ML20041F125

Ro:On 820303,instrumentation Components That Monitor Primary Coolant Flow & Core Outlet Temp Would Not Provide Scram for Power Failure.Cause Not Given.Components Reworked to Provide Scram

ML20041F125
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	03/05/1982
From:	Dimeglio A RHODE ISLAND, STATE OF
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8203160212
Download: ML20041F125 (1)

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j STATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS RHODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center South Ferry Road ,,g l

Narragansett, R. I. 02882 -

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March 5, 1982 ,

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Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission IEECEfVED 9 Region 1 b 631 Park Avenue 2 MARI'57982=0 hl' King of Prussia, Pa. 19406

- a License R-95 /f Docket 50-193  %

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Gentlemen:

On March 3, 1982, during maintenance of the reactor system, we learned that components in the process instrumentation, which monitor primary coolant flow and primary coolant core outlet temperature, would not provide a scram for power failure. After approval of our Reactor Utilization Committee (safety review com-mittee), the components were reworked so that in addition to pro-viding a scram for loss of flow and high temperature, they would cause a scram for power loss to individual components.

At no time during the almost 18 years of operating history has a power failure occurred which did not shut down the reactor. In addition, at no time did process control instrumentation compo-nents fail without causing a shutdown of the reactor.

This situation was discussed by telephone with R. Starostecki, R.

Gallo and E. Greenman of NRC, Region 1 on March 3, 1982.

Very truly yours, s v:rt&M A. Francis DiMeglio Director AFD:ag cc: RUC RIAEC 8203160212 820305 }h $1 &

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