Event Notification Report for February 07, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/06/2000 - 02/07/2000
EVENT NUMBERS
36666366673666836669
Power Reactor
Event Number: 36666
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KEVIN PEDERSON
HQ OPS Officer: DOUG WEAVER
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KEVIN PEDERSON
HQ OPS Officer: DOUG WEAVER
Notification Date: 02/07/2000
Notification Time: 03:11 [ET]
Event Date: 02/07/2000
Event Time: 00:55 [CST]
Last Update Date: 02/07/2000
Notification Time: 03:11 [ET]
Event Date: 02/07/2000
Event Time: 00:55 [CST]
Last Update Date: 02/07/2000
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):
TONY VEGEL (R3)
TONY VEGEL (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
ESF ACTUATION - RECIRC SAMPLE ISOLATION VALVES
During the performance of standby liquid control refueling tests, a signal is sent to the reactor water cleanup isolation valves and the recirc sample valves. The procedure addresses the RWCU valves, but not the recirc sample valves. Since the outboard sample valve was secured (tagged) open, it unexpectedly closed upon initiation of the standby liquid control system.
The valves were returned to their pre-test positions.
The licensee will notify the NRC resident inspector.
During the performance of standby liquid control refueling tests, a signal is sent to the reactor water cleanup isolation valves and the recirc sample valves. The procedure addresses the RWCU valves, but not the recirc sample valves. Since the outboard sample valve was secured (tagged) open, it unexpectedly closed upon initiation of the standby liquid control system.
The valves were returned to their pre-test positions.
The licensee will notify the NRC resident inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 36667
Facility: DRESDEN
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: DAVE KLIMECK
HQ OPS Officer: DOUG WEAVER
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: DAVE KLIMECK
HQ OPS Officer: DOUG WEAVER
Notification Date: 02/07/2000
Notification Time: 04:28 [ET]
Event Date: 02/07/2000
Event Time: 02:40 [CST]
Last Update Date: 02/11/2000
Notification Time: 04:28 [ET]
Event Date: 02/07/2000
Event Time: 02:40 [CST]
Last Update Date: 02/11/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
TONY VEGEL (R3)
TONY VEGEL (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
Minimum security personnel staffing requirements not met. Immediate compensatory actions taken upon discovery. The licensee will notify the NRC resident inspector. Additional details of this event may be obtained by contacting the NRC operations officer.
* * * UPDATE AT 2057 ON 02/11/00 BY CHRIS KENT TO JOLLIFFE * * *
The licensee desires to retract this event since the commitments in the approved Plant Physical Security Plan had been complied with during this event. The licensee plans to notify the NRC Resident Inspector. The NRC Operations Officer notified the R3DO Mike Parker. Additional details of this event retraction may be obtained by contacting the NRC Operations Officer.
* * * UPDATE AT 2057 ON 02/11/00 BY CHRIS KENT TO JOLLIFFE * * *
The licensee desires to retract this event since the commitments in the approved Plant Physical Security Plan had been complied with during this event. The licensee plans to notify the NRC Resident Inspector. The NRC Operations Officer notified the R3DO Mike Parker. Additional details of this event retraction may be obtained by contacting the NRC Operations Officer.
Hospital
Event Number: 36668
Rep Org: ST. ANTHONY MEDICAL CENTER
Licensee: ST. ANTHONY MEDICAL CENTER
Region: 3
City: CROWN POINT State: IN
County:
License #: 13-15933-01
Agreement: N
Docket:
NRC Notified By: RAM BASAVATIA
HQ OPS Officer: BOB STRANSKY
Licensee: ST. ANTHONY MEDICAL CENTER
Region: 3
City: CROWN POINT State: IN
County:
License #: 13-15933-01
Agreement: N
Docket:
NRC Notified By: RAM BASAVATIA
HQ OPS Officer: BOB STRANSKY
Notification Date: 02/07/2000
Notification Time: 17:14 [ET]
Event Date: 02/07/2000
Event Time: 09:00 [CST]
Last Update Date: 02/07/2000
Notification Time: 17:14 [ET]
Event Date: 02/07/2000
Event Time: 09:00 [CST]
Last Update Date: 02/07/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
35.33 - MED MISADMINISTRATION
10 CFR Section:
35.33 - MED MISADMINISTRATION
Person (Organization):
MICHAEL PARKER (R3)
JOE HOLONICH (NMSS)
MICHAEL PARKER (R3)
JOE HOLONICH (NMSS)
MEDICAL MISADMINISTRATION
A patient, who was prescribed a dose of 100 µCi I-131 for a thyroid scan, was administered a dose of 500 µCi I-131. The patient was released before the error was discovered. The patient has since been contacted and is returning to the hospital to be administered KI (potassium iodide) to limit the uptake of radioiodine in the thyroid. The licensee radiation safety officer did not provide an estimate of the thyroid dose, but stated that whole body dose would be approximately 31 rads without administration of KI.
The patient's attending physician will be informed of this misadministration. The licensee has already contacted NRC Region III (T. Go).
A patient, who was prescribed a dose of 100 µCi I-131 for a thyroid scan, was administered a dose of 500 µCi I-131. The patient was released before the error was discovered. The patient has since been contacted and is returning to the hospital to be administered KI (potassium iodide) to limit the uptake of radioiodine in the thyroid. The licensee radiation safety officer did not provide an estimate of the thyroid dose, but stated that whole body dose would be approximately 31 rads without administration of KI.
The patient's attending physician will be informed of this misadministration. The licensee has already contacted NRC Region III (T. Go).
Power Reactor
Event Number: 36669
Facility: FARLEY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BILL ARNES
HQ OPS Officer: BOB STRANSKY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BILL ARNES
HQ OPS Officer: BOB STRANSKY
Notification Date: 02/07/2000
Notification Time: 18:56 [ET]
Event Date: 02/07/2000
Event Time: 14:30 [CST]
Last Update Date: 02/07/2000
Notification Time: 18:56 [ET]
Event Date: 02/07/2000
Event Time: 14:30 [CST]
Last Update Date: 02/07/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(2)(iii)(A) - POT UNABLE TO SAFE SD
Person (Organization):
KERRY LANDIS (R2)
KERRY LANDIS (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
POTENTIAL ENTRY INTO TECHNICAL SPECIFICATION 3.0.5
While the 'A' emergency diesel generator (EDG) was out of service for maintenance, the licensee determined that the 'B' service water booster pump had previously been removed from service due to its breaker repeatedly tripping on overcurrent. The 'B' service water booster pump may be attendant equipment for the 'B' service water train. The licensee is currently performing an attendant equipment evaluation of the 'B' service water booster pump. This condition may have required that the unit enter Technical Specification 3.0.5.
The NRC resident inspector has been informed of this event by the licensee.
While the 'A' emergency diesel generator (EDG) was out of service for maintenance, the licensee determined that the 'B' service water booster pump had previously been removed from service due to its breaker repeatedly tripping on overcurrent. The 'B' service water booster pump may be attendant equipment for the 'B' service water train. The licensee is currently performing an attendant equipment evaluation of the 'B' service water booster pump. This condition may have required that the unit enter Technical Specification 3.0.5.
The NRC resident inspector has been informed of this event by the licensee.