U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/11/2010 - 05/12/2010 ** EVENT NUMBERS ** | General Information or Other | Event Number: 45905 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM Licensee: GEOTECHNICAL CONSULTING, INC Region: 1 City: RICHMOND State: VA County: License #: 153-332-1 Agreement: Y Docket: NRC Notified By: CHARLES COLEMAN HQ OPS Officer: ERIC SIMPSON | Notification Date: 05/06/2010 Notification Time: 15:09 [ET] Event Date: 05/06/2010 Event Time: 12:00 [EDT] Last Update Date: 05/07/2010 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): WILLIAM COOK (R1DO) GREG SUBER (FSME) ILTAB (EMAI) | This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - MISSING TROXLER GAUGE The following information was provided by the Commonwealth of Virginia via facsimile: "On May 6, 2010 the licensee reported a missing Troxler portable gauge, Model 3430, Serial Number 36089. The utilization log indicated that a user had returned the gauge to the storage facility on April 23, 2010. On the morning of April 24, 2010 the user found the gauge was no longer in storage and assumed it had been sent for routine maintenance and repair and did not report it missing to the RSO (Radiation Safety Officer) or management. They became aware it was missing on May 6, 2010 while routine leak testing was being performed. "The licensee's representative stated that procedures require the gauge to be secured by a chain with padlock inside a locked caged area in a warehouse. The chain was present with the open padlock and there was no reported vandalism or forced entry into the warehouse or caged area. "The circumstances regarding the gauge are under investigation by the Virginia Department of Health Radioactive Materials Program. The licensee has contacted the Loudoun County Sheriff's Office and is conducting interviews with the user and other staff to determine if additional information is available." This event is VA report #VA-10-03. * * * UPDATE FROM MIKE WISE TO DONALD NORWOOD ON 5/7/2010 AT 1844 EDT * * * The gauge was found in the trunk of an authorized user's car. The gauge is being returned to its normal storage location and will be secured there. Notified R1DO (Cook), FSME EO (Suber), and ILTAB (via E-mail). 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 | General Information or Other | Event Number: 45907 | Rep Org: NE DIV OF RADIOACTIVE MATERIALS Licensee: OMAHA PUBLIC POWER DISTRICT Region: 4 City: OMAHA State: NE County: License #: 01-39-04 Agreement: Y Docket: NRC Notified By: RANDY LAMBERT HQ OPS Officer: PETE SNYDER | Notification Date: 05/06/2010 Notification Time: 16:19 [ET] Event Date: 05/06/2010 Event Time: 13:46 [CDT] Last Update Date: 05/06/2010 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): THOMAS FARNHOLTZ (R4DO) GREG SUBER (FSME) | Event Text AGREEMENT STATE REPORT - PROCESS GAUGE SHUTTER MALFUNCTION The following information was received from the State of Nebraska via facsimile: "The licensee uses fixed industrial gauges for measuring densities in fly ash hoppers at the station's precipitator building. The industrial gauges contain a Cesium 137 sealed source. The Cesium 137 sources were originally installed in 1975 and at the time contained 50 millicuries per source. "The sources were manufactured and installed by Kay Ray Inc. "The gauges are Model No. 7700-50. "The licensee was attempting to close the shutter on the fixed gauge prior to performing maintenance. One of the external closure cables was found to be slightly bound up and only partially closed the internal source shutter. The cable closure was reopened, which reopened the source shutter up at the sealed source. Closure was tried again. This time the cable, which connects the handle at the floor to the sealed source shutter mechanism 20 feet above, bent instead of sliding the cable to the closed position. "This event happened at 1346 [CDT] and was reported to the station's Shift Supervisor who in turn contacted the plant electricians to make repairs so the precipitator tag-out could continue. By 1353, the cable had been closed and the lab contacted to perform a survey to verify the source shutter was in the closed position. No personnel were exposed to radiation during this event." | General Information or Other | Event Number: 45908 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM Licensee: CHEVRON USA PRODUCTS COMPANY Region: 4 City: RICHMOND State: CA County: License #: Agreement: Y Docket: 0490-07 NRC Notified By: KENT PRENDERGAST HQ OPS Officer: CHARLES TEAL | Notification Date: 05/07/2010 Notification Time: 02:39 [ET] Event Date: 04/29/2010 Event Time: [PDT] Last Update Date: 05/07/2010 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): THOMAS FARNHOLTZ (R4DO) ANGELA MCINTOSH (FSME) MEXICO VIA FAX () | This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - POSSIBLE LOST X-RAY ANALYZER The following was received from the State of California via email: On May 5, 2010 the California Radiologic Health Branch (RHB) was informed by the alternate Radiation Safety Officer (RSO) of Chevron USA that they may have lost a Niton, XLP 818, S/N 13354, containing a 30 mCi Am241/Be sealed source. According to the alternate RSO, the Niton XLP was lost and was reported to him by the Material Inspection Group supervisor on April 29, 2010. This incident was not reported to RHB because the licensee was looking for the Niton XLP until the date of this report. CA Report #: 050610 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 This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source | General Information or Other | Event Number: 45909 | Rep Org: LOUISIANA RADIATION PROTECTION DIV Licensee: H&H X-RAY SERVICES, INC Region: 4 City: RINGOLD State: LA County: License #: LA-2970-L01 Agreement: Y Docket: NRC Notified By: ANN TROXLER HQ OPS Officer: ERIC SIMPSON | Notification Date: 05/07/2010 Notification Time: 09:10 [ET] Event Date: 04/26/2010 Event Time: 12:00 [CDT] Last Update Date: 05/07/2010 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): THOMAS FARNHOLTZ (R4DO) ANGELA MCINTOSH (FSME) | Event Text AGREEMENT STATE REPORT - STUCK/DAMAGED RADIOGRAPHY SOURCE Received this report from the State of Louisiana via facsimile: "On April 26, 2010, at a temporary job site a field crew was performing an X-Ray on a pipeline when the X-Ray source could not be returned to the shielded position. Using their survey meters, the crew determined the source was exposed and could not be retrieved. They called the Assistant Radiation Safety Officer who came and did a source retrieval and [received] a 150 mrem exposure. With the source shielded, the licensee transported the camera to QSA Global in Baton Rouge, LA for analysis. The equipment was a Sentinel, model 660E, S/N 82187, loaded with 69.5 Ci of Ir-l92, S/N 60611B. QSA Global observed the source and performed further evaluation. The results were that the weld on the source cracked and the capsule was catching on the exit port of the camera. QSA Global put out a recall for that particular lot of sources and forwarded the damaged camera to QSA Global in Burlington, MA." This event is Louisiana report # LA1000004 | General Information or Other | Event Number: 45910 | Rep Org: MA RADIATION CONTROL PROGRAM Licensee: LANTHEUS MEDICAL IMAGING Region: 1 City: NORTH BILLERICA State: MA County: License #: 60-0088 Agreement: Y Docket: NRC Notified By: JOHN SUMARES HQ OPS Officer: ERIC SIMPSON | Notification Date: 05/07/2010 Notification Time: 14:35 [ET] Event Date: 04/23/2010 Event Time: 14:45 [EDT] Last Update Date: 05/10/2010 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): WILLIAM COOK (R1DO) GREG SUBER (FSME) | Event Text AGREEMENT STATE REPORT - EXTERNAL RADIATION LEVELS EXCEED LIMITS The following was received via email from the Commonwealth of Massachusetts: "Lantheus Medical Imaging (LMI) received a customer complaint on 4/23/10 from a customer (GE Healthcare in Tampa, FL) reporting a reading of 310 mR/hr on a Tc-99m generator that was manufactured on 4/22/10 at the facility in Billerica, MA. On 4/27/10, LMI was able to clarify that the reading was on the package surface rather than on the generator itself. "The customer reported the situation to the Florida Bureau of Radiation Control on 4/28/10. LMI has been investigating and have not yet found any evidence of a problem with this generator in their manufacturing records. LMI will continue to investigate and will be receiving the generator back from the customer in the next week or so. They will then examine it directly." The R1DO (Cook) and FSME (Suber) have been notified. * * * UPDATE FROM JOHN SUMARES TO JOE O'HARA VIA FAX AT 1041 ON 5/10/10 * * * The Commonwealth clarified their report that the TC-99m generator is actually a Mo-99 generator. Notified R1DO (Gray) and FSME (McIntosh). | General Information or Other | Event Number: 45911 | Rep Org: COLORADO DEPT OF HEALTH Licensee: MERCY MEDICAL CENTER Region: 4 City: DURANGO State: CO County: License #: 5-01 Agreement: Y Docket: NRC Notified By: JAMES DeWOLFE HQ OPS Officer: PETE SNYDER | Notification Date: 05/07/2010 Notification Time: 15:49 [ET] Event Date: 04/29/2010 Event Time: [MDT] Last Update Date: 05/07/2010 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): THOMAS FARNHOLTZ (R4DO) GREG SUBER (FSME) | Event Text AGREEMENT STATE REPORT - POTENTIAL DOSE TO EMBRYO OR FETUS The State of Colorado provided the following information via email: "In accordance with [Colorado Code] 7.23.1 [similar to 10 CFR 35.3047], Mercy Medical Center, Durango, CO is reporting a dose to an embryo/fetus in excess of 5 mSv." "On March 16, 2010 1110 MBq (30 mCi) of I-131 was administered to a 31 [year old] female patient." "A serum blood [pregnancy] test was taken prior to administration and was negative. On April 26, 2010 the patient, thinking she might be pregnant, took a home urine [pregnancy] test that showed positive. Pregnancy was confirmed by blood serum test on April 27, 2010. Patients OB/GYN physician estimates conception occurred on March 13, 2010." "Fetal dose was estimated to be approximately 80 mGy (8 rem). At this dose level and administration time in relation to fetal development (still in blastogenesis), there will likely be no impact upon subsequent fetal development or subsequent health risks. The patient has been notified as such." The Department has begun an investigation of this incident and will keep the NRC informed of the status of our investigation. The licensee stated that all procedures to prevent this occurrence were followed. Human chorionic gonadotropin (Hcg) is not detectable in the blood until 7 - 12 days post conception. The licensee is considering including additional questions during the screening process. | Power Reactor | Event Number: 45916 | Facility: FARLEY Region: 2 State: AL Unit: [1] [2] [ ] RX Type: [1] W-3-LP,[2] W-3-LP NRC Notified By: J.J. HUTTO HQ OPS Officer: CHARLES TEAL | Notification Date: 05/11/2010 Notification Time: 16:12 [ET] Event Date: 05/11/2010 Event Time: 09:30 [CDT] Last Update Date: 05/11/2010 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE | Person (Organization): KATHLEEN O'DONOHUE (R2DO) | 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 | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text LOSS OF TECHNICAL SUPPORT CENTER "On 05-11-10 at 09:30 hours the Technical Support Center (TSC) ventilation, filtration and climate control system was identified as nonfunctional. The TSC was declared nonfunctional. A plan has been implemented for performance of TSC functions in alternate locations in accordance with site emergency implementation procedures. "At 13:00 hours on 05-11-10, the system was placed back in service but is still considered non-functional while additional trouble shooting is being performed and final repairs are made." The licensee notified the NRC Resident Inspector. | Fuel Cycle Facility | Event Number: 45917 | Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT RX Type: URANIUM ENRICHMENT FACILITY Comments: 2 DEMOCRACY CENTER 6903 ROCKLEDGE DRIVE BETHESDA, MD 20817 Region: 2 City: PIKETON State: OH County: PIKE License #: GDP-2 Agreement: Y Docket: 0707002 NRC Notified By: KEITH VANDERPOOL HQ OPS Officer: CHARLES TEAL | Notification Date: 05/11/2010 Notification Time: 17:48 [ET] Event Date: 05/11/2010 Event Time: 17:09 [EDT] Last Update Date: 05/11/2010 | Emergency Class: NON EMERGENCY 10 CFR Section: OTHER UNSPEC REQMNT | Person (Organization): KATHLEEN O'DONOHUE (R2DO) MARISSA BAILEY (NMSS) | Event Text OFFSITE NOTIFICATION "[On] May 10, 2010 at 1710 hours a USEC (United States Enrichment Corporation) Protective Force Officer entered the X-104 Police Headquarters Weapon Cleaning Area to perform cleaning maintenance on his assigned weapon. The officer began to disassemble the weapon [while] pointing the weapon in a safe direction. He pulled the trigger to release the slide and the weapon discharged (this action is required to remove the slide from this type of weapon). The officer in question was the only person in the room at the time of the incident. The officer was not struck by the discharge, however he did sustain minor powder burns to his hand. The area and weapon was immediately secured by Protective Force Management personnel. USEC Fire/EMS were summoned to the incident scene where the officers injury was evaluated at which time the officer refused treatment. Personal statements were collected from all personnel in the immediate area. A critique was conducted. The Protective Force Manager has generated a Long Term Order to provide compensatory actions to prevent recurrence of an accidental discharge of a weapon due to the same or similar circumstances. An internal investigation as well as an independent investigation are currently in progress. "This event was reportable to the Department of Energy per XP2-RA-RE1001 6.2.1, which requires a formal notification. This formal notification constitutes the need to report this event to the Nuclear Regulatory Commission within four (4) Hours per criteria listed in procedure UE2-RA-RE1030, Appendix 'D', P." | Power Reactor | Event Number: 45918 | Facility: PERRY Region: 3 State: OH Unit: [1] [ ] [ ] RX Type: [1] GE-6 NRC Notified By: DAVE DUESING HQ OPS Officer: BILL HUFFMAN | Notification Date: 05/12/2010 Notification Time: 03:12 [ET] Event Date: 05/11/2010 Event Time: 23:18 [EDT] Last Update Date: 05/12/2010 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL | Person (Organization): MARK RING (R3DO) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO LOSS OF CONTROL ROD DRIVE CHARGING WATER HEADER PUMPS "On May 11, 2010, at approximately 2318 hours, a manual Reactor Protection System (RPS) actuation was initiated as required by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.1.5 'Control Rod Scram Accumulators.' Control Rod Drive (CRD) charging water header pressure was less than 1520 psig (i.e., no CRD pumps operating) and there were multiple accumulator faults on withdrawn control rods. At the time of the event, the plant was in Mode 1 at 100% power. All control rods are inserted into the core and the plant is currently stable, in Mode 3 (Hot Shutdown) with reactor pressure at approximately 930 psig. No Emergency Core Cooling Systems were required or utilized to respond to the event and there were no other 10 CFR 50.72 reportable actuations. Reactor coolant level is being maintained in its normal band by the feedwater system and decay heat is being removed by the condenser. The plant is in a normal electrical line-up with all three Emergency Diesel Generators operable and available if needed. "The cause of the event initiator, an invalid Division 2 Loss of Coolant Accident (LOCA), i.e., High Drywell Pressure/Low Reactor Vessel Water Level, signal, is currently under investigation. Prior to the manual RPS Actuation, the invalid LOCA signal resulted in invalid actuations of Division 2 equipment and systems including, the Division 2 Emergency Diesel Generator (EDG), (which started but did not load onto the bus), Low Pressure Coolant Injection B and C subsystems (which started the pumps but did not inject into the vessel), discharge of the Suppression Pool Makeup subsystem B into the suppression pool, startup of the Control Room Emergency Recirculation subsystem B, and isolation of Group 2B Containment isolation valves which included the Nuclear Closed Cooling System Containment Return Isolation valve that was not already closed. The affected equipment is being restored in accordance with plant procedure. The NRC Resident Inspector has been notified." The licensee experienced an instrumentation rack loss of power which appears to have resulted in the inadvertent Division 2 initiation. The initiator of this event also and led to a loss of power to both control rod drive charging water header pumps resulting in charging water header pressure less than required and related accumulator faults which placed the licensee in a technical specification required shutdown condition. The action statement allows only 20 minutes to restore the condition which was insufficient time for the licensee to correct the condition so a manual scram was initiated from 100% power. The scram was characterized as an uncomplicated scram and all system responses (not related to the initial instrument fault) functioned as required. | |