Event Notification Report for February 01, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/31/2000 - 02/01/2000
Power Reactor
Event Number: 36648
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: STEVE MERRILL
HQ OPS Officer: STEVE SANDIN
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: STEVE MERRILL
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/01/2000
Notification Time: 09:27 [ET]
Event Date: 02/01/2000
Event Time: 07:40 [EST]
Last Update Date: 02/01/2000
Notification Time: 09:27 [ET]
Event Date: 02/01/2000
Event Time: 07:40 [EST]
Last Update Date: 02/01/2000
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):
CAUDLE JULIAN (R2)
CAUDLE JULIAN (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 |
NOTIFICATION TO THE FLORIDA DEPARTMENT OF THE ENVIRONMENT INVOLVING A GREEN SEA TURTLE FOUND IN THE INTAKE CANAL
"AT APPROXIMATELY 0740 EST ON 2/1/00, A JUVENILE GREEN SEA TURTLE WAS RESCUED FROM THE PLANT'S INTAKE CANAL. THE TURTLE WAS ALIVE BUT IN NEED OF REHABILITATION. AS REQUIRED BY THE PLANT'S SEA TURTLE PERMIT, THE FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION WAS NOTIFIED OF THE EVENT."
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.
"AT APPROXIMATELY 0740 EST ON 2/1/00, A JUVENILE GREEN SEA TURTLE WAS RESCUED FROM THE PLANT'S INTAKE CANAL. THE TURTLE WAS ALIVE BUT IN NEED OF REHABILITATION. AS REQUIRED BY THE PLANT'S SEA TURTLE PERMIT, THE FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION WAS NOTIFIED OF THE EVENT."
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.
Power Reactor
Event Number: 36651
Facility: WNP-2
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: J. McBRIDE
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: J. McBRIDE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/01/2000
Notification Time: 18:49 [ET]
Event Date: 02/01/2000
Event Time: 12:25 [PST]
Last Update Date: 02/01/2000
Notification Time: 18:49 [ET]
Event Date: 02/01/2000
Event Time: 12:25 [PST]
Last Update Date: 02/01/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(2)(iii)(C) - POT UNCNTRL RAD REL
Person (Organization):
CLAUDE JOHNSON (R4)
CLAUDE JOHNSON (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
A condition that alone could have caused the loss of initiation capability of an engineered safety feature.
At 1038 PST on 01/31/00, the division 2 low condenser vacuum main steam isolation initiation channel B was found to trip at approximately 2.4 inches Hg vacuum during the performance of plant technical specification surveillance test. This was less than the plant technical specification allowable value of greater than or equal to 7.2 inches Hg vacuum. The channel was declared inoperable and entry into plant technical specification limiting condition of operation (LCO) 3.3.6.1.A was made for the channel. Channel B was then adjusted to plant technical specification tolerance per approved plant procedures and returned to service. LCO 3.3.6.1.A was then exited at 1135 PST on 01/31/00.
At 1310 PST on 01/31/00, the division 2 low condenser vacuum main steam isolation initiation channel D was found to trip at approximately 2.8 inches Hg vacuum during the performance of a plant technical specification surveillance test. This was less than the plant technical specification allowable value of greater than or equal to 7.2 inches Hg vacuum. The channel was declared inoperable and entry into plant technical specification LCO 3.3.6.1.A was made for the channel. Channel D was then adjusted to plant technical specification tolerance per approved plant procedures and returned to service. LCO 3.3.6.1.A was then exited at 1335 PST on 01/31/00.
A problem evaluation request was initiated on 01/31/00 to investigate the cause of the setpoint problem. Preliminary investigation determined that on 11/10/99 the pressure switches had been miscalibrated during the previous surveillance due to a calibration equipment problem. The division 1 low condenser vacuum main steam isolation initiation pressure switch setpoints were verified to be in compliance with plant technical specifications.
At 1225 PST on 02/01/00, plant system engineering determined, based on engineering judgement, that a loss of engineered safety feature initiation capability had occurred since the time that the pressure switches were miscalibrated and informed the control room staff. The control room staff performed an independent review and concurred with the assessment. Investigation into the cause of this condition will continue.
The licensee notified the NRC Resident Inspector.
At 1038 PST on 01/31/00, the division 2 low condenser vacuum main steam isolation initiation channel B was found to trip at approximately 2.4 inches Hg vacuum during the performance of plant technical specification surveillance test. This was less than the plant technical specification allowable value of greater than or equal to 7.2 inches Hg vacuum. The channel was declared inoperable and entry into plant technical specification limiting condition of operation (LCO) 3.3.6.1.A was made for the channel. Channel B was then adjusted to plant technical specification tolerance per approved plant procedures and returned to service. LCO 3.3.6.1.A was then exited at 1135 PST on 01/31/00.
At 1310 PST on 01/31/00, the division 2 low condenser vacuum main steam isolation initiation channel D was found to trip at approximately 2.8 inches Hg vacuum during the performance of a plant technical specification surveillance test. This was less than the plant technical specification allowable value of greater than or equal to 7.2 inches Hg vacuum. The channel was declared inoperable and entry into plant technical specification LCO 3.3.6.1.A was made for the channel. Channel D was then adjusted to plant technical specification tolerance per approved plant procedures and returned to service. LCO 3.3.6.1.A was then exited at 1335 PST on 01/31/00.
A problem evaluation request was initiated on 01/31/00 to investigate the cause of the setpoint problem. Preliminary investigation determined that on 11/10/99 the pressure switches had been miscalibrated during the previous surveillance due to a calibration equipment problem. The division 1 low condenser vacuum main steam isolation initiation pressure switch setpoints were verified to be in compliance with plant technical specifications.
At 1225 PST on 02/01/00, plant system engineering determined, based on engineering judgement, that a loss of engineered safety feature initiation capability had occurred since the time that the pressure switches were miscalibrated and informed the control room staff. The control room staff performed an independent review and concurred with the assessment. Investigation into the cause of this condition will continue.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 36652
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: BLAIR
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: BLAIR
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/01/2000
Notification Time: 23:26 [ET]
Event Date: 02/01/2000
Event Time: 22:24 [EST]
Last Update Date: 02/01/2000
Notification Time: 23:26 [ET]
Event Date: 02/01/2000
Event Time: 22:24 [EST]
Last Update Date: 02/01/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
TONY DIMITRIADIS (R1)
FRANK CONGEL (IRO)
TONY DIMITRIADIS (R1)
FRANK CONGEL (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 |
INFORMATION CALL INVOLVING A NON-CREDIBLE PLANT THREAT.
CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS.
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.
CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS.
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.