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Event Notification Report for July 30, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/27/2007 - 07/30/2007

** EVENT NUMBERS **


43497 43514 43516 43519 43521 43527 43529 43531 43533 43534

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General Information or Other Event Number: 43497
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: TERRACON CONSULTANTS, INC.
Region: 4
City: TUSCON State: AZ
County:
License #: AZ 10-130
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: JASON KOZAL
Notification Date: 07/17/2007
Notification Time: 14:26 [ET]
Event Date: 07/17/2007
Event Time: 09:00 [MST]
Last Update Date: 07/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG PICK (R4)
SANDRA WASTLER (FSME)
MEXICO (E-MAIL) ()
ILTAB (E-MAIL) ()

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

Event Text

AGREEMENT STATE REPORT - LOST MOISTURE DENSITY GAUGE

The State provided the following information via email:

"At approximately 9:00 AM July 17, 2007, the Agency was informed that the Licensee had a gauge in a pickup truck traveling north from 67 Avenue and Lower Buckeye to I-10 noticed at the I-10 ramp the gauge was missing. He began the trip at approximately 7:00 AM. The Gauge case was secured in the truck as required. He did not put the gauge in the case however. The gauge is a Troxler Model 3430, Serial Number 39005 and contains 8 mCi of Cesium-137 and 40 mCi Am:Be-241. The Company plans a press release and will offer a reward for the gauge.

"Phoenix PD is investigating.

"The Agency continues to investigate this event.

"The states of CA, NV, CO, UT, and NM and Mexico and U.S. NRC and FBI are being notified of this event."

Arizona report number: 07-010

* * * UPDATE PROVIDED BY AUBREY V. GODWIN TO JASON KOZAL ON 07/27/07 AT 1306 EDT * * *

"The gauge has been recovered. It was found by a street sweeper. It was not opened and no radiation exposures appear to have occurred.

"The states of CA, NV, CO, UT, and NM and Mexico and U.S. NRC and FBI are being notified of this event."

Notified the R4DO (Smith), FSME (Thorp), ILTAB (via e-mail) , Mexico (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.

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General Information or Other Event Number: 43514
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: FRED WEBER, INC.
Region: 3
City: EAST ST. LOUIS State: IL
County:
License #: IL-02260-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/24/2007
Notification Time: 09:57 [ET]
Event Date: 07/21/2007
Event Time: 05:00 [CDT]
Last Update Date: 07/24/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICHARD SKOKOWSKI (R3)
SCOTT MOORE (FSME)

Event Text

AGREEMENT STATE REPORT INVOLVING EQUIPMENT DAMAGE DUE TO A VEHICLE ACCIDENT

The following information was provided via email:

"At approximately 5:00 AM on Saturday morning the Division's Radiological Duty Officer (RDO) was notified by the Illinois Emergency Management Agency Communications Center that a nuclear gauge was involved in a vehicular accident at the 3rd Street on-ramp at I-70 (E) in East St. Louis, Illinois. The RDO then contacted the responsible licensee, Fred Weber, Inc., and talked to [DELETED], the licensee's Radiation Safety Officer, who was at the scene.

"The RSO reported that the portable gauge had been struck at high speed by a car which had crossed into the marked and barricaded construction zone on the entrance ramp to the interstate. As a result the gauge had been destroyed into many parts. One of those parts, the source rod containing Cs-137 in a special form capsule had become separated from the gauge and its shielded housing. Using a hand held Geiger counter, [the RSO] performed wipe tests on the gauge base containing the Am-241 source and the Cs-137 source rod and found no removable gross contamination. [The RSO] had also contacted the manufacturer, Troxler for assistance and instruction in resolving the scene.

"After discussion with the Agency's RDO, [the RSO] was able to place the source rod in its original shielding and secure the rod into the shielding with tape. He then placed the base of the gauge and the source rod, with the shielding, in its Type 'A' transport case and filled any voids with sand to provide additional shielding and stabilization. Radiation readings taken by [the RSO] from the side of the case exhibited normal levels.

"The RDO then contacted the St. Clair County Emergency Services [DELETED]. [DELETED] of the Hazardous Materials unit were enroute to the scene at the time of that call. When they arrived, they performed confirmatory radiation surveys with their radiation instrumentation and noted no contamination on the roadway. Radiation levels of the transport case were also determined to be at normal levels. Surveys of [the RSO] noted no contamination. [The RSO] transported the gauge back to their storage site in Maryland Heights, MO. Arrangements were made for [the RSO] to contact the gauge manufacturer for further instructions with regards to returning the device for repair/disposal.

"[The RSO] confirmed he would send the required written report as well as notify the U.S. Nuclear Regulatory Commission as the firm is also an NRC licensee. Pending receipt of that report and successful disposition of the damaged gauge, this item remains open. This event was reported to the U.S. NRC Operations Center on July 24 and assigned event number 43514.

"Corrective Actions:

Action Number: 1
Corrective Action: EQUIPMENT RETURNED TO MANUFACTURER FOR REPAIR OR DISPOSAL

"Keywords: DEVICE INVOLVED IN ACCIDENT

"Source of Radiation:

Source Number: 1
Form of Radioactive - SEALED SOURCE
Source Use: PORTABLE GAUGE
Manufacturer: AMERSHAM
Model Number:
Serial Number:77-5535
Radionuclide or Voltage (kVp/MeV): CS-137
Activity: 0.008 Ci or 0.296 GBq
Problem with Source: NONE

Source Number: 2
Form of Radioactive SEALED SOURCE
Source Use: PORTABLE GAUGE
Manufacturer: AMERSHAM
Model Number:
Serial Number: 78-2987
Radionuclide or Voltage (kVp/MeV): AM-BE
Activity: 0.040 Ci or 1.48 GBq
Problem with Source: NONE

"Device/Associated Equipment:

Device Number: 1
Device Name: PORTABLE GAUGE
Manufacturer: TROXLER
Model Number: 3440
Serial Number: 38181
Problem with Equipment: SHIELDING COMPROMISED

"Reporting Requirements:

Reporting Requirement: 32 IAC 340.1220(c)(2) - The Licensee shall notify the Division within 24 hours in the event equipment is disabled or fails to function as designated.
Mode Reported: Telephone"

The licensee whose principal business location is in Maryland Heights, MO is also licensed and maintains storage locations in Illinois due to the volume of work performed in that state.

Illinois Report ID: IL070041

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Hospital Event Number: 43516
Rep Org: LESTER COX MEDICAL CENTER
Licensee: LESTER COX MEDICAL CENTER
Region: 3
City: SPRINGFIELD State: MO
County:
License #: 24-01143-06
Agreement: N
Docket:
NRC Notified By: JOHN PACYNIAK
HQ OPS Officer: JASON KOZAL
Notification Date: 07/24/2007
Notification Time: 14:15 [ET]
Event Date: 07/24/2007
Event Time: 10:00 [CDT]
Last Update Date: 07/24/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
RICHARD SKOKOWSKI (R3)
CINDY FLANNERY (FSME)

Event Text

MEDICAL EVENT - ADMINISTERED DOSE LESS THAN PRESCRIBED DOSE

The treatment consisted of 3 fractionated high dose rate (HDR) brachytherapy procedures. The dose was prescribed by the physician at 5 millimeters from the surface of the cylinder, however, the dose was calculated at the surface of the cylinder. The HDR brachytherapy was administered at 5 millimeters as prescribed. Due to the discrepancy between the prescribed and calculated dose an under dose of the patient of over 4 Grays (Gy) resulted. The prescription was for an administration of 15 Gy. Only 10.3 Gy was administered. The physician is planning to add one more fraction to complete the intended treatment of 15 Gy. The patient will be informed of this misadministration.

The licensee indicated that they will verify the prescription and the film prior to administration to insure consistency between the two. Additionally, when the dose distribution is plotted, the licensee will overlay the cylinder over the dose distribution to visually verify the dose.

A "Medical Event" may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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General Information or Other Event Number: 43519
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: TEAM INDUSTRIAL
Region: 4
City: TULSA State: OK
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MIKE BRODERICK
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/25/2007
Notification Time: 06:52 [ET]
Event Date: 07/25/2007
Event Time: 04:30 [CDT]
Last Update Date: 07/25/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
LINDA SMITH (R4)
CINDY FLANNERY (FSME)
RANDY ERICKSON (R4)

Event Text

SOURCE STUCK OUTSIDE OF RADIOGRAPHY CAMERA

Team Industrial was performing radiography at the Sinclair Refinery in Tulsa, Oklahoma approximately 25 feet above the ground. During the exposure, the camera fell approximately 3-4 feet onto scaffolding. The fall damaged the ball joint connecting the source to the retraction wire i.e. the source will not retract. The RSO has contacted their corporate office and is contracting with a source retrieval company. The area has been secured and cordoned off. Inability to enter this area does not affect continued refinery operation. The radiography technician received a dose of 40 mR during this incident.

Source: 27 Ci Ir-192
Camera: Amersham 880D

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General Information or Other Event Number: 43521
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: SAVOY TECHNICAL SERVICES
Region: 4
City: SULPHUR State: LA
County:
License #: LA-11235-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: JASON KOZAL
Notification Date: 07/25/2007
Notification Time: 14:17 [ET]
Event Date: 07/23/2007
Event Time: [CDT]
Last Update Date: 07/25/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
LINDA SMITH (R4)
CINDY FLANNERY (FSME)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA STUCK CONTROL ASSEMBLY

The State provided the following information via facsimile:

"During a routine maintenance inspection it was noted that the control assembly [of the radiography camera] would not project or retract the drive cable. After an investigation, it was found that 2 of 4 'small gear housing' screws were interfering with the gear teeth of the large gear.

"The two screws that interfere with the operation of the large gear only interfere when they are loose in the housing. Since the outside of the small housing is where the handle for the controls is kept, the screws inevitably come loose over time and use. Since the screws are applied in the housing there is no way to tighten the small housing screws with out disassembling the control arm assembly.

"A small design change is needed on these 4 small housing screws to prevent a source from stuck out in the shielded position."

Equipment involved: SPEC 150, (no serial number provided), Source: Ir-192 (no source strength provided), Control assembly: SPEC 'Red-Red' conduit control.

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Power Reactor Event Number: 43527
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: TOM SHAUB
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/27/2007
Notification Time: 09:05 [ET]
Event Date: 07/26/2007
Event Time: [EDT]
Last Update Date: 07/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
JOEL MUNDAY (R2)
PART 21 (E-MAIL) (NRR)

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

PART 21 NOTIFICATION - FAILURE OF ENERSYS (EXIDE) BATTERY

In March 2005, battery cell internal resistance for an EDG battery bank revealed five cells with abnormal resistance. "There was one cell for which no reading could be obtained and was replaced immediately. A second cell had a reading that was nearly four times the average of the associated string and was subsequently replaced as a proactive measure during the EDG maintenance outage. Three (3) other cells were noted with higher than average readings that are not considered to be operability concerns. In total, five (5) cells out of a total of 240 were found with higher than expected internal resistance values."

The failed battery was destructively tested revealing significant corrosion within the battery. The unit-2 batteries have been replaced. The unit-1 batteries will be replaced in the fall 2007 outage.

Manufacturer: Enersys (Exide)
Model: 3CA-5
Serial Number: beginning with 05

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 43529
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JOE HESSLING
HQ OPS Officer: JASON KOZAL
Notification Date: 07/27/2007
Notification Time: 13:13 [ET]
Event Date: 07/27/2007
Event Time: 12:00 [EDT]
Last Update Date: 07/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JOEL MUNDAY (R2)

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

OFFSITE NOTIFICATION DUE TO HYDRAZINE SPILL

"At 1200 EDT, the following off-site agencies were notified of 0.68 gallons of 35 weight-percent Hydrazine spillage into a concrete berm: National Response Center, State Emergency Response Commission, and Florida Department of Environmental Protection. The amount of Hydrazine spilled was greater than the reportable quantity of 0.34 gallons of 35 weight-percent hydrazine. As stated above, the leak was fully contained in its designated containment area and none reached the environment. The leak has been identified and stopped, area has been cleaned. Notification is due to 10CFR50.72 (b)(2)(xi), due to notification of off-site agencies."

The licensee notified the NRC Resident Inspector.

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Fuel Cycle Facility Event Number: 43531
Facility: WESTINGHOUSE ELECTRIC CORPORATION
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 to UO2)
                   COMMERCIAL LWR FUEL
Region: 2
City: COLUMBIA State: SC
County: RICHLAND
License #: SNM-1107
Agreement: Y
Docket: 07001151
NRC Notified By: RALPH WINIARSKI
HQ OPS Officer: JOE O'HARA
Notification Date: 07/27/2007
Notification Time: 16:27 [ET]
Event Date: 07/26/2007
Event Time: 16:30 [EDT]
Last Update Date: 07/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(4) - NAT PHENOM AFFECTING SAFETY
Person (Organization):
JOEL MUNDAY (R2)
DENNIS RATHBUN (FSME)

Event Text

FIRE IN THE PELLETING AREA

"On 7/26/07, an attempt to extinguish a small grease fire with water was observed by a Westinghouse engineer. This is a violation of IROFS-PELFIRE-902 (also identified as IROFS-BWR-107), which restricts the use of water for fire suppression in pellet/rod areas. The fire observed was located beneath the Line 4 polypak lift. The fire was estimated to be approximately three feet by three feet in area and approximately 2 inches in height. Three polypaks with an unknown quantity of material were observed on the lift at the time the fire occurred.

"The fire was believed to have been started by weld sparks originating from overhead work being performed by construction workers. The water used to extinguish the fire was delivered to the fire in hardhats and welding masks that the construction personnel had at their immediate disposal from a nearby hand-wash basin. The total quantity of water involved was estimated to be a maximum of one gallon.

"Notification is being made based on the potential for 'Any natural phenomenon or other external event, including fires internal and external to the facility, that has affected or may have affected the intended safety function or availability or reliability of one or more items relied on for safety', reference Appendix A, Section (b)(4) to Part 70 of 10CFR70.

"Safety Basis: At no time was the integrity of nearby special nuclear material (SNM) containers challenged. No SNM was involved with the fire. None of the water involved in putting out the fire came into contact with SNM. Even if fissile material had been present during the fire, and that water had contacted and mixed with the fissile material, the quantity of water was limited to approximately one gallon. The minimum quantity of water necessary to challenge the normal case conditions involving homogenous SNM is 3.8 gallons. It should also be pointed out that the quantity of water was limited by the ability of the construction personnel to apply the water using their improvised method and further limited by the source of the water. (The intention of PELFIRE 902 is to prevent the large, uncontrolled addition of water as with firefighters wielding fire hoses attached to an effectively infinite source.)

"Summary of Activity: All construction work has been halted pending a stand-down meeting with personnel. The event was documented in the plant Corrective Action Process (CAPs #07-208-C007).

"Conclusions: Problem was self identified by Westinghouse Operations personnel. The fire was put out immediately and there was no challenge to the integrity of nearby special nuclear material containers. At no time was the health or safety to any employee or member of the public in jeopardy. No exposure to hazardous material was involved. A causal analysis will be performed.

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Other Nuclear Material Event Number: 43533
Rep Org: THYSSENKRUPP WAUPACA
Licensee: THYSSENKRUPP WAUPACA
Region: 3
City: TELL CITY State: IN
County:
License #: 48-150-31-01
Agreement: N
Docket:
NRC Notified By: GARY GREUBEL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/28/2007
Notification Time: 11:32 [ET]
Event Date: 07/25/2007
Event Time: 20:00 [EDT]
Last Update Date: 07/28/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
ERIC DUNCAN (R3)
DENNIS RATHBUN (FSME)

Event Text

DAMAGED LEVEL GAUGE

The licensee (a foundry) reported damage to a level gauge (Texas Nuclear/Thermal Fischer Scientific containing a 100 millicurie source) due to a loss of area cooling. The cooling was lost when a unrelated fire damaged a water cooling pump in another part of the facility and radiant heat from the foundry process apparently caused damage to lead shielding around the gauge. The damage was discovered when the gauge started reading erratically. Investigation into the erratic level reading revealed a high radiation level in the vicinity of the gauge. The area in the vicinity of the gauge was cordoned off and assistance from the gauge manufacturer was requested. Shielding on one of the gauges was found to be partially melted and was assumed to have occurred when cooling in the area was lost. No contamination or damage to the source took place and no overexposure occurred. The damaged gauge and another gauge in the area were both removed and packaged for shipment back to the manufacturer for repair.

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Power Reactor Event Number: 43534
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAVE HELD
HQ OPS Officer: JOE O'HARA
Notification Date: 07/28/2007
Notification Time: 19:24 [ET]
Event Date: 07/28/2007
Event Time: 16:57 [EDT]
Last Update Date: 07/28/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JOHN WHITE (R1)
MICHAEL TSCHILTZ (NRR)
THOMAS BLOUNT (IRD)

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

OFFSITE NOTIFICATION TO FIRE DEPARTMENT

"At 1605 hours on 7/28/07, an offsite breaker in the Beaver Valley Power Station Switchyard developed a failed 'B' phase which resulted in a fire and a subsequent 'B' phase insulator failure. Station fire brigade personnel were dispatched. Offsite assistance was requested at 1657 hours. The fire was extinguished at 1747 hours. The offsite fire department left the site at 1806 hours.

"The circuit containing the failed breaker is associated with a local steel manufacturer and is not a feeder to Beaver Valley Power Station. This is a 4 hour reportable event per 10CFR50.72(b)(2)(xi), Notification to Offsite Governmental Agencies. The operation of BVPS Unit 1 plant systems are not affected by this event. At BVPS Unit 2, the non safety related station air compressors tripped during this event. A backup air compressor was manually started. These compressors were reset and restarted locally without impacting the operation of Beaver Valley Unit 2.

"No EAL criteria was met for this event."

The licensee intends to issue a press release. The NRC Resident Inspector has been notified

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