U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/31/2004 - 04/01/2004 ** EVENT NUMBERS ** | General Information or Other | Event Number: 40611 | Rep Org: TENNESSEE DIV OF RAD HEALTH Licensee: SAINT FRANCIS HOSPITAL Region: 1 City: MEMPHIS State: TN County: License #: R-79104 Agreement: Y Docket: NRC Notified By: DEBRA SHULTS HQ OPS Officer: STEVE SANDIN | Notification Date: 03/26/2004 Notification Time: 14:53 [ET] Event Date: 03/25/2004 Event Time: 08:45 [EST] Last Update Date: 03/26/2004 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): RONALD BELLAMY (R1) ROBERTO TORRES (NMSS) | Event Text AGREEMENT STATE REPORT INVOLVING A MISADMINSTRATION DURING EYE TREATMENT "Event description: A pterygium patient was scheduled to receive a 42.5 second treatment utilizing a 100 millicurie Srontium-90 sealed source manufactured by 3M Company, model number 6D1A. The dosimetrist programmed the manual timer for 4 minutes and 25 seconds. During the treatment, the physician questioned the treatment time and it was terminated after 2 minutes and 30 seconds. The prescribed dose was 20 Gy. The patient received 70.59 Gy. The patient and the physician were notified of the misadministration. The licensee notified the Division the same day of the event. The licensee will submit a written report within 15 days. This incident is reportable under 1200-2-5-.32 (79) (e) (4) of 'State Regulations for Protection Against Radiation.'" TN Event Report ID No.: TN-04-035 | General Information or Other | Event Number: 40613 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM Licensee: GLOBAL GEO ENGINEERING Region: 4 City: WEST COVINA State: CA County: License #: 6899-30 Agreement: Y Docket: NRC Notified By: BARBARA HAMRICK HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 03/27/2004 Notification Time: 19:00 [ET] Event Date: 03/26/2004 Event Time: 22:00 [PST] Last Update Date: 03/27/2004 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): DAVID GRAVES (R4) PATRICIA HOLAHAN (NMSS) AARON DANIS (TAS) VICTOR GONZALES (MEX) | Event Text STATE LICENSEE, GLOBAL GEO ENGINEERING, REPORTED A TROXLER GAUGE WAS STOLEN FROM A TECHNICIAN'S TRUCK. A Troxler moisture/density gauge, Model 3430, with nominal activity of 10 mCi Cs-137 and 30 mCi Am-241, was stolen from the back of a flat bed truck sometime after 10:00 pm on 3/26/04, and before 5:00 am 3/27/04. The truck was parked at the technician's residence in West Covina. The technician involved worked late last night, and took the gauge home and left it chained to the flat bed truck overnight. The licensee contacted the West Covina PD. The licensee will be offering a $500 reward for the return of the gauge. | Power Reactor | Event Number: 40630 | Facility: POINT BEACH Region: 3 State: WI Unit: [1] [2] [ ] RX Type: [1] W-2-LP,[2] W-2-LP NRC Notified By: JIM WILSON HQ OPS Officer: ARLON COSTA | Notification Date: 03/31/2004 Notification Time: 18:02 [ET] Event Date: 03/31/2004 Event Time: 07:57 [CST] Last Update Date: 03/31/2004 | Emergency Class: NON EMERGENCY 10 CFR Section: 26.73 - FITNESS FOR DUTY OTHER UNSPEC REQMNT | Person (Organization): MICHAEL PARKER (R3) TERRY REIS (NRR) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 1 | N | Y | 92 | Power Operation | 92 | Power Operation | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text NON-LICENSED EMPLOYEE TESTED POSITIVE FOR ALCOHOL A non-licensed supervisor tested positive for alcohol during a "for cause" test. A review of the employee's work concluded that the individual had not been engaged in safety-related activities. The individual has been denied access to Point Beach Nuclear Plant and to all other Nuclear Management Company, LLC (NMC) sites. Contact the Headquarters Operations Officer for additional details. The licensee notified the NRC Resident Inspector. | Power Reactor | Event Number: 40631 | Facility: SAINT LUCIE Region: 2 State: FL Unit: [1] [ ] [ ] RX Type: [1] CE,[2] CE NRC Notified By: JEFF ABERNETHY HQ OPS Officer: ARLON COSTA | Notification Date: 03/31/2004 Notification Time: 19:28 [ET] Event Date: 03/31/2004 Event Time: 18:56 [EST] Last Update Date: 03/31/2004 | Emergency Class: UNUSUAL EVENT 10 CFR Section: 50.72(a) (1) (i) - EMERGENCY DECLARED | Person (Organization): JOEL MUNDAY (R2) MICHAEL JOHNSON (NRR) SUSAN FRANT (DIRO) GIL AGUIRRE (DHS) MIKE EACHES (FEMA) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text UNUSUAL EVENT DECLARED DUE TO REACTOR COOLANT SYSTEM LEAKAGE GREATER THAN 10 GPM On 3/31/04, Saint Lucie Unit 1 was in a refueling outage when it experienced a leak-by which appeared to be at a Volume Control Tank to Hold Up Tank divert valve off the Shutdown Purification System. The Reactor Coolant System (RCS) leakage was greater than ten gallons per minute as indicated in the Control Room. The Facility declared an Unusual Event at 1856 EST since the RCS leakage was greater than ten but less fifty gallons per minute. Refueling activities were stopped as a result of the incident. The RCS leakage was isolated and the Unusual Event was terminated at 1915. The licensee has notified local, state and other government agencies through the ring down phone system. The NRC Resident Inspector will be notified. | Power Reactor | Event Number: 40632 | Facility: WATERFORD Region: 4 State: LA Unit: [3] [ ] [ ] RX Type: [3] CE NRC Notified By: ROBERT MURILLO HQ OPS Officer: MIKE RIPLEY | Notification Date: 04/01/2004 Notification Time: 00:44 [ET] Event Date: 03/31/2004 Event Time: 19:19 [CST] Last Update Date: 04/01/2004 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(ii)(B) - UNANALYZED CONDITION OTHER UNSPEC REQMNT | Person (Organization): DALE POWERS (R4) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text NEW WORST CASE SINGLE FAILURE MAY EXCEED 10 CFR 46 ACCEPTANCE CRITERION FOR SBLOCA "A new worst case single failure was identified on 03-31-04 for the small break LOCA analysis of record due to a postulated loss of a DC power bus. This condition may result in the analysis of record exceeding 10 CFR 50.46 acceptance criterion of 2200 F when a small break LOCA with this failure is postulated. "The current small break LOCA analysis of record assumes a single failure of one Emergency Diesel Generator (EDG) and credits flow from one charging pump. The peak cladding temperature for the analysis of record is 1929 F compared to the acceptance criteria of less than or equal to 2200 F. Half of the flow from a charging pump is assumed to go to the RCS and half is assumed to flow out the break. It was identified on 03-31-04 that a single failure of a DC power bus would be more limiting than the currently assumed single failure of an EDG. The DC bus failure will result in the EDG failure to start and also cause a charging loop isolation valve to the RCS to fail closed on loss of DC power. The other charging flow path to the RCS is on the assumed broken RCS leg so it is assumed to be spilled to the containment resulting in no charging flow to the RCS. Therefore, no charging flow would be delivered to the RCS as assumed in the current small break LOCA analysis of record. This condition has not been analyzed. "Engineering judgment indicates that in the event of a small break accident the 10 CFR 50.46 acceptance criterion of 2200 F may be exceeded if the charging flow is not credited in the analysis of record. Therefore, this condition is reportable pursuant to 10 CFR 50.46 and 10 CFR 50.72(b)(3)(ii)(B). "The current conservatism in the analysis of record and previous Westinghouse SBLOCA non-design basis scoping analyses using the NOTRUMP code provide assurance the plant is operating in a safe manner and is operable. The NOTRUMP analyses included cases with no changing flow. The peak clad temperature for these analyses were significantly below the acceptance criteria of 2200 F by more than 200 F. Thus, if an analysis were performed for Waterford 3 with the NOTRUMP code there is reasonable assurance due to the large margins that acceptable results would be achieved without any charging flow. "This report is based on conservative judgment and available information. This report may be retracted based on the results of further evaluation." The licensee notified the NRC Resident Inspector. | |