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Event Notification Report for December 14, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/13/2010 - 12/14/2010

** EVENT NUMBERS **


46468 46475 46477

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General Information or Other Event Number: 46468
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: THE SCHEMMER ASSOCIATES INC
Region: 4
City: LINCOLN State: NE
County:
License #: 01-124-01
Agreement: Y
Docket:
NRC Notified By: JIM DEFRAIN
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/09/2010
Notification Time: 09:33 [ET]
Event Date: 12/08/2010
Event Time: 10:45 [CST]
Last Update Date: 12/09/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL HAY (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - DAMAGED NUCLEAR MOISTURE/DENSITY GAUGE

The following report was received via facsimile:

"Event date and time: December 8, 2010 - Time: 10:45 am

"Event location: 91st & Heritage Lake Drive, Lincoln, Nebraska, 685

"Event description: The licensee possesses a Humboldt Scientific, Inc. Model 5001-EZ 122 Nuclear Moisture/Density Gauge Serial Number 2027. On December 8, 2010, the gauge was being used at a construction site just east of Lincoln, NE. The operator of the gauge had started a test when he was distracted by another worker asking questions. During that time a front end loader backed into the gauge and broke the stationary guide rod. No other damage was observed to the gauge. The area was secured and radiation surveys as well as a leak test were performed. No unusual readings were observed. The source rod was secured in to safe position in the gauge housing and the gauge was place in the transport case for return to the licensee's office. No personnel were exposed to radiation during this event."

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Power Reactor Event Number: 46475
Facility: POINT BEACH
Region: 3 State: WI
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: KARL COSSEY
HQ OPS Officer: VINCE KLCO
Notification Date: 12/13/2010
Notification Time: 15:07 [ET]
Event Date: 12/13/2010
Event Time: 12:10 [CST]
Last Update Date: 12/13/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
LAURA KOZAK (R3DO)
JANE MARSHALL (IRD)
MELANIE GALLOWAY (NRR)

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

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO NOT MEETING ROD GROUP ALLIGNMENT LIMITS

"On 12/13/10 at 1210 CST a Technical Specification (TS) required shutdown was initiated on Unit 2. TS Limiting Condition for Operation (LCO) 3.1.4, Rod Group Alignment Limits, was not met as a result of Surveillance Requirement (SR) 3.1.4.2 not being met. TS Action Condition (TSAC) 3.1.4.A was entered which requires the shutdown margin to be within the limits of the Core Operating Limits Report (COLR) or boration be initiated to restore shutdown margin to within the limits within one hour and that the reactor to be in MODE 3 within 6 hours. Shutdown margin has been verified to be within the limits specified in the COLR and a reactor shutdown has been initiated.

"On 12/10/10 at 1350 [CST], during performance of Technical Specification surveillance procedure TS-06 Rod Exercise Test, rod control urgent and non-urgent failure alarms occurred while stepping Control Bank B rods out. These alarms were verified locally in the Unit 2 rod drive room. On 12/10/10 at 2212 [CST], the test recommenced and control bank B was stepped out one step as procedurally required with no alarms. When control bank B was subsequently stepped inward one step, both rod control urgent and non-urgent failure alarms were received. Both of the times that Control Bank B rods failed to move, the movable gripper coil power supply fuse blew for control rod F-6. On 12/12/10 at 2143 CST, the surveillance procedure for Control Banks A, C, and D and Shutdown Banks A and B were completed satisfactorily, however, the failure of the Control Bank B rods to step in correctly resulted in the inability to satisfy SR 3.1.4.2, and entry into TSAC 3.1.4.A being required. During continuation of the surveillance on 12/12/10, it was not recognized that troubleshooting and repairs could not be conducted satisfactorily prior to the expiration of the surveillance interval. Therefore, a TS-required shutdown in accordance was not initiated.

"The likely cause of the failure is a damaged cable in the movable gripper circuitry for control rod F6. Troubleshooting is continuing and a repair plan has been developed.

"The NRC Senior Resident Inspector and Region III have been notified."

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Power Reactor Event Number: 46477
Facility: COOK
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BUD HINCKLEY
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/14/2010
Notification Time: 02:02 [ET]
Event Date: 12/13/2010
Event Time: 21:19 [EST]
Last Update Date: 12/14/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
LAURA KOZAK (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 49 Power Operation

Event Text

MANUAL ACTUATION OF AUXILIARY FEEDWATER SYSTEM IN RESPONSE TO LOSS OF ONE MAIN FEEDWATER PUMP

"At 2119 EST on December 13, 2010, operators manually started all Auxiliary Feedwater (AFW) pumps in response to a loss of the Unit 1 East Main Feedwater Pump.

"Operators were responding to decreasing condenser vacuum on the East Main Feedwater Pump and reducing turbine load when the East Main Feedwater Pump was manually tripped at approximately 21 inches of vacuum Hg. Operators entered the abnormal operating procedure for Loss of One Main Feedwater Pump, which directs starting all three AFW pumps.

"Plant power was stabilized at approximately 49%.

"The licensee will be notifying the NRC Senior Resident Inspector.

"This notification is being made in accordance with 10CFR50.72(b)(3)(iv)(A) due to the valid actuation of the AFW system in response to equipment failure."

No maintenance was in progress, and the cause of the decreasing condenser vacuum in the MFP was due to debris in the traveling water screen.

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