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Event Notification Report for December 10, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/09/2010 - 12/10/2010

** EVENT NUMBERS **


46453 46458 46459 46462 46469 46471 46473

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General Information Event Number: 46453
Rep Org: COLORADO DEPT OF HEALTH
Licensee: PROSTATE SEED CENTER
Region: 4
City: LITTLETON State: CO
County:
License #: 972-01
Agreement: Y
Docket:
NRC Notified By: EDGAR ETHINGTON
HQ OPS Officer: ERIC SIMPSON
Notification Date: 12/03/2010
Notification Time: 15:39 [ET]
Event Date: 12/02/2010
Event Time: 16:00 [MST]
Last Update Date: 12/03/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DALE POWERS (R4DO)
JAMES DANNA (FSME)

Event Text

AGREEMENT STATE REPORT - DELIVERED DOSE GREATER THAN PRESCRIBED DOSE

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

"At approximately 1600 MST, 12/2/10, the Colorado Department of Public Health and Environment received a report of a possible misadministration at the Prostate Seed Center, a Colorado radioactive materials licensee.

"Additional information was received on 12/3/10 that there was indeed a misadministration of I-125 in seed form. An excess dose of 27 to 32% was administered above the prescribed dose.

"There was an apparent miscommunication between the supplier and the Prostate Seed Center about the units of dose the seeds were to contain. Apparently, Air Kerma units were ordered and milliCuries were delivered.

"An investigation as to the cause of the misadministration is being performed. A written report on the incident is required by the Department within 30 days."

The excess dose was delivered to the patient's prostate.

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 Event Number: 46458
Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: UNIVERSITY OF IOWA
Region: 3
City: IOWA CITY State: IA
County:
License #: 0037152AAB
Agreement: Y
Docket:
NRC Notified By: RANDAL DAHLIN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/06/2010
Notification Time: 10:56 [ET]
Event Date: 11/29/2010
Event Time: [CST]
Last Update Date: 12/06/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARK RING (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - LEAKING SOURCE IN A STATIC ELIMINATOR

The following report was received via e-mail:

"The following report was received by the Iowa Department of Public Health (IDPH) on December 3, 2010. On November 29, 2010, the University of Iowa Environmental Health and Safety (EHS) staff discovered evidence that a Nickel-63 foil in a custom made static eliminator had lost its seal integrity. The source in question consists of two 10 mCi Ni-63 foils that are housed in a custom built static eliminator (2 inch diameter steel pipe with the foils glued to the walls of the pipe). The static eliminator is attached to a chamber apparatus located in a fume hood within a principal investigator's lab. The results of the leak test indicated approximately 11,500 dpm (0.0052 microCuries) of activity on a wipe taken of several areas in the apparatus housing the Ni-63 foils. EHS personnel bagged the static eliminator and returned it to EHS for disposal."

Iowa Report Number: IA100008

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General Information Event Number: 46459
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: HAYNES ELECTRIC CONSTRUCTION COMPANY
Region: 1
City: ASHEVILLE State: NC
County:
License #: 011-2650-0G
Agreement: Y
Docket:
NRC Notified By: WILLIAM JOHNSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/06/2010
Notification Time: 14:03 [ET]
Event Date: 12/06/2010
Event Time: [EST]
Last Update Date: 12/06/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
ANGELA MCINTOSH (FSME)

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

Event Text

AGREEMENT STATE INVOLVING A LOST TRITIUM EXIT SIGN

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

"Brief Description of Incident: General License: 011-2650-0G, was issued on August 2, 2010 to HB Haynes for one Exit Light, Serial Number: 421564, from Safety Light.

"Model Number: SLX-60 for 7.5 Curies of H-3 (Tritium), Date Shipped; 7-20-2007. In August 2007, Haynes Electric installed the sign at Memorial Mission Hospital in Asheville, NC in the Stairwell at the new Dogwood Building and completed [work at] the temporary site in the fall at 2009.

"The General License was issued on August 2, 2010 and [the President of Haynes Electric] called to confirm that they had gone back to the site and could not locate the sign. [The] RSO for Mission Memorial Hospital was contacted and confirmed the sign was lost and that they did not possess any radioactive material with exit signs. Also, on December 6, 2010 [the representative] with Safety Light also listed as Isolite confirmed that they had not received the light. The light was considered lost on December 6, 2010 and the NRC was notified."

NC Incident No.: 10-51

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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General Information Event Number: 46462
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: EXCELLIMS COPORATION
Region: 1
City: ACTON State: MA
County: MIDDLESEX
License #: 55-0588
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/07/2010
Notification Time: 15:01 [ET]
Event Date: 12/07/2010
Event Time: 13:30 [EST]
Last Update Date: 12/24/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
DIANA DIAZ-TORO (FSME)

Event Text

AGREEMENT STATE REPORT - LEAKING ECKERT & ZIEGLER MODEL NER-004 NI-63 SOURCE

"Excellims Corporation in Acton, MA, (license # 55-0588) telephoned to inform the Agency [Commonwealth of Massachusetts, Radiation Control Program] that a 6 month wipe test of a stored Ni-63 source foil yielded 0.0061 uCi. The Eckert & Ziegler model NER-004 source is stored in the container in which the manufacturer sent the source. The RSO stated that a previous wipe test of the same Ni-63 source yielded higher results and he concluded that he had wiped the 'hot' side. This wipe test (0.0061 uCi) was a wipe of the 'inactive' side, however, he thought that he may have spread contamination to the inactive side during the previous inadvertent wipe test of the 'hot' side.

"ACTION REQUESTED: The RSO will send to the Agency an initial written notification of this wipe test result and the technical data sheet of the NER-004 source that he received from the manufacturer. He stated that he could complete this request in a few days.

"ACTION TAKEN: Document this telephone notification; inform Agency supervision; submit a report to US NRC."

The source has been secured in the original container and stored in a secure location. A Eckert & Ziegler model NER-004 is used in a Gas Chromatograph and has a Ni-63 source of less that 50 milliCuries.

* * * UPDATE FROM JOHN SUMARES TO VINCE KLCO ON 12/24/10 AT 1004 EST * * *

The following information was received by facsimile:

"Analysis results of a Ni-63 source foil wipe test indicated 0.0061 uCi, which is above 0.005 uCi limit.

"The original wipe test sample registered a high reading because the swab test was accidentally performed incorrectly when the active side and inactive side were swabbed. The leak test procedure was reviewed and the test was repeated using the correct procedure. The repeat test indicated 0.0061 uCi and the licensee concluded that some of the Ni-63 from the active side had been transferred to the inactive side during the initial wipe test. The licensee reported this wipe test result to the Agency. The source foil was kept in storage. To address the issue, the leak test procedures for the Ni-63 foil provided by the manufacturer and testing facility was reviewed again, and the leak test instructions were incorporated into the licensee's radiation safety manual. The foil was decontaminated using appropriate safety and control measures and all decontamination materials were placed in waste storage. After decontamination of the inactive side of the foil, the wipe test was repeated using the correct procedure, and the results were <0.00005 uCi. The Ni-63 source was considered ready for use.

"The Agency was provided written notification of this event, initial wipe test results, the technical data sheet for the source involved, and the final wipe test results after foil decontamination.

"The Agency considers this event to be closed."

Notified R1DO (Perry) and FSME (Lewis).

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Power Reactor Event Number: 46469
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: NEWTON LACY
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/09/2010
Notification Time: 12:53 [ET]
Event Date: 12/06/2010
Event Time: 08:15 [EST]
Last Update Date: 12/09/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMES MOORMAN (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

Event Text

OFFSITE NOTIFICATION - OSHA CONTACTED DUE TO FATALITY OF CONTRACTOR EMPLOYEE

"At 0815 Eastern Standard Time on December 6, 2010, TVA Construction Contractor, Bechtel, notified the Occupational Safety and Health Administration (OSHA), in accordance with 29 CFR 1904.39, that a Bechtel employee had suffered a fatality from an apparent heart attack, while working on the Watts Bar Unit 2 Construction completion project. This information was also provided to Tennessee Department of Labor and Workforce Development, Division of Occupational Safety and Health (TOSHA).

"This event had no consequences to the health and safety of the public, other onsite workers, or the environment.

"The NRC Resident Inspector has been notified of this event."

The employee's heart attack happened while he was operating a fork lift at the Parts/Receiving area. Offsite responders were called to the scene, however, the employee was unresponsive to their actions. Employee was transported to the Rhea County Hospital where he was pronounced dead.

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Power Reactor Event Number: 46471
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: NICHOLAS DESANTIS
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/10/2010
Notification Time: 01:25 [ET]
Event Date: 12/09/2010
Event Time: 22:58 [EST]
Last Update Date: 12/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JAMES MOORMAN (R2DO)

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

Event Text

MANUAL REACTOR TRIP AFTER INDICATIONS OF A CONDENSER TUBE LEAK

"At 2200 [EST] 12/09/2010, Unit 4 had indication of a condenser tube leak. A power reduction was commenced in accordance with plant procedures to allow isolation of the leaking waterbox. Sodium levels in the Steam Generators increased and a unit shutdown was required. Power was reduced to 20% and a manual reactor trip was initiated at 2258 [EST] 12/09/10, in accordance with plant procedures. All systems operated as required and the unit is stable in mode 3."

The reactor trip was not complicated. All control rods inserted fully and decay heat is being removed by the atmospheric steam dumps. There is no indications of primary to secondary leakage. Normal offsite power is available and Unit 3 is unaffected. 3 of 3 steam generators are affected by the increase in sodium levels. The licensee is in progress of conducting steam generator blowdowns.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 46473
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: LEE GRZECK
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/10/2010
Notification Time: 15:54 [ET]
Event Date: 12/09/2010
Event Time: 23:04 [EST]
Last Update Date: 12/12/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMES MOORMAN (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

OFFSITE NOTIFICATION - AGENCIES NOTIFIED OF ONSITE TRITIUM LEAK

"On December 9, 2010, elevated levels of tritium were identified in water samples taken from in-leakage into the below ground elevation of the diesel generator building (i.e., through underground conduit penetrations). The tritium levels were determined to be in excess of the Nuclear Energy Institute (NEI) voluntary reporting criteria (i.e., 30,000 pCi/L for onsite groundwater, as specified in the Offsite Dose Calculation Manual). Further investigation determined that the likely source of the tritiated water is buried piping located west of the diesel generator building. The area of the leak is inside the plant protected area, well inside the site's property boundary. There is no indication that tritium has migrated into drinking water sources or has migrated off plant property. The leakage has not impacted plant reliability or the operability of any safety-related equipment.

"Corrective actions taken were to capture the in-leakage of water into the diesel generator building and route it through our normal permitted discharge paths. Additional water samples will continue to be obtained from site monitoring wells until the source of the leak is isolated. Efforts to identify and isolate the source of the leakage, and plans for excavation of the suspected area, are in-progress.

"The Brunswick plant has had an extensive groundwater protection monitoring program in place since 2007. This environmental sampling program consists of more than 100 monitoring wells which are routinely sampled.

"The following agencies will be updated on the status of the onsite tritium samples: City of Southport, Brunswick County, State Officials, NEI, INPO, and ANI.

"The Licensee has notified the NRC Resident Inspector."

* * * UPDATE ON 6/12/10 AT 1610 EST FROM GRZECK TO HUFFMAN * * *

"On December 10, 2010, at 2124 hours (EST), the buried piping leak was stopped after isolating the Unit 1 Condensate Make-up line to the Main Condenser (i.e., from the Condensate Storage Tank (CST)). The elevated levels of tritium are confined to the area in close proximity to the identified buried pipe location, west of the diesel generator building, well within the site's property boundary. The perimeter monitoring wells to the plant's protected area and site boundary continue to be analyzed with no increase in tritium levels identified. Preparations for the excavation and repair of the Condensate Make-up line are in-progress.

"The following agencies will be provided an update of this event: City of Southport, Brunswick County, State Officials, NEI, INPO, and ANI.

"The initial safety significance of this event is minimal. The Brunswick Steam Electric Plant has not identified any health or safety risk to the public or onsite personnel. There is no impact to plant reliability or safety.

"The Licensee has notified the NRC Resident Inspector." R2DO (Moorman) notified.

Page Last Reviewed/Updated Tuesday, August 11, 2015
Tuesday, August 11, 2015