Event Notification Report for December 18, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/17/2002 - 12/18/2002 ** EVENT NUMBERS ** 39442 39451 39452 39453 39454 39455 39456 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39442 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: IOWA DEPARTMENT OF PUBLIC HEALTH |NOTIFICATION DATE: 12/12/2002| |LICENSEE: IOWA METHODIST MEDICAL CENTER |NOTIFICATION TIME: 15:57[EST]| | CITY: DES MOINES REGION: 3 |EVENT DATE: 12/03/2002| | COUNTY: STATE: IA |EVENT TIME: [CST]| |LICENSE#: 0310-1-77-HDR AGREEMENT: Y |LAST UPDATE DATE: 12/12/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |PATRICK HILAND R3 | | |JIM LYNCH R3 | +------------------------------------------------+TOM ESSIG NMSS | | NRC NOTIFIED BY: GEORGE JOHNS | | | HQ OPS OFFICER: MIKE NORRIS | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING MEDICAL MISADMINISTRATION | | | | "The licensee reported a medical misadministration involving a High Dose | | Rate Afterloader. The patient treatment plan required 20 steps in a | | treatment with the stepping distance of 0.5 centimeters. The licensee | | reported that the stepping distance was actually 1.0 centimeter. (The cause | | of the deviation has not yet been determined.) The deviation resulted in | | an unplanned dose to an unintended site. The exposure was to 10 centimeters | | outside the planned treatment area. The dose has not yet been determined." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39451 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 12/17/2002| | UNIT: [1] [] [] STATE: ME |NOTIFICATION TIME: 09:57[EST]| | RXTYPE: [1] CE |EVENT DATE: 12/17/2002| +------------------------------------------------+EVENT TIME: 06:50[EST]| | NRC NOTIFIED BY: BILL BRYANT |LAST UPDATE DATE: 12/17/2002| | HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |DANIEL HOLODY R1 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Decommissioned |0 Decommissioned | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO DUCK HUNTERS NEAR PLANT SITE | | | | Notified by the licensee that they made offsite notifications to the FBI, | | Maine Game Warden, and the Lincoln County, Maine Sheriff's Office due to | | duck hunters shooting in the direction of the plant from an island 50-100 | | feet away from plant property. There were no injuries to plant personnel | | and no damage to plant property. The hunters were approached by plant | | security personnel and subsequently found another place to hunt. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 39452 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: COLORADO DEPT OF HEALTH |NOTIFICATION DATE: 12/17/2002| |LICENSEE: PSI CORPORATION |NOTIFICATION TIME: 10:52[EST]| | CITY: WHEAT RIDGE REGION: 4 |EVENT DATE: 12/17/2002| | COUNTY: STATE: CO |EVENT TIME: [MST]| |LICENSE#: 928-02 AGREEMENT: Y |LAST UPDATE DATE: 12/17/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |LINDA HOWELL R4 | | |LARRY CAMPER NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: PHILIP EGIDI | | | HQ OPS OFFICER: HOWIE CROUCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT DUE TO LOST TROXLER DENSITY GAUGE | | | | "At about 4:45 PM [CST] our time last evening (12/16/02) we received a call | | from PSI Corporate in Illinois. Their Colorado license number is 928-02 for | | the Wheat Ridge Office. They reported a lost moisture-density gauge which | | apparently fell out of the back of a truck on a highway construction project | | located on Hwy 85, between Hwy 7 & 136th earlier in the day. According to | | the RSO [Radiation Safety Officer], the technician admitted that the device | | was not secured in the back of the truck during movement. It is not clear | | yet whether the tailgate was down or not. PSI reported the gauge loss to | | CSP [Colorado State Police] and Adam's County [Sheriff's Office]. They have | | also issued a reward for the return of the device. Visual Inspection of the | | shoulder and median failed to find the device, which was reported to be in | | the case. RSO claims that the case is clearly marked with PSI's phone | | number and address, and is properly labeled according to regulatory | | requirements. | | | | "It is a Troxler 3411-B, SN 12179." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39453 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 12/17/2002| | UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 10:59[EST]| | RXTYPE: [1] W-4-LP |EVENT DATE: 12/17/2002| +------------------------------------------------+EVENT TIME: 06:55[EST]| | NRC NOTIFIED BY: R. STRICKLAND |LAST UPDATE DATE: 12/17/2002| | HQ OPS OFFICER: GERRY WAIG +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |DANIEL HOLODY R1 | |10 CFR SECTION: | | |ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SEABROOK EMERGENCY OFF-SITE SIRENS INOPERABLE | | | | "There was a simultaneous inoperability of Mass. Emerg. Mgt. Agency | | Framingham and Tewksbury Region 1 siren activation equipment for [greater | | than] 1 hour. This is reportable per 10 CFR 50.72 (b)(3)xiii. | | This condition has been corrected (~0900 today). | | Both systems relied on a single uninterruptable power supply which had | | failed. This single failure vulnerability was previously identified and is | | scheduled to be modified in Jan. 2003." | | | | The licensee notified the NRC Resident Inspector of this event. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39454 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 12/17/2002| | UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 12:24[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/29/2002| +------------------------------------------------+EVENT TIME: 09:17[EST]| | NRC NOTIFIED BY: DON BRADLEY |LAST UPDATE DATE: 12/17/2002| | HQ OPS OFFICER: GERRY WAIG +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |PAUL FREDRICKSON R2 | |10 CFR SECTION: | | |AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 60 - DAY OPTIONAL 10 CFR 50.73 REPORT - INVALID ACTUATION OF THE AFW SYSTEM | | | | "60 DAY REPORT - INVALID ACTUATION OF SPECIFIED SYSTEM - This 60-day | | optional report as allowed by 10 CFR 50.73(a)(1), is being made under the | | reporting requirement in 10 CFR 50.73 (a)(2)(iv)(A) to describe an invalid | | actuation of a specified system, specifically the Auxiliary Feedwater (AFW) | | system. On October 29, 2002, at 0917, with Unit 1 in MODE 1 at 100% power, | | an invalid signal was generated on Train A of the AFW system during | | auxiliary safeguards testing. During the performance of resistance checks, | | technicians reported hearing relay chattering inside the # 1 AFW pump | | turbine control panel. Following the autostart of the 1A motor driven AFW | | pump, increased AFW flow was noted for steam generators 1A and 1B. This was | | indicative that valves in Train A of the AFW system had automatically | | repositioned, in addition to the 1A motor driven pump automatically | | starting. The pump was subsequently secured and the AFW system was returned | | to standby readiness. This was considered a partial system/train actuation. | | During this event, the AFW system performed as expected. This event was | | entered into the site specific corrective action program for resolution." | | | | The NRC Resident Inspector will be notified of the event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 39455 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: STEEL OF WEST VIRGINIA |NOTIFICATION DATE: 12/17/2002| |LICENSEE: STEEL OF WEST VIRGINIA |NOTIFICATION TIME: 13:45[EST]| | CITY: HUNTINGTON REGION: 2 |EVENT DATE: 12/16/2002| | COUNTY: CABELL STATE: WV |EVENT TIME: 13:00[EST]| |LICENSE#: 47-16310-02 AGREEMENT: N |LAST UPDATE DATE: 12/17/2002| | DOCKET: 03028692 |+----------------------------+ | |PERSON ORGANIZATION | | |PAUL FREDRICKSON R2 | | |TOM ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: STEVE POWELL | | | HQ OPS OFFICER: MIKE RIPLEY | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |ISAF 30.50(b)(2) SAFETY EQUIPMENT FAILUR| | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED SOURCE HOLDER ON STEEL LEVEL GAUGE | | | | At 1345 EST on 12/17/02, the licensee reported that at approximately 1300 | | EST on 12/16/02, a radioactive source holder on a molten steel level gauge | | was damaged from molten metal at the Steel of West Virginia facility in | | Huntington, WV. The gauge is a Kay-Ray, Model # 7060SD, Serial # S93K0407. | | The gauge contains 500 millicuries of cesium-137. The molten metal | | penetrated the outer casing on the holder and melted the lead shielding. | | The holder was placed in a shielded container and moved to a secure | | location. The licensee is making arrangements for disposal. A radiation | | survey of the area was conducted and no contamination or abnormal readings | | were detected. The licensee notified NRC Region 2. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39456 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 12/17/2002| | UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 15:12[EST]| | RXTYPE: [1] W-4-LP |EVENT DATE: 12/17/2002| +------------------------------------------------+EVENT TIME: 12:40[CST]| | NRC NOTIFIED BY: EURMAN HENSON |LAST UPDATE DATE: 12/17/2002| | HQ OPS OFFICER: GERRY WAIG +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |LINDA HOWELL R4 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Hot Standby |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION TO STATE OF PLANT OUTAGE EXCEEDING 3 DAYS | | | | At 1240, 12/17/02, Callaway Plant notified the Missouri Public Service | | Commission (MPSC) of a forced outage lasting longer than three days. This | | notification was performed in accordance with 4CSR240-20.080(3)(B) and | | included the following information: | | | | On Saturday, December 14, 2002, at 0420 the Callaway Plant shutdown while | | preparing to secure a condensate pump located in the non-radioactive | | secondary system. While shutdown, problems were discovered with a steam | | driven auxiliary feedwater pump and these problems had to be corrected prior | | to returning the plant to service. Repairs to the steam driven auxiliary | | feedwater pump have been completed and it is anticipated that the Callaway | | Plant will return to service on December 17, 2002. | | | | This ENS notification is being made in accordance with I0CFR50.72(b)(2)(xi) | | for notification to another government agency. | | | | The licensee has notified the NRC Resident Inspector of this event. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021