Event Notification Report for February 09, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/08/2002 - 02/09/2002
EVENT NUMBERS
38687
Power Reactor
Event Number: 38687
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DOUGLAS DYE
HQ OPS Officer: FANGIE JONES
Region: 4 State: CA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DOUGLAS DYE
HQ OPS Officer: FANGIE JONES
Notification Date: 02/09/2002
Notification Time: 10:09 [ET]
Event Date: 02/09/2002
Event Time: 03:37 [PST]
Last Update Date: 02/09/2002
Notification Time: 10:09 [ET]
Event Date: 02/09/2002
Event Time: 03:37 [PST]
Last Update Date: 02/09/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOHN PELLET (R4)
JOHN PELLET (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER TO A STEAM GENERATOR
"At 0337, on 2/9/2002, Unit 2 reactor was manually tripped due to a failure of feedwater regulating valve FW-2-FCV-540. The valve failed closed isolating feedwater to steam generator 2-4. The reason for the failure is currently unknown, investigation continues. All safety systems responded as required. [All control rods fully inserted]. Auxiliary feedwater pumps 2-1, 2-2, 2-3 started as required in response to low steam generator water levels.
"DCPP unit 2 is stable in Mode 3, heat removal is via steam dumping to the normal condenser, auxiliary feedwater continues to supply the steam generators." The unit will remain in Mode 3 until repairs are made.
The unit 2 steam generator 4 has had a long term tube leak (about 2 years) on the order of about 3.82 gpd (TS limit 150 gpd) by most recent calculation. Secondary activity is less than detectable and only a count rate on steam jet air ejector is positive indication. Primary activity pretrip was 3.47E-3 µCi/ml.
The licensee notified the NRC Resident Inspector and will make a normal press release.
(Refer to event #38697 for additional information.)
"At 0337, on 2/9/2002, Unit 2 reactor was manually tripped due to a failure of feedwater regulating valve FW-2-FCV-540. The valve failed closed isolating feedwater to steam generator 2-4. The reason for the failure is currently unknown, investigation continues. All safety systems responded as required. [All control rods fully inserted]. Auxiliary feedwater pumps 2-1, 2-2, 2-3 started as required in response to low steam generator water levels.
"DCPP unit 2 is stable in Mode 3, heat removal is via steam dumping to the normal condenser, auxiliary feedwater continues to supply the steam generators." The unit will remain in Mode 3 until repairs are made.
The unit 2 steam generator 4 has had a long term tube leak (about 2 years) on the order of about 3.82 gpd (TS limit 150 gpd) by most recent calculation. Secondary activity is less than detectable and only a count rate on steam jet air ejector is positive indication. Primary activity pretrip was 3.47E-3 µCi/ml.
The licensee notified the NRC Resident Inspector and will make a normal press release.
(Refer to event #38697 for additional information.)