Event Notification Report for February 09, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/08/2000 - 02/09/2000
EVENT NUMBERS
36671366723667336674366753667736735
Power Reactor
Event Number: 36671
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: MACLENNAN
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: MACLENNAN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/09/2000
Notification Time: 06:45 [ET]
Event Date: 02/09/2000
Event Time: 04:21 [CST]
Last Update Date: 02/09/2000
Notification Time: 06:45 [ET]
Event Date: 02/09/2000
Event Time: 04:21 [CST]
Last Update Date: 02/09/2000
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):
MICHAEL PARKER (R3)
MICHAEL PARKER (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
INVALID ESF ACTUATION CAUSED BY BACKFILLING OF REACTOR LEVEL INSTRUMENTATION
On 02/09/2000 @ 0421 hours, Unit Two received a full reactor SCRAM and a full Group II and Group lll isolation, including a Shutdown Cooling isolation. This event occurred as a result of scheduled backfilling of reactor level instrumentation, and is being reported as an invalid ESF actuation.
At the time of the event, all control rods were fully inserted, so no rod motion occurred. All systems responded as designed. Shutdown Cooling was restored at 0432 hours with minimal temperature increase(5°F).
The NRC Resident Inspector was notified.
On 02/09/2000 @ 0421 hours, Unit Two received a full reactor SCRAM and a full Group II and Group lll isolation, including a Shutdown Cooling isolation. This event occurred as a result of scheduled backfilling of reactor level instrumentation, and is being reported as an invalid ESF actuation.
At the time of the event, all control rods were fully inserted, so no rod motion occurred. All systems responded as designed. Shutdown Cooling was restored at 0432 hours with minimal temperature increase(5°F).
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 36672
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: GOMEZ
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: GOMEZ
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/09/2000
Notification Time: 11:16 [ET]
Event Date: 02/09/2000
Event Time: 09:15 [EST]
Last Update Date: 02/09/2000
Notification Time: 11:16 [ET]
Event Date: 02/09/2000
Event Time: 09:15 [EST]
Last Update Date: 02/09/2000
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):
HAROLD GRAY (R1)
HAROLD GRAY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
THE LICENSEE NOTIFIED THE NEW YORK DEPARTMENT OF ENVIRONMENTAL CONSERVATION THEY EXCEEDED THEIR DELTA T DISCHARGE LIMIT.
On 2/9/00 @ 0915, the following information was reported as a State Pollutant Discharge Elimination System(SPDES) exception to the New York State DEC per the 24 hour notification requirement. On 2/8/00 from ~0630 - 0715 hours, the delta t for the main condenser at the site was above the limit of 28°F, with a maximum of 30.4°F, and estimated that the maximum discharge temperature would have been ~ 63°F. For the period ~ 0800 - 1100 hours, delta t was again above the 28°F limit, attaining a maximum delta t of 62°F, with an estimated discharge temperature of ~ 95°F. Observations indicate that no significant fish kill occurred.
The NRC Resident Inspector was notified.
On 2/9/00 @ 0915, the following information was reported as a State Pollutant Discharge Elimination System(SPDES) exception to the New York State DEC per the 24 hour notification requirement. On 2/8/00 from ~0630 - 0715 hours, the delta t for the main condenser at the site was above the limit of 28°F, with a maximum of 30.4°F, and estimated that the maximum discharge temperature would have been ~ 63°F. For the period ~ 0800 - 1100 hours, delta t was again above the 28°F limit, attaining a maximum delta t of 62°F, with an estimated discharge temperature of ~ 95°F. Observations indicate that no significant fish kill occurred.
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 36673
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM BEAUDIN
HQ OPS Officer: STEVE SANDIN
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM BEAUDIN
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/09/2000
Notification Time: 12:35 [ET]
Event Date: 02/09/2000
Event Time: 11:33 [CST]
Last Update Date: 02/09/2000
Notification Time: 12:35 [ET]
Event Date: 02/09/2000
Event Time: 11:33 [CST]
Last Update Date: 02/09/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
THE SERVER TO THE EMERGENCY OFFSITE FACILITY FAILED CAUSING THE SAFETY PARAMETER DISPLAY SYSTEM (SPDS) AND EMERGENCY RESPONSE DATA SYSTEM (ERDS) TO BECOME INOPERABLE
At 1645 CT on February 8, 2000 the server which transfers Plant Computer data to the two SDSs in the EOF and the ERDS modems failed. This caused the Safety Parameter Display System (SPDS) and the Emergency Response Data System (ERDS) to become unavailable in the EOF as specified in the FSAR section III.A.1.2. The server was replaced by Telecommunications and SPDS and ERDS restored to the EOF at 0834 CT on February 9, 2000. The total time that SPDS and ERDS were unavailable to the EOF is 15 hours and 49 minutes. The failure of the server occurred at the same time as a report of a fire at the Nuclear Operations Support Facility (the EOF is located inside) building.
The server was replaced by Telecommunication. The SPDS and ERDS are available at the EOF.
The NRC Resident Inspector was notified of this event by the Licensee.
At 1645 CT on February 8, 2000 the server which transfers Plant Computer data to the two SDSs in the EOF and the ERDS modems failed. This caused the Safety Parameter Display System (SPDS) and the Emergency Response Data System (ERDS) to become unavailable in the EOF as specified in the FSAR section III.A.1.2. The server was replaced by Telecommunications and SPDS and ERDS restored to the EOF at 0834 CT on February 9, 2000. The total time that SPDS and ERDS were unavailable to the EOF is 15 hours and 49 minutes. The failure of the server occurred at the same time as a report of a fire at the Nuclear Operations Support Facility (the EOF is located inside) building.
The server was replaced by Telecommunication. The SPDS and ERDS are available at the EOF.
The NRC Resident Inspector was notified of this event by the Licensee.
Power Reactor
Event Number: 36674
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE WILLIAMS
HQ OPS Officer: STEVE SANDIN
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE WILLIAMS
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/09/2000
Notification Time: 13:49 [ET]
Event Date: 02/09/2000
Event Time: 12:45 [EST]
Last Update Date: 02/09/2000
Notification Time: 13:49 [ET]
Event Date: 02/09/2000
Event Time: 12:45 [EST]
Last Update Date: 02/09/2000
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):
MARK LESSER (R2)
MARK LESSER (R2)
| 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 |
OFFSITE NOTIFICATION TO THE FLORIDA DEP INVOLVING THE REMOVAL OF A LOGGERHEAD SEA TURTLE IN THE PLANT INTAKE CANAL BARRIER NET.
NOTIFICATION MADE TO FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP) REGARDING REMOVAL OF LOGGERHEAD TURTLE FROM PLANT INTAKE CANAL BARRIER NET. THE TURTLE WILL BE SENT OFFSITE FOR REHABILITATION. THERE WERE NO INJURIES TO THE TURTLE.
THE LICENSEE INFORMED THE FLORIDA DEP AND THE NRC RESIDENT INSPECTOR.
NOTIFICATION MADE TO FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP) REGARDING REMOVAL OF LOGGERHEAD TURTLE FROM PLANT INTAKE CANAL BARRIER NET. THE TURTLE WILL BE SENT OFFSITE FOR REHABILITATION. THERE WERE NO INJURIES TO THE TURTLE.
THE LICENSEE INFORMED THE FLORIDA DEP AND THE NRC RESIDENT INSPECTOR.
Power Reactor
Event Number: 36675
Facility: LASALLE
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: D. COVEYOU
HQ OPS Officer: BOB STRANSKY
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: D. COVEYOU
HQ OPS Officer: BOB STRANSKY
Notification Date: 02/09/2000
Notification Time: 16:36 [ET]
Event Date: 02/09/2000
Event Time: 12:12 [CST]
Last Update Date: 02/09/2000
Notification Time: 16:36 [ET]
Event Date: 02/09/2000
Event Time: 12:12 [CST]
Last Update Date: 02/09/2000
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 | 100 | Power Operation | 100 | Power Operation |
EMERGENCY DIESEL GENERATOR TRIPPED FOLLOWING TESTING
"While performing LOS-DG-M3, Monthly Operability Run of 2B Diesel Generator, Division three, the Diesel Generator tripped on reverse power before the output breaker was opened while preparing to take the Diesel Generator off line following this surveillance. Concurrently, a local alarm was received indicating a DC power failure, The reverse power trip is a function that is bypassed under accident conditions. Upon investigation, two fuses supplying engine control power were discovered blown. It is not known whether the fuses would have blown with the reverse power bypassed. The fuses which were installed were verified to be the correct type. The fuses were replaced with like for like and the power failure alarm cleared and the installed fuses did not blow. A plan is being developed to investigate the cause of the fuses blowing. The Diesel Generator is not available and is inoperable per LaSalle Technical Specifications, pending troubleshooting and potential corrective actions. The cause of the blown fuses is unknown at this time."
The NRC resident inspector has been informed of this event by the licensee.
"While performing LOS-DG-M3, Monthly Operability Run of 2B Diesel Generator, Division three, the Diesel Generator tripped on reverse power before the output breaker was opened while preparing to take the Diesel Generator off line following this surveillance. Concurrently, a local alarm was received indicating a DC power failure, The reverse power trip is a function that is bypassed under accident conditions. Upon investigation, two fuses supplying engine control power were discovered blown. It is not known whether the fuses would have blown with the reverse power bypassed. The fuses which were installed were verified to be the correct type. The fuses were replaced with like for like and the power failure alarm cleared and the installed fuses did not blow. A plan is being developed to investigate the cause of the fuses blowing. The Diesel Generator is not available and is inoperable per LaSalle Technical Specifications, pending troubleshooting and potential corrective actions. The cause of the blown fuses is unknown at this time."
The NRC resident inspector has been informed of this event by the licensee.
Power Reactor
Event Number: 36677
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIM FRAWLEY
HQ OPS Officer: BOB STRANSKY
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIM FRAWLEY
HQ OPS Officer: BOB STRANSKY
Notification Date: 02/09/2000
Notification Time: 18:38 [ET]
Event Date: 02/09/2000
Event Time: 15:46 [CST]
Last Update Date: 02/09/2000
Notification Time: 18:38 [ET]
Event Date: 02/09/2000
Event Time: 15:46 [CST]
Last Update Date: 02/09/2000
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):
LINDA HOWELL (R4)
LINDA HOWELL (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 32 | Power Operation | 2 | Startup |
AUXILIARY FEEDWATER SYSTEM ACTUATION DUE TO UNEXPECTED AMSAC ACTUATION
A main turbine trip and auxiliary feedwater system actuation occurred due to an unexpected ATWS mitigation system actuation circuitry (AMSAC) actuation. Because the reactor was operating below 50% power, the turbine trip did not cause an automatic reactor trip. The licensee is currently investigating the cause of the AMSAC actuation.
The NRC resident inspector has been informed of this notification by the licensee.
A main turbine trip and auxiliary feedwater system actuation occurred due to an unexpected ATWS mitigation system actuation circuitry (AMSAC) actuation. Because the reactor was operating below 50% power, the turbine trip did not cause an automatic reactor trip. The licensee is currently investigating the cause of the AMSAC actuation.
The NRC resident inspector has been informed of this notification by the licensee.
General Information or Other
Event Number: 36735
Rep Org: NEW YORK CITY DEPARTMENT OF HEALTH
Licensee: COLUMBIA UNIVERSITY
Region: 1
City: NEW YORK State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BORRI
HQ OPS Officer: BOB STRANSKY
Licensee: COLUMBIA UNIVERSITY
Region: 1
City: NEW YORK State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BORRI
HQ OPS Officer: BOB STRANSKY
Notification Date: 02/28/2000
Notification Time: 10:40 [ET]
Event Date: 02/09/2000
Event Time: 00:00 [EST]
Last Update Date: 02/28/2000
Notification Time: 10:40 [ET]
Event Date: 02/09/2000
Event Time: 00:00 [EST]
Last Update Date: 02/28/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JIM TRAPP (R1)
DON COOL (NMSS)
JOHN DAVIDSON (IAT)
ROBERT SKELTON (IAT)
JIM TRAPP (R1)
DON COOL (NMSS)
JOHN DAVIDSON (IAT)
ROBERT SKELTON (IAT)
AGREEMENT STATE REPORT
On 2/9/2000, Columbia University discovered that a graduate student in the biology department had contamination (phosphorus-32 and sulfur-35) of her hair and fingers. A radiological survey also discovered contamination in her apartment, which is owned by the university. An assessment based upon urinalysis indicated a dose of several millirem to the student.
An investigation by the university and NYC Department of Health determined that the contamination was intentionally self-inflicted by the student. The university is currently determining whether to expel the student. The student is a foreign national living in the United States on a student visa.
The NYC Department of Health has already contacted NRC Region I (Duncan White) regarding this event.
On 2/9/2000, Columbia University discovered that a graduate student in the biology department had contamination (phosphorus-32 and sulfur-35) of her hair and fingers. A radiological survey also discovered contamination in her apartment, which is owned by the university. An assessment based upon urinalysis indicated a dose of several millirem to the student.
An investigation by the university and NYC Department of Health determined that the contamination was intentionally self-inflicted by the student. The university is currently determining whether to expel the student. The student is a foreign national living in the United States on a student visa.
The NYC Department of Health has already contacted NRC Region I (Duncan White) regarding this event.