| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/26/2010 - 03/01/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45716 | Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: UNIVERSITY OF KENTUCKY
Region: 1
City: LEXINGTON State: KY
County: FAYETTE
License #:
Agreement: Y
Docket:
NRC Notified By: MARISSA VEGA VELEZ
HQ OPS Officer: DAN LIVERMORE | Notification Date: 02/23/2010
Notification Time: 13:56 [ET]
Event Date: 02/23/2010
Event Time: 09:45 [CST]
Last Update Date: 02/23/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE SCHMIDT (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - GAMMA KNIFE TREATMENT TO WRONG LOCATION
A gamma knife treatment prescribed to be administered to the left side of a patient was instead administered to the patient's right side. The scheduled 30 minute, 90 Gray procedure was terminated after 1.4 minutes when the administering physician detected the error. It is estimated that 4% of the prescribed dose was administered to the wrong area.
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: 45720 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: ALCOA WORLD ALUMINA
Region: 4
City: POINT COMFORT State: TX
County:
License #: 05189
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 02/24/2010
Notification Time: 11:11 [ET]
Event Date: 02/19/2010
Event Time: [CST]
Last Update Date: 02/24/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RYAN LANTZ (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - STUCK PROCESS GAUGE SHUTTER
The following information was received from the State of Texas via email:
"On February 23, 2010, at 1500 hours, the [State of Texas] was notified by the licensee that the operating mechanism for the shutter shielding device on a Thermo Fisher model 5201 nuclear gauge had failed. The gauge is normally operated with the shielding for the source in the open position. The licensee stated that the current condition of the gauge poses no additional health risk to individuals. The gauge contains a Cesium (Cs)-137 source with an original activity of 100 milliCuries. The gauge is located 10 feet off of the ground and is accessed using a ladder to a platform. The area has been posted to prevent anyone from performing maintenance in the area. The licensee has contacted the manufacturer to repair the gauge. [State of Texas] will provide additional information as it is obtained."
TX Report I-8713 |
| Power Reactor | Event Number: 45729 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: BRIEN STRIZZI
HQ OPS Officer: JOHN KNOKE | Notification Date: 02/26/2010
Notification Time: 11:48 [ET]
Event Date: 02/26/2010
Event Time: 11:25 [EST]
Last Update Date: 02/26/2010 | 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):
WAYNE SCHMIDT (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO LOSS OF TWO CIRCULATING WATER PUMPS
The "C" Circulating Water Pump tripped on high delta pressure across the screens. Another Circulating Water Pump was out of service for maintenance. This condition required a shutdown, therefore the reactor was manually tripped. This caused the steam generator level to reach the low level setpoint. There was a loss of Main Feedwater Pumps when breaking condenser vacuum. Auxiliary Feedwater Pumps started automatically upon low level in the steam generators. The letdown system was isolated post trip and the charging and letdown systems are restored to normal lineup. The plant is in Mode 3.
All rods fully inserted. Decay heat is being removed via atmospheric dump valves. There are no known primary to secondary leaks in the steam generator tubes. The electrical lineup is normal with offsite power.
The licensee has notified the NRC Resident Inspector. |
| Other Nuclear Material | Event Number: 45730 | Rep Org: ALPHA COAL WEST
Licensee: ALPHA COAL WEST
Region: 4
City: GILLETTE State: WY
County:
License #: 963-03
Agreement: N
Docket:
NRC Notified By: TERRY BOSECKER
HQ OPS Officer: JOHN KNOKE | Notification Date: 02/26/2010
Notification Time: 13:15 [ET]
Event Date: 02/26/2010
Event Time: 10:20 [MST]
Last Update Date: 02/26/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
RYAN LANTZ (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text MISSING SHUTTER ON TEXAS NUCLEAR LEVEL GAUGE
While on a routine inspection, a technician from Thermal Fisher notified the RSO that a shutter was missing from Texas Nuclear gauge #5202, s/n #B2302. The technician indicated he will try and get a replacement shutter for the gauge. This gauge is used for level indication in a coal hopper and the shutter is normally open. The gauge's source is 200 mCi of Cs-137. |
| Power Reactor | Event Number: 45731 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: JOE O'HARA | Notification Date: 02/26/2010
Notification Time: 14:17 [ET]
Event Date: 02/26/2010
Event Time: 08:30 [CST]
Last Update Date: 02/26/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RYAN LANTZ (R4DO)
|
| 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 IN-PLANT PAGING SYSTEM OUT OF SERVICE
"At about 0830 CST on 2/26/2010 , it was discovered that the station paging system was not operating. Repair efforts were initiated. The Control Room and station personnel were notified of the pager outage. The automated callout system is available to notify the emergency response organization during the pager outage if needed."
* * * UPDATE FROM JOHN MUSSER TO JOE O'HARA AT 1556 EST ON 2/26/10 * * *
The station paging system was restored to operable status at 1400 CST. The licensee will notify the NRC Resident Inspector.
Notified the R4DO(Lantz). |
| Power Reactor | Event Number: 45732 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JERRY PIERCE
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/27/2010
Notification Time: 07:37 [ET]
Event Date: 02/27/2010
Event Time: 01:58 [EST]
Last Update Date: 02/27/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
BRIAN BONSER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM MANUALLY STARTED TO MAINTAIN REACTOR PRESSURE VESSEL LEVEL FOLLOWING A PRE-PLANNED REACTOR SCRAM
"On February 27, 2010, at 0116 hours, as part of a pre-planned sequence of events, Unit 1 control room operators manually inserted a Reactor Protection system trip to shut down the reactor from approximately 21 percent of rated thermal power to begin a planned refuel outage. At 0158 hours, the Reactor Core Isolation Cooling (RCIC) system was manually started to maintain reactor pressure vessel (RPV) coolant level after the 1A Reactor Feedwater Pump (RFP) was shutdown due to high turbine casing drain level, and the 1B Reactor Feedwater Pump (RFP) had been removed from service and isolated to support maintenance activities. The Reactor Core Isolation Cooling (RCIC) system started and maintained reactor pressure vessel (RPV) coolant level until the 1B Reactor Feedwater Pump (RFP) could be returned to service at 0248 [hours]. The Reactor Core Isolation Cooling (RCIC) system was shutdown at 0306 [hours].
"The safety significance of this occurrence is considered minimal. The RCIC system is designed to operate either automatically or manually following RPV isolation, accompanied by a loss of normal coolant flow from the Reactor Feedwater system, to provide adequate core cooling, and control of the RPV coolant level. The function of the RCIC system is to respond to transient events by providing makeup coolant to the reactor. For this event, the RPV was not isolated, but there was a loss of normal coolant flow from the Reactor Feedwater System. The RCIC system was manually started and successfully controlled RPV coolant level for approximately 68 minutes until Reactor Feedwater system flow could be restored to the RPV. All emergency core cooling systems were operable and ready for use, if needed, during this event. This transient is bounded by the analyses in the Updated Final Safety Analysis Report."
RPV level remained in the normal post-shutdown band of 170-200 inches during the transient. The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 45734 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JOHN KEMPKES
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/28/2010
Notification Time: 04:10 [ET]
Event Date: 02/28/2010
Event Time: 01:45 [CST]
Last Update Date: 02/28/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANN MARIE STONE (R3DO)
DENNIS ALLSTON (ILTA)
|
| 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 OF STATE AND TRIBAL AGENCIES
"At 0145 Prairie Island Security personnel detected an unknown person within the Owner Controlled Area. The individual was walking from the area near the Mississippi River boat ramp West and was intercepted by Security personnel in the plant parking lot. He was then taken into custody by Prairie Island Police.
"The event was determined to be media sensitive and courtesy notifications are being made to state, local and tribal agencies. No news release is planned and there was no effect on plant operations.
"It was later determined the individual had fled from the Treasure Island Casino. Local police had been searching for him at the time plant Security stopped him." The individual had been detained at the casino due to suspected underage drinking and was being held for local law enforcement when he fled on foot.
The licensee notified the NRC Resident inspector. | |