| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/29/2010 - 07/30/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 46119 | Rep Org: NEW MEXICO RAD CONTROL PROGRAM
Licensee: UNIVERSITY OF NEW MEXICO
Region: 4
City: ALBUQUERQUE State: NM
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MICHAEL ORTIZ
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/23/2010
Notification Time: 13:13 [ET]
Event Date: 07/21/2010
Event Time: 15:00 [MDT]
Last Update Date: 07/23/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL HAY (R4DO)
GLENDA VILLAMAR (FSME)
| Event Text AGREEMENT STATE REPORT - POTENTIAL MEDICAL EVENT INVOLVING LESS THAN PRESCRIBED DOSE
The following information was received from the State of New Mexico via email:
"Medical Event was reported 7/23/2010 at 8:39 am by the Radiation Safety Specialist, UNM Radiation Safety Office.
"Location: UNM Nuclear Medicine Department
1801 Tucker Avenue
Albuquerque, NM 87131
"Medical Event: 7/21/2010 at 3:00 pm, patient written directive order to receive Iodine-131 Therapy treatment 200 mCi (NaI), patient received 80 mCi.
"A detailed report will be supplied to State of New Mexico Radiation Control Bureau by UNM RSO within 15 days."
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. |
| 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). |
| Fuel Cycle Facility | Event Number: 46138 | Facility: WESTINGHOUSE ELECTRIC CORPORATION
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 to UO2)
COMMERCIAL LWR FUEL
Region: 2
City: COLUMBIA State: SC
County: RICHLAND
License #: SNM-1107
Agreement: Y
Docket: 07001151
NRC Notified By: GERARD COUTURE
HQ OPS Officer: ERIC SIMPSON | Notification Date: 07/29/2010
Notification Time: 13:40 [ET]
Event Date: 07/28/2010
Event Time: 14:00 [EDT]
Last Update Date: 07/29/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
| Person (Organization):
ALAN BLAMEY (R2DO)
DENNIS DAMON (NMSS)
| Event Text INCORPORATION OF 'INCREDIBLE' CRITICALITY SEQUENCES INTO INTEGRATED SAFETY ANALYSIS
"This notification is being made based on 10 CFR 70 Appendix A (b)(1) 'Any event or condition that results in the facility being in a state that was not analyzed, was improperly analyzed, or is different from that analyzed in the Integrated Safety Analysis, and which results in failure to meet the performance requirements of 10 CFR 70.61.'
"Westinghouse Environmental Health and Safety (EH&S) staff evaluated the compliance posture concerning the extent of condition for an open Notice of Violation (NOV) 70-1151/2009-201-01, and evaluation of the information provided in the 'Summary of the June 28, 2010, Public meeting to discuss the use of Design Features to meet the performance requirements of Title 10 of the Code of Federal Regulations part 70, Subpart H,' (ML101950377). This evaluation identified a contradiction between the guidance and [the] approved SNM-1107 License and procedures. Therefore, criticality events evaluated as incredible in accordance with procedure NCS-010 'Categorizing Potential Criticality Scenarios and Criticality Safety Significant Controls' are no longer deemed in compliance with 10 CFR Part 70. Following the NCS-010 methodology allowed for an incredibility conclusion 'based on crediting passive engineered controls or passive design features.' When the logic demonstrated that the passive control or design feature absolutely prevented the scenario from leading to a criticality, the scenario was categorized as incredible; the control was designated as a Safety Significant Control (SSC) in the Integrated Safety Analysis (ISA). SSCs are subject to Management Measures required by the SNM-1107 License to ensure they are available and reliable to perform their intended function. However, failure to identify these accident sequences as credible led to these sequences not being included in the ISA Summary, and therefore Items Relied on For Safety (IROFS) were not designated for these sequences.
"Immediate Corrective Actions: A governing policy was issued as an interim compensatory measure to identify all current Nuclear Criticality Safety (NCS) engineered SSCs as IROFS. A currently in place NCS Facility Walk-through Assessment process, procedure RA-316, is also designated as an Administrative IROFS as a verification activity of the engineered controls.
"Interim controls are being established on modifications pertaining to Criticality Safety Related SSCs to ensure no situation occurs where a modification may require NRC pre-approval.
"This event has been entered into the Facility Corrective Action Process CAPS #10-210-C002." |
| Power Reactor | Event Number: 46139 | Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: GENE DORMAN
HQ OPS Officer: VINCE KLCO | Notification Date: 07/29/2010
Notification Time: 18:02 [ET]
Event Date: 07/29/2010
Event Time: 07:40 [EDT]
Last Update Date: 07/29/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
JOHN ROGGE (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 24 HOUR FITNESS-FOR-DUTY REPORT
A non-licensed contract foreman had a confirmed positive during a follow-up fitness-for duty test. The contract employee's unescorted access has been terminated. Contact the Headquarters Operation Officer for additional details.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 46140 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JORGE RODRIGUEZ
HQ OPS Officer: ERIC SIMPSON | Notification Date: 07/30/2010
Notification Time: 15:50 [ET]
Event Date: 07/30/2010
Event Time: 07:20 [MST]
Last Update Date: 07/30/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| 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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF EMERGENCY SIREN
"On July 30, 2010, at approximately 0720 Mountain Standard Time (MST), the Palo Verde Emergency Planning Department discovered that public warning system siren No. 17 was not responding, and therefore, is out of service. The loss of siren No. 17 could potentially impact a population of approximately 1196 people in the 5-mile emergency planning zone (EPZ).
"Since the loss of siren No. 17 could impair Arizona Public Service Company's ability to inform greater than 5% of the population within the EPZ, this notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii). If an event occurs while siren No. 17 is out of service, the Palo Verde Emergency Plan has a contingency for dispatching Maricopa County Sheriff's Office (MCSO) vehicles with loud speakers to alert persons within the affected area. The MCSO is prepared to implement this contingency should it become necessary.
"Troubleshooting to determine the cause of the failure has commenced."
The NRC Resident Inspector has been notified. | |