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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/17/2009 - 02/18/2009
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 44847 |
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: NUCOR STEEL COMPANY
Region: 4
City: ARMOREL State: AR
County:
License #: ARK-078603120
Agreement: Y
Docket:
NRC Notified By: KATIA GRAY
HQ OPS Officer: MARK ABRAMOVITZ |
Notification Date: 02/12/2009
Notification Time: 11:41 [ET]
Event Date: 01/20/2009
Event Time: [CST]
Last Update Date: 02/12/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
GEOFFREY MILLER (R4)
ANGELA McINTOSH (FSME) |
Event Text
AGREEMENT STATE REPORT - SOURCE SHUTTER STUCK OPEN
The following report was received from the state via e-mail:
"Nucor Steel Company informed the [Arkansas] Department [of Health] that they had a stuck shutter on one of their caster sources. The licensee utilized a lifting mechanism that allowed the technicians to lift and move the source without being near the source. The source and source holder were placed in an appropriate container and surveys were performed. The highest reading on the storage container with the shutter open at contact was 120 MicroR/hour.
"The storage container was relocated to a remote area on the casting deck and surveys were performed. A source service provider was contacted and arrived on site the next day to evaluate the problem.
"Source: Berthold Model LB 300 MLT, Serial number 730-4-97, 36 mCi of Co-60 used for mold level control.
"On 02/12/2009, at 10:01 AM the licensee provided the Department with a more detailed description of the steps taken by the technicians during the event, storage of the source, exposure reading at the source, and security of the source at this time. The licensee is currently awaiting feedback from the gauge service provider.
"The Department will leave this report open pending receipt of a final written report from the licensee, due in 30 days."
Arkansas Report: 09-02-01 |
| Fuel Cycle Facility |
Event Number: 44848 |
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: RANDY SHAKELFORD
HQ OPS Officer: MARK ABRAMOVITZ |
Notification Date: 02/12/2009
Notification Time: 16:30 [ET]
Event Date: 02/12/2009
Event Time: 12:15 [EST]
Last Update Date: 02/12/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(3) - MED TREAT INVOLVING CONTAM |
Person (Organization):
JONATHAN BARTLEY (R2)
MICHAEL WATERS (NMSS)
REBECCA TADESSE (FSME)
FUELS OUO (EMAIL) () |
Event Text
CONTAMINATED WORKER SENT TO OFFSITE HOSPITAL FOR TREATMENT
"Operator was changing a filter in a glove box when he noticed liquid on his sleeve. Safety Department was notified and operator was found to be contaminated above limits. Decontamination attempts were unsuccessful due to nitric acid burn on forearm. Several small holes/cuts in rubber glovebox glove were identified. Operator was sent to medical facility for further evaluation. Operator was treated for second degree burns at medical facility and released.
"There were no exposures from licensed material. There were no actual consequences to the public or environment.
"Personal protective equipment was used by the worker. Emergency safety shower was available and utilized. Locker room shower was also available and utilized."
The NRC Resident Inspector was notified. |
| Power Reactor |
Event Number: 44856 |
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: KENT MILLS
HQ OPS Officer: JASON KOZAL |
Notification Date: 02/17/2009
Notification Time: 11:16 [ET]
Event Date: 02/17/2009
Event Time: 10:00 [EST]
Last Update Date: 02/17/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
TODD JACKSON (R1) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
Y |
93 |
Power Operation |
93 |
Power Operation |
Event Text
LOSS OF SAFETY PARAMETER DISPLAY SYSTEM DUE TO PLANNED MAINTENANCE
"At 04:05 hours EST, on February 17, 2009, the Plant Process Computer System was removed from service to perform a planned maintenance on the inverter power supply. The plant computer provides monitoring capability for the Safety Parameter Display System (SPDS). The expected duration of plant computer inoperability is approximately 16 hours. The loss of the plant computer requires alternate methods, as described in plant procedures, to be used. Therefore, appropriate assessment of plant conditions, notifications and communications can still be made, if required, during the time that the plant computer is inoperable.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii) which is any event that results in a major loss of emergency assessment capability, offsite response capability or offsite communications capability. As previously stated, alternate means remain available to assess plant conditions, make notifications and accomplish required communications, as necessary. An additional notification will be provided when plant computer operability is restored.
"The NRC Senior Resident Inspector has been notified."
* * * UPDATE AT 1600 EST ON 02/17/09 FROM KENT MILLS TO S. SANDIN * * *
The SPDS was restored at 1545 EST.
The licensee informed the NRC Resident Inspector. Notified R1DO (Jackson). |
| Fuel Cycle Facility |
Event Number: 44857 |
Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: BOB STOKES
HQ OPS Officer: STEVE SANDIN |
Notification Date: 02/17/2009
Notification Time: 13:52 [ET]
Event Date: 02/16/2009
Event Time: 10:30 [CST]
Last Update Date: 02/17/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(1) - UNPLANNED CONTAMINATION |
Person (Organization):
CHARLIE PAYNE (R2)
THOMAS HILTZ (NMSS) |
Event Text
24-HOUR REPORT INVOLVING AN UNPLANNED CONTAMINATION EVENT
"An unplanned contamination event occurred on February 16th, 2009. This is a reportable event in accordance with 10CFR40.60 paragraph (1) based on an unplanned event that results in additional radiological controls being required for more than 24 hours. The 24 hour period ended at 1030 on February 17th, 2009. The additional controls imposed was wearing a half-face respirator in the basement of the Feed Materials Building. The Feed Materials Building converts uranium ore concentrates into uranium hexafluoride. Air samples from the basement were analyzed and the airborne radioactivity average was approximately 8.27 e-11 ÁCi/ml. The airborne radioactivity exceeded the MTW action level of 30% of a DAC (5.0 e-11 ÁCi/ml). One DAC is 1.7e-10. Uranium Tetrafluoride (green salt) was the material that was airborne in the basement. An elevator that is used to transport green salt to different levels of the Feed Materials Building was leaking around an inspection cover which caused the airborne radioactive material."
The licensee attributes the contamination to a failed gasket. The airborne contamination was discovered during routine air sampling which is performed daily. There is no plan to perform personnel testing for uptake or ingestion at this time. |
| Fuel Cycle Facility |
Event Number: 44858 |
Facility: WESTINGHOUSE ELECTRIC CORPORATION
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 to UO2)
COMMERCIAL LWR FUEL
Region: 2
City: COLUMBIA State: SC
County: RICHLAND
License #: SNM-1107
Agreement: Y
Docket: 07001151
NRC Notified By: RALPH WINIARSKI
HQ OPS Officer: PETE SNYDER |
Notification Date: 02/17/2009
Notification Time: 16:33 [ET]
Event Date: 01/28/2009
Event Time: [EST]
Last Update Date: 02/17/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL |
Person (Organization):
CHARLIE PAYNE (R2)
TOM HILTZ (NMSS) |
Event Text
NOTIFICATION TO SC-DHEC CONCERNING EXCEEDANCE OF BIOLOGICAL OXYGEN DEMAND (BOD5) LIMIT
"On January 28, 2009, the composite sample from our waste treatment facility analyzed by our NPDES certified vendor laboratory indicated that wastewater discharged from the Westinghouse Columbia plant (to Congaree River) during the 24 hour period contained 60.8 pounds of BOD5 (56 mg/l BOD5) which exceeded the Daily Maximum Permit Limit of 60 # of BOD5 per day. The daily average for BOD5 discharges during January was approximately 23.6 pounds per day and is within permit limitations (30 #/D). Other BOD5 results for the month were less than 12 # BOD5/day.
"Following recognition of the problem on 2/3/09, Westinghouse immediately responded to evaluate the waste treatment facility including the sanitary package plant, the sanitary lagoon, process lagoons, and final discharge tanks. All systems were operating properly and producing clear effluent with no unusual odors or solids present. Waste treatment operations logs were inspected and no unusual problems were noted. All dissolved oxygen results for the month of January were greater than 10.0 mg/l indicating satisfactory performance of the wastewater treatment facility. Visual analysis of the entire waste treatment facility on 2/3/09 indicated that all processes were operating normally and no problems were being experienced.
"Investigation samples for BOD5 were collected on 2/3/09 from process source locations prior to the final discharge. All precursor investigation BOD5 samples were analyzed to contain less than 11.0 mg/l BOD5.
"Based on our information and discussions with [South Carolina - Department of Health and Environmental Control (SC-DHEC)], we are reporting the exceedance data, but believe the sample was anomalous (or contaminated) due to the lack of any elevated source of BOD5 (based on investigation samples) or process upsets noted in the entire waste treatment facility.
"Westinghouse remains deeply committed to continuous compliance with all NPDES requirements." |
| Power Reactor |
Event Number: 44859 |
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE INGALLS
HQ OPS Officer: STEVE SANDIN |
Notification Date: 02/17/2009
Notification Time: 18:28 [ET]
Event Date: 02/17/2009
Event Time: 11:00 [CST]
Last Update Date: 02/17/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION |
Person (Organization):
DAVID HILLS (R3) |
| 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
BOTH EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE AFTER REVIEW OF WORK BOUNDARY ISOLATION
"At 1100 on 2/17/2009 with D5 Diesel Generator (A-Train EDG) out of service for planned maintenance, it was discovered that an isolation had been hung that inadvertently disabled the D5 Fuel Oil Storage Tanks Transfer Pumps. These transfer pumps provide the primary fuel oil supply to D5 EDG Day Tank and the secondary supply to D6 (B Train EDG) Day Tank. With D5 Fuel Oil Storage Tanks Transfer Pumps not functional, their ability to transfer fuel oil to the D6 Diesel Generator (B-Train EDG) Fuel Oil Storage Tanks was disabled. Although D6 had both of its primary fuel oil transfer pumps available with approximately 50,000 gallons of diesel fuel, this left PINGP Unit Two with less than the Tech Spec required 65,000 gallons available to maintain Unit Two EDG operability. Therefore, at 1100 on 2/17/2009 D6 EDG was declared inoperable. Thus, both trains of Unit 2 EDGs were inoperable (safety function was lost) for ~34 hours. 65,000 gallons fuel oil inventory is to ensure the EDGs have enough inventory to mitigate the probable maximum flood which would result in being unable to get new fuel oil on site for ~14 days. There is no flooding predicted per the National Weather Service Advanced Hydrologic Prediction Service. The observed level at Lock & Dam #3 is more than 12 feet below flood stage with river level decreasing the last four days. This isolation had been in place since 0129 on 2/16/2009.
"At 1145 on 2/17/2009 the 21 and 23 D5 Fuel Oil Transfer Pumps were returned to service and D6 Diesel Generator was declared Operable."
This did not affect Unit 1. The licensee informed the NRC Resident Inspector. |
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