United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2011 > January 10

Event Notification Report for January 10, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/06/2011 - 01/10/2011

** EVENT NUMBERS **


46523 46524 46525 46526

To top of page
Part 21 Event Number: 46523
Rep Org: FAIRBANKS MORSE ENGINE
Licensee: FAIRBANKS MORSE ENGINE
Region: 3
City: BELOIT State: WI
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DOMINIC DEDOLPH
HQ OPS Officer: JOE O'HARA
Notification Date: 01/07/2011
Notification Time: 17:13 [ET]
Event Date: 11/16/2010
Event Time: [CST]
Last Update Date: 01/07/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
NEIL PERRY (R1DO)
PART 21 GRP ()

Event Text

PART 21 REPORT FOR POTENTIAL SAFETY HAZARD ON SPEED SWITCH INSTALLED ON EMERGENCY DIESEL GENERATOR (EDG)

The following was received via fax:

"[Fairbanks Morse (FM) determined] that when the speed switch assembly was mounted on a conductive surface, the voltage regulator grounded out the 24 volt direct current power through the heat sink preventing the speed switch from operating.

"This condition was not detected prior to the first speed switch being shipped to Hope Creek in September, 2010. It was never installed on the EDG prior to being recalled. The unit was returned to FM and has since been reworked and verified to be in compliance with the latest design to eliminate the deficiency."

To top of page
Power Reactor Event Number: 46524
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ADAM SMITH
HQ OPS Officer: JOE O'HARA
Notification Date: 01/08/2011
Notification Time: 13:21 [ET]
Event Date: 01/08/2011
Event Time: 13:03 [EST]
Last Update Date: 01/09/2011
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
CHRISTINE LIPA (R3DO)
ERIC LEEDS (NRR)
MIKE CHEOK (NRR)
WILLIAM GOTT (IRD)
MARK SATORIUS (R3)
FLINTER (DHS)
VIA (FEMA)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 55 Power Operation

Event Text

UNUSUAL EVENT DECLARED DUE TO CATASTROPHIC FAILURE OF NON-SAFETY RELATED BUS BREAKER

A notice of unusual event was declared for 'Hazards and other conditions affecting plant safety' at 1303 EST for Emergency Action Level (EAL) HU1 as a result of a breaker/bus fault in a non-safety related feeder bus 'F'. The loss of the bus resulted in loss of cooling water tower pumps and fans and subsequently a loss of one cooling tower. There is indication of a pressure transient on the breaker panel and smoke but no fire. There is no indication of sabotage or terrorism, and no offsite assistance requested. There is no radiological release in progress. The NRC remains in the normal mode. NRC Resident staff are enroute to the site. Plant is stable at 55 % reactor power following a down-power maneuver from 100% reactor power with all safety related equipment operable.


* * * UPDATE FROM CARYLIN MCCOY TO JOHN KNOKE AT 0102 EST ON 01/09/11 * * *

At 0043 Palisades terminated from their Unusual Event for 'Hazards and Other Conditions Affecting Plant Safety'. The faulted bus has been isolated, and licensee started their investigation into the cause of this incident. The licensee has tagged out and racked out the breaker, and has isolated the startup power to the 'F' bus. The associated Startup Transformer has also been isolated. The 'F' bus and associated Startup Transformer will not be energized until the situation is better understood, and repaired if necessary. Power level will be maintained at 53% due to the loss of associated equipment supporting one cooling tower. The licensee is in a 72 hour LCO.

The licensee has notified the NRC Resident Inspector. Notified the R3DO (Christine Lipa), IRD MOC (Bill Gott), NRR EO (Mike Cheok), DHS (Gates), FEMA (Casto)

To top of page
Power Reactor Event Number: 46525
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIMOTHY THOMPSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/08/2011
Notification Time: 15:29 [ET]
Event Date: 01/08/2011
Event Time: 14:38 [EST]
Last Update Date: 01/09/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
STEVEN VIAS (R2DO)

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 DUE TO PLANNED MAINTENANCE

"A condition is being reported per Technical Requirements Manual 13.13.1, Emergency Response Facilities, Action B.2. The functionality of the Technical Support Center (TSC) has been lost due to planned maintenance being performed on the 480V Motor Control Switchgear ANBL. Alternate facilities are available to provide emergency response functions and actions are proceeding to return the TSC to functional status with a high priority. A 10CFR50.54(q) evaluation has been performed for this planned maintenance activity. Normal power is still available but may be lost during a loss of offsite power. Contingency plans are in place to restore backup power if necessary. Expected return to service is Tuesday, January 11, 2011.

The NRC Resident Inspector has been notified.


* * * UPDATE FROM CARL GRANT TO JOE O'HARA AT 1505 ON 1/9/11 * * *

TSC returned to service at 1430 EST. Normal power supply is aligned and the temporary modifications have been removed.

The NRC Resident Inspector has been notified. Notified R2DO(Vias)

To top of page
Power Reactor Event Number: 46526
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: BOB MEIXELL
HQ OPS Officer: JOE O'HARA
Notification Date: 01/08/2011
Notification Time: 17:06 [ET]
Event Date: 01/08/2011
Event Time: 14:00 [EST]
Last Update Date: 01/08/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
STEVEN VIAS (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 0 Hot Standby

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO PARTIAL CLOSURE OF LETDOWN LINE ISOLATION VALVE 1HP-5

"At 1400 on Saturday, January 8, 2011, Oconee Unit 1 initiated a shutdown required by Technical Specification (TS) 3.6.3, 'Containment Isolation Valves.' Unit 1 experienced an unexpected partial closure of letdown line containment isolation valve 1HP-5 during Engineered Safeguards (ES) Channel 2 on-line testing. 1HP-5 reopened when power was restored. Unit 1 entered TS 3.6.3, CONDITION A at 0148 on 1/8/11. Unit 1 entered TS 3.6.3, CONDITION D at 0548 on 1/8/11. TS 3.6.3, CONDITION D requires Unit 1 to be in mode 3 by 1748 on 1/8/11, and in mode 5 by 1748 on 1/9/11. An updated notification will be provided if the TS CONDITION is exited prior to Unit 1 reaching mode 5. An investigation is in progress to determine the cause of the unexpected partial closure of 1HP-5."

All safety systems required for safe shutdown are operable and the electrical lineup is normal. The licensee is evaluating any potential impact of this event on Unit 2 and Unit 3. There is no estimate for the completion of the investigation at this time.

The NRC Resident Inspector has been notified.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012