| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/05/2008 - 03/06/2008 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 44018 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: LOUISIANA DEPT OF TRANSPORTATION & DEVELOPMENT
Region: 4
City: LAKE CHARLES State: LA
County:
License #: LA-2467-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/29/2008
Notification Time: 10:39 [ET]
Event Date: 02/22/2008
Event Time: [CST]
Last Update Date: 02/29/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VIVIAN CAMPBELL (R4)
GREG MORELL (FSME)
| Event Text AGREEMENT STATE REPORT INVOLVING POTENTIAL DAMAGE TO A MOISTURE DENSITY GAUGE
The following report was received via email:
"A Louisiana Department of Transportation and Development (DOTD) van was involved, in an accident while carrying a Humboldt 5001 soil moisture density gauge. The gauge contained 10 mCi of Cs-137 (s/n9733GQ) and 40 mCi of Am-241 (s/nNJ03934). The Louisiana State Police notified LA DEQ of the accident and stated that the overpack was not breached and that readings at the surface were 0.9 mR/hr. The gauge and overpack were inspected at the DOTD district laboratory that was 0.5 miles from the accident. The overpack was in overall excellent condition except for a small hole (approximately 1 inch in circumference) which had been punched through the exterior wall but did not puncture the interior wall of the overpack. The overpack and gauge were surveyed by a DEQ inspector and recorded readings of 0.2 mR/hr at 1 meter which, correspond to the transportation index. A leak test has been sent off for the gauge and the results are pending. Will update with further information when it becomes available."
LA Event Report ID No.: LA080005 |
| General Information or Other | Event Number: 44019 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: TEAM INDUSTRIAL SERVICES
Region: 4
City: State: LA
County: ASCENSION PARISH
License #: LA-9098-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 02/29/2008
Notification Time: 11:09 [ET]
Event Date: 02/28/2008
Event Time: [CST]
Last Update Date: 02/29/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VIVIAN CAMPBELL (R4)
GREG MORELL (FSME)
| Event Text AGREEMENT STATE REPORT - OVEREXPOSED PERSONNEL MONITORING BADGE
The following information was received from the State of Louisiana via fax:
"On February 28, 2008, TEAM Industrial Services reported that an industrial radiographer's personnel monitoring badge received an excessive exposure of 10 rem. The industrial radiographer left his badge in the work truck while he was not performing radiography for a few days. The truck was parked next to a tank that was being x-rayed. According to TEAM, this exposure was just to the badge and not to the radiographer. According to TEAM, the actual exposure to the radiographer is 67 mrem. This incident is under investigation and further information will be forwarded once available."
LA Event Report ID: LA 080006 |
| General Information or Other | Event Number: 44022 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: AVERY DENNISON
Region: 1
City: CHICOPEE State: MA
County:
License #: G0342
Agreement: Y
Docket:
NRC Notified By: JOSH DAEHLER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 02/29/2008
Notification Time: 16:39 [ET]
Event Date: 07/01/2007
Event Time: [EST]
Last Update Date: 02/29/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LAWRENCE DOERFLEIN (R1)
PATRICE BUBAR (FSME)
ILTAB via email ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - MISSING RADIOACTIVE MATERIAL
"Avery Dennison, a General Licensee, reported to the Agency [MA Bureau of Environmental Health] via telephone at 10:15 a.m. on February 26, 2008 that two static eliminator devices are believed to be missing. Avery Dennison reported that one device was sent to the manufacturer in July, 2007 but that the manufacturer never received it. Avery Dennison reported that another device was in a box and it was tossed.
"The Agency followed up with the Licensee and the Manufacturer (NRD, LLC) of the devices and confirmed that the following two devices are believed to be missing:
"Device 1: NRD, LLC Model P-2001-080, s/n A2EV025, containing 181.1 millicuries of Po-210
"Device 2: NRD, LLC Model P-2001-080, s/n A2FM086, containing 181.1 millicuries of Po-210
"Device 1 has an approximate assay date of January 3, 2006.
"Device 2 has an approximate assay date of January 12, 2007.
"The Agency has scheduled a site visit with cognizant individuals to investigate the matter."
Notified R1DO (Doerflein), FSME EO (Bubar) and ILTAB 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. |
| Other Nuclear Material | Event Number: 44030 | Rep Org: PACIFICORP ENERGY
Licensee: PACIFICORP ENERGY
Region: 4
City: GILLETTE State: WY
County:
License #: GL714332-12
Agreement: N
Docket:
NRC Notified By: GARY L. HARRIS
HQ OPS Officer: JOE O'HARA | Notification Date: 03/05/2008
Notification Time: 11:47 [ET]
Event Date: 02/16/2007
Event Time: [MST]
Last Update Date: 03/05/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
CHUCK CAIN (R4)
SCOTT FLANDERS (FSME)
ILTAB VIA E-MAIL ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text TWELVE LOST TRITIUM EXIT SIGNS
The licensee provided the following information via email:
"In February of 2007 PacifiCorp Energy received the NRC letter (NRC Regulatory Issue Summary 2006-25) regarding Tritium exit signs. The receipt of the NRC 2006-25 instruction letter prompted Wyodak plant to do an inventory of Tritium exit signs and review the NRC standards and rules. When reviewing the 10CFR20.2201 rules in regards to missing sources, Wyodak plant subsequently started an investigation and discovery of the now missing Tritium exit signs.
"The following is a brief description of our investigation of missing Tritium exit signs:
"In 1993 a contractor (Montague) was hired to build a new coal handling facility at Wyodak plant that is owned by Black Hills Power and PacifiCorp Energy. An assumption is made that the contractor ordered 22 Tritium self luminating exit signs from Isolite and installed them in the new coal facility. The contractor (Montague) who built the Secondary Crusher Facility is no longer in business to verify any of the assumptions.
"During the facility construction most of the new coal handling facility was being handled by Black Hills Corporation. Later owner / operator lines were finalized and PacifiCorp Energy took over operation of the facility.
"In about 1999 the coal handling operator's control building which was a part of the 1993 facility was torn down. It is believed that two of the 1993 Tritium exit signs were destroyed with the demolition of this building.
"In 2003 Isolite notified PacifiCorp that the 22 self luminating Tritium exit signs purchased in 1993 were about to come to the end of their effective life. This call is what leads us to the assumption that 22 Tritium signs were purchased and installed in 1993. From the Isolite telephone call in 2003 PacifiCorp Energy's Wyodak plant purchased 22 new Tritium exit signs to replace the original 1993 signs. A work order was written to change out the old signs. The work order was never completed.
"From the ongoing investigation we now believe that only 16 of the original 22 Tritium exit signs were installed by the contractor (14 in the coal handling facility and 2 in its control building). It is assumed that 6 of the Tritium exit signs left the plant at the end of the 1993 construction with the contractor.
"We are currently working with Isolite to identify the serial numbers of the missing Tritium exit signs.
"Disposition of the radioactive material:
"6 - Tritium exit signs with 7.5 curries each are assumed to have been taken by the contractor (Montague) in 1993 - lost and not recoverable.
"2 - Tritium exit signs with 7.5 curries each were hauled to trash with the demolition of the coal operators control building in 1999 assumed lost and not recoverable.
"2 - Tritium exit signs with 7.5 curries lost by plant in 2003 assumed to be in a landfill and not recoverable.
"2 - Tritium exit signs with 11.5 curries, S/N's 224944 and 224947 lost by plant somewhere between 1993 and 2007 assumed to be in a landfill and not recoverable..
"Radiation exposure to individuals:
"It is believed that no individual exposure took place or any individual risk was involved.
"Actions taken to recover the material:
"Plant personnel have made a comprehensive search throughout the plant, plant storage and shop areas, plant warehouses, and coal facilities. Plant tried to make contact with the original installation contractor (Montague) but the company has gone out of business. Interviewed employees that might have had any knowledge of the Tritium exit signs. The results of the plant investigation are reported above.
"Actions taken to prevent recurrence.
"Wyodak Plant has completed an inventory of the 1993 and 2003 signs. Maps have been made of Tritium exit signs in use.
"A corporate policy has been initiated on the use and handling of Tritium exit signs. An annual inventory list with model and serial numbers has been created for tracking and inventory purpose. Employees responsible for the ordering, disposal, and installation of Tritium signs will receive annual training on the corporate policy."
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.
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: 44034 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: TIM SCHENK
HQ OPS Officer: PETE SNYDER | Notification Date: 03/05/2008
Notification Time: 17:44 [ET]
Event Date: 03/05/2008
Event Time: 14:43 [CST]
Last Update Date: 03/05/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
CHUCK CAIN (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 60 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC SCRAM DUE TO APPARENT MALFUNCTION IN TURBINE CONTROL SYSTEM
"At 2:43 p.m. CST, an unplanned automatic reactor scram occurred. The initial investigation determined that the event resulted from an apparent malfunction in the main turbine control system. This had the effect of causing reactor steam pressure to exceed the trip set point for the reactor protection system, initiating the reactor scram signal. All reactor control rods inserted, and the main feedwater system remained in service. Reactor safety-relief valves initially lifted as a result of the pressure transient. Reactor pressure is now being controlled by steam line drains with turbine bypass valves as a backup. There was no condition requiring the actuation of emergency diesel generators or emergency core cooling systems."
"NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 44036 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: RAYFORD RENO
HQ OPS Officer: PETE SNYDER | Notification Date: 03/05/2008
Notification Time: 20:15 [ET]
Event Date: 03/05/2008
Event Time: [CST]
Last Update Date: 03/05/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
CHUCK CAIN (R4)
|
| 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 FIFTEEN EMERGENCY SIRENS INOPERABLE FOR A TIME
"On March 5, 2008, at 1312 CST, fifteen (15) emergency notification system sirens in the Fort Calhoun Station Emergency Planning Zone (eleven in Harrison County, Iowa, four in Pottawattamie County, Iowa) were de-energized due to a un-planned power outage. The loss of AC Power to these emergency notification sirens impacted 15 of 101 total sirens; 8 of which had DC Battery Backup Power. As a result, this event is being reported under 10 CFR 50.72 (b)(3)(xiii) and guidance in NUREG-1022 as a major loss of off-site communications capability (e.g. offsite notification system).
"Power was restored to 8 sirens, 4 in Harrison County and all 4 from Pottawattamie County on March 5, 2008 at 1413 hours. One siren in Harrison County was restored at 1417 hours. The remaining 6 sirens were restored at 1529 hours. The power loss was determined to be due to a farm equipment malfunction."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44037 | Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: JOHN TAYLOR
HQ OPS Officer: JOE O'HARA | Notification Date: 03/05/2008
Notification Time: 22:20 [ET]
Event Date: 03/05/2008
Event Time: 21:00 [EST]
Last Update Date: 03/05/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
GEORGE HOPPER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text CIRCUMFERENTIAL PIPING CRACK
"On March 5, 2008, a volumetric ultrasonic examination of a Reactor Coolant to Decay Heat System pipe weld was analyzed and determined to identify an unacceptable indication. This dissimilar metal weld is located on the nozzle to the Decay Heat System drop line piping, which is the common suction line from the Reactor Coolant System and is a 12 inch outer diameter pipe. The indication is circumferential, is 15 inches in length, and reaches a maximum localized depth of 65 percent through-wall in one location. The weld was previously partially inspected during the November 2007 refueling outage using manual ultrasonic examination and no indications were identified. The current inspection was done using newly qualified phased array ultrasonic examination techniques in response to industry operating experience regarding dissimilar metal weld flaws. The indication has been found unacceptable per paragraph IWB 3514.4 of the 1989 Addenda of ASME Section XI without further fracture mechanics analysis and is therefore considered reportable.
"Preparations for a weld overlay repair and further confirmatory manual ultrasonic testing examinations are in progress.
"The licensee notified the NRC Resident Inspector." | |