United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for June 13, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/12/2012 - 06/13/2012

** EVENT NUMBERS **


47989 47991 47993 47994 47996 48016 48018 48019

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Non-Agreement State Event Number: 47989
Rep Org: NUCLEAR REGULATORY COMMISSION R-I
Licensee: NUCLEAR REGULATORY COMMISSION R-I
Region: 1
City: KING OF PRUSSIA State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: RAY LORSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/01/2012
Notification Time: 15:09 [ET]
Event Date: 05/08/2012
Event Time: [EDT]
Last Update Date: 06/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
ANGELA MCINTOSH (FSME)
ILTAB (EMAI)
FSME EVENTS (EMAI)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

MISSING CHECK SOURCE

"On May 8, 2012, Region I identified that a survey instrument check source containing approximately 2.64 microCuries of strontium-90 was missing. The source is believed to have been inside of a metal cabinet that was inadvertently discarded on May 2, 2012, during the removal of excess property in preparation for relocation of the regional office. The source is not considered to be a hazard to public health and safety due to its low activity level and beta emission decay path. Upon discovery, the Region implemented several immediate actions including: attempts to locate and retrieve the source; confirmation that the remaining instrument check source was properly secured; and, a courtesy notification regarding this issue to the Commonwealth of Pennsylvania. In addition, a review of this event, consistent with the NRC's Management Directives, was initiated to identify and implement appropriate follow-up actions to prevent recurrence.

"This report is being submitted in accordance with NRC MD 10.131, Part V for missing material in a quantity greater than 10 times the quantity specified in 10 CFR 20 Appendix C."

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

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Agreement State Event Number: 47991
Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: TESTAMERICA ANALYTICAL TESTING CORP.
Region: 4
City: BEAVERTON State: OR
County:
License #: ORE-90559
Agreement: Y
Docket:
NRC Notified By: DARYL LEON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/04/2012
Notification Time: 16:45 [ET]
Event Date: 06/01/2012
Event Time: 08:00 [PDT]
Last Update Date: 06/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS EMAIL ()
ILTAB VIA EMAIL ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST NI-63 ELECTRON CAPTURE DETECTOR

On June 1, 2012, the licensee reported a lost Ni-63 electron capture detector to the state of Oregon. The source is an Agilent Technology model 19233, serial number L5286 and was used in a gas chromatograph device. The source was obtained in April of 2006. The last time the source was known to be in possession of the licensee was during a 6-month wipe test performed on November 1, 2011.

The gas chromatograph was sent to Far West Fiber Metal Recycling around the first of the year and it is possible the source was in the machine at the time of disposal. The licensee will continue to search for the source. The state of Oregon will follow-up with the licensee.

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

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Agreement State Event Number: 47993
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: EASTMAN CHEMICAL COMPANY
Region: 1
City: KINGSPORT State: TN
County:
License #: R-82007-H15
Agreement: Y
Docket:
NRC Notified By: JOHN GRAVES
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/05/2012
Notification Time: 12:47 [ET]
Event Date: 06/04/2012
Event Time: [EDT]
Last Update Date: 06/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
FSME EVENTS EMAIL ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

TENNESSEE AGREEMENT STATE REPORT - STUCK SHUTTER ON FIXED GAUGE

The following information was obtained from the state of Tennessee via fax:

"On June 4, 2012 Eastman Chemical Company contacted the [Tennessee] Division of Radiological Health concerning an incident that had just occurred. A shutter on a fixed level gauge was difficult to operate and could not be completely closed. In an attempt to close the shutter, a viscous polymer material which had leaked onto the top part of the gauge was removed. However, removal of the polymer still did not allow for complete closing of the shutter. Surveys have confirmed that radiation levels around the gauge are normal. The vessel manway is posted and procedures are in place to prevent entry into the vessel prior to the gauge being repaired or replaced."

The level gauge contained 173 mCi of Cs-137. No personnel overexposures were reported.

Tennessee Event: TN-12-148

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

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Agreement State Event Number: 47994
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: OCALA HEALTH IMAGING SERVICES, LLC
Region: 1
City: OCALA State: FL
County:
License #: 4236-2
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/05/2012
Notification Time: 13:14 [ET]
Event Date: 06/05/2012
Event Time: [EDT]
Last Update Date: 06/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
FSME EVENTS EMAIL ()
ANGELA MCINTOSH (FSME)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

FLORIDA AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE

The following information was obtained from the state of Florida via email:

"First quarter 2012 whole body dosimeter badge for a nuclear med tech indicated a 10.5 Rem dose. Badge was recounted and the dose remained the same. Dose is not confirmed by ancillary ring dosimeters. Ring dosimeters indicate a typical 100 mR/month. Because the ring dosimeters do not confirm the badge dose, the consulting health physicist does not think this is a valid dose and the med tech is still working. Florida is investigating."

The isotope used by the medical technician is Tc-99, 30 mCi.

Florida Incident Number: FL12-049

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

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source

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Non-Agreement State Event Number: 47996
Rep Org: INBERG-MILLER ENGINEERING
Licensee: INBERG-MILLER ENGINEERING
Region: 4
City: CHEYENNE State: WY
County:
License #: 49-19477-01
Agreement: N
Docket:
NRC Notified By: GLEN BOBNICK
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/05/2012
Notification Time: 18:24 [ET]
Event Date: 06/05/2012
Event Time: 16:00 [MDT]
Last Update Date: 06/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS EMAIL ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

DAMAGED TROXLER MOISTURE DENSITY GAUGE

The gauge operator finished with a density reading and left the Troxler device at the measurement area when he was storing his tools in his truck. When he was returning to the measurement area, an end-loader drove over the Troxler, destroying the hand operating pad. At the time of the accident, the source was retracted into the shield. Immediately after the accident, the operator covered the gauge with shielding and established a boundary zone. No overexposures or contaminations are expected as the sources were retracted into the shielded position.

The Troxler is a model 3430 which contains 40 mCi of Am-241 and 8 mCi of Cs-137. The licensee is conferring with Troxler to determine whether the gauge will be repaired or returned for disposal.

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

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Power Reactor Event Number: 48016
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: LOGAN MILLER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/12/2012
Notification Time: 14:45 [ET]
Event Date: 06/12/2012
Event Time: 11:21 [CDT]
Last Update Date: 06/12/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BILLY DICKSON (R3DO)

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 TAKEN OUT OF SERVICE FOR MAINTENANCE

"On June 12, 2012, at approximately 1121 hours [CDT], the Kewaunee Power Station Technical Support Center (TSC) ventilation system was removed from service to allow TSC electrical distribution system repairs. The removal of the ventilation system potentially affects the TSC habitability during a declared emergency requiring activation. The Emergency Response Organization [ERO] team has been notified of the maintenance and the possible need to relocate during an emergency. If an emergency is declared and TSC ERO activation is required, the TSC will be staffed and activated unless the TSC becomes uninhabitable due to ambient temperatures, radiological, or other conditions. If relocation of the TSC staff becomes necessary, the Station Emergency Director will relocate the staff to an alternate TSC location.

"The ventilation system is expected to be out of service for approximately 2 hours.

"This condition is being reported in accordance with 10CFR50.72(b)(3)(xiii) as an event that resulted in a major loss of emergency assessment capability.

"The NRC Resident Inspector has been notified."

TSC work was completed and the TSC was returned to service at 1326 CDT.

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Power Reactor Event Number: 48018
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: TERRY DAVIS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/12/2012
Notification Time: 17:27 [ET]
Event Date: 06/12/2012
Event Time: 14:56 [EDT]
Last Update Date: 06/12/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
BILLY DICKSON (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 50 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN

"At 1456 hours on June 12, 2012, the plant commenced a shutdown due to water leakage from the SIRW [Safety Injection Refueling Water] tank exceeding the operational decision-making issue process trigger point of 31 gallons per day causing it to be declared inoperable and requiring entry into Technical Specification (TS) 3.5.4, Condition B. TS 3.5.4 Condition B requires the SIRW Tank to be returned to operable status within one hour or entry into Condition C that requires the plant to be in Mode 3 within 6 hours and Mode 5 within 36 hours.

"Actual leakage from the SIRW Tank was measured at approximately 31.4 gallons per day. This event had no impact on the health and/or safety of the public.

"The NRC Senior Resident Inspector has been notified."

The licensee believes that the tank is leaking from several locations. However, at this time, they cannot determine exact locations. The refueling water has minor tritium contamination. The refueling water is being collected in a reservoir and then pumped into a holding tank. The licensee will be shutting down to cold shutdown.

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Power Reactor Event Number: 48019
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN MILLER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/13/2012
Notification Time: 01:38 [ET]
Event Date: 06/12/2012
Event Time: 17:57 [EDT]
Last Update Date: 06/13/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVID AYRES (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 98 Power Operation
2 N Y 100 Power Operation 98 Power Operation

Event Text

LOSS OF THE PLANT PROCESS COMPUTER SYSTEM

"At 1757 EDT on 6/12/12, Brunswick Nuclear Plant experienced a fault on the Emergency Response Facility Information System (ERFIS) uninterruptible power supply (UPS) electrical bus 'A'. This resulted in a loss of site Safety Parameter Display System (SPDS), Emergency Response Data System (ERDS) and Plant Process Computer (PPC) for both Unit 1 and Unit 2. The cause of the fault is not yet understood and under investigation. No other major plant effects occurred and no major plant evolutions are planned.

"During the loss of SPDS, the emergency response capability of that system was lost to the site. During the loss of ERDS, the automatic data transfer feature of that system was lost for transmissions to the NRC, however manual data transfer is still available. During the loss of the PPC, automatic core thermal power averaging and automatic core thermal limit monitoring was lost. Manual calculations are available for these functions.

"Unit 1 SPDS was restored to the Emergency Operations Facility (EOF) at 1949 EDT. Unit 2 SPDS was restored to the EOF at 2030 EDT. ERDS and PPC remain unavailable with troubleshooting in progress. Both units reduced power to 98% as a conservative measure.

"The NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Wednesday, June 13, 2012
Wednesday, June 13, 2012