| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/17/2006 - 11/20/2006 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 42939 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: STEVE WHEELER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/27/2006
Notification Time: 10:02 [ET]
Event Date: 10/27/2006
Event Time: 03:37 [CDT]
Last Update Date: 11/17/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
JEFFREY CLARK (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text CONTAINMENT PATHWAY DECLARED INOPERABLE FOLLOWING LOCAL LEAK RATE TESTING
"This condition is being reported in accordance with the requirements of 10CFR50.72(b)(3)(ii) as an event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
"During local leak rate testing (LLRT) of the 'B' reactor feed line to the reactor, both primary containment boundary check valves (RF-CV-13CV and RF-CV-14CV) failed LLRT. Efforts to quantify the leak rate were unsuccessful. The maximum leakage indicated on the test equipment used is 424 standard cubic feet per hour (SCFH). The allowable leakage (La) for Primary Containment is 317.41 SCFH. The affected primary containment pathway was declared inoperable. CNS is in MODE 5 for refueling with vessel level greater than 21 feet above the flange and the spent fuel pool gates removed. No fuel movements or operations with the potential to drain the reactor vessel were in progress. Primary containment is not required per CNS Technical Specifications in this mode of operation.
"The NRC Senior Resident Inspector has been notified."
* * * RETRACTION FROM FLEMING TO HUFFMAN AT 1500 EST ON 11/17/06 * * *
"This notification is being made to retract Event Notification #42939 which reported a Primary Containment isolation pathway being declared inoperable following Local Leak Rate Testing (LLRT); specifically, the 'B' reactor feed line containment boundary inboard and outboard check valves. CNS has determined that the LLRT test method established test conditions that were not representative of the conditions under which the check valves would be required to perform their safety function. Inspection, in-situ testing and evaluation demonstrated the reactor feed line check valves would have performed their isolation functions during credible accident conditions. Thus, the condition was not a serious degradation of a principal safety barrier.
"During the normal plant shutdown to refueling outage RE23 with gradually decreasing feed flow, the check valve discs had not completely settled into the valve seats. Due to the slow pressurization rate of the LLRT working medium (air), sufficient differential pressure across the valve could not be developed which resulted in failing the test. Inspection of the check valves in their as-found condition revealed that a slight contact between the disc and the top of seat left a crescent shaped gap which, at the maximum (the bottom), was no more than 1/2 inch. An in-situ test measured the force needed to settle the disc into the seat and found it equated to a flow related pressure drop of less than 1 psid. A review of accident sequences concluded that post-accident pressurization of the feed lines would have closed the check valves for all credible accident scenarios. Check valve disc to pivot arm spacing adjustments were made to ensure sufficient disc float to reseat and fully close the valve from any open position. Subsequently, LLRT results were satisfactory."
The licensee notified the NRC Resident Inspector. R4DO (Johnson) notified. |
| Power Reactor | Event Number: 42971 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BOB VANDERBYE
HQ OPS Officer: JOHN KNOKE | Notification Date: 11/08/2006
Notification Time: 09:19 [ET]
Event Date: 11/08/2006
Event Time: 08:05 [CST]
Last Update Date: 11/17/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
PAUL FREDRICKSON (R2)
|
| 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 PLANT COMPUTER DOWN FOR UPGRADE
"Farley Nuclear Plant is replacing the Unit 1 plant computer with an upgraded plant computer. The total time that the plant computer may be down is a maximum of 10 days. The functions for emergency preparedness will be completed within the first 12 hours of the outage. During that first 12 hours a contingency plan is in place to ensure that the TSC would have the required data if an emergency was declared. A 5054Q was written for this and was reviewed by the Region 2 NRC EP staff prior to implementation."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 2045 EST ON 11/17/06 FROM FOREST LERO TO S. SANDIN * * *
The licensee successfully completed functional testing earlier today of the SPDS and has returned it to service as of 2045 EST on 11/17/06.
The licensee will inform the NRC Resident Inspector. Notified R2DO (Chuck Casto). |
| General Information or Other | Event Number: 42988 | Rep Org: ALABAMA RADIATION CONTROL
Licensee: BUILDING & EARTH SCIENCES, INC.
Region: 1
City: ALBERTVILLE State: AL
County:
License #: 1266
Agreement: Y
Docket:
NRC Notified By: DAVID A. TURBERVILLE
HQ OPS Officer: JOHN MacKINNON | Notification Date: 11/13/2006
Notification Time: 16:03 [ET]
Event Date: 11/12/2006
Event Time: 12:45 [CST]
Last Update Date: 11/17/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PAMELA HENDERSON (R1)
DUNCAN WHITE (R1)
GREG MORELL (NMSS)
ILTAB (NSIR)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT FROM ALABAMA - STOLEN TROXLER MOISTURE DENSITY GAUGE
Information was received via facsimile
"SUBJECT: Stolen Gauge Containing Radioactive Material - Alabama Event 06-46
"On the morning of November 13, 2006 at 8:00 am, (deleted) of Building and Earth Sciences, Inc. notified the Alabama Office of Radiation Control Duty Officer that a Troxler Model 3430 moisture density gauge was stolen from the back of pickup truck that was parked at a commercial storage location in Albertville, Alabama. Building and Earth Sciences, Inc. is authorized to possess and use radioactive material under their Alabama Radioactive Material License No. 1266. Preliminary information indicates that the gauge was discovered stolen approximately 1:30 pm on the afternoon of November 12, 2006. (Deleted) indicated that the Albertville Police Department had been notified and responded to the incident. The gauge was believed stolen sometime between 12:45 pm and 1:30 pm on November 12, 2006. The stolen gauge was identified as a Troxler model 3430, serial number 37367 with 8 millicuries of Cs-137, and 40 millicuries of Am-241:Be. (Deleted) indicated that a number of other items were stolen from the victim including three motorcycles and an air compressor.
"This information is current as of 3:00 pm CDT - November 13, 2006."
* * * UPDATE PROVIDED BY ALABAMA (TURBERVILLE) TO KOZAL VIA FAX ON 11/17/06 AT 0848 * * *
"On the morning of November 16, 2006, [Deleted] of Building and Earth Sciences,. Inc, notified the Alabama Office of Radiation Control that the Albertville Police Department had found the Troxler model 3430 moisture density gauge that was stolen from the licensee on November 12, 2006. Building and Earth Sciences, Inc is authorized to possess and use radioactive material under their Alabama Radioactive Material License No. 1266. The police department was given as anonymous tip and found the device in its transport container located in an abandoned lot in Albertville, Alabama. [Deleted] surveyed the device and found radiation levels were acceptable. An inspection of the device confirmed that this was the device stolen from the licensee on November 12, 2006. It was noted that someone had poured bleach on the unit. This appeared to be the only damage to the unit. [Deleted] took possession of the unit and was advised to perform a leak test of the unit before placing it back in service."
Notified R1DO (Henderson), NMSS EO (Camper), R1 (White) via-email and ILTAB (Sandler) via-email.
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. |
| General Information or Other | Event Number: 42997 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SCHLUMBERGER
Region: 4
City: ZAPATA State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: BILL GOTT | Notification Date: 11/16/2006
Notification Time: 08:54 [ET]
Event Date: 11/15/2006
Event Time: 21:30 [CST]
Last Update Date: 11/17/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CLAUDE JOHNSON (R4)
GREG MORELL (NMSS)
ILTAB VIA EMAIL ()
MEXICO VIA EMAIL ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text MISSING WELL LOGGING TOOL
At 2130 CST on 11/15/06, Schlumberger reported that a well logging tool was missing from the truck transporting the tool. The tool contained 1.5 curies of Tritium in a neutron target. It appears that the tool was lost or fell from the truck along a 50 mile portion of County Road 3169 in Zapata County, TX. A search for the tool is in progress.
* * * UPDATE VIA E-MAIL FROM TEXAS (JISHA) TO HUFFMAN AT 1630 EST ON 11/16/06 * * *
"At 2130 on Nov 15, 2006, a third party transport driver noted that he was missing a well logging tool that contains a neutron generator. The tool appears to have fallen off the truck along a fifty mile stretch of county road 3169 in Zapata county. The neutron generator contains 1.5 curies of tritium that is impregnated into the target of tube and is sealed within the tube and tool. No radiation is emitted by the generator and no public exposure is expected.
"Schlumberger personnel are searching the fifty miles of road and if the tool is not located on the first search, the Zapata county sheriff's office will be contacted. The search will continue at daylight. Additional notifications have been made to the Nuclear Regulatory Commission (NRC), U.S. Department of Transportation (DOT), and State Operations Center (SOC). The tool is a model 7158 manufactured by Schlumberger and is ~10 feet in length with an outside diameter of one and 11/16 inches. The device is made of stainless steel and has few markings on the exterior surface. The external surface of each neutron generator target is engraved with a target assembly I.D. number consisting of year-month-day (date of construction) and target position and the sequential serial number assigned to the neutron generator. After tritiation, the neutron generators have the model number (758, 761, or 762) and 'Radioactive H3' etched or engraved on the annulus of the end Kovar piece at the pinchoff end. The remaining annular space is taken by a second engraving of the serial number.
"Specific Item Missing: 1 11/16 inches OD logging tool continuing neutron generator approximately 108 inches (9 feet) long. The tool is made of steel and is cylindrical. Neutron Generator: Schlumberger Model 7158 covered by SSDR NR-316-D-101-S-1 (attached), Serial Number, 5710
Activity and Nuclide: 1.5 curies of tritium
"Description: Tritium is impregnated in a metal target contained within a sealed tube. The tube is sealed within an electronic housing (PNG-1032) and this electronic housing is contained with a well logging tool that is sealed and pressure rated to 15,000 psi."
The generator only produces neutron radiation when high voltage is applied.
R4DO (Johnson) and NMSS EO (Camper) notified. ILTAB notified via e-mail.
* * * UPDATE VIA E-MAIL FROM TEXAS (JISHA) TO GOTT AT 0831 EST ON 11/17/06 * * *
On 11/16/06, the licensee found the tool with the source intact, and it is reportedly at their Laredo facility.
Notified R4DO (C. Johnson) and NMSS (G. Morell) and emailed to ILTAB.
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. |
| Power Reactor | Event Number: 42998 | Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: ARNIE CRIBB
HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/17/2006
Notification Time: 15:48 [ET]
Event Date: 11/09/2006
Event Time: 14:44 [EST]
Last Update Date: 11/17/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
ROBERT HAAG (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text EMERGENCY DIESEL GENERATOR ACTUATION DURING TESTING
"At 1444 on 11/09/06, after initial installation of the Alternate AC power source, post modification testing was being performed in accordance with STP-125.021, requiring an abnormal lineup of the 'B' diesel generator (DG). Prior to starting the test, potential unforeseen conditions were discussed, but not documented in STP-125.021. During the test, 'B' DG was secured and returned to the standby mode. As individual loads were manually loaded on the 1 DB bus, bus voltage momentarily decreased. When the 'B' emergency feedwater pump was loaded, an undervoltage condition on 1 DB existed momentarily, starting the 'B' DG. The 'B' Engineered Safety Features Actuation System load sequencer had been de-energized prior to the test as required by STP-125.021. The 'B' DG did not tie onto the 1 DB bus since the load sequencer was de-energized. Voltage on the 1 DB bus was restored by the Alternate AC source, which was supplying the bus for testing. All loads were successfully loaded on the 1 DB bus and the test was satisfactorily completed.
"After further review and evaluation, SCE&G considers the actuation of 'B' DG, while undergoing post modification testing of the Alternate AC power source, reportable under 10CFR50.72(b)(3)(iv)(A)."
The licensee notified the NRC Resident Inspector and will also notify State and local authorities. | |