Event Notification Report for June 23, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/20/2003 - 06/23/2003 ** EVENT NUMBERS ** 39952 39954 39955 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39952 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 06/20/2003| | UNIT: [1] [2] [] STATE: TN |NOTIFICATION TIME: 16:08[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/11/2003| +------------------------------------------------+EVENT TIME: 22:00[EDT]| | NRC NOTIFIED BY: JAY WHITWORTH |LAST UPDATE DATE: 06/20/2003| | HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |LEONARD WERT R2 | |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 Cold Shutdown |0 Cold Shutdown | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION TO STATE OF TENNESSEE MADE DUE TO LOSS OF POWER TO | | EMERGENCY SIRENS | | | | The following information was obtained from the licensee via facsimile: | | | | "On June 11, 2003, 23 of the 108 emergency sirens were out of service | | because of a storm passing through the area, causing power outages. The TVA | | Operations Duty Specialist notified the State of Tennessee of the loss of | | the sirens. This report is being made to NRC in accordance with 10 CFR | | 50.72(b)(2)(xi) as a situation, related to the health and safety of the | | public or on-site personnel, or protection of the environment, for which a | | news release is planned or notification to other government agencies has | | been made. As power was restored to the area, the sirens were returned to | | service. | | | | "This report is being made at this time since Sequoyah Operations personnel | | have become aware that the State of Tennessee was notified by the TVA | | Operations Duty Specialist on June 11, 2003." | | | | The TVA Operations Duty Specialist is based in a location different from the | | Sequoyah plant. | | | | The licensee has notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 39954 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: NUCOR STEEL |NOTIFICATION DATE: 06/21/2003| |LICENSEE: NUCOR STEEL |NOTIFICATION TIME: 13:50[EDT]| | CITY: CRAWFORDSVILLE REGION: 3 |EVENT DATE: 06/21/2003| | COUNTY: STATE: IN |EVENT TIME: 11:50[CST]| |LICENSE#: 13-25975-01 AGREEMENT: N |LAST UPDATE DATE: 06/21/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |KENNETH RIEMER R3 | | |C.W. (BILL) REAMER NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JEFF JORDAN | | | HQ OPS OFFICER: HOWIE CROUCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |ISAF 30.50(b)(2) SAFETY EQUIPMENT FAILUR| | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SOURCE HOLDER FRAME AND CONTROL SYSTEM DAMAGED | | | | | | On 6/21/03 at approximately 1150 CST, a source holder frame that houses a 1 | | Curie Am-241 source was damaged. The licensee, Nucor Steel, uses the source | | to determine steel strip thickness. The source holder and the source are | | intact and the source is retracted into the safe position. Only the metal | | frame that supports the source holder and the source control system was | | damaged. The manufacturer, Radiometric, has been contacted to repair the | | frame. The source is exposed using an air signal which is currently locked | | and tagged out by the licensee. | | | | Informed R3DO (Riemer) and NMSS EO (Reamer). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39955 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 06/22/2003| | UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 21:18[EDT]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 06/22/2003| +------------------------------------------------+EVENT TIME: 17:42[EDT]| | NRC NOTIFIED BY: ANDY BARTLIK |LAST UPDATE DATE: 06/22/2003| | HQ OPS OFFICER: BILL GOTT +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |KENNETH JENISON R1 | |10 CFR SECTION: |RICHARD WESSMAN IRO | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|HERB BERKOW NRR | |AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |3 A/R Y 100 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP WITH AFW ACTUATION | | | | The following information was obtained from the licensee via facsimile: | | | | "In order to support maintenance on feeder W-98 [Distribution Line], 345 KV | | Circuit Breaker #3 was opened. Indian Point 3 remained in service utilizing | | the feed via 345 KV Circuit Breaker #1. After Con Edison completed | | maintenance on W-98, at 17:42 [EDT] an attempt was made to close 345 KV | | Circuit Breaker #3. While attempting to close 345 KV Circuit Breaker #3, a | | fault occurred, resulting in an automatic Generator Trip, Reactor Trip and | | Turbine Trip. | | | | "Automatic Safety Features operated as required, with all control rods | | inserting. | | | | "Decay heat is being removed by the Steam Generators, with make up provided | | by Auxiliary Feedwater with steam being relieved to the Main Condenser. | | | | "Off site power feeders remained available. Off Site power is currently | | stable and providing power to all 480 Volt Safeguards Buses. Automatic | | start and operation of the Emergency Diesel 'G' was not required." | | | | The licensee has notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021