Event Notification Report for February 11, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/10/2000 - 02/11/2000
EVENT NUMBERS
36684366803668136682
Power Reactor
Event Number: 36684
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: STEVE WHEELER
HQ OPS Officer: DICK JOLLIFFE
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: STEVE WHEELER
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 02/11/2000
Notification Time: 20:13 [ET]
Event Date: 02/11/2000
Event Time: 17:07 [CST]
Last Update Date: 02/11/2000
Notification Time: 20:13 [ET]
Event Date: 02/11/2000
Event Time: 17:07 [CST]
Last Update Date: 02/11/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
LINDA HOWELL (R4)
LINDA HOWELL (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 |
- Nebraska Game and Parks Department notified of a dead American Bald Eagle found onsite -
At 1707 CST on 02/11/00, a licensee employee found an American Bald Eagle under a 345 kV line on licensee property. The licensee notified the Nebraska Game and Parks Department. A Nebraska Game Warden reported to the site and took possession of the eagle. The warden stated that the eagle had been dead for some time. The warden plans to notify the Fish and Wildlife Service of this incident and to send the bird to them.
The licensee notified the NRC Resident Inspector.
At 1707 CST on 02/11/00, a licensee employee found an American Bald Eagle under a 345 kV line on licensee property. The licensee notified the Nebraska Game and Parks Department. A Nebraska Game Warden reported to the site and took possession of the eagle. The warden stated that the eagle had been dead for some time. The warden plans to notify the Fish and Wildlife Service of this incident and to send the bird to them.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 36680
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: OSELAND
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: OSELAND
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/11/2000
Notification Time: 07:13 [ET]
Event Date: 02/11/2000
Event Time: 02:58 [CST]
Last Update Date: 02/11/2000
Notification Time: 07:13 [ET]
Event Date: 02/11/2000
Event Time: 02:58 [CST]
Last Update Date: 02/11/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(2)(iii)(D) - ACCIDENT MITIGATION
Person (Organization):
MICHAEL PARKER (R3)
MICHAEL PARKER (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 4 | Startup | 4 | Startup |
HPCI DECLARED INOPERABLE, PLACING THE PLANT IN A LCO ACTION STATEMENT.
On 2/11/2000 at 0258 hours, HPCI low pressure operability testing was in progress following a scheduled refueling outage. At that time, the HPCI turbine failed to roll when the motor speed changer was taken to its high speed stop. There was no change in steam flow as indicated by the main turbine bypass valve position. The operator in attendance visually verified HPCI was still on the turning gear. The surveillance was terminated and the system restored to standby lineup. At 0341 hours, reactor pressure was reduced below 150 psig to place the reactor in a condition where HPCI was not required to be operable, and they exited the LCO at that time.
The cause of this failure is under investigation.
The NRC Resident Inspector was notified.
On 2/11/2000 at 0258 hours, HPCI low pressure operability testing was in progress following a scheduled refueling outage. At that time, the HPCI turbine failed to roll when the motor speed changer was taken to its high speed stop. There was no change in steam flow as indicated by the main turbine bypass valve position. The operator in attendance visually verified HPCI was still on the turning gear. The surveillance was terminated and the system restored to standby lineup. At 0341 hours, reactor pressure was reduced below 150 psig to place the reactor in a condition where HPCI was not required to be operable, and they exited the LCO at that time.
The cause of this failure is under investigation.
The NRC Resident Inspector was notified.
Hospital
Event Number: 36681
Rep Org: JASPER COUNTY HOSPITAL
Licensee: JASPER COUNTY HOSPITAL
Region: 3
City: RENSSELAER State: IN
County:
License #: 13-26527-01
Agreement: N
Docket:
NRC Notified By: ROTH
HQ OPS Officer: CHAUNCEY GOULD
Licensee: JASPER COUNTY HOSPITAL
Region: 3
City: RENSSELAER State: IN
County:
License #: 13-26527-01
Agreement: N
Docket:
NRC Notified By: ROTH
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/11/2000
Notification Time: 10:45 [ET]
Event Date: 02/11/2000
Event Time: 08:45 [CST]
Last Update Date: 02/11/2000
Notification Time: 10:45 [ET]
Event Date: 02/11/2000
Event Time: 08:45 [CST]
Last Update Date: 02/11/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JAMES CREED (R3)
BRIAN SMITH (NMSS)
JAMES CREED (R3)
BRIAN SMITH (NMSS)
JASPER COUNTY HOSPITAL RECEIVED A SURFACE CONTAMINATED BOX WHICH CONTAINED NUCLEAR MEDICINE.
A METAL AMMO BOX USED TO TRANSPORT NUCLEAR MEDICINE CONTAINED IN INDIVIDUAL PIGS WAS FOUND TO HAVE SURFACE TECHNICIUM CONTAMINATION ON THE LOCKING CLASP MEASURING 604 DPM/CM2 (LIMIT IS EQUAL TO OR LESS THAN 220 DPM/CM2). THERE WAS NO DAMAGE TO THE PIG CONTAINERS INSIDE THE AMMO BOX AND NO CONTAMINATION WAS MEASURED INSIDE THE BOX. THE SOURCE OF THE CONTAMINATION IS UNKNOWN, BUT IT COULD HAVE OCCURRED AT THE PHARMACEUTICAL COMPANY, THE TRANSPORTER OR IN THE HOSPITAL LABORATORY. HOSPITAL PERSONNEL HAVE ISOLATED THE AMMO BOX AND WILL ALLOW THE TECHNICIUM CONTAMINATION TO DECAY OFF.
(CALL THE NRC OPERATIONS OFFICER FOR A LICENSEE CONTACT TELEPHONE NUMBER.)
A METAL AMMO BOX USED TO TRANSPORT NUCLEAR MEDICINE CONTAINED IN INDIVIDUAL PIGS WAS FOUND TO HAVE SURFACE TECHNICIUM CONTAMINATION ON THE LOCKING CLASP MEASURING 604 DPM/CM2 (LIMIT IS EQUAL TO OR LESS THAN 220 DPM/CM2). THERE WAS NO DAMAGE TO THE PIG CONTAINERS INSIDE THE AMMO BOX AND NO CONTAMINATION WAS MEASURED INSIDE THE BOX. THE SOURCE OF THE CONTAMINATION IS UNKNOWN, BUT IT COULD HAVE OCCURRED AT THE PHARMACEUTICAL COMPANY, THE TRANSPORTER OR IN THE HOSPITAL LABORATORY. HOSPITAL PERSONNEL HAVE ISOLATED THE AMMO BOX AND WILL ALLOW THE TECHNICIUM CONTAMINATION TO DECAY OFF.
(CALL THE NRC OPERATIONS OFFICER FOR A LICENSEE CONTACT TELEPHONE NUMBER.)
Power Reactor
Event Number: 36682
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MIKE BAIN
HQ OPS Officer: DICK JOLLIFFE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MIKE BAIN
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 02/11/2000
Notification Time: 14:32 [ET]
Event Date: 02/11/2000
Event Time: 13:46 [EST]
Last Update Date: 02/11/2000
Notification Time: 14:32 [ET]
Event Date: 02/11/2000
Event Time: 13:46 [EST]
Last Update Date: 02/11/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
Person (Organization):
HAROLD GRAY (R1)
HAROLD GRAY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 96 | Power Operation | 0 | Hot Standby |
- MANUAL REACTOR TRIP FROM 96% POWER AFTER 2 CONTROL RODS DROPPED INTO THE CORE -
During the performance of a tech spec surveillance test of control rod motion with Unit 2 at 100% power, one control rod dropped into the core for unknown reasons. Control room operators reduced power. With Unit 2 at 96% power, a second control rod dropped into the core for unknown reasons. Control room operators manually tripped Unit 2 from 96% power. All control rods inserted completely into the core. The auxiliary feedwater system actuated, as expected. Control room operators manually secured the auxiliary feedwater system. Steam generator water levels are being maintained in their normal range by the main feedwater system. Steam is being dumped to the main condenser. No safety or relief valves lifted. Unit 2 is stable in Mode 3 (Hot Standby). The licensee is investigating the cause of the control rods dropping into the core.
The licensee notified state and local officials and the NRC Resident Inspector and plans to issue a press release.
During the performance of a tech spec surveillance test of control rod motion with Unit 2 at 100% power, one control rod dropped into the core for unknown reasons. Control room operators reduced power. With Unit 2 at 96% power, a second control rod dropped into the core for unknown reasons. Control room operators manually tripped Unit 2 from 96% power. All control rods inserted completely into the core. The auxiliary feedwater system actuated, as expected. Control room operators manually secured the auxiliary feedwater system. Steam generator water levels are being maintained in their normal range by the main feedwater system. Steam is being dumped to the main condenser. No safety or relief valves lifted. Unit 2 is stable in Mode 3 (Hot Standby). The licensee is investigating the cause of the control rods dropping into the core.
The licensee notified state and local officials and the NRC Resident Inspector and plans to issue a press release.