United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for September 13, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/12/2012 - 09/13/2012

** EVENT NUMBERS **


47768 48125 48271 48272 48273 48275 48296 48300 48301

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Agreement State Event Number: 47768
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: NON-DESTRUCTIVE INSPECTION CORPORATION
Region: 4
City: LAKE JACKSON State: TX
County:
License #:
Agreement: Y
Docket: L02712
NRC Notified By: ROBERT FREE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/25/2012
Notification Time: 09:20 [ET]
Event Date: 03/24/2012
Event Time: 16:00 [CDT]
Last Update Date: 09/12/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - OVEREXPOSURE TO RADIOGRAPHER WHEN CAMERA SOURCE BECAME DISCONNECTED

The following information was received by facsimile:

"On March 24, 2012, the licensee notified the Agency that it one of its radiography teams had experienced a disconnect of a 65 curie iridium-192 on a QSA Delta 880 radiography camera at a temporary work site in Pasadena, Texas. The crank out drive cable had broken and the source had completely disconnected. After an authorized individual performed the source retrieval, the licensee's RSO learned that the radiographer trainer disconnected the source tube from the camera and had carried the source tube around his neck while he climbed down the ladder of the scaffold. The source was in the tube at this time, but it is uncertain at this time the source's location within the tube. When the radiographer trainer reached the platform he removed the source tube from his neck. The licensee's initial dose estimates for the radiographer trainer are a whole body dose of at least 56 rem and an extremity limit that may exceed 100 rem. The radiographer's film badge is being sent for immediate reading. The licensee is conducting an investigation.

"NOTE: During the licensee's initial phone call to the Agency, the Agency understood the whole body dose estimate to be 6 rem and considered the event to be a 24-hour report (the Agency did report to the NRC HOO within 24 hours). However, when the Agency received the written initial report this morning, March 26, 2012, it was discovered that the estimate is 56 rem, which requires immediate notification. This report is being submitted to update and upgrade the event. More information will be provided as it is obtained.

The State also corrected the source strength to 65 curie Ir-192 source. REAC/TS was notified on 03/26/12 and the licensee has made contact with them.

Texas Incident: I-8942

* * * UPDATE FROM KAREN BLANCHARD TO CHARLES TEAL ON 3/29/12 AT 1712 EDT * * *

"The radiographer's badge was processed on March 28, 2012. The badge reading was 812 mrem whole body (deep dose equivalent). Dose reconstruction continues as the investigation continues. More information will be provided as it is obtained."

Notified R4DO (Farnholtz) and FSME (McKenney).

* * * UPDATE AT 1414 EDT ON 09/12/12 FROM KAREN BLANCHARD TO S. SANDIN * * *

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

"Investigation of the event provided the following information. The radiographer stated he had performed a survey of the camera and source guide tube prior to disconnecting it. He stated he observed normal readings, including approximately 20 mr/hr at the camera. He lowered the camera and drive cable assembly down to the radiographer trainee who was working with him. After climbing down the ladder and removing the source guide tube from around his neck, the radiographer walked over to assist the trainee who was having trouble disconnecting the drive cable assembly. The radiographer stated he saw that the camera was not locked and was still in the red position. The radiographer stated he again surveyed the camera and then the source guide tube and got high readings at the end of the source guide tube. Sometime between the time the radiographer began attempting to disconnect the drive cable assembly and the time he surveyed the guide tube, both of their alarming rate meters (ARM) began alarming. They both moved back and notified the licensee's Radiation Safety Officer (RSO) of the apparent disconnect. The radiographer then used a pair of 3-foot long tongs to lift the guide tube from the collimator end. As he lifted the tube, the source fell out onto the floor. He again moved back, re-established a 2 mr/hr boundary, and waited on the RSO. The RSO arrived on-site as did an individual authorized to perform source retrieval. The source was then properly retrieved and secured. The RSO checked ARMs and the survey meter and all were working properly at that time.

"The camera, drive cable assembly, and source guide tube were sent to the manufacturer for evaluation. The manufacturer reported that . . . 'the cable was severed directly behind the 550 connector. The male connector passed the no go gauge but is heavily worn . . . The cable is corroded/rusted and stiff at the broken area and was dry of any lubricant grease . . . the control pistol assembly components showed significant signs of rusting and the control housings were taped to allow continued use . . . there are no indications of improper manufacture or defect in the Teleflex drive cable . . . Based on this evaluation, the drive cable failed due to a combination of wear, corrosion and lack of lubrication indicative of improper maintenance.' The radiographer stated he did not check the condition of the crank out drive cable prior to using it (as required) even though he initialed the daily work sheet indicating he had completed his daily equipment check.

"The survey meter and ARMs were sent to the manufacturer for evaluation. All were within the calibration date and all were operating properly. The ARMs began alarming at 400 mr/hr when they were checked.

"The radiographer was wearing his dosimetry badge on his right chest pocket. It was sent for immediate processing following the incident. The badge reading was 812 mrem. The licensee performed dose assessment calculations for the event and assigned an estimated dose of 29.32 rem for this event.

"Key issues identified:

1. Failure to perform proper survey.
2. Failure of licensee to properly inspect and maintain equipment (specifically the drive cable in this instance).
3. Failure of radiographer to perform daily equipment inspections and remove from service components in need of maintenance.
4. Failure to ensure camera is in locked position after cranking source into camera and before proceeding."

Notified R4DO (Lantz) and FSME via email.

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Power Reactor Event Number: 48125
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: ROBERT SALES
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/23/2012
Notification Time: 04:24 [ET]
Event Date: 07/23/2012
Event Time: 03:29 [EDT]
Last Update Date: 09/12/2012
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
HO NIEH (NRR)
WILLIAM GOTT (IRD)
BILL DEAN (R1RA)
BRUCE BOGER (NRR)
HASSEL (DHS)
GUERRA (FEMA)
GAMBINO (NICC)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

UNUSUAL EVENT DUE TO LOSS OF OFFSITE POWER

At 0329 EDT, Oyster Creek experienced a loss of offsite power. As a result of the loss of offsite power, the unit automatically scrammed from 100% with all control rods fully inserting and all safety systems functioning as required. Both Emergency Diesel Generators automatically started and are carrying loads on the safety buses.

At 0341 EDT, Oyster Creek declared an Unusual Event based on a loss of offsite power for greater than 15 minutes. The unit is stable in Hot Shutdown with decay heat removal via the Isolation Condenser. The cause of the loss of offsite power is currently under investigation by JCP&L.

The licensee notified the State and local agencies, as well as the NRC Resident Inspector. The licensee will be making a press release.

* * * UPDATE ON 7/23/12 AT 0625 EDT FROM ROBERT SALES TO DONG PARK * * *

"Oyster Creek has terminated from the loss of offsite power Unusual Event [at 0538 EDT]. All safety systems functioned as expected for this event."

The licensee has notified the NRC Resident Inspector.

Notified R1DO (Dimitriadis), NRR EO (Nieh), IRD (Gott), DHS SWO, FEMA, and DHS NICC.

* * * UPDATE ON 7/23/12 AT 1205 EDT FROM ANDREW ZUCHOWSKI TO VINCE KLCO * * *

"As a result of the loss of offsite power, both Emergency Diesel Generators automatically started and carried loads on the safety buses, as required. Offsite power was returned to service at 0457 EDT and both Emergency Diesel Generators were secured at 0520 EDT.

"Per 50.72(b)(3)(iv)(A), Oyster Creek is reporting any event or condition that results in valid actuation of an Emergency AC electrical power system.

"Additionally, the Reactor Building (Secondary Containment) differential pressure indicated positive 0.25 inches W.G. at approximately 0357 EDT. Reactor Building differential pressure indication returned to normal at 0434 EDT. Oyster Creek is currently investigating the cause of the positive Reactor Building pressure indication.

"Per 50.72(b)(3)(v)(C), Oyster Creek is reporting an event that could have prevented the fulfillment of the safety function of a system needed to control the release of radioactive material."

The licensee notified the NRC Resident Inspector.

Notified R1DO (Gray).

* * * UPDATE AT 0914 EDT ON 9/12/12 FROM ERIC SWAIN TO HUFFMAN * * *

As a result of further investigation it was found that the Reactor Building Differential Pressure issue was an indication issue only and not indicative of a loss of the secondary containment barrier. The positive indication was caused by a degradation of instrument air pressure to the instrument used to generate the differential pressure indication. The degradation of instrument air pressure was an expected condition caused by the loss of offsite power. Alternate indication, not affected by instrument air pressure, was available throughout the event. The alternate indication read negative 0.4 Inches water gauge throughout the event.

Based on this information Oyster Creek is retracting the portion of this report that was reported per 50.72(b)(3)(v)(C), an event that could have prevented the fulfillment of the safety function of a system needed to control the release of radioactive material.

The licensee has notified the NRC Resident Inspector. R1DO (Newport) notified.

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Agreement State Event Number: 48271
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: REYNOLDS, SMITH, AND HILLS C.S.
Region: 1
City: ORLANDO State: FL
County:
License #: 2732-2
Agreement: Y
Docket:
NRC Notified By: STEVE L. FURNACE
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/04/2012
Notification Time: 09:49 [ET]
Event Date: 09/01/2012
Event Time: [EDT]
Last Update Date: 09/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICHARD CONTE (R1DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE

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

The State of Florida was notified by the licensee that one of their Troxler moisture density gauges has been stolen. The theft is believed to have occurred on the night of September 1st, 2012. The gauge was properly stored in a secure storage shed when the theft occurred. The licensee has notified the manufacturer and local law enforcement and will be offering a reward for its recovery. The State of Florida will investigate.

Gauge Information: Troxler Model 3440, Serial # 14471
Sources: Americium-241/Beryllium, 40 millicuries
Cesium-137, 8 millicuries

Florida Incident #: FL12-065

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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Non-Agreement State Event Number: 48272
Rep Org: PPG INDUSTRIES INC.
Licensee: PPG INDUSTRIES INC.
Region: 1
City: NEW MARTINSVILLE State: WV
County:
License #: GL
Agreement: N
Docket:
NRC Notified By: ERIKA BALDAUFF
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/04/2012
Notification Time: 14:10 [ET]
Event Date: 09/01/2012
Event Time: 18:45 [EDT]
Last Update Date: 09/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(4) - FIRE/EXPLOSION
Person (Organization):
RICHARD CONTE (R1DO)
FSME EVENT RESOURCE (EMAI)

Event Text

TWO TRITIUM EXIT SIGNS DESTROYED IN WAREHOUSE FIRE

"At approximately 6:45 pm on 9-1-12, there was a fire in two warehouses at the PPG Industries, Inc. Natrium Plant located in New Martinsville, WV. The warehouses are storage areas for product, where personnel are usually not stationed. The facility does have a specific license from the NRC. However, the mentioned signs are not covered under the license. They are generally licensed.

"Two tritium exit signs, one in each warehouse, were destroyed in the fire. The signs were:

- manufactured by Self-Powered Lighting, LTD.
- Model No. CPI-700
- Activity on the manufacture date of 2-1983 was 12.5 Curies
- Decay corrected activity on 9-1-2012 was calculated to be 2.4 Curies

The area around the former location of the signs is barricaded off. This afternoon an outside contractor performed testing to determine if there is tritium contamination. The area will remain barricaded off until results are received.

"A follow-up report will be submitted within 30 days."

* * * UPDATE AT 1210 EDT ON 9/5/12 FROM BALDAUFF TO HUFFMAN * * *

Sampling has been completed and analyzed to determine if any contamination was present from the destroyed tritium exit signs. The results verify that there is no contamination present.

R1DO (Conte) notified. FSME Events Resource e-mailed.

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Agreement State Event Number: 48273
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: ACUREN INSPECTION, INC
Region: 3
City: DAYTON State: OH
County:
License #: 03320990006
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/04/2012
Notification Time: 15:01 [ET]
Event Date: 07/24/2012
Event Time: [EDT]
Last Update Date: 09/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
KENNETH RIEMER (R3DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA SOURCE DISCONNECT

The following information was provided by the Ohio Bureau of Radiation Protection via e-mail:

"Licensee experienced a source disconnect with an industrial radiography camera. The radiographers were working at a temporary job site and attempted to retrieve source after completing the first exposure of the workday. Source would not retrieve and a source disconnect was suspected, with the source remaining at the exposure end of the guide tube. The source position was verified by on-site radiation surveys. The guide tube (containing the source at the far end) was disconnected from the camera and moved to an isolated location at the client site. The radiographers established appropriate barriers and entry controls for the temporary area and maintained constant surveillance until licensee's source retrieval personnel arrived. Retrieval personnel were able to reconnect the source using a special tool and the source was able to be retracted back into the camera. The camera and all associated equipment were sent to the manufacturer for evaluation. Cause of the problem was determined to be a worn connecting collar around the plug assembly and failure to follow a source connect procedure recommended by the manufacturer. Ohio Bureau of Radiation Protection will visit site and conduct an investigation.

"The licensee's report was received at Ohio Bureau of Radiation Protection today, 9/4/12, at approximately 1240 EDT.

"Based on manufacturer's evaluation of the equipment used, Ohio Bureau of Radiation Protection will conduct an investigation of licensee's maintenance program and to determine reasons for failure by licensee to make initial notification and follow-up written report in a timely manner."

No significant personnel exposure was received during retrieval procedures.

Ohio Report OH 120003

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Agreement State Event Number: 48275
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: WEATHERFORD ARTIFICIAL LIFT SYSTEM
Region: 4
City: HOUSTON State: TX
County:
License #: G02201
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/04/2012
Notification Time: 17:55 [ET]
Event Date: 09/01/2012
Event Time: [CDT]
Last Update Date: 09/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4DO)
FSME EVENT RESOUCE (EMAI)

Event Text

AGREEMENT STATE REPORT - DAMAGED PROCESS GAUGE SHUTTER

The Texas Department of State Health Services Radiation Branch provided the following report via e-mail:

"On September 4, 2012, the Agency [Texas Department of Health] was notified by the licensee that the shutter on an Ohmart / Vega nuclear gauge model SHLD-1 containing a 20 millicurie cesium - 137 source had been damaged and no longer functioned as designed. The licensee stated that the gauge is mounted on the side of a truck trailer. The licensee stated that the gauge operator had tried to close the gauge shutter and could not get the shutter to move. The operator obtained a hammer and struck the shutter mechanism. The four bolts holding the shutter mechanism in place snapped and the shutter fell off the gauge. The operator placed the shutter back on the gauge to provide shielding, but the shutter is not attached to the gauge housing. The gauge is at the licensee's facility isolated inside of a locked fence. A barrier has been placed around the gauge to prevent inadvertent entry to the area around the gauge. The licensee has contacted the manufacturer to repair the gauge. The licensee stated that the gauge does not present an exposure hazard to any individual. Additional information will be provided as it is received in accordance with SA 300: 'Reporting Material Events'."

Texas Incident # I-8984

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Power Reactor Event Number: 48296
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: HANS OLSON
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/11/2012
Notification Time: 04:08 [ET]
Event Date: 09/11/2012
Event Time: 03:08 [CDT]
Last Update Date: 09/12/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN GIESSNER (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 94 Power Operation 94 Power Operation

Event Text

TECHNICAL SUPPORT CENTER NON-FUNCTIONAL DUE TO PLANNED MAINTENANCE

"A planned maintenance evolution at the Duane Arnold Energy Center (DAEC) will remove the TSC [Technical Support Center] ventilation system from service. The TSC would be rendered non-functional with the loss of ventilation. The repair to the TSC ventilation is expected to last 3 days.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. Maintenance will be expedited to restore ventilation to the TSC.

"This notification is being made in accordance with 10CR50.72(b)(3)(xiii) due to the loss of an Emergency Response Facility (ERF). An update will be provided once the TSC ventilation system has been restored to normal operation."

The licensee notified the NRC Resident Inspector

* * * UPDATE FROM MIKE STROPE TO CHARLES TEAL ON 9/12/12 AT 1157 EDT * * *

The TSC maintenance has been completed. The TSC has been restored to service.

The NRC Resident Inspector has been informed.

Notified R3DO (Kunowski).

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Agreement State Event Number: 48300
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: HALLIBURTON
Region: 4
City: HOUSTON State: TX
County:
License #: 02113
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/12/2012
Notification Time: 08:37 [ET]
Event Date: 09/11/2012
Event Time: 21:00 [CDT]
Last Update Date: 09/12/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RYAN LANTZ (R4DO)
BRIAN MCDERMOTT (FSME)
JANE MARSHALL (IRD)
MEXICO (E-MA)
JIM WHITNEY (ILTA)
DEBORAH HASSEL (DHS)
FSME EVENTS RESOURCE (E-MA)

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

Event Text

AGREEMENT STATE REPORT - LOST AM-241/BE WELL LOGGING SOURCE

The following information was obtained from the Texas Department of State Health Services Radiation Branch via e-mail:

"On September 11, 2012, the Agency [Texas Department of State Health Services] was notified by the licensee that an Americium-241/ Beryllium [well logging] source could not be located. The source had been used earlier that day at a well site near Pecos, Texas. The well logging crew left the Pecos site and went about 130 miles to a well site south of Odessa, Texas. When the crew went to remove the Am-241 source they discovered the source transport container lock and plug were not in place and that the source was missing. The crew returned to the well site near Pecos and searched for the source, but did not find it. The Radiation Safety Officer (RSO) stated that the lock was found in the storage compartment in the back of the truck. The transport container plug was not in the container. The RSO stated they were putting together a group to look for the source along the roadway between the two locations.

"The RSO stated that the crew stated that they did not stop anywhere along the route between the two locations. The RSO stated they were verifying that using the vehicles black box. The RSO agreed to contact the appropriate local law enforcement. The RSO stated he would send a copy of the latest dose rate readings for the source to the Agency.

"The Agency has notified their local inspectors of the event. Additional information will be provided as it is received in accordance with SA-300 [Reporting Material Events]."

The source was described as approximately 7 inches long by 1 inch in diameter stainless steel cylinder. The State has not requested any assistance in locating the source at this time.

Texas Report I-8988

* * * UPDATE AT 1744 EDT ON 09/12/12 FROM ART TUCKER TO S. SANDIN * * *

The following update was received from the State of Texas via fax:

"[At] 1430 hours [CDT] the Agency [Texas Department of State Health Services] was contacted by the licensee and provided the following information.

"The licensee has completed a press release which provides a description of the source, actions to take if found, and stated that they would offer a reward. The press release will be issued by their Public Information Group. The licensee has completed logging of the well near Pecos and the source was not located.

"The licensee stated that the well site had been searched and surveyed twice. The licensee stated that the road between Pecos and Odessa had been surveyed using well logging tools extended from pickup trucks and driven between 5 and 10 miles per hour and the source was not found. The licensee stated they have had people on the ground searching, but did not know how much area away from the well site in Pecos had been searched.

"The licensee has sent a Radiation Safety Officer and a second supervisor to the Pecos well site. The RSO is bringing scintillation survey instruments to the well site for additional surveys. An Agency inspector will meet the RSO at the well site.

"The licensee has reviewed the well logging data and confirmed that the source was installed on the tool during logging operations. The licensee has performed preliminary interviews with the operator involved. The licensee indicated that additional interviews are required. They have not been able to determine how the source could have been lost during transport. The licensee stated that they completed a review of the truck's black box and confirmed that the truck did not stop while traveling between the two well sites.

"The license stated that the local sheriff has responded to the Pecos location and was interviewing the tool operators. The licensee stated they believe that the group supervisor involved had been evaluated under the IC's [Increased Controls] as trust worthy and reliable.

"The licensee stated that other entities at the well site as well as the lease holder have been notified of the event. The licensee stated that they will continue to search for the source until it can be located. The Agency has offered their assistance to the licensee. Additional information will be provided as it is received in accordance with SA - 300 [Reporting Material Events]."

Notified R4DO (Lantz) and FSME (McDermott), IRD (Marshall), ILTAB (Whitney) and Mexico via email/fax.

THIS MATERIAL EVENT CONTAINS A "CATEGORY 3" LEVEL OF RADIOACTIVE MATERIAL

Category 3 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for some hours. It could possibly - although it is unlikely - be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in practices such as fixed industrial gauges involving high activity sources (for example: level gauges, dredger gauges, conveyor gauges and spinning pipe gauges) and well logging. 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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Power Reactor Event Number: 48301
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: CURTIS MARTIN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/12/2012
Notification Time: 09:33 [ET]
Event Date: 09/12/2012
Event Time: 08:06 [CDT]
Last Update Date: 09/12/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RYAN LANTZ (R4DO)

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

TECHNICAL SUPPORT CENTER OUT OF SERVICE FOR PLANNED MAINTENANCE

"A planned maintenance activity at Cooper Nuclear Station will remove the TSC [Technical Support Center] ventilation system from service. The TSC ventilation system will be rendered non-functional during this maintenance period. The repair to the TSC ventilation is expected to last less than 2 days.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless uninhabitable due to ambient temperature, radiological, or other conditions. CNS Station procedures provide appropriate monitoring and compensatory measures to ensure habitability of the TSC and, if necessary, instructions for relocation of TSC personnel should the need arise. In the event of TSC activation, maintenance will be expedited to restore ventilation to service.

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the loss of an Emergency Response Facility (ERF). An update will be provided once the TSC ventilation system has been restored to normal operation.

"The licensee notified the NRC Resident Inspector."

Page Last Reviewed/Updated Thursday, September 13, 2012
Thursday, September 13, 2012