Update Date: 08/15/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAYMOND LORSON (R1)
CINDY FLANNERY (NMSS)
| Event Text AGREEMENT STATE REPORT - MEDICAL EVENT
The State provided the following information regarding a previously unreported event via facsimile:
"The Agency [MA Radiation Control Program] received a report on 6/23/03 of a misadministration; ie., The wrong area of the scalp was treated during a treatment for a superficial scalp cancer. The wrong area of the scalp was treated because of a malfunction with the source position simulator. The misadministration was not noticed during the treatment period of May 12, 2003, thru June 5, 2003. It was discovered on June 23, 2003 while doing a similar procedure. After the source position simulator malfunction was detected, all cases that used this same device were reviewed and it was determined that only the last patient treatment was affected by this malfunction. Corrective actions were implemented to ensure this event will not happen again.
"Corrective action
1. Licensee reviewed all cases that involved the same device and determined that the only patient affected by this malfunction was the last one treated before discovery.
2. All HDR treatments involving variable length catheters will have the length of the catheters measured by 2 independent means.
3. The HDR manufacturer was notified of the problem encountered with the catheter measuring device." |
| General Information or Other | Event Number: 42775 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: QSA GLOBAL, INC
Region: 1
City: BURLINGTON State: MA
County:
License #: 12-8361
Agreement: Y
Docket:
NRC Notified By: MIKE WHALEN
HQ OPS Officer: BILL GOTT | Notification Date: 08/15/2006
Notification Time: 14:33 [ET]
Event Date: 08/08/2006
Event Time: [EDT]
Last Update Date: 08/15/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAYMOND LORSON (R1)
BLAIR SPITZBERG (R4)
CINDY FLANNERY (NMSS)
| Event Text AGREEMENT STATE REPORT - SURFACE CONTAMINATION
The State provided the following information via email:
"Licensee received an 'empty' lead pod with exterior contamination of 1.3 E-5 microCi/cm2. Contamination identified as Cs-137. Shipment came from Thermo Electron, 1410 Gillingham Lane, Sugarland, Texas via Conway Trucking."
"Licensee informed Conway Trucking of the contamination." |
| General Information or Other | Event Number: 42780 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: NITRON CORPORATION
Region: 1
City: BILLERICA State: MA
County:
License #: 55-0238
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: BILL HUFFMAN | Notification Date: 08/16/2006
Notification Time: 09:58 [ET]
Event Date: 10/13/2004
Event Time: [EDT]
Last Update Date: 08/16/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAYMOND LORSON (R1)
CINDY FLANNERY (NMSS)
| Event Text MASSACHUSETTES AGREEMENT STATE REPORT OF LEAKING FE-55
The State provided the following information regarding a previously unreported event via facsimile:
"On October 15, 2004, Niton Corporation provided a report of a leaking sealed source that was discovered by Niton on October 13, 2004, during routine maintenance of a customer's model Xli 868p XRF device, S/N 5043. The sealed source is AEA Technology model IEC.A1, S/N 8765LG containing 10.3 mCi of Fe-55. The estimated leakage was 700,000 dpm or 0.3 microcuries.
"The source and a few contaminated device components were removed from the device and placed into a waste storage container. The area where the source removal was performed was surveyed and no contamination was found. The source manufacturer, AEA Technology, was notified of the leaking source. The source manufacturer, AEA Technology, has re-designed the source."
The cause and corrective action were determined and this event is considered closed by the Agency. |
| Power Reactor | Event Number: 42783 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JEFF YEAGER
HQ OPS Officer: MIKE RIPLEY | Notification Date: 08/18/2006
Notification Time: 01:00 [ET]
Event Date: 08/17/2006
Event Time: 19:00 [EDT]
Last Update Date: 08/18/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID HILLS (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMERGENCY DIESEL GENERATORS INOPERABLE DUE TO UNDERSIZED BREAKER CONTROL TRANSFORMERS
"At 1900 hrs on 8/17/06, all four Emergency Diesel Generators (EDGs) were declared INOPERABLE. The inoperability is a result of undersized control transformers for each of the Emergency Diesel Generator Service Water (DGSW) Pumps. The concern is that the DGSW pump contactors will not receive adequate voltage at the starters to ensure the starters pickup under degraded voltage conditions. A 2 hour Limiting Condition for Operability (LCO) was entered per LCO 3.8.1 to restore both EDGs in one division to OPERABLE status. At 2100 hours on 8/17/06 the two hour time requirement expired and a 12 hour LCO to place the plant in Mode 3 (Hot Shutdown) was entered.
"At 0042 hrs on 8/18/06, compensatory measures have been put in place to restore operability to both division 2 EDGs. The compensatory measures include placing the local control switch for both division 2 DGSW Pumps in run. Placing the local control switches in run ensures sufficient voltage will be available at the starters to ensure the starters pickup following a loss of offsite power, load shed, and restoration of power to the applicable busses. With operability restored to division 2 EDGs, the new expiration time for the LCO has been revised to 72 hours based on discovery of one or both EDGs in one division inoperable concurrent with CTG 11-1 [station blackout Combustion Turbine Generator 11-1] not available. After 72 hours, if operability is not restored to either CTG 11-1 or both division 1 EDGs, the plant will be required to enter Mode 3 within the following 12 hours.
"This report is being made pursuant to 10CFR50.72.(b)(3)(v) as an event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to (A) Shut down the reactor and maintain it in a safe shutdown condition; (B) Remove Residual Heat; (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident. The NRC resident inspector has been notified."
The licensee stated that the current 72 hour LCO will expire at 1900 EDT 08/20/06. |
| General Information or Other | Event Number: 42786 | Rep Org: DEFENSE DISTRIBUTION CENTER
Licensee: DEFENSE DISTRIBUTION CENTER
Region: 1
City: NEW CANTERBURY State: PA
County:
License #: 37-30062-01
Agreement: N
Docket:
NRC Notified By: DAVID COLLINS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/18/2006
Notification Time: 15:25 [ET]
Event Date: 08/18/2006
Event Time: 14:00 [EDT]
Last Update Date: 08/18/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
RAYMOND LORSON (R1)
GREG MORELL (NMSS)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text TRITIUM SOURCES MISSING DURING ANNUAL INVENTORY
An inventory of the tritium sources at the Defense Logistics Agency in Aniston, AL was performed.
"Initial results of Annual Inventory indicates a loss of the following items:
4 ea NSN 1240001508886 Telescopic panoramic at 3.8 Curies each
5 ea NSN 1240001508890 Mount Telescope at 0.15 Curies each
2 ea NSN 1240003321780 Collimator at 10 Curies each
Causative research is currently being conducted and results will be reported in follow up letter to NRC. Total loss would equal 35.95 Curies of H3."
The last annual inventory was completed 10/11/2005.
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: 42787 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MATHEW RASMUSSEN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/19/2006
Notification Time: 15:15 [ET]
Event Date: 08/19/2006
Event Time: 11:05 [CDT]
Last Update Date: 08/19/2006 | 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):
MARK LESSER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM Of UNIT 3 DUE TO THE LOSS OF BOTH REACTOR RECIRCULATION PUMPS
"At 1105 CST both Reactor Recirculation pumps tripped on Unit 3. In accordance with procedure 3-AOI-68-1, a manual scram was initiated. Reactor water level lowered to Reactor Pressure Vessel Level 3, resulting in the automatic actuation of the Primary Containment Isolation System as expected: Group 2 (RHR Shutdown Cooling), Group 3 (Reactor Water (Clean Up), Group 6 (Ventilation), and Group 8 (Traversing Incore Probe) along with the automatic start of Control Room Emergency Ventilation and all 3 trains of the Standby Gas Treatment System. Reactor water level was recovered to normal levels with the reactor feedwater system.
"During this time Unit 2 was at 100% power and was unaffected by the event.
"This event is reportable as a 4-hour and 8-hour notification along with a 60-day written report in accordance with 10 CFR 50.72(b)(2)(iv)(B), 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.73(a)(2)(iv)(A)."
All control rods fully inserted on the scram. Decay heat is being removed with normal feedwater and the turbine bypass valves. No relief valves lifted during this event. Electrical power to the plant is aligned for the normal shutdown lineup. The cause of this event is under investigation.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42788 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: BART BLAKESLEY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/19/2006
Notification Time: 23:10 [ET]
Event Date: 08/19/2006
Event Time: 18:49 [CDT]
Last Update Date: 08/19/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
DAVID HILLS (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text RADIATION MONITOR ELECTRICAL SPIKE CAUSES SECONDARY CONTAINMENT ISOLATION
"The 'B' fuel pool radiation monitor spiked high causing an actuation of the secondary containment relays. 'A' SBGTS [Standby Gas Treatment System] train started, reactor building, turbine building, and rad waste building ventilation isolated. The Drywell Continuous Air Monitor (DW CAM) and O2 analyzer containment valves isolated. The control room ventilation system transferred to the high radiation mode.
"At the time of the occurrence the 'A' Fuel Pool radiation monitor was reading normal (0.5 mr/hr). The 'B' Fuel Pool radiation monitor was reading 80 mr/hr. The 'B Fuel Pool radiation monitor, soon after lowered to 30-40 mr/hr and then back to normal (10 mr/hr). The trip setpoint is 50 mr/hr. The trip was reset. The secondary containment isolation and all ventilation trips were restored to normal. The DW CAM and control room ventilation were restored to normal. A local survey was performed on the refuel floor, readings obtained were < 5 mr/hr at the detector and < 2 mr/hr in surrounding areas. The 'B' fuel pool radiation monitor high level trips were placed in the trip/bypass position. The 'B' fuel pool radiation monitor was placed in downscale trip condition to comply with Technical Specification Table 3.2.4. A team is being established to investigate the cause of the trip."
The licensee notified the NRC Resident Inspector. |
| Other Nuclear Material | Event Number: 42789 | Rep Org: SUPERIOR WELL SERVICES, INC.
Licensee: SUPERIOR WELL SERVICES, INC.
Region: 1
City: INDIANA State: PA
County:
License #: GL704677-7
Agreement: N
Docket:
NRC Notified By: JOHN SROCK
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/20/2006
Notification Time: 18:30 [ET]
Event Date: 08/18/2006
Event Time: [EDT]
Last Update Date: 08/20/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
RAYMOND LORSON (R1)
BLAIR SPITZBERG (R4)
GARY JANOSKO (NMSS)
ILTAB (via email) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text GENERAL LICENSE DENSITY GAUGE DISCOVERED MISSING
On 8/18/06 the Superior Well Services crew at a temporary worksite approximately 2 hours drive from Vernal, UT discovered that their Thermo MeasureTech Density Gauge was missing. The device, a Model #5192 - S/N B7000 containing a 200 mCi Cs-137 source, is normally stored in the back of their vehicle and was last used the day before on 8/17/06. The licensee is continuing their investigation to determine whether the device was stolen or fell off the back of the vehicle. The device itself weighs 150 pounds and is in a metal housing 36 inches in length (Sealed Source Registry No. TX0634D105B).
The licensee contacted the Utah Highway Patrol, the Vernal County Sheriff's Office and will contact the Utah Radiation Control Office. Also, a press release offering a $10,000.00 reward for return of the device will be issued.
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. | |