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Event Notification Report for May 13, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/12/2011 - 05/13/2011

** EVENT NUMBERS **


46834 46835 46836 46841 46844 46845 46846 46847

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Agreement State Event Number: 46834
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: METCO
Region: 4
City: HOUSTON State: TX
County:
License #: 03018
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/10/2011
Notification Time: 12:16 [ET]
Event Date: 04/19/2011
Event Time: [CDT]
Last Update Date: 05/10/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - STUCK RADIOGRAPHY CAMERA SOURCE

The following information was received via facsimile:

"On May 10, 2011, the Agency [Texas Department of Health] received written notification from a licensee that on April 19, 2011, at approximately 12:45 p.m. while performing radiographic operations on a tank, a radiographer found he was unable to retract a 58.6 Curie Iridium (Ir) -192 source into to a QSA Model 880D radiography camera. The radiographers working with the camera immediately repositioned the restricted area barricade to ensure that the barricade was set at less than 2 millirem per hour. The radiographers contacted their office and two source retrieval supervisors immediately proceeded to the jobsite. The Site Radiation Safety Officer was contacted and went to the location.

"The source retrieval team arrived at the secured barricaded area at 1:40 p.m. The radiographers maintained visual surveillance to ensure no members of the public had entered the area. The exposure device was adjacent to the tank's exterior; secured by a magnetic plate lifter, and located approximately 40 feet above ground. The exposure device was removed from the tank using a JLG lift and lowered to the ground. The guide tube was removed from the front of the camera and it was discovered that the source pigtail was sticking out of the front of the camera about one and a half inches. The source was manually retracted to the shielded position and locked in place. A radiation survey of the camera found the readings to be normal. No one exceeded any exposure limits and there was no exposure to any member of the general public. The camera was transported to the licensee's facility and inspected. The camera has been returned to the manufacturer for inspection and repair. The investigation into this event is on going. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident # I-8843.

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Agreement State Event Number: 46835
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TEAM INDUSTRIAL SERVICE INC.
Region: 4
City: ALVIN State: TX
County:
License #: L00087
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: PETE SNYDER
Notification Date: 05/10/2011
Notification Time: 12:43 [ET]
Event Date: 05/10/2011
Event Time: [CDT]
Last Update Date: 05/10/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WAYNE WALKER (R4DO)
GLENDA VILLAMAR (FSME)

Event Text

AGREEMENT STATE REPORT - STUCK RADIOGRAPHY CAMERA SOURCE

"On May 10, 2011, the Agency [Texas Department of Health] was notified by a licensee that while conducting radiography operations at a temporary job site, a pipe fell on the guide tube of a QSA Model 880D camera. The pipe damaged the guide tube preventing the radiographer from retracting the 34.1 curie Iridium (Ir) -192 source into the camera. The radiographer contacted his supervisor and a source recovery team was sent to the location.

"The recovery team was able to repair the guide tube enough to retract the source into the camera. The camera was returned to the licensee's facility for inspection. There was no exposure to a member of the general public and the highest exposure to a member of the recovery team was 28 millirem for the event.

"The investigation into this event is ongoing. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident No. I-8844

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Agreement State Event Number: 46836
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: GEORGIA PACIFIC
Region: 3
City: GREEN BAY State: WI
County:
License #: 009-1106-01
Agreement: Y
Docket:
NRC Notified By: MARK PAULSON
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/10/2011
Notification Time: 14:28 [ET]
Event Date: 05/05/2011
Event Time: [CDT]
Last Update Date: 05/10/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVE PASSEHL (R3DO)
GLENDA VILLAMAR (FSME)

Event Text

AGREEMENT STATE REPORT - STUCK FIXED GAUGE SHUTTER MECHANISM

The following information was received via facsimile:

"On May 5, 2011, the Licensee's Radiation Safety Officer reported via phone message that the shutter mechanism on an installed fix gauge failed to close. The gauge is an Ohmart model SHRM-3 with a 500 mCi Cesium-137 source. This malfunction was discovered during routine maintenance testing. No persons were exposed to radiation as a result of the malfunction. The Licensee has restricted access to the area and has scheduled repairs to be done by the manufacturer. DHS plans to perform a follow up inspection within the next 6 months."

Wisconsin Event Report # WI-110004.

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Power Reactor Event Number: 46841
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: VINCE KLCO
Notification Date: 05/11/2011
Notification Time: 15:50 [ET]
Event Date: 05/11/2011
Event Time: 09:00 [EDT]
Last Update Date: 05/12/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
EUGENE GUTHRIE (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 55 Power Operation 55 Power Operation

Event Text

TECHNICAL SUPPORT CENTER OUT OF SERVICE DUE TO VENTILATION ROLL FILTER MAINTENANCE

"During an Emergency Preparedness drill on May 11, 2011 the Hatch Nuclear Plant's Technical Support Center (TSC) HVAC [Heating, Ventilation and Air-Conditioning] system's Roll Filter Indicating Light on the 1X75B001 TSC Air Handling Unit was illuminated. The ARP [Alarm Response Procedure] response actions in the 73EP-EIP-016-0 indicated that the roll filter needed to be replaced. Reference [Hatch] Condition Report 2011106603.

"The TSC HVAC is being considered non-functional during the performance of this corrective work activity. If an emergency condition occurs during the time these work activities are being performed, which requires activation of the TSC, the contingency plan calls for utilization of the TSC, as long as radiological conditions allow for habitability of the facility. Procedure 73EP-EIP-063-0, Technical Support Center Activation, provides instructions to direct TSC management to the Control Room and TSC support personnel to the Simulator Building to continue TSC activities if it is necessary to relocate from the primary TSC so that TSC functions can be continued.

"This event is reportable per 10CFR50.72 (b)(3)(xiii) as described In NUREG-1022, Rev. 1 since this activity affects the functionality of the TSC emergency response facility for the duration of the evolution."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM KENNY HUNTER TO VINCE KLCO ON 5/12/2011 AT 1443 EDT * * *

The TSC has been returned to service following completion of filter maintenance.

The licensee notified the NRC Resident Inspector.

Notified the R2DO (Guthrie).

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Power Reactor Event Number: 46844
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DANNY WILLIAMSON
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 05/12/2011
Notification Time: 11:29 [ET]
Event Date: 03/20/2011
Event Time: 07:24 [CDT]
Last Update Date: 05/12/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
DAVID PROULX (R4DO)

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

"A" TRAIN REACTOR PROTECTION SYSTEM UNEXPECTEDLY DE-ENERGIZED RESULTING IN A HALF SCRAM SIGNAL

"On March 20, 2011, at approximately 7:24 a.m. CDT, the 'A' reactor protection system (RPS) bus was unexpectedly de-energized. Plant systems responded as designed, resulting in a half-scram signal and the actuation of the Division 1 primary containment isolation sub-system. The Division 1 primary containment isolation valves closed in several balance-of-plant systems. After confirming that no valid RPS trip signal had occurred, operators executed the appropriate procedures to return the affected systems to the proper configuration, and to reset the half-scram signal. Plant capacity was not affected by this event.

"This event is being reported in accordance with 10CFR50.73(a)(1) as an automatic actuation of the Division 1 primary containment isolation valves in multiple systems resulting from an invalid signal.

"Each of the two redundant distribution buses in the RPS system is normally powered by its own motor-generator (MG) set. The investigation of this event determined that the output breaker of the 'A' MG set had tripped open. The most likely cause for this trip was a malfunction of the over-voltage relay circuit card in the MG set. Although the troubleshooting was inconclusive, there apparently was a momentary transient in the output of the trip setpoint adjustment potentiometer on the card, likely caused by oxidation on the contacting surface between the wiper arm and the windings.

"The over-voltage relay card on the 'A' MG set was replaced, and the unit was restored to service. Preventative maintenance tasks are being revised to periodically cycle all potentiometers in the MG set control circuits to wipe oxidation from the windings."

The Licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 46845
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/12/2011
Notification Time: 11:47 [ET]
Event Date: 05/12/2011
Event Time: 08:15 [CDT]
Last Update Date: 05/12/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DAVID PROULX (R4DO)

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

Event Text

CONTRACT EMPLOYEE ADMITTED TO USING ILLEGAL SUBSTANCE

A contract employee was questioned and admitted to using an illegal substance. The employee's access to the plant been suspended. Local law enforcement has custody of the individual. The licensee has notified the NRC Resident Inspector.

Contact the Headquarters Operations Officer for additional details.

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Part 21 Event Number: 46846
Rep Org: ASCO VALVE
Licensee: ASCO VALVE
Region: 1
City: AIKEN State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT ARNONE
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/12/2011
Notification Time: 16:14 [ET]
Event Date: 05/12/2011
Event Time: [EDT]
Last Update Date: 05/12/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
ANNE DEFRANCISCO (R1DO)
EUGENE GUTHRIE (R2DO)
DAVE PASSEHL (R3DO)
DAVID PROULX (R4DO)
PART 21 GROUP ()

Event Text

U-RINGS FABRICATED WITH INCORRECT MATERIAL

"The following was received via facsimile:

"This report relates to two NP8344E series four-way solenoid valves found to be leaking through the exhaust port in both the energized and de-energized states.

"Background - On January 21, 2011, ASCO Valve, Inc. (ASCO) was notified by AREVA that a four-way solenoid valve NP8344A75E AC, (serial number F623557002-002) from the Dresden Station was leaking from the exhaust port in both the energized and de-energized states. AREVA reported that Exelon Labs had performed a Fourier Transform Infrared Spectroscopy (FTIR) analysis which indicated the piston U-ring exhibited properties consistent with a Nitrile compound instead of Teflon« coated Ethylene Propylene as required by the ASCO design drawing. The valve itself was not returned to ASCO. At ASCO's request, Exelon returned the U-ring on January 27, 2011. ASCO provided a letter to Dresden Station on February 3, 2011 (Reference A) maintaining the correct U-ring material was installed at the time of shipment and that no additional action was required.

"The second occurrence involved another four-way solenoid valve, NPK8344A072E DC, (serial number F337837-2), from PSEG Nuclear's Salem station, returned to ASCO on Service RMA 47113 on February 25, 2011. The valve was brought to ASCO where testing confirmed the valve was leaking through the exhaust ports in both the energized and de-energized states. The inspection of parts showed that the U-ring material had become brittle. If the U-ring becomes brittle, it may no longer perform its sealing function.

"ASCO Investigation Results - The above referenced valves were manufactured in 1992 (Dresden) and 1995 (Salem) respectively. It was determined that both valves used the same piston U-ring, part number 029043-024-S. This U-ring is common to both the 3/8" and 1/2" NPT valve constructions, A review of ASCO's incoming and dedication inspection records indicated that these U-rings were Teflon« coated Ethylene Propylene. The piston U-rings from the Salem and Dresden valves, along with a piston U-ring from ASCO's current stock, were sent to a third party laboratory for a FTIR analysis. The U-rings from both the Salem and Dresden valves were determined by the laboratory to be Nitrile. The U-ring from current stock was determined to be Teflon« coated Ethylene Propylene, as called for by the design drawings,

"Impact on Performance - The use of a Nitrile piston U-ring could potentially reduce the valve life and result in leakage through the exhaust port.

"Initial Action - FTIR analysis confirmed that the piston U-ring in ASCO's current stock was Teflon« coated Ethylene Propylene. ASCO records disclosed no prior cases of piston U-rings fabricated with incorrect material. Discussions with the distributor of the U-rings disclosed no other cases of improper material.

"Corrective Action - The customers that were shipped potentially affected NP8344E valves are being notified of the potential deviation. All variations of NP8344A72E, NP8344A73E, NP8344A74E, NP8344A75E, NP8344850E, NP8344B52E, NP8344B62E, and NP8344B64E manufactured from 1992 through 1995 are recommended to be monitored for leakage. Due to the qualified service life and date of manufacture, it is believed a majority of these valves are no longer in service, Subsequent to 1995, ASCO has implemented a more rigorous lot and batch control to verify the material compound at incoming and dedication inspection. This action further enhanced traceability of resilient materials used in specific production lots.

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Power Reactor Event Number: 46847
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RICKY GIVENS
HQ OPS Officer: JOHN KNOKE
Notification Date: 05/13/2011
Notification Time: 01:53 [ET]
Event Date: 05/12/2011
Event Time: 18:25 [CDT]
Last Update Date: 05/13/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
EUGENE GUTHRIE (R2DO)

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

Event Text

LOSS OF SHUTDOWN COOLING

"At 1825 CDT on 05/12/2011, with Browns Ferry Nuclear Plant Unit 3 in Mode 4, Browns Ferry Nuclear Plant PCIS [Primary Containment Isolation System] relay maintenance activities for a Group 1 PCIS relay inadvertently interrupted the neutral for a Group 2 PCIS relay and a Group 2 PCIS isolation occurred resulting in a loss of Shutdown Cooling. Relays were reset and Shutdown Cooling was restored at 1905 CDT. Moderator temperature prior to the event was 112.5 degrees F and the highest moderator temperature recorded during the loss of Shutdown Cooling was 122 degrees F.

"This condition is reportable under 10CFR50.72(b)(3)(v) - Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: B.) Remove residual heat.

"This is also reportable as a 60 day written report IAW 10CFR 50.73(a)(2)(v).

"The NRC Resident Inspector has been notified of this event.

"This event was entered into the licensee's Corrective Action Program as SR# 368205".

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Thursday, March 29, 2012