| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/12/2007 - 03/13/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43219 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: MC SQUARED, INC
Region: 1
City: TAMPA State: FL
County:
License #: 3424-1
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: PETE SNYDER | Notification Date: 03/07/2007
Notification Time: 15:18 [ET]
Event Date: 03/07/2007
Event Time: [EST]
Last Update Date: 03/07/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHN CARUSO (R1)
GREG MORELL (FSME)
ILTAB (email) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE
The State provided the following information via facsimile:
The gauge was used at a jobsite at 35050 Halls Road, Clewiston, Florida on a Seminole Indian Reservation. After being used on the jobsite, the gauge was placed in a storage trailer. The gauge is a Model 3411B Troxler soil moisture density gauge, serial number 13563. The gauge contained a 8 millicurie Cs-137 source and a 40 millicurie Am-241:Be source.
"Device was used Friday 03/02/07 and placed in a storage trailer. It was noticed missing when the trailer was opened 03/07/07 [in the morning]. The trailer had not been broken into. The Seminole Reservation authorities are investigating. Licensee will submit a written report. [State of] Florida will investigate within the limits of its authority.
FL Incident Number: FL07-039
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: 43227 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAVID G. LANTZ
HQ OPS Officer: JOHN MacKINNON | Notification Date: 03/09/2007
Notification Time: 15:02 [ET]
Event Date: 03/09/2007
Event Time: 10:43 [CST]
Last Update Date: 03/12/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
VINCENT GADDY (R4)
JIM DYER (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP AT REDUCED POWER DUE TO INADEQUATE FEEDWATER CONTROL
"At approximately 0803 Central Standard Time (CST) on 3/9/2007, Callaway Plant received indications of a condenser tube leak. At approximately 0826 CST, a power reduction from 100 percent to less than 5 percent was initiated in accordance with the Secondary Water Chemistry Program. At 1043 CST, with the reactor at approximately 30 percent power, a manual reactor trip was initiated due to inadequate feedwater control to the C steam generator. There was indication of feedwater flow to and increasing level in the C steam generator with both the main feedwater reg valve and its bypass valve closed. Cause of the inadequate feedwater control is under investigation.
"All safety systems functioned as designed with the exception of the digital rod position indication for control rod K10 which failed during the trip due to an existing problem. Control rod K10 is believed to be fully inserted, but is being treated as indeterminate at this time. Main feedwater isolation and motor-driven auxiliary feedwater actuations occurred as expected. Both trains of the emergency diesel generators and the offsite power supplies are available.
" Callaway plant is currently stable in Mode 3 at normal reactor coolant system parameters.
"This notification is being made in accordance with 10CFR50.72(b)(2)(iv)(B) for manual reactor trip (RPS actuation), 10CFR50.72(b)(2)(xi) for offsite notification and 10CFR50.72(b)(3)(iv)(A) Specified System Actuation.
"The licensee informed the resident inspector of the event and will be making State notifications. A press release is expected."
* * * UPDATE ON 03/12/07 AT 2116 EDT FROM S. GANZ TO MACKINNON * * *
"Repairs were made to the Digital Rod Position Indication (DRPI) for control rod K10. The cause was determined to be a bent pin on a cable connector. When DRPI was restored, control rod K10 was verified to be fully inserted. Post maintenance testing was completed satisfactorily.
"The cause of the inadequate feedwater control for the C steam generator was a failure of the positioner for the C main feedwater reg valve. The positioner was replaced and tested satisfactory.
"The plant is currently in Mode 2 (Startup)
"The resident inspector was informed of the update."
R4DO (Mike Shannon) notified. | |