Event Notification Report for June 6, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/05/2002 - 06/06/2002 ** EVENT NUMBERS ** 38956 38965 38966 38967 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 38956 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: OR DEPT OF HEALTH RAD PROTECTION |NOTIFICATION DATE: 05/31/2002| |LICENSEE: US AIR FORCE |NOTIFICATION TIME: 17:28[EDT]| | CITY: REGION: 4 |EVENT DATE: 05/30/2002| | COUNTY: HOOD RIVER STATE: OR |EVENT TIME: 14:00[PDT]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 05/31/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |GARY SANBORN R4 | | |E. WILLIAM BRACH NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: KEVIN SIEBERT | | | HQ OPS OFFICER: MIKE NORRIS | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF LICENSED NUCLEAR MATERIAL IN HELICOPTER ACCIDENT | | | | An Air Force Pave Hawk Helicopter crashed approximately 800 feet from the | | summit of Mount Hood. Each of the 4 rotors contains a 500 microcurie Sr-90 | | source. More information will follow as it becomes available. | | | | The State will be contacting R4. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38965 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WESTINGHOUSE ELECTRIC CORPORATION |NOTIFICATION DATE: 06/05/2002| | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 13:10[EDT]| | COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 06/05/2002| | COMMERCIAL LWR FUEL |EVENT TIME: 10:45[EDT]| | |LAST UPDATE DATE: 06/05/2002| | CITY: COLUMBIA REGION: 2 +-----------------------------+ | COUNTY: RICHLAND STATE: SC |PERSON ORGANIZATION | |LICENSE#: SNM-1107 AGREEMENT: Y |BRIAN BONSER R2 | | DOCKET: 07001151 |DOUG BROADDUS NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: B. W. WALLACE | | | HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01 RESPONSE -- FAILURE TO MAINTAIN A DOUBLE CONTINGENCY | | INVOLVING MATERIAL TRANSFER INTO THE ERBIA MODCON AREA WITHOUT MOISTURE | | RESULTS (24-Hour Report) | | | | The following text is a portion of a facsimile received from the licensee: | | | | "Facility | | Westinghouse Electric Company, Commercial Fuel Fabrication Facility, | | Columbia SC, low enriched ([<=]5.0 wt. % U-235) PWR fuel fabricator for | | commercial light water reactors. | | License: SNM-1107." | | | | "Time and Date of Event | | Approximately 10:45 hours, Wednesday, June 5, 2002." | | | | "Reason for Notification | | Thirteen packs of oxidized U3O8 were improperly transferred into the Erbia | | Modcon area without proper moisture analysis results." | | | | "Summary of Process | | UO2 powder is oxidized to U3O8 to be used as addback in powder blends. | | After staying in an oven at a high temperature for over one hour, the | | material is screened and put into polypaks. Each pack is sampled for | | moisture and stored pending results of the moisture analysis. Then the | | material is bar code scanned and transferred into the Modcon area using a | | polypak elevator interlocked with the moisture analysis results." | | | | "As-Found Condition | | A summary of the as-found conditions is as follows: | | * Thirteen packs of material were found to have been taken into the Modcon | | area via a freight elevator, bypassing the bar code scanning interlock. The | | packs did not have moisture analysis results completed and posted. | | * The packs were immediately removed from the area, and the Nuclear | | Criticality Safety (NCS) function was immediately notified. | | * The material in question was oxidized U3O8, visually dry." | | | | "Double Contingency Protection | | Double contingency protection for the erbia blender and bulk containers is | | based on moderation control, that is, (1) prevent greater than 20.48 liters | | of water equivalent from becoming available to the mixer or container, and | | (2) prevent 20.48 liters of water equivalent from entering the mixer or | | container. It was determined that double contingency protection was | | bypassed because, for the 13 packs involved, there were no effective | | controls to prevent material with undocumented moisture from being brought | | into the Modcon area. It is also noted that at no time was greater than the | | safety limit of moderator involved. Therefore, the incident requires | | 24-hour notification in accordance with Westinghouse Operating License (SNM- | | 1107), paragraph 3.7.3(c.5)." | | | | "Summary of Activity | | * The packs were immediately removed from the area, and the Nuclear | | Criticality Safety (NCS) function was immediately notified. | | * The Erbia Process Engineer stopped all erbia powder blending | | operations." | | | | "Conclusions | | * There was a loss of double contingency protection. | | * At no time was greater than a safe limit of moderator involved. | | * At no time was criticality possible. | | * 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 causal | | analysis will be performed." | | | | The licensee reported that the information provided via facsimile (and | | quoted above) does NOT contain sensitive information. | | | | The licensee notified an onsite NRC Region 2 inspector (Bill Gloersen) and | | plans to notify the NRC Region 2 office (Manuel Crespo) and NMSS (Dennis | | Morey). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38966 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/05/2002| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:18[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/04/2002| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:20[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/05/2002| | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION | |LICENSE#: GDP-1 AGREEMENT: Y |SONIA BURGESS R3 | | DOCKET: 0707001 |DOUG BROADDUS NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: B. W. WALLACE | | | HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01 RESPONSE -- FAILURE TO MAINTAIN A DOUBLE CONTINGENCY | | INVOLVING TWO CONTROLS ON THE MASS PARAMETER (24-Hour Report) | | | | The following text is a portion of a facsimile received from Paducah | | personnel: | | | | "A container of improperly exempted uranium hexafluoride compressor parts | | was discovered in the C-333 process building which had not been | | characterized for storage as a group, in violation of the governing Nuclear | | Criticality Safety Approval NCSA GEN-010. NCSA GEN-010 requires individual | | items to be either spaced or grouped. Grouping is allowed if mass | | requirements are met. These items were not identified as GEN-010 items and | | had been stored as an unanalyzed group. The purpose of the GEN-010 | | requirement is to ensure that only safe mass items/groups are handled." | | | | "The NRC Resident Inspector has been notified of this event." | | | | "PGDP Assessment and Tracking Report No. ATR-02-2713; PGDP Event Report No. | | PAD-2002-017, Event Worksheet 38966" | | | | "Responsible Division: Engineering" | | | | "SAFETY SIGNIFICANCE OF EVENTS:" | | | | "Double contingency was not maintained because the independent determination | | of mass had not been performed. The independent determination of mass has | | since been performed and [was] found to be less than the maximum safe | | mass." | | | | "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW | | CRITICALITY COULD OCCUR:" | | | | "In order for a criticality to be possible, more than a critical mass would | | need to be accumulated in an unsafe geometry." | | | | "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):" | | | | "The controlled parameter is mass." | | | | "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND % WORST CASE CRITICAL MASS):" | | | | "A non-destructive analysis was conducted and determined the mass of U235 in | | the parts was less than 91 grams; the always-safe mass at the assay involved | | is [ ] grams of U235." | | | | "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES:" | | | | "Double contingency is maintained by implementing two controls on the mass | | parameter." | | | | "The first leg of double contingency is based on determining the mass of the | | group. The mass was not determined during the legacy characterization | | process. Therefore, the control was violated." | | | | "The second leg of double contingency is based on independently determining | | the mass of the group. The mass was not determined during the legacy | | characterization process; therefore, the control was violated. Since there | | are two controls on one parameter, the mass parameter was not maintained and | | double contingency was not maintained." | | | | "Since double contingency is based on two controls on one parameter, double | | contingency was not maintained." | | | | "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS | | IMPLEMENTED:" | | | | "Use the independent NDA results in conjunction with approved plant | | procedures to establish and post these items as a GEN-010 group." | | | | Paducah personnel reported that the information provided via facsimile (and | | quoted above) does NOT contain sensitive information. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38967 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 06/06/2002| | UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 02:51[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/05/2002| +------------------------------------------------+EVENT TIME: 23:00[EDT]| | NRC NOTIFIED BY: DUANE COBB |LAST UPDATE DATE: 06/06/2002| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: UNUSUAL EVENT |JAMES CREED R3 | |10 CFR SECTION: |STUART RICHARDS NRR | |AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |JOSEPH HOLONICH IRO | | |DEPUY FEMA | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Hot Shutdown |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 DECLARED AN UNUSUAL EVENT DUE TO RCS LEAKAGE > 25 GPM DURING | | SURVEILLANCE TESTING | | | | "D.C. Cook Unit One declares entry and exit of an Unusual Event due to | | Reactor Coolant System leakage of greater than 25 gallons per minute. On | | June 5 @ 23:00 while performing an 18 month surveillance [1-IHP-4030-102-017 | | 'Pressurizer PORV/Actuation Channel Calibration with Valve Operation'] on | | the Pressurizer Power Operated Relief Valves (PORVs) an unblocked PORV | | lifted and discharged to the Pressure Relief Tank (PRT) for approximately 15 | | seconds. This lifting discharged approximately 100 gallons to the PRT. The | | Initiating Condition for this Unusual Event is Reactor Coolant System | | leakage greater than 25 gallons per minute. | | | | "The plant is and was in Mode 4. Conditions remain stable after manual | | isolation of the PORV with the Control Switch of the Block Valve by the | | assisting Reactor Operator." | | | | The licensee attributed this occurrence to the recently revised procedure | | identified above which did not address blocking the other PORVs during | | testing. The licensee informed state and local agencies and the NRC | | Resident Inspector. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021