United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for March 21, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/20/2012 - 03/21/2012

** EVENT NUMBERS **


47747 47750 47754 47755

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Agreement State Event Number: 47747
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: SUNLAND FABRICATION INC
Region: 4
City: WALKER State: LA
County:
License #: LA-3462-L01
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/16/2012
Notification Time: 08:59 [ET]
Event Date: 03/15/2012
Event Time: 01:00 [CDT]
Last Update Date: 03/16/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHUCK CAIN (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA DAMAGED DURING BUILDING FIRE

A fire at one of the licensee's facilities resulted in damage to a Spec 880 Delta radiography camera (33 Ci of Ir-192; source serial number 76628B and camera serial number D7538). The outer casing was charred and brittle as a result of the fire. The source remained intact and in the shielded position. All radiation levels were normal for a shielded source.

QSA global has been contacted and will pick up the camera. There were no personnel exposures as a result of this event.

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Agreement State Event Number: 47750
Rep Org: MINNESOTA DEPARTMENT OF HEALTH
Licensee: BRAUN INTERTEC CORPORATION
Region: 3
City: WELCH State: MN
County:
License #: 1082-103-27
Agreement: Y
Docket:
NRC Notified By: BRANDON JURAN
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 03/16/2012
Notification Time: 15:44 [ET]
Event Date: 03/15/2012
Event Time: 15:30 [CDT]
Last Update Date: 03/16/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL KUNOWSKI (R3DO)
JAMES DANNA (FSME)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA STUCK SOURCE

The following information was provided by the State of Minnesota via email:

"Braun Intertec was performing radiography on a valve in a pit at a temporary jobsite. The camera was a model QSA 680 SN: A334 with a 29 Ci Co-60 source model 424-14 SN: 2905. When cranking out the source after about 10-15 revolutions the controls went free; the radiographer could not crank the source back in. The barrier around the worksite was set at <2mR/hr, so the barrier was maintained. The RSO (Radiation Safety Officer) and Corporate RSO were notified and responded to the site. They suspected the drive cable went past the controls. They disconnected the conduit from the controls and were able to use a tool to grab the end of the drive cable and pull back through until the source was back to the shielded position. The exposure level at the crank during the retrieval was <1 mR/hr, and the operation took about 20 min. The RSO and Corporate RSO did not receive a measurable dose during the operation. The two radiographers on site received 4 mR and 2 mR for the shift, not necessarily from the disconnect or retrieval."

Minnesota Department of Health Report #MN120004

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Power Reactor Event Number: 47754
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAN WILLIAMSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/19/2012
Notification Time: 12:41 [ET]
Event Date: 03/19/2012
Event Time: 13:00 [EDT]
Last Update Date: 03/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WAYNE SCHMIDT (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown
2 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER VENTILATION OUT OF SERVICE

"On March 19th 2012 at 1300, Limerick Generating Station will be performing routine preventative maintenance on the Charcoal Adsorber and HEPA Filter associated with the on-site Technical Support Center (TSC) Emergency Ventilation system. While performing this maintenance, the TSC Emergency Ventilation system will not be available to be restored within the time period required to staff and activate the TSC Emergency Response Organization (ERO).

"This work is expected to be completed by 3/19/12. If an emergency is declared requiring TSC ERO activation, the TSC will be staffed and activated using emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of TSC staff becomes necessary, the Station Emergency Director will relocate the staff to an alternate TSC location in accordance with applicable procedures.

"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the loss of an Emergency Facility because of the planned unavailability of the TSC Emergency Ventilation system. The NRC Resident Inspector has been informed."

The TSC ventilation is expected to be out of service for approximately four hours.

The licensee notified the NRC Resident Inspector.

* * * UPDATE ON 3/20/12 AT 0019 EDT FROM WEISSINGER TO HUFFMAN * * *

The TSC emergency ventilation system has been returned to a normal status. The licensee will notify the NRC Resident Inspector. R1DO (Schmidt) notified.

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Power Reactor Event Number: 47755
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: CHRISTOPHER BUSH
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/20/2012
Notification Time: 00:20 [ET]
Event Date: 03/19/2012
Event Time: 16:12 [CDT]
Last Update Date: 03/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MICHAEL KUNOWSKI (R3DO)

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

POTENTIAL FOR AERIAL LIFT TO IMPACT SERVICE WATER PIPING DURING SEISMIC EVENT

"At 1612 on 3/19/12 it was identified that an aerial lift was located in the Auxiliary Building stored in a seismic storage area near Train A and Train B safety related service water piping to Control Room Air Conditioning (CRAC) Alternate Cooling System. This resulted in both trains of Service Water being INOPERABLE per TS 3.7.8 and both trains of CRAC Alternate Cooling system per TS 3.7.11.

"At this time, there is no conclusive information that would support the OPERABILITY of the Service Water System during a seismic event therefore this event is being conservatively reported under 50.72(b)(3)(ii)(B), 'The nuclear plant being in an unanalyzed condition that significantly degrades plant safety.' and 50.72(b)(3)(v)(A) and (D) 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structure systems that are needed for: (A) shutdown the reactor and maintain it in a safe shutdown condition, (D) mitigate the consequences of an accident.'

"The aerial lift was removed and the plant is no longer in the condition noted above."

The NRC Resident Inspector has been informed.

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