| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/17/2007 - 08/20/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43570 | Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: PEPSI BOTTLING GROUP
Region: 4
City: CANTON State: MS
County:
License #: WN-R0831
Agreement: Y
Docket:
NRC Notified By: BOBBY SMITH
HQ OPS Officer: JASON KOZAL | Notification Date: 08/15/2007
Notification Time: 18:06 [ET]
Event Date: 08/15/2007
Event Time: [CDT]
Last Update Date: 08/15/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LINDA HOWELL (R4)
JOSEPH HOLONICH (FSME)
| Event Text AGREEMENT STATE REPORT - INADVERTENT SHIPMENT OF RADIOACTIVE MATERIAL
The State provided the following information via email:
"DRH received notification on 8-15-07 from the Washington Dept. of Health, about the possibility of two (2) Industrial Dynamic Models FT-12 (Device Serial # 101942/Source # 318) and FT-50 (Device Serial No. 116158/Source # 3109) each containing 100 millicuries of Americium 241, being [inadvertently] delivered to a company in Mississippi. Washington DOH asked MS DRH to assist. DRH sent inspectors to the Canton, Mississippi location and verified that the sources were in both devices. DRH called Washington DOH and reported that the devices were indeed at that location.
"DRH called contractor QSA Global for assistance with disposal. QSA will deal directly with company that shipped devices to Mississippi.
"DRH confirmed both sources were in [the] devices with survey measurements of 0.7 mR/hr at [the] surface."
Mississippi report number - MS 07003 |
| Power Reactor | Event Number: 43573 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MIKE RAMSEY
HQ OPS Officer: JOE O'HARA | Notification Date: 08/17/2007
Notification Time: 10:35 [ET]
Event Date: 08/17/2007
Event Time: 09:55 [EDT]
Last Update Date: 08/17/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
HAROLD GRAY (R1)
|
| 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 WEATHER ALERT SYSTEM WAS INOPERABLE
"Received notification from VY E-Plan of an outage of the Ames Hill NOAA transmitter.
"Made notifications per AP 0156. E-Plan Duty Officer investigating the cause.
"Ames Hill NOAA transmitter restored at 1037.
No sirens were affected during the transmitter outage.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43574 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: S. MAZURKIEWICZ
HQ OPS Officer: JOHN MacKINNON | Notification Date: 08/17/2007
Notification Time: 11:00 [ET]
Event Date: 08/17/2007
Event Time: 08:00 [PDT]
Last Update Date: 08/17/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANTHONY GODY (R4)
HAROLD GRAY (R1)
|
| 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 OFFSITE NOTIFICATION TO THE UNITED STATES DEPARTMENT OF TRANSPORTATION
"Pursuant to 10 CFR 50.72(b)(2)(xi), Energy Northwest hereby informs the Nuclear Regulatory Commission (NRC) of an intent to report a undeclared shipment of hazardous material to the Department of Transportation (DOT).
"Energy Northwest recently discovered that two EntryScan Explosive Detectors, each containing a 10 mCi (millicurie) Nickel-63 source, were transferred to PPL Susquehanna, LLC without designating the shipment as Radioactive Material, Excepted Package, Instruments or Articles, 7, UN2911 and received in Berwick, PA on April 17, 2007. Energy Northwest has confirmed that the devices are under the control of an entity licensed to possess such material.
"There were no consequences associated with this incident and the potential for radioactive exposure of any individual as a result of this shipment was negligible."
The NRC Resident Inspector was notified of this event by the licensee. |
| Power Reactor | Event Number: 43575 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: KEN KINGSTON
HQ OPS Officer: JASON KOZAL | Notification Date: 08/17/2007
Notification Time: 15:21 [ET]
Event Date: 08/17/2007
Event Time: 10:53 [CDT]
Last Update Date: 08/17/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANTHONY GODY (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 OFFSITE NOTIFICATION PERFORMED DUE TO EXTERNAL ENVIRONMENTAL EVENT
"On Friday August 17, 2007 at 10:30 CDT, the Fort Calhoun Nuclear Station Control Room was notified of a 'diesel fuel' type smell and oil sheen on the Missouri River. Further investigation found the source of the oil was from an outside source upstream of Fort Calhoun Station, which is approximately 20 miles north of Omaha, NE. Per station procedures, the Omaha Public Power District (OPPD) Corporate Environmental Affairs was notified of the oil sheen observations.
"On Friday, August 17 at 1053 CDT, OPPD Corporate Environmental Affairs contacted the Nebraska Department of Environmental Quality (NDEQ) of the oil sheen observations. Two contacts were made to Release Response Unit and the Compliance Inspectors Office. OPPD Corporate informed the NDEQ that an oil sheen was observed coming down the river past Fort Calhoun Station. The oil sheen smelled of diesel fuel or similar odor. The oil sheen was not coming from Fort Calhoun Station."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43577 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF TODD
HQ OPS Officer: JOHN MacKINNON | Notification Date: 08/18/2007
Notification Time: 00:02 [ET]
Event Date: 08/17/2007
Event Time: 21:58 [EDT]
Last Update Date: 08/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
CHARLES R. OGLE (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE PUBLIC ALERTING SIRENS INOPERABLE FOR A SHORT TIME DUE TO A LIGHTNING STRIKE
"On the evening of 8/17/07 several light(n)ing strikes were noted in the Vogtle Electric Generating Plant area during a rain storm. Information Technology (IT) personnel were dispatched to check for proper operations of IT equipment and found the primary transmitter for the offsite public alerting sirens to be damaged and out of service. IT personnel swapped the offsite public alerting sirens over to a secondary transmitter and verified that they were operable and returned them to service @ 22:01 hrs on 8/17/07. The primary transmitter will be repaired next week. This is reportable under 10CFR50.72(b)(3)(xiii). (8 hour notification)"
The NRC Resident Inspector was notified of this event by the licensee. |
| Fuel Cycle Facility | Event Number: 43578 | Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PIKETON State: OH
County: PIKE
License #: GDP-2
Agreement: Y
Docket: 0707002
NRC Notified By: JIM MCCLEERY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/18/2007
Notification Time: 20:18 [ET]
Event Date: 08/18/2007
Event Time: 02:10 [EDT]
Last Update Date: 08/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
CHARLES R. OGLE (R2)
JOSEPH HOLONICH (FSME)
| Event Text FEED FACILITY AUTOCLAVE O-RING FAILURE
"08-18-07 at 0210 in the X-342 , Feed Facility, Autoclave #1, 10 minutes into the heating cycle (mode II) experienced an air leak past the Viton O-ring. The steam was secured and autoclave shell opened 30 minutes later. Inspection of the Viton O-ring resulted in the discovery of a 3/8" separation of splice joint. A pressure decay was performed to determine if the O-ring would have performed its 'Q' function. The test failed resulting in a 24 hr. event."
This was reported under 10CFR76.120(c)(2)(i).
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 43579 | Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: MICHAEL MCBREARTY
HQ OPS Officer: JOHN MacKINNON | Notification Date: 08/19/2007
Notification Time: 02:23 [ET]
Event Date: 08/18/2007
Event Time: 19:55 [PDT]
Last Update Date: 08/19/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
| Person (Organization):
ANTHONY GODY (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 99 | Power Operation | 99 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMERGENCY DIESEL GENERATOR WORK PLATFORMS NOT PROPERLY RESTRAINED
"On August 18, 2007, at about 1955 PDT, both of SONGS Unit 3 Emergency Diesel Generators (EDG) were found in a condition that was not seismically analyzed. At about 2015 PDT on August 18, 2007, both of SONGS Unit 2 EDGs were found to be in the same unanalyzed condition. The condition involved EDG maintenance work platforms that had not been properly restrained, and, in the position found, could potentially render the EDGs inoperable during a seismic event.
"SCE is reporting this occurrence as a potential loss of safety function in accordance with 10CFR50.72(b)(3)(v).
"SCE took immediate actions to properly restrain the EDG work platforms, and an evaluation will be conducted to determine the cause of this event. At the time of this occurrence, Unit 2 was operating at about 99% power and Unit 3 was operating at about 100% power. SCE has notified the NRC Senior Resident Inspector about this occurrence and will provide them with a copy of this report." |
| Power Reactor | Event Number: 43580 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: CALVIN WARD
HQ OPS Officer: JASON KOZAL | Notification Date: 08/19/2007
Notification Time: 22:19 [ET]
Event Date: 08/19/2007
Event Time: 17:00 [EDT]
Last Update Date: 08/19/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
CHARLES R. OGLE (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text PLANT SHUTDOWN DUE TO UNISOLABLE REACTOR COOLANT SYSTEM LEAKAGE
"On 08/18/2007 at 16:03 EDT a Planned Manual Reactor Trip was initiated on Unit 2 based on increased unidentified RCS leakage. The RCS leakage had increased over a two day period and surpassed the hard limit of 0.28 gpm established by a plant Operational Decision Making (ODM) plan. The downpower was initiated on 08/18/07 at 10:35 EDT from 100% power and proceeded in a controlled manner to 25% power. The Feedwater Control System was maintained in the automatic mode. Station Power was transferred by procedure from the Auxiliary to the Startup Transformers. The reactor was manually tripped at 16:03 EDT. Following the reactor trip, EOP-1, Standard Post Trip Actions, and EOP-2, Reactor Trip Recovery procedures were completed without contingencies and the unit was stabilized in Mode 3. Decay heat was removed by the Steam Bypass Control System (SBCS) to the condenser. The Steam Generators were fed by the MFW System and levels remained above Auxiliary Feedwater Actuation (AFAS) setpoint. There were no significant equipment failures identified post trip. The plant was cooled down and entered Mode 5 on 8/19/07 at 15:09 EDT.
"On 8/19/07 at 17:00 EDT while in Mode 5, a Containment walkdown confirmed the 2B1 RCP Seal injection line to be the only active RCS leakage source. The leak is unisolable from the RCS and is located at or adjacent to a socket weld on the 3/4" Class 1 Schedule 160 seal injection line. Removal of obstructions and insulation must occur before the specific details of the leak can be identified.
"This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(3)(ii)(A). Additional investigation is being perform to determine the detailed configuration of the leak and the root cause."
The licensee notified the NRC Resident Inspector. | |