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> July 23
Current Event Notification Report for July 23, 2014
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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/22/2014 - 07/23/2014
** EVENT NUMBERS **
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| Agreement State |
Event Number: 49971 |
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: CNA METALS INC.
Region: 4
City: STAFFORD State: TX
County:
License #: 02260
Agreement: Y
Docket:
NRC Notified By: ART L. TUCKER
HQ OPS Officer: STEVE SANDIN
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Notification Date: 03/28/2014
Notification Time: 18:28 [ET]
Event Date: 03/26/2014
Event Time: [CDT]
Last Update Date: 07/22/2014
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Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
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Person (Organization):
DAVID PROULX (R4DO)
DENNIS ALLSTON (ILTA)
FSME_EVENTS RESOURCE (EMAI)
MEXICO (FAX)
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This material event contains a "Less than Cat 3
" level of radioactive material.
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Event Text
AGREEMENT STATE REPORT INVOLVING A STOLEN THERMO NITON DEVICE USED IN METAL ALLOY IDENTIFICATION
The following information was provided by the State of Texas via email:
"On March 28, 2014, the Agency [Texas Department of State Health Services] received a letter from the licensee Radiation Safety Officer (RSO) stating they had determined a Thermo Niton device model number XLP-8182 containing 30 millicuries of Americium- 241 had been stolen by one of their employees. The employee had been sent to the country of Mexico with the device to analyze materials for purchase by their company. The RSO stated when they had gone several weeks without contact with the employee they began trying to locate him. The RSO stated they had not located either the employee or the device. The RSO stated he did not believe the individual had come to any harm in Mexico, but stated they had heard the employee had bought a new home in the State of Arizona and was probably there. The licensee has contacted local law enforcement. The RSO stated they did not believe any individual would receive any exposure due to this event. The Agency will contact the State of Arizona's program on March 31, 2014. Additional information will be provided as it is received in accordance with SA-300."
The device is used to identify metal alloys.
Texas Incident #: I-9172
* * * UPDATE AT 1147 EDT ON 07/22/14 FROM ART TUCKER TO S. SANDIN * * *
The following information was provided by the State of Texas via email:
"This update is provided to correct the licensee's name, the model number of the device and provide additional information. The Company's name is CNA Metals Inc. and not CAN Metals as initially reported. The model number for the device is XLP 818Q and not XLP 8182 as initially reported. During the Agency's investigation, the licensee stated they had not authorized the individual to take the device into the country of Mexico. The licensee has no information that confirms the device entered the country of Mexico. Additional information will be provided as it is received in accordance with SA 300."
Notified R4DO (Miller), ILTAB (email), FSME Events Resource (email) and Mexico (fax).
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Agreement State |
Event Number: 50280 |
Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: GEO/ENVIRONMENTAL ASSOCIATES
Region: 1
City: HATFIELD State: KY
County:
License #: 45-31292-01
Agreement: Y
Docket:
NRC Notified By: CURT PENDERGRASS
HQ OPS Officer: CHARLES TEAL
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Notification Date: 07/14/2014
Notification Time: 15:47 [ET]
Event Date: 07/11/2014
Event Time: 14:00 [CDT]
Last Update Date: 07/14/2014
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Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
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Person (Organization):
CHRISTOPHER CAHILL (R1DO)
FSME EVENT RESOURCE (EMAI)
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Event Text
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The following was received from the Commonwealth of Kentucky via email:
"KY RHB [Kentucky Radiation Health Branch] was notified by telephone on 7/11/14 by Todd Ramkey, Corporate RSO at Schnabel Engineering Inc. in Glenn Allen, VA, of the fact that a CPN model MC-1 portable moisture/density gauge had been run over and crushed at a coal slurry impoundment belonging to Long Fork Coal Company in Hatfield, KY. The CPN gauge contained 10 mCi of Cs-137 and 50 mCi of Am-241/Be.
"Initial surveys performed by the licensee with a RadAlert GM survey instrument indicated the sources were not breached and that there was no contamination on the ground where the incident occurred or on the bulldozer involved. The shattered pieces of the device, including the two sources, were packaged on-site by the licensee into a 55 gallon drum in accordance with guidance provided by the radiation safety staff at Instro-Tek in Raleigh, NC, labeled appropriately and shipped back to the offices of Geo/Environmental Associates, Inc. in Knoxville, TN in a company owned vehicle. The shipment was met by a representative of the TN Division of Radiological Health where follow-on surveys and contamination smears were taken. They also instructed the licensee to send leak test wipes to Instro-Tek for expedited analysis and instructed the licensee to send personal monitoring for those involved in for analysis.
"A telephone call to RHB from the CRSO at Schnabel on 7/14/14 at approximately 1500 said indicated leak test results from Instro-Tek were less than the 185 Bq limit and that no breach of the sources had occurred. RHB gave the CRSO permission to release the control of the site and the equipment at Long Fork Coal based on these negative leak test results. The CRSO at Schnabel indicated that hardcopies of the leak test results would be provided to both RHB and TN Div. Rad Health as well as the results of personal monitoring for those involved in the incident including transportation of the gauge back to Knoxville. Reporting criteria defined in 902 KAR 100:040, Section 15(2)(b) [10 CFR 30.50(b)(2)]." |
| Power Reactor |
Event Number: 50289 |
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: MATT KERCHENFAUT
HQ OPS Officer: DONG HWA PARK
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Notification Date: 07/21/2014
Notification Time: 06:42 [ET]
Event Date: 07/21/2014
Event Time: 05:25 [CDT]
Last Update Date: 07/22/2014
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
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Person (Organization):
PATTY PELKE (R3DO)
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| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
| 3 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
TECHNICAL SUPPORT CENTER OUT OF SERVICE FOR PLANNED PREVENTATIVE MAINTENANCE
"At 0525 [CDT] on Monday, July 21, 2014, the Dresden Nuclear Power Station (DNPS) Technical Support Center (TSC) emergency ventilation system was removed from service for planned preventative maintenance activities on the TSC air handling unit, air compressor units, and TSC air filtration unit. During the maintenance, the TSC Ventilation was shut down. The TSC air filtration fan and dampers are non-functional, rendering the TSC HVAC accident mode nonfunctional. This maintenance is scheduled to minimize out of service time. The planned TSC ventilation outage is scheduled to be completed within 48 hours. Contingency plans are in place so that if an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing Emergency Planning (EP) procedures and checklists. If radiological or environmental conditions require TSC facility evacuation during ventilation system restoration; the Station Emergency Director will evacuate and relocate the TSC staff in accordance with station procedures.
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM MATT KERCHENFAUT TO DONALD NORWOOD AT 2035 EDT ON 7/22/2014 * * *
"At 1540 CDT on July 22, 2014, Dresden TSC Ventilation was restored. The Dresden TSC Ventilation is functional at this time.
"The NRC Resident Inspector has been notified."
Notified R3DO (Orth). |
| Power Reactor |
Event Number: 50293 |
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: WILLIAM TAYLOR
HQ OPS Officer: DONG HWA PARK
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Notification Date: 07/22/2014
Notification Time: 07:53 [ET]
Event Date: 07/22/2014
Event Time: 04:14 [EDT]
Last Update Date: 07/22/2014
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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
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Person (Organization):
GERALD MCCOY (R2DO)
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| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
A/R |
Y |
48 |
Power Operation |
0 |
Hot Standby |
Event Text
AUTOMATIC REACTOR TRIP DUE TO LOW STEAM GENERATOR LEVEL
"At 0414 [EDT on 7/22/2014], VC Summer Nuclear Station automatically tripped due to decreasing water level in the 'C' Steam Generator. The trip occurred when valve XVB-09210 WI System Condensate Bypass Valve failed to open as required while the station was removing the Condensate Polishing System during startup. The Condensate Polishing System is used to purify and filter the condensate from the non-nuclear, secondary side of the plant. This valve failure caused low level in the Deaerator Storage Tank, which consequently tripped all feedwater pumps. This loss of feedwater led to Lo-Lo Steam Generator level in the 'C' Steam Generator. All Emergency Feedwater pumps automatically started on Lo-Lo Steam Generator level and all control rods inserted fully. The Steam Generator levels recovered quickly.
"Presently the plant is in Mode 3. Decay heat is being removed by dumping steam to the condenser. A station response team is actively investigating the cause of the event.
"The NRC Resident Inspector has been notified."
The licensee will notify the State and local governments. |
| Power Reactor |
Event Number: 50294 |
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: NICHOLAS E. RULLMAN
HQ OPS Officer: STEVE SANDIN
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Notification Date: 07/22/2014
Notification Time: 16:57 [ET]
Event Date: 07/22/2014
Event Time: 06:35 [PDT]
Last Update Date: 07/22/2014
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
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Person (Organization):
GEOFFREY MILLER (R4DO)
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| 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
RADIATION MONITORING SAMPLE RACK DECLARED NON-FUNCTIONAL
"At 0635 hours PDT on July 22, 2014, Turbine Building Exhaust Air Radiation Indicating Switch (TEA-RIS-13) and the Turbine Building Process Radiation Monitoring Sample Rack (TEA-SR-26) were declared non-functional. The cause of the malfunction is under investigation. Compensatory measures have been implemented to obtain radiation readings from the associated effluent release pathway. Field team assessment function was unaffected and remains available.
"This event is being reported as a major loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor |
Event Number: 50296 |
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL JONES
HQ OPS Officer: STEVE SANDIN
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Notification Date: 07/22/2014
Notification Time: 21:36 [ET]
Event Date: 07/22/2014
Event Time: 13:43 [EDT]
Last Update Date: 07/22/2014
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
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Person (Organization):
MEL GRAY (R1DO)
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| 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
DIESEL GENERATOR FOR HIGH PRESSURE CORE SPRAY DECLARED INOPERABLE DURING SURVEILLANCE TESTING
"This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to Mitigate the Consequences of an Accident. During the conduct of the Unit 2 Division 3 High Pressure Core Spray (HPCS) Diesel Generator (DG) surveillance test, one of 2 Cooling Water Outlet Valves failed to automatically open. The Division 3 Diesel is supplied by two redundant trains of cooling water one from each Service Water Divisional Header. Although the redundant cooling water supply was fully available and supplied adequate cooling to the diesel generator, the DG was at reduced margin to have adequate cooling water supply, if required during a loss of offsite power. Due to this loss of margin and inoperable condition, it has been determined that this failure could potentially affect the safety function of this system, and is being reported as an 8 hour ENS notification."
The licensee has attributed the failure to high resistance in a relay which is currently being replaced. This places Unit 2 in the Technical Specification Action Station 3.8.1, which requires restoration of Diesel Generator within 72 hours or commence a Reactor Shutdown. All other ECCS Systems have been verified operable.
The licensee informed the NRC Resident Inspector and will inform the State of New York. |
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