| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/19/2009 - 11/20/2009 ** EVENT NUMBERS ** |
 | Fuel Cycle Facility | Event Number: 45497 | 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: DONALD NORWOOD | Notification Date: 11/14/2009
Notification Time: 18:43 [ET]
Event Date: 11/14/2009
Event Time: 07:30 [EST]
Last Update Date: 11/18/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(4) - FIRE/EXPLOSION
| Person (Organization):
MARK LESSER (R2DO)
E. WILLIAM BRACH (NMSS)
FUEL'S GROUP E-MAIL ()
| Event Text FIRE IN PROCESS GLOVE BOX
"On Saturday November 14, 2009 at approximately 0730 there was a heated high pressure release from the 5A/5B UF6 cylinder in the CDL facility Sublimation Station 3. At the time of the upset, the operators were in the process of preparing the cylinder for sublimation. They had just satisfactorily performed the valve leak checks (SOP 409 Section 56 step 5.3) and were performing the cylinder pressure test (SOP 409 Section 56 step 5.4). The cylinder was not being heated. The upset occurred when the cylinder valve was opened (step 5.4.7) to vent the cylinder to column 1D01. The release ruptured the connective teflon tubing that was enclosed in braided stainless steel. When flame was observed the operator actuated the CO2 release valve and extinguished the flame. The subsequent damage appears to be limited to: 1). Braided teflon tubing, 2). Singed area on lexan cover of the enclosure, 3). Possible leak on the inlet and outlet side of the eductor.
"Of note, column 1D01 was filled with DI water in preparation for startup. The solution should have a clear appearance but has been discolored by the upset. It appears to have been blackened, possibly from burning Teflon.
"As of 1200 PM the following actions have been taken to place the system in a safe condition:
1. Building 333 personnel were notified of the event and the 301/333 door was posted with caution.
2. Immediate area is roped off.
3. All involved personnel have received incident report forms for completion.
4. A firewatch has been posted (ISA requirement as cylinder contains >7.2 kgs UF6)
5. Supervisor verified valves on UF6 cylinder are shut.
6. Nasal smears taken on all affected personnel (7 dpm max; below action limit of 90).
7. High volume air sample taken with no elevated activity identified.
8. Area sampled for HF with a Draegor Tube (negative).
9. Verified no increase on room CAM [continuous air monitor].
10. Subsequent NCS [nuclear criticality safety] evaluation identified no concerns or NCS reportability issues.
11. System has been locked out of service with operational locks and appropriate signage placed on sublimation station #3.
12. Solution on the floor from the enclosure P traps has been cleaned up.
13. The enclosure overflow traps have been filled.
14. The CO2 gage has been verified functional and operations personnel are in the process of replacing the spent CO2 cylinder.
15. NDA has scanned the NaF trap (no elevated levels found).
16. Plant Superintendent took photos of equipment damage.
17. HP verified no damage to gloves.
18. Sublimation station #1 & 2 have been tagged 'Not Authorized for Use.'
19. All proper notifications made.
20. Plant Superintendent is in the process of developing a timeline of events.
"No actual exposures occurred to the workers, the public, and environment. Potential UF6 exposure to workers. However, no loss of containment occurred.
"No other structures, systems, or equipment components in the area were affected. Safety systems are operational.
"All sublimation stations have been taken out-of-service pending investigation results.
"The event is terminated. No declared emergency class.
"Notifications were made to the local county Emergency Management Coordinator and the Town of Erwin Fire Department.
"The NRC Resident Inspector has been notified." |
| General Information or Other | Event Number: 45501 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: OWENSBY & KRITIKOS
Region: 4
City: ALLIANCE State: LA
County:
License #: LA-2234-L01
Agreement: Y
Docket:
NRC Notified By: SCOTT BLACKWELL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/16/2009
Notification Time: 15:53 [ET]
Event Date: 11/12/2009
Event Time: [CST]
Last Update Date: 11/16/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4DO)
PATRICE BUBAR (FSME)
| Event Text AGREEMENT STATE REPORT - PERSONNEL OVEREXPOSURE DURING RADIOGRAPHY
The following report was received via facsimile:
"On November 13, 2009 the RSO [Radiation Safety Officer] for Owensby & Kritikos (O & K), contacted LDEQ [Louisiana Department of Environmental Quality] to report an excessive exposure. O & K had a radiography crew x-raying a pressure vessel. The radiographers believed that they had cranked the source in the camera. One of the radiographers went to the camera without a survey meter to remove the source guide tube. He was trying to put the safety plug on the end of the camera, but it would not go on. At this point, he realized that the source was not in the shielded position. Instead of roping off the area and calling the RSO per their procedures, they got the source in the shielded position themselves. This occurred on November 12, 2009 and the radiographers did not tell the RSO until November 13, 2009. Both of the pocket dosimeters were off scale. The radiographers said they where wearing their rate alarm meters. The personnel monitors were sent to Landauer for emergency processing. One of the radiographers had a dose of 5.57 rem for November with a year dose of 6.67 rem. The other radiographer had a November dose of 0.45 rem and a year dose of 1.00 rem. At this time, LDEQ believes these exposures to be true exposures to the radiographers. The crew had an AEA 660B camera, s/n B1495, that had a 79 Ci Ir-192 source, s/n 57338B. The last leak test was on October 12, 2009. LDEQ has begun an investigation and will report any new information. |
| General Information or Other | Event Number: 45509 | Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: TERRACON CONSULTING INC.
Region: 4
City: BRYANT State: AR
County:
License #: ARK082003121
Agreement: Y
Docket:
NRC Notified By: TAMMY KRIESEL
HQ OPS Officer: VINCE KLCO | Notification Date: 11/19/2009
Notification Time: 08:58 [ET]
Event Date: 11/18/2009
Event Time: 08:30 [CST]
Last Update Date: 11/19/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4DO)
LANCE ENGLISH (ILTA)
ANGELA MCINTOSH (FSME)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT INVOLVING A STOLEN/RECOVERED TROXLER MOISTURE DENSITY GAUGE
The following information was received via email:
"At approximately 0830 on the morning of November 18, 2009, the RSO (Radiation Safety Officer) of Terracon Consulting Inc. (ARK-0820-03121) reported the theft of a Troxler 3440 Moisture Density gauge (SN#27140) from a construction site at the Two Pines landfill in Jacksonville, Arkansas. The gauge contained an 9 mCi Cesium-137 source and a 44 mCi Americium-241/Beryllium source. According to the RSO, the gauge had been secured with two independent chains to the rear rack of an all terrain vehicle (ATV), which in turn was locked inside of a cargo shipping container after work was halted on November 17, 2009. When personnel arrived at the construction site at approximately 0700 on the 18th, they noted that the lock on the cargo container had been cut and that the ATV and gauge were missing. Local and state law enforcement were notified.
"At approximately 1340 on that same day, the Jacksonville Police Department reported that the gauge had been found along a roadside in Pulaski County. The gauge was examined by Department personnel and appeared to be undamaged, wipes tests were taken to further verify that the sources were not leaking. Terracon personnel were then allowed to take possession the gauge.
"The [Arkansas Department of Health] will keep this incident open pending the receipt of a report and corrective actions from the licensee."
Arkansas Incident Number: 11-09-01
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 |
| Power Reactor | Event Number: 45510 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: MIKE SLABY
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/19/2009
Notification Time: 13:59 [ET]
Event Date: 11/19/2009
Event Time: 13:00 [EST]
Last Update Date: 11/19/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RAYMOND MCKINLEY (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 OFFSITE NOTIFICATION DUE TO LOW LEVEL RADIOACTIVE SPILL
"The New York State Department of Environmental Conservation and other State and Local officials were notified today, November 19, 2009, that there had been a spill of low level radioactive material at an excavation site at the facility.
"Workers were conducting planned modification activities, replacing a section of piping, when sediment fell from the pipe to the ground and localized water at the excavation site. Samples of the localized water in the excavation after the sediment had fallen in exceeded the limit of the site procedure for notifying State and Local officials for a groundwater spill. No elevated levels have been detected in the nearest plant monitoring well. Therefore, we have no indications that there has been a release beyond the site from this source. Cleanup activities are currently in progress.
"The licensee notified the NRC Resident Inspector."
The section of piping being replaced was between the plant storm drain system and the discharge canal. The radioactive material was identified as Cs-137 but was not quantified at the time of this report. |
| Power Reactor | Event Number: 45511 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: JACK GADZALA
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/19/2009
Notification Time: 16:45 [ET]
Event Date: 09/27/2009
Event Time: 16:48 [CST]
Last Update Date: 11/19/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
ERIC DUNCAN (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text OPTIONAL 60-DAY TELEPHONIC NOTIFICATION FOR INVALID SPECIFIED SYSTEM ACTUATION
"[This is a] telephone notification made under 10 CFR 50.73(a)(2)(iv)(A) in lieu of submitting written Licensee Event Report.
"On September 27, 2009, following reactor shutdown and cooldown for a planned refueling outage, 4160 VAC Safeguard Bus 5 was being restored to normal electrical lineup. Emergency Diesel Generator (EDG) A was powering Bus 5 following successful completion of planned testing to satisfy Technical Specification requirements for testing of EDG automatic start, load shedding, and restoration, initiated by a simulated loss of all normal AC power.
"At 1648, while restoring Bus 5 to normal electrical lineup, breaker 1-503, Tertiary Auxiliary Transformer (TAT) supply to Bus 5, reopened after being closed. EDG A continued to supply Bus 5 without interruption. The following equipment tripped when breaker 1-503 opened: Residual Heat Removal (RHR) Pump A, Containment Fan Coil Units (CFCUs) A & B, Shield Building Ventilation (SBV) Fan A, and Service Water (SW) Pump A1. Auxiliary Feedwater (AFW) Pump A, Component Cooling (CC) Pump A, and SW Pump A2 were tripped and restarted by the blackout sequencer. All actuations were completed as designed and the components started and functioned successfully. AFW Train A had been properly removed from service for the EDG test and operated on minimum recirculation following AFW Pump A start.
"The equipment actuations resulted from an invalid signal caused by an electrical jumper for the blackout signal remaining installed during Bus 5 restoration. The jumper continued to inject a simulated loss of voltage (blackout) signal, causing the TAT supply breaker opening and load shedding and sequencer operation as designed.
"Inspection of breaker 1-503 was completed with no abnormalities noted. The jumper was removed and Bus 5 was restored to normal lineup. Corrective actions were initiated to revise the test procedure to more appropriately control bus restoration.
"Although the actuating signal that caused this event was invalid and the electrical bus had been appropriately aligned for the EDG test, this event is being reported because of the multiple and diverse components that were inadvertently actuated."
The licensee has notified the NRC Resident Inspector. | |