United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for August 19, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/16/2013 - 08/19/2013

** EVENT NUMBERS **


49250 49251 49254 49255 49258 49264 49270 49287 49288

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Agreement State Event Number: 49250
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: AEROJET ORDNANCE TENNESSEE
Region: 1
City: JONESBOROUGH State: TN
County:
License #: S-90009
Agreement: Y
Docket:
NRC Notified By: LAURA TURNER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/08/2013
Notification Time: 11:09 [ET]
Event Date: 08/05/2013
Event Time: 10:00 [EDT]
Last Update Date: 08/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES TRAPP (R1DO)
FSME EVENT RESOURCES (E-MA)

Event Text

AGREEMENT STATE REPORT - ELEVATED AIRBORNE URANIUM LEVELS DUE TO EQUIPMENT MALFUNCTION

The following report was received from the State of Tennessee Division of Radiological Health via e-mail:

"Tennessee's Division of Radiological Health was notified on Wednesday August 7, 2013 by the RSO from Aerojet Ordnance Tennessee, regarding the failure of a primary ventilation system. On August 5, 2013 at 10:00 AM, an employee at the Deflash Station observed smoke outside the operation booth while grinding burrs off radiography camera castings. A supervisor was notified and investigation showed the ventilation system was working, but the belt connecting the pump and fan was broken. Operations were suspended and personnel evacuated.

"The belt was replaced on the pumps and the ventilation system was up and operational by 10:30 AM. Event resulted in elevated airborne uranium concentrations. All personnel in the building submitted urinalysis. Workers at the Deflash station were wearing respiratory protection during time of event as part of standard procedures. Area air samplers along with environmental air samplers were pulled and analyzed; initial results identified no concerns of elevated concentrations.

"The State will follow-up and keep NRC informed of the status of our investigation."

Tennessee Report Number:TN-13-134

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Agreement State Event Number: 49251
Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: NCM USA BRONX, LLC
Region: 1
City: Bronx State: NY
County:
License #: NYS C5494 & C
Agreement: Y
Docket:
NRC Notified By: ROBERT DANSEREAU
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/08/2013
Notification Time: 16:06 [ET]
Event Date: 07/15/2013
Event Time: [EDT]
Last Update Date: 08/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES TRAPP (R1DO)
FSME EVENTS RESOURCE (EMAI)
PAMELA HENDERSON (FSME)

Event Text

AGREEMENT STATE REPORT - EXTREMITY DOSE EXCEEDS LIMIT

The following information was obtained from the State of New York via facsimile:

"On 08/07/2013, the licensee called to report an overexposure of an individual as measured with an extremity monitoring device (ring badge). The licensee had been notified by the processor on the morning of 08/07/13 in regard to the 242 rem shallow extremity dose. The monitoring period for the ring badge is one week, and the whole body monitors are exchanged on a monthly basis. The affected individual is a male production technologist whose duties include cyclotron operations. The RSO and consulting health physicist are investigating and NYS DOH [New York State Department of Health] will perform an onsite review. The licensee has reassigned the technologist to non-radiological duties, sent the individual's whole body badge via overnight service for an emergency read and has requested the badge vendor to perform any additional analysis of the ring badge that may provide additional information. This event summary will be updated after the results of the licensee's and DOH's investigations are available."

New York Event Number: NY-13-04

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Agreement State Event Number: 49254
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: FLAKEBOARD AMERICA, LLC
Region: 4
City: MALVERN State: AR
County:
License #: ARK-0664-0312
Agreement: Y
Docket:
NRC Notified By: TAMMY KRIESEL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/09/2013
Notification Time: 10:26 [ET]
Event Date: 02/09/2011
Event Time: [CDT]
Last Update Date: 08/09/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL VASQUEZ (R4DO)
FSME EVENT RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - SHUTTER PROBLEM ON A GAMMA GAUGE

The following report was received via e-mail from the State of Arkansas Radiation Control Program:

"During an on-site inspection on August 8, 2013, the licensee stated that a VEGA Americas Corporation model A-2102 gamma gauge shutter was vibrating shut. The source rotor and top plate was replaced on February 9, 2011. The gauge is serial number 6757GK and contains 10 mCi of Cesium-137.

"The licensee indicated the gauge was locked out and unused until it was repaired.

"In accordance with RH-1502.f.2. (10 CFR 30.50(b)(2)) the stuck shutter should have been reported to the State of Arkansas within 24 hours.

"The State of Arkansas is awaiting a written report from the licensee. "

Arkansas Report: ARK-2013-005.

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Agreement State Event Number: 49255
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: GEOTECHNICAL ENVIRONMENTAL TESTING SOLUTIONS, INC
Region: 1
City: VIRGINIA BEACH State: VA
County:
License #: VA-810-333-1
Agreement: Y
Docket:
NRC Notified By: MIKE WELLING
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/09/2013
Notification Time: 10:40 [ET]
Event Date: 08/08/2013
Event Time: 23:00 [EDT]
Last Update Date: 08/09/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES TRAPP (R1DO)
FSME EVENT RESOURCES ()

Event Text

AGREEMENT STATE REPORT - FIRE DAMAGES A TROXLER MOISTURE DENSITY GAUGE

The following report was received via fax:

"An employee of GET [Geotechnical Environmental Testing] went home with a Troxler 3430 portable gauge in the bed of his work truck. The employee mishandled charcoal embers after cooking dinner on a grill, which caused the bed of the truck to start on fire. A neighbor noticed the fire and called 911 . When the fire trucks arrived, the employee discovered it was his truck on fire and talked with the VA Beach fire personnel. He stated that a portable gauge containing radioactive material was in the bed of the truck. The VA Beach hazmat team was contacted and arrived on scene. The fire was extinguished and surveys were performed by the hazmat team indicating 1 mR/hr, a normal. reading for a secured gauge. The GET employee began to contact management regarding the situation. The VA Beach GET RSO was on vacation so the North Carolina GET RSO responded and also performed surveys when he arrived. Survey readings indicated the sources were in their shielded position. The RSO was able to package the damaged gauge into another transportation case and return it to the VA Beach office. GET has contacted Troxler and has sent a swab for leak test analysis. The gauge will be returned to Troxler after verification of the sources not leaking. There is no threat to public health or safety from this event. The Virginia RMP [Radiological Materials Program] will be performing an investigation and inspection.

"Media attention: Yes, two local news stations ran a story this morning on the incident."

VA Report ID: VA-13-06

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Fuel Cycle Facility Event Number: 49258
Facility: B&W NUCLEAR OPERATING GROUP, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: KENNY KIRBY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/09/2013
Notification Time: 16:20 [ET]
Event Date: 08/09/2013
Event Time: 13:00 [EDT]
Last Update Date: 08/09/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
Person (Organization):
SCOTT SHAEFFER (R2DO)
BRIAN SMITH (NMSS)
FUELS OUO GROUP (EMAI)

Event Text

STORAGE RACKS DETERMINED TO BE IN AN UNANALYZED CONDITION

EVENT DESCRIPTION:

"At B&W's NOG-L [Nuclear Operations Group - Lynchburg] facilities, scrap and waste material is generated during fuel bearing operations. Certain streams are collected in favorable volume less than or equal to 2.5 liter containers and eventually transferred to the Drum Count Area for U-235 assay. Because the U-235 content of such containers is not known until they have been assayed, they are referred to as 'unknowns' and are subject to a bulk weight limit. These containers are limited to a maximum of 7,000 grams net weight (approximately 15 pounds). The unknowns are stored on designated less than or equal to 2.5 liter container storage racks.

"The construction of the storage racks controls the spacing between storage locations and the distance from the floor. The racks' materials of construction are credited as a fixed neutron poison. Some of the unknown racks are fitted with an additional poison plate which allows the rack-to-rack spacing to be reduced.

"On August 9, 2013, at approximately 1:00 p.m., a contract Nuclear Criticality Safety (NCS) engineer working with B&W's NCS staff identified a safety concern. While working to consolidate information in several Safety Analysis Reports, it was determined that the poisoned less than or equal to 2.5 liter storage racks fitted with a horizontal poison plate were improperly analyzed.

EVALUATION OF THE EVENT:

"The NCS evaluation of the poisoned less than or equal to 2.5 liter storage racks fitted with a horizontal poison plate was completed in October of 2000. The analysis was based on an evaluation of a poisoned transport cart completed earlier the same year. However, a review by the B&W NCS staff indicated the conclusions of this earlier analysis were not properly applied to the analysis of the poisoned less than or equal to 2.5 liter storage racks fitted with a horizontal poison plate. The racks were improperly analyzed.

"The requirement of 10 CFR 70.61 (d) states in part: '...the risk of nuclear criticality accidents must be limited by assuring that under normal and credible abnormal conditions, all nuclear processes are subcritical, including use of an approved margin of subcriticality for safety.'

"Further evaluation of the poisoned less than or equal to 2.5 liter storage racks fitted with a horizontal poison plate indicated that under optimal moderation the keff exceeds the safety limit of 0.95 in NRC License SNM-42. Therefore the performance requirement of 10 CFR 70.61 (d) was not maintained.

NOTIFICATION REQUIREMENTS:

"B&W is making this 24 hour report in accordance with 10 CFR 70, Appendix A, (b)(1) - 'Any event or condition that results in the facility being in a state that was not analyzed, was improperly analyzed, or is different from that analyzed in the Integrated Safety Analysis, and which results in failure to meet the performance requirements of 70.61.'

"There was no immediate risk of a criticality or threat to the safety of workers or the public as a result of this event. A portion of the storage locations in the poisoned less than or equal to 2.5 liter storage racks fitted with a horizontal poison plate were removed from service. This action was taken to restore compliance with the performance requirements of 10 CFR 70.61.

STATUS OF CORRECTIVE ACTIONS:

"An investigation of the root causes of this event is ongoing. Corrective actions will be determined as a result of the investigation."

The licensee has notified the NRC Resident Inspector.

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Agreement State Event Number: 49264
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: AMC THEATRES FASHION VALLEY 18
Region: 4
City: SAN DIEGO State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: L. ROBERT GREGER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/11/2013
Notification Time: 23:26 [ET]
Event Date: 07/02/2013
Event Time: [PDT]
Last Update Date: 08/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL VASQUEZ (R4DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)

Event Text

AGREEMENT STATE REPORT - SEVEN STOLEN TRITIUM EXITS SIGNS

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

The California Department of Public Health received the following information from the licensee:

"Please be advised that during a survey of the location seven missing exit signs were discovered in the exit corridors.

"Having been stolen prior to site survey we are unable to provide the specific manufacturer or serial number of the stolen units. A police report was filed (case: 13705804) within the jurisdiction of San Diego with the San Diego Police Department. The state of California has also been notified."

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Power Reactor Event Number: 49270
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: KEVIN ABELL
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 08/12/2013
Notification Time: 20:56 [ET]
Event Date: 08/12/2013
Event Time: 15:50 [EDT]
Last Update Date: 08/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
SCOTT SHAEFFER (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 (TSC) VENTILATION OUT OF SERVICE DUE TO DISCOVERED CONDITION

"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as the discovered condition affects the functionality of an emergency response facility. There is no impact to public health and safety due to this condition.

"On August 12, 2013 at 1550 [EDT], during routine testing of the HVAC [Heating Ventilation Air Conditioning] system, the TSC Emergency filtration Fan, MUF-1, was observed to have high vibration levels. Maintenance is working to determine the cause of the high vibrations and to make necessary repairs.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. If the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions, the Site Emergency Coordinator - TSC will relocate the TSC staff to an alternate TSC in accordance with applicable site procedures. The Emergency Response Organization team has been notified of the condition and the possible need to respond to or relocate to an alternate TSC during an emergency.

"An update will be provided once the TSC ventilation has been restored to normal operation. The NRC Resident Inspector has been notified."

* * * UPDATE ON 8/16/13 AT 2126 EDT FROM TIM ENGLISH TO DONG PARK * * *

"Technical Support Center (TSC) ventilation has been returned to service on August 16, 2013 at 2100 [EDT] following bearing replacement on TSC Emergency Make-up Fan, MUF-1. Post maintenance testing has been completed and the emergency response facility is functional."

The licensee has notified the NRC Resident Inspector.

Notified R2DO (Musser).

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Power Reactor Event Number: 49287
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DARRELL JOHNSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/16/2013
Notification Time: 02:36 [ET]
Event Date: 08/15/2013
Event Time: 18:24 [PDT]
Last Update Date: 08/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RAY KELLAR (R4DO)

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

LOSS OF STARTUP POWER RESULTS IN VALID STARTS OF ALL THREE EMERGENCY DIESEL GENERATORS

"At 1824 PDT on August 15, 2013, Unit 1 experienced a loss of startup power due to a failure of Startup Transformer 1-1 load tap changer. This loss caused a valid auto-start signal to all three emergency diesel generators and they all started successfully. At 1921, all EDGs were shutdown and returned to standby per plant procedures."

As a result of the loss of startup power, power was also lost to site service buildings. ERDS was lost but compensatory measures are in place to transmit required data via the ENS line if required.

The plant is in a 72-hr. shutdown LCO action statement under T.S. 3.8.1 for the loss of one of three qualified circuits. The two other qualified circuits (vital power via auxiliary transformers and the EDGs) remain operable.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49288
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RUSSELL A. STROUD
HQ OPS Officer: DONG HWA PARK
Notification Date: 08/16/2013
Notification Time: 13:50 [ET]
Event Date: 06/09/2013
Event Time: 20:16 [EDT]
Last Update Date: 08/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
RANDY MUSSER (R2DO)
PART 21 GROUP (EMAI)

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

PART 21 - AUXILIARY FEEDWATER LEVEL CONTROL VALVE STEM/PLUG ASSEMBLY OUT OF TOLERANCE

"On June 9, 2013, Auxiliary Feedwater Level Control Valve [AFW LCV] 1-LCV-3-156-A, failed its closed-to-open stroke time during quarterly surveillance testing. This level control valve is a basic component which regulates auxiliary feedwater (AFW) flow to Steam Generator 2. The valve failed to open during two attempts. Local observation during testing indicated that the valve 'popped' off the seat, and then traveled smoothly to its full open position on the third and fourth attempt. The failure was determined to be a Maintenance Rule Functional Failure and a CC1 Functional Failure. There were no previous indication(s) of this failure mode during the previous quarterly stroke time testing. The valve internals were replaced on October 7, 2009, during a refueling outage.

"TVA installed a new trim kit which included the cage, lower seat ring, and stem/plug assembly. The valve was returned to service on June 12, 2013, following successful post modification testing. A Kepner-Tregoe (K-T) problem analysis revealed the direct cause was binding due to the stem/plug assembly being out of tolerance. Upon inspection, the Total Indicated Run-out (TIR) of the stem/plug assembly removed from the affected valve was determined to be 0.022 inches. The valve was manufactured by Dresser Masoneilan with a TIR specification of less than or equal to 0.005 inches. The valve model and stem/plug assembly part numbers are:

"Valve: Masoneilan Model 37-20721, 4 inch Control Valve
"Stem: 012160204-215-J000
"Plug: 011501710-1H6U

"Inspection of the five unused spare stem/plug assemblies in storage had a TIR that ranged from 0.006 to 0.022 inches, which is outside vendor specifications. Because the stem/plug assembly removed from the affected AFW LCV and five of the unused stem/plug assemblies were found to be out-of-tolerance, a condition exists and is being reported in accordance with 10CFR50 Part 21.21(d).

"Similar LCVs in the AFW systems were tested and are OPERABLE with no known defects.

"A detailed report using NRC Form 366, Licensee Event Report, will be submitted to the NRC by 09/15/13 in accordance with 10CFR50 Part 21.21(d)(3)(ii)."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Monday, August 19, 2013
Monday, August 19, 2013