| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/07/2006 - 04/10/2006 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 42470 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GLOBAL GEO ENGINEERING, INC.
Region: 4
City: TUSTIN State: CA
County: ORANGE
License #: 6899
Agreement: Y
Docket:
NRC Notified By: DONELLE KRAJEWSKI
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/04/2006
Notification Time: 17:08 [ET]
Event Date: 03/17/2006
Event Time: [PDT]
Last Update Date: 04/05/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LINDA SMITH (R4)
WILLIAM RULAND (NMSS)
MEXICO (via fax) ()
ILTAB (via email) ()
| Event Text AGREEMENT STATE REPORT INVOLVING THE POSSIBLE LOSS OF A TROXLER MOISTURE DENSITY GAUGE
At 1430 PDT on 4/4/06, the CA Rad Control Program Office was notified by Global Geo Engineering, Inc. that one of their Troxler Moisture Density Gauges, a Model 3430 - S/N 32401 containing 8 mCi Cs-137 and 40 mCi Am-241/Be, was missing and could not be accounted for. The last known log out occurred on 3/17/06 when the gauge had been used by a temporary worker at a jobsite. The licensee, unable to locate the temporary worker for a work assignment, reported the gauge as missing to both the State of CA and their local police department. CA will conduct an investigation into the circumstances involving this incident.
* * * UPDATE ON 04/05/06 AT 1548 EDT FROM DONELLE KRAJEWSKI, STATE OF CALIFORNIA, TO MACKINNON * * *
Gauge was returned to licensee today, 04/05/06. The temporary worker had the gauge in his possession.
R4DO (Linda Smith) and NMSS (Greg Morell). E-mailed to Mexico and ILTAB.
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: 42482 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MARK ADAMS
HQ OPS Officer: JOE O'HARA | Notification Date: 04/07/2006
Notification Time: 17:07 [ET]
Event Date: 04/07/2006
Event Time: 17:07 [EDT]
Last Update Date: 04/07/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ANNE MARIE STONE (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text LOSS OF OFFSITE COMMUNICATION CAPABILITY - PLANNED MAINTENANCE ON SPDS AND ERDS SYSTEMS
"The Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service for planned Preventive Maintenance on the Uninterruptible Power Supply (UPS) system. SPDS and ERDS are scheduled to be restored on 4/9/2006. During this period any out of service indication on the SPDS can be obtained from control board indications. The Emergency Notification System will remain operable. These conditions are reportable in accordance with 10CFR50.72(b)(3)(xiii). The NRC Resident Inspector has been notified. The Reactor is currently defueled while in a refuel outage. Reactor Coolant Temperature is 87 degrees and Div 2 RHR is in shutdown cooling."
The licensee maintains secondary indication capability via control panel indicators. |
| Power Reactor | Event Number: 42483 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JIM CROSSMAN
HQ OPS Officer: PETE SNYDER | Notification Date: 04/08/2006
Notification Time: 01:11 [ET]
Event Date: 04/07/2006
Event Time: 22:31 [EDT]
Last Update Date: 04/08/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
BRIAN BONSER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | N | 0 | Hot Standby | 0 | Hot Standby | Event Text GROUP STEP COUNTER FAILURE DURING REACTOR STARTUP
"While in Mode 3 at 547 degrees and 2235 psig in the Reactor Coolant System, during Rod Control System rod drop testing, the group 2, 'A' shutdown bank step counter failed. The step counter is required to be operable in Modes 3, 4 and 5 per [Technical Requirements Manual requirement] 3.1.3 or the reactor trip breakers must be opened within 15 minutes. The step counter failed at 2217 and at 2231 the reactor trip breakers were opened. This was considered a valid actuation of the [Reactor Protection System] due to the [Technical Requirements Manual] requirements and due to the equipment malfunction."
Shutdown margin is adequate and all emergency buses are on offsite power. Emergency Diesel Generators are available.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42484 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: TIM RITI
HQ OPS Officer: PETE SNYDER | Notification Date: 04/09/2006
Notification Time: 02:37 [ET]
Event Date: 04/08/2006
Event Time: 23:42 [EDT]
Last Update Date: 04/09/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
PAT FINNEY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 1 | Startup | 0 | Hot Standby | Event Text CONTROL ELEMENT ASSEMBLY STUCK DURING PHYSICS TESTING
"During the performance of PSTP-2, Low Power Physics Testing on U-1 for Regulating Control Element Assemblies Group 2, CEA #21 was declared untrippable, Technical Specification 3.1.4.F, CEA Alignment, was entered and Plant shutdown to Mode 3 was commenced at 2342 on 4/8/06."
The reactor is shutdown in Mode 3. The licensee borated to maintain adequate shutdown margin. The reactor trip breakers were opened but CEA #21 remains not fully inserted into the core. The licensee is currently troubleshooting to determine the cause of the stuck CEA. Offsite power is stable and powers the safety buses. Emergency Diesel Generators are available. The licensee is currently at normal operating pressure and temperature with decay heat being removed by the steam generators steaming to the condenser.
The licensee notified the NRC Resident Inspector. | |