ML19249F317

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Forwards IE Info Notice 79-22, Qualification of Control Sys. No Action Required
ML19249F317
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 09/14/1979
From: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Arneal A
SOUTHERN CALIFORNIA EDISON CO.
References
NUDOCS 7910110306
Download: ML19249F317 (1)


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NUCLEAR REGULATORY COMMISSION nEGION V U, Q'.',.g 'y j O

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9 V!ALNU T CR E E K. CALIFORNI A 9 *,59G September 14, 1979 Docket flo. 50-206 Southern California Ediscn Ccmpany P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Attention:

Mr. A. L. Arenal Vice President, Advanced Engineering Gentlemen:

The enclosed Information !!otice No. 79-22 providee information with regard to a potential unreviewed safety question involving high energy lines and control systems.

Sincerely',

l Ylirm.fL-R. H. Engelken Director

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Enclosures:

1.

Information Notice 79-22 2.

List of IE Information tiotices Issued in Last Six Months cc w/ enclosures:

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S Accession No: 79082201112 SSINS:

6870 UNITED STATES NUCLEAR PsEGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMEllT WASHINGTON, D.C.

20555 September 14, 1979 IE Infomation Notice No. 79-22 OUALIFICATION OF CONTROL SYSTEMS Public Service Electric and Gas Company notified the NRC of a potential unreviewed safety question at their Salem Unit 1 facility. This notification was based on a continuing review by Westinghouse of the environmental qualifications of equipment that they supply for nuclear steam supply systems. Based on the present status of this effort, Westinchouse has informed their customers that the performance of non-safety grade equipment subjected to an adverse environment could impact the protective functions performed by safety grade equipment. These non-safety grade systems include:

Steam generator power operated relief valve control system Pressurizer power operated relief valve control system Main feedwater control system Automatic rod control system These systems could potentially malfunction due to a $igh energy line break inside or outside of containment. NRC is also concerned that the adverse environment could also give erroneous information to the plant operators.

Westinghouse states that the consequences of such an event could possibly be more limiting than results presented in Safety Analysis Reports, however, Westinghouse also states that the severity of the results can be limited by operator actions together with operating characterisitics of the safety systems.

Further, Westinghouse has recommended to their customers that they review their systems to determine whether any unreviewed safety questions exist.

This Infomation Notice is provided as an early notification of a possibly significant matter.

It is expected that recipients will review the information for possible applicability to their facilities.

No specific action or response is requested at this time.

If NRC evaluations so indicate, further licensee actions may be requested or required.

If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional.0ffice.

No written response to this Information Notice is required.

1076 081

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