At
1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> on April 15, 2005, while conducting
excess flow check valve testing in conjunction with a reactor vessel pressure test during a scheduled refueling outage, Unit 1 received an invalid Anticipated
Transient Without
Scram (
ATWS) Channel A trip signal and invalid reactor Lo-Lo water level trips on the A and C channels for
ECCS. The operating
Reactor Recirculation pump (1 A) tripped and both
Emergency Diesel Generators (Unit 1 and Unit 0) auto-started and ran unloaded.
RCIC received an initiation signal, which resulted in proper valve repositioning for the system but no injection due to the steam supply being isolated to support the reactor vessel pressure test. In addition, all appropriate running equipment tripped due to load shedding. Reactor pressure was 787 psig at the time of the event and no pressure
transient or vessel injection occurred. All equipment responded to the actuation as expected for plant conditions. The
excess flow check valve testing was stopped and the reactor vessel pressure test was terminated as a result of this invalid actuation.
It was subsequently determined that a leaking drain valve at the instrument rack where the excess flow check valve testing was being performed caused a slow depressurization of the high-pressure side sensing line for the level transmitters associated with ATWS Channel A and the A and C channels for ECCS, resulting in an erroneous level signal and the invalid actuation. The instrument rack drain valve is scheduled for replacement.
The NRC Resident Inspector was notified