Event Notification Report for July 18, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/17/2003 - 07/18/2003 ** EVENT NUMBERS ** 39986 40001 40004 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Hospital |Event Number: 39986 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: UNIVERSITY OF WISCONSIN - MADISON |NOTIFICATION DATE: 07/09/2003| |LICENSEE: UNIVERSITY OF WISCONSIN |NOTIFICATION TIME: 18:07[EDT]| | CITY: Madison REGION: 3 |EVENT DATE: 07/09/2003| | COUNTY: Dane STATE: WI |EVENT TIME: 13:00[CDT]| |LICENSE#: 48-09843-18 AGREEMENT: N |LAST UPDATE DATE: 07/17/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |CHRIS MILLER R3 | | |SUSAN FRANT NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: RONALD BRESELL | | | HQ OPS OFFICER: ERIC THOMAS | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |LDIF 35.3045(a)(1) DOSE <> PRESCRIBED DOSA| | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MEDICAL EVENT | | | | At 1300 CDT on 7/9/03, an underadministration of Yttrium-90 (Y-90) occurred | | at the University of Wisconsin Hospital in Madison, WI. A patient being | | treated for secondary liver cancer was to receive a dose of approximately 50 | | millicuries of Y-90. The dose was delivered using a SIRTECH (Selective | | Radiation Implantation) to pulse microspheres of Y-90 from a vial into the | | liver via a needle and catheter. | | | | During the procedure, the SIRTECH did not develop enough pressure to deliver | | the entire dose to the patient, and only about 8 percent of the Y-90 was | | delivered to the patient (between 3-4 millicuries). The remainder of the | | Y-90 microspheres were contained within the vial. | | | | There was no adverse affect on the patient due to this underadministration, | | and the licensee is still investigating how to prevent a re-currence. The | | patient was notified of the underadministration. | | | | * * * RETRACTION AT 0615 EDT ON 07/17/03 FROM BRESELL TO GOTT * * * | | | | The licensee determined that the technician had misinterpreted the | | measurement of the Y-90 administered to the patient and determined that the | | correct amount of Y-90 was administered. Because the correct amount of Y-90 | | was administered, the licensee is retracting the event. The licensee | | discussed this with Deborah Piskura, NRC Region III. | | | | Notified R3DO (Riemer) and NMSS EO (Pierson) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 40001 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 07/17/2003| | UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 06:57[EDT]| | RXTYPE: [1] W-4-LP |EVENT DATE: 07/16/2003| +------------------------------------------------+EVENT TIME: 22:08[CDT]| | NRC NOTIFIED BY: STEVEN HENRY |LAST UPDATE DATE: 07/17/2003| | HQ OPS OFFICER: BILL GOTT +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |LINDA SMITH R4 | |10 CFR SECTION: |TERRYREIS NRR | |NINF INFORMATION ONLY |TIM MCGINTY IRO | | |MATT HAHN NSIR | | |AL TARDIFF NSIR | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNDECLARED UNUSUAL EVENT | | | | At 0501 CDT on 07/17/03 the shift manager determined that a condition | | existed for 10 minutes the previous evening which met the emergency plan | | criteria but no emergency was declared. The basis for the emergency class | | no longer existed at the time of discovery. Upon discovery he notified the | | NRC Operations Center and the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 40004 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WESTINGHOUSE ELECTRIC CORPORATION |NOTIFICATION DATE: 07/17/2003| | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 16:00[EDT]| | COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 07/17/2003| | COMMERCIAL LWR FUEL |EVENT TIME: 03:35[EDT]| | |LAST UPDATE DATE: 07/17/2003| | CITY: COLUMBIA REGION: 2 +-----------------------------+ | COUNTY: RICHLAND STATE: SC |PERSON ORGANIZATION | |LICENSE#: SNM-1107 AGREEMENT: Y |JOHN PELCHAT R2 | | DOCKET: 07001151 |CHARLIE MILLER NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: CARL SYNDER | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC 91-01 BULLETIN NOTIFICATION INVOLVING LOSS OF CRITICALITY | | CONTROL | | | | The following is a portion of text from a fax submitted by the licensee: | | | | "Pump-Out to UNBSS Without Sample Results. | | "Reason for Notification: An operator pumped out a batch from the clean | | dissolver to the uranyl nitrate bulk storage tank prior to receiving the | | required sample results for grams U-235 per liter, percent free acid, and | | pH. | | | | "Double Contingency Protection: Double contingency protection for the bulk | | storage tank is based on concentration control. Concentration control is | | based upon maintaining uranyl nitrate that is pumped to the tanks at less | | than 5 grams U-235/liter. The pH is maintained at a value of less than 2 to | | ensure that the uranyl nitrate stays in solution. The percent free acid is | | maintained at greater than 4 percent to ensure that the uranyl nitrate stays | | in solution and depresses the freezing temperature of the solution to | | prevent concentration by freezing. | | | | "It has been determined that less than previously documented double | | contingency protection remained for the system and that greater than a safe | | mass was involved., but a sufficient number of controls that were lost were | | restored within 4 hours. In accordance with Westinghouse Operating License | | (SNM-1107), paragraph 3.7.3 (c.5b), this event satisfies the criteria for a | | 24-hour notification. | | | | "As Found Condition: See 'Reason for Notification' above. | | | | "Summary of Activity: (1) Pump outs to the bulk storage tanks were | | stopped, (2) Samples for grams U-235/liter, pH, and %free acid were taken to | | ensure the tanks were in specification, (3) Before the end of the shift, | | sample results for grants U-235/liter, pH, and %free acid were determined to | | be acceptable. | | | | "Conclusions: (1) Loss of double contingency protection occurred, (2) | | Greater than a safe mass was involved, (3) At no time was the health or | | safety to any employee or member of the public in jeopardy. No exposure to | | hazardous material was involved, (4) The Incident Review Committee (IRC) | | determined that this is a safety significant incident in accordance with | | governing procedures, (5) Notification was the result of an event, not a | | deficient NCS analysis, (6) A causal analysis will be performed." | | | | The licensee attributes the cause of this incident to personnel error. The | | licensee will inform both NRC Region 2 and the NRC Headquarters PM. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021