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Event Notification Report for August 12, 2015

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
08/11/2015 - 08/12/2015

EVENT NUMBERS
51313

Power Reactor
Event Number: 51313
Facility: FERMI
Region: 3     State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: BRETT JEBBIA
HQ OPS Officer: STEVEN VITTO
Notification Date: 08/12/2015
Notification Time: 13:31 [ET]
Event Date: 08/12/2015
Event Time: 10:07 [EDT]
Last Update Date: 08/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
Event Text
SECONDARY CONTAINMENT TECHNICAL SPECIFICATIONS NOT MET

"At 1007 [EDT] on August 12, 2015, while restoring Reactor Building (RB) HVAC (RBHVAC) after surveillance testing, an equipment malfunction resulted in improper damper alignment resulting in Secondary Containment Technical Specifications (TS) to not be met.

"The plant TS require Secondary Containment pressure be maintained greater than or equal to -0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1). This specification was not maintained for five seconds and the highest pressure observed was -0.095 inches of vacuum water gauge. This value was observed on only one of two installed recorders, of the Secondary Containment pressure recorders. The highest observed pressure on the other recorder was -0.14 inches of vacuum water gauge. Secondary Containment was restored by the Standby Gas Treatment System (SGTS) already in operation and shutting down the affected train of RBHVAC.

"The technical specification requirement is to maintain secondary containment at -0.125 inches of vacuum water gauge for secondary containment operability. Declaring secondary containment inoperable is reportable under 10 CFR50.72(b)(3)(v)(c) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material."

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 1159 EDT ON 08/13/15 FROM BRETT JEBBIA TO S. SANDIN * * *

The licensee is updating this report to delete the minus sign for all references to inches of vacuum water gauge.

"FOLLOW UP - CORRECTED INFORMATION: At 1007 [EDT] on August 12, 2015, while restoring Reactor Building (RB) HVAC (RBHVAC) after surveillance testing, an equipment malfunction resulted in improper damper alignment resulting in Secondary Containment Technical Specifications (TS) to not be met.

"The plant TS require Secondary Containment pressure be maintained greater than or equal to .125 inches of vacuum water gauge (TS SR 3.6.4.1.1). This specification was not maintained for five seconds and the highest pressure observed was .095 inches of vacuum water gauge. This value was observed on only one, of two installed recorders, of the Secondary Containment pressure recorders. The highest observed pressure on the other recorder was .14 inches of vacuum water gauge. Secondary Containment was restored by the Standby Gas Treatment System (SGTS) already in operation and shutting down the affected train of RBHV AC.

"The technical specification requirement is to maintain secondary containment greater than or equal to .125 inches of vacuum water gauge for secondary containment operability. Declaring secondary containment inoperable is reportable under 10CFR50.72(b)(3)(v)c as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material."

the licensee informed the NRC Resident Inspector. Notified R1DO (Powell).