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Event Notification Report for February 16, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/12/2010 - 02/16/2010

** EVENT NUMBERS **


45691 45694 45696 45697 45698 45699 45700

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General Information or Other Event Number: 45691
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SOUTHERN SERVICES INC.
Region: 4
City: LAKE JACKSON State: TX
County:
License #: 05270
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 02/09/2010
Notification Time: 10:54 [ET]
Event Date: 02/08/2010
Event Time: 12:30 [CST]
Last Update Date: 02/09/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WILLIAM JONES (R4DO)
MARK SHAFFER (FSME)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA SOURCE FAILED TO FULLY RETRACT

"On February 9, 2010, the Agency [Texas Department of Health] was notified by the licensee that while performing radiography with a 22 curie Iridium (Ir)-192 source, the source could not be retracted into the camera. The device is an Amersham 660B camera. The radiographer noted that when he returned the source to the camera, the auto locking mechanism failed to activate. The radiographer then cranked the source back out and tried again to locked the source in the camera. The locking mechanism failed to lock. The source drive cable was left in the position where the source should be shielded. The radiographer performed a dose rate survey on the guide tube. He found the dose rates near the end of the guide tube were elevated. He contacted his Radiation Safety Officer. An individual listed on the license to perform source retrieval went to the location and retrieved the source. No over exposures were reported. An inspection of the source pig tail and drive cable found that the connection of the drive cable to the source pig tail failed because the ball on the drive cable side of the connection had broken off from the drive cable."

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General Information or Other Event Number: 45694
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: C.Y. GEOTECH, INC.
Region: 4
City: CHATSWORTH State: CA
County:
License #: 6617-19
Agreement: Y
Docket:
NRC Notified By: DONELLE KRAJEWSKI
HQ OPS Officer: DONG HWA PARK
Notification Date: 02/11/2010
Notification Time: 20:36 [ET]
Event Date: 02/11/2010
Event Time: 13:10 [PST]
Last Update Date: 02/11/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WILLIAM JONES (R4DO)
MARK SHAFFER (FSME)

Event Text

AGREEMENT STATE REPORT - DAMAGED NUCLEAR DENSITY GAUGE

The following report was received via e-mail:

"At 1310 [PST] on February 11, 2010, the C.Y. Geotech Radiation Safety Officer [RSO] reported that one of the nuclear density gauges (CPN, MC-1DRP, MD90905316 containing 10 milliCurie of Cesium 137 and 50 milliCurie of Americium-241:Be) had been run over by a truck at a construction site. Los Angeles County Radiation Management responded to the scene and found that although the source rod was broken and the plastic case was broken into pieces, the Cesium 137 and the Americium-241:Be sources were still in the shielded body of the device and were intact. There was no contamination. The highest dose rate on the body of the device housing the sources was 9 mR/hr and at one foot was 0.9 mR/hr. The gauge was placed into 2 plastic bags and was placed into the transportation case. The licensee will deliver the gauge to Maurer Technical Services (a licensed CPN representative) who will then ship the gauge to CPN for disposal. [The RSO] reported the gauge user walked about 10 feet away from the gauge to report his test results to a job supervisor and this is when the gauge was run over. The RHB-Brea office will cite the licensee for failure to maintain adequate control over the gauge. The licensee has been instructed they need to provide [California Radiation Control Program] with a report within 30 days as required by regulation. The licensee states they will retrain all of the gauge users regarding the control of the gauge to avoid a similar incident in the future.

"Event Location: 951 25th Street, Santa Monica, CA"

California Event Number: 021110

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General Information or Other Event Number: 45696
Rep Org: UNITED CONTROLS INTERNATIONAL
Licensee: THOMAS AND BETTS
Region: 1
City: TUCKER State: GA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT B. HALE
HQ OPS Officer: VINCE KLCO
Notification Date: 02/12/2010
Notification Time: 12:28 [ET]
Event Date: 01/06/2010
Event Time: [EST]
Last Update Date: 02/12/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
RAY POWELL (R1DO)
PART 21 GROUP (EMAI)

Event Text

INSTALLATION OF INCORRECT TRANSFORMER ON A CONTROL BOARD FOR A BATTERY CHARGER

On January 6, 2010, Thomas & Betts (TNB) informed United Controls International (UCI) that TNB's sub-contractor (RBB Systems) had installed the incorrect transformer on a sub-component (control board) of a Cyberex battery charger.

During a review of the Bill of Material (BOM) and assembly documentation for the control board by TNB, it was discovered that the incorrect transformer was being installed on the board. The control board affected is designed for systems with a 120 VAC primary input voltage. The incorrect transformer installed is designed for systems with a 208 VAC primary input voltage.

Subsequent testing and risk assessment performed by TNB's sub-contractor, RBB Systems, found that under nominal input voltage, the control card operated marginally. Under low input voltage, the card could fail to operate properly, which could cause a failure of its parent component, the battery charger.

Per TNB, the only sale on record of the Cyberex battery charger is of eight units sold to Philadelphia Electric Company (now part of Exelon-Peach Bottom Nuclear Power Station) in 1993, which are designed for 120 VAC primary input voltage to the control board.

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General Information or Other Event Number: 45697
Rep Org: WESTINGHOUSE ELECTRIC COMPANY
Licensee: WESTINGHOUSE ELECTRIC COMPANY
Region: 1
City: PITTSBURGH State: PA
County: ALLEGHENY
License #:
Agreement: Y
Docket:
NRC Notified By: J.A. GRESHAM
HQ OPS Officer: PETE SNYDER
Notification Date: 02/12/2010
Notification Time: 13:40 [ET]
Event Date: 02/12/2010
Event Time: [EST]
Last Update Date: 02/12/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
RAY POWELL (R1DO)
ALAN BLAMEY (R2DO)
HIRONORI PETERSON (R3DO)
WILLIAM JONES (R4DO)
PART 21 GROUP (EMAI)

Event Text

INTERIM REPORT CONCERNING AN ISSUE IN SUMP BLOCKAGE GENERIC TESTS

Westinghouse is evaluating an identified inconsistency between test assumptions and the test rig configurations used for Generic Safety Issue (GSI) 191, "Experimental Studies of Loss-of-Coolant-Accident-Generated Debris Accumulation and Head Loss with Emphasis on the Effects of Calcium Silicate Insulation," NUREG/CR-6874, LA-UR-04-1227 testing. Specifically, this issue is related to jet impingement zone-of-influence (ZOI) tests and it applies to testing done for coatings and insulation.

Prior to discovery of the inconsistency, Westinghouse provided letters to the utilities to summarize the testing, analyze the test results, and propose acceptable ZOIs to support resolution of the ZOI aspect of GSI-191. The ZOI tests assumed the smallest diameter in the nozzle producing the jet to be at the nozzle. Westinghouse discovered however, that the inner diameter of an upstream component was smaller than the nozzle. This inconsistency may have resulted in undersized ZOIs being proposed in the letters.

Westinghouse has not yet concluded its determination as to whether there is a defect as defined by 10 CFR 21.

Westinghouse has been working with the Pressurized Water Reactors Owners Group and the NRC NRR Safety Issues Resolution Branch to resolve general test protocol issues and establish methods to evaluate the test results in terms of ZOIs.

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Power Reactor Event Number: 45698
Facility: COOK
Region: 3 State: MI
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRADDOCK LEWIS
HQ OPS Officer: JOE O'HARA
Notification Date: 02/15/2010
Notification Time: 08:58 [ET]
Event Date: 02/15/2010
Event Time: 09:30 [EST]
Last Update Date: 02/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HIRONORI PETERSON (R3DO)

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

UNAVAILABILITY OF EMERGENCY RESPONSE DATA SYSTEM (ERDS) DUE TO PLANT PROCESS COMPUTER (PPC) SCHEDULED MAINTENANCE

"At 0930 on Monday, February 15, 2010, the Cook Nuclear Plant (CNP) Unit 2 Plant Process Computer will be removed from service for scheduled maintenance for data backup and preventative maintenance which will take ERDS out of service to the NRC Operations Center. The scheduled maintenance will affect the Safety Parameter Display System (SPDS) and the Real Time Data Repository (RDR), PPC data to Emergency Response Facilities at CNP.

"The scheduled maintenance is expected to take up to 6 hours to complete.

"Compensatory measures exist within the CNP Emergency Response procedure to provide plant data via the Emergency Notification System to the NRC Operations Center until the ERDS can be returned to service.

"The licensee notified the NRC Resident Inspector 2/15/2010 at 8:45 a.m.

"This notification is being made in accordance with NUREG 1022 Revision 2 for CFR 50.72 (b)(3)(xiii) due any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system)."

The unit is expected to be maintained at 100% during the maintenance evolution. PPC trending and indication and rod position monitor will be out of service (OOS) while the PPC is OOS.


* * * UPDATE FROM BRAD LEWIS TO DONALD NORWOOD AT 1205 EST ON 2/15/2010 * * *

The DC Cook U-2 Plant Process Computer was returned to service and a fully operable and available status at 1144 EST on 2/15/2010. The licensee notified the NRC Resident Inspector.

Notified R3DO (Peterson) via E-mail.

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Power Reactor Event Number: 45699
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JOHN GOODBRED, JR.
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/15/2010
Notification Time: 15:28 [ET]
Event Date: 02/15/2010
Event Time: 12:05 [EST]
Last Update Date: 02/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
RAY POWELL (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
3 N Y 100 Power Operation 100 Power Operation

Event Text

FITNESS FOR DUTY EVENT - POSSESSION OF ALCOHOL INSIDE THE PROTECTED AREA

A non-licensed, non-supervisory employee was found in possession of alcohol inside the protected area. For-cause fitness-for-duty testing was conducted with negative results. The individual's unescorted access has been prohibited pending further investigation. Contact the Headquarters Operations Officer for additional details.

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Power Reactor Event Number: 45700
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: MARK HOFFMAN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/15/2010
Notification Time: 16:42 [ET]
Event Date: 02/15/2010
Event Time: 09:05 [EST]
Last Update Date: 02/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
HIRONORI PETERSON (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

FITNESS FOR DUTY EVENT - CONFIRMED POSITIVE FOR CONTROLLED SUBSTANCE USE

A non-licensed, contract supervisor had a confirmed positive for a controlled substance during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.

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