| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/06/2010 - 04/07/2010 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | General Information or Other | Event Number: 45787 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: PET IMAGING OF NORTHERN COLORADO
Region: 4
City: FORT COLLINS State: CO
County:
License #: 1105-0
Agreement: Y
Docket:
NRC Notified By: ED STROUD
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/24/2010
Notification Time: 12:30 [ET]
Event Date: 12/14/2009
Event Time: [MDT]
Last Update Date: 04/06/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RICK DEESE (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - FETAL EXPOSURE IN EXCESS OF 500 MILLIREM DURING A PET/CT SCAN
The following information was obtained from the State of Colorado via facsimile:
"The Department received notification on March 23, 2010, of a fetal exposure in excess of 500 milliRem from a PET/CT Scan. The licensee, PET Imaging of Northern Colorado, License No. 1105-0, is located in Fort Collins, Colorado. The licensee reported that on December 14, 2009, a female patient received 17.4 mCi of F-18 and underwent a PET/CT scan. The patient had indicated that she was not pregnant on her medical history questionnaire and told the technologist she was not pregnant prior to the scan. Later, the patient's physician notified the licensee that the patient was indeed pregnant at the time of the scan.
"A consulting medical physicist calculated the total dose to the fetus from the PET/CT scan as 2.6 Rem (26 mGy). However, the medical physicist did not report the individual dose from the F-18 component alone, and this information has been requested from the licensee.
"The licensee's authorized user physician reported that the risk of abnormality for the fetus is considered to be negligible per the guidance from the American College of Radiology Practice Guidelines.
"No other details are available at this time."
* * * RETRACTION FROM ED STROUD TO PETE SNYDER AT 1550 ON 4/6/10 * * *
The following information was obtained from the State of Colorado via facsimile:
"Following a full investigation of the incident, the fetal exposure was determined to be below the NRC's reporting requirement of 5 REM."
Notified R4DO (Proulx) and FSME EO (VonTill). |
| General Information or Other | Event Number: 45804 | Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: TESTAMERICAN LABORATORIES INC
Region: 3
City: CEDAR FALLS State: IA
County:
License #: 3063-1-07-ECD
Agreement: Y
Docket:
NRC Notified By: RANDY DAHLIN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/01/2010
Notification Time: 11:55 [ET]
Event Date: 03/26/2010
Event Time: [CDT]
Last Update Date: 04/01/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ERIC DUNCAN (R3DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - LEAKING SEALED SOURCES IN GAS CHROMATOGRAPH
The following information was obtained from the State of Iowa via facsimile:
Two sealed sources in a gas chromatograph (electron capture device) were wipe tested and had removable contamination. The sources will be sent to the manufacturer for disposal.
Manufacturer: Agilent Technologies Incorporated
Model: G2397A
Sources: Each source contained 15 milliCuries Ni-63
(1) Serial: U12585 Leakage: 0.028 microCuries
(2) Serial: U12586 Leakage: 0.00549 microCuries
Iowa incident number: IA100002 |
| General Information or Other | Event Number: 45807 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: ECS MID-ATLANTIC LLC
Region: 1
City: State: VA
County: ROANOKE
License #: 170-314-1
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/02/2010
Notification Time: 12:17 [ET]
Event Date: 04/01/2010
Event Time: [EDT]
Last Update Date: 04/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PAUL KROHN (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - TROXLER GAUGE DAMAGED BY CONSTRUCTION EQUIPMENT
The following information was received from the Commonwealth of Virginia via facsimile:
"The licensee's portable density gauge (Troxler Model 3430 S/N 038435) was damaged on April 1, 2010 when it was struck by a piece of earth moving equipment. The accident occurred at a commercial construction site in Roanoke County, Virginia. The gauge operator secured the area of the gauge and telephoned the licensee's Radiation Safety Officer who performed an onsite investigation and a radiation survey. The source was in the shielded position at the time of the accident and the survey confirmed that it remained so. There was no damage to the source rod or handle and only minor damage to the gauge trigger and casing. The gauge was returned to the licensee's storage facility. There were no injuries or radiation exposures as a result of the accident."
Virginia Event Report ID No: VA-10-02 |
| Power Reactor | Event Number: 45814 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: FRED POLLACK
HQ OPS Officer: VINCE KLCO | Notification Date: 04/06/2010
Notification Time: 02:42 [ET]
Event Date: 04/05/2010
Event Time: 23:02 [EDT]
Last Update Date: 04/06/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
JAMES MOORMAN (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text TRANSPORT OF A CONTAMINATED INDIVIDUAL OFFSITE
"On 4/5/2010, at 2244 [EDT], the Unit 1 Control Room was notified of an individual in the Unit 1 Containment Building complaining of chest pains. Offsite medical was contacted via 911 emergency call and the individual was transported, via ambulance, to Lawnwood Regional Medical Center at 2302. Radiation Protection personnel accompanied the individual to the hospital. The individual was admitted at 2335. Radiation Protection personnel determined that the individual was radioactively contaminated at a level of 3500 corrected counts per minute on his left ankle. The individual was successfully decontaminated. The transport of a radioactively contaminated individual to an offsite medical facility is reportable under 10CFR50.72(b)(3)(xii)."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45815 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DOUGLAS SHORTER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/06/2010
Notification Time: 06:11 [ET]
Event Date: 04/05/2010
Event Time: 22:50 [EDT]
Last Update Date: 04/06/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
HIRONORI PETERSON (R3DO)
|
| 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 LOSS OF SAFETY FUNCTION TO CONTROL THE RELEASE OF RADIOACTIVE MATERIAL
"At 2145 [EDT] hours on April 5, 2010, a loss of electrical power to the Division 1 Loss of Coolant Accident (LOCA) initiation logic occurred. Control room annunciators for 'Residual Heat Removal (RHR) Out of Service', 'Reactor Core Isolation Cooling (RCIC) Out of Service', and 'RCIC/RHR D2 to D1 00 File Power Loss' were received. At 2250 hours, the Control Room staff determined a loss of isolation function existed. The operators entered Technical Specification (TS) action statements for Emergency Core Cooling System Instrumentation (TS 3.3.5.1), RCIC Instrumentation (TS 3.3.5.2), and Primary Containment and Drywell Isolation Instrumentation (TS 3.3.6.1). The power loss was caused by a blown fuse which occurred during surveillance testing. The surveillance test was suspended and plant personnel commenced troubleshooting and investigation efforts. A recovery plan is being developed to back out of the surveillance test and replace the fuse to re-energize the logic, while ensuring the plant does not experience an undesirable actuation of the logic.
"The power loss caused five containment isolation valves to lose automatic isolation function. These valves have no associated inboard automatic isolation valve powered by Division 2. As a result of the power loss, the valves cannot automatically close on demand to isolate and therefore cannot perform their automatic function to isolate the containment.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(C) 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 control the release of radioactive material.
"The NRC Resident Inspectors have been notified."
The licensee entered a 12-hour shutdown action statement for the loss of containment isolation function as a result of the power failure. |
| Power Reactor | Event Number: 45816 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: ERIC FRANKE
HQ OPS Officer: DONALD NORWOOD | Notification Date: 04/07/2010
Notification Time: 00:33 [ET]
Event Date: 04/06/2010
Event Time: 17:47 [PDT]
Last Update Date: 04/07/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID PROULX (R4DO)
|
| 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 INITIATION OF TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO CONTROL ROOM EMERGENCY FILTRATION SYSTEM BEING DECLARED INOPERABLE
"At 1650 PDT Columbia Generating Station entered LCO 3.0.3 as required by LCO 3.7.3 for both divisions of Control Room Emergency Filtration (CREF) [being] inoperable. Entry into LCO 3.0.3 was required by Condition E of LCO 3.7.3, 'Two CREF subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B' and has a Required Action to enter LCO 3.0.3 with an immediate Completion Time. Columbia commenced a plant shutdown at 1747 as required by LCO 3.0.3.
"[Columbia Generating Station] entered into Condition E of LCO 3.7.3 when it was determined that Radwaste Building Outside Air Smoke Detectors WOA-SMD-1A and WOA-SMD-1B did not meet seismic qualifications. Actuation of these smoke detectors would cause Radwaste Building Mixed Air Fire Dampers WMA-FD-1 and WMA-FD-2 to close. These fire dampers shutting would cause all CREF airflow to cease, preventing the control room from achieving a positive pressure. Both divisions of CREF [being] inoperable is an unanalyzed condition requiring immediate entry into LCO 3.0.3.
"This event is reportable under 50.72(b)(2)(i) due to the initiation of a plant shutdown as required by Columbia's Technical Specifications. This event is also reportable under 50.72(b)(3)(v)(D) as an event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.
"WMA-FD-1 and WMA-FD-2 have been deactivated in the open position for the smoke actuation function. [Columbia Generating Station] entered RFOLCS (Requirements for Operability of Licensee Controlled Specifications) 1.10.6 for these fire dampers [being] nonfunctional. [Columbia Generating Station] completed the required actions of LCS 1.10.6.
"The CREF system remains inoperable pending completion of a TMR (Temporary Modification Request)."
The licensee notified the NRC Resident Inspector. | |