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Event Notification Report for January 17, 2014

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
01/16/2014 - 01/17/2014

EVENT NUMBERS
49735497364973849739

Power Reactor
Event Number: 49735
Facility: FARLEY
Region: 2     State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN ANDREWS
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/17/2014
Notification Time: 12:45 [ET]
Event Date: 01/17/2014
Event Time: 09:25 [CST]
Last Update Date: 01/17/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MICHAEL F. KING (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
Event Text
PYRO PANEL TAKEN OUT OF SERVICE FOR PLANNED MAINTENANCE

"At 0925 [CST] on January 17, 2014, the Unit 1 pyro panel (smoke detection panel) was removed from service for required maintenance. The pyro panel was declared non-functional when it was removed from service. Compensatory measures have been established for all affected areas except the Unit 1 Containment Building. Since a fire in Containment is an entry condition for the site's Emergency Plan, this is considered a loss of emergency assessment capability and is being reported per 10CFR50.72(b)(3)(xiii). Containment temperatures are being monitored while the pyro panel is out of service, however, this is not considered a satisfactory compensatory measure for maintaining effective assessment capability.

"The site NRC Resident Inspector has been notified."

* * * UPDATE FROM DARRIN GARD TO CHARLES TEAL AT 2202 EST ON 1/17/14 * * *

The pyro panel was restored to service as of 1650 CST. The licensee has notified the NRC Resident Inspector.

Notified R2DO (King).


Power Reactor
Event Number: 49736
Facility: WATTS BAR
Region: 2     State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HENRY TAYLOR
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/17/2014
Notification Time: 12:50 [ET]
Event Date: 01/17/2014
Event Time: 11:43 [EST]
Last Update Date: 01/17/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MICHAEL F. KING (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 N 0 Under Construction 0 Under Construction
Event Text
OFFSITE NOTIFICATION DUE TO ONSITE DEATH OF AN EMPLOYEE

"On January 17, 2014, at approximately 0931 EST, with Watts Bar Nuclear Unit 1 at 100% power and Unit 2 under construction, an off duty security officer was found unresponsive in a personal vehicle in an owner controlled parking lot located outside of the Protected Area.

"An emergency medical team responded and the individual was transported off site to a nearby medical facility where he was pronounced dead at 1143 EST. The individual was not contaminated and there were no radiological or industrial safety issues associated with Watts Bar Nuclear Plant. Due to notification of local sheriff and OSHA, this report is submitted pursuant to 10 CFR 50.72(b)(2)(xi), as a notification to a government agency.

"NRC Senior Resident Inspector has been notified."


Power Reactor
Event Number: 49738
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: CHARLES TEAL
Notification Date: 01/17/2014
Notification Time: 14:54 [ET]
Event Date: 01/17/2014
Event Time: 14:00 [EST]
Last Update Date: 01/17/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MICHAEL F. KING (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
FUEL OIL FOUND DURING CORE DRILLING

"On January 17, 2014, at 1400 EST Sequoyah (SQN) notified the Tennessee Department of Environment and Conservation (TDEC) of a condition that was identified on December 4, 2013, while conducting core samples. The core drilling contractor detected a petroleum odor, notified the SQN Environmental Group who observed the core drilling and confirmed a slight petroleum odor from a core boring in which water was detected at approximately 41 feet below the ground surface. At that time, as a result of the type of core drilling that was conducted, TVA could not verify if there were petroleum products in the groundwater.

"SQN obtained geoprobe boring samples to determine the extent and the depth of the petroleum. Petroleum product was detected in the soil between 30 and 35 feet in depth. This condition has been determined to be associated with a legacy diesel fuel oil leak at SQN in the 1990's and was previously reported. SQN previously completed a remediation project from 1992 - 2010, with oversight from TDEC. The petroleum product appears to be isolated at approximately 30 to 35 feet in depth, is in a perched water table not utilized for drinking water, and appears to be isolated to the diesel building area. To verify the petroleum product is isolated; TVA is conducting additional geoprobe boring to help define the limited area impacted by the legacy diesel fuel oil leak.

"The Sequoyah NRC Resident Inspectors have been notified."


Power Reactor
Event Number: 49739
Facility: MONTICELLO
Region: 3     State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: ANGEL BRAY
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/17/2014
Notification Time: 23:11 [ET]
Event Date: 01/17/2014
Event Time: 17:36 [CST]
Last Update Date: 01/17/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 91 Power Operation 0 Cold Shutdown
Event Text
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO REACTOR PRESSURE BOUNDARY LEAKAGE

"Leakage into the Reactor Building Closed Cooling Water (RBCCW) system has been determined to be Reactor Pressure Boundary leakage as identified by the plant's Technical Specification [LCO 3.4.4]. Based on this, the LCO is not met and a plant shutdown is required. The shutdown commenced at 2029 CST.

"All of the leakage has been retained within the RBCCW system. There has been no radioactive release from the Monticello plant and all other systems remain operable and available. The unit continues to be operated in a safe and predictable fashion as it is being removed from service.

"The NRC Resident Inspector has been notified."

The leakage rate was 0.12 gallons per minute at power.