Event Notification Report for April 13, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/12/2014 - 04/13/2014
EVENT NUMBERS
50032
50032
Power Reactor
Event Number: 50032
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WILLIAM MUFFLEY
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WILLIAM MUFFLEY
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/13/2014
Notification Time: 23:49 [ET]
Event Date: 04/13/2014
Event Time: 21:13 [EDT]
Last Update Date: 04/14/2014
Notification Time: 23:49 [ET]
Event Date: 04/13/2014
Event Time: 21:13 [EDT]
Last Update Date: 04/14/2014
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):
RAY POWELL (R1DO)
RAY POWELL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
REACTOR TRIP DUE TO ACTUATION OF MAIN GENERATOR PROTECTION RELAY
"This 4 and 8 hour notification is being made to report that Salem Unit 1 experienced an unplanned automatic reactor trip and subsequent Auxiliary Feedwater system actuation. The automatic trip was initiated from a generator protection relay. A walkdown of the main generator and all protection circuitry has been completed with no visible problems identified. A troubleshooting team is being assembled to determine the exact cause for the generator protection actuation. 11, 12, and 13 Aux Feedwater Pumps automatically started as expected on low Steam Generator water level following the reactor trip. All control rods inserted on the reactor trip. All ECCS and ESF systems functioned as expected.
"Salem Unit 1 is currently in Mode 3. Reactor Coolant System pressure is at 2235 psig and temperature is 547 degrees F with decay heat removal via the main steam dumps and Auxiliary Feedwater Systems.
"There was no major primary or secondary equipment tagged for maintenance prior to this event. Condenser vacuum and Steam Generator Feed Pumps were available for the duration of the event. No personnel were injured during this event."
The licensee notified the NRC Resident Inspector and the Lower Alloways Creek Township.
Unit 1 is in a normal shutdown electrical lineup. Unit 2 is in a refueling outage and was unaffected by the Unit 1 trip.
"This 4 and 8 hour notification is being made to report that Salem Unit 1 experienced an unplanned automatic reactor trip and subsequent Auxiliary Feedwater system actuation. The automatic trip was initiated from a generator protection relay. A walkdown of the main generator and all protection circuitry has been completed with no visible problems identified. A troubleshooting team is being assembled to determine the exact cause for the generator protection actuation. 11, 12, and 13 Aux Feedwater Pumps automatically started as expected on low Steam Generator water level following the reactor trip. All control rods inserted on the reactor trip. All ECCS and ESF systems functioned as expected.
"Salem Unit 1 is currently in Mode 3. Reactor Coolant System pressure is at 2235 psig and temperature is 547 degrees F with decay heat removal via the main steam dumps and Auxiliary Feedwater Systems.
"There was no major primary or secondary equipment tagged for maintenance prior to this event. Condenser vacuum and Steam Generator Feed Pumps were available for the duration of the event. No personnel were injured during this event."
The licensee notified the NRC Resident Inspector and the Lower Alloways Creek Township.
Unit 1 is in a normal shutdown electrical lineup. Unit 2 is in a refueling outage and was unaffected by the Unit 1 trip.