| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/01/2006 - 08/02/2006 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 42735 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: NONDESTRUCTIVE & VISUAL INSPECTION
Region: 4
City: HOUMA State: LA
County:
License #: LA-5601-01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: MIKE RIPLEY | Notification Date: 07/27/2006
Notification Time: 16:50 [ET]
Event Date: 07/27/2006
Event Time: [CDT]
Last Update Date: 07/27/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS FARNHOLTZ (R4)
EDWIN HACKETT (NMSS)
GREG MORELL (EMAIL) (NMSS)
| Event Text LOUISIANA AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE
The State provided the following information via facsimile:
"Non-Destructive & Visual Inspection (NVI) reported an excessive exposure to an industrial radiographer on July 27, 2006. [NAME DELETED], RSO, was called by Landauer [dosimetry service] with an exposure of 11,792 mrem for the month of June 2006 for [NAME DELETED]. [The RSO] is conducting an investigation into the excessive exposure and will supply further information once it is available. [The radiographer] told [the RSO] that he could not remember when he would have received such a high dose. Additional information will be provided to the NRC from the State of Louisiana as it becomes available."
Louisiana Event Report ID No.: LA-060016 |
| General Information or Other | Event Number: 42736 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: CHILDREN'S MEMORIAL MEDICAL CENTER
Region: 3
City: CHICAGO State: IL
County:
License #: IL-01165-01
Agreement: Y
Docket:
NRC Notified By: JOE KLINGER
HQ OPS Officer: MIKE RIPLEY | Notification Date: 07/27/2006
Notification Time: 18:45 [ET]
Event Date: 07/24/2006
Event Time: [CDT]
Last Update Date: 07/27/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ROGER LANKSBURY (R3)
EDWIN HACKETT (NMSS)
GREG MORELL (EMAIL) (NMSS)
| Event Text ILLINOIS AGREEMENT STATE REPORT - MEDICAL EVENT
The State provided the following information via email:
"On July 26, the RSO at a broad-scope medical facility contacted the agency to report a possible medical event involving I-131. He stated that on July 24, a 5 microCurie Na-I thyroid uptake diagnostic study was ordered by an endocrinologist at the facility; however, instead of 5 microCuries, the doctor ordered a 2 millicurie dose. The nuclear technologist did not question the request and the dose was drawn and administered to the 16-year old male patient. When the authorized user listed on the license came in to do the imaging on July 25, he noted the error. It appears the authorized user was not directly involved in ordering the study. The licensee estimated the whole body dose as 1.89 Rem and the dose to the thyroid of 4,140 Rem based on 59.2% uptake. Using the same assumptions, the intended dose for 5 microCurie I-131 would be 10.4 Rem. The licensee anticipates some depletion of thyroid function as a result of this administration of 2 millicuries. The RSO continues to investigate the matter and more information will be provided."
Illinois Item Number: IL-060036 |
| Power Reactor | Event Number: 42746 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GEOFF BENNETT
HQ OPS Officer: JASON KOZAL | Notification Date: 08/01/2006
Notification Time: 11:32 [ET]
Event Date: 08/01/2006
Event Time: 03:35 [EDT]
Last Update Date: 08/01/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
JAY HENSON (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text RCS PRESSURE BOUNDARY LEAKAGE
"At approximately 0335 EDT, LCO 3.4.13, RCS Operational Leakage, Action C was entered due to the identification of a pressure boundary leak. Reactor Coolant System (RCS) leak is believed to be a small pinhole on the weld on the downstream side of the check valve on Loop 1 Cold Leg Safety Injection Line. The estimated RCS leak rate is 0.1 gallons per minute. The Unit was in Mode 3 at the time of discovery. This event is being reported under 10 CFR 50.72(b)(3)(ii)(A).
"The plant is currently evaluating the appropriate repair method for this condition."
The licensee notified the NRC Resident Inspector. |
| Fuel Cycle Facility | Event Number: 42747 | Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: RICK FOLECK
HQ OPS Officer: ARLON COSTA | Notification Date: 08/01/2006
Notification Time: 15:16 [ET]
Event Date: 08/01/2006
Event Time: 05:00 [EDT]
Last Update Date: 08/01/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
JAY HENSON (R2)
GREG MORELL (NMSS)
MELVYN LEACH (IRD)
| Event Text AUDIBLE HORN SYSTEM MALFUNCTION
"During a routine monthly test of the Criticality Warning System (CWS), a segment of that system (DCP & DOP Warehouse) was found to have no audible horns functioning. Processes were shutdown, the personnel evacuated and the emergency organization assembled.
"The preliminary investigation found that an Uninterruptible Power Supply (UPS) that supplies power to the CWS horn amplifiers was not functioning.
"After a retest verified that the horns in the balance of the plant were functioning, those areas were allowed to resume operations. At the same time, the UPS for the DCP/DOP Warehouse segment of the system was replaced with a new unit and allowed to charge. Once charged, the system was tested and verified to have audible horn coverage. Operations were then allowed to restart in these areas.
"As of approximately 1210 PM the CWS horns were fully operational and the facility was returned to normal operational status. Investigation of the incident is continuing including an attempt to determine the root cause of the UPS malfunction."
The licensee notified Region II (J. Pelchat) and will notify State and local organizations. |
| Power Reactor | Event Number: 42749 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: NICK LIZZO
HQ OPS Officer: JASON KOZAL | Notification Date: 08/02/2006
Notification Time: 04:49 [ET]
Event Date: 08/02/2006
Event Time: 00:06 [EDT]
Last Update Date: 08/02/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
PAT FINNEY (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 | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF ALL OFF SITE EMERGENCY NOTIFICATION SIRENS
"On August 2, 2006 at approximately 0006 hours, the Emergency Planning Department determined that all of the 156 sirens in the Indian Point Energy Center, Emergency Planning Zone were unavailable due to, an inability to activate the sirens through the computer operating system. In accordance with the Indian Point reporting criteria, the loss of 16 or more sirens that cannot be returned to service in one hour, constitutes a major loss of the offsite notification capability that requires an 8-hour non-emergency notification in accordance with 10CFR 50.72(b)(3)(xiii).
"The Emergency Plan has route alerting and public radio announcement available as necessary to notify the public in lieu of the non-operational sirens.
"The condition was recorded in the IPEC Corrective Action Program as CR# 1P2-2006-04625 and actions have been initiated to investigate and correct the condition.
"Troubleshooting continues. The cause of failure is still unknown at this time."
The licensee notified the NRC Resident Inspector, state, and local governments of this event. | |