Event Notification Report for May 13, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/12/2002 - 05/13/2002
EVENT NUMBERS
38921389163891738918
Power Reactor
Event Number: 38921
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JERRY FREEMAN
HQ OPS Officer: RICH LAURA
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JERRY FREEMAN
HQ OPS Officer: RICH LAURA
Notification Date: 05/15/2002
Notification Time: 15:30 [ET]
Event Date: 05/13/2002
Event Time: 05:15 [EDT]
Last Update Date: 05/15/2002
Notification Time: 15:30 [ET]
Event Date: 05/13/2002
Event Time: 05:15 [EDT]
Last Update Date: 05/15/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DANIEL HOLODY (R1)
TIM MCGINTY (IRO)
DANIEL HOLODY (R1)
TIM MCGINTY (IRO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
LATE DECLARATION OF AN UNUSUAL EVENT FOR TORNADO
The licensee reported that on May 13, 2002, the national weather service issued a tornado warning for Central Ocean County, NJ. The Oyster Creek Station was within the tornado warning area. At 15:30 on May 15, 2002, the licensee determined that an Unusual Event should have been declared. No tornados were sighted nor did the conditions affect safe station operation.
The NRC Resident Inspector was notified.
The licensee reported that on May 13, 2002, the national weather service issued a tornado warning for Central Ocean County, NJ. The Oyster Creek Station was within the tornado warning area. At 15:30 on May 15, 2002, the licensee determined that an Unusual Event should have been declared. No tornados were sighted nor did the conditions affect safe station operation.
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 38916
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: TOM CLAY
HQ OPS Officer: LEIGH TROCINE
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: TOM CLAY
HQ OPS Officer: LEIGH TROCINE
Notification Date: 05/13/2002
Notification Time: 03:21 [ET]
Event Date: 05/13/2002
Event Time: 00:16 [CDT]
Last Update Date: 05/13/2002
Notification Time: 03:21 [ET]
Event Date: 05/13/2002
Event Time: 00:16 [CDT]
Last Update Date: 05/13/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
ANTON VEGEL (R3)
ANTON VEGEL (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 86 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM ON HIGH WATER LEVEL DUE TO THE FAILURE OF THE STARTUP LEVEL CONTROLLER DURING EXTENDED POWER UPRATE TESTING ON FEEDWATER LEVEL CONTROL
The following text is a portion of a facsimile received from the licensee:
"With the reactor at 86% power, extended power uprate testing on feedwater level control was in progress. A six-inch level step change from 32" to 38" was inputted for testing. Feedwater was being controlled by the startup level controller. The startup level controller failed to respond, allowing reactor water level to go high and cause a reactor scram on level 8, 52". All other systems responded normally."
The licensee stated that all control rods fully inserted due to the automatic reactor scram and that the highest reactor water level was 53". There were no safety injections or emergency core cooling system actuations, and none were required.
The licensee stated that the unit is currently in Hot Shutdown. Normal feedwater is being supplied to the reactor vessel for level control, and pressure is being controlled via the main steam line drains which go to the condenser (the heat sink). The outboard main steam isolation valves were manually closed. Containment parameters are normal.
The licensee notified the NRC resident inspector.
The following text is a portion of a facsimile received from the licensee:
"With the reactor at 86% power, extended power uprate testing on feedwater level control was in progress. A six-inch level step change from 32" to 38" was inputted for testing. Feedwater was being controlled by the startup level controller. The startup level controller failed to respond, allowing reactor water level to go high and cause a reactor scram on level 8, 52". All other systems responded normally."
The licensee stated that all control rods fully inserted due to the automatic reactor scram and that the highest reactor water level was 53". There were no safety injections or emergency core cooling system actuations, and none were required.
The licensee stated that the unit is currently in Hot Shutdown. Normal feedwater is being supplied to the reactor vessel for level control, and pressure is being controlled via the main steam line drains which go to the condenser (the heat sink). The outboard main steam isolation valves were manually closed. Containment parameters are normal.
The licensee notified the NRC resident inspector.
Power Reactor
Event Number: 38917
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOD KASPAR
HQ OPS Officer: MIKE NORRIS
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOD KASPAR
HQ OPS Officer: MIKE NORRIS
Notification Date: 05/13/2002
Notification Time: 15:04 [ET]
Event Date: 05/13/2002
Event Time: 11:18 [EDT]
Last Update Date: 05/13/2002
Notification Time: 15:04 [ET]
Event Date: 05/13/2002
Event Time: 11:18 [EDT]
Last Update Date: 05/13/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
RONALD GARDNER (R3)
RONALD GARDNER (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | N | 0 | Hot Standby | 0 | Hot Standby |
FITNESS-FOR-DUTY REPORT
A contract supervisor tested positive for drug use during a follow-up test. The individual's site access has been terminated. Contact the NRC Operations Center for additional information.
The NRC Resident Inspector has been notified.
A contract supervisor tested positive for drug use during a follow-up test. The individual's site access has been terminated. Contact the NRC Operations Center for additional information.
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 38918
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DANIEL J. BOYLE
HQ OPS Officer: MIKE NORRIS
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DANIEL J. BOYLE
HQ OPS Officer: MIKE NORRIS
Notification Date: 05/13/2002
Notification Time: 15:49 [ET]
Event Date: 05/13/2002
Event Time: 00:25 [EDT]
Last Update Date: 05/13/2002
Notification Time: 15:49 [ET]
Event Date: 05/13/2002
Event Time: 00:25 [EDT]
Last Update Date: 05/13/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DANIEL HOLODY (R1)
JOSEPH HOLONICH (IRO)
MICHAEL JOHNSON (NRR)
DANIEL HOLODY (R1)
JOSEPH HOLONICH (IRO)
MICHAEL JOHNSON (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 72 | Power Operation |
OPERATING LICENSE REPORT OF SIGNIFICANT ELECTRICAL TRANSIENT DUE TO LIGHTNING STRIKE
"On May 13, 2002, at 0025, Hope Creek Generating Station experienced a significant electrical transient as a result of lightning strike that caused the trip and re-closure of the New Freedom Line.
"The most significant impact was the loss of Feedwater Heating Transient due to the trip of the 6A, 6B, and 6C Feedwater Heaters. This Feedwater trip resulted in a peak transient power level of 105% power.
"Hope Creek Generating Facility Operating License (NPI-57) item 2.C(1) specifically authorizes operation of the facility not in excess of 3339 megawatts thermal (100%).
"Additionally, Operating [License] Item 2.C(11) prohibits operating the facility with Feedwater Heater capacity that would result in a rated power Feedwater Heater temperature less than 400 degrees.
"Both of these Operating License conditions were challenged during this transient and are reportable IAW section 2F of the Operating License.
"Station power was manually reduced and subsequently stabilized at approximately 75% to deal with the transient, and the Feedwater Heaters were restored to service.
"Additional equipment affected as a result of the electrical transient is as follows: 'C' ECCS keep fill Jockey pump tripped; Hydrogen Water Chemistry Injection system tripped; the North and South plant Ventilation Radiation Monitoring system tripped; the Drywell Leak Detection system tripped; Cooling Tower Blowdown Radiation Monitor tripped; the 'B' 1E Panel room Ventilation Train tripped and the standby 'A' train started; the 'A' Control Room Ventilation train tripped and the 'B' train auto started. The unit sustained a loss of Drywell cooling, and the 'B' Fuel Pool Cooling Pump tripped. The RWCU system pumps tripped.
"The plant is stable, and the event is under investigation."
The NRC Resident Inspector has been notified.
"On May 13, 2002, at 0025, Hope Creek Generating Station experienced a significant electrical transient as a result of lightning strike that caused the trip and re-closure of the New Freedom Line.
"The most significant impact was the loss of Feedwater Heating Transient due to the trip of the 6A, 6B, and 6C Feedwater Heaters. This Feedwater trip resulted in a peak transient power level of 105% power.
"Hope Creek Generating Facility Operating License (NPI-57) item 2.C(1) specifically authorizes operation of the facility not in excess of 3339 megawatts thermal (100%).
"Additionally, Operating [License] Item 2.C(11) prohibits operating the facility with Feedwater Heater capacity that would result in a rated power Feedwater Heater temperature less than 400 degrees.
"Both of these Operating License conditions were challenged during this transient and are reportable IAW section 2F of the Operating License.
"Station power was manually reduced and subsequently stabilized at approximately 75% to deal with the transient, and the Feedwater Heaters were restored to service.
"Additional equipment affected as a result of the electrical transient is as follows: 'C' ECCS keep fill Jockey pump tripped; Hydrogen Water Chemistry Injection system tripped; the North and South plant Ventilation Radiation Monitoring system tripped; the Drywell Leak Detection system tripped; Cooling Tower Blowdown Radiation Monitor tripped; the 'B' 1E Panel room Ventilation Train tripped and the standby 'A' train started; the 'A' Control Room Ventilation train tripped and the 'B' train auto started. The unit sustained a loss of Drywell cooling, and the 'B' Fuel Pool Cooling Pump tripped. The RWCU system pumps tripped.
"The plant is stable, and the event is under investigation."
The NRC Resident Inspector has been notified.