Power Reactor

Event Number: 42395

Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PAUL ABBOTT
HQ OPS Officer: MIKE RIPLEY

Notification Date: 03/08/2006
Notification Time: 14:08 [ET]
Event Date: 03/08/2006
Event Time: 11:09 [EST]
Last Update Date: 03/08/2006

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

Person (Organization):
JOHN WHITE (R1)
ERIC BENNER (NRR)
PETER WILSON (IRD)

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

AUTOMATIC REACTOR TRIP AS A RESULT OF A TURBINE GENERATOR TRIP

"This 4-hour notification is being made in accordance with 10CFR50.72(b)(2)(iv)(b). Salem Unit-1 reactor automatically tripped at 1109 (RPS actuation). The trip was initiated due to turbine trip. The cause of the turbine trip is being investigated.

"All safety systems functioned as designed with the exception of control rod 1SC1, which did not fully insert. 1SC1 indicates 16 steps. It should indicate zero steps when fully inserted. Auxiliary Feedwater pumps started as expected. Off-site power is available. Emergency diesel generators are available but not required at this time.

"During the implementation of the EOP's, a steam leak was reported in the Turbine Building . The Main Steam Isolation Valves (MSIV's) were closed as a conservative measure. This is an 8-hour reportable occurrence in accordance with 10CFR50.72(b)(3)(iv)(a). The leak was subsequently identified as a feedwater leak on the 11CN32 (11 Steam Generator Feed Pump suction valve). The Condensate System was placed in a normal shutdown line-up and the leak is not an impact to personnel safety or plant stability. Decay heat removal is via the atmospheric steam dumps at this time. The MSIV's are being bypassed to restore the main condenser as a heat sink.

"Salem Unit-1 is currently in Mode 3 with reactor coolant system temperature at approximately 549 deg F with pressure at 2235 psig.

"There was no equipment out of service that contributed to this event and there were no personnel injuries or radiological occurrences associated with this event."

The licensee has notified the NRC Resident Inspector and will be making State and local notifications. A press release is expected.

Power Reactor

Event Number