| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/05/2009 - 02/06/2009 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 44823 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: CHARLOTTE-MECKLENBURG HOSPITAL AUTHORITY
Region: 1
City: CHARLOTTE State: NC
County:
License #: 060-0014-3
Agreement: Y
Docket:
NRC Notified By: SHARN JEFFRIES
HQ OPS Officer: HOWIE CROUCH | Notification Date: 02/02/2009
Notification Time: 12:25 [ET]
Event Date: 01/27/2009
Event Time: [EST]
Last Update Date: 02/02/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE SCHMIDT (R1)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - MEDICAL EVENT
The following information was obtained from the State of North Carolina via facsimile:
"On January 27, 2009, a Therasphere (Y-90 microsphere) procedure was scheduled for a patient in Room 4, Special Procedures. The treatment was planned to deliver 110 Gy to the left lobe of the liver. The delivery apparatus was assembled according to manufacturer instructions, without incident. The treatment was initiated. During the first infusion, the Authorized User noticed fluid leakage at the outlet flow line and needle insertion at the source vial. The RSO was contacted. An attempt was made to continue the infusion. The liquid continued to leak at the outlet flow line and needle junction. No additional radioactivity was delivered to the patient. The procedure was terminated.
"Post procedure survey readings of the source vial indicated that approximately 65% of the intended radioactivity was delivered to the patient. This resulted in a dose of 70 Gy delivered to the left lobe of the liver.
"The Authorized User indicated that no adverse clinical symptoms are expected. This was the second treatment for this patient.
"The manufacturer (MDS Nordion) was notified of the device problem on 01/28/09.
"All liquid and contamination was contained by Radiation Safety personnel."
A Medical Event may indicate potential problems in a medical facilities use of radioactive materials. It does not necessarily result in harm to the patient. |
| Power Reactor | Event Number: 44830 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: ERIC STRONG
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/05/2009
Notification Time: 14:34 [ET]
Event Date: 02/05/2009
Event Time: 14:13 [EST]
Last Update Date: 02/06/2009 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
JOHN WHITE (R1)
MARC DAPAS (RDAR)
MJ ROSS-LEE (EO)
JEFFERY GRANT (IRD)
JIM WIGGINS (ET)
MIKE INZER (DHS)
DENNIS VIA (FEMA)
|
| 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 UNUSUAL EVENT DECLARED DUE TO LOSS OF CONTROL ROOM ANNUNCIATORS
At 1413 EST Ginna Station declared an Unusual Event due to the Loss of Main Control Board Annunciators E, F, G and H. There was ongoing maintenance at the time, however, no specific cause for the loss has been identified. The licensee confirmed that they have redundant indication available to monitor plant parameters. The unit is currently stable and operating at 100% power.
The licensee informed state and local agencies and the NRC Resident Inspector.
* * * UPDATE FROM DOUG GOMEZ TO DONALD NORWOOD AT 0458, 2/6/09 * * *
Based on testing, troubleshooting, and restoration of power to the Main Control Board Annuciators, Ginna Station exited the Unusual Event at 0435 hours, 2/6/09.
The licensee notified the NRC Resident Inspector.
Notified RDO (Gray), NRR EO (Hiland), IRD MOC (Grant), DHS (Kettles), and FEMA(LaForty). |
| Power Reactor | Event Number: 44831 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: BOB FOWLER
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/05/2009
Notification Time: 19:20 [ET]
Event Date: 02/05/2009
Event Time: 15:24 [CST]
Last Update Date: 02/05/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
JEFF CLARK (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 61 | Power Operation | 0 | Hot Standby | Event Text UNIT 1 MANUALLY TRIPPED DUE TO CONTROL ROD DRIVE MOTOR HIGH TEMPERATURES
"Arkansas Nuclear One Unit 1 was manually tripped from 61% power due to Control Rod Drive motor (CRD) high temperatures due to a loss of cooling water flow from Non-Nuclear Intermediate Cooling Water (ICW). No significant equipment issues were observed. No primary safeties lifted. Secondary safeties lifted for ~18 seconds. Emergency feedwater did not actuate and was not needed. Post trip response was normal and the plant is stable in mode 3. Post transient review is in progress."
All control rods fully inserted into the core. There is no known primary-secondary steam generator tube leakage. The offsite electrical grid is stable. The loss of ICW flow is attributed to the mechanical failure of service air compressor C-3A. Decay heat removal is via main feedwater to the steam generator and steam to the main condenser.
The licensee informed state, other government agencies and the NRC Resident Inspector and will inform local government agencies. No press release is planned. |
| Power Reactor | Event Number: 44832 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: GARY AHRENS
HQ OPS Officer: VINCE KLCO | Notification Date: 02/05/2009
Notification Time: 21:36 [ET]
Event Date: 02/05/2009
Event Time: 15:39 [CST]
Last Update Date: 02/05/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
MARK RING (R3)
|
| 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 STEAM EXCLUSION DOOR GAP
"At 1539 on 02/05/2009 it was identified that a Steam Exclusion door seal was not flush with the door. The door seal gap was noted during a Fire Zone Inspection. It was determined that the door exceeded the allowed limit. This could have allowed steam from the Turbine Drive Auxiliary Feed Pump room into the emergency safeguards bus area. This could have resulted in both trains of ESF Equipment failing to perform their required functions. Upon discovery Specification 3.0.c was entered at 1539. Work was completed on the door to return it to functional status at 1601, and Technical Specification 3.0.c was exited at that time.
"The NRC Resident inspector has been notified." |
| Power Reactor | Event Number: 44833 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: SHANNON SHEA
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/05/2009
Notification Time: 22:25 [ET]
Event Date: 02/05/2009
Event Time: 18:28 [CST]
Last Update Date: 02/05/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JEFF CLARK (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 TO LOCAL FIRE DEPARTMENTS FOR ASSISTANCE
"At 1828 CST, a fire alarm in the Administration Building was reported to the Fort Calhoun Station Control Room. The Administration Building is located outside of the Protected Area on Owner Controlled Property. An Equipment Operator was dispatched to investigate the cause of the alarm. The Control Room entered AOP-06 Fire Emergency at 1830 CST.
"At 1832 CST, a report was received from a building occupant that smoke was emanating from a Mechanical Equipment Room located on the first floor of the building. At that time, personnel in the building attempted to extinguish the fire using a portable fire extinguisher but were unsuccessful. Local Fire Departments in the City of Blair and Fort Calhoun were dispatched.
"At 1840 CST, the Operator arrived at the scene, found light smoke coming from the Mechanical Equipment Room and proceeded to de-energize the ventilation equipment. At 1844 CST, the fire was then extinguished using portable fire extinguishers. It was at that time that Blair and Fort Calhoun Fire Companies arrived on site to assist.
"At 1911 CST, AOP-06 was exited. Preliminary investigation shows that filter media had become dislodged and contacted duct heaters in the ventilation system. The fire ignited secondary material in the area. The Protected Area of Fort Calhoun Station was not affected at any time during this incident.
"This event may cause heightened public or government concern related to the health and safety of on-site personnel. Therefore, this report is being made in reference to 10 CFR 50.72(b)(2)(xi)."
The licensee informed the NRC Resident Inspector and plans to issue a press release. | |