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Event Notification Report for October 12, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/08/2010 - 10/12/2010

** EVENT NUMBERS **


46253 46306 46314 46316 46321 46323 46324 46325 46327

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46253
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [ ] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: BETH JENKINS
HQ OPS Officer: KARL DIEDERICH
Notification Date: 09/15/2010
Notification Time: 12:03 [ET]
Event Date: 09/15/2010
Event Time: 03:13 [CDT]
Last Update Date: 10/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID HILLS (R3DO)

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

Event Text

HPCI DECLARED INOPERABLE DURING SURVEILLANCE TESTING

"In preparation for quarterly valve testing, the High Pressure Coolant Injection system was declared inoperable and the technical specification required actions were implemented. The system was available for on-line risk. During the testing, the inboard steam isolation valve was stroked closed and reopened and operated properly. The valve was reclosed to continue with valve testing. When an attempt was made to reopen the inboard isolation valve, the valve failed to indicate full open.

"The system remained inoperable due to the valve malfunction. Therefore, the condition is being reported in accordance with 10 CFR 50.72 (b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

"Maintenance activities are currently in progress to restore the system to the operable status."

The licensee entered a 14-day Limiting Condition of Operation per Technical Specification 3.5.1.

The licensee notified the NRC Resident Inspector.


* * * RETRACTION FROM SCOTT BRILEY TO BILL HUFFMAN 1302 EDT ON 10/8/10 * * *

"On September 15, 2010, the NRC Operation Center was notified of Event Number 46253 that described a failure of the High Pressure Coolant Injection (HPCI) system inboard steam isolation valve to fully reopen using the Main Control Room (MCR) control switch.

"At the time, it was not readily apparent that the system was capable of performing its intended safety function. Therefore, the condition was reported in accordance with 10 CFR 50.72 (b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

"Troubleshooting identified that a contact in the control switch circuit had malfunctioned. This contact is bypassed during an initiation signal. Therefore the valve would have opened fully in the event the HPCI system received an initiation signal.

"In light of these findings, the HPCI function was not impaired as a result of the contact malfunction and would have been capable of performing its safety function. Therefore, the notification associated with Event Number 46253 is being retracted."

The NRC Resident Inspector has been notified.

R3DO (Dave Passehl) has been notified.

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General Information or Other Event Number: 46306
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: CLINTON MEMORIAL HOSPITAL
Region: 3
City: WILMINGTON State: OH
County:
License #: 02120140000
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/04/2010
Notification Time: 14:59 [ET]
Event Date: 02/06/2008
Event Time: [EDT]
Last Update Date: 10/04/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVE PASSEHL (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - MEDICAL UNDERDOSE DURING PROSTATE BRACHYTHERAPY

The following report was received via e-mail:

The following report details "three Ohio Event Reports for two unreported medical events in 2008 (OH100022 and OH100023) and one unreported medical event in 2009 (OH100024). These events were discovered as a result of a special inspection conducted by ODH on 9/10/2010."

Ohio Report Number OH100022: "An unreported medical event occurred at Clinton Memorial Hospital in Wilmington, Ohio on 2/6/08. On that date the licensee performed a prostate seed implant with I-125 seeds prescribed to deliver a dose of 144 Gray to the prostate. Post implant dosimetry showed that the received dose was >20 % below the prescribed dose." [The actual dose delivered was 97.5 Gray]

Ohio Report Number OH100023: "An unreported medical event occurred at Clinton Memorial Hospital in Wilmington, Ohio on 3/21/08. On that date the licensee performed a prostate seed implant with I-125 seeds prescribed to deliver a dose of 145 Gray to the prostate. Post implant dosimetry showed that the received dose was >20 % below the prescribed dose." [The actual dose delivered was 102.5 Gray]

Ohio Report Number OH100024: "An unreported medical event occurred at Clinton Memorial Hospital in Wilmington, Ohio on 5/20/09. On that date the licensee performed a prostate seed implant with I-125 seeds prescribed to deliver a dose of 144 Gray to the prostate. Post implant dosimetry showed that the received dose was >20 % below the prescribed dose." [The actual dose delivered was 107.5 Gray]

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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General Information or Other Event Number: 46314
Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: TJADEN BIOSCIENCES, LLC
Region: 3
City: BURLINGTON State: IA
County:
License #: 0344-1-29-MD
Agreement: Y
Docket:
NRC Notified By: NANCY FARRINGTON
HQ OPS Officer: JOHN KNOKE
Notification Date: 10/07/2010
Notification Time: 09:25 [ET]
Event Date: 12/03/2009
Event Time: [CDT]
Last Update Date: 10/07/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVE PASSEHL (R3DO)
ANGELA MCINTOSH (FSME)

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

Event Text

AGREEMENT STATE REPORT - UNPLANNED EXPLOSION DAMAGING MIXTURE OF 400 MILLICURIES OF CARBON 14

This information was emailed from the state as follows:

During a routine health and safety inspection, the [state] inspector learned that an explosion had occurred at the facility on December 3, 2009. An Authorized User was quenching a mixture containing 400 milliCuries of Carbon-14 at the time of the explosion. The individual showered and was taken to the emergency room. The individual had several bioassays done prior to returning to work. The licensee decontaminated the area of concern within the lab. Iowa Item Number: IA100005

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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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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General Information or Other Event Number: 46316
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: TEAM INDUSTRIAL SERVICES
Region: 4
City: FULTON State: AR
County:
License #:
Agreement: Y
Docket:
NRC Notified By: STEVE MACK
HQ OPS Officer: CHARLES TEAL
Notification Date: 10/07/2010
Notification Time: 15:45 [ET]
Event Date: 10/03/2010
Event Time: [CDT]
Last Update Date: 10/07/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL SHANNON (R4DO)
PAUL MICHALAK (FSME)

Event Text

AGREEMENT STATE - RADIOGRAPHY SOURCE FAILED TO RETRACT

"On October 4, 2010, the Arkansas Radiation Control Program was notified by Team Industrial Services, Arkansas license number ARK-0344-03320, involving the failure of a radiography source to retract into the camera. The radiography crew involved in this incident was based in Sulphur, Louisiana.

"On October 3, 2010, radiography work was being conducted in Fulton, Arkansas using a rented SPEC-300 Camera, serial number 017, containing a 27 Curie SPEC G-70 source, serial number GE2503, both manufactured by Source Production and Equipment Company. The source was last leak tested on 10/1/2010. A J-Tube manufactured by QSA, owned by the licensee, was also employed in the radiography work.

"The source was cranked out of the SPEC-300 and the radiographer was unable to retract the source back into the camera. The radiography crew contacted the RSO and the crew attempted to safely straighten out the guide tube. After realigning the guide tube, the source was retracted into the camera.

"After the source was determined to be safely stored in the camera, the crew returned to the office to determine the cause of the inability to retract the source. SPEC was also notified.

"At this time, no overexposures have been reported by the licensee.

"The Radiation Control Program is awaiting a written report on the incident from the licensee."

Report #: ARK-0344-03320

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Power Reactor Event Number: 46321
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CECIL H. WILLIAMS, JR.
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/08/2010
Notification Time: 13:54 [ET]
Event Date: 10/08/2010
Event Time: 11:00 [EDT]
Last Update Date: 10/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GERALD MCCOY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 98 Power Operation 98 Power Operation

Event Text

INTEGRATED PLANT COMPUTER REMOVED FROM SERVICE FOR UPGRADE WORK

"At 1100, October 8, 2010, Unit 1 Integrated Plant Computer (IPC) was shutdown for upgrade work. This includes the SPDS [Safety Parameter Display System] system which is a function of the IPC. The IPC will be returned to service in approximately two weeks and SPDS function will be restored at that time. In addition, the ERDS [Emergency Response Data System] is out of service and will be restored in the same time frame. Per the 50.54.Q that was prepared by our Emergency Preparedness group, notification has been made to the NRC ERDS group of the unavailability of the ERDS system. While the IPC is out of service, control board indications are being utilized by the control room crew. In addition, the safety-related Plant Safety Monitoring System (PSMS) Is OPERABLE. Restoration of SPDS and ERDS functions have been given the highest priority during restoration of the system. Both the NRC Ops Center and the NRC ERDS group will be notified when SPDS and ERDS capability have been restored."

The NRC Resident Inspector has been notified.

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Other Nuclear Material Event Number: 46323
Rep Org: KAKIVIK ASSET MANAGEMENT
Licensee: KAKIVIK ASSET MANAGEMENT
Region: 4
City: NORTH SLOPE State: AK
County:
License #: 50-27667-01
Agreement: N
Docket:
NRC Notified By: KEENAN REMELE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/09/2010
Notification Time: 21:03 [ET]
Event Date: 10/09/2010
Event Time: 16:00 [YDT]
Last Update Date: 10/09/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
MICHAEL SHANNON (R4DO)
PAUL MICHALAK (FSME)

Event Text

LOCKING MECHANISM MALFUNCTION ON RADIOGRAPHY CAMERA

On October 9, the radiography crew working the Kuparuk Oil Field on the North Slope of Alaska experienced a malfunction of the locking system on an INC IR-100 exposure device.

After completing radiography activities, the source was cranked in and the camera was surveyed per the proper procedure. There were no abnormal readings observed during the survey and the key was turned to the lock position. When the crank assembly was removed it was noted that the pigtail was not fully seated.

The 2 mR/Hr boundary was reconfirmed and the Radiation Safety Supervisor was notified. A trained radiographer came to the site and removed the locking system and cleaned it. The locking system was successfully reinstalled. The camera has been returned to service.

Exposure Device: Industrial Nuclear IR-100
Device S/N: 6631
Source S/N: P661
Source Activity: 61 curies
Source Type: Ir192
Source Model # INC Model 32

There was no exposure to the crew or the general public during this incident.

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Power Reactor Event Number: 46324
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: AARON CHLADIL
HQ OPS Officer: CHARLES TEAL
Notification Date: 10/11/2010
Notification Time: 12:10 [ET]
Event Date: 10/11/2010
Event Time: 11:10 [CDT]
Last Update Date: 10/11/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MICHAEL SHANNON (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

TECHNICAL SUPPORT CENTER OOS FOR MAINTENANCE

"This is an eight-hour report as required per 10 CFR 50.72(b)(3)(xiii) due to maintenance which will result in the Fort Calhoun Station Technical Support Center (TSC) being degraded. On Monday, October 11th scheduled maintenance will commence on the TSC Air Handling unit that will render the unit non-functional. This maintenance is scheduled to be completed on Thursday, October 14th. Station procedures contain compensatory measures to ensure appropriate habitability monitoring and, if necessary, relocation of TSC personnel should the need exist to activate the emergency response organization."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46325
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [ ] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: JEFF SIMPSON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/11/2010
Notification Time: 13:38 [ET]
Event Date: 10/11/2010
Event Time: 10:04 [CDT]
Last Update Date: 10/11/2010
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):
DAVE PASSEHL (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 A/R Y 94 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DURING TRANSFER OF REACTOR PROTECTION SYSTEM BUS

"On October 11, 2010 in preparation for maintenance, the 'A' Reactor Protection System Bus was being transferred from the normal to the reserve power supply. As a part of the transfer, a half scram is expected. During the transfer a [full] reactor scram occurred. All rods inserted to their full-in positions.

"Following the reactor scram, all systems operated as expected. Reactor vessel inventory is being maintained by the Condensate / Feedwater system.

"Following the scram, the Unit 2/3 Emergency Diesel Generator auto started due to the transfer of the Auxiliary Power system.

"Currently the cause of the full Reactor Protection System [scram] is unknown. Troubleshooting is in progress to determine the malfunction.

"This condition is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B), Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical."

The auto-start of the EDG was expected as a result of the 'A' RPS bus transfer and has been secured and placed back in standby. Decay heat is being discharged to the condenser. The Unit is in a normal shutdown electrical line-up. The scram had no impact on Unit 2. The licensee characterized the scram as uncomplicated.

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46327
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MARK PIKUS
HQ OPS Officer: CHARLES TEAL
Notification Date: 10/11/2010
Notification Time: 22:05 [ET]
Event Date: 10/11/2010
Event Time: 13:05 [CDT]
Last Update Date: 10/11/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DAVE PASSEHL (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 95 Power Operation 95 Power Operation

Event Text

TECHNICAL SPECIFICATION DOES NOT ACCOUNT FOR POWER UPRATE

"On October 11, 2010 at 1305 CDT it was identified that the analysis of record for the Technical Specification 3.3.5.1, Table 3.3.5.1-1 function 1e and 2e, Reactor Steam Dome Pressure Permissive-Bypass timer (Pump Permissive) did not reflect current plant conditions. Specifically, the analysis was not updated to account for any increase in plant licensed power and a change to the RWCU (Reactor Water Cleanup System) isolation for enhanced ability to isolate RWCU on a line break on critical crack. The allowable value for these function is greater than or equal to 18 minutes and less than or equal to 22 minutes.

"All equipment associated with emergency core cooling function are unaffected. Discussion with General Electric indicates that a margin exists to accommodate the higher power level. Additionally, the changes to the RWCU isolation logic added leak detection instruments that will isolate RWCU earlier for the majority of pipe leaks. This discovery is being reported as an unanalyzed condition solely due to the lack of a formal analysis of current plant conditions."

The NRC Resident Inspector has been notified.

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