United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for May 15, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/14/2012 - 05/15/2012

** EVENT NUMBERS **


47899 47921 47922 47923

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Agreement State Event Number: 47899
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: RONE ENGINEERING
Region: 4
City: DALLAS State: TX
County:
License #: L02356
Agreement: Y
Docket:
NRC Notified By: ROBERT FREE
HQ OPS Officer: PETE SNYDER
Notification Date: 05/04/2012
Notification Time: 12:44 [ET]
Event Date: 05/04/2012
Event Time: [CDT]
Last Update Date: 05/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG WERNER (R4DO)
JAMES DANNA (FSME)

Event Text

AGREEMENT STATE REPORT - MOISTURE DENSITY GAUGE DAMAGED AT JOBSITE

The State of Texas supplied the following information via email:

"The RSO for Rone Engineering contacted the Texas Radiation Program by phone on 4 May 2012 at approximately 10:15 AM CDT. The RSO reported a gauge had been damaged when run over by a water truck on a highway construction site in San Antonio. The RSO requested a radiation program inspector to conduct a radiation survey of the device because there was no radiation detection equipment immediately available.

"An inspector was dispatched to the site and reported that the device was severely damaged, but the radioactive sources were still shielded. However, the source rod was broken and radiation levels at the point where it broke were measured to be 86 millirem per hour. The licensee contacted a company licensed to recover and ship radioactive sources. The recovery company packaged the gauge and will return it to the manufacturer.

"The gauge was a Troxler 3430 plus, Serial number 60001. The gauge contained two sources; one 0.696 GBq Cs-137 and one 1.48 GBq Am-241 The Cs-137 source serial number was 77-7272 and the Am-241 source serial number was 78-4445."

Texas Incident #: I - 8951

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Power Reactor Event Number: 47921
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: MOTLEY HEDGES
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/14/2012
Notification Time: 11:02 [ET]
Event Date: 05/14/2012
Event Time: 03:00 [PDT]
Last Update Date: 05/14/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DALE POWERS (R4DO)

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

TECHNICAL SUPPORT CENTER OUT-OF-SERVICE DUE TO PLANNED MAINTENANCE

"At 0300 PDT on 5-14-2012, planned maintenance was started on the Technical Support Center (TSC) HVAC system. The scope of work is to replace the carbon tray gaskets and perform carbon filter testing. The duration of this scheduled maintenance is planned for 26 hours.

"This condition represents a major loss of emergency preparedness capability per 10 CFR 50.72(b)(3)(xiii) in that the TSC habitability might not be sustainable during events due to the inability of the filtration system to maintain a habitable atmosphere. Station procedures provide instructions to relocate the TSC if monitoring during an emergency event indicates habitability cannot be maintained. Compensatory measures are in place to heighten awareness of responsible TSC staff following ERO activation to monitor TSC habitability in accordance with procedures and to consider TSC relocation as necessary as described in the station emergency plan."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 47922
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RUSTY WHITEHEAD
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/14/2012
Notification Time: 13:45 [ET]
Event Date: 05/14/2012
Event Time: 10:24 [EDT]
Last Update Date: 05/14/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
SCOTT FREEMAN (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 DUE TO OIL SHEEN OBSERVED ON DIFFUSER POND

"On 05/14/2012 at 1024 EDT, a notification to the National Response Center was made as a result of an oil sheen on waters of the U.S. (Sequoyah's Diffuser pond). The discharge from an onsite pond was isolated stopping what appears to be the source of all to the diffuser pond. The source of leakage is still under investigation.

"The following additional agencies have also been notified:

"EPA Region 4,
"Tennessee Department of Environment and Conservation (TDEC), and
"Tennessee Emergency Management Agency (TEMA).

"Oil is maintained onsite, [and] no oil has been discharged to the river. Cleanup is in progress.

The licensee notified the NRC Resident Inspector. Notified DOE (Turner), EPA (Post), USDA (Beverly), HHS (Emerson), and FEMA (Casto).

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Part 21 Event Number: 47923
Rep Org: SHAW GROUP INC.
Licensee: GERDAU LONG STEEL NORTH AMERICA
Region: 1
City: CHARLOTTE State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: EDWARD HUBNER
HQ OPS Officer: PETE SNYDER
Notification Date: 05/14/2012
Notification Time: 14:46 [ET]
Event Date: 05/14/2012
Event Time: [EDT]
Last Update Date: 05/14/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
SCOTT FREEMAN (R2DO)
PART 21 REACTORS GRP (EMAI)

Event Text

THREADING DEVIATIONS ON STEEL REINFORCING BAR SUPPLIED TO CONSTRUCTION PROJECTS

This report was supplied for informational purposes. The threaded ends of some of the reinforcing bar supplied to the V.C. Summer Units 2 and 3 and the Vogtle Units 3 and 4 nuclear projects were found to have threads too long or too short, double threaded areas, voids in threads, or an incorrect thread profile.

"The results of evaluations of this condition as documented by Shaw Nuclear and conducted in accordance with the procedure for performing evaluations required by 10 CFR 21.21, have concluded that the deviations in the rebar would not create a substantial safety hazard, if they were to remain uncorrected. Therefore, it has been determined that these deviations are not reportable under the requirements of 10 CFR Part 21. This information is being provided for industry awareness of the occurrence of these types of deviations in reinforcing steel being provided as a basic component."

Page Last Reviewed/Updated Tuesday, May 15, 2012
Tuesday, May 15, 2012