| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/27/2005 - 07/28/2005 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 41862 | Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: IRBY STEEL, DIV OF STRUTHERS INDUSTRIES
Region: 1
City: GULFPORT State: MS
County:
License #: MS-750-01
Agreement: Y
Docket:
NRC Notified By: BOBBY SMITH
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/22/2005
Notification Time: 12:47 [ET]
Event Date: 07/20/2005
Event Time: [CDT]
Last Update Date: 07/22/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RICHARD CONTE (R1)
TOM ESSIG (NMSS)
| Event Text AGREEMENT STATE REPORT INVOLVING POTENTIALLY ABANDONED SOURCES
The following information was received from the State of Mississippi via email:
"Description of Incident: Received notification 7-20-05 from Mississippi Emergency Management Agency (MEMA) that another State Agency (DEQ) had discovered the abandonment of a AEA Model 680 Cobalt-60 exposure device and a SPEC Model 150 exposure device containing Iridium-192. Division of Rad Health (DRH) personnel responded to location and determined that no devices were missing from the licensed storage facility. It had been assumed from other emergency responders that a overpack (Model 680-OP) for the Cobalt device may have contained radioactive material and was missing from the container. The event generated television and newspaper media attention. DRH personnel explained that the overpack was only used when the device was transported on public roads. All radioactive material was accounted for and secured in the storage area. Also, DRH and DEQ personnel went to Struthers Industries location at the 34th Street facility located in Gulfport, MS, where all radioactive material ( a Model 680 Cobalt 60 exposure device and a Model 660 Iridium 192 device) was accounted for and still secured in the locked storage vault. There was security concerns due to the companies being in bankruptcy and the new owners not knowing about the radioactive devices. DRH had investigated the security of the sources on 6-28-05 and found the sources safe, but met with the president of company who assured DRH he would properly dispose of the devices. On 7-21-05 AEA Technology was contacted to remove the sources. The sources were put in approved overpacks. Leak tests had been performed on the sources and determined that the sources were not leaking. AEA personnel also removed all radiation signs and associated equipment at the 2 locations. DRH personnel did closeout surveys along with AEA personnel to ensure no radioactive sources were left behind. All radioactive material that was licensed by the 2 licenses (MS-750-01 and MS-259-01) were accounted for and removed by AEA personnel. It has not been determined by DRH personnel if devices were abandoned and the investigation is ongoing by DRH personnel.
"Isotope(s)/Activity: Cobalt 60 (2 devices/sources) @ 23 curies in each device, Iridium 192 (2 devices/sources) @ 5 curies in each device
"Date of Incident: 7-20-05
"Date Reported To DRH: 7-20-05
"Describe clean-up actions taken by DRH: After determining all radioactive devices were accounted for, DRH contacted AEA Technology about the removal of the devices. DRH personnel stayed at location until all sources and devices were removed and caution signs and associated radiography equipment was removed.
"List radiation measurements taken by DRH: Highest readings were @ 30 mR/hr at surface of the Co-60 exposure devices. The readings on the Iridium-192 devices were less than 5 mR/hr.
"List any other actions required of DRH: Event is under investigation by DRH, EPA, MS DEQ, and FBI.
"List any actions taken to notify NRC, other Agreement States: NRC Ops Center notified by E-mail 7-22-05; NMED notified 7-22-05 by E-mail. Event was reported to EPA due to other hazardous materials that were discovered at the site. Also investigated by FBI and inquiries made from Homeland Security.
"Enforcement action taken: Investigation ongoing as to if devices were abandoned or if the owner was still in process of disposing of the devices." |
| General Information or Other | Event Number: 41867 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: CITGO PETROLEUM CORPORATION
Region: 4
City: LAKE CHARLES State: LA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DIRENE ALLEN
HQ OPS Officer: PETE SNYDER | Notification Date: 07/25/2005
Notification Time: 13:30 [ET]
Event Date: 07/25/2005
Event Time: [CDT]
Last Update Date: 07/25/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID GRAVES (R4)
MICHELE BURGESS (NMSS)
| Event Text AGREEMENT STATE REPORT INVOLVING FIRE DAMAGED GAUGES
The State provided the following information via facsimile:
"Fire broke out in the Coker 1 unit at Citgo. The FA201A and 201B vessel structures (24,000 cu. Ft.) holding Coker feed (heavy black oil) product were impacted by the fire / heat from fire. Each of the above-mentioned vessels have three nuclear gauges (Am-241 / Be, 500mCi activity) attached in linear formation to them. The gauges are used for product level measurements. Three of the six total number of gauges sustained fire / heat from fire that impacted the functioning of the housing of devices, specifically the shutters. According to Citgo licensee:
"1) Of the three shutters impacted, two cannot be closed (and therefore, unlocked) and remain open as they usually are during regular production, the third could be closed but not locked.
"2) All six gauges are scheduled to be removed by the manufacturer for maintenance, repair, etc. as needed.
"3) The gauges are Kay-Ray (Thermo Measure Tech) brands.
"4) The three gauges with functional impact are: Gauge Housing - all are model number 7100B; Sealed Source model number MRL2723C and serial numbers -- 17235, 26053, and S95M2201." |
| Other Nuclear Material | Event Number: 41871 | Rep Org: HARBINSON AND WALKER
Licensee: HARBINSON AND WALKER
Region: 3
City: LUDINGTON State: MI
County:
License #:
Agreement: N
Docket:
NRC Notified By: JOHN CROOKS
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 07/26/2005
Notification Time: 14:27 [ET]
Event Date: 04/25/2005
Event Time: [EDT]
Last Update Date: 07/27/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
MARK RING (R3)
SCOTT MOORE (NMSS)
M.HAHN (E-MAILED) (TAS)
| Event Text LOST SOURCE FROM A LEVEL MEASURING DEVICE
Licensee reported that two 50 millicurie Cs-137 sources, used in level measuring devices, were found to be missing from a magnesium oxide producing facility that had been closed for two years. It was determined that two sources were missing after a review of their registration around the April-May time period. Since then, they located one of the two sources, brand new, in a crate on a shelf at the facility. They located the non-nuclear part of the device (the receiver) on a hopper which was at a scrap yard on site, but the sending unit (the nuclear part) was missing. They continued looking for the sender, but could not find it.
* * * UPDATE ON 07/27/05 @ 1745 BY ASHLEY TULL TO CHAUNCEY GOULD * * *
The single source which is still lost is a TN Technologies Model 5200 gauge containing 200 millicuries Cs-137 not 50 millicuries.
Notified Reg 3 RDO (Mark Ring) and NMSS EO (Joe Giitter)
* * * UPDATE ON 07/27/05 @ 2142 BY JOHN CROOKS TO CHAUNCEY GOULD * * *
Two NRC Inspectors visited the closed facility with a radiation detector and located the missing device in a parts warehouse at the facility. It was on a shelf and had turned rusty and was unidentifiable. The device was isolated in another building with the other device that had been found.
Notified Reg 3 RDO (Mark Ring), NMSS EO (Joe Giitter) and TAS(E-MAIL) |
| Hospital | Event Number: 41872 | Rep Org: WINCHESTER MEDICAL CENTER
Licensee: VALLEY HEALTH SYSTEM
Region: 1
City: WINCHESTER State: VA
County:
License #: 450158901
Agreement: N
Docket:
NRC Notified By: KERI WILLIAMS
HQ OPS Officer: PETE SNYDER | Notification Date: 07/26/2005
Notification Time: 16:10 [ET]
Event Date: 07/22/2005
Event Time: 10:00 [EDT]
Last Update Date: 07/27/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
GLENN MEYER (R1)
SCOTT MOORE (NMSS)
| Event Text MEDICAL EVENT - ADMINISTRATION OF LOWER DOSE THAN PRESCRIBED
On July 22, 2005 a patient was administered a dose of 2.64 rem from a 66 mCi (millicurie) source of Sm 153 versus the intended dose of 4.28 rem for bone pain therapy. This was discovered later when the medical technologist questioned the dose and raised a question with the supervisor. When the technologists checked the calibration setting of the instrument used to measure the source they discovered that the calibration setting was incorrect. With the incorrect calibration setting a source of 66 mCi of Sm 153 was used versus the intended 107 mCi source. The prescribing physician will notify the patient's doctor who will contact the patient. There was no known adverse affect on the patient.
The hospital took a corrective action of retraining and adding a check on their administration sheet that requires the technologist to check the instrument calibration setting.
* * * UPDATE TO NRC (HUFFMAN) FROM LICENSEE (WILLIAMS) AT 15:11 EDT ON 7/27/05 * * *
The following follow-up calculations related to the dose were provided by the licensee:
Whole body dose (assuming a qualify factor of 10) - 0.108 millisieverts per megabecquerel
Bony Surfaces dose (assuming a qualify factor of 10) - 67.56 millisieverts per megabecquerel
Bone Marrow dose (assuming a qualify factor of 10) - 15.37 millisieverts per megabecquerel
R1DO (Meyers) notified. |
| Power Reactor | Event Number: 41875 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: J. GAINES
HQ OPS Officer: BILL HUFFMAN | Notification Date: 07/27/2005
Notification Time: 16:03 [ET]
Event Date: 07/27/2005
Event Time: 15:00 [EDT]
Last Update Date: 07/27/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GLENN MEYER (R1)
SCOTT MOORE (NMSS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text IMPROPERLY LABELED RADIOACTIVE MATERIAL SHIPMENT
The licensee reported that three main steam line radiation monitors (unused) were recently shipped from a site storage warehouse to a salvage vendor (ATS Corporation in Woodridge, Illinois). When the material arrived at the vendor, it was discovered that each of the monitors contained a 100 nanocurie Americium-241 source (a total of three 100 nanocurie sources). The vendor informed Calvert Cliffs of the radioactive sources in the shipment. Apparently, the licensee was unaware of the sources in the monitors when the material was sent to salvage. Calvert is sending a representative to the vendor to retrieve the sources. Calvert will also be issuing a 30 day Hazardous Material Incident Report in accordance with 49 CFR 171.21 for making the shipment without properly marking the packaging as containing radioactive material.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41876 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: ROY GILLOW
HQ OPS Officer: BILL HUFFMAN | Notification Date: 07/27/2005
Notification Time: 21:08 [ET]
Event Date: 07/27/2005
Event Time: 20:00 [EDT]
Last Update Date: 07/27/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GLENN MEYER (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 45 | Power Operation | Event Text OFFSITE NOTIFICATION CONCERNING POWER REDUCTION TO TAKE PLANT OFFLINE
"The New York State Public Service Commission was notified that Ginna is coming offline due to chemistry concerns. EPRI level 3 guidelines [for sodium and chloride levels] were exceeded during line-up of the blow down system during maintenance. Required action is to reduce power to less than 5% reactor power and perform system cleanup."
The licensee notified the NRC Resident Inspector. | |