U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/08/2004 - 09/09/2004 ** EVENT NUMBERS ** | General Information or Other | Event Number: 41014 | Rep Org: SC DIV OF HEALTH & ENV CONTROL Licensee: KING ASPHALT INC Region: 1 City: LIBERTY State: SC County: License #: 436 Agreement: Y Docket: NRC Notified By: JEREMY HANNA HQ OPS Officer: ARLON COSTA | Notification Date: 09/03/2004 Notification Time: 15:47 [ET] Event Date: 09/03/2004 Event Time: 12:50 [EDT] Last Update Date: 09/03/2004 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): PAMELA HENDERSON (R1) PATRICIA HOLAHAN (NMSS) DONNA-MARIE PEREZ (TAS) | Event Text SC AGREEMENT STATE REPORT: STOLEN MOISTURE DENSITY GAUGE Upon returning from lunch, the King Asphalt Inc. technician noticed that the moisture density gauge had been missing from the storage box casing. The gauge was previously secured in the box casing stored on the pickup truck bed. The box locking mechanism appears to have been pried open in order to retrieve the gauge. The moisture density gauge is a Humboldt Model No.5001EZ, S/N 670, containing 11 milliCuries of Cs-137 and 44 milliCuries of Am-241:Be. A report of the stole gauge was filed with the Greenville, SC police. | General Information or Other | Event Number: 41015 | Rep Org: WISCONSIN RADIATION PROTECTION Licensee: UNIVERSITY OF WISCONSIN Region: 3 City: MADISON State: WI County: License #: 25-1323-01 Agreement: Y Docket: NRC Notified By: PAUL SCHMIDT HQ OPS Officer: ARLON COSTA | Notification Date: 09/03/2004 Notification Time: 15:41 [ET] Event Date: 09/03/2004 Event Time: 13:30 [CDT] Last Update Date: 09/03/2004 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): JULIO LARA (R3) SCOTT FLANDERS (NMSS) | Event Text WI AGREEMENT STATE: LOSS OF CONTROL OF RADIOACTIVE MATERIAL "On Friday, September 3, 2004 at approximately 1:30 p.m., the Wisconsin Radiation Protection Section (RPS) received a telephone call from the University of Wisconsin - Madison (license number 25-1323-01) informing the section of a lost Ir-192 source that had been inadvertently shipped to the University of Arizona Medical Center, Tucson, AZ. "Preliminary Information From the Licensee "On Monday, August 30, 2004, the University of Wisconsin - Madison calibration lab had completed calibration of a Standard Imaging, Model 1000+ reentrant well chamber (ion chamber used to determine brachytherapy seed dose) and shipped it back to the chamber owner, the University of Arizona Medical Center. Shortly after arrival, the U.A. Medical Center discovered that the chamber contained a 0.4 mCi [milliCurie] Iridium-192 brachytherapy seed that had been used during calibration. The U.A. Medical Center subsequently notified the U.W. Madison of the incident on Friday, September 3, 2004. "The licensee estimates that the dose rate from an unshielded 0.4 mCi Ir-192 seed source would be approximately 0.192 mR/hr at 1 meter. The licensee believes that the chamber shielded the source so the dose rate on the surface of the shipping container was negligible." | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | Power Reactor | Event Number: 41024 | Facility: CRYSTAL RIVER Region: 2 State: FL Unit: [3] [ ] [ ] RX Type: [3] B&W-L-LP NRC Notified By: LARRY MOFFATT HQ OPS Officer: JOHN MacKINNON | Notification Date: 09/08/2004 Notification Time: 03:11 [ET] Event Date: 09/08/2004 Event Time: 01:00 [EDT] Last Update Date: 09/09/2004 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(ii)(A) - DEGRADED CONDITION | Person (Organization): CAROLYN EVANS (R2) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 3 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text POTENTIAL REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAK LOCATED "At 0100 on September 8, 2004, while in Mode 3 conducting a Reactor Building walkdown after an unplanned reactor trip during Tropical Storm Frances, Crystal River Unit 3 identified a potential Reactor Coolant System pressure boundary leak located on a weld associated with a pressurizer level sensing line (upstream of reactor coolant isolation valve RCV-75). The cause of the leak is not known at this time, and the leak did not have a significant effect on plant operation. The last unidentified leak rates that were completed prior to the plant shutdown were 0.10 - 0.13 gpm. This defect in the primary coolant system is unacceptable per ASME Section XI. The condition is 8-Hour reportable per 10CFR 50.72 (b)(3)(ii)(A). The plant will be cooled down to Mode 5 and additional inspections and necessary repairs implemented. Dry boron crystal deposit are on the sensing line upstream of RCV-75 . See similar event reported by Crystal River Unit 3 on 10/04/03 (event # 40222) The NRC Resident Inspector was notified of this event by the licensee. * * * RETRACTED ON 9/9/04 AT 0424 EDT FROM LARRY MOFFATT TO GERRY WAIG * * * "At 0311 on 9/8/04, Crystal River Unit 3 made an 8-Hour ENS notification in accordance with 10CFR50.72 (b)(3)(ii)(A) concerning a potential Reactor Coolant System pressure boundary leak (Event Notification # 41024). The leak was presumed to exist based on the presence of white, crystalline material deposited on the pipe. The material has been sampled and does NOT contain boron. The presumed leak site has been cleaned and visually inspected with no evidence of a defect in the weld joint or pipe. These additional inspections have demonstrated that the material deposited on the pipe does NOT constitute pressure boundary leakage, and therefore EN 41024 is retracted." The licensee has notified the NRC resident inspector. | Power Reactor | Event Number: 41025 | Facility: ROBINSON Region: 2 State: SC Unit: [2] [ ] [ ] RX Type: [2] W-3-LP NRC Notified By: RAY CRANDALL HQ OPS Officer: GERRY WAIG | Notification Date: 09/08/2004 Notification Time: 08:41 [ET] Event Date: 09/08/2004 Event Time: 05:56 [EDT] Last Update Date: 09/08/2004 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION | Person (Organization): CAROLYN EVANS (R2) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION - HIGH WATER FLOW FROM LAKE ROBINSON DUE TO HEAVY RAIN "On 09/08/2004, at 0556 EDT, the H. B. Robinson site reached a condition that warranted notification of local and state government agencies of conditions with potential public safety consequences. "Due to rain from Tropical Storm Frances, the Lake Robinson water level rose to levels that required opening of valves to increase the discharge flow from the lake. At 0556, the discharge flow exceeded 1100 cubic feet per second. Unit 1 (adjacent fossil unit) procedures require the notification of local and state government agencies when the discharge flow exceeds this rate, due to the potential for downstream flooding. Notification of local and state agencies began at 0557 EDT. No press or media releases have been made. "Unit 2 continues to operate and there is no threat to plant equipment or operation due to this condition." The licensee has notified the NRC Resident Inspector. | Power Reactor | Event Number: 41027 | Facility: CRYSTAL RIVER Region: 2 State: FL Unit: [3] [ ] [ ] RX Type: [3] B&W-L-LP NRC Notified By: JON HUECKER HQ OPS Officer: STEVE SANDIN | Notification Date: 09/08/2004 Notification Time: 18:23 [ET] Event Date: 09/08/2004 Event Time: 14:45 [EDT] Last Update Date: 09/08/2004 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION | Person (Organization): CAROLYN EVANS (R2) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 3 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text EMERGENCY FEEDWATER SYSTEM ACTUATION "At 1445 on September 8, 2004, while in Mode 3 after an unplanned reactor trip during tropical storm Frances, Crystal River Unit 3 experienced a re-actuation of the B-Train of the Emergency Feedwater System. The Emergency Feedwater System had previously actuated during a Loss of Offsite Power experienced during Hurricane Frances and the B-Train actuation had procedurally been bypassed as part of the plant recovery. While In the process of restoring a Main Feedwater Pump to an operating condition, the signal bypassing the B-Train Emergency Feedwater actuation was momentarily removed due to unusual plant conditions present during recovery from the loss of power This resulted in the re-actuation of the B-Train of Emergency Feedwater. This condition is 8-Hour reportable per 10CFR50.72(b)(3)(iv)(B)(6). The re-actuation of the B-Train of Emergency Feedwater did not have a significant impact on plant operation and the associated equipment has been returned to a standby condition." The licensee informed the NRC Resident Inspector. | Power Reactor | Event Number: 41028 | Facility: SALEM Region: 1 State: NJ Unit: [ ] [2] [ ] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: M. STRAUBMULLER HQ OPS Officer: JOHN MacKINNON | Notification Date: 09/09/2004 Notification Time: 03:20 [ET] Event Date: 09/09/2004 Event Time: 01:06 [EDT] Last Update Date: 09/09/2004 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL | Person (Organization): HAROLD GRAY (R1) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text TURBINE TRIP/REACTOR TRIP "Salem Unit 2 experienced a Turbine Trip > P-9 which initiated a Reactor Trip. All rods fully inserted. Aux Feedwater auto start initiated on steam generator low-low level. The cause of the turbine trip is Generator Diff [Differential Current] or Loss of Field. Decay heat removal is via the steam dumps to the main condenser. All safety related systems are available and functioned as designed. The 500 KV breaker 2-10 was cleared and tagged prior to the trip. Upon the turbine/reactor trip, the 500KV breakers 1-9 and 9-10 opened as designed. Due to the 2-10, 1-9, 9-10 breakers being opened, the 500 KV transmission line 5037 is de-energized. Two offsite power sources are available and all 3 Emergency Diesel Generators are operable. The 5037 line will be energized following restoration from scheduled maintenance. There were no personnel injuries." The licensee stated that the NRC resident inspector and the local township were notified. | |