United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2013 > July 8

Event Notification Report for July 8, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/05/2013 - 07/08/2013

** EVENT NUMBERS **


49174 49175 49176 49177

To top of page
Power Reactor Event Number: 49174
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JASON ADAMS
HQ OPS Officer: CHARLES TEAL
Notification Date: 07/05/2013
Notification Time: 12:34 [ET]
Event Date: 05/22/2013
Event Time: 11:34 [CDT]
Last Update Date: 07/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
MICHAEL KUNOWSKI (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

Event Text

60 DAY OPTIONAL TELEPHONIC NOTIFICATION OF INVALID DIVISION 1 CONTAINMENT ISOLATION DUE TO MOTOR GENERATOR TRIP

"On May 22, 2013, at approximately 1134 CDT, while Unit 1 was operating at 100% power, the 1A Reactor Protection System (RPS) Motor Generator (M/G) set tripped causing a loss of the A RPS bus. This caused the actuation of the Division 1 (outboard) primary containment isolation logic. This was an event that resulted in the actuation of a general containment isolation signal affecting more than one system. However, as this event meets the definition of an invalid actuation (i.e. not a response to an actual plant parameter exceeding a trip setpoint), this notification is being made in accordance with 10 CFR 50.73(a)(1) in lieu of a Licensee Event Report.

"In response to the trip of the 1A RPS M/G, operators swapped the A RPS bus to the alternate power supply using the applicable response procedure. The containment isolation signal was reset and the systems were restored to their normal lineup. Reactor power was not affected by this event. All safety related equipment controlled by the affected primary containment isolation circuits operated as designed.

"The 1A RPS M/G trip was due to a motor fault requiring motor replacement. Replacement of the motor was completed on 5/26/13 and the A RPS bus was restored to its normal power supply on 5/27/13."

The licensee has notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 49175
Facility: MILLSTONE
Region: 1 State: CT
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JOHN MAGYARIK
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/06/2013
Notification Time: 23:47 [ET]
Event Date: 07/06/2013
Event Time: 20:04 [EDT]
Last Update Date: 07/07/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES NOGGLE (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Decommissioned 0 Decommissioned

Event Text

UNIT 1 SPENT FUEL POOL ISLAND RADIATION MONITOR INOPERABLE

The Millstone Unit 1 spent fuel pool island ventilation system tripped offline for reasons unknown at the time of this report. The spent fuel pool island radiation monitor requires the ventilation system to be in service to function. Therefore, the radiation monitor was declared inoperable. The loss of the radiation monitor results in a loss of assessment capability.

The licensee's chemistry department is taking compensatory samples in accordance with the Radiation Effluent Monitoring Offsite Dose Calculation Manual action statement until the spent fuel pool island ventilation can be restored.

The licensee has notified the NRC Resident Inspector, state and local authorities.

To top of page
Power Reactor Event Number: 49176
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CHRIS AULT
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/07/2013
Notification Time: 06:49 [ET]
Event Date: 07/07/2013
Event Time: 04:00 [EDT]
Last Update Date: 07/07/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES NOGGLE (R1DO)

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

LOSS OF RADWASTE/REACTOR BUILDING VENT GASEOUS EFFLUENT RADIATION MONITORING CAPABILITY

"At 0400 EDT on July 7, 2013, Nine Mile Point Unit 2 isolated the Reactor Building to comply with Tech Spec 3.3.6.2.A.1 Secondary Containment Isolation Instrumentation. Isolating the Reactor Building was the result of Refuel Floor Radiation Monitor 2HVR*CAB14A becoming inoperable on 7/6/13 at 0430 hours. As a result of the Reactor Building being isolated, the Radwaste/Reactor Building Vent Gaseous Effluent Radiation Monitor has been declared non-functional based on sample flow rates.

"The Radwaste/Reactor Building Vent Gaseous Effluent Radiation Monitor is necessary for accident assessment and is credited for Emergency Action Level (EAL) classification. The inability to classify an EAL due to the out-of-service Radwaste/Reactor Building Vent Gaseous Effluent Monitor is considered a loss of emergency assessment capability and is reportable per 10 CFR 50.72(b)(3)(xiii).

"Repairs and testing are currently in progress to correct the cause and restore functionality of Radiation Monitor 2HVR*CAB14A. The expected return to service time is within the next 12 hours.

"Compensatory actions for the non-functional Radwaste/Reactor Building Vent Gaseous Effluent Radiation Monitor are in place to take and analyze periodic grab samples and flow estimates in accordance with the Offsite Dose Calculation Manual.

"The NRC Resident Inspector has been notified." The licensee will also be notifying state authorities.

To top of page
Power Reactor Event Number: 49177
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: TOM FOUTS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/07/2013
Notification Time: 11:15 [ET]
Event Date: 07/07/2013
Event Time: 03:26 [EDT]
Last Update Date: 07/07/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES NOGGLE (R1DO)

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

Event Text

LOSS OF EMERGENCY SIRENS DUE TO POWER OUTAGES

"At 0326 EDT on 07/07/2013, it was determined that 14 of 96 Ginna Nuclear Power Plant Emergency Offsite Sirens were nonfunctional. The apparent cause is loss of power to the sirens due to storm related power outages. The weather has since returned to normal conditions, and residential power restoration is in progress. [At the time of this report, only 3 sirens remained without power]. This event is being reported as a Loss of Emergency Preparedness Capabilities pursuant to 10 CFR 50.72(b)(3)(xiii).

"The NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Monday, July 08, 2013
Monday, July 08, 2013