| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/02/2010 - 07/06/2010 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Other Nuclear Material | Event Number: 45786 | Rep Org: WASHINGTON UNIVERSITY ST. LOUIS
Licensee: WASHINGTON UNIVERSITY ST. LOUIS
Region: 3
City: ST. LOUIS State: MO
County:
License #: 24-00167-11
Agreement: N
Docket:
NRC Notified By: SUE LANGHORST
HQ OPS Officer: BILL HUFFMAN | Notification Date: 03/23/2010
Notification Time: 18:10 [ET]
Event Date: 02/04/2010
Event Time: [CDT]
Last Update Date: 07/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2202(b)(1) - PERS OVEREXPOSURE/TEDE >= 5 REM
| Person (Organization):
LAURA KOZAK (R3DO)
ANDREA KOCK (FSME)
| Event Text EXTREMITY OVEREXPOSURE TO FINGERTIPS
The licensee's RSO reported that on March 9, 2010, a report was received from Landauer indicating that a technician that worked at the licensee's facility received a left hand ring dose of 11,900 millirem. The right hand ring dose was 4030 millirem. The licensee began an investigation into these readings and determined that the technician may have had a high extremity dose to the finger tips. After interviews with the technician and reconstruction of the event the licensee now believes that the technician may have received a dose between 50 rem and 400 rem over a 10 square-centimeter area of his fingertips as the result of improper handling of the radionuclide Bromine-76. The dose exposure to the fingertips was calculated using the Varskin computer code.
The technician was handling 32 millicurie vials of Bromine-76 between February 4 and February 5, 2010, related to research activities at Washington University. Normally, the vials would be handled with a long-handled tool with shielding. For reasons uncertain, the technician is believed to have directly handled the vials on several occasions. The technician has approximately six years of work-history with this type of activity.
The technician experienced no observable effects from the exposure. The technician has not worked with radioactive materials since mid-February. The Landauer whole-body deep dose badge reading for the period in question was 25 millirem.
* * * RETRACTION FROM SUSAN LANGHORST TO PETE SNYDER ON 7/2/2010 at 1631 EDT * * *
The licensee reconstructed the dose for the event after conversing with NRC Region 3. The licensees reconstructed dose estimate was 26 rem which is not over the dose limit of 50 rem. Therefore, this event is not reportable.
Notified R3DO (Daley), FSME EO (Lueman). |
| General Information or Other | Event Number: 46055 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: TETRA TECH, INC
Region: 3
City: JEFFERSON State: WI
County:
License #: 073-1165-01
Agreement: Y
Docket:
NRC Notified By: KURT PEDERSEN
HQ OPS Officer: ERIC SIMPSON | Notification Date: 06/29/2010
Notification Time: 17:20 [ET]
Event Date: 06/28/2010
Event Time: 20:35 [CDT]
Last Update Date: 06/29/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ROBERT DALEY (R3DO)
CHRISTIAN EINBERG (FSME)
| Event Text AGREEMENT STATE REPORT - MOISTURE DENSITY GAUGE DESTROYED IN FIRE
The following report was received via fax from the State of Wisconsin:
"On June 28, 2010 at 20:35 the Department of Health Services (DHS) on-call State Radiological Coordinator (SRC) was informed that there had been a fire involving two trailers at the Dodge Concrete Ready Mix plant, W6298 US Hwy 18, Jefferson, WI. One of the trailers contained a Troxler 3440 portable moisture density gauge owned by Tetra Tech, a Wisconsin Radioactive Materials Licensee who was performing licensed activities at the concrete plant. The gauge contains a maximum of 9 milliCuries of Cesium-137 and 44 milliCuries of Americium-241:Beryllium as radioactive sealed sources. The original call to the DHS 24 hour emergency hotline was made by the Tetra Tech Radiation Safety Officer (RSO).
"The SRC subsequently received a page from the Wisconsin Emergency Management (WEM) Duty Officer at 20:45. The Duty Officer explained to the SRC that he had been informed of a fire in Jefferson, (WI) involving two burning trailers involving radioactive material. The SRC informed the duty officer that DHS intended on following up on the incident and would provide additional information.
"The SRC then contacted the licensee RSO. The RSO was at the scene of the fire interacting with the fire department. He (RSO) indicated that a fire had consumed two of their job trailers at Dodge Ready Mix and that one trailer contained a portable gauge which housed both a Cs-137 and an Am-241/Be radioactive source. The RSO indicated that radiation surveys around the trailer indicated radiation levels of less than 1 mR/hr around the burned trailer containing the gauge. After the RSO proposed his course of action to the SRC, they agreed that it was unsafe to attempt to extract the gauge from the trailer in the dark. The RSO cordoned off the trailer with yellow "Caution-Do Not Enter" tape pending an attempt to extract the gauge the following morning. All of the licensee's proper radiation postings and equipment were also destroyed in the fire. All postings and labels on the gauge transport container and the gauge itself were destroyed. DHS informed the RSO that they would arrive at the scene of the fire the next morning to supervise the extraction and provide technical radiation safety support.
"DHS investigators arrived at Dodge Ready Mix in Jefferson, Wl at 09:30. The Tetra Tech RSO and Authorized Users (AU) were present. Both trailers were completely destroyed by the fire and the gauge housing, transport case and associated equipment were melted together and fused to the trailer floor. The melted plastic, gauge and trailer housing had to be removed as a block. The maximum radiation level was ~8 mR/hr near contact with the Cs-137 shielding, which appeared to be intact. The radiation levels indicated that the shielding for both sources had retained its integrity. Contamination wipes were taken on the source rod, source shielding and the source exit point. No evidence of contamination was found. The DHS investigators were informed that the fire department had moved the trailers away from the site garage to reduce the risk of the fire spreading. All debris, trailers and trailer sites were surveyed. No elevated radiation levels were found. These surveys gave the DHS investigators and RSO confidence that the source remained in the fully shielded position.
"After consulting with Troxler, the gauge manufacturer, the RSO decided to remove the melted plastic and debris from the gauge remnants so it could be transported and shipped back to Troxler in a standard transport case. The licensee succeeded in removing the debris and melted plastic and at 12:45 was able to package the gauge in the Type-A transport container for return to their office in Wausau. The gauge was to be leak tested prior to shipment to Troxler for disposal. All debris removed from the gauge and the gauge itself was surveyed for contamination and radiation levels. The maximum radiation level remained at ~8 mR/hr and no evidence of contamination was found. The transport index was consistent with what the RSO typically finds with an intact gauge."
Event Report ID: WI100011 |
| General Information or Other | Event Number: 46058 | Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: OMAHA PUBLIC POWER DISTRICT
Region: 4
City: OMAHA State: NE
County:
License #: 01-39-04
Agreement: Y
Docket:
NRC Notified By: RANDY LAMBERT
HQ OPS Officer: JOHN KNOKE | Notification Date: 06/30/2010
Notification Time: 16:04 [ET]
Event Date: 06/30/2010
Event Time: 11:00 [CDT]
Last Update Date: 06/30/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RYAN LANTZ (R4DO)
CHRISTIAN EINBERG (FSME)
| Event Text AGREEMENT STATE REPORT - SHUTTER ON FIXED INDUSTRIAL GAUGE FAILED TO CLOSE
The following report was received via fax from the State of Nebraska:
"The licensee uses fixed industrial gauges for measuring densities in flyash hoppers at the Stations precipitator building. The Industrial gauges contain a Cesium 137 sealed source. The Cesium 137 sources were originally installed in 1984 and at the time contained 50 millicuries per source. The sources were manufactured and installed by Kay Ray Inc. The gauge housing Model No. is 7080.
"The licensee was performing the semi-annual 'Shutter Function Test' on Unit #4's precipitator sources. The 'external' source closure mechanism for the 4FA-1B & 2B hoppers did not operate as designed and the shutter did not close when the handle on the floor was operated. The external closure cable had detached from the cable clamp on the side of the hopper. In this condition, when the shutter closure mechanism was moved, the cable that operates the source shutter mechanism 20 feet above the floor, bent instead of sliding the cable to the closed position. No personnel were exposed to radiation during this event.
"This was the fourth similar event at the licensee's plant (March 25, 27, May 6, & June 30, 2010). On June 17, a NE DHHS (Nebraska Department of Health and Human Services), Radioactive Material inspector performed a follow-up investigation on-site. At this plant, OPPD (Omaha Public Power District) has 58 installed operating nuclear fixed gauges. At the time of the investigation, OPPD had replaced 20 of the old shutter cables with a new redesigned direct replacement cable. OPPD plans to replace all of the 58 shutter cables when they fail to operate or as time permits." |
| General Information or Other | Event Number: 46061 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: UNKNOWN
Region: 1
City: HOLLISTON State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/01/2010
Notification Time: 10:23 [ET]
Event Date: 06/24/2010
Event Time: 12:00 [EDT]
Last Update Date: 07/01/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY POWELL (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT INVOLVING A FOUND RA-226 SOURCE
"[A] transfer station for waste disposal detected radioactive material contained in a roll-off container with other debris. [The] debris came from a house clean-out job in Newton Corners, MA. [The] transfer station called Holliston Fire Department who responded with survey instruments capable of identifying radioactive material (RAM). [The]RAM was identified as Ra-226 contained in a device that appeared to be from a WWII vintage aircraft.
"[The] Agency sent an inspector to verify description of RAM trash. [The] inspector confirmed the RAM is Ra-226 contained in an aircraft leveling device. [The] inspector placed the device in a plastic container and sealed [it] with radioactive warning tape. The external dose rate measured 0.1 mR/ hr. The plastic container was placed in secure storage awaiting disposition of RAM. |
| Fuel Cycle Facility | Event Number: 46064 | Facility: NUCLEAR FUEL SERVICES INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
Region: 2
City: ERWIN State: TN
County: UNICOI
License #: SNM-124
Agreement: Y
Docket: 07000143
NRC Notified By: TONY SCHILL
HQ OPS Officer: JOE O'HARA | Notification Date: 07/01/2010
Notification Time: 20:02 [ET]
Event Date: 07/01/2010
Event Time: 19:18 [EDT]
Last Update Date: 07/01/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
74.57 - ALARM RESOLUTION
| Person (Organization):
BINOY DESAI (R2DO)
DOUG WEAVER (NMSS)
FUELS OUO GRP EMAIL ()
| Event Text MATERIAL CONTROL AND ACCOUNTABILITY (MC&A) ALARM ACTUATION
"10 CFR 74.57(f)(2) requires notification within 24 hours that an MC&A alarm resolution procedure has been initiated. Because the alarm investigation has been initiated, this notification is being made. There is no indication that a material loss has occurred. "
Material processing operations related to this alarm have been suspended.
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 46066 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: BRIAN MAZE
HQ OPS Officer: PETE SNYDER | Notification Date: 07/02/2010
Notification Time: 14:23 [ET]
Event Date: 07/02/2010
Event Time: 12:32 [CDT]
Last Update Date: 07/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
BINOY DESAI (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION FROM A LOSS OF POWER TO THE REACTOR PROTECTION SYSTEM (RPS) 3A
"This 60 day telephone notification is being made in-lieu of a written report under the requirements specified by 10 CFR 50.73(a)(2)(iv) and 10 CFR 50.73(a)(1) to describe an invalid actuation of general containment isolation signals affecting more than one system.
"On May 12, 2010, at 1232 hours Central Daylight Time (CDT), with Unit 3 operating at 100 percent thermal power the electrical power to the 3A RPS was interrupted during the transfer of the 3A 480V shutdown board from its alternate supply to its normal power supply. During the transfer, the normal breaker did not close for several seconds. This resulted in the interruption of power to the 3A shutdown board which caused the 3A RPS to de-energize, resulting in a half scram and the actuation of PCIS logic Groups 2, 3, 6, and 8, and the initiation of Trains B and C of Standby Gas Treatment, and the initiation of Train A Control Room Emergency Ventilation.
"Plant conditions which require PCIS actuations and the associated system initiations (e.g., low reactor water level, high drywell pressure, abnormal area radiation level, or high area temperature) did not exist; therefore, the actuation was invalid.
"The affected equipment responded as designed. On May 12, 2010, by approximately 1342 hours CDT, Unit 3 operations personnel restored the 3A RPS power and realigned affected equipment as appropriate.
"There were no safety consequences or impact on the health and safety of the public as a result of this event. The event was entered into the corrective actions program as PER 229613.
"The NRC Senior Resident Inspector has been notified." |
| Power Reactor | Event Number: 46067 | Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES DAVIS
HQ OPS Officer: JOE O'HARA | Notification Date: 07/02/2010
Notification Time: 14:40 [ET]
Event Date: 07/01/2010
Event Time: 14:15 [EDT]
Last Update Date: 07/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
BINOY DESAI (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | Event Text FITNESS FOR DUTY PROGRAMMATIC ISSUE APPLICABLE TO CONSTRUCTION UNITS 3 AND 4
"An internal audit of a contractors Fitness for Duty program revealed potential non-compliances with elements of 10 CFR 26.61 related to self disclosure requirements. The investigation into the extent of the potential noncompliance continues including whether associated elements of 10 CFR 26.63 are in compliance. Safety related construction activities will be suspended pending resolution and completion of corrective actions.
Southern Nuclear Operating Company (SNC) is providing this notification under the provisions of 10 CFR26.719(b)(4)."
The licensee will notify the Public Service Commission of Georgia and the NRC Construction Inspection Staff. |
| Power Reactor | Event Number: 46068 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JOE KLECHA
HQ OPS Officer: PETE SNYDER | Notification Date: 07/04/2010
Notification Time: 15:16 [ET]
Event Date: 07/04/2010
Event Time: 11:30 [EDT]
Last Update Date: 07/04/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
OTHER UNSPEC REQMNT
| Person (Organization):
RAY POWELL (R1DO)
|
| 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 | 85 | Power Operation | 85 | Power Operation | Event Text TELEPHONE COMMUNICATIONS OUTAGE
"At 1130 on 7/4/2010, Station Security contacted Calvert Control Center to notify them of a loss of offsite communication phone lines. Calvert Control Center recognized the loss of phone lines and reported that their phone lines were also out of service. This notification to an offsite government agency is reportable under 50.72(b)(2)(xi) and is a 4 hour ENS report. Security noted the lack of offsite communications at 1122 on 7/4/2010 and communicated this loss of communications to the control room.
"The control room verified that the microwave phone system, 800 MHz radio system, plant page, internal phone lines, satellite phone system, Emergency Response Organization Notification System (ERONS) and commercial line to NRC headquarters were still available, this met all of the requirements for contacting offsite agencies in the event of an emergency condition. It was noted that the ENS (dedicated) line to the NRC was not in operation.
"Contingency measures were put into place for communications with the NRC (CCNPP can still contact the NRC via commercial lines and the NRC can contact CCNPP via dedicated email and cell phone). The initiating event (loss of offsite communications - specifically the dedicated ENS phone line) which occurred at 1122 is reportable under 50.72(b)(3)(xiii) and is an 8 hour ENS report."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM JOE KLECHA TO PETE SNYDER ON 7/4/10 AT 1741 * * *
DISCOVERY OF AN AFTER-THE-FACT EMERGENCY CONDITION
"At 1645, Calvert Cliffs recognized that they were unable to contact St. Mary's County emergency response organization due to a loss of phone communications and radio deficiencies on the counties part. This met the requirement of an Unusual Event in accordance with [EAL] AU 5.1.1 (Unplanned loss of all onsite or offsite communication capabilities). Prior to making the EAL notification, phone communications were restored at 1650 and the conditions of the EAL were no longer met. This report is a one hour ENS notification per 50.72(a)(1)(i) - Declaration of an emergency class, footnote for events which conditions are no longer met."
Event classification "Other Unspecified Requirement" was added to the original header for this event concerning the after-the-fact emergency condition discovered by the licensee.
Notified R1DO (Powell), NRR EO (Lubinski), and IRD (Grant). |
| Power Reactor | Event Number: 46069 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JIM BROOKS
HQ OPS Officer: PETE SNYDER | Notification Date: 07/04/2010
Notification Time: 21:30 [ET]
Event Date: 07/04/2010
Event Time: 19:30 [EDT]
Last Update Date: 07/04/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RAY POWELL (R1DO)
|
| 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 PROBLEM WITH TONE ALERT SYSTEM
"At about 1930 on 7/4/10 the control room was notified by the E-plan Duty Officer that the Ames Hill NOAA transmitter (Tone Alert Radio) was inoperable as of 1752 on 7/4/10.
"The E-plan Duty Officer has affected repairs and the transmitter is operable as of 2030."
The licensee notified the NRC Resident Inspector. | |