Semantic search
| Entered date | Event description | |
|---|---|---|
| ENS 52111 | 20 July 2016 15:48:00 | The following report was received via e-mail: On Monday, July 18, Manufacturing Sciences Corp. (MSC) shipped five pallets (18 drums) of product containing depleted uranium oxide (DU) to a customer, Clariant, in Louisville, KY. On Wednesday, July 20, the customer contacted MSC to report only four pallets containing 14 drums were received by Clariant. When the bill of lading was examined by the customer, 5 and 18 had been marked through by hand and changed to 4 and 14. The carrier, was contacted and is conducting a thorough search of its terminal and investigating to locate the missing material. The carrier is routinely used by MSC for transport of product. Total activity of missing material: 271,285 microcuries DU. Tennessee Report: TN-16-100 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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| ENS 48422 | 19 October 2012 15:51:00 | The following information was received by facsimile: DRH (Tennessee Division of Radiological Health) was notified on 10/19/12 by the licensee that preliminary analytical results of a 30-gallon waste container of tritium contaminated waste oil and absorbents indicate approximately 8,600 curies of tritium. The container was manifested by the generator (SRS) (Savannah River Site) as containing 14.9 curies. Post sampling of this container, DSSI (Diversified Scientific Services, Inc.) had a controlled but elevated level of tritium contamination in the process room; this room is under negative ventilation. The room has been decontaminated back to normal processing levels. Contents of the container have been overpacked and placed in a safe state, (and) not a source of tritium contamination to the air or surface. Tennessee Event: TN-12-267 |
| ENS 47702 | 28 February 2012 13:09:00 | The following was received from the State of Tennessee via facsimile: On 10/19/10, it was discovered that the source carrier on Ohmart gauge, Model SHLM-C, could not retract from the well pipe back into the source holder. An Ohmart technician attempted to repair the gauge without success. A visual inspection confirmed that the process materials had leaked into the well pipe around the source carrier preventing retraction of the source. A remediation team was called to retrieve the source carrier. The gauge contained Cesium-137, two sealed sources of 63 milliCuries each. Event Report ID No.: TN-10-143 |
| ENS 45579 | 17 December 2009 10:59:00 | The following report was received via facsimile: (Tennessee Division of Radiological Health) TN DRH was notified on 12/15/09, by the medical physicist at Cookeville Regional Medical Center, of a possible therapeutic misadministration that occurred the morning of 12/15. A patient was being treated with three sealed sources of cesium-137 (total activity of 70 mg Ra-equivalent) contained in a vaginal applicator. The patient was elderly and heavily sedated. The applicator was inserted and after twenty minutes of treatment, the nurse came into the room to check on the patient and noticed the applicator outside the treatment area. The applicator was removed and placed in a lead pig. The patient may have received a maximum dose of 76 Rem to the thigh area. A written report will be submitted by the licensee. Tennessee Report Number: TN-09-155 A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| ENS 47703 | 28 February 2012 13:09:00 | The following was received from the State of Tennessee via facsimile: A pharmacy technician noted that the exhaust fan connected to the I-131 glove box was not working. Maintenance was contacted and found a broken fan belt which was repaired the same day. Up to 35% of the air exhaust of the I-131 vapor was not available for dilution. On 8/28/09, it was noted the effluent concentration of I-131 was over the limit of state regulations. It was immediately reported to the Radiation Safety Officer. An investigation revealed a bolus of I-131 was released through the ventilation system. Minor release in the room but the continuous air concentration in the pharmacist's breathing zone remained under regulatory limits. Surveys of the room revealed three locations of fixed contamination which were covered with cardboard and allowed to decay to background. All staff bioassays were below detectable limits. Event Report ID No.: TN-09-110 |
| ENS 43915 | 18 January 2008 10:32:00 | The following information was provided via fax: Duratek called DRH at approx. 1430 EST Jan. 17, 2008 to report a contamination event which required control of an area of their building for greater than 24 hours. While unpackaging a sealed source that was sent to them for processing for disposal, the container which the source was in was found to be contaminated. An area of about 10' by 10', covered with herculite, was contaminated and an area of 20' by 50' is being access controlled. Three personnel working at the scene were contaminated with the maximum contamination found on the personnel being 300 cpm alpha. The source was a 140 �Ci U-232 solid source from the Portsmouth Facility in Ohio. The source was re-secured in containers and the contaminated area is being decontaminated. Max contamination levels on container were 400,000 dpm/100 cm2 beta/gamma and 100,000 dpm/100 cm2 alpha. The personnel were decontaminated and had lung counts. Lung counts for all were negative for elevated intake. Fecal bioassays were initiated and are ongoing. Media attention: None at this time. Event Report ID No.: TN-08-005 |
| ENS 43306 | 17 April 2007 12:28:00 | The licensee provided the following information via facsimile: The Radiation Safety Officer at Energy Solutions waste processing facility (Duratek Radwaste Processing, Oak Ridge ,TN) called the State to report an incoming shipment (open bed trailer) containing 12 boxes (of Dry Active Waste - 323 millicuries) from Dairyland Power Cooperative in Genoa, Wisconsin was surveyed for receipt and found to have greater than 200 Mr/hr on one box. The dose rate exceeded the DOT regulations referenced in 49 CFR 173.441. NRC regions 1 and 3 were notified on 4/16/07. In further discussions with Dairyland Power Cooperative it was stated that when the shipment left La Cross power plant facility the survey of the boxes was within DOT shipping regulations. During transport the Dry Active Waste most likely settled to the bottom of the box which accounted for the elevated radiation levels. Dairyland Power Cooperative stated the state of TN would be contacting the state of WI about this incident. TN Report ID Number: TN-07-074
Spoke to state of TN and they indicated they were not contacting the state of WI since Dairyland Power Cooperative was a NRC licensee. Notified FSME (Morell) and R1DO (Miller) and R3DO (Kozak). |
| ENS 41136 | 19 October 2004 16:15:00 | On October 18, the licensee called the Division (Tennessee Division of Radiological Health) to report that a shipment brokered by Duratek from their facility in Memphis, TN on September 29 arrived at Laguna Verde Power Station near Veracruz, Mexico on October 5 with three boxes exceeding the removable contamination limits of 49CFR173.443. The boxes contained contaminated equipment, to be used at the Power Station during an outage. The equipment was contaminated with mixed fission/activation products. There was no contamination found on the truck. The boxes were decontaminated onsite. Tennessee Event report ID No.: TN-04-151
This event was reported on 10/19/04 as exceeding the removable contamination limits of 49 CFR 173.443. The licensee has investigated the incident which involved three boxes of GE Nuclear equipment shipped from the licensee to Laguna Verde Nuclear Plant in Mexico. The investigation has shown that this shipment did not violate applicable regulations for international shipments of radioactive materials and most likely did not violate the limits for shipments under the US DOT regulations. The latter statement is qualified. Because the data from Laguna Verde is not sufficient to make any other determination. The area averaging and the smear removal efficiencies were not determined. The investigation has revealed that the shipment violated Laguna Verde's acceptance procedures for loose contamination. NMSS EO ( Miller), R1DO (Cahill), and R4DO (Sanborn) have been informed. |
| ENS 40857 | 8 July 2004 15:42:00 | Terracon Consultants reported a Troxler moisture density gauge, Model 3430 SN 26411, containing 8 milliCuries of Cesium-137 and 40 milliCuries of Americium-241;Beryllium was stolen from the locked cab of a pickup truck parked at a hotel in Memphis, TN. The door of the truck was damaged and the locked container removed. State Department of Radiological Health (DRH) inspectors are onsite investigating at this time. Tennessee DRH notified US NRC Region 1, Memphis Police Department, Mississippi Division of Radiological Health, Arkansas Radiation Control, FBI, and Tennessee Emergency Management Agency. A press release was also issued by the Tennessee DRH. |
| ENS 40611 | 26 March 2004 14:53:00 | Event description: A pterygium patient was scheduled to receive a 42.5 second treatment utilizing a 100 millicurie Srontium-90 sealed source manufactured by 3M Company, model number 6D1A. The dosimetrist programmed the manual timer for 4 minutes and 25 seconds. During the treatment, the physician questioned the treatment time and it was terminated after 2 minutes and 30 seconds. The prescribed dose was 20 Gy. The patient received 70.59 Gy. The patient and the physician were notified of the misadministration. The licensee notified the Division the same day of the event. The licensee will submit a written report within 15 days. This incident is reportable under 1200-2-5-.32 (79) (e) (4) of 'State Regulations for Protection Against Radiation.' TN Event Report ID No.: TN-04-035 |