Event Notification Report for April 20, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/19/2002 - 04/20/2002
EVENT NUMBERS
38871388673886838869
Other Nuclear Material
Event Number: 38871
Rep Org: SEIMENS MEDICAL SOLUTIONS USA, INC
Licensee: SEIMENS MEDICAL SOLUTIONS USA, INC
Region: 1
City: ISELIN State: NJ
County: MIDDLESEX
License #: 29-32349-01
Agreement: N
Docket:
NRC Notified By: ROBERT F. WILEY
HQ OPS Officer: MIKE NORRIS
Licensee: SEIMENS MEDICAL SOLUTIONS USA, INC
Region: 1
City: ISELIN State: NJ
County: MIDDLESEX
License #: 29-32349-01
Agreement: N
Docket:
NRC Notified By: ROBERT F. WILEY
HQ OPS Officer: MIKE NORRIS
Notification Date: 04/22/2002
Notification Time: 11:03 [ET]
Event Date: 04/20/2002
Event Time: 02:00 [EDT]
Last Update Date: 04/22/2002
Notification Time: 11:03 [ET]
Event Date: 04/20/2002
Event Time: 02:00 [EDT]
Last Update Date: 04/22/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
CLIFFORD ANDERSON (R1)
MARK SHAFFER (R4)
CHARLIE COX (NMSS)
CLIFFORD ANDERSON (R1)
MARK SHAFFER (R4)
CHARLIE COX (NMSS)
LOSS/STOLEN NUCLEAR LICENSED MATERIAL >1000X
Two calibration sources were stolen from a rental car in Oahu, Hawaii on 4/19/02. The sources, 2 millicuries of Am-241 and 2 millicuries of Co-57, were in tungsten shielded containers with screwed on lead caps. The sources were in a locked tool box, which was in the locked trunk. The thief pulled out the driver door lock, pried open the glove box and opened the trunk. The source numbers and dates were as follows: Am-241, #0191LX, 8-4-89 and Co-57, #5971 LC, 10-13-00. The Kaneohe Police Department was notified, report # 02-145893. Ads will be placed in the local newspapers. Licensee indicated that there were no measurable dose rates on the outside of the shielded container.
Two calibration sources were stolen from a rental car in Oahu, Hawaii on 4/19/02. The sources, 2 millicuries of Am-241 and 2 millicuries of Co-57, were in tungsten shielded containers with screwed on lead caps. The sources were in a locked tool box, which was in the locked trunk. The thief pulled out the driver door lock, pried open the glove box and opened the trunk. The source numbers and dates were as follows: Am-241, #0191LX, 8-4-89 and Co-57, #5971 LC, 10-13-00. The Kaneohe Police Department was notified, report # 02-145893. Ads will be placed in the local newspapers. Licensee indicated that there were no measurable dose rates on the outside of the shielded container.
Power Reactor
Event Number: 38867
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROB DORMAN
HQ OPS Officer: MIKE NORRIS
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROB DORMAN
HQ OPS Officer: MIKE NORRIS
Notification Date: 04/20/2002
Notification Time: 06:52 [ET]
Event Date: 04/20/2002
Event Time: 05:12 [EDT]
Last Update Date: 04/20/2002
Notification Time: 06:52 [ET]
Event Date: 04/20/2002
Event Time: 05:12 [EDT]
Last Update Date: 04/20/2002
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BRIAN BONSER (R2)
BRIAN BONSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 30 | Power Operation | 0 | Hot Standby |
MANUAL RPS ACTIVATION DUE TO LOSS OF FEEDWATER
"Unit 1 was at approximately 30% power and preparing to synchronize the Main Generator to the grid. The A Main Feedwater Pump mini flow valve was isolated per plant procedures. The isolation of the mini flow valve caused the Steam Generator levels to rise. A Hi-Hi Steam Generator level occurred in #4 Steam Generator. This resulted in a trip of the Main Feedwater Pump, a Feedwater Isolation Signal, and the trip of the Main Turbine. The Reactor was tripped due to having no Main Feedwater available to the Steam Generators in anticipation of a low-low Steam Generator level trip at 38% level. Both Motor Driven Auxiliary Feedwater pumps did start as a result of the only running Main Feedwater pump being tripped." All rods fully inserted into the core.
The NRC Resident Inspector has been notified.
"Unit 1 was at approximately 30% power and preparing to synchronize the Main Generator to the grid. The A Main Feedwater Pump mini flow valve was isolated per plant procedures. The isolation of the mini flow valve caused the Steam Generator levels to rise. A Hi-Hi Steam Generator level occurred in #4 Steam Generator. This resulted in a trip of the Main Feedwater Pump, a Feedwater Isolation Signal, and the trip of the Main Turbine. The Reactor was tripped due to having no Main Feedwater available to the Steam Generators in anticipation of a low-low Steam Generator level trip at 38% level. Both Motor Driven Auxiliary Feedwater pumps did start as a result of the only running Main Feedwater pump being tripped." All rods fully inserted into the core.
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 38868
Facility: YANKEE ROWE
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DON MILLER
HQ OPS Officer: MIKE NORRIS
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DON MILLER
HQ OPS Officer: MIKE NORRIS
Notification Date: 04/20/2002
Notification Time: 07:49 [ET]
Event Date: 04/20/2002
Event Time: 06:51 [EDT]
Last Update Date: 04/20/2002
Notification Time: 07:49 [ET]
Event Date: 04/20/2002
Event Time: 06:51 [EDT]
Last Update Date: 04/20/2002
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
JOHN ROGGE (R1)
DICK WESSMAN (IRO)
WAYNE HODGES (NMSS)
S. BAYWA (NRR)
R. ZAPATA (FEMA)
JOHN ROGGE (R1)
DICK WESSMAN (IRO)
WAYNE HODGES (NMSS)
S. BAYWA (NRR)
R. ZAPATA (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Decommissioned | 0 | Decommissioned |
USUAL EVENT DECLARED DUE TO SEISMIC ANOMALY
Licensee felt tremors in the control room lasting more than 5 seconds and declared an Unusual Event at 0700 and immediately downgraded at 0701. Walkdowns were performed and no damage was noted. Licensee does not have any has seismic monitors. Offsite notifications have been made to the states of MA and VT.
The NRC Resident Inspector will be notified.
Licensee felt tremors in the control room lasting more than 5 seconds and declared an Unusual Event at 0700 and immediately downgraded at 0701. Walkdowns were performed and no damage was noted. Licensee does not have any has seismic monitors. Offsite notifications have been made to the states of MA and VT.
The NRC Resident Inspector will be notified.
Power Reactor
Event Number: 38869
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JEFF DEAL
HQ OPS Officer: RICH LAURA
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JEFF DEAL
HQ OPS Officer: RICH LAURA
Notification Date: 04/20/2002
Notification Time: 20:34 [ET]
Event Date: 04/20/2002
Event Time: 16:57 [EDT]
Last Update Date: 04/20/2002
Notification Time: 20:34 [ET]
Event Date: 04/20/2002
Event Time: 16:57 [EDT]
Last Update Date: 04/20/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BRIAN BONSER (R2)
BRIAN BONSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 4 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNPLANNED LOSS OF CONTROL ROOM ANNUNCIATORS LESS THAN 15 MINUTES
The licensee reported the loss of control room annunciators for 9 minutes when the electrical supply breaker tripped free. The breaker was reset and closed which restored the annunciators. However, later the same electrical breaker tripped free again resulting in the loss of control annunciators lasting for 14 minutes. The breaker was reset and closed for the second time. Maintenance troubleshooting revealed that the breaker needed to be replaced. The isolation for this corrective maintenance will result in a planned loss of control room annunciators greater than 15 minutes. Alternate plant monitoring will be utilized for the duration of the breaker change out.
The NRC Resident Inspector was notified.
The licensee reported the loss of control room annunciators for 9 minutes when the electrical supply breaker tripped free. The breaker was reset and closed which restored the annunciators. However, later the same electrical breaker tripped free again resulting in the loss of control annunciators lasting for 14 minutes. The breaker was reset and closed for the second time. Maintenance troubleshooting revealed that the breaker needed to be replaced. The isolation for this corrective maintenance will result in a planned loss of control room annunciators greater than 15 minutes. Alternate plant monitoring will be utilized for the duration of the breaker change out.
The NRC Resident Inspector was notified.