United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for February 22, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/21/2012 - 02/22/2012

** EVENT NUMBERS **


47667 47669 47671 47672 47674 47675 47676 47681 47682 47683

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Agreement State Event Number: 47667
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: ALLEGHENY LUDLUM CORPORATION
Region: 1
City: LATROBE State: PA
County:
License #: PA-G0010
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 02/16/2012
Notification Time: 08:01 [ET]
Event Date: 02/14/2012
Event Time: [EST]
Last Update Date: 02/16/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY POWELL (R1DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - X-RAY FLUORESCENCE ANALYZER STUCK OPEN SHUTTER

The following report was received via e-mail:

"On February 14, 2012, the operator of the handheld unit notified the Radiation Safety Officer (RSO) that he just got a 'shutter not available' message on the unit. The RSO was at a different plant and he instructed the operator to turn off the unit, remove the battery pack, place the unit in the case, and secure the unit. Upon examination on February 15, 2012, the same message was displayed when the battery was installed. The RSO performed a survey indicating 40 microR/hr at a distance of 1ft. The employee was wearing extremity dosimetry at the time of the event which has been sent for evaluation. More details will follow when available.

"The device is identified as:
Manufacturer: Thermo Niton
Model: XLp 818 [The XLp is an x-ray fluorescence (XRF) analyzer.]
Serial #: 5917
Isotope: Am-241
Activity: 30 mCi

"A local service provider has been contacted to try to close the shutter and package the device so it can be returned to the manufacturer. The RSO sent out the employee's dosimetry to be analyzed. Licensee has been made aware of the 30-day follow-up report requirement."

PA Event Report No.: PA120006

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Agreement State Event Number: 47669
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: JANX NDT/NDE
Region: 1
City: KING State: NC
County:
License #: 085-1117-2
Agreement: Y
Docket:
NRC Notified By: DIANA SULAS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/16/2012
Notification Time: 11:55 [ET]
Event Date: 02/16/2012
Event Time: [EST]
Last Update Date: 02/16/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY POWELL (R1DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - GAS EXPLOSION OF X-RAY INSPECTION TRAILER - STORED SOURCE UNAFFECTED

The following report is an edited version of information was provided by the North Carolina Radiation Protection Section via e-mail:

"On February 16, 2012 the agency [NC Radiation Protection Section] was notified of a propane tank explosion near Gastonia, NC by the corporate RSO of JANX [NDT/NDE]. This morning when workers at the job site started a generator, an explosion [occurred and] damaged an x-ray trailer at the site. The source of the explosion seems to be a leaking valve on a propane tank. The explosion 'blew off' a wall [of the trailer] and resulted in some burning. On board this trailer was a 1 Ci Ir-192 stopping source contained in a SPEC check model housing. The corporate RSO indicated that the trailer had three compartments and, from what he understood, the back-up x-ray unit onboard the trailer was damaged (Panasonic XIT) [but] the compartment in which the [Ir-192] source was stored was not damaged during the explosion. The housing of the source itself did not show any damage and all radiation levels were normal. The 1 Ci source was moved to a secured Industrial Radiography truck containing a SPEC 150 camera with 110 Ci of Ir-192 that was also on site but not damaged during the explosion. This truck has increased controls on it and was not damaged.

"Two employees have been taken to the emergency room for injuries and the local RSO is on his way to the incident (~10:30am). A NC Rad Mat Inspector was in the area and he will go and verify the report of the corporate RSO.

"The corporate RSO that will be expected [to provide] a written report within 30 days and to leak test the source to ensure that there was no damage. [The NC State x-ray staff] has been notified about the industrial radiography unit [and] they have since contacted the licensee. Since they were working under reciprocity of an NRC license, [NC will also] notify NRC Region I agreement state officer, Monica Oreindi.

"There are no radiation concerns to public health and safety at this time. The inspector was sent just for verification of the report.

"The North Carolina License Number of JANX is 085-1117-2 and physical location address is 1073 Kentland Drive in King, NC 27021. The licensee had issued a reciprocity notification using their NRC license NRC: 21-16560-01 (Reciprocal License NO. 122-0361-R) for their work at the location of the explosion. The notification listed 1441 Delta Drive, Gastonia, NC as the location for work.

"Local media is on site."

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Agreement State Event Number: 47671
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: TESTING ENGINEERS, INC.
Region: 4
City: MARTINEZ State: CA
County:
License #: 3691-07
Agreement: Y
Docket:
NRC Notified By: KENT PRENDERGAST
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/16/2012
Notification Time: 18:03 [ET]
Event Date: 02/15/2012
Event Time: [PST]
Last Update Date: 02/16/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
ADELAIDE GIANTELLI (FSME)
ILTAB via email ()
MEXICO via fax ()

This material event contains a "Category 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT INVOLVING A STOLEN MOISURE DENSITY GAUGE

The following information was received from the State of California via email:

"On 02/16/12, the RSO at Testing Engineers (TE) contacted the RHB [Radiological Health Branch] reception desk to report a stolen gauge. She reported that an employee had his truck stolen which also contained his nuclear gauge. The gauge a CPN MC1, S/N MD 20206438 containing 10 mCi of Cs-137 and 50 mCi of Am-241 was stolen yesterday (02/15/12) between 1:00 to 4:15 pm [PST] in a parking lot near the employee's residence . . . [in] Fremont, CA. The gauge was stored inside of its transportation case and placed in the back of the truck with the bed cover locked in place. The transport case was secured with a cable attached to the bed of the truck. The gauge user found the truck stolen around 4:15 pm [PST]. The incident was reported to the Fremont police at that time. The gauge user failed to notify the RSO of the stolen gauge until the following day (02/16/12) [in the] morning.

"On 02/16/12, The TE [Testing Engineers, Inc.] RSO also notified this incident to Operations Emergency Center (report # 120902) and the NRC.

"5010 Number (Date Notified): 021612"

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

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Agreement State Event Number: 47672
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: NLMK PENNSYLVANIA
Region: 1
City: FARRELL State: PA
County:
License #: PA-1074
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 02/17/2012
Notification Time: 10:20 [ET]
Event Date: 02/16/2012
Event Time: 11:00 [EST]
Last Update Date: 02/17/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY POWELL (R1DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - STUCK OPEN SHUTTER ON A METAL THICKNESS GAUGE

The following report was received via e-mail:

"On February 16, 2012, during leak testing by a consultant vendor a radioactive materials gauge shutter was discovered to be stuck open. No radiation exposure to personnel occurred.

"The device is identified as:

Manufacturer: LFE
Model: SS-3A
Serial #: 02311
Isotope: Am-241
Activity: 37 GBq (1 Ci)

"The gauge manufacturer was notified and repairs are scheduled to be conducted today.

"Event Report ID No.: PA120007"

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Agreement State Event Number: 47674
Rep Org: COLORADO DEPT OF HEALTH
Licensee: TEST AMERICA
Region: 4
City: ARVADA State: CO
County:
License #: 486-03
Agreement: Y
Docket:
NRC Notified By: EDGAR ETHINGTON
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/17/2012
Notification Time: 14:08 [ET]
Event Date: 02/16/2012
Event Time: [MST]
Last Update Date: 02/17/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT INVOLVING A FAILED LEAK TEST OF AN ECD SOURCE

The following information was received from the State of Colorado via fax:

"On February 16, 2012 Test America at 4955 Yarrow Street in Arvada, Colorado (CO License # 486-03), notified the Colorado Department of Public Health and Environment that one of their Ni-63 electron capture detectors [ECD] failed a leak test. The leak test results for Device HPU0946 exceeded the 0.005 microCurie level. The test wipe measured at 0.0062 microCurie.

"The ECD detector was immediately withdrawn from service and the instrument in which the ECD was located was decontaminated by cleaning with Radiac Wash solution. A direct beta survey was then performed which showed no residual contamination present on the instrument or ECD. ECD No. HPU0946 was sent to the manufacturer for repair."

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Agreement State Event Number: 47675
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: SUNOCO PHILADELPHIA REFINERY
Region: 1
City: PHILADELPHIA State: PA
County:
License #: PA-0853
Agreement: Y
Docket:
NRC Notified By: DAVID J. ALLARD
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/17/2012
Notification Time: 14:11 [ET]
Event Date: 01/18/2012
Event Time: [EST]
Last Update Date: 02/17/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY POWELL (R1DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT INVOLVING SHUTTER TEST FAILURES ON FIXED GAUGES

The following information was received from the State of Pennsylvania via fax:

"Notifications: On Wednesday February 15, 2012, the licensee left a voice message to the Central Office and followed with a phone conversation on February 16th regarding an event that took place on January 18, 2012. Additional information was then sent to Central Office via email on Friday, February 17, 2012. This event is reportable within 24-hours under 10CFR30.50(b)(2).

"Event Description: Shutter test failures occurred on 3 fixed gauge devices at the Sunoco Philadelphia Refinery. Air actuators are used as the primary testing means to close the shutters. All three actuators failed to close the shutters on the devices and the instrument technicians were unable to manually close the shutters. The instrument technician foreman was unaware of any reporting requirements to the State and did not communicate this event to the Radiation Safety Officer (RSO) until February 14, 2012.

"The 3 devices are identified as:

Manufacturer: Ohmart Vega
Model: SH-F1
Serial #: OVO125; OVO129; OVO131
Isotope: Cs-137
Activity: 10 mCi (each)

"CAUSE OF THE EVENT: Air actuator malfunction

"ACTIONS: The manufacturer has been contacted and the parts have been ordered to repair the shutter mechanisms. The RSO reported that the failures of the shutter mechanism do not pose any additional threat to employee safety, and surveys in the area indicate readings of <0.5 mR/hr at 1 foot from the source. The Department plans to do a reactive inspection.

"Media attention: None at this time

"Event Report ID No.: PA120008"

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Agreement State Event Number: 47676
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: METCO
Region: 4
City: HOUSTON State: TX
County:
License #: 03018
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/17/2012
Notification Time: 16:21 [ET]
Event Date: 02/17/2012
Event Time: [CST]
Last Update Date: 02/17/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
ADELAIDE GIANTELLI (FSME)
ANGELA MCINTOSH (FSME)
CINDY JONES (NSIR)

Event Text

AGREEMENT STATE REPORT INVOLVING POTENTIAL RADIOGRAPHER OVEREXPOSURE

The following information was received from the State of Texas via email:

"On February 17, 2011, the Agency [State of Texas] was notified by the licensee of an overexposure event involving one of their radiographers. The radiographer was working in a shooting bay at the licensee's facility using a QSA D880 radiography camera serial number D7293 containing a 37 curie iridium 192 source. The radiographer entered the shooting bay to setup for their next shoot. They stated that they carried their dose rate meter with them but did not pay attention to the reading. The radiographer completed the setup and left the shooting bay. The radiographer attempted to crank the source out, but discovered that the source was already cranked fully out. The radiographer cranked the source back to the fully shielded position and notified their Radiation Safety Officer (RSO) of the event. The RSO questioned the radiographer and found that the radiographer had spent approximately 3 minutes within 10 inches of the source, and about 3 minutes at 3 feet from the source during the setup. Initial calculations by the licensee indicated that the radiographer may have received as much as 20 rem TEDE from the event. The RSO stated that the radiographer did not have to relocate the source to perform the shot so they do not believe there is any extremity dose involved. The RSO also stated that the electrical breaker that supplied power to the shooting bay had been opened therefore the alarm did not function. The RSO stated that they were going to review security video to determine who opened the breaker. The radiographer has been removed from all work involving exposure to radiation and their personal monitoring device will be sent to the licensee's processor. The Agency provided contact information for the Radiation Emergency Assistance Center/Training Site to the RSO. Additional information will be provided as it is received in accordance with SA-300.

"Texas Incident #: I-8934"

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Power Reactor Event Number: 47681
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: CHERIE SONODA
HQ OPS Officer: JOHN KNOKE
Notification Date: 02/21/2012
Notification Time: 11:38 [ET]
Event Date: 02/21/2012
Event Time: 00:55 [PST]
Last Update Date: 02/21/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RICK DEESE (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

DATA PROCESSING NETWORK FAILURE IMPACTED EMERGENCY RESPONSE DATA SYSTEM

"At 0055 PST on 2/21/12, it was discovered that portions of the data processing network (eDNA) had failed. This failure resulted in the Emergency Response Data System (ERDS) entering a mode of operation that caused an interruption of the ability of the ERDS transmission capabilities. At approximately 0213 PST on 2/21/12, actions were taken and all transmission capabilities were restored. The total outage time was determined to be 78 minutes. During the period that ERDS was not available, backup communications were available,

"This is determined to be a partial, but major loss of emergency assessment capability, and is reportable under 10 CFR 50,72(b)(3)(xiii) as 'Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portions of control room indication, Emergency Notification System, or offsite notification system)'."

"The cause of the data processing network (eDNA) and ERDS failure is under investigation."

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 47682
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DON TAYLOR
HQ OPS Officer: PETE SNYDER
Notification Date: 02/21/2012
Notification Time: 13:57 [ET]
Event Date: 02/21/2012
Event Time: 13:45 [EST]
Last Update Date: 02/21/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MIKE ERNSTES (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 Y 100 Power Operation 100 Power Operation

Event Text

TRITIUM IDENTIFIED ONSITE ABOVE THE VOLUNTARY REPORTING THRESHOLD

"On February 17, 2012, North Anna Power Station (NAPS) was notified by its vendor laboratory that a water sample, taken from an onsite ground water sample point, was confirmed to contain tritium above the voluntary reporting threshold of 20,000 picocuries per liter(pCi/L). The water sample, measuring 53,300 pCi/L, was obtained as a part of ongoing activities to determine the source of tritium previously reported to the state and NRC on October 29, 2010 (Event Notification - 46377). Current hydrological studies have determined the ground water in the area migrates to the station power block which is in the opposite direction from the lake. The ground water at the power block is collected in building subsurface drains and transported to a clarifier for processing. Clarifier discharge is accounted for as a monitored liquid effluent release pathway under the radiological effluent control program in accordance with the station's Offsite Dose Calculation Manual. As such, there is no increase to the projected annual dose to a member of the public. There are also no sources of drinking water in this area. Sampling of eight (8) ground water sample points outside the station protected area show no detectable levels of tritium confirming there is no migration offsite.

"The NRC Resident Inspector has been notified. A 30 day written report will be submitted to the NRC in accordance with NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document."

The licensee will inform both state and local agencies.

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Power Reactor Event Number: 47683
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: WAYNE EPPEN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/22/2012
Notification Time: 01:55 [ET]
Event Date: 02/21/2012
Event Time: 23:42 [CST]
Last Update Date: 02/22/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
PATTY PELKE (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 11 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO FEEDWATER HEATER HI HI ALARM

"During a normal shutdown in preparation for refueling outage 2R27, with Unit 2 at approximately 11.42% power, Unit 2 was manually tripped on 2/21/2012 at 2342 CST. The manual reactor trip was in response to a 21/22/23 Feedwater Heater Hi Hi alarm and was directed by the alarm response. Procedure 2E-0, 'Reactor Trip or Safety Injection,' was completed at 2345 CST. No Safety Injection was required. 2ES-0.1, 'Reactor Trip Recovery,' is in progress. Offsite power remains on all safeguards buses for both units. Unit 2 decay heat is via forced circulation and condenser steam dump with main feedwater providing flow to 21/22 steam generators. Auxiliary Feedwater start was not required and Unit 2 AFW remains in its safeguards alignment. No emergency event was declared as a result of this trip. Unit 1 remains at 100% power in Mode 1. Reportable actuations are: Unit 2 reactor protection (scram). The NRC resident was notified. State [State of Minnesota] / local [Goodhue county] / Press release will be made. Other government agencies will not be notified. Nothing unusual / not understood. Unit 2 will continue to mode 5."

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012