ML20150B696

Advises That Failure of Control Blade Safety 2 Clutch Indicating Lamp Constitutes Ro,Per 880613 Telcon

ML20150B696
Person / Time
Site:	05000083
Issue date:	06/13/1988
From:	Whaley P FLORIDA, UNIV. OF, GAINESVILLE, FL
To:	Grace N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20150B685	List: ML20150B682 ML20150B696
References
NUDOCS 8807120128
Download: ML20150B696 (2)

Text

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NUCLEAR ENGINEERING SCIENCES DEPARTMENT Nuclear Reactor Facility University of Florida = . T. *

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" Phone (904) 3921429. To:e 56330 June 13, 1938 Nuclear Regulatory Comission Suite 2900 101 Marietta Street, N.W.

Atlanta , GA 30323 Attention: J. Nelson Grace Regional Administra tor, Region II Re: University of Florida Training Reactor Facility License: R-56, Docket No. 50-83 As per telephone call of 13 June 1988, relative to failure of Control Blade Safety 2 clutch status indicating lamp, the Reactor Safety Review Subcomittee has reviewed and concluded that this event constitutes a potentially reportable cecurrence per Tech-nical Specifications 6.6.2( 3)(d). The RSR3 has instructed NRC F' notification per Section 6.6.2 of the UPTR Technical Specifica-tions.

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• 1 y ATTACHMr"v iII y University of Florida Technical Specifications 6.6.2 Special Reports There shall be a report not later than the following working day by telephone and confirmed in writing by telegraph or similar conveyance to the Commission, to be followed by a written report that describes the circumstances of the event within 14 days of any of the following:

(3) any of the following:

(d) an unanticipated or uncontrolled change in reactivity greater than one dollar (Reactor trips resulting from a known cause are excluded.)

Reactor Trip: A reactor trip is considered to occur whenever one of the two fo'. lowing actions take place:

(1) Rod-Drop Trip -- a gravity drop of all control blades into the reactor core as a result of terminating electrical power to the blade drive magnetic clutches.

(2) Full-Trip -- the water is dumped from the reactor core by the safety actuation of the dump valve in addition to the rod-drop trip.

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