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Event Notification Report for September 7, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/03/2010 - 09/07/2010

** EVENT NUMBERS **


46130 46181 46216 46227 46229 46230

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General Information or Other Event Number: 46130
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: APPLIED INSPECTION SYSTEMS, INC.
Region: 4
City: WILBURN State: AR
County:
License #: ARK-057603320
Agreement: Y
Docket:
NRC Notified By: KAYLA AVERY
HQ OPS Officer: ERIC SIMPSON
Notification Date: 07/27/2010
Notification Time: 12:04 [ET]
Event Date: 07/26/2010
Event Time: 15:10 [CDT]
Last Update Date: 09/03/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID PROULX (R4DO)
GLENDA VILLAMAR (FSME)

Event Text

AGREEMENT STATE REPORT - STUCK RADIOGRAPHY SOURCE

The following was received via email from the State of Arkansas:

"The following are the findings of the Arkansas Department of Health, Radioactive Materials Program, concerning Event Number [AR] 07-10-01 involving a stuck radiography source in Wilburn, Arkansas at a pipeline location. The Department was contacted on July 26, 2010 and informed by the licensee that the incident occurred around 9:30 a.m. on the first shot. The camera involved was an Industrial Nuclear IR-100 (Serial Number 6961) that contained a 34 Curie Iridium-192 source (Model G-40T, Serial Number RC3103). [Source Production and Equipment Company] (SPEC) [- the vendor -] had been contacted and was expected to arrive at the location around 5:00 a.m. on July 27, 2010. In the meantime, the crew and both of the Assistant Radiation Safety Officers maintained constant surveillance.

"Health Physicists from the Arkansas Department of Health also went to the incident location. On arrival, it was discovered that the source was in an approximately 10 foot hole and it was indicated that the radiography crew had performed three cranks and then the source would not retract back into the shielded position. SPEC successfully retrieved the source. The source, camera and associated equipment are being transported to the SPEC facility in Louisiana for evaluation.

"It appears that this incident may have been caused by the failure of the locking mechanism of the camera. The licensee and SPEC [are] to supply the Department with a written report.

"The Department will provide updates as information is received."

This is Arkansas Department of Health, Radioactive Materials Program event number 07-10-01.

* * * UPDATE FROM KAYLA AVERY TO ERIC SIMPSON AT 0925 EDT ON 9/3/2010 * * *

The following report was received via e-mail from the State of Arkansas:

"A report received from SPEC states that the cause of the incident was a source misconnect and the source locking mechanism failing to function properly. The report also states that if the camera had been operating properly, the radiographer should not have been able to push the flag down and release the source. There was no evidence of damage to the drive cable connector or to the source assembly. The source was reloaded into the camera and returned to the licensee.

"The Arkansas Department of Health considers this incident to be closed."

Notified R4DO (Deese) and FSME (McIntosh).

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General Information or Other Event Number: 46181
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TURNER INDUSTRIES GROUP, LLC
Region: 4
City: PARIS State: TX
County:
License #: 05237
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOHN KNOKE
Notification Date: 08/17/2010
Notification Time: 13:53 [ET]
Event Date: 07/30/2010
Event Time: [CDT]
Last Update Date: 09/03/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHER'S BADGE HAD READING OF 37 REM

On August 17, 2010, at 1115 hours, the Agency (State of Texas) was notified by the licensee that their dosimetry processor had notified them that a radiographer's badge was reading 37.060 rem for the month of July, 2010. The Radiation Safety Officer (RSO) stated that he had reviewed the daily dose records for the radiographer and the radiographer's recorded total exposure was less than 50 millirem for the exposure period. Also, the radiographer's coworker's badge reading was normal for the same period. The RSO stated that he believed that it was a badge only exposure. He stated that the radiographer works the afternoon shift, so he has not had a chance to interview him. The RSO stated that the radiographer has been removed from all activities which would expose him to any additional radiation exposure. The RSO stated that he was not aware of any single event which would have caused this type of exposure. The RSO stated that he interacts with the radiographer on a daily basis and has not noted any indications of an exposure of this magnitude. The RSO stated that medical exams would be considered if they could not prove that the exposure was to the badge only. Additional information will be provided as it is received in accordance with SA-300.

Texas Incident # I-8773

* * * UPDATE FROM ART TUCKER TO JOHN KNOKE AT 1655 EDT ON 8/18/10 * * *

Received the following report from the State of Texas via email:

"On August 18, 2010 at 1045 hours, the Agency [State of Texas] was contacted by the licensee's Radiation Safety Officer (RSO) and informed that they had conducted an interview with the radiographer receiving the over exposure. The radiographer stated that he did not remember ever dropping his TLD. He could not think of any reason why he would have received so much exposure. The RSO stated that the radiographer had performed all of his work within the shooting bays at their facilities. The licensee sent the radiographer to a medical facility for blood work. The RSO stated that the results of the blood work were normal. The RSO stated that the radiographers badge may have been intentionally exposed by another individual. He stated that they have security cameras and would review the tapes for any activities that could explain the exposure. The RSO stated that they had implemented new controls on their workers TLD's. Shift managers will control access to the badges when the workers are not wearing them. The RSO stated that the dosimetry processor could not determine if the dose recorded by the badge was while the badge was moving or stationary."

Notified R4DO (Geoffrey Miller), FSME (Mark Delligatti)

* * * UPDATE FROM ART TUCKER TO ERIC SIMPSON AT 1030 EDT ON 9/3/2010 * * *

The following report was received from the State of Texas via e-mail:

"The [State of Texas] was contacted by the licensee and informed the Radiation Emergency Assistance Center/Training Site has sent the licensee notification that based on their evaluation of the samples submitted to them by the licensee, no overexposure had occurred."

Notified R4DO (Deese) and FSME (McIntosh).

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General Information or Other Event Number: 46216
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GENERAL ATOMICS
Region: 4
City: SAN DIEGO State: CA
County:
License #: CA - 0145-37
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: ERIC SIMPSON
Notification Date: 08/31/2010
Notification Time: 12:59 [ET]
Event Date: 08/19/2010
Event Time: 10:30 [PDT]
Last Update Date: 08/31/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICK DEESE (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

CALIFORNIA AGREEMENT STATE REPORT - SOURCES DAMAGED BY FIRE

The following information was obtained from the State of California via e-mail:

"Six sources of Am-241 were involved in a fire. Three of the sources were not damaged. The other three are believed to be encased in melted/solidified masses of metal that had encased the sources. Each source was approximately 24 nanocuries. Initial surveys did not identify radiological contamination. Further analysis of the solidified metal believed to contain the three sources is planned. "

The fire was initiated by the spontaneous combustion of charcoal fines used at the facility.

There were no personnel injuries related to the fire event.

Local media carried a story on the fire, but not the radiological component.

The Am-241 sources are used as stabilizing sources in the air monitors.

The sealed sources are not believed to have been breeched. The State and licensee will be performing follow-up investigations into the final disposition of the three sources encased in the solidified metal.

California Report Number: 5010-081910.

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Power Reactor Event Number: 46227
Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BILL DUVALL
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/02/2010
Notification Time: 23:45 [ET]
Event Date: 09/02/2010
Event Time: 22:50 [EDT]
Last Update Date: 09/03/2010
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
EUGENE GUTHRIE (R2DO)
JEFFERY GRANT (IRD)
MIKE CHEOK (NRR)
BILL FLINTER (DHS)
GENE CENUPP (FEMA)

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

NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO HIGH WATER LEVEL IN THE RCIC INSTRUMENT SUMP

"This is a one-hour report for the discovery of a condition that met an emergency action level (EAL) for a Notification of Unusual Event (NOUE). EAL HU1 - Natural and Destructive Phenomena Affecting the Protected Area Threshold Value 6 states: 'Exceeding Max Normal Operating Values specified in EOP 31EO-EOP-014-1(2) SC - Secondary Containment Control Table 5 Secondary Containment Operation Water Levels.'

"On September 2, 2010 Plant Hatch Unit 2, as part of an on-going RCIC [Reactor Core Isolation Cooling] system outage, was restoring a tagout which un-isolated the CST [Condensate Storage Tank] from the RCIC system. The shift crew received several alarms in a short period of time for RCIC Northwest Diagonal Instrument Sump levels culminating with receiving the RCIC N-W DIAG INSTRSUMP LVL HIGH HIGH HIGH alarm at 2240. There was a report of water on the floor of the diagonal and 2E51-FV005 (a vent valve on the discharge of the barometric condensate pump) was identified as the source. The shift crew closed 2E51-F010 [suction isolation valve to the CST] to isolate the CST from the RCIC system. The Shift Manager declared an NOUE at 2250 for HU-1 Natural and Destructive Phenomena Affecting the Protected Area. At 2255 the Triple High alarm cleared."

Plant personnel have visually confirmed that the sump level has been pumped down to normal level. The water level in the RCIC room did not rise to a level such that any equipment was adversely affected. Plant Hatch notified the following agencies: Georgia EMA, Appling County EMA, Jeff Davis County EMA, Tattnall County EMA, and Toombs County EMA.

At the time of this notification, exit criteria for exiting the NOUE had been met and Hatch personnel were in the process of officially terminating the NOUE. The licensee will notify the NRC Resident Inspector.


* * * UPDATE FROM BILL DUVALL TO DONALD NORWOOD AT 0022 EDT ON 9/3/2010 * * *

The licensee officially terminated the NOUE at 0013 EDT on 9/3/2010.

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Power Reactor Event Number: 46229
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN DIGNAM
HQ OPS Officer: ERIC SIMPSON
Notification Date: 09/03/2010
Notification Time: 13:11 [ET]
Event Date: 09/03/2010
Event Time: 10:58 [EDT]
Last Update Date: 09/03/2010
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):
RICHARD CONTE (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 41 Power Operation 0 Hot Standby

Event Text

UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR TRIP DUE TO HIGH STEAM GENERATOR LEVEL

"On September 3, 2010, at approximately 1058 hrs., Indian Point Unit 2 automatically tripped from 41% power due to High Steam Generator Level. At the time of the trip, Unit 2 was performing a power reduction to take the unit offline for a planned maintenance outage. Unit 2 is currently stable in Mode 3. All automatic actions occurred as required. All control rods fully inserted with the exception of rod H-8 - which indicates 26 inches withdrawn. No primary or steam generator safety or relief valves lifted. The motor driven auxiliary feedwater pumps automatically started on low steam generator level as designed. Decay heat removal is via the steam generators to the main condenser. Offsite power is available and supplying all safeguards busses.

"The cause of the trip and rod H-8 position indication are under investigation.

"Unit 3 is unaffected and remains in Mode 1 at 100% power."

The NRC Resident Inspector has been notified.

Offsite notification was made to the State of New York.

No press releases are planned.

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General Information or Other Event Number: 46230
Rep Org: GE HITACHI NUCLEAR ENERGY
Licensee: GE HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DALE E. PORTER
HQ OPS Officer: ERIC SIMPSON
Notification Date: 09/03/2010
Notification Time: 15:23 [ET]
Event Date: 09/03/2010
Event Time: [EDT]
Last Update Date: 09/03/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
RICHARD CONTE (R1DO)
EUGENE GUTHRIE (R2DO)
TAMARA BLOOMER (R3DO)
RICK DEESE (R4DO)
MIKE CHEOK (NRR)
PART 21 GP via email ()

Event Text

PART 21 - FAILURE TO INCLUDE SEISMIC INPUT IN REACTOR CONTROL BLADE CUSTOMER GUIDANCE

The following is text of a facsimile submitted by the vendor:

"GE Hitachi Nuclear Energy (GEH) has identified that engineering evaluations that support the guidance provided in SC 08-05, Revision 1, do not address the potential impact of a seismic event on the ability to scram as it relates to the channel-control blade interference issue. Note that the seismic loads are not a consideration in the scram timing, but rather the ability to insert the control blades. In other words, the control blades must be capable of inserting during the seismic event, but not to the timing requirements of the Technical Specifications. GEH is evaluating the impact of the seismic loads between the fuel channel and the control blade associated with an Operating Basis Earthquake (OBE), and a Safe Shutdown Earthquake (SSE) on BWR/2-5 plants. The scram capability is expected to be affected due to the added seismic loads at low reactor pressures in the BWR/2-5 plants. The ability to scram for the BWR/6 plants is not adversely affected by the seismic events. Additional evaluation is required to determine to what extent the maximum allowable friction limits specified for the BWR/2-5 plants in SC 08-05 Revision 1 is affected by the addition of seismic loads.

"GEH issues this 60-Day Interim Report in accordance with the requirements set forth in 10 CFR 21.21 (a)(2) to allow additional time to for this evaluation to be completed."

Affected US plants previously notified by vendor and recommended for surveillance program include: Nine Mile Point, Units 1 and 2; Fermi 2; Columbia; FitzPatrick; Pilgrim; Vermont Yankee; Grand Gulf; River Bend; Clinton; Oyster Creek; Dresden, Units 2 and 3; LaSalle, Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3; Quad Cities, Units 1 and 2; Perry, Unit 1; Duane Arnold; Cooper; Monticello; Brunswick, Units 1 and 2; Hope Creek; Hatch, Units 1 and 2; and Browns Ferry, Units 1and 2.

Affected US plants previously notified by vendor and provided information include: Susquehanna, Units 1 and 2 and Browns Ferry, Unit 3.

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Thursday, March 29, 2012