U-600947, Notification of Unusual Event:On 870524,motor-driven Feed Pump Regulating Valve 1FW-F004 Malfunctioned,Increasing Reactor Water Level.Cause Under Investigation.Valve Shifted to Manual Control W/No Response.Event Terminated Same Day

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Notification of Unusual Event:On 870524,motor-driven Feed Pump Regulating Valve 1FW-F004 Malfunctioned,Increasing Reactor Water Level.Cause Under Investigation.Valve Shifted to Manual Control W/No Response.Event Terminated Same Day
ML20214K931
Person / Time
Site: Clinton Constellation icon.png
Issue date: 05/26/1987
From: Spangenberg F
ILLINOIS POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
U-600947, NUDOCS 8705290099
Download: ML20214K931 (2)


Text

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i U- 600947

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L30-87(05 26)-L 1A.120 ILLINDIS POWER 00MPANY

~ CLINTON POWER STATION, P.o. BOX 678, CLINToN, ILLINOIS 61727

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10CFR50.47 May 26, 1987 Docket No. 50-461 U.S. Nuclear _ Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Clinton Power Station Notification of Unusual Event

Dear Sir:

Please find attached a summary report of the " Notification of Unusual Event (NOUE)" which occurred at Clinton Power Station on May 24, 1987. This summary report is submitted pursuant to Appendix 1 of NUREG-0654 (Revision 1) and Table 4-1 of the Clinton Power Station Emergency Plan. Please call me if you have any questions on this report.

Sincerely yours, F. A. Sp ge rg r Manager - Licensing'and Safety PJT/cke Attachment ec: Regional Administrator, Region III, USNRC W. Snell, Chief Emergency Preparedness Section B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Illinois Department of Nuclear Safety 8705290099 870526 PDR ADOCK 05000461 S PDR:

., Attcchacnt to U- 600947 1 of 1-Clinton Power Station Notification of Unusual Event On Sunday, May 24, 1987, at approximately 1800, with the reactor at 18% power, and the generator carrying 122 MWe, the motor driven feed pump regulating valve (1W-F004) malfunctioned causing reactor water level to increase.

The feed pump regulating valve was shifted from automatic to manual control, but the valve did not respond. At 1815, the water level

oscillations resulted in a power excursion which resulted in an automatic trip at 40% reactor power. The high flux trip is set at 40%

instead of 120% during the startup test program. A notification of.

Unusual Event was declared at 1815 and subsequently terminated at 1855.

An investigation into the failure of IWOO4 is ongoing.

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