| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/18/2007 - 12/19/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43700 | Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: PHARMACY SERVICES OF THE QUAD CITIES
Region: 3
City: DAVENPORT State: IA
County:
License #: 0207-1-82-NP
Agreement: Y
Docket:
NRC Notified By: NANCY FARMINGTON
HQ OPS Officer: JOE O'HARA | Notification Date: 10/08/2007
Notification Time: 09:53 [ET]
Event Date: 10/04/2007
Event Time: [CDT]
Last Update Date: 12/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LAURA KOZAK (R3)
NADER MAMISH (FSME)
| Event Text AGREEMENT STATE REPORT - MOLYBDENUM 99 CONCENTRATION TOO HIGH ON ELUTION ON MOLYBDENUM 99/TECHNETIUM- 99M GENERATOR
The State provided the following information via email:
"Event Cause: MOLYBDENUM 99 CONCENTRATION TOO HIGH ON ELUTION ON MOLYBDENUM 99/TECHNETIUM- 99M GENERATOR
"Event Date: 10/04/2007 Report Date: 10/05/2007
"Licensee/Reporting Party Information:
"Name: PHARMACY SERVICES OF THE QUAD CITIES, License Number: 0207-1-82-NP, DAVENPORT, IA 52807
"IDPH received a call from the Pharmacy Services of Quad Cities RSO on Friday, October 5, 2007, concerning a Bristol-Myers Squibb (BMS) Mo99/Tc99M generator that they had received on Wednesday, October 3, 2007. The licensee first eluted the generator on Thursday, October 4, 2007, and discovered an elevated Mo99 concentration in the elution. Subsequent elutions also had elevated Mo99 concentrations. The licensee contacted the manufacturer (BMS) and was asked to ship the generator back to the manufacturer. The licensee contacted IDPH concerning the shipping container. An Information Notice that was issued in 1997 talks to this issue, and IDPH told the licensee to hold the generator 10 1/2 lives or a special salvage container would be needed to ship the generator back to BMS."
The State reported that elutions greater than .15 micro Curies per milli Curie Tc-99m are unacceptable and exceed establish limits. See Information Notice No. 84-85: 'Molybdenum Breakthrough From Technetium-99m Generators' Also a state representative said that the lot number of this generator was "M275711D," the size was 15 curies, the calibration date is 10/2 and the expiration date is 10/6.
"As of Monday October 8, 2007, the generator is being held at the pharmacy.
"Corrective Actions: Action Number: 1 MANUFACTURER WILL NOTIFY CUSTOMERS OF DEFECT
"Keywords: ELEVATED MO99 CONCENTRATION FROM GENERATOR ELUTION
"Source of Radiation: Source Number: 1 Form of Radioactive: ELEVATED MO99 CONCENTRATION
"Radionuclide or Voltage (kVp/MeV): MO-99
"Source Use: RADIOPHARMACEUTICAL
"Manufacturer: BRISTOL-MEYERS SQUIB
"Device/Associated Equipment: Device Number: 1
"Device Name: RADIOPHARMACEUTICAL GENERATOR
"Manufacturer: BRISTOL-MEYERS SQUIB
"Problem with Equipment: ELEVATED MO99
"Reporting Requirements: 30.50(b)(2)(ii) - The 24 hour report of an event where required equipment is disabled or fails to function as designed when the equipment is required to be available and operable when it is disabled or fails to function.
"Iowa Event # IA070004"
*** UPDATE FROM IDPH (FARRINGTON) TO CROUCH VIA EMAIL AT 0938 EST ON 12/18/07 ***
"The manufacturer, Bristol-Meyers Squibb Medical Imaging Inc., reported back to the Iowa licensee number: IA-207-1-82-NP that it was indeterminate as to the cause of the problem. The State of Iowa considers this event closed.
Notified R3DO (Duncan) and FSME (Burgess). |
| General Information or Other | Event Number: 43842 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: EUSTIS ENGINEERING
Region: 4
City: State: LA
County: ST. JAMES PARISH
License #: LA-2922-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: JOHN MacKINNON | Notification Date: 12/14/2007
Notification Time: 10:49 [ET]
Event Date: 11/15/2007
Event Time: 08:00 [CST]
Last Update Date: 12/14/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RUSSELL BYWATER (R4)
GREG MORELL (FSME)
| Event Text LOUISIANA AGREEMENT STATE REPORT - TROXLER MOISTURE DENSITY GAUGE HIT BY A BULLDOZER
This information was received via email
"Eustis Engineering reported an incident that occurred on November 15, 2007. At 8:00AM on this date a Troxler gauge model number 3440 with serial number 25934 was hit by a bulldozer. This gauge has a 8.0 mCi source Cs-137 and a 20 mCi source of Am241:Be. The bulldozer that hit the gauge was operated by James Construction at the Marathon GME Refinery construction site. The technician called the Eustis Engineering office immediately after it occurred. Mr. (deleted), the Eustis RSO, was dispatched to the site. The RSO arrived at 9:30AM and conducted a survey using a Trox Alert survey meter. At 30 feet away the meter reading was 0.1 Mr. At 2 feet away the meter reading was 0.2 Mr. A leak test was conducted by Gamma Tron on November 15, 2007 after the incident with the results being less than 0.005 uCi (microCuries) of removable contamination"
Event Report ID No.: LA070031. |
| Power Reactor | Event Number: 43849 | Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MATT FORREST
HQ OPS Officer: PETE SNYDER | Notification Date: 12/18/2007
Notification Time: 09:49 [ET]
Event Date: 12/18/2007
Event Time: 07:39 [EST]
Last Update Date: 12/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JAMES TRAPP (R1)
WATTS (USDA)
SMITH (DOE)
TURNER (HHS)
EACHES (FEMA)
RAWLS (EPA)
|
| 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 HYDRAULIC FLUID SPILL ONSITE
"On 12/18/07 at 0739, the Control Room was notified of an approximate 50 gallon oil spill onsite. The spill appears to have originated from a broken hydraulic fluid line on a nearby crane. The spill is contained and did not reach any storm drain or body of water. The spill is reportable to the State of New Hampshire Department of Environmental Services in accordance with State regulation. The NRC Resident has been notified of the event."
This incident did not impact plant operations and there were no radiological materials involved. |
| Power Reactor | Event Number: 43850 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: RODNEY JOHNSON
HQ OPS Officer: JOE O'HARA | Notification Date: 12/18/2007
Notification Time: 10:43 [ET]
Event Date: 10/22/2007
Event Time: 18:30 [EST]
Last Update Date: 12/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
ERIC DUNCAN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text INVALID SYSTEM ACTUATION
"The following information is provided as a 60 day telephone notification under 10 CFR 5O.73(a)(l) in lieu of submitting a written LER to report a condition that resulted in an invalid actuation of a 10 CFR 50.73(a)(2)(iv)(B) system. NUREG 1022, Revision 2, identifies the information that is to be reported as discussed below.
"On October 22. 2007, at 1830 hours, Division 2 of Residual Heat Removal (RHR) was being placed in Shutdown Cooling (SDC) following completion of a SDC outage. The plant was in Mode 5, Refueling. Reactor Protection System (RPS) A was deenergized for maintenance. RPS B was being supplied by the alternate supply because the B RPS Motor Generator was removed from service for maintenance. Upon start of the RHR D pump motor the RPS B Alternate Supply Electrical Protection Assembly (EPA) breakers tripped due to sensed undervoltage. The loss of the power supply to RPS B resulted in the following: A reactor scram (all rods were already fully inserted), RHR SDC outboard valve isolation, trip of the Reactor Water Cleanup System (RWCU), outboard valve isolation of the Torus Water Management System (TWMS).
"A secondary containment isolation also occurred resulting in a trip of Reactor Building Heating Ventilation and Air Conditioning (HVAC), auto start of Division 2 of Standby Gas Treatment System (SGTS), and shift of the Control Center HVAC system to recirculation mode. All actuations and isolations were as expected for existing plant conditions. The initiation signal was invalid because it did not result in response to an actual plant parameter, nor did it trip as a result of any other requirement for initiation of a safety function. Due to the actuation of equipment in multiple systems that were not removed from service or otherwise prevented from changing states, this event is reportable under 50.73(a)(2)(iv) as an invalid actuation of one of the specified systems.
"The reactor scram actuation was complete because a half scram was already present due to RPS A being deenergized for maintenance. The Division 2 SGTS system automatically started, secondary containment fully isolated, Reactor Building HVAC system tripped, and the Control Center HVAC fully shifted into the recirculation mode. The following were partial isolations due to loss of RPS B, Division 2: RHR SDC isolation and TWMS isolation.
"All systems functioned properly in response to the RPS power loss based on refuel outage system configurations."
The licensee believes that the cause of the undervoltage was a result of the start of the RHR pump which caused an in-rush current. The licensee is considering a design change, and captured this event in their corrective action program system as CARD 07-26537.
The licensee will notify the NRC Resident Inspector. |
| Other Nuclear Material | Event Number: 43851 | Rep Org: DEFENSE LOGISTICS AGENCY
Licensee: DEFENSE LOGISTICS AGENCY
Region: 1
City: ANNISTON State: AL
County:
License #: 37-30062-01
Agreement: Y
Docket:
NRC Notified By: DAVID MACK
HQ OPS Officer: HOWIE CROUCH | Notification Date: 12/18/2007
Notification Time: 13:54 [ET]
Event Date: 12/15/2007
Event Time: [CST]
Last Update Date: 12/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
JAMES TRAPP (R1)
DUNCAN WHITE (FSME)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text TRITIUM AIMING POST LIGHTS MISSING
The Defense Distribution Center Defense Depot in Anniston, AL reported a shortage of 7 aiming post lights, each containing 9 Ci of tritium. The shortage was discovered during a shipment pick denial process. A physical inventory conducted at the time of denial confirmed that the lights were not at the designated storage location. The lights were last accounted for during a September, 2007 inventory. It was noted, however, that 88 Material Release Orders were processed for the lights on the same date that the inventory was conducted. No reported overages by receiving agencies were identified.
The Defense Depot will contact each recent recipient to determine quantities received in an attempt to reclaim the devices.
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. |
| Other Nuclear Material | Event Number: 43852 | Rep Org: TURKEY HILL DAIRY
Licensee: TURKEY HILL DAIRY
Region: 1
City: LANCASTER State: PA
County:
License #:
Agreement: N
Docket:
NRC Notified By: JEFFREY GROFF
HQ OPS Officer: JASON KOZAL | Notification Date: 12/17/2007
Notification Time: 17:45 [ET]
Event Date: 12/17/2007
Event Time: [EST]
Last Update Date: 12/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2202(b)(2) - EXCESSIVE RELEASE
| Person (Organization):
JAMES TRAPP (R1)
DUNCAN WHITE (FSME)
| Event Text BROKEN TRITIUM EXIT SIGN
The licensee called to report that they discovered a broken tritium exit sign in a storage locker in their parts room. They contacted a contractor who did the site characterization and cleanup. Currently, the sign is stored on site in the safety storage room, doubled bagged and labeled. No over exposure or personnel contamination was indicated. The only data for the sign is it was manufactured in 1999. There was no damage to any additional exit signs. | |