| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/23/2010 - 08/24/2010 ** EVENT NUMBERS ** |
 | 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. |
| 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." |
| 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 |
| 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. |
| Power Reactor | Event Number: 46198 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MICHAEL PETERSON
HQ OPS Officer: HOWIE CROUCH | Notification Date: 08/23/2010
Notification Time: 12:33 [ET]
Event Date: 08/23/2010
Event Time: 08:14 [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):
WAYNE WALKER (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 96 | Power Operation | Event Text TECH SPEC REQUIRED SHUTDOWN DUE TO BOTH EDGS AND AN RHR LOOP INOPERABLE
"On 8/23/2010 at 0814 [hrs. CDT] with the unit in Mode 1, 100%, Control Room personnel were informed by a Maintenance Planner that each (A and B) Emergency Diesel Generator [EDG] was missing a u-bolt on the relief valve tail pipes on Auxiliary Lube Oil Keep Warm system. The System Engineer concluded that this could affect the seismic qualification of the EDGs. Both EDGs were declared inoperable as a result. In addition, 'A' Residual Heat Removal (RHR) was out of service for emergent work. This resulted in less than 100% of the ECCS flow equivalent to a single ECCS train and entry into LCO 3.0.3 as required by TS 3.5.2, Condition C. A plant shutdown was commenced at 0907.
"At 0935, the Control Room was informed by Engineering that a calculation existed for continued operation of the EDGs with the u-bolt missing from the tailpipe of the relief valves on the Auxiliary Lube Oil Keep Warm system. Both EDGs were declared operable and LCO 3.0.3 was exited. The power reduction was stopped at 0940 with reactor power at 96%.
"The NRC Senior Resident Inspector was informed." |
| Power Reactor | Event Number: 46199 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: DENNIS MOORE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 08/23/2010
Notification Time: 14:06 [ET]
Event Date: 08/23/2010
Event Time: 09:00 [EDT]
Last Update Date: 08/23/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
PAMELA HENDERSON (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 LOSS OF ERDS CAPABILITY
"This report is being made per 10 CFR 50.72(b)(3)(xiii) regarding a loss of offsite communication capability in that Oyster Creek Nuclear Generating Station would not have been able to establish a connection with the NRC Emergency Response Data System (ERDS) within one hour if the need had arisen. This condition was discovered at 0900 hours on August 23, 2010, and existed from approximately 1900 hours on August 20 until 1123 hours on August 23, 2010.
"Oyster Creek Nuclear Generating Station switched the plant telephone system from a digital system to a Voice Over IP system at approximately 1900 hours on August 20, 2010. This change resulted in eliminating the requirement to dial the number '9' prior to dialing an outside line. The plant process computer (PPC) modem function program contained the NRC modem number preceded by the number '9' and when the changeover occurred the '9' was not deleted in the PPC program. This would have resulted in an error message if an attempt to connect with the NRC had been made. Information Technology (IT) estimates that it would have taken two hours to reprogram and establish the ERDS connection to the NRC. The ERDS data on the PPC was available but would have to have been transmitted to the NRC by an alternate method. 10 CFR 50.72(a)(4) requires one hour to activate the ERDS after declaring an emergency class of alert, site area, or general emergency.
"This situation was recognized at 0900 hours on August 23, 2010 by IT personnel. The ERDS connection capability was restored to fully functional status at 1123 hours on August 23, 2010."
The licensee has notified the NRC Resident Inspector. | |