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Event Notification Report for May 6, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/05/2010 - 05/06/2010

** EVENT NUMBERS **


45885 45886 45887 45895 45898 45900 45901 45902 45903

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General Information or Other Event Number: 45885
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: SHAW ENVIRONMENTAL, INC
Region: 4
City: LITTLE ROCK State: AR
County:
License #: 20-31340-01
Agreement: Y
Docket:
NRC Notified By: STEVE MACK
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/30/2010
Notification Time: 17:33 [ET]
Event Date: 04/01/2010
Event Time: [CDT]
Last Update Date: 04/30/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JEFF CLARK (R4DO)
JAMES DANNA (FSME)

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

Event Text

ARKANSAS AGREEMENT STATE REPORT - MISSING TRITIUM EXIT SIGNS

The following was received from the State via email:

"The Department [State] received notice on April 1, 2010 by telephone and a written report on April 30, 2010, from Shaw Environmental, Inc. of seven (7) missing Tritium (H-3) exit signs.

"The signs were purchased and installed in a military recruiting center, located on University Avenue in Little Rock, Arkansas. The recruiting center was located in a mall complex that had been demolished and removed for the construction of a new shopping center.

"The signs were installed sometime between March, 2004 and October, 2005. The signs are described as:

"Manufacturer: SRB Technologies
"Model: BetaLux-E
"Activity: 10 Curies each
"Serial numbers: 318671-318675 and 318887-318888 (7 signs total)"

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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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
General Information or Other Event Number: 45886
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: ENERGY SOLUTIONS
Region: 1
City: OAK RIDGE State: TN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BILLY FREEMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 04/30/2010
Notification Time: 17:05 [ET]
Event Date: 04/30/2010
Event Time: 11:31 [EDT]
Last Update Date: 05/03/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN ROGGE (R1DO)
JAMES DANNA (FSME)
TIM MCCARTIN (NMSS)
GERALD MCCOY (R2DO)

Event Text

AGREEMENT STATE REPORT - LEAKING SHIPPING CONTAINER IDENTIFIED AFTER SHIPMENT

Energy Solutions notified the State of Tennessee about a shipping container that was found leaking radioactively contaminated liquid at their site. The container was part of a shipment of two containers containing radwaste shipped to Energy Solutions from Areva in Lynchburg, VA. After the shipment arrived onsite the containers were stored on a slope in a holding area for about fourteen hours.

The State dispatched people to the site who conducted surveys. When the shipping container was opened a bag of freestanding liquid was found near the doors of the container inside. The liquid was surveyed and determined to contain Co-60 and Cs-137. Cs-137 was not manifested on the shipping manifest. The liquid's consistency was described as semi-viscous similar to hydraulic fluid.

The State surveyed the area from where the containers came into the site gate to the area where they were stored with floor monitors and did not find radioactive contamination. The trailer and surrounding area were also surveyed with no contamination found.

Tennessee contacted Areva - Lynchburg and was told that the shipping container that contained the leaking bag was stored for a long period of time on top of the other shipping container at Lynchburg. Tennessee representatives surveyed the top of the other shipping container but again no radioactive contamination was found.

* * * RETRACTION FROM BILLY FREEMAN TO ERIC SIMPSON AT 1354 ON 5/3/10 * * *

The State Radiation Health Department, upon consultation with Regional NRC representatives, has determined that this event does not meet the notification requirements of SA-300 and is retracting the event.

Notified R1DO (Cook), FSME DEO (McIntosh), NMSS EO (McCartin) and R2DO (Musser).

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General Information or Other Event Number: 45887
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: APEX GEOSCIENCE, INC
Region: 4
City: TYLER State: TX
County:
License #: 04929
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/30/2010
Notification Time: 20:38 [ET]
Event Date: 04/30/2010
Event Time: [CDT]
Last Update Date: 04/30/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JEFF CLARK (R4DO)
JAMES DANNA (FSME)
ILTAB VIA (EMAI)
MEXICO VIA (FAX)

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

Event Text

AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE

The State provided this information via email:

"On April 30, 2010, at 1750 hours, the Agency [State] received a report from the licensee stating that a Troxler moisture/density gauge (Model 3430 - Serial # 31489) was missing from a construction site at 6185 Retail Road in Dallas, Texas. The gauge contains an 8 milliCuries Cesium (Cs) - 137 source serial # 750-6245, and a 40 milliCuries Americium - 241/Beryllium (Am\Be) source serial # 47- 5598.

"The license reported that the gauge user (worker) had used the gauge earlier in the day and had secured and locked it in their storage trailer at the site around 1300. The worker left the site around 1400 for his lunch break. The worker returned to the site around 1500, and around 1630 he returned to the storage trailer. At that time, he discovered the trailer lock and gauge were missing. The worker informed the Apex Project manager and the company service manager. The worker was instructed to conduct a thorough site search and contact all of their personnel with access to the site to see if they could determine the location of the gauge. After a thorough search and numerous telephone calls to various Apex personnel to make sure the gauge in fact was missing and not inadvertently picked up by another employee, the Corporate Radiation Safety Officer, Apex President, and this Agency was contacted to report the gauge missing.

"The licensee speculates that the gauge was stolen. They are not aware of any former employees who left under bad circumstances and would have reason to take the gauge as a prank or as a vehicle for reprisal against them. The licensee has spoken to others at the site and does not believe any one at the site is in possession of the gauge.

"The licensee has stated that they are considering a reward for the gauges' return."

Texas Incident Report # I-8738

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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General Information or Other Event Number: 45895
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: ST AUGUSTINE COLLEGE
Region: 1
City: RALEIGH State: NC
County:
License #: 092-0438-0G
Agreement: Y
Docket:
NRC Notified By: WILLIAM JOHNSON
HQ OPS Officer: ERIC SIMPSON
Notification Date: 05/03/2010
Notification Time: 11:53 [ET]
Event Date: 05/03/2010
Event Time: [EDT]
Last Update Date: 05/03/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WILLIAM COOK (R1DO)
ANGELA MCINTOSH (FSME)

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

Event Text

AGREEMENT STATE REPORT - LOSS OF RADIUM CHECK SOURCE

The following information is a summary of a report provided by the State of North Carolina via facsimile:

A state inspector performed an inspection on April 20, 2010, and learned that a radiation source (Ra-226, 20 microCuries) used in the facility's liquid scintillation counter, Packard Tri-Carb Model, was lost or missing. The RSO [Radiation Safety Officer] and inspector performed a survey of all the labs with a Ludlum Model 19 and were not able to find the source. In addition, it was found that no paperwork was available indicating proper source tracking, leak testing, or disposal of the source. A violation letter has been mailed to the RSO allowing the licensee thirty days to respond to the violation.

NC Incident No. 10-22.

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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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45898
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: NATHAN SEID
HQ OPS Officer: ERIC SIMPSON
Notification Date: 05/04/2010
Notification Time: 16:56 [ET]
Event Date: 05/04/2010
Event Time: 15:12 [CDT]
Last Update Date: 05/05/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
THEODORE QUAY (NRR)
BRIAN McDERMOTT (IRD)

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

DISCOVERY OF AFTER-THE- FACT EMERGENCY CONDITION - UNUSUAL EVENT DUE TO RCS LINEUP

"On 5/4/2010 at 15:12 CDT when attempting to flush CH-1A charging pump, a loss of charging flow occurred.
CH-193 discharge valve for CH-1A charging pump was found to be open. This resulted in a flow path to the auxiliary building sump tank when CH-356 charging pump CH-1A discharge drain valve to waste disposal system was opened. This resulted in an approximately 38 gpm leak from the reactor coolant system via letdown to waste. This leak was isolated within 1 minute."

The site entered and exited the conditions for NOUE before the shift manager was able to make an E-plan call. There are currently no emergency conditions on site and an NOUE was never declared. The reactor continued to operate at 100% power throughout the event. The cause of this event is believed to be a valve line-up error.

The NRC Resident Inspector has been notified. The site plans to notify the State of Nebraska. No other notifications are planned.

* * * RETRACTION AT 1625 EDT ON 5/5/10 FROM MATZKE TO HUFFMAN * * *

"The declaration of Unusual Event SU 5 EAL 2, RCS leakage, on 5/4/10 is being retracted, because the declaration was inaccurate. The leak was an intersystem leak of the CVCS, not RCS leakage, and the leak was isolated as previously noted. Therefore, the leakage did not meet the initiating condition for the EAL."

The licensee has notified the NRC Resident Inspector and plans to notify the State of Nebraska. Notified R4DO (Farnholtz), NRR EO (Quay), and IRD (McDermott).

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Power Reactor Event Number: 45900
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: GREG MILLER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/05/2010
Notification Time: 05:07 [ET]
Event Date: 05/05/2010
Event Time: 05:00 [EDT]
Last Update Date: 05/05/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVE PASSEHL (R3DO)

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

TECHNICAL SUPPORT CENTER OUT OF SERVICE FOR PREVENTIVE MAINTENANCE

"On May 5, 2010, at 0500 hours EDT, Fermi 2 removed the Technical Support Center (TSC) from operation to facilitate routine preventive maintenance on the facilities' heating ventilation and air-conditioning system. During this work, which is expected to last approximately 12 hours, the TSC will be unavailable. In the event TSC activation is necessary, the Emergency Operations Facility (EOF) will be used for the TSC function. Activation and use of the EOF as a backup for the TSC is included in Fermi 2's Radiological Emergency Response Preparedness Plan. The Emergency Call Out System (ECOS) is designed to facilitate contacting TSC personnel to respond directly to the EOF in the event of an emergency. Fermi 2 is making this notification in accordance with 10 CFR 50.72(b)(3)(xiii). Fermi 2 will notify the NRC upon completion of this work. Fermi 2 has notified the NRC Resident Inspector."

* * * UPDATE FROM JIM KONRAD TO PETE SNYDER ON 5/5/10 AT 1725 EDT * * *

"Maintenance to restore ventilation has been completed. The TSC has been restored as an Emergency Response Facility."

Notified R3DO (Passehl).

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Power Reactor Event Number: 45901
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JIM PETERSON
HQ OPS Officer: ERIC SIMPSON
Notification Date: 05/05/2010
Notification Time: 14:04 [ET]
Event Date: 03/15/2010
Event Time: 01:38 [CDT]
Last Update Date: 05/05/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
DAVE PASSEHL (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 96 Power Operation 96 Power Operation

Event Text

OPTIONAL 60-DAY REPORT OF INVALID SPECIFIED SYSTEM ACTUATION

"This telephone notification is being provided in accordance with 10CFR50.73(a)(1) for an invalid actuation reportable under 50.73 (a)(2) (iv)(A).

"On March 15, 2010 at 0138 hours, during full power operations, Division 2 Drywell Ventilation (VP) and Drywell Cooling (WO) Primary Containment Isolation Valves (PCIVs) closed for isolation Groups 11 and 17. The affected valves were inboard PCIVs 1VP005A, 1VP005B, 1VP014A, 1VP014B, 1WO001B, 1W0002B, 1WO551B and1WO552B. The shunt trip devices for the breakers for the following components were tripped: Drywell cooling fan 1B (1VP01CB), Drywell cooling fan 1D (1VP01CD), Drywell chiller 18 oil pump, DC Motor Control Center (MCC) 1B ground detection, DC MCC 1B ground detection, Drywell Chiller 1B(1VP04CB), and Drywell Chiller control panel 1B.

"The cause of the isolation was determined to be that a Division 2 load driver card spuriously actuated all of its loads without a valid Loss Of Coolant Accident (LOCA) signal or a manual initiation signal present. A reset of the Group 11 and 17 isolations was completed at 0208; the shunt trips were reset at 0215; and Drywell Cooling was restored by 0259 on March 15. The load driver circuit remained in service until a replacement load driver card could be installed on March 19, 2010. The cause of the card failure could not be determined; however the most probable cause is either an intermittent failure of the card or an intermittent short of the output connectors.

"The actuation of primary containment isolation Groups 11 and 17 was complete and the isolation/actuation was limited to only these two groups.

"The NRC Resident Inspector was notified of this notification."

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Power Reactor Event Number: 45902
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVE JESTER
HQ OPS Officer: ERIC SIMPSON
Notification Date: 05/05/2010
Notification Time: 15:11 [ET]
Event Date: 05/05/2010
Event Time: 11:44 [EDT]
Last Update Date: 05/05/2010
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):
RANDY MUSSER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TO REACTOR FEED PUMP TRIP

"On May 5, 2010, at 1144 hours Eastern Daylight Time (EDT), an automatic reactor scram occurred on Unit 1 following a trip of the 1B Reactor Feed Pump (RFP). Following the 1B RFP trip, the reactor recirculation pumps did not run back as expected. The resulting water level shrink caused level in the Reactor Pressure Vessel (RPV) to drop to Low Level 1, causing the activation of the Reactor Protection System (RPS) and the Primary Containment Isolation System (PCIS). All control rods properly inserted.

"PCIS Group 2 (i.e., Drywell Equipment and Floor Drain, Residual Heat Removal (RHR) Discharge to Radwaste, and RHR Process Sample), Group 6 (i.e., Containment Atmosphere Control/Dilution, Containment Atmosphere Monitoring, and Post Accident Sampling Systems), and Group 8 (i.e., RHR Shutdown Cooling) isolation signals were received on Low Level 1. Actuations of the Primary Containment Isolation Valves (PCIVs) were completed and the affected equipment responded as designed.

"Due to the expected RPV level reduction following a reactor scram, water level in the RPV momentarily reached Low Level 2. This initiated the High Pressure Coolant Injection (HPCI) System, the Reactor Core Isolation Cooling (RCIC) System, and a partial Group 3 PCIS (i.e., RWCU) isolation. The HPCI and RCIC systems did not inject. The 1-G31-F001 isolated (i.e., inboard isolation) but 1-G31-F004 (i.e., outboard isolation) did not automatically isolate. Based on a preliminary assessment, this response appears to be in accordance with plant design. Further
assessments of plant response are on-going to validate plant response.

"The licensee has notified the NRC Resident Inspector."

The scram was uncomplicated. No SRVs lifted. Decay heat removal is via the 'A' feed water pump via the turbine bypass valves to the condenser. The electrical line-up of Unit 1 is normal. Brunswick Unit 2 was not affected.

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Power Reactor Event Number: 45903
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: NICK RULLMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 05/05/2010
Notification Time: 19:26 [ET]
Event Date: 05/05/2010
Event Time: 15:10 [PDT]
Last Update Date: 05/05/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
THOMAS FARNHOLTZ (R4DO)

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

INJURED INDIVIDUAL HOSPITALIZED

"On May 5, 2010 at approximately 1510 PDT, a notification was made to the Washington State Department of Labor and Industries regarding an in-patient hospitalization of an Energy Northwest employee as required by Washington Administrative Code.

"On May 3, 2010 high wind conditions were occurring at the plant site. While this individual was outside, a high gust of wind occurred resulting in the individual falling and injuring himself. The individual received treatment from a local medical facility and was released that day. On May 5, the individual identified additional symptoms and was admitted to a local hospital which resulted in in-patient hospitalization and treatment."

The licensee notified the NRC Resident Inspector.

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Thursday, March 29, 2012