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Event Notification Report for July 30, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/29/2009 - 07/30/2009

** EVENT NUMBERS **


45226 45235 45236

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General Information or Other Event Number: 45226
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: DUKE UNIVERSITY
Region: 1
City: DURHAM State: NC
County:
License #: 032-0247-1
Agreement: Y
Docket:
NRC Notified By: JAMES ALBRIGHT
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/24/2009
Notification Time: 16:35 [ET]
Event Date: 07/15/2009
Event Time: [EDT]
Last Update Date: 07/24/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN ROGGE (R1DO)
PATRICE BUBAR (FSME)
ILTAB (via email) ()

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

Event Text

AGREEMENT STATE REPORT INVOLVING THE LOSS OF A CALIFORNIUM-252 SOURCE

On 07/24/09 the State of North Carolina was notified by Duke University that a Cf-252 source could not be located during a mid-July inventory of their TUNL facility.

The following information is a portion of an email forwarded by the State of North Carolina:

"TUNL staff today formally reported the loss of a Californium-252 source:

"(1) Source description: 3.4 microcuries of Cf-252 with an active layer of 8 mm diameter on the platinum backing 15 mm in diameter, 0.2 mm thick. The source was inside an ionization chamber, which was purchased in 1995 from Physikalish-Technische Bundesanstalt, Berlin with an initial activity of 5.17 MBq (86 microcuries; T = 2.645 y)

"(2) Circumstances: A physical inventory of TUNL sources during mid-July determined that this source was missing. A search of the TUNL facility failed to locate this source. Although the investigation is continuing, TUNL staff have concluded that the source is lost.

"(3) Disposition or probable disposition of lost source: This source was incorporated into a piece of equipment (ion chamber) composed of a metal tube with several smaller metal tubes (vacuum lines) coming off of it. TUNL staff suspect that this piece of equipment containing the source may have been left with other scrap items shipped off site for disposal as radioactive waste during the Fall of 2008. However it is quite possible that this ion chamber and the source inside are still somewhere inside the TUNL facility. TUNL staff have been instructed to report if they happen upon it.

"(4) Possible radiation exposure: None under any reasonably probable scenario.

"(5) Actions taken to recover the material: TUNL staff conducted a search of the TUNL facility; the investigation into this incident is ongoing.

"(6) Steps taken to prevent a recurrence: TUNL staff are developing and implementing a series of measures to tighten control over TUNL radioactive sources. The development of these policies and procedures is still underway."

The RSO at the TUNL facility said the lost source is a target foil used in the TUNL linear accelerator (032-247-A1), and it was stored at TUNL. The loss occurred under the Duke University broad scope academic license 032-0247-1 and not the TUNL license. No manufacturer, make, model, or serial number reported at this time (16:45 7/24/09)."

North Carolina Incident ICD 09-30


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.

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: 45235
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: KEVIN UMPHREY
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/29/2009
Notification Time: 12:40 [ET]
Event Date: 07/28/2009
Event Time: 17:00 [EDT]
Last Update Date: 07/29/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)

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

FITNESS FOR DUTY REPORT - POSSIBLE LOSS OF TEST RESULTS

The licensee submitted test specimens to a certified laboratory for analysis. After 5 business days, the results of the test were not reported back to the licensee. The individuals affected are being retested. Contact the Headquarters Operations Officer for additional details.

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General Information or Other Event Number: 45236
Rep Org: AREVA NP INC
Licensee: AREVA NP INC
Region: 4
City: RICHLAND State: WA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ALAN MEGINNIS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/29/2009
Notification Time: 17:06 [ET]
Event Date: 02/16/2009
Event Time: [PDT]
Last Update Date: 07/29/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
JAMES MOORMAN (R2DO)
ROBERT DALEY (R3DO)
PART 21 COORD (NRR)

Event Text

PART 21 REPORT - THERMO-HYDRAULIC LIMITS BASED ON INCORRECT FUEL LIFTOFF ASSUMPTIONS

Measurements obtained from LaSalle spent fuel indicates that the liftoff [corrosion film and coolant system crud deposit thickness] on LaSalle fuel may be greater than assumed in thermal-hydraulic calculations for MCPR (Minimum Critical Power Ratio) and LHGR (Linear Heat Generation Rate). Thickness measurements of liftoff on ATRIUM-10 fuel at LaSalle are as high as 93 micrometers whereas the maximum value observed for other facilities is less than 60 micrometers. The greater than expected liftoff present on LaSalle fuel has been attributed to the operation with zinc levels that exceeded EPRI guidelines for reactor water chemistry. AREVA thermal-hydraulic analyses for LaSalle did not account for the higher liftoff.

Following discovery of the deviation, AREVA supplied an operability assessment to Exelon that identified limitations on the operating limit MCPR and rod average exposure. Revised operating limits are being provided to Exelon based on liftoff values that are lower than used in the original operability assessments. These limits are scheduled to be provided by July 31, 2009. Actions have been identified where AREVA will obtain information from the licensees on the anticipated water chemistry environment to be implemented for the next operating cycle, in advance of AREVA core design efforts supporting that cycle. This will assure that AREVA can adequately project the impact of this chemistry environment on liftoff, and to account for it during the design activities.

AREVA states that this defect affects only LaSalle Units 1 and 2. Data from other plants currently operating with fuel licensed using AREVA methods indicate that the liftoff is low and within historical levels.

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