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
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|Power Reactor |Event Number: 37077 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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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