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Event Notification Report for May 28, 2015

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/27/2015 - 05/28/2015

** EVENT NUMBERS **


51092 51093 51094

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Power Reactor Event Number: 51092
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC MORE
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/27/2015
Notification Time: 10:45 [ET]
Event Date: 05/27/2015
Event Time: 09:45 [CDT]
Last Update Date: 05/27/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRISTINE LIPA (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER OUT OF SERVICE FOR PLANNED MAINTENANCE

"On 5/27/15, planned preventive maintenance activities are being performed on the Braidwood Generating Station Technical Support Center (TSC), Ventilation System. The work will be completed within approximately 10 hours. This activity includes preventative maintenance that requires the TSC ventilation system to be out of service which will render the TSC ventilation system non-functional.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff as necessary.

"This event is reportable per 10CFR50.72(b)(3)(xiii) for 'any event that results in a major loss of emergency assessment capability.' The planned maintenance will not be able to restore the TSC condensing unit or ventilation system to service within the facility activation time specified in the emergency plan (1 hour) in the event of an accident. The Emergency Response Organization team has been notified of the maintenance and the possible need to relocate during an emergency."

The licensee informed the NRC Resident Inspector.

* * * UPDATE FROM PETER MOODIE TO VINCE KLCO ON 5/27/2015 AT 2153 EDT * * *

Planned work is complete and the Technical Support Center was restored to service on May 27, 2015 at 1808 CDT.

The licensee will notify the NRC Resident Inspector. Notified the R3DO (Lipa).

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Power Reactor Event Number: 51093
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: FRED MUHLY
HQ OPS Officer: STEVEN VITTO
Notification Date: 05/27/2015
Notification Time: 18:37 [ET]
Event Date: 05/27/2015
Event Time: 09:52 [CDT]
Last Update Date: 05/27/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRISTINE LIPA (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

CONTROL ROOM EMERGENCY VENTILATION SYSTEM INOPERABLE

"On May 27, 2015, at 0952 CDT, the Control Room Emergency Ventilation (CREV) system was declared inoperable due to opening a ventilation duct hatch to facilitate fire damper inspection without administrative controls. The hatch was opened and upon discovery was immediately shut, re-establishing the boundary of the Control Room Envelope. As a result, Technical Specification 3.7.4, Condition C, was entered and subsequently exited.

"The CREV system maintains a habitable control room environment and ensures the operability of components in the control room emergency zone during accident conditions as well as protection of the operators from a high dose environment assumed during a design basis accident.

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(D) because the CREV system is a single train system, and loss of the CREV system could impact the plant's ability to mitigate the consequences of an accident as stated in Chapter 6 of the UFSAR. This event is also reportable under 10 CFR 50.72(b)(3)(xiii) since this condition also impacts the control room as an Emergency Response Facility.

"At 0955, Technical Specification 3.7.4, Condition C, for CREV System Inoperable due to inoperable Control Room Envelope was exited.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 51094
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: QUOC VO
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/28/2015
Notification Time: 03:35 [ET]
Event Date: 05/27/2015
Event Time: 22:17 [PDT]
Last Update Date: 05/28/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WAYNE WALKER (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

AREA RADIATION MONITORS NON-FUNCTIONAL DURING PLANNED BUS OUTAGE

"A planned outage of the Division 2 medium voltage switchgear (SM-8) was initiated at 22:17 PDT on 5/27/15. The bus outage results in all area radiation monitors required for emergency classification being non-functional. Compensatory measure monitoring equipment has been established prior to the loss to provide alternate means of monitoring area radiation levels. The SM-8 outage window is scheduled to last 124 hours. Although the monitoring function is maintained by the compensatory monitoring equipment, the planned loss of area radiation monitors for greater than 72 hours is being reported as a major loss of emergency assessment capability in accordance with 10 CFR 50. 72(b )(3)(xiii).

"The NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Thursday, May 28, 2015
Thursday, May 28, 2015