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Event Notification Report for April 03, 2014

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
04/02/2014 - 04/03/2014

EVENT NUMBERS
5000049993499944999549991

Agreement State
Event Number: 50000
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: HI-TECH TESTING SERVICES
Region: 4
City: BEEVILLE   State: TX
County:
License #: L05021
Agreement: Y
Docket:
NRC Notified By: ROBERT FREE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/04/2014
Notification Time: 18:18 [ET]
Event Date: 04/03/2014
Event Time: 00:00 [CDT]
Last Update Date: 04/04/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (EMAI)
Event Text
TEXAS AGREEMENT STATE REPORT - STUCK RADIOGRAPHY SOURCE

The following information was obtained from the State of Texas via email:

"The licensee called to report that a radiography crew had damaged the source guide tube of their QSA 880D industrial radiography camera. The incident occurred at a temporary job site near Beeville, Texas. The crew was working in some elevated pipe racks and had used a rope to suspend the camera. The knot on the rope came loose, dropping the camera to the ground. The camera landed on the source guide tube crimping it and preventing the retraction of the radiography source which was extended into the collimator. A second radiography crew on the site secured their camera and placed it on the collimator to shield the source. The radiographers then called an RSO in Deer Park, Texas and another in Corpus Christi, Texas to get advice and instruction to secure the source. The crew then dragged the camera to a shielded location behind a concrete pillar. Two radiographer trainees were assigned to maintain a perimeter around the camera to prevent access by unmonitored individuals. The radiographers were able to use pliers to un-crimp the source guide tube and return the source to its shielded position."

No radiography personnel received overexposures due to this event.

Texas Incident # I-9177


Power Reactor
Event Number: 49993
Facility: BRUNSWICK
Region: 2     State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CRAIG OLIVER
HQ OPS Officer: DANIEL MILLS
Notification Date: 04/03/2014
Notification Time: 11:43 [ET]
Event Date: 04/03/2014
Event Time: 10:06 [EDT]
Last Update Date: 04/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
STEVEN VIAS (R2DO)
Power Reactor Unit Info
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
OFFSITE NOTIFICATION DUE TO OIL SPILL ON SITE

"At 0730 EDT on April 3, 2014, it was determined that approximately 40 gallons of turbine lube oil (MOBIL DTE 732) had been released to the ground from the Unit 1 Turbine Building. The release occurred during the process of depressurizing the Unit 1 main generator. The source of the leak was identified and secured. The area of the oil spill has been contained, [and] no oil reached storm sewers or surrounding waters.

"Notification of the lube oil spill was made to the Underground Storage Tank Section of the North Carolina Division of Waste Management at 1006 hours EDT on April 3, 2014. This report is made in accordance with 10 CFR 50.72(b)(2)(xi) as an event related to protection of the environment for which notification to another government agency has been made.

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

"The safety significance of this event is minimal. There was no adverse impact to public health and safety. The area of the oil spill has been contained, no oil reached storm sewers or surrounding waters. Efforts are in progress to excavate the soil containing the lube oil.

"The source of the lube oil leak was identified and secured. Efforts are in progress to excavate the soil containing the lube oil."

The licensee has notified the NRC Resident Inspector.


Power Reactor
Event Number: 49994
Facility: HARRIS
Region: 2     State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICHARD HONEYCUTT
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/03/2014
Notification Time: 13:54 [ET]
Event Date: 04/03/2014
Event Time: 09:06 [EDT]
Last Update Date: 04/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
STEVEN VIAS (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
EMERGENCY SIRENS DECLARED NONFUNCTIONAL

"At approximately 0906 EDT, the Harris Nuclear Plant (HNP) offsite emergency sirens were identified to be nonfunctional. Troubleshooting was initiated and the offsite emergency sirens were restored and verified to be functional at 1127 EDT. This event requires an 8-hour non-emergency notification per 10CFR 50.72(b)(3)(xiii) due to the loss of a significant portion of the offsite notification system. In the event that the sirens would have been needed, the State of North Carolina and all four counties within the 10-mile emergency planning zone would have implemented mobile route alerting, as detailed in the Emergency Plan.

"The NRC Senior Resident Inspector was informed. There was no impact to public health and safety."


Power Reactor
Event Number: 49995
Facility: ARKANSAS NUCLEAR
Region: 4     State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: ROBERT W. CLARK
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/03/2014
Notification Time: 17:08 [ET]
Event Date: 04/03/2014
Event Time: 13:01 [CDT]
Last Update Date: 04/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
HEATHER GEPFORD (R4DO)
TIM McGINTY (NRR)
WILLIAM GOTT (IRD)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Standby
Event Text
AUTOMATIC REACTOR TRIP

"At approximately 1301 [CDT] on 4/3/2014, Unit 2 tripped from 100% power for unknown reason(s). All Control Element Assemblies [CEA] inserted into the core. (Note that CEA 03 Plant Monitoring System indication still indicates fully withdrawn. However, CEA 03 in-limit light and control panel indication validate that CEA 03 is fully inserted.) 4160v bus 2A1 and 6900v bus 2H1 transferred to Startup Transformer #2. 4160v bus 2A2 appeared to de-energize and re-energize on Startup Transformer #3. 6900v bus 2H2 is de-energized. 2K4B emergency diesel generator started but did not tie onto the 2A4 4160v bus. Emergency Feedwater actuated on low steam generator level."

Offsite power remains available and decay heat is being removed to the main condensers using the turbine bypass valves. Unit 1 was not affected.

The licensee has notified the NRC Resident Inspector and will notify the State.


Power Reactor
Event Number: 49991
Facility: MCGUIRE
Region: 2     State: NC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WESLEY HILL
HQ OPS Officer: DANIEL MILLS
Notification Date: 04/03/2014
Notification Time: 02:44 [ET]
Event Date: 04/03/2014
Event Time: 01:00 [EDT]
Last Update Date: 04/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
STEVEN VIAS (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling
Event Text
REACTOR COOLANT SYSTEM SAFETY INJECTION LINE ULTRASONIC TEST INDICATION

"On Tuesday, April 1, 2014, while performing planned inspections of Reactor Coolant System piping welds, two flaw indications were identified on a 1.5 inch Safety Injection Line connection to the Reactor Coolant System piping. On Wednesday, April 2, 2014, after confirmatory inspections and evaluation, one of the two flaw indications was determined to not meet the acceptance criteria specified in ASME Code Section XI. As such, this indication is reportable under 10 CFR 50.72(b)(3)(ii) as a degraded condition. A repair plan is being developed. There is no impact on current Unit 2 refueling operations. This condition and repair have no impact to the health and safety of the public or employees.

"The NRC Resident Inspector was notified."