Event Notification Report for March 26, 2015

SEISMIC MONITOR NOT AVAILABLE FOR EMERGENCY PLAN ASSESSMENT

"LaSalle Station has completed a review of seismic monitor performance. The seismic monitor is currently operable; however, this review identified 6 times in the past 3 years that the seismic monitor was inoperable such that emergency classification at the ALERT level could not be obtained with site instrumentation. The seismic monitor was determined to be inoperable on the following dates:

1) January 28, 2015
2) May 28, 2014
3) January 1, 2014
4) August 5, 2013
5) April 17, 2013
6) April 10, 2012

"These unplanned inoperable conditions of the seismic monitor were entered into the LaSalle Corrective Action Program when they occurred.

"While Exelon procedural direction allowed the use of offsite sources to obtain seismic data when the seismic monitor is incapable of assessing emergency plan Emergency Action Levels (EALs), this was not explicitly referenced in the approved EALs. The loss of assessment capability is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). This report is required per 10 CFR 50.72(a)(1)(ii) as an event that occurred within 3 years of the date of discovery."

The licensee has notified the NRC Resident Inspector.

SEISMOGRAPH NOT AVAILABLE FOR EMERGENCY PLAN ASSESSMENT

"Quad Cities Station has completed a review of the station strong motion seismograph's performance. The seismograph is currently functional; however, this review identified 3 times in the past 3 years that the seismograph was non-functional such that emergency classification at the ALERT level could not be obtained with site instrumentation:

1) 02/03/2014
2) 10/07/2014
3) 10/19/2014

"These unplanned non-functional conditions of the seismograph were entered into the Quad Cities Corrective Action Program when they occurred.

"While Exelon procedural direction allowed the use of offsite sources to obtain seismic data when the seismograph was nonfunctional, this was not explicitly referenced in the approved Emergency Action Levels. The loss of assessment capability is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). This report is required per 10 CFR 50.72(a)(1)(ii) as an event that occurred within 3 years of the date of discovery."

Corrective actions are in progress.

The licensee notified the NRC Resident Inspector.

60-DAY OPTIONAL TELEPHONIC NOTIFICATION FOR AN INVALID PRIMARY CONTAINMENT AND DRYWELL ISOLATION VALVE ACTUATION

"This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation of a containment isolation signal affecting more than one system.

"At 1629 EDT on March 26, 2015, the plant received a Division 1 balance of plant outboard containment and drywell isolation signal. The isolation signal was received while removing fuses to establish a clearance for the replacement of an average power range monitor bypass switch. The removal of two fuses removed power to the manual initiation logic resulting in an isolation signal.

"The following component actuations occurred: valves 1P51F0150 and 1P51F0652, isolating service air to the containment and drywell; valves 1G61F0155 and 1G61F0170, isolating the containment and drywell floor drain sumps; valves 1D17F0071A and 1D17F0079A, isolating the drywell radiation monitor; valves 1D17F0081A and 1D17F0089A, isolating the containment radiation monitor; valve 1P11F0080, isolating the containment pools drain; valves 1P50F0060 and 1P50F0150, isolating the containment vessel chilled water system; valves 1P53F0070 and 1P53F0075, isolating the upper and lower airlock local leak rate air supply; valves 1P52F0160 and 1P52F0170, isolating the upper and lower airlock air supply; valve 1P22F0015, isolating mixed bed water to the drywell; and valve 1P54F0395, isolating fire protection carbon dioxide to the drywell.

"This event is considered an invalid system actuation reportable under 10 CFR 50.73(a)(2)(iv)(A).

"The isolation was not initiated in response to actual plant conditions or parameters, and was not a manual initiation. Therefore, this notification is provided via a 60-day optional phone call in accordance with 10 CFR 50.73(a)(1) instead of submitting a written Licensee Event Report.

"The event meets reporting criteria specified in 10 CFR 50.73(a)(2)(iv)(B)(2) as a general containment isolation valve signal affecting containment isolation valves in more than one system. All affected systems functioned as expected in response to the loss of power to the manual initiation logic. The valves were reopened in accordance with plant procedures. The inadvertent isolation signal was the result of a human performance error.

"The NRC Resident Inspector has been notified."