Event Notification Report for December 27, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/26/2001 - 12/27/2001
EVENT NUMBERS
38598
Power Reactor
Event Number: 38598
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DOUG PERRY
HQ OPS Officer: LEIGH TROCINE
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DOUG PERRY
HQ OPS Officer: LEIGH TROCINE
Notification Date: 12/27/2001
Notification Time: 16:03 [ET]
Event Date: 12/27/2001
Event Time: 13:21 [EST]
Last Update Date: 12/29/2001
Notification Time: 16:03 [ET]
Event Date: 12/27/2001
Event Time: 13:21 [EST]
Last Update Date: 12/29/2001
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):
MICHELE EVANS (R1)
MICHELE EVANS (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
REACTOR SCRAM AFTER TWO RECIRCULATION MOTOR-GENERATOR (MG) SETS TRIPPED DURING THE PERFORMANCE OF ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) LOGIC TESTING
The following text is a portion of a facsimile received from the licensee:
"While performing ATWS logic testing, both [the] 'A' [and] 'B' [recirculation] MG sets tripped, and the reactor was scrammed. The cause of the scram is being determined at this time. All control rods fully inserted on the scram. All safety systems functioned properly during the transient. The plant is in the process of being maneuvered to Cold Shutdown."
The licensee stated that the main steam isolation valves remained open and that none of the safety relief valves lifted. In addition, there were no emergency core cooling system actuations, and none were required. The reported engineered safety feature actuation was the actuation of the reactor protection system.
The unit is currently stable in Hot Shutdown. Normal condensate and feedwater is being utilized to supply water to the reactor vessel, and the condenser is being utilized as a heat sink. Containment parameters are normal, offsite power is available, and the electrical grid is stable. The emergency diesel generators and engineered safety feature systems are available if needed.
The licensee stated that the ATWS logic test procedure was not new and that it had been performed on several occasions in the past. The ATWS logic test was successfully completed for the 'A' side earlier today, and the plant transient occurred during the performance of the ATWS logic test for the 'B' side. The cause of the recirculation MG set trips is currently under investigation.
The licensee notified the NRC resident inspector.
* * * UPDATED AT 0023 ON 12/29/01 BY ERIC OLSON TO FANGIE JONES * * *
The licensee reported the cause of the scram as Average Power Range (APR) Hi-Hi trip caused by a flow control trip reference card signal from the low flow due the trip of both recirc pumps.
The NRC Resident Inspector has been informed by the licensee. The R1DO (Michele Evans) has been informed.
The following text is a portion of a facsimile received from the licensee:
"While performing ATWS logic testing, both [the] 'A' [and] 'B' [recirculation] MG sets tripped, and the reactor was scrammed. The cause of the scram is being determined at this time. All control rods fully inserted on the scram. All safety systems functioned properly during the transient. The plant is in the process of being maneuvered to Cold Shutdown."
The licensee stated that the main steam isolation valves remained open and that none of the safety relief valves lifted. In addition, there were no emergency core cooling system actuations, and none were required. The reported engineered safety feature actuation was the actuation of the reactor protection system.
The unit is currently stable in Hot Shutdown. Normal condensate and feedwater is being utilized to supply water to the reactor vessel, and the condenser is being utilized as a heat sink. Containment parameters are normal, offsite power is available, and the electrical grid is stable. The emergency diesel generators and engineered safety feature systems are available if needed.
The licensee stated that the ATWS logic test procedure was not new and that it had been performed on several occasions in the past. The ATWS logic test was successfully completed for the 'A' side earlier today, and the plant transient occurred during the performance of the ATWS logic test for the 'B' side. The cause of the recirculation MG set trips is currently under investigation.
The licensee notified the NRC resident inspector.
* * * UPDATED AT 0023 ON 12/29/01 BY ERIC OLSON TO FANGIE JONES * * *
The licensee reported the cause of the scram as Average Power Range (APR) Hi-Hi trip caused by a flow control trip reference card signal from the low flow due the trip of both recirc pumps.
The NRC Resident Inspector has been informed by the licensee. The R1DO (Michele Evans) has been informed.