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Event Notification Report for December 19, 2011

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
12/18/2011 - 12/19/2011

EVENT NUMBERS
475344753547536

Power Reactor
Event Number: 47534
Facility: SEQUOYAH
Region: 2     State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIM RIEGER
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/19/2011
Notification Time: 17:25 [ET]
Event Date: 12/19/2011
Event Time: 16:44 [EST]
Last Update Date: 12/19/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
SCOTT FREEMAN (R2DO)
Power Reactor Unit Info
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 DUE TO TRITIUM LEVELS EXCEEDING THRESHOLD FOR DRINKING WATER

"At 1644 EST, on 12/19/11, TVA's Sequoyah Nuclear Plant made voluntary offsite notifications to the Tennessee Radiological Health Department Director and the Tennessee Department of Environmental Conservation - Senior Director Water Programs, to inform them of the following:

"On October 31, 2011, Sequoyah proactively installed two new groundwater monitoring wells in an area known to have contained previously reported releases of tritium in an effort to further characterize and validate the scope of the plume. These releases were reported in 2006 as part of NEI's [Nuclear Energy Institute] groundwater initiative. On December 16, 2011, elevated levels of tritium were identified in water samples taken from one new onsite monitoring well. The tritium levels were confirmed to be greater than 20,000 pCi/L which is the threshold for drinking water. No groundwater monitoring wells are used for drinking or irrigation purposes onsite. The highest level sampled was 22,760 pCi/L.

"Samples taken in the discharge channel located 30 yards from this groundwater monitoring well confirmed no detectable tritium. Refueling Water Storage Tank levels are being monitored and no active leak is in progress. Samples of adjacent wells have been taken and confirmed no unexpected changes in tritium levels of these wells. Additionally, Sequoyah has sampled at the station discharge to the Tennessee River and confirmed no detectable levels in any sample.

"In a conservative decision making process and in accordance with the groundwater protection initiative established by the nuclear industry, Sequoyah is voluntarily communicating sample results likely attributed to a previously reported tritium spill. The plant is continuing to review the sample results to confirm this is related to the historical tritium plume. The plant will take appropriate actions as outlined in the Groundwater Tritium Action Plan, which has been initiated to address this issue. Sequoyah Nuclear Plant has had an extensive groundwater monitoring program in place since 2008. The environmental sampling program consists of sixteen groundwater wells which are periodically sampled in accordance with industry standards.

"The NRC Resident Inspector has been notified. The following agencies have been, or will be updated: Hamilton County, State of Tennessee, Nuclear Energy Institute and American Nuclear Insurers. Tennessee Valley Authority plans a media notification for this issue."


Agreement State
Event Number: 47535
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: KRATON POLYMERS
Region: 3
City: BELPRE   State: OH
County:
License #: 31201850010
Agreement: Y
Docket:
NRC Notified By: KARL VON AHN
HQ OPS Officer: JOE O'HARA
Notification Date: 12/20/2011
Notification Time: 08:14 [ET]
Event Date: 12/19/2011
Event Time: 11:30 [EST]
Last Update Date: 12/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
PATTY PELKE (R3DO)
MICHELE BURGESS (FSME)
Event Text
AGREEMENT STATE REPORT - SHUTTER FAILURE ON OHMART SH-100 PROCESS GAUGE

"At 11:30 AM December 19, 2011, the licensee's radiation safety officer provided a 24-hour telephone report notification of a shutter failure on a gauge. The gauge involved was an Ohmart SH-100, serial number 70230, containing 10 mCi of CS-137, with an assay date of Aug 1981. The shutter mechanism is a lead block screwed to a sliding aluminum plate. The licensee was removing the gauge from its mounting to replace it with a different new gauge as permitted by their license. When the licensee removed the gauge from its mounting, the lead block separated from the aluminum plate. The licensee replaced the lead shielding and secured it in place. The licensee secured the gauge from unauthorized access and will return it to the manufacturer for disposal with other gauges they are replacing. The licensee states that no personnel received radiation doses during this event."

Ohio Report #OH110005


Agreement State
Event Number: 47536
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: NUCOR-YAMATO STEEL
Region: 4
City: BLYTHEVILLE   State: AR
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TAMMY KRIESEL
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/20/2011
Notification Time: 13:07 [ET]
Event Date: 12/19/2011
Event Time: 00:00 [CST]
Last Update Date: 12/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
BOB HAGAR (R4DO)
MICHELE BURGESS (FSME)
Event Text
AGREEMENT STATE REPORT - SCRAP METAL FACILITY REJECTED LOAD

The following information was provided by the state via email:

"Nucor-Yamato Steel in Blytheville, Arkansas reported to the Arkansas Radiation Control Program on December 19, 2011, that a sealed source containing radioactive material had been found in a load of scrap metal received at their facility. The broker for this load of scrap metal was The David J. Joseph Company. The load of scrap originated in Louisiana.

"Survey readings on contact with the source using a sodium iodide detector were 1.0 mR/hr. Smears taken and counted using a thin window GM detector in the field indicates that the source does not appear to be leaking.

"The source has a glass covered flange end approximately 1.125" diameter, with a fitting on the back side of approximately 0.5" diameter. Overall length is approximately 1.0". No identifying marks have been found at this time.

"The source was contained within a small can, secured within a locked storage room. The steel mill is awaiting a consultant to pick-up, identify and dispose of the source."