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Alert

Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for July 25, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/24/2012 - 07/25/2012

** EVENT NUMBERS **


48115 48123 48126 48127 48131

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Agreement State Event Number: 48115
Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: SSAB IOWA, INC.
Region: 3
City: MUSCATINE State: IA
County:
License #: 0259170FG
Agreement: Y
Docket:
NRC Notified By: RANDAL S DAHLIN
HQ OPS Officer: JOHN SHOEMAKER 		Notification Date: 07/17/2012
Notification Time: 16:11 [ET]
Event Date: 05/17/2012
Event Time: [CDT]
Last Update Date: 07/17/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
 Person (Organization):
LAURA KOZAK (R3DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

STUCK OPEN SHUTTER ON SEALED SOURCE GAUGE

The following report was received via email.

"During an unannounced health, safety, and security inspection conducted on July 12, 2012 at SSAB Iowa, Inc. the Agency [Iowa Department of Public Health] discovered that the licensee had a shutter fail open on an EG & G Berthold, model LB 300 MLT, serial number 1739-10-05 containing approximately 50 millicuries of Cobalt-60. This failure occurred on May 17, 2012 while the device was measuring the level of molten metal in a caster. On May 22, 2012 a contractor arrived on site and repaired the shutter. Cause of failure appears to have been binding due to the extreme heat conditions of the castor. Precautions were taken to ensure that no individual received a radiation dose and normal operations continued until the shutter was repaired."

Iowa Event Report # IA 120003

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 48123
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MARK EGHIGIAN
HQ OPS Officer: DONALD NORWOOD 		Notification Date: 07/20/2012
Notification Time: 22:27 [ET]
Event Date: 07/20/2012
Event Time: 22:30 [EDT]
Last Update Date: 07/24/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
 Person (Organization):
LAURA KOZAK (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

ANTICIPATORY LOSS OF SPDS AND ERDS DUE TO POSSIBLE LOSS OF INTEGRATED PLANT COMPUTER SYSTEM DURING TROUBLESHOOTING

"Beginning July 20, 2012, at approximately 2230, troubleshooting of MUX A components and fiber optic cables on the Fermi 2 Integrated Plant Computer System (IPCS) will be performed. A loss of IPCS during the troubleshooting is possible.

"The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the IPCS platform and will be out of service if IPCS is lost. These systems would be unavailable to the Control Room and all other Emergency Response Facilities (ERFs). During this time dose assessment capability would only be available in the manual data input mode. The majority of the Control Room indications will remain available to the plant staff, and would be used for emergency response, if needed. Information would be communicated to the NRC using other available communication systems as needed. A follow-up notification will be submitted when the IPCS troubleshooting is complete.

"This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10CFR50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION FROM BRETT JEBBIA TO VINCE KLCO ON 7/24/2012 AT 2243 EDT * * *

"Troubleshooting and repairs have been completed to the Fermi 2 Integrated Plant Computer System (IPCS) as of July 24, 2012 at 1855 [EDT]. No loss of communication ability occurred from initial notification while repairs and restoration were in progress. Event 48123 is retracted.

"[The initial anticipatory] notification was made per 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."

The licensee notified the NRC Resident Inspector.

Notified the R3DO (Bloomer).

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Power Reactor Event Number: 48126
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WAYNE JARMAN
HQ OPS Officer: DONG HWA PARK 		Notification Date: 07/24/2012
Notification Time: 11:04 [ET]
Event Date: 07/23/2012
Event Time: 05:08 [EDT]
Last Update Date: 07/24/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
 Person (Organization):
BINOY DESAI (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

TSC VENTILATION SYSTEM OUT OF SERVICE

"On July 23, 2012, at 0508 EDT, the Technical Support Center (TSC) ventilation was tagged out for routine maintenance. It was believed that only the cooling function was affected and that the TSC ventilation system was still capable of performing its intended function of pressurization and filtration. A review by operations today determined that the TSC filtration and pressurization portion was also affected. Under certain accident conditions, the TSC may become unavailable due to the inability of the filtration system to maintain a habitable atmosphere. Compensatory measures exists to relocate the TSC to an alternate location. Currently it is expected that the TSC ventilation system maintenance will be completed by the end of the day shift today and turned over to operations. Operations should start up the system early during night shift (7/24).

"This is reportable to the NRC per 10 CFR 50.72 (b)(3)(xiii) as an eight hour non-emergency notification. The event had no effect on plant operations and no impact on public health and safety has been identified. The licensee will notify the NRC Resident Inspector, States and Counties."

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Power Reactor Event Number: 48127
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: JUSTIN KELLY
HQ OPS Officer: VINCE KLCO 		Notification Date: 07/24/2012
Notification Time: 13:43 [ET]
Event Date: 07/24/2012
Event Time: 05:55 [EDT]
Last Update Date: 07/24/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
 Person (Organization):
BINOY DESAI (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

TECHNICAL SUPPORT CENTER OUT OF SERVICE

"At approximately 0555 [EDT] on 07/24/2012, the AH-17 TSC Cooling Fan was found with the cooling system not fully working. The fan is running, but the condensing compressor is not. Repairs are being planned and will be worked immediately. This event is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Revision 2. The on call Site Emergency Coordinator and Emergency Response Manager have been notified. The Alternate TSC is available per plant procedure, if required."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 48131
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: RYAN OAKES
HQ OPS Officer: DONALD NORWOOD 		Notification Date: 07/24/2012
Notification Time: 19:29 [ET]
Event Date: 07/24/2012
Event Time: 11:22 [PDT]
Last Update Date: 07/24/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
 Person (Organization):
JAMES DRAKE (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

LOSS OF SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE DUE TO THE TRIP OF SECONDARY CONTAINMENT SUPPLY AND EXHAUST FANS

"Reactor Building (Secondary Containment) Supply Fan 1B (ROA-FN-1B) and Reactor Building Exhaust Fan 1B (REA-FN-1B) inadvertently tripped. Secondary containment pressure exceeded atmospheric pressure which does not meet the surveillance requirement to have secondary containment vacuum greater than or equal to 0.25 inches of water vacuum. This event is reportable as an event that could have prevented fulfillment of a safety function needed to control the release of radiation and mitigate the consequences of an accident. Alternate supply and exhaust fans were manually started within 4 minutes and Secondary Containment pressure was restored to normal (greater than 0.25 inches water vacuum) within 5 minutes, returning Secondary Containment to operable status.

"Event investigation is on-going to determine exact cause of the fans tripping; however, electrical maintenance activities were in progress at the time.

"There were no radiological releases associated with the event.

"No safety system actuations or isolations occurred."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Wednesday, March 24, 2021

Page Last Reviewed/Updated Wednesday, March 24, 2021