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Event Notification Report for January 11, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/08/2010 - 01/11/2010

** EVENT NUMBERS **


45451 45606 45610 45615 45616 45617 45618

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
General Information or Other Event Number: 45451
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: UNIVERSITY OF TEXAS
Region: 4
City: AUSTIN State: TX
County:
License #: L00485
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: VINCE KLCO
Notification Date: 10/21/2009
Notification Time: 19:18 [ET]
Event Date: 10/21/2009
Event Time: [CDT]
Last Update Date: 01/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
NEIL OKEEFE (R4DO)
RICHARD TURTIL (FSME)

Event Text

AGREEMENT STATE REPORT - REMOVABLE CONTAMINATION ON A PACKAGE

Packaged vials of Sulfur-35 were delivered to the University of Texas with an indicated removable contamination of 10,000 dpm per swipe on the outside of the package. The vials of sulfur were reported as frozen with 1600 dpm per swipe. A lead pig located in the package indicated 600 dpm per swipe. There was no other reported contamination on the package.

A Texas incident report number will follow.

* * * UPDATE AT 1136 EDT ON 10/22/2009 TO PARK FROM TUCKER * * *

The following report was provide by the State via e-mail:

"On October 21, 2009 at 1735 [CDT] the Agency [Texas Dept of State Health Services] received a telephone call from [Redacted] the Radiation Safety Officer [RSO] for the University of Texas. [The RSO] stated that a package had arrived at the University of Texas facility in Port Aransas, Texas, and was found to have removable contamination on the outside of the package. The package was shipped as expected and contained vials of Sulfur-35, and did not appear to be damaged. The vials that contained the radioactive material were packed in dry ice and were still frozen when the package was opened. Swipes taken on the outside of the package, as part of the arrival survey, indicated contamination of 10,000 disintegrations per minute (dpm). Contamination levels on the vials in the package were 1,600 dpm. The contamination level on the lead pig shielding the vials was 600 dpm. Removable contamination on the inside of the package was between 1000-2000 dpm. All contamination levels are reported as per swipe, but [the RSO] was unsure of the areas that were swiped. No contamination was detected on personnel involved at the receiving facility. [The RSO] was not convinced that the contamination came from the package because none of the vials appeared damaged, and the highest contamination levels were located on the outside of the package. He stated that they are still investigating and may request assistance from the Agency to identify the radionuclide. It was shipped by [a common carrier] from PerkinElmer, but [the RSO] was unaware of the location it was shipped from. The common carrier tracking number given was [provided], but when tracked online using the [common carrier] website, the package was not in the system. The Agency is awaiting further information from the licensee's investigation."

Notified the R4DO (O'Keefe) and FSME (McIntosh).

Texas Incident Number: I-8680

* * * RETRACTION FROM ANNIE BACKHAUS TO HOWIE CROUCH VIA EMAIL AT 1639 EST ON 1/08/10 * * *

"On November 2, 2009, [the RSO] concluded, through his investigation, that the initial readings were false-positives. He concluded this after he conducted two independent surveys of the package and detected nothing above background. [The RSO] concluded the false-positive was due to chemiluminescence and ionizing radiation. Therefore, the State of Texas would like to retract this report from the Nuclear Materials Events Database."

Notified the R4DO (Shannon) and FSME EO (McConnell).

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General Information or Other Event Number: 45606
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: LANTHEUS
Region: 4
City:  State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 01/05/2010
Notification Time: 12:57 [ET]
Event Date: 12/27/2009
Event Time: [CST]
Last Update Date: 01/05/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL SHANNON (R4DO)
ANGELA MCINTOSH (FSME)
MEXICO (VIA)

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

Event Text

AGREEMENT STATE REPORT - LOST Mo-99 ISOTOPE GENERATOR

"On January 5, 2010, at 0740 hours, the Agency [Texas Department of State Health Services] received a phone call from the United States Department of Transportation (USDOT) informing them that on December 27, 2009, 38 molly generators containing various activities of molybdenum (Mo) 99 were shipped to the Dallas/Forth Worth Airport. Some of the generators were to be delivered to various surrounding states and 24 were intended for delivery to licensees in the State of Texas.

"The shipper was Lantheus and they are located in N. Billerica, Massachusetts. The shipper stated that the number of units shipped was verified at the airport prior to shipping. The number of generators arriving in Texas was not verified by the shipping company according to USDOT. A device containing four curies of Mo-99 for the National Central Pharmacy in Abilene, Texas was not found.

"USDOT has contacted all companies who received generators from this shipment, and none of them indicated that they had received the generator that is missing. The consultant for the shipping company stated that during transit the devices were flown from Massachusetts to Cincinnati, Ohio, and then to Dallas/Fort Worth, where they were removed from the plane. A search of all transportation vehicles used to transport the devices was conducted, but the device was not located.

"The consultant stated that the shipping company also contacted each company who received a device and confirmed that they had not received any additional material. The consultant stated that there may be some discrepancies in the shipping documents and that it could be a clerical error and not a missing source. The shipping company is currently conducting a document review. Additional information will be provided as it is obtained."

Texas Incident #: I-8696


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

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General Information or Other Event Number: 45610
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: UNKNOWN
Region: 3
City: MILWAUKEE State: WI
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SHUNLAI ZHU
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/06/2010
Notification Time: 11:56 [ET]
Event Date: 01/04/2010
Event Time: [CST]
Last Update Date: 01/06/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ROBERT DALEY (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE - MOISTURE DENSITY GAUGE FOUND IN SCRAP METAL

"The department received an email on January 4, 2010 from Miller Compressing, Milwaukee, WI, describing a load of scrap metal received on December 24, 2009 that set off the radiation detector. On January 4, 2010, they isolated a damaged Seaman Nuclear Model R-75 moisture density gauge containing 4.5 mCi of Radium-226, serial number 3276. Miller Compressing placed the device in a locked storage area. Seaman Nuclear has agreed to conduct a leak test to ensure source integrity and transport the device back to their facility in Oak Creek, WI this week."

WI Report No.: WI100001

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Power Reactor Event Number: 45615
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/08/2010
Notification Time: 15:00 [ET]
Event Date: 01/08/2010
Event Time: 13:29 [CST]
Last Update Date: 01/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MICHAEL SHANNON (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

EMERGENCY SIRENS MAY BE IMPACTED BY EXTREME WEATHER CONDITIONS

"The current NOAA weather forecast for the station is predicted to be about -25 degrees Fahrenheit [on the morning of January 9, 2010]. Based on this forecast, the station reviewed the impact of these temperatures on the 101 sirens in the Fort Calhoun Station 10-mile Emergency Planning Zone (EPZ). The siren manufacturer's and the FEMA approved siren design report information states that the sirens (Federal Signal model 2001) are designed for operation between the temperature readings of -22 degrees Fahrenheit and +140 degrees Fahrenheit.

"Event Numbers 44782 and 44783, on a similar condition at another utility having the same sirens, were reviewed. It was noted that the reports documented discussion with the manufacturer's technical representative confirming that the sirens are operational and no special testing is required when the temperature goes below and then returns within the operating temperature limits.

"The current temperature at the station is within the operational limits. Therefore, the 101 sirens are considered functional at this time.

"The following agencies were notified that if the temperature falls below a negative twenty-two degrees Fahrenheit, the established process of back-up route alerting is to be used notifying the public in the event of a nuclear emergency where the sirens are activated but fail to respond:

-Washington County, NE Emergency Management
-Pottawatomie County, IA Emergency Management
-Harrison County, IA Emergency Management

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii). No media press release is being made."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 45616
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: LEON RAFNER
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/08/2010
Notification Time: 18:15 [ET]
Event Date: 12/23/2009
Event Time: 10:14 [PST]
Last Update Date: 01/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
MICHAEL SHANNON (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

LOSS OF RHR COOLING CAPABILITY DUE TO ISOLATION OF THE SPENT FUEL POOL COOLING HEAT SINK

"This is a late eight hour report submitted under 10CFR50.72(b)(3)(v), 'Loss of Safety Function to (B) Remove Residual Heat'

"On December 23, 2009 at about 0957 PST, with SONGS Unit 2 defueled for the Cycle 16 refueling outage, a decrease in salt water cooling flow to the Train A Component Cooling Water Heat Exchanger indicated debris was entering the system. The loss of flow appears to have been caused by debris entering the system through a failed pump suction screen. At 1014 PST operators removed the heat exchanger from service for approximately one hour to reverse the salt water cooling flow though the heat exchanger and clear the debris. The Train B cooling system had previously been removed from service for scheduled maintenance, relying on the single Train A heat exchanger to supply cooling to the Spent Fuel Pool cooling system.

"Salt water cooling flow was fully restored at approximately 1118 PST. Operators conservatively declared the Spent Fuel Pool Cooling System inoperable and maintained compliance with the conditions of Licensee Controlled Specification 3.7.106. Time to exceed the 160 degree Fahrenheit allowable pool temperature was estimated at over twenty three hours.

"It has been determined that the temporary isolation of the heat sink from the spent fuel pool constituted a loss of safety function for residual heat removal. Therefore SCE is reporting this occurrence as a loss of safety function in accordance with 10 CFR 50.72(b)(3)(v).

"The safety significance of this event was minimal. Flow reversal to clear ocean debris from the heat exchangers is a routine procedurally controlled evolution and bounded by design calculations which consider post-accident heat loads with a full core offload in the spent fuel pool. These actions are within the limits of both the Technical Specifications and Licensee Controlled Specifications."

The licensee will inform the NRC Resident Inspector.

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Power Reactor Event Number: 45617
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ED LESSMANN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/09/2010
Notification Time: 12:14 [ET]
Event Date: 01/09/2010
Event Time: 10:28 [CST]
Last Update Date: 01/09/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MICHAEL SHANNON (R4DO)

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

Event Text

AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP ON SUDDEN PRESSURE IN OUTPUT TRANSFORMER

"At 1028 CST on the 9th of January, Unit 1 tripped due to turbine trip greater than 50% reactor power. The turbine trip was caused by a sudden pressure fault of the Unit 1 main generator output transformer (1MT1).

"All systems operated as designed. All three auxiliary feedwater pumps auto-started as required. There were no complications noted on the reactor trip.

"Current status: Holding in mode 3 and shutting down secondary equipment. Decay heat removal is via auxiliary feed and main condenser steam dumps."

All rods inserted during the trip. No relief or safety valves lifted during the transient. The electrical grid is stable and Unit 1 is in its' normal shutdown electrical lineup. Investigation of the transformer fault is underway. Unit 2 was unaffected by the transient.

The licensee will be notifying the NRC Resident Inspector.

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Power Reactor Event Number: 45618
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE DEBOARD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/09/2010
Notification Time: 21:33 [ET]
Event Date: 01/09/2010
Event Time: 19:51 [CST]
Last Update Date: 01/09/2010
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
ANN MARIE STONE (R3DO)
JEFFERY GRANT (IRD)
JOSEPH GIITTER (NRR)
MARK SATORIUS (R3RA)
ERIC LEEDS (NRR)
MICHAEL INZER (DHS)
ERWIN CASTO (FEMA)

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

NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO A FIRE IN THE AUXILIARY BUILDING LASTING GREATER THAN 15 MINUTES

"At 1925 [hrs. CST], the Main Control Room received a notification of smoke in the Auxiliary Building Ventilation Supply Plenum. Fire Brigade and the Incident Commander were dispatched. Once [they] arrived at the scene, they noted smoke in the area of the 0C VA Supply Fan and requested the fan be shutdown. The 0C VA supply fan was shutdown at 1933 hrs. The operators reported smoke and a small fire coming from the inboard bearing of the 0C VA supply fan. A CO2 fire extinguisher was used to put the fire out and cool the bearing. A total of 2 extinguishers were used. The fire was declared out at 1941 hrs. Both Units remained stable and at full power during the entire event.

"There were no injuries, and no off site assistance was required."

The licensee notified state and local authorities and the NRC Resident Inspector.

* * * UPDATE FROM DEBOARD TO CROUCH @ 2231 CST ON 01/09/10 * * *

"At 2111 CST [on] 1-9-2010, the Unusual Event was terminated. The fire is out. Both Units are stable. A fire watch is established. There are no signs of reflash. [Braidwood] no longer [meets the] Unusual Event action level threshold."

The licensee has notified the NRC Resident Inspector. Notified IRD (Grant), R3DO (Stone), NRR EO (Giiter), DHS (Inzler) and FEMA (Casto).

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