United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2010 > August 23

Event Notification Report for August 23, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/20/2010 - 08/23/2010

** EVENT NUMBERS **


46073 46180 46181 46185 46187 46191 46192 46194 46195 46196 46197

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46073
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: BENJAMIN CHANG
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/06/2010
Notification Time: 18:02 [ET]
Event Date: 07/06/2010
Event Time: 13:05 [EDT]
Last Update Date: 08/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)

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

POST CONTINGENCY LOW VOLTAGE ALARM RECEIVED FOR OFFSITE POWER

"The Rochester Gas and Electric (RG&E) Energy Control Center (ECC) notified Ginna Operations that the Post Contingency Low Voltage Alarm was received for the offsite power system. Ginna Operations entered procedure O-6.9, Operating Limits for Ginna Station Transmission, and declared the offsite power inoperable per ITS 3.8.1 [72 hour LCO]. Per NUREG-1022, section 3.2.7, if either offsite power or onsite emergency power is unavailable to the plant, it is reportable per 50.72(b)(3)(v)(A) regardless of whether the other system is available.

"The RG&E ECC monitors 115 kV voltage using their State Estimation and Contingency Analysis System. The State Estimation portion of the system evaluates real time system power flow and voltages on the 115 and 34.5 kV transmission systems. The Contingency Analysis portion analyzes the voltage effect of a Ginna main generator trip concurrent with worst case accident loading. If the Station 13A voltage would drop below the minimum required voltage for offsite power alignment a Ginna Post Contingency Low Voltage Alarm occurs.

"If the main generator should trip, then the absence of a Post Contingency Low Voltage Alarm on the RG&E State Estimation and Contingency Analysis System will ensure that the subsequent offsite 115kV system voltage transient will not result in Ginna Station experiencing an under voltage condition on the 480V Safeguard Busses.

"The RG&E ECC notified Ginna operations that the Post Contingency Low Voltage Alarm cleared at 1311 EDST on 07/06/2010. The plant was maintained at 100% steady state conditions throughout the event. Both circuits remain inoperable but available for use. And will be restored to operable status when the system reliability is assured.

"The licensee notified the NRC Resident Inspector."



* * * RETRACTION AT 0852 ON 8/20/10 FROM DETTMAN TO HUFFMAN * * *

"The purpose of this report is to retract the event discussed in ENS report #46071 (July 6, 2010). The ENS report covered an offsite power related event which occurred on July 6, 2010. In this event, both sources of offsite power were declared inoperable following notification to the R.E. Ginna Nuclear Power Plant that the calculated post contingency off-site system voltage was below the required value necessary to ensure that offsite power would remain available following a design basis accident.

"Since the ENS report, an engineering analysis of the event has been completed. The analysis determined that the offsite power system was actually operable at all times on July 6, 2010. The 'Post Contingency Low Voltage Alarm (PCLVA)' computer model that is being utilized by the transmission system provider, Rochester Gas & Electric, to calculate the post contingency offsite system voltage, is inherently conservative in that it assumes the site is relying on a worst case single source of offsite power. However on July 6, 2010, both offsite power sources were available and the site was aligned in the 50/50 Normal offsite power configuration. The engineering analysis calculated the acceptable voltage in this configuration and identified that at no point did the calculated post contingency voltage decrease below the 50/50 Normal offsite power configuration's acceptable value. As such, the July 6, 2010 event is being retracted.

"The licensee notified the NRC Resident Inspector."

R1DO (Burritt) was notified.

To top of page
General Information or Other Event Number: 46180
Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: RADIOLOGY GROUP BC
Region: 3
City: DAVENPORT State: IA
County:
License #: 0306-1-82-M1
Agreement: Y
Docket:
NRC Notified By: NANCY FARRINGTON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/17/2010
Notification Time: 09:45 [ET]
Event Date: 08/07/2010
Event Time: [CDT]
Last Update Date: 08/17/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
NICK VALOS (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE - POSSIBLE EXPOSURES OF MEMBERS OF GENERAL PUBLIC FROM A THYROID ABLATION PATIENT

A representative of the Iowa Bureau of Radiological Health reported a possible exposure event involving members of a medical center staff and perhaps others who were exposed to a patient that had recently been given a thyroid ablation treatment. The patient had been administered a dose of 150 millicuries of I-131 to ablate the thyroid on 8/6/10. The patient was then released and cautioned on avoiding contact with other people. On 8/7/10, the patient experienced an medical condition that resulted in an incoherent condition and was rushed to a medical center for treatment of that condition. The medical center was unaware of the patient's recent I-131 thyroid ablation treatment. The Radiology Group that administered the thyroid ablation subsequently became aware of the patient's admittance to the medical center. The Radiology Group is working with the medical center and also contacted the State of Iowa with the concerns about exposure that general members of the public may have received from the thyroid patient.

The State does not know details on the radiation levels that were present near the thyroid patient at the time of this event. The State is investigating the details of the event and possible exposures. The State is uncertain if the event is reportable under the State equivalent of 10 CFR 35.75 assuming that the patient met the release criteria after the thyroid treatment at the Radiology Group.

To top of page
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: 08/18/2010
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)

To top of page
General Information or Other Event Number: 46185
Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: PHILOTECHNICS, LTD
Region: 4
City: AMMON State: UT
County:
License #: MA 56-0543
Agreement: Y
Docket:
NRC Notified By: MARIO BETTOLO
HQ OPS Officer: JOHN KNOKE
Notification Date: 08/18/2010
Notification Time: 13:01 [ET]
Event Date: 07/09/2010
Event Time: [MDT]
Last Update Date: 08/18/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - TRITIUM EXIT SIGN WITH BROKEN TUBES DISCOVERED

Received the following report from the State of Utah via facsimile:

"On July 9, 2010, while working under reciprocity to package and ship 70 H-3 [Tritium] exit signs for Canyons School District, Philotechnics, Ltd. discovered a Tritium exit sign with broken tubes. The broken sign was manufactured in November, 1992 by Safety Sign Technologies and contained 20 Ci of H-3 ( Model #13200, S/N 550047). It is unknown when or how the sign was broken. At the time of discovery, Philotechnics, Ltd. was not equipped to conduct surveys or decontamination procedures, so the sign was placed in a secure area. The school district has appropriate control over the broken sign and is seeking contract for decontamination."

To top of page
General Information or Other Event Number: 46187
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: CHARTER STEEL
Region: 3
City: CUYAHOGA HEIGHTS State: OH
County:
License #: 31200180001
Agreement: Y
Docket:
NRC Notified By: MICHAEL SNEE
HQ OPS Officer: JOHN KNOKE
Notification Date: 08/18/2010
Notification Time: 15:08 [ET]
Event Date: 08/16/2010
Event Time: 20:00 [EDT]
Last Update Date: 08/18/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
NICK VALOS (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - DAMAGED CO-60 CASTER GAUGE

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

"At approximately 2000 [CDT] on 8/16/2010 a molten metal overflow event occurred at Charter Steel. Molten metal flowed down a tube outside the crucible where the caster gauge is located. The caster gauge, a Berthold LB300MLT containing 5 mCi of Co-60, was covered in molten metal as a result. On the morning of 8/17/2010 the licensee's environmental contractor was called to help assess the situation. Radiological surveys were conducted and no contamination was found. The gauge manufacturer recommended that the licensee contact Radiametrics (Ohio license # 03225480000) to recover the gauge. Radiametrics responded on the afternoon of 8/17/2010. Ohio Department of Health dispatched an inspector to investigate the incident and observed as Radiametrics removed the gauge from the now solidified block of steel. The gauge was found intact and the shutter was found in the closed position. Radiation surveys indicated that the source was intact and was not leaking. At approximately 1400 on 8/17/2010 the gauge was placed in secure storage at Charter Steel. The licensee has contracted with Radiametrics to transfer the source to a new Berthold gauge when it arrives in the next few days."

Ohio Incident # OH100010

To top of page
Power Reactor Event Number: 46191
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRAD HARDT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/20/2010
Notification Time: 17:47 [ET]
Event Date: 08/20/2010
Event Time: 15:25 [CDT]
Last Update Date: 08/20/2010
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):
GEOFFREY MILLER (R4DO)

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

Event Text

AUTOMATIC REACTOR TRIP DUE TO AN INADVERTENT TURBINE TRIP SIGNAL DURING TESTING

" At 1525 [hrs. CDT] on 08/20/10, Unit 1 experienced an automatic reactor trip while the plant was stable at 100% power in Mode 1. All systems actuated as designed. The reactor trip was caused by an inadvertent turbine trip signal initiated during testing.

"All ESF [Engineered Safety Features] systems actuated as designed. The following systems actuated: Auxiliary Feed Water and Feed Water Isolation."

All control and shutdown rods fully inserted. The plant is currently stable at normal operating pressure and temperature with decay heat being removed via steam dumps to the condenser. No primary or secondary relief valves lifted during the transient. The plant is in its normal shutdown electrical lineup with no problems noted. The trip was uncomplicated.

The turbine trip signal was generated by a human performance error during reactor trip breaker testing. The licensee has notified the NRC Resident Inspector.

To top of page
Other Nuclear Material Event Number: 46192
Rep Org: JANX INTEGRITY GROUP
Licensee: JANX INTEGRITY GROUP
Region: 1
City: WESTON State: WV
County:
License #: 21-16560-01
Agreement: N
Docket:
NRC Notified By: STEVE FLICKINGER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 08/20/2010
Notification Time: 18:24 [ET]
Event Date: 08/20/2010
Event Time: 13:00 [EDT]
Last Update Date: 08/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
JOHN WHITE (R1DO)
NICK VALOS (R3DO)
MARK DELLIGATTI (FSME)

Event Text

DAMAGED RADIOGRAPHY CAMERA GUIDE TUBE PREVENTING SOURCE RETRACTION

JANX crew was working on a piping fabrication. A piece of 2 inch pipe fell while making an exposure. It is believed that the falling pipe struck the guide tube. The radiographer then attempted to retrieve the source. The source partially retracted and then became stuck. The area was then cordoned off. The area is being well controlled. JANX's customer is Dominion Gas Transmission. There are no residential units close to this area. Source Production & Equipment Co. Inc. (SPEC) has been contacted. SPEC is dispatching personnel to effect source retrieval. No overexposures resulted from this event.

The radiography camera is a SPEC model 150 containing 90 curies IR-192.

GPS coordinates of event location: 39.10699 N 80.49879 W

Notified R1DO (White) and FSME EO (Delligatti).

To top of page
Power Reactor Event Number: 46194
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: CLINT SIX
HQ OPS Officer: DONALD NORWOOD
Notification Date: 08/21/2010
Notification Time: 11:41 [ET]
Event Date: 08/21/2010
Event Time: 11:00 [EDT]
Last Update Date: 08/21/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
JOHN WHITE (R1DO)

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

FLOOD BARRIERS NEEDED TO PROTECT SAFETY RELATED EQUIPMENT MISSING

"On August 21, 2010 an inspection of the Air Intake Tunnel (AIT) sump identified missing flood barriers needed to protect safety related equipment in the plant. If enough flood water had entered into the AIT, water could have entered into the Auxiliary Building (AB) through the ventilation ductwork that connects the AIT and the AB. If flood water continued to enter the AB, then safety related equipment in the AB could have been affected.

"This condition could have resulted in the unavailability of equipment in the Auxiliary Building including the 1A and 1B Decay Heat pumps, the 1A and 1B Building Spray pumps and 1A, 1B and 1C Make-up Pumps. This is reportable as an 8 hour ENS notification under 10CFR50.72(b)(3)(v)(B) and 10CFR50.72(a)(1)(ii) 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 remove residual heat.

"Flood protection barriers have been established for the affected penetrations. Inspections of the flood protection barriers are ongoing. Further engineering review is being performed to determine the impact of the potential water intrusion into the AIT and AB."

The licensee notified the NRC Resident Inspector. The licensee will notify the Pennsylvania Bureau of Radiation Protection.

To top of page
Power Reactor Event Number: 46195
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRUCE BUCH
HQ OPS Officer: DONALD NORWOOD
Notification Date: 08/21/2010
Notification Time: 15:47 [ET]
Event Date: 08/21/2010
Event Time: 15:09 [EDT]
Last Update Date: 08/21/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MIKE ERNSTES (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 100 Power Operation 100 Power Operation

Event Text

NOTIFICATION OF STATE AGENCIES DUE LEAK OF A WATER TREATMENT CHEMICAL

"At 1509 on 08/21/2010, a notification to outside state agencies, Tennessee Department of Environment and Conservation (TDEC) and Tennessee Emergency Management Agency (TEMA), was made due to a Towerbrom 960 [a microbiocide] chemical leak that developed at the Essential Raw Cooling Water (ERCW) intake station. The leak occurred during scheduled chemical treatment of the ERCW system. The leak was identified at 1850 EDT on 08/20/2010 and terminated at 1955 EDT on 08/20/2010. Chemically treated ERCW containing 55 ppm total residual chlorine reached the waters of the US which is above the 0.1 ppm allowed by the plant's National Pollutant Discharge Elimination System (NPDES) permit. There have been no observable adverse effects to the environment at this time. This occurrence does not affect safety related or other plant equipment."

The licensee notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 46196
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: SETH BELL
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/22/2010
Notification Time: 00:15 [ET]
Event Date: 08/21/2010
Event Time: 17:00 [CDT]
Last Update Date: 08/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
GEOFFREY MILLER (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

ONE TRAIN ECCS DECLARED INOPERABLE DUE TO VOID IN "A" RHR HEAT EXCHANGER

"On 8/21/10 at 1700 [CDT] with the Unit in Mode 1, 100% power, Engineering personnel provided information to the Control Room that a known void in the 'A' Residual Heat Removal (RHR) heat exchanger could move from the heat exchanger to other locations in the Emergency Core Cooling System (ECCS). The analysis provided by a vendor indicates that during a specific RCS leak scenario with a failure of the A' RHR Pump, our [Unit 1] piping configuration could potentially allow the void to be swept from the 'A' RHR heat exchanger and be transported to the 'A' Centrifugal Charging Pump (CCP) and 'A' Safety Injection Pump (SIP) while in the cold leg recirculation mode of operation. This condition results in one train of ECCS being inoperable. The ECCS safety function is maintained due to redundant and interconnecting piping, in both injection and recirculation phases of operation.

"The NRC Resident has been informed."

The licensee declared one train of ECCS inoperable placing Unit 1 in the 72-hour Technical Specification [TS] 3.5.2, Condition A, Action A.1. Corrective actions are on going to remove the void and exit the TS Action Statement.

To top of page
Power Reactor Event Number: 46197
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: DAVID DAVENPORT
HQ OPS Officer: PETE SNYDER
Notification Date: 08/23/2010
Notification Time: 04:42 [ET]
Event Date: 08/23/2010
Event Time: 03:30 [CDT]
Last Update Date: 08/23/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
GEOFFREY MILLER (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 68 Power Operation

Event Text

SHUTDOWN DUE TO PLANNED EMERGENCY DIESEL GENERATOR OUTAGE EXCEEDING ALLOWED TIME

"This is a 4 hour non-emergency 10 CFR 50.72(b)(2)(i) notification due to a Technical Specification required shutdown. 2EDG-2 (Unit 2 Emergency Diesel Generator #2) is currently inoperable due to a planned outage which has exceeded the allowed 14 day time clock IAW [in accordance with] TS 3.8.1.1. This requires that Unit 2 be in at least Hot Standby within the next 6 hours and in Cold Shutdown within the following 30 hours. Unit 2 is currently at 68% power and shutting down to comply with Technical Specifications."

The licensee notified the Arkansas Department of Health and the NRC Resident Inspector.

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