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Event Notification Report for February 23, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/20/2009 - 02/23/2009

** EVENT NUMBERS **


44780 44860 44861 44866 44869

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General Information or Other Event Number: 44780
Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: JANX INTEGRITY GROUP
Region: 4
City: HATTIESBURG State: MS
County:
License #: 21-16560-01
Agreement: Y
Docket:
NRC Notified By: JAYSON MOAK
HQ OPS Officer: JASON KOZAL
Notification Date: 01/16/2009
Notification Time: 13:16 [ET]
Event Date: 01/15/2009
Event Time: [CST]
Last Update Date: 02/20/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RYAN LANTZ (R4)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE - FIRE INVOLVING RADIOGRAPHY CAMERA

The following was provided by the State via e-mail:

"On 1-15-09, DRH was notified by the Forrest County ERC that JANX Integrity Group had an accident with one of their darkroom trucks off Hwy 59 N., in Hattiesburg, MS. The driver for JANX struck a tree off the side of the interstate causing the vehicle to catch fire. The driver then left the scene of the accident. The radiography camera, SPEC-150, SN 150 (Ir-192, 65 Ci), was not discovered until the fire department saw a 'Caution Radiation Area' sign in the bed of the darkroom truck after extinguishing the fire. Surveys were conducted by firefighter personnel for their safety and to pinpoint the location of the radioactive device in the darkroom truck. The Forrest County ERC contacted an industrial radiography company and MS licensee located in Hattiesburg to take possession of the camera and secure it in their storage vault. The radiography camera was retrieved off the darkroom truck and out of its locked storage box by the MS licensee. The radiography camera was surveyed by the MS licensee before being transported to their storage facility. On 1-15-09, JANX retrieved the radiography camera out of storage for transport back to the manufacturer to assess the damage.

"DRH took surveys of the darkroom truck and the radiography camera. Radiation measurements were as follows: 24 mR/hr at the surface of the camera; 4 mR/hr at 6 inches from the camera; levels were background at the vehicle. DRH coordinated the receipt of radiography camera between JANX and a MS licensee for delivery back to the manufacturer."

MS report number - MS 09001

* * * UPDATE FROM JAYSON MOAK TO HOWIE CROUCH AT 1739 ON 1/23/09 * * *

The following was provided by the State via e-mail:

"On 1-15-09, swipes were taken on the camera and revealed no removable contamination. Leak test results for the source and DU shielding were received from SPEC on 1-23-09 and also revealed no removable contamination."

Notified FSME EO (Chang) and R4DO (Farnholtz).


* * * UPDATE FROM JAYSON MOAK (VIA EMAIL) TO JASON KOZAL AT 1232 ON 1/28/09 * * *

The following was provided by the State via e-mail:

"On 1-28-09, DRH received the SPEC - 150, Exposure Device S/N 150 Final Inspection Certificate from SPEC. The camera met the requirements contained in 10 CFR 34.20, ANSI N432 1980, USA/9263/B(U)-96 and SPEC's QA Program approval number 102."

Notified FSME EO (White) and R4DO (Cain).


* * * UPDATE FROM JAYSON MOAK (VIA EMAIL) TO JOHN KNOKE AT 1718 ON 02/20/09 * * *

"Source was Ir-192, 65 Ci, S/N PJ1606, Source Model G-60."

Notified FSME EO (Vontill) and R4DO (Powers).

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Power Reactor Event Number: 44860
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: JOE BENNETT
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/18/2009
Notification Time: 08:03 [ET]
Event Date: 02/18/2009
Event Time: 03:51 [CST]
Last Update Date: 02/21/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CHARLIE PAYNE (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

TURBINE TRIP DUE TO POWER LOAD UNBALANCE SIGNAL ON MAIN GENERATOR RESULTING IN REACTOR SCRAM

"At 0351 on 2/18/09, the Unit 1 reactor automatically scrammed due to actuation of the Reactor Protection System from a turbine trip due to a power load unbalance signal on the main generator. The cause of the power load unbalance signal was due to a generator neutral over voltage condition of which the cause is unknown and the investigation is continuing. All systems responded as expected to the turbine trip. One Safety Relief Valve (SRV) opened due to the reactor pressure transient, and then reactor pressure was automatically controlled by the Main Turbine Bypass valves. No Emergency Core Cooling System (ECCS), or Reactor Core Isolation Cooling (RCIC) reactor water level initiation set points were reached, all expected containment isolation and initiation signals were received, and reactor water level is being automatically controlled by the feedwater system.

"This event is reportable within 4 hours per 10CFR 50.72(b)(2)(iv)(B) for any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. It is also reportable within 8 hours per 10CFR 50.72(b)(3)(iv)(A) and requires an LER within 60 days per 10CFR 50.73(a)(2)(iv)(A).

"The NRC Resident Inspector has been notified."

All control rods fully inserted. The plant electrical system is in normal shut down alignment. No Diesel Generators started as a result of this event. There was no ECCS injection to the reactor vessel.



* * * * UPDATE FROM RICKY GIVENS TO JOHN KNOKE AT 1828 0N 02/21/09 * * * *

"Review of available data indicates that no Main Steam safety/relief valves (MSRVs) opened in response to the Unit 1 reactor scram on 02/18/2009. There were no indications of an open MSRV on any discharge tailpipe thermocouple or acoustic monitor. Initial indications of the discharge tailpipe thermocouples for MSRV (1-PCV-1-30) did indicate a slight increase in temperature (approximately 36 degrees F) as reactor pressure decreased, which resulted in the initial assumption of an SRV opening. However, this behavior is a classical indication of slight main seat leakage and system engineering believes this seat leakage is what the post scram data indicates. Utilizing multiple reactor pressure instrumentation responses, the peak reactor pressure was determined to be approximately 1130 psig which is 15 psi below MSRV 1-PCV-1-30 setpoint. Additionally, the rise in tailpipe temperature did not coincide with the peak pressure but was after pressure had lowered. Based upon a thorough review of this data and a better understanding of the timing of the temperature rise, it is now believed that the MSRVs performed as designed during the reactor pressure transient event. The initial determination that concluded an MSRV opened will be further investigated within the corrective action program; reference PER 164114."

The licensee has notified the NRC Resident Inspector. Notified R2 DO (Charlie Payne)

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General Information or Other Event Number: 44861
Rep Org: ALABAMA RADIATION CONTROL
Licensee: QORE, INC.
Region: 1
City: BIRMINGHAM State: AL
County:
License #: 708
Agreement: Y
Docket:
NRC Notified By: DAVID WALTER
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/18/2009
Notification Time: 16:45 [ET]
Event Date: 02/18/2009
Event Time: 13:45 [CST]
Last Update Date: 02/18/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
TODD JACKSON (R1)
BILL VONTILL (FSME)
ILTAB via email ()

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

Event Text

AGREEMENT STATE REPORT INVOLVING A STOLEN MOISTURE DENSITY GAUGE

The following report was received from the State of Alabama via fax:

"At 1:45 PM CST the Alabama Office of Radiation Control received a call from Qore, Inc. in Birmingham, Alabama (Alabama license No. 708). They reported that a CPN Model MC1DR (S/N MD30406940) had been stolen from the back of one of their trucks. The licensee indicated that the device case had been secured with 2 separate locked chains, but that they had been cut. The device had been stolen sometime during the morning or early afternoon while the truck was parked at an employees residence in Center Point, Alabama. The licensee is filing a report with local law enforcement. They are also sending an information flyer to area pawn shops, and will issue a message to the media regarding the device, and offer a reward for information leading to the recovery of the device.

"This information is accurate as of 3:20 PM CST. Further information, including methods to prevent a recurrence, is forthcoming from the licensee."

Alabama Incident # 09-08

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.

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Other Nuclear Material Event Number: 44866
Rep Org: EDAX, INC
Licensee: EDAX, INC
Region: 1
City: MAHWAH State: NJ
County:
License #: 29-17369-02
Agreement: N
Docket:
NRC Notified By: BOB WESTERDALE
HQ OPS Officer: JOHN KNOKE
Notification Date: 02/20/2009
Notification Time: 14:25 [ET]
Event Date: 02/18/2009
Event Time: [EST]
Last Update Date: 02/20/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
TODD JACKSON (R1)
ANGELA McINTOSH (FSME)
ILTAB via email ()

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

Event Text

LOST CALIBRATION SEALED SOURCE OF FE-55

A 2 milliCurie sealed source of Iron-55, used for calibration, was misplaced and believed to be lost. The source (Mfg # C1-375) was stored in a pig in a locked cabinet in a secure lab. Inventory is taken daily, and the last time it was seen was 2/17/09. Licensee believes that a lab technician was working with the source and it accidently rolled off the desk into a trash container. Licensee has searched every possible area where it may have gone. The sealed source was in a plastic tube, and therefore the exposure to personnel is just above background.


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: 44869
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL RICHARDSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/23/2009
Notification Time: 05:46 [ET]
Event Date: 02/23/2009
Event Time: 04:06 [EST]
Last Update Date: 02/23/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CHARLIE PAYNE (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 87 Power Operation

Event Text

INADVERTENT ACTUATION OF THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP

"The Turbine Driven Auxiliary/Emergency Feedwater pump auto started when power was lost to the steam admittance solenoid valves. Additional feedwater to the steam generators caused an increase in power an turbine load was manually decreased. At no time were any power limits exceeded. Power level in currently at 87% and stable."

Maximum power, as determined by core delta temperatures, did not exceed 100%.

The licensee has notified the NRC Resident Inspector.

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