Event Notification Report for September 26, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/25/2006 - 09/26/2006
EVENT NUMBERS
42864
Power Reactor
Event Number: 42864
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF ERDMANN
HQ OPS Officer: BILL GOTT
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF ERDMANN
HQ OPS Officer: BILL GOTT
Notification Date: 09/26/2006
Notification Time: 17:18 [ET]
Event Date: 09/26/2006
Event Time: 15:13 [EDT]
Last Update Date: 09/26/2006
Notification Time: 17:18 [ET]
Event Date: 09/26/2006
Event Time: 15:13 [EDT]
Last Update Date: 09/26/2006
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):
CHRIS HOTT (R1)
CHRIS HOTT (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 94 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO REACTOR COOLANT PUMP SEAL LEAKAGE.
Salem Unit 2 was manually tripped from 94.1 percent reactor power due to Reactor Coolant Pump "21" number 1 seal leakoff exceeding 6 gpm in accordance with abnormal operating procedure. Reactor Coolant Pump "21" was subsequently stopped upon reactor trip verification in accordance with the Abnormal Operating Procedures. Forced reactor coolant system circulation is via the remaining 3 reactor coolant pumps. All safety systems functioned as designed. Auxiliary feedwater pumps started as expected, offsite power is available, Emergency Diesel Generators are available but not required at this time. Decay heat removal is via steam dumps to the main condenser. Salem Unit 2 is currently stable in Mode 3 (Hot Standby). There is no equipment out of service that contributed to this event. There were no personnel injuries or radiological occurrences associated with this event. The licensee is investigating to determine the cause of the abnormal reactor coolant pump seal leakoff flow rate.
The licensee notified local government officials. The licensee notified the NRC Resident Inspector.
Salem Unit 2 was manually tripped from 94.1 percent reactor power due to Reactor Coolant Pump "21" number 1 seal leakoff exceeding 6 gpm in accordance with abnormal operating procedure. Reactor Coolant Pump "21" was subsequently stopped upon reactor trip verification in accordance with the Abnormal Operating Procedures. Forced reactor coolant system circulation is via the remaining 3 reactor coolant pumps. All safety systems functioned as designed. Auxiliary feedwater pumps started as expected, offsite power is available, Emergency Diesel Generators are available but not required at this time. Decay heat removal is via steam dumps to the main condenser. Salem Unit 2 is currently stable in Mode 3 (Hot Standby). There is no equipment out of service that contributed to this event. There were no personnel injuries or radiological occurrences associated with this event. The licensee is investigating to determine the cause of the abnormal reactor coolant pump seal leakoff flow rate.
The licensee notified local government officials. The licensee notified the NRC Resident Inspector.