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Event Notification Report for October 4, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/03/2006 - 10/04/2006

** EVENT NUMBERS **


42868 42872 42873

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General Information or Other Event Number: 42868
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: SEWERAGE & WATER BOARD OF NEW ORLEANS
Region: 4
City: NEW ORLEANS State: LA
County:
License #: LA-3618-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/29/2006
Notification Time: 15:29 [ET]
Event Date: 06/01/2006
Event Time: [CDT]
Last Update Date: 09/29/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ZACH DUNHAM (R4)
SANDRA WASTLER (NMSS)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT INVOLVING A LOST GAS CHROMATOGRAPH

The following information was received via fax:

"During an inspection of the Sewerage and Water Board of New Orleans it was discovered that a Hewlett-Packard Gas Chromatograph, model number 18713A, with 15 mCi of Ni-63 foil could not be located. According to the inventory, it was placed into storage in 1995, but it could not be inventoried in December 2005 due to Hurricane damage to the storage facility. The facility tried to locate the GC around June 2006, but could not locate the unit. The facility failed to notify the Louisiana Department of Environmental Quality of the missing GC and has been cited. This incident is under investigation. The NRC will be notified of any additional information once it is received.

"Event Report ID No.: LA060018"

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source

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Power Reactor Event Number: 42872
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By:
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/03/2006
Notification Time: 14:51 [ET]
Event Date: 10/03/2006
Event Time: [EDT]
Last Update Date: 10/03/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
PAUL KROHN (R1)

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 ISSUE - 24 HOUR NOTIFICATION MISSED

Notification was to report that on 9/27/06 at 1418 hours a company employee self identified the use of a controlled substance. Access was immediately suspended; employee was mandatory referred to EAP and will require admission into the follow-up testing program. The employee is not involved in any safety related activities and is not licensed.

The NRC Resident Inspector was notified of this event by the licensee.

Contact the Headquarters Operations Officer for additional details.

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Power Reactor Event Number: 42873
Facility: CATAWBA
Region: 2 State: SC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOMAS GARRISON
HQ OPS Officer: JASON KOZAL
Notification Date: 10/03/2006
Notification Time: 15:40 [ET]
Event Date: 08/08/2006
Event Time: 16:17 [EDT]
Last Update Date: 10/03/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
THOMAS DECKER (R2)

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

60 DAY REPORT - INVALID ACTUATION OF AUXILIARY FEED PUMP 2B

"This 60-day report as allowed by 10 CFR 50.73 (a)(2)(iv)(A) to describe an invalid actuation of a specified system, specifically the Auxiliary Feedwater System (AFW). This event involved an invalid actuation of the Motor Driven Auxiliary Feedwater pump 2B during routine Unit 2 Auxiliary Safeguards Testing on 8/8/06. The system was properly aligned and did inject water into Steam Generators 2C and 2D as designed to perform a complete actuation of AFW pump 2B.

"The motor driven auxiliary feedwater pumps will automatically start and provide the minimum required feedwater flow within one minute following any of these conditions:

"1. Two out of four low-low level alarms in any one of the four steam generators.

"2. Loss of both main feedwater pumps

"3. Initiation of safety injection signal

"4. Loss of station normal auxiliary electric power

"5. AMSAC signal

"Since none of the five auto-start parameters were met at the time of the system actuation the signal was determined to be invalid.

"Engineering reviewed the CA Pump Start circuit to determine which equipment failures could cause the switchgear breaker for the AFW Pump 2B to close and start the pump. These included reviewing sequencer start signals, manual pushbuttons, and associated contacts and breakers. The failure of the fluke meter used during the testing was considered, also. In addition, the Operations Test Group performed an analysis of the human performance aspects of this testing. Based on these investigations potential equipment failures have been ruled out and based on the correspondence in time with when the inadvertent start occurred and when the meter reading was taken, it is believed that the inadvertent start is due to an anomaly with the Fluke 189 meter or issues when taking the measurement. The measurement is taken across an energized circuit, which can be susceptible to inadvertent actuations. The test procedure has been revised to open links on the circuit to prevent inadvertent operation."

The licensee notified the NRC Resident Inspector.

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