| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/18/2003 - 08/19/2003 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40062 | Rep Org: GEORGIA RADIOACTIVE MATERIAL PGM
Licensee: KEWELL, LLC
Region: 2
City: Atlanta State: GA
County:
License #: GA 1488-1
Agreement: Y
Docket:
NRC Notified By: THOMAS E. HILL
HQ OPS Officer: JOHN MacKINNON | Notification Date: 08/14/2003
Notification Time: 14:32 [EST]
Event Date: 08/12/2003
Event Time: 00:00 [EDT]
Last Update Date: 08/14/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID AYRES (R2)
LINDA PSYK (NMSS)
MATTHEW HAHN (TAS)
| Event Text STOLEN NITON ANALYZER
"Overnight, August 12, 2003 unknown persons entered the licensees facility and stole various office equipment including copiers, computers and a Niton analyzer containing radioactive material."
The Niton Analyzer is a model Xli or XLp series device which contains 30 millicuries of Am-241.
The Licensee, Kewell, LLC, reported the theft to the local law enforcement.
Media attention: None
Georgia Event Report No: GA-2003-241 |
| Power Reactor | Event Number: 40086 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: R. HUBBARD
HQ OPS Officer: JOHN MacKINNON | Notification Date: 08/18/2003
Notification Time: 18:36 [EST]
Event Date: 08/18/2003
Event Time: 15:54 [CDT]
Last Update Date: 08/18/2003 | 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):
BLAIR SPITZBERG (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE LOW LOW "B" STEAM GENERATOR WATER LEVEL
"At 1554 CDT on 08/18/2003 all four Steam Generators alarmed with Steam Flow/Feed Flow Mismatch followed by indication that there was no feedwater flow to the "B" Steam Generator. The reactor tripped approximately 20 seconds later on Steam Generator Low-Low Level, 23.5% Narrow Range, as required. A review of the plant computer information shows that event-initiating cause may be the unexplained closure of the "B" Feedwater Isolation Valve.
"All plant safety related systems operated as required. The Steam Dumps, which function to remove excess heat as the secondary systems shutdown, exhibited control problems when they were shifted from temperature control mode to steam pressure mode, as required by the emergency operating procedures. The Steam Dumps are currently operating and controlling in manual mode. When the reactor tripped all four Steam Generator Atmospheric Relief Valves opened, a normal response for a trip from full power. The "A" Steam Generator Atmospheric Relief Valve was slow to close in automatic. The valve was closed in manual and returned to automatic and is controlling properly.
"The plant is currently stable in Mode 3 at NOP and NOT while plant personnel investigate the causes of the trip and formulate the repair/restart plan."
All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed. The electrical grid is stable.
The NRC Resident Inspector is in the Control Room. | |