| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/10/2007 - 01/11/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43069 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: HDR CONSTRUCTION CORP
Region: 1
City: TAMPA State: FL
County: POLK
License #: 2763-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: BILL HUFFMAN | Notification Date: 01/02/2007
Notification Time: 10:37 [ET]
Event Date: 01/01/2007
Event Time: 20:30 [EST]
Last Update Date: 01/10/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAYMOND LORSON (R1)
JOE GIITTER (NMSS)
ILTAB VIA E-MAIL ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - FLORIDA - STOLEN MOISTURE DENSITY GAUGE.
A truck belonging to the licensee flipped over on a highway in Polk County, FL on January 1, 2007, at approximately 8 or 9 pm. The truck was carrying a Humboldt Model 5001EZ moisture density gauge (nominal 50 millicuries Am-241/Be and 10 millicuries Cs-137). The driver was unhurt and walked to a local business to report the accident leaving the gauge unattended. The gauge was stolen while the driver was gone. Police were notified and a report filed. The gauge was locked inside of the locked case and chained to the vehicle.
FL report #FL07-001
* * * UPDATE FROM STATE OF FLORIDA (FURNACE) TO HUFFMAN AT 0726 EST ON 1/10/07 * * *
The State reports that a gauge meeting the description of the missing gauge was found by a Polk County representative on the side of a road. The gauge was not in its case but was intact and did not appear to be damaged. The gauge is being stored by the County (which is licensed to possess and use moisture density gauges) in an authorized safe and secure storage location and will be transferred to the licensee today. The licensee plans to send the gauge to a vendor to have it checked-out, leak tested, and certified for use before returning it to service.
R1DO (Bellamy) and NMSS (Morell) have been notified. ILTAB notified by e-mail.
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: 43074 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: UNIV. OF WISCONSIN HOSPITAL AT MADISON
Region: 3
City: MADISON State: WI
County:
License #: 25-1323-01
Agreement: Y
Docket:
NRC Notified By: JASON HUNT
HQ OPS Officer: JOHN MacKINNON | Notification Date: 01/04/2007
Notification Time: 11:33 [ET]
Event Date: 12/27/2006
Event Time: 12:00 [CST]
Last Update Date: 01/04/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHN MADERA (R3)
GREG MORELL (NMSS)
| Event Text WISCONSIN AGREEMENT STATE REPORT
"Event Location: University of Wisconsin Hospital, 600 Highland Avenue, Madison, Wisconsin 53792
"The event occurred on Wednesday, December 27, 2006. A patient was to receive 4 high dose-rate brachytherapy fractions of 5 Gy each over a 7 cm length of the vaginal mucosa using a vaginal cylinder.
"About halfway through the first treatment fraction, the actual dose delivered to part of the target organ, over the inferior 3 cm of the treatment length, exceeded the prescribed dose by more than 50%, (range 1.5 - 2.37 times the prescribed dose).
"The biological dose to the patient from this event was under the prescribed dose. The subsequent 3 fractions will be modified to deliver the intended biological dose to the patient, and no adverse health effects are expected to the patient.
"Notification, by the licensee, of this event to the Department of Health and Family Services (DHFS) occurred on Thursday, December 28, 2006. DHFS will dispatch a team on Monday, January 8, 2007 to investigate this event."
Event Report ID No: WI-07-01
A "Medical Event" may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| General Information or Other | Event Number: 43079 | Rep Org: MAINE RADIATION CONTROL PROGRAM
Licensee: CITY OF PRESQUE ISLE
Region: 1
City: PRESQUE ISLE State: ME
County:
License #: 03701G
Agreement: N
Docket:
NRC Notified By: SHAWN SEELEY
HQ OPS Officer: PETE SNYDER | Notification Date: 01/05/2007
Notification Time: 15:45 [ET]
Event Date: 12/21/2006
Event Time: 14:00 [EST]
Last Update Date: 01/05/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANTHONY DIMITRIADIS (R1)
GREG MORELL (NMSS)
ILTAB (EMAIL) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS
On December 21, 2006 at approximately 2 pm local time the Maine Radiation Control Program received notification from a licensee, the City of Presque Isle, that they had lost 5 tritium exit signs during building renovations. Sometime between August 2006 and December 2006 at the time of the report to the state the licensee noted that 6 tritium exit signs had been disposed of as part of renovations to Building 1309. The signs were manufactured by Safety Light Corporation, Model 2040-50-20. The serial numbers are 0941221, 0941229, 0941223, 0941227, 0941225, and 0941228. While the exact location of the signs is not known they were probably disposed of in the trash. The state estimated the activity per sign to be about 5 Curies. The state is following up on this report.
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: 43081 | Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: HENRY T CURRY
HQ OPS Officer: JASON KOZAL | Notification Date: 01/06/2007
Notification Time: 10:00 [ET]
Event Date: 01/06/2007
Event Time: 10:00 [EST]
Last Update Date: 01/10/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
CHARLIE PAYNE (R2)
|
| 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 LOSS OF SPDS PARAMETER DISPLAY DUE TO PLANNED MODIFICATION
"At 0904 hours EST, on January 6, 2007, the Emergency Response Facility Information System (ERFIS) computer system was removed from service to perform a planned modification of the ERFIS power supply system. The expected duration of ERFIS inoperability is approximately 2 hours. The ERFIS computer system provides monitoring and communications capability for plant data systems including the Emergency Response Data System (ERDS), Safety Parameter Display System (SPDS), Meteorological Data link system, and the Inadequate Core Cooling Monitor (ICCM). The loss of ERFIS requires alternate methods, as described in plant procedures, to be used for the above-described functions. Therefore, it is expected that appropriate assessment of plant conditions, notifications, and communications could still be made, if required, during the time that the ERFIS Computer system 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 remained available to assess plant conditions, make notifications, and accomplish required communications, as necessary. An additional message will be provided when the ERFIS is restored."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE PROVIDED BY HENRY CURRY TO JEFF ROTTON AT 1158 EST ON 01/06/07 * * *
ERFIS computer has been returned to operable status at 1146 EST. Licensee notified NRC Resident Inspector.
Notified R2DO(Payne) |
| Other Nuclear Material | Event Number: 43085 | Rep Org: AIR PRODUCTS & CHEMICALS, INC.
Licensee: AIR PRODUCTS & CHEMICALS, INC.
Region: 1
City: ALLENTOWN State: PA
County:
License #: GL
Agreement: N
Docket:
NRC Notified By: KEVIN B. SNYDER
HQ OPS Officer: STEVE SANDIN | Notification Date: 01/10/2007
Notification Time: 15:17 [ET]
Event Date: 12/15/2006
Event Time: [EST]
Last Update Date: 01/10/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
| Person (Organization):
RONALD BELLAMY (R1)
GREG MORELL (NMSS)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text MISSING GENERAL LICENSE ELECTRON CAPTURE DETECTOR
During an inventory for license transfer, a Delphi Instruments electron capture device, model #4402 S/N 2546, containing 50 mCi Tritium was discovered missing. The device was used to measure contamination in argon gas streams. The licensee received the device at their NY facility in April 2000. Since no wipe test is required the last use of this device is unknown. The licensee conducted two exhaustive searches with negative results.
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: 43086 | Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRAD HARDT
HQ OPS Officer: STEVE SANDIN | Notification Date: 01/10/2007
Notification Time: 16:36 [ET]
Event Date: 01/10/2007
Event Time: 12:35 [CST]
Last Update Date: 01/10/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BLAIR SPITZBERG (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF OFFSITE LANDLINE COMMUNICATIONS CAPABILITY DUE TO CUT FIBER OPTIC CABLE
"On 01/10/2007 at 1235 CST, the Unit 1 control room was notified that the offsite fiber cable from Palacios to Port Lavaca was cut at approximately 1155 hours by a building contractor just out of Palacios on Texas Highway 35. Verizon dispatched a crew to repair. Estimated time for repair is about 4 hours.
"Offsite communications is lost from both Unit 1 and Unit 2 control rooms including the state and county ring down lines, the NRC ring down line and the ability to transfer information from the Emergency Response Data System (ERDS) to offsite agencies. Satellite phones remain available.
"At 1258 CST, the NRC Operations Center was notified via satellite communications of alternate phone numbers to contact the Unit 1 and Unit 2 Control Rooms. This is a follow-up to make the notification of this event to the NRC pursuant to 10 CFR 50.72 (b)(3)(xiii).
"The NRC Senior Resident Inspector was notified of this issue."
* * * UPDATED AT 1830 EST ON 01/10/07 FROM CHRIS VAN FLEET TO S. SANDIN * * *
All offsite lines have been restored as of 1716 CST on 01/10/07. The licensee informed the NRC Resident Inspector. Notified R4DO (Spitzberg). |
| Power Reactor | Event Number: 43088 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: ROBERT SCHREIFELS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 01/10/2007
Notification Time: 19:46 [ET]
Event Date: 01/10/2007
Event Time: 15:28 [CST]
Last Update Date: 01/10/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
THOMAS KOZAK (R3)
HO NIEH (NRR)
THOMAS BLOUNT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 87 | Power Operation | 0 | Hot Shutdown | Event Text REACTOR SCRAM WITH STUCK OPEN MAIN TURBINE CONTROL VALVES
"At 1528 hours Central Time, a RPS trip occurred, all rods fully inserted. Turbine valve testing was in progress. A group 1 isolation occurred with all MSIVs closing. A partial group 2 occurred due to low reactor water level. All safety systems (valves) operated correctly. Currently reactor pressure/cooldown in progress using HPCI in pressure control, normal condensate and feedwater in service for reactor water level control. Investigation of cause is in progress."
Group isolations resulted from low pressure and low reactor water level. During the transient and subsequent cooldown, Operators manually opened the main steam relief valves to maintain pressure control in accordance with the plant EOPs. HPCI was manually started to maintain reactor level. The group 2 isolation has been reset. The group 1 isolation (MSIVs) will not be reset until after the main turbine control valves are shut. The plant is being cooled down to initiate RHR cooling and is in the normal shutdown electrical lineup.
The licensee notified the NRC Resident Inspector. | |