Event Notification Report for July 28, 2000
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/27/2000 - 07/28/2000 ** EVENT NUMBERS ** 37188 37189 37190 37191 37192 37193 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 37188 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 07/27/2000| |LICENSEE: QORE, INC. d/b/a ATLANTA TESTING & EN|NOTIFICATION TIME: 10:13[EDT]| | CITY: TAMPA REGION: 2 |EVENT DATE: 07/27/2000| | COUNTY: STATE: FL |EVENT TIME: 08:30[EDT]| |LICENSE#: 1646-1 AGREEMENT: Y |LAST UPDATE DATE: 07/27/2000| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |STEPHEN CAHILL R2 | | |JOHN HICKEY NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: CHARLEY ADAMS | | | HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE OWNED BY QORE, INC. | | d/b/a ATLANTA TESTING & ENGINEERING, INC. LOCATED IN TAMPA, FLORIDA | | | | The following text is a portion of a facsimile received from the Florida | | Bureau of Radiation Control: | | | | "Licensee: Qore, Inc., d/b/a Atlanta Testing & Engineering, Inc." | | | | "City, State, and Zip Code: Tampa, FL 33313" | | | | "License #: 1646-1" | | | | "License Type; Category: Specific; 3L(1)" | | | | "Isotope(s): Cs-137; Am-241:Be" | | | | "Activity(s): 8 mCi, 40.2 mCi" | | | | "Material Form; Chemical Form; Physical Form: By-product: Special Form" | | | | "Probable Disposition of Material: Unknown" | | | | "Exposure? No" | | | | "Number: N/A" | | | | "Type of Individual(s): N/A" | | | | "Exposure Source: N/A" | | | | "Dose Delivered to: N/A" | | | | "Maximum Dose Received: N/A" | | | | "Incident Category: Loss of Control - Lost, Abandoned, or Stolen | | Materials" | | | | "Incident Location: 2306 Isabel St., Tampa, FL" | | | | "Location Classification: Unrestricted Area" | | | | "Incident Description: [The] licensee reported that a gauge was stolen from | | a technician's home between 8 p.m. on 26 July and 8 a.m. on 27 July. The | | technician had worked late at a job and went home for the evening. When he | | checked the container the next morning[,] the gauge was missing. The gauge | | is locked[,] but the container had not been locked. The keys to the gauge | | were not stolen. The Tampa PD and the Florida Bureau of Radiation Control | | are investigating. The licensee is considering [offering] a $500 reward for | | the gauge's return." | | | | "Device Type (Quantity): Soil Moisture/Density Gauge (1)" | | | | "Manufacturer: Troxler" | | | | "Model Number: 3430" | | | | "Serial Number: 23299" | | | | "Emergency Groups at Scene: None" | | | | "Organizations Notified: NRC, Tampa PD" | | | | "Media Contacted: None" | | | | "Investigator's Name; Title: Charles Adams, Environmental Specialist II" | | | | "Office: Environmental Radiation Control" | | | | "Date; Time Investigated: 27-Jul-00; 0830" | | | | "[NRC] Region II has been notified." | | | | Call the NRC operations officer for contact information. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 37189 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WESTINGHOUSE ELECTRIC CORPORATION |NOTIFICATION DATE: 07/27/2000| | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 11:33[EDT]| | COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 07/26/2000| | COMMERCIAL LWR FUEL |EVENT TIME: 12:52[EDT]| | |LAST UPDATE DATE: 07/27/2000| | CITY: COLUMBIA REGION: 2 +-----------------------------+ | COUNTY: RICHLAND STATE: SC |PERSON ORGANIZATION | |LICENSE#: SNM-1107 AGREEMENT: Y |STEPHEN CAHILL R2 | | DOCKET: 07001151 |JOSIE PICCONE NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JIM HEATH | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT | | | | "During a routine procedure review associated with a plant-wide procedure | | upgrade process, a Nuclear Criticality Safety (NCS) engineer noted that a | | procedure was not written in compliance with the documented criticality | | safety evaluation. | | | | "The procedure under review was 'Filter Disassembly Process' which provides | | instructions for the disassembly of HEPA filters to remove non-combustible | | material and recover gross contamination (i.e. particles which are not | | imbedded in the media) prior to incineration. The procedure instructed the | | operator to 'Place paper filter media into a 30-gal paper bag for | | shredding.' The NCS engineer subsequently examined the criticality safety | | evaluation for the shredder system and found that mass control in the system | | is maintained by administrative controls which prohibit the shredding of | | filters surveyed to contain greater than 5g U-235/10 liters. It was | | determined that the procedure for shredding of the paper bags filled with | | un-assayed filter media failed to provide the documented double contingency | | protection for the system. | | | | "Double Contingency Protection: | | Double contingency protection for the shredder is based on mass control | | (prevent greater than 43 kg U from accumulating in the feeder hopper or the | | receiver drums). It was determined that less than double contingency | | protection remained for the system. However, at no time was greater than a | | safe mass involved. In accordance with Westinghouse Operating License | | (SNM-1107), paragraph 3.7.3 (c.5), this event meets the criteria for a 24 | | hour notification because it constitutes a 'nuclear criticality safety | | incident, in an analyzed system, for which less than previously documented | | double contingency protection remains ...and: Less than a safe mass ... is | | involved...' | | | | "Summary of Activity: | | Immediately upon determining that less than double contingency protection | | remained, the NCS engineer directed that shredding of bags containing | | disassembled filter media be stopped. Thus double contingency protection was | | immediately restored. | | | | "Conclusions: | | * Loss of double contingency protection occurred. | | * At no time was greater than a safe mass involved. | | * At no time was there any risk to the health or safety of any employee or | | member of the public. No exposure to hazardous material was involved. | | * The Incident Review Committee (IRC) determined that this is a safety | | significant incident in accordance with governing procedures. A formal root | | cause analysis is underway. | | * Notification was the result of a deficient procedure, not 'a deficient | | NCS analysis." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37190 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 07/27/2000| | UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 11:50[EDT]| | RXTYPE: [1] CE |EVENT DATE: 07/26/2000| +------------------------------------------------+EVENT TIME: 14:27[EDT]| | NRC NOTIFIED BY: SHERI KING |LAST UPDATE DATE: 07/27/2000| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |THOMAS KOZAK R3 | |10 CFR SECTION: | | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY OFFSITE FACILITY (EOF) TELEPHONE LAND LINES CUT DURING | | CONSTRUCTION. | | | | "ON 7/26/00 AT APPROXIMATELY 1427 HOURS, IT WAS DISCOVERED THAT ALL LAND | | LINKED TELEPHONES IN THE EMERGENCY OFFSITE RESPONSE FACILITY WERE | | INOPERATIVE. SUBSEQUENT INVESTIGATION REVEALED A MAJOR TELEPHONE TRUNK LINE | | HAD BEEN SEVERED AT APPROXIMATELY 1130 HOURS DURING CONSTRUCTION ACTIVITIES | | APPROXIMATELY ONE MILE FROM THE EOF. THIS SIGNIFICANT LOSS OF TELEPHONES | | WOULD HAVE IMPAIRED THE CAPABILITY TO ACTIVATE THE EOF IN THE EVENT OF AN | | ACCIDENT OR EMERGENCY. AT THE TIME OF THE DISCOVERY, COMMUNICATIONS FROM | | THE CONTROL ROOM TO THE NRC AND OFFSITE AGENCIES WERE VERIFIED AS | | OPERATIONAL. THE PHONE LINES WERE REPAIRED BY 1700 HOURS ON 7/26/00. | | | | "REPORTABILITY OF THE OCCURRENCE WAS DETERMINED AT 1100 HOURS ON 7/27/00." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Research Reactor |Event Number: 37191 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: UNIV OF ARIZONA |NOTIFICATION DATE: 07/27/2000| | RXTYPE: 100 KW TRIGA MARK I |NOTIFICATION TIME: 12:00[EDT]| | COMMENTS: |EVENT DATE: 07/27/2000| | |EVENT TIME: 08:45[MST]| | |LAST UPDATE DATE: 07/27/2000| | CITY: TUCSON REGION: 4 +-----------------------------+ | COUNTY: PIMA STATE: AZ |PERSON ORGANIZATION | |LICENSE#: R-52 AGREEMENT: Y |BILL JONES R4 | | DOCKET: 05000113 |JIM LYONS NRR | +------------------------------------------------+JOSIE PICCONE NMSS | | NRC NOTIFIED BY: J.G. WILLIAMS | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT INVOLVING POTENTIAL I-131 CONTAMINATION | | | | "FACILITY LICENSE R-52 | | | | "Report, possibly spurious, of I-131 contamination | | | | "July 27, 2000 | | | | "Description of the Occurrence: | | | | "On the afternoon of July 18, 2000, a routine contamination survey was | | performed at the Nuclear Reactor Laboratory (NRL), University of Arizona by | | staff of the Radiation Control Office (RCO). On July 26, at approximately | | 0845, the Reactor Supervisor received word that four out of 30 wipe samples | | showed contamination, with the highest count rate about 1100 counts per | | minute. Subsequently, he was told that I-131 (8-day half life) was | | identified by gamma spectrometry. | | | | "Immediate surveys of the Reactor Laboratory and reviews of records showed | | no confirmatory evidence, which should have been found if the reported | | contamination was genuine. | | | | "Contamination of the samples while in RCO custody is suspected, and this | | possibility is being investigated. | | | | "On the morning of 18 July a group of 20 visitors, members of the public, | | was present for about one hour in the morning. One half of the visitors, | | mostly school children grades 6 to 9, carried pocket dosimeters, which | | showed no exposure. The continuous air monitor showed no indication. The | | area monitors showed no indication. Finally, no indication of I-131 could be | | found in the laboratory yesterday, even though no clean-up had been | | attempted. | | | | "The report we received from RCO is at the moment considered to be spurious. | | This report is transmitted within 24 hours of our receiving that report, | | however, in case it proves to have some foundation. Investigation is in any | | case needed of how this occurred, and of why the report we received from RCO | | was not timely." | | | | * * * UPDATE 7/27/00 FROM J. WILLIAMS TO S. SANDIN VIA FAX * * * | | | | The licensee is retracting this report based on the following: | | | | "FACILITY LICENSE R-52 | | | | Withdrawn: previous report, dated today, entitled, "Report, possibly | | spurious, of I-131 contamination" | | | | "July 27, 2000 | | | | "Investigation of information that formed the basis for my previous report, | | dated today, has led to the conclusion that there exists no credible | | evidence of any violation of 10CFR20 at this facility or of any other basis | | for an immediate report in accordance with our Technical Specification. In | | particular no exposure or contamination of any person has occurred. | | Therefore, the previous report is withdrawn. | | | | "The basis for this conclusion, briefly, is as follows: | | | | "- The Radiation Control Office has reason to believe that the gamma | | spectrometer used to identify I-131 may have been previously contaminated | | with I-131. | | | | "- I-131 is not an isotope in use in the Reactor Laboratory. It is present | | in the reactor fuel elements, but could not have leaked from them without | | causing other indications that were not present. | | | | "- The liquid scintillation counts were incorrectly reported by an | | inexperienced analyst (though experienced in operating the equipment). | | | | "- At low counting levels, the techniques used to obtain the liquid | | scintillation counts may be sensitive to spurious effects such as static | | electricity. | | | | "- Even if accurate, the count rates reported would not credibly lead to | | the possibility of exposures above 10CFR20 limits. | | | | "- The absence of indications from Reactor Laboratory instruments, as | | reported previously, cannot be explained if there were any reactivity | | released from the reactor. Channel checks of those instruments had been | | performed on the day in question (7/18/00), and their calibrations were | | current. | | | | "- In addition to the absence of air monitor indication and area monitor | | indication, the reactor pool water monitoring system showed no indication. | | | | "- Further wipe samples of the locations occupied by visitors on 7/18/00, | | showed no indications of activity above background, and other wipes from | | areas not accessible to visitors showed no significant indications. | | | | "As stated in the original report, the reasons for the reporting of possibly | | spurious data, also after an apparently undue delay, require investigation. | | The results will be reported in writing to the NRC within 30 days, as an | | 'observed inadequacy in the implementation of administrative or procedural | | controls,' (Tech. Specs. 6.7.c.4)." | | | | Notified R4DO(Jones) and NMSS(Collins). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37192 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 07/27/2000| | UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 13:54[EDT]| | RXTYPE: [1] GE-6 |EVENT DATE: 07/27/2000| +------------------------------------------------+EVENT TIME: 09:02[CDT]| | NRC NOTIFIED BY: VERNON CARLSON |LAST UPDATE DATE: 07/27/2000| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |BILL JONES R4 | |10 CFR SECTION: | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL LOSS OF SAFETY FUNCTION RELATED TO CONTROL ROOM CHILLED WATER | | SYSTEM | | | | "While alternating Divisions of Control Room Chilled water to perform post | | maintenance testing on HVK-CHL1B the 'B' chiller tripped. When actions | | were taken to restart the 'A' chiller the breaker for the service water | | recirc valve SWP-MOV 27A tripped. The breaker was reset and the chiller was | | started. Due to the indeterminate nature of the breaker trip on the valve, | | the 'A' chiller was declared Inoperable. The 'C' & 'D' chillers were | | already Inoperable due to non-related existing conditions. This places the | | unit in Action 'B' of Tech Spec 3.7.3. We are conservatively reporting | | this pending the investigation of the condition and it's affect on the | | system response to postulated events to determine if the safety function was | | truly lost. System is currently operating and maintaining normal control | | room temperature." | | | | The licensee will inform the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 37193 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: IDAHO NAT ENGR & ENVIRONMENTAL LAB |NOTIFICATION DATE: 07/27/2000| |LICENSEE: IDAHO NAT ENGR & ENVIRONMENTAL LAB |NOTIFICATION TIME: 19:22[EDT]| | CITY: IDAHO FALLS REGION: 4 |EVENT DATE: 07/27/2000| | COUNTY: STATE: ID |EVENT TIME: 15:55[MDT]| |LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 07/28/2000| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |BILL JONES R4 | | |ELLIS MERSCHOFF RA | +------------------------------------------------+ELMO COLLINS NMSS | | NRC NOTIFIED BY: JOE GARCIA |CHARLES MILLER IRO | | HQ OPS OFFICER: STEVE SANDIN |STEINDURF FEMA | +------------------------------------------------+DOE, USDA, HHS (fax) | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COURTESY NOTIFICATION OF A DOE EMERGENCY DECLARATION AT AN INDEPENDENT SPENT | | FUEL STORAGE INSTALLATION (ISFSI) IN IDAHO | | | | At 1555MDT, DOE INEEL declared a Site Area Emergency due to wildland fires | | on DOE controlled property. The ISFSI containing the TMI spent fuel is not | | threatened. This notification is a courtesy call only and does not involve | | the NRC Radiological Emergency Plan. No NRC assistance is requested. | | | | DOE INEEL has notified the State of Idaho, all surrounding counties and DOE | | Headquarters. | | | | *** UPDATE AT 0304 EDT ON 07/28/00 FROM JOE GARCIA AND FOREST HOLMS TO LEIGH | | TROCINE *** | | | | This event status update was provided as a courtesy notification. The Site | | Area Emergency remains in progress. There is a site-wide emergency action | | level in effect because of a wildland fire. The TMI-2 ISFSI is located at | | the Idaho National Engineering & Environmental Laboratory (INEEL), but the | | Site Area Emergency does not impact the TMI-2 ISFSI. However, INEEL has | | been directed by the Department of Energy (DOE) to notify the NRC when | | emergency action levels of this nature are in place. The Site Area | | Emergency will remain in effect until the fire is extinguished. | | | | The following text is a portion of a facsimile received from the INEEL: | | | | "Description of Incident: Wildland fire on the INEEL. Fire suppression | | efforts continue. Emergency response centers [are] operational at RWMC, | | CFA, INTEC, TRA, EOC with reduced staffing. INTEC and TRA [are] continuing | | to monitor facilities." | | | | The NRC operations officer notified the R4DO (Jones), R4RA (Merschoff), NMSS | | EO (Collins), IRO (Miller), and the Federal Emergency Management Agency | | (FEMA) (Storer). DOE, U.S. Department of Agriculture (USDA), Department of | | Health and Human Services (HHS), Environmental Protection Agency (EPA), and | | Department of Transportation (DOT) (via the National Response Center) were | | also notified via facsimile. | +------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021