| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/09/2012 - 08/10/2012 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 47541 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DANNY WILLIAMSON
HQ OPS Officer: JOHN KNOKE | Notification Date: 12/21/2011
Notification Time: 11:52 [ET]
Event Date: 12/21/2011
Event Time: 09:30 [CST]
Last Update Date: 08/09/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
BOB HAGAR (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 OFFSITE NOTIFICATION FOR DETECTABLE LEVELS OF TRITIUM IN GROUNDWATER WELL
"On Tuesday, December 20, 2011, technicians discovered detectable levels of tritium in an onsite groundwater well. The measured concentration of the isotope was approximately 48,000 picocuries per liter. This discovery was made during the conduct of the site's ongoing groundwater monitoring program.
"The tritium concentration in the well sample exceeds the EPA established threshold for drinking water of 20,000 picocuries per liter. However, no groundwater wells on the River Bend site are used for drinking water. There has been no tritium identified in any wells downstream of, or surrounding, the affected well.
"This test result does not indicate any threat to public health or safety, since the affected well is only used for groundwater monitoring, and not drinking water. Other onsite wells in the area were tested and will continue to be tested to ensure the tritium is not migrating offsite. The monitoring of the wells in the area immediately surrounding the affected well will be increased to a monthly frequency.
"Voluntary notification of this discovery has been made to local and state governmental agencies, with the initial notification being made at 0930 CST today. This event is being voluntarily reported in accordance with 10CFR50.72(b)(2)(xi) as a condition related to health and safety of the public and onsite personnel for which a news release is planned."
The licensee has notified the NRC Resident Inspector, state and local agencies and will be releasing information to the media.
* * * UPDATE FROM DANNY WILLIAMSON TO JOHN KNOKE AT 1518 EDT ON 08/09/12 * * *
"On August 7, 2012, one of the six new groundwater monitoring wells installed near the monitoring well which yielded the positive results on December 20, 2011, produced a groundwater sample containing 432,733 picocuries per liter of tritium. The investigation of the groundwater tritium activity is still ongoing, and the installation of these wells is part of that effort to determine the source.
"The NRC Resident Inspector has been notified and officials with the Louisiana Department of Environmental Quality will be briefed."
Notified R4DO (Michael Vasquez) |
| Agreement State | Event Number: 48147 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: ECS
Region: 1
City: RALEIGH State: NC
County:
License #: 092-0253-1
Agreement: Y
Docket:
NRC Notified By: HENRY BARNES
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/01/2012
Notification Time: 13:34 [ET]
Event Date: 07/31/2012
Event Time: [EDT]
Last Update Date: 08/01/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PAUL KROHN (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE
The following was received from the State of North Carolina via email:
"On July 31, 2012 a portable nuclear gauge owned by ECS of Raleigh (License Number 092-0253-1) was run over and crushed by a tracked dozer. The incident occurred off Caveness Farm Road in Wake Forest, NC.
"The gauge user stated that he had finished performing density testing for the day and was proceeding to leave the job-site. After exiting the job site and traveling the length of Caveness Farms Road to US Highway 1, he noted that his tailgate was down on his pick-up truck. He exited the truck to close the tailgate and noticed that the gauge was missing. He then traveled back to the job site and retraced his path to his testing location. He then observed the gauge approximately 100 feet from where he had been testing. Upon approaching the gauge he noted that it had been crushed by the dozer. The rod on the gauge was in the safe position with the source being shielded. A trigger lock was not present on the gauge at this time.
"The ECS RSO was notified and the user instructed the other workers in the area to remain at least 50 feet from the damaged gauge. They did.
"The ECS RSO arrived on the job site at approximately 3:00 pm. Upon arrival, he surveyed the damaged gauge with survey meter. A reading of 0.4 mrem/hr was noted at approximately 1 meter and a reading of 1 mrem/hr was noted on contact with the source. The RSO interviewed the dozer operator, who said that he did not see the density gauge in his path of travel but felt the gauge under the dozer as he traveled over it. He proceeded to a safe distance and notified his supervisor. He stated that moments later the ECS technician returned to the area of the damaged gauge.
"The RSO contacted the NC Radiation Protection Section and notified them of the incident. A NC RPS inspector was dispatched to the scene. Troxler Laboratories (gauge Mfg) was also contacted about the incident.
"When the NC RPS inspector arrived on the job site, he and the ECS RSO surveyed the damaged gauge. Once it was determined the gauge was safe to move, the gauge source rod and shield assembly was placed into the transport case. The rest of the gauge was collected and contained. After the pieces of the gauge were removed from the area where it was damaged, the area was surveyed and no reading over 0.03 mrem/hr were noted. The Inspector indicated that the sources had been recovered and the area was safe to resume work.
"Survey readings were taken of the transport case after the sources had been placed in the case. The highest reading was 70 mR/hr contact on the outside of the transport case at the end where the damaged source shield was located. The tungsten sliding block was damaged and was loose. Dose rates on the rest of the transport box were in the 0.1 range, with higher doses on the end. Dose at 1 meter (app) from the transport box end where the source was 0.2 mR/hr.
"At 6:00 pm the gauge was transported back to the ECS office. It arrived at the ECS office at approximately 6:45 pm and was stored in the appointed nuclear gauge storage location. The gauge was marked 'Do Not Use' and ECS technicians were instructed not to move the damaged gauge.
"ECS will take leak tests on August 1, 2012 and upon being notified of the results of the leak test, Troxler Labs will be notified of our intent to transport the gauge to their RTP location."
North Carolina Incident NC 12-43. |
| Agreement State | Event Number: 48152 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: AG WASSENAAR, INC
Region: 4
City: DENVER State: CO
County:
License #: 212-01
Agreement: Y
Docket:
NRC Notified By: MEGAN BROWN
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/02/2012
Notification Time: 11:53 [ET]
Event Date: 08/02/2012
Event Time: 08:40 [MDT]
Last Update Date: 08/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
FSME EVENTS RESOURCE ()
DARYL JOHNSON (ILTA)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - POTENTIALLY STOLEN MOISTURE DENSITY GAUGE
The following information was obtained from the State of Colorado via email:
"On Thursday August 2, at approximately 0840 MDT (Mountain Daylight Time) a portable gauge licensee (AG Wassenaar, Inc. License 212-01 Amendment 21) based in Denver, Colorado notified the Colorado Department of Public Health and Environment (CDPHE) Radioactive Materials Unit on-call duty officer that a gauge was missing and possibly stolen. The gauge had last been seen on Monday July 30 at 4:00 pm at the temporary work site. Upon returning to the office, the gauge user unlocked the box but became distracted and did not check-in the gauge. The gauge user then returned to his residence and parked his truck. The employee did not return to work until the morning of Thursday August 2nd, when he realized that the gauge was not in its case in the truck. The employee believes it may have been stolen from his residence on Tuesday night, however the licensee's employees are currently searching the residence, surrounding neighborhood, and last job site.
"The gauge involved was a Troxler model 3430 (gauge serial number 26071), containing 8 mCi of Cs-137 (serial #75-9099) and 40 mCi of Am-241:Be (serial #47-22450).
"The licensee was instructed to conduct a thorough search for the gauge in all known locations where it could be, and to also notify the local police should it not be found within the hour.
"Additional information and an incident report from the licensee is pending."
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 |
| Power Reactor | Event Number: 48170 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: RICK KERRONE
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 08/08/2012
Notification Time: 23:32 [ET]
Event Date: 08/08/2012
Event Time: 13:50 [PDT]
Last Update Date: 08/09/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL VASQUEZ (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 LOSS OF EMERGENCY ASSESSMENT CAPABILITY
"At 1350 PDT on 08-08-2012, during the performance of an annual surveillance, power supply ARM-E/S-603A was discovered to have out of tolerance voltage readings. ARM-E/S-603A was declared non-functional. This resulted in a loss of the ability to monitor and quantify radiological conditions in multiple areas of the reactor building, due to the loss of ARM-RIS-1 through 10 (Area Radiation Monitor Radiation Indicating Switches 1 through 10).
"The loss of ability to monitor and quantify radiological conditions in multiple areas of the reactor building represents a major loss of emergency assessment capability per 10 CFR 50.72(b)(3)(xiii). As directed by station procedures, compensatory measures have been enacted to have Health Physics personnel tour the affected areas once per shift to document and trend the radiological conditions. ARM-RIS-1 and 4 thru 10 are used for EAL determinations.
"ARM-E/S-603A was returned to service at 1524 PDT on 08/08/2012."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48171 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DARRELL JOHNSON
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 08/09/2012
Notification Time: 11:47 [ET]
Event Date: 08/09/2012
Event Time: 10:00 [PDT]
Last Update Date: 08/09/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL VASQUEZ (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMERGENCY OPERATIONS FACILITY DATA NETWORK MAINTENANCE
"At about 1000 PDT on August 9, 2012, Pacific Gas and Electric Company (PG&E) will disconnect the Diablo Canyon Power Plant (DCPP) Plant Data Network to the Emergency Operations Facility (EOF) and redirect the data via the Utility Data Network for hosting the emergency facility data systems. These systems include the Safety Parameter Display System, Plant Process Computer, Emergency Response Facility Display System, and Emergency Assessment and Response System in the EOF.
"PG&E expects to have the Emergency Response Data System and the EOF data network unavailable for about 8 hours. During this time, if needed, the TSC will have command and control once staffed, and will have classification, notification and dose assessment responsibility until the display systems are restored to the EOF. Also, if required, a dedicated licensed operator will be available in the control room to provide plant data to the NRC's Emergency Operations Center.
"DCPP is making this 8-hour, non-emergency notification under 10 CFR 50.72(b)(3)(xiii) as any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48172 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: JEFF KOPACZ
HQ OPS Officer: JOHN KNOKE | Notification Date: 08/09/2012
Notification Time: 13:34 [ET]
Event Date: 08/09/2012
Event Time: 08:55 [CDT]
Last Update Date: 08/09/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
CHRISTINE LIPA (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text CONFIRMED POSITIVE FITNESS FOR DUTY TEST
A non-licensed employee supervisor had a confirmed positive for alcohol during a follow-up fitness for duty test. The employee's unescorted access to the plant has been denied. Contact the Headquarters Operations Officer for additional details.
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 48173 | Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: MICHAEL KENNARD
HQ OPS Officer: JOHN KNOKE | Notification Date: 08/09/2012
Notification Time: 19:46 [ET]
Event Date: 08/09/2012
Event Time: 18:00 [EDT]
Last Update Date: 08/09/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DANIEL RICH (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Refueling Shutdown | 0 | Refueling Shutdown | Event Text OFFSITE NOTIFICATION - NON WORK RELATED ON-SITE FATALITY
"This is a non-emergency 4 hour informational notification to the NRC in accordance with the reporting requirements of 10 CFR 50.72(b)(2)(xi).
"On August 9, 2012 at approximately 1510 hours [EDT], a contract employee suffered a non-work related personal medical event while in an office environment that was located outside of the protected area. The individual was transported offsite and was pronounced deceased at a local hospital.
"OSHA is being notified pursuant to the requirements of 29 CFR 1904.39. There was no radioactive contamination involved in this event. Duke Energy has not observed any heightened media interest as a result of the fatality. No other notifications to government agencies are expected and no press releases are intended to be made at this time.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 48174 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JAMES M. KURAS
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 08/10/2012
Notification Time: 02:27 [ET]
Event Date: 08/09/2012
Event Time: 18:45 [CDT]
Last Update Date: 08/10/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
MICHAEL VASQUEZ (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 CONTROL BUILDING A/C UNIT MAY NOT PERFORM DESIGN FUNCTION ON LOSS OF REDUNDANT A/C UNIT
"Affected equipment includes two 4160 volt safety buses, four 480 volt safety buses, four 120 volt AC safety trains, and four 125 volt DC safety trains.
"Following an accident Class 1E AC Unit SGK05B may not be able to perform is design safety function if a single failure causes a loss of redundant Class 1E AC unit SGK05A. This is due to continued latent heat input from A train Control Room Pressurization Fan which continues to operate. SGK05A and B provide room cooling for all safety related electrical busses.
"Action Taken: Established the following compensatory measure - During accident conditions with both trains of CRVIS [Control Room Ventilation Isolation System] actuated if at any time SGKO5A trips then following completion of immediate actions Control Room pressurization fan CGK04A will be secured to reduce latent heat removal requirements for SGK05B."
The licensee has notified the NRC Resident Inspector. | |