| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/05/2013 - 07/08/2013 ** EVENT NUMBERS ** |
 | 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. |
| 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. |
| 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. |
| 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." | |