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Event Notification Report for March 7, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/06/2014 - 03/07/2014

** EVENT NUMBERS **


49861 49869 49878 49879 49880

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Power Reactor Event Number: 49861
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JAMES HOUGH
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 02/27/2014
Notification Time: 18:56 [ET]
Event Date: 02/27/2014
Event Time: 12:22 [EST]
Last Update Date: 03/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DANIEL RICH (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation
4 N Y 100 Power Operation 100 Power Operation

Event Text

DEGRADATION OF THE TECHNICAL SUPPORT CENTER VENTILATION SYSTEM

"At approximately 1222 EST on February 27, 2014, the site discovered degradation of the Technical Support Center (TSC) ventilation air handling unit. Maintenance is in progress. The functionality of the TSC ventilation system is in question.

"The emergency assessment function could have been performed in the Control Room as addressed in emergency response procedures.

"This event is reported in accordance with 10 CFR 50.72 (b)(3)(xiii)."

A TSC ventilation fan was vibrating because of a thrown fan blade.

The licensee has notified the NRC Resident Inspector.

* * * UPDATE AT 1105 EST ON 3/6/2014 FROM CHRIS TRENT TO JEFF ROTTON * * *

"Turkey Point Nuclear Station declared the TSC functional but degraded due to its normal power supply breaker tripping unexpectedly. The TSC is capable of going on emergency recirculation on its alternate power supply. The TSC is currently in its normal standby alignment with its power being supplied from its alternate source breaker. Compensatory measures are in place IAW 0-ADM-117, Equipment Important to Emergency Response, and will remain in place until the cause of the normal power supply breaker tripping is identified and corrected. Emergency Preparedness department will be making a notification to ERO members to report to the TSC as their primary notification again."

Notified R2DO (Rose).

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Power Reactor Event Number: 49869
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JIM RITCHIE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/04/2014
Notification Time: 06:04 [ET]
Event Date: 03/04/2014
Event Time: 05:02 [EST]
Last Update Date: 03/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
FRED BOWER (R1DO)

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 FOR PLANNED MAINTENANCE

"A planned maintenance evolution at the Oyster Creek Nuclear Generating Station has removed the Technical Support Center (TSC) ventilation system from service. The TSC ventilation system will be rendered non-functional during the course of the work activities. The TSC ventilation is expected to be out of service for approximately twenty hours from 0500 [EST] to 2400, today, March 4, 2014.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures.

''This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to potential loss of the TSC. An update will be provided once the TSC ventilation has been restored to normal operation. The NRC Resident Inspector has been notified."

* * * UPDATE AT 1532 ON 3/6/14 FROM SPAGNUOLO TO SNYDER * * *

On 3/6/14 at 1532 EST the Technical Support Center was returned to service.

Notified R1DO (Bower).

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Fuel Cycle Facility Event Number: 49878
Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
                   LEU FABRICATION
                   LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: PHILLIP OLLIS
HQ OPS Officer: PETE SNYDER
Notification Date: 03/06/2014
Notification Time: 11:22 [ET]
Event Date: 03/06/2014
Event Time: 10:26 [EST]
Last Update Date: 03/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (a)(5) - ONLY ONE SAFETY ITEM AVAILABLE
Person (Organization):
STEVE ROSE (R2DO)
ROBERT JOHNSON (NMSS)

Event Text

FEED TUBE LEVEL SENSOR FAILED AS AN ITEM RELIED ON FOR SAFETY

"Feed tube level sensor was found to be in a state such that it has failed as an IROFS [Item Relied On For Safety] for a fire accident sequence leading to the loss of a criticality control. Another IROFS is in place and the accident sequence continues to meet performance requirements. Less than a safe mass was always maintained. This event is being reported because only one item relied on for safety, as documented in the Integrated Safety Analysis summary, remains available and reliable to prevent a nuclear criticality accident, and has been in this state for greater than eight hours.

"Portion of the plant affected: FMO [Fuel Manufacturing Operation] Press."

The licensee notified the North Carolina State Radiation Protection Branch, New Hanover County Emergency Management, and NRC Region II.

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Power Reactor Event Number: 49879
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ADAM PECK
HQ OPS Officer: PETE SNYDER
Notification Date: 03/06/2014
Notification Time: 19:33 [ET]
Event Date: 03/06/2014
Event Time: 09:06 [PST]
Last Update Date: 03/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
TOM ANDREWS (R4DO)

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

UNANALYZED CONDITION REGARDING POTENTIAL TORNADO MISSILE DAMAGE TO EMERGENCY DIESEL EXHAUST PLENUM

"The condition described below is being reported as an unanalyzed condition per 10 CFR 50.72(b)(3)(ii)(B) and per the guidance of NUREG-1022, Rev. 3.

"On 03/06/2014 at 0906 PST, Diablo Canyon Power Plant (DCPP) identified a nonconforming condition involving the Emergency Diesel Generator (EDG) ventilation exhaust plenums installed in Unit 1 and Unit 2. Specifically, the radiator exhaust plenums and exhaust piping need to be re-evaluated to ensure adequate protection against flying debris that could be generated by a tornado.

"The occurrence of such an event is highly unlikely and there is no imminent concern regarding severe weather involving tornados. The EDGs are located inside the power plant structure and are capable of performing their safety function. Compensatory measures are being developed to address the associated nonconformance.

"This event does not adversely affect the health and safety of the public.

"The licensee informed the NRC Resident Inspector."

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Power Reactor Event Number: 49880
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MITCH STACY
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/06/2014
Notification Time: 20:41 [ET]
Event Date: 03/06/2014
Event Time: 16:05 [EST]
Last Update Date: 03/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
STEVE ROSE (R2DO)

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

SECONDARY CONTAINMENT AIRLOCK DOOR INTERLOCK MALFUNCTION

"At 1605 EST on March 6, 2014, Operations determined that both the inner and outer secondary containment airlock doors, on the 50 foot elevation of the reactor building, had been simultaneously opened for approximately one minute on March 5, 2013. This event occurred while an employee was exiting secondary containment. The inner door failed to latch and opened as the employee was opening the outer door. Upon recognition of the condition the employee took action to secure both doors. The cause of this event was malfunction of the secondary containment airlock door interlock.

"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(v)(C), event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material. With both doors open, Surveillance Requirement 3.6.4.1.3 of Technical Specification 3.6.4.1, Secondary Containment, was not met, rendering secondary containment inoperable.

"Repairs to the secondary containment airlock door interlock have been completed.

"This event did not result in any adverse impact to the health and safety of the public.

"The NRC Senior Resident Inspector has been notified."

Page Last Reviewed/Updated Wednesday, May 14, 2014
Wednesday, May 14, 2014