U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/09/2005 - 06/10/2005 ** EVENT NUMBERS ** | General Information or Other | Event Number: 41749 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL Licensee: MIAMI CHILDREN'S HOSPITAL Region: 1 City: MIAMI State: FL County: MIAMI-DADE License #: 993-1 Agreement: Y Docket: NRC Notified By: CHARLES ADAMS HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/07/2005 Notification Time: 07:37 [ET] Event Date: 06/06/2005 Event Time: [EDT] Last Update Date: 06/07/2005 | Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): TODD JACKSON (R1) TOM ESSIG (NMSS) | Event Text FLORIDA AGREEMENT STATE REPORT - LOST AM-241 SOURCE The following information was obtained from the State of Florida Bureau of Radiation Control via e-mail: "Searle marker containing Am-241 source was reported missing from Children's Hospital Miami. Device was bought in early 1980's. This source is in a 'storage only' mode and was last seen during the May 2005 inventory. Florida is investigating." The device description is a Searle marker, manufacturer and model unknown, serial number ACM-24, containing 14 milliCuries of Am-241. Florida Incident Number FL05-088 | Power Reactor | Event Number: 41759 | Facility: DUANE ARNOLD Region: 3 State: IA Unit: [1] [ ] [ ] RX Type: [1] GE-4 NRC Notified By: BOB MURRELL HQ OPS Officer: JOHN KNOKE | Notification Date: 06/09/2005 Notification Time: 14:12 [ET] Event Date: 04/14/2005 Event Time: 06:13 [CDT] Last Update Date: 06/09/2005 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION | Person (Organization): JULIO LARA (R3) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) ACTUATION DURING POST MAINTENANCE TESTING "This 60-day telephone notification is being made under reporting requirements specified by 10CFR50.73 (a)(2)(iv)(A) to describe an invalid actuation of a containment isolation signal affecting more than one system. "At 0613 on April 14, 2005, with the Duane Arnold Energy Center (DAEC) shutdown for refueling, a PCIS Group 7 (Well Water and RBCCW Drywall Isolation Valves) signal was generated during post-maintenance testing on MO-4841A. This event was caused by an error in work planning which resulted in an incorrect relay being listed in a work order. When a jumper was installed across the terminals of the incorrect relay, an isolation signal was generated. "All equipment responded in accordance with the plant design. Specifically, all isolations were complete and successful. "There were no safety consequences or impacts on the health and safety of the public. The event was entered into DAEC's corrective action program for resolution." The licensee will notify the NRC Resident Inspector. | Power Reactor | Event Number: 41760 | Facility: DUANE ARNOLD Region: 3 State: IA Unit: [1] [ ] [ ] RX Type: [1] GE-4 NRC Notified By: BOB MURRELL HQ OPS Officer: JOHN KNOKE | Notification Date: 06/09/2005 Notification Time: 14:12 [ET] Event Date: 04/14/2005 Event Time: 15:40 [CDT] Last Update Date: 06/09/2005 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION | Person (Organization): JULIO LARA (R3) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) ACTUATION WHILE PERFORMING RE-TERMINATION. "This 60-day telephone notification is being made under reporting requirements specified by 10CFR50.73 (a)(2)(iv)(A) to describe an invalid actuation of a containment isolation signal affecting more than one system. "At 1540 on April 14, 2005, with the Duane Arnold Energy Center (DAEC) shutdown for refueling, an invalid Group 3 isolation on the 'A' side of PCIS occurred. Group 3 isolation signals were generated for Primary Containment Isolation Valves for Drywell and Torus Ventilation, and Purge, Containment Nitrogen Compressor Suction and Discharge; Recirculation Pump Seals, and Post Accident Sample System. "This event was caused while landing a lead on a relay terminal. During this activity the lead brushed another terminal, causing a fuse to blow which resulted in the inadvertent Group 3 isolation. "All equipment responded In accordance with the plant design. Specifically, all actuations were complete and successful. "There were no safety consequences or impacts on the health and safety of the public. The event was entered into DAEC's corrective action program for resolution." The licensee will notify the NRC Resident Inspector. | |