Event Notification Report for June 13, 2000
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/12/2000 - 06/13/2000 ** EVENT NUMBERS ** 37077 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37077 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 06/12/2000| | UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 11:50[EDT]| | RXTYPE: [1] W-2-LP |EVENT DATE: 06/12/2000| +------------------------------------------------+EVENT TIME: 09:15[CDT]| | NRC NOTIFIED BY: GARY HARRINGTON |LAST UPDATE DATE: 06/12/2000| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DAVID HILLS R3 | |10 CFR SECTION: | | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 71 Power Operation |71 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADEQUATE SERVICE WATER SYSTEM FLOW TO EDGs (HISTORICAL REPORT) | | | | "On June 2, 2000, Kewaunee completed a scheduled refueling outage. During | | the outage, comprehensive flow data was measured on the plant's service | | water system. Subsequent analysis of the flow data revealed that for less | | than one hour on August 8, 1991, both of the redundant diesel generators | | could have had cooling water flow below design basis post-accident | | requirements. The cause of the condition is a combination of elevated | | cooling water temperatures, conservative calculation assumptions using | | recent data, and a previously unidentified design problem that results in | | reduced flow through the diesel coolers. The design problem occurs due to | | system backpressure caused by the diesels' cooling water discharges being | | connected to a common header. During the outage, the diesel generator heat | | exchangers were replaced for reasons unrelated to this report. The new heat | | exchangers' increased capacity precludes recurrence." | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+
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