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Event Notification Report for June 3, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/02/2009 - 06/03/2009

** EVENT NUMBERS **


45101 45102 45107 45111 45112

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General Information or Other Event Number: 45101
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: DOUGLAS COUNTY HEALTH DEPARTMENT
Region: 4
City: OMAHA State: NE
County: DOUGLAS
License #: 01-45-01
Agreement: Y
Docket:
NRC Notified By: JIM DEFRAIN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/28/2009
Notification Time: 18:10 [ET]
Event Date: 05/26/2009
Event Time: 11:30 [CDT]
Last Update Date: 05/28/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL SHANNON (R4DO)
MARK THAGGARD (FSME)

Event Text

AGREEMENT STATE REPORT - DAMAGED X-RAY FLOURESCENCE DEVICE

The following information was obtained from the State of Nebraska via facsimile:

"The Douglas County Health Department, a Nebraska licensee (license no. 01-45-01), reported that a Radiation Monitoring Devices, Inc. (RMD) Model LPA-1 portable x-ray fluorescence [XRF] device had been damaged on May 27, 2009. The XRF contained 12 millicuries of Cobalt-57. An authorized user left the XRF on a window sill and the XRF fell approximately eight feet to the floor. The XRF case was cracked in several pieces, but the integrity of the sealed source shield was not damaged. Radiation dose readings of the damaged XRF were within the expected range [for this device]. No individuals of the public or occupational workers were exposed as a result of this event. The licensee was able to return the XRF to its shipping container [which was placed in the] licensee's secured storage facility. The licensee was instructed to contact the manufacturer, perform a leak test and contact [the State of Nebraska] prior to shipping the XRF back to the manufacturer."

Nebraska Event Report ID: NE-09-00X

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General Information or Other Event Number: 45102
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GRUBB & ELLIS
Region: 4
City: ROSEVILLE State: CA
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: EUGENE FORRER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/28/2009
Notification Time: 18:55 [ET]
Event Date: 05/28/2009
Event Time: [PDT]
Last Update Date: 05/28/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL SHANNON (R4DO)
MARK THAGGARD (FSME)
ILTAB via email ()
Mexico via email ()

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

Event Text

CALIFORNIA AGREEMENT STATE REPORT - STOLEN TRITIUM EXIT SIGN

The following information was obtained from the licensee via email:

"[The licensee] notified the [California Radiation Health Bureau] that a tritium exit sign had been stolen from a Roseville property they manage. The sign was an SRB Technologies Model 171-10-wh-s-gn."

SRB Technologies Tritium exit signs typically contain 10-20 Ci of tritium.

California Incident number: 5010-052809

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: 45107
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WILLIAM BAKER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/31/2009
Notification Time: 17:39 [ET]
Event Date: 05/31/2009
Event Time: 13:30 [CDT]
Last Update Date: 06/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
GEORGE HOPPER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

DEGRADED CONDITION DUE TO DISCOVERY OF PRESSURE BOUNDARY LEAKAGE

"During the performance of 2-SI-3.3.1.A ASME Section XI System Leakage Test of the Reactor Pressure Vessel and Associated Piping (ASME Section III, Class 1 and 2), a pressure boundary leak was identified on the RHR Shutdown Cooling Root Valve (2-SHV-074-0049) at a weld between the valve body and a 3/4 inch schedule 160 pipe nipple. The pipe nipple is a 6 inch long capped valve leak off line. This valve and line are ASME Code Class 1 equivalent components located between the A recirculation piping and the inboard Shutdown Cooling isolation valve (2-FCV-074-0048). This condition caused entry into Technical Requirements Manual (TRM) 3.4.3 - Structural Integrity - Condition A - in which the applicability is at all times and the required action is to immediately restore the structural integrity of the affected component to within its limit or maintain the reactor in MODE 4 or 5 or the reactor coolant system less than 50?F above the minimum temperature required by NDT considerations, until each indication of a defect has been investigated and evaluated. The plant is currently in MODE 4 with Shutdown Cooling in service.

"This event is reportable within 8 hours under 10CFR50.72 (b)(3)(ii)(A), 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.' This event is also a reportable within 60 days under 10CFR50.73(a)(2)(ii)(A), 'Any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.' The NRC Resident Inspector has been notified. This condition has been documented in the BFN [Browns Ferry Nuclear] Corrective Action program as PER# 172551.

"Unit 1 and 3 remain at 100% power and are not affected by this event."

* * * UPDATE FROM W. BAKER TO P. SNYDER AT 1839 ON 6/2/09 * * *

"Additional review of available data and inspection results revealed that the original identification of a 6 inch long inch diameter schedule 160 pipe nipple was part of the original design of the 2-SHV-074-0049. This connection to the valve body was subsequently modified by a design change documented in DCN S17640C and installed in 1992 by Work Order 92-49415-00 as a 2.55 inch long plug with a 0.800 inch tapered end, fabricated from bar stock to fit the existing valve socket weld cavity. All other details described in the original (REV 0) event notification remain as stated. The BFN Corrective Action PER# 172551 will be amended to include this additional information.

"The NRC [Resident Inspector] has been notified of this event notification revision."

Notified R2DO (Lesser).

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Power Reactor Event Number: 45111
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: BRUCE HUGO
HQ OPS Officer: JOHN KNOKE
Notification Date: 06/02/2009
Notification Time: 00:54 [ET]
Event Date: 06/01/2009
Event Time: 16:50 [PDT]
Last Update Date: 06/02/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RYAN LANTZ (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

LOSS OF TSC AIR CONDITIONING UNIT COMPRESSOR

"On 5/20/09, the Technical Support Center (TSC) air conditioning unit compressor failed to restart following refueling outage electrical bus maintenance. On 5/31/09, the compressor was discovered to be shorted to ground. The short renders the air conditioning unit nonfunctional and at 1650 on 6/1/09 the nonfunctional air conditioner was determined to adversely affect TSC habitability based on meteorological conditions. TSC filtration capabilities are not affected by this problem. The nonfunctional air conditioner leaves the TSC in a degraded state; however, the TSC is currently habitable and available for service. Should the TSC need to be activated, habitability of the TSC will be monitored per existing plant procedures. Relocation of the TSC to an alternate location would be performed in accordance with station procedures as necessary to ensure continued TSC functionality. The control room and all other emergency response facilities are unaffected by the TSC chiller outage. Work instructions to repair the chiller are in review and work is expected to commence on June 2nd and proceed with high priority. A follow-up notification will be made when the TSC chiller has been restored. This event is being reported as a loss of emergency preparedness capabilities in accordance with 10 CFR 50.72(b)(3)(xiii). The NRC resident has been notified."

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Power Reactor Event Number: 45112
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES DILLIS
HQ OPS Officer: JOHN KNOKE
Notification Date: 06/02/2009
Notification Time: 04:50 [ET]
Event Date: 06/02/2009
Event Time: 01:22 [PDT]
Last Update Date: 06/02/2009
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
RYAN LANTZ (R4DO)
ERIC LEEDS (NRR)
BRIAN MCDERMOTT (NSIR)
ELMO COLLINS (RA)
JEFF GRANT (NSIR)
LINDA HOWELL (R4)
MIKE INZER (DHS)
HEYMAN (FEMA)

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

UNUSUAL EVENT - SMOKE ALARM IN PROTECTED AREA LASTING GREATER THAN 15 MINUTES

Licensee declared an Unusual Event due to a possible fire in the protected area inside containment. The smoke alarm could not be verified before 15 minutes, therefore licensee entered into EAL HU 2.1. Seventeen smoke detectors located inside the containment feed into this alarm, and it is unknown if more than one smoke detector initiated the alarm. The local fire department was not requested to respond to the site. Licensee is sending personnel inside containment to investigate whether or not this alarm was spurious. There is no indication of smoke or an increase in temperature in or around the containment. There was no radiological release to the environment.


* * * UPDATE FROM JAMES DILLIS TO JOHN KNOKE AT 0618 EDT ON 06/02/09 * * *

Licensee completed their investigation inside containment and determined there was no fire. Licensee terminated the Unusual Event at 0618 EDT.

Licensee has notified the NRC Resident Inspector. Notified R4DO (Ryan Lantz), IRD MOC (Jeff Grant), NRREO (M. Evans), DHS (Inzer), FEMA (D. Barden)

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