ML19259C801

Submits Info Concerning 790627 Rept Re Errors in Steam Generator Levels During Accident Conditions,Per 10CFR21

ML19259C801
Person / Time
Site:	North Anna
Issue date:	07/02/1979
From:	Brown S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-79-136-001 NUDOCS 7908150192
Download: ML19259C801 (4)

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ATTACHED IS A PART 21 REPORT FROM IE t%IL UNIT-- ROEM 359E/W J

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i uly 2 ,1979 Mr. James P. O'Reilly, Director Serial No. 539 Office of Inspection & Enforcement PSE&C/GLP:adw:me U. S. Nuclear Regulatory Co: mission Region II Docket No. 50-339 101 Marietta Street, Suite 3100 Atlanta, C-corgia 30303

Dear Mr. O'Reilly:

On June 27, 1979, a report was made under th'e provisions of ICCFR50.55(e) concerning errors that can occur in steam generator levels during accident con-ditions.

In accordance sith the reporting requirements of 10CFR21, the following in-fornation is submitted:

A. Name and address of reporting individual:

Mr. E. A. Baum, Executive Manager Licensing and Quality Assurance Vi ginia Electric and P wer Coccany P. O. Box 25656 Richmond, Virginia 23251 B. Facility, activity, and/or component affected:

Nortn Anna Power Station, Unit 2 Steam Generater Level Indication and Trip Signals.

C. .Name of firm const ucting the facilicy or su;; plying tne ccc;:enent.

activity or service:

Westi ghouse Electric Cor;;cration P. C. sox 355 Pittsburgh, Pennsylvania 15230

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D. Description of defect, deficiency, or failure to comply: _

We are infomed by Westinghouse that the heating of the S. team Generator level reference legs following a high energy line break inside contairment was not taken into account during the original Westinghouse analysis.

An increase in reference leg water column temperature will result in a decrease of the water column density with a con-

- sequent apparent increase in the indicated steam generator water level (i.e., apparent level exceeding actual level).

The error could result in a delay in reacning the tw Steam Generator Level Reactor trip. This could occur when the tem-peratures in the containment are in excess of 1100F.

E. Date of determination cf reportability:

June 27, 1979 F. Similar components, activities, ur services:

North Anna Unit 1, Surry Units 1 and 2 G. Corrective action which has been, is being or will be taken, the individual resconsible and the lengtn of time to cccplete the action:

The prcblem is being analyzed by Westinghouse to detemine the necessary actions to be taken, if any, to insure that these errors are accounted for and that the ap;ropriate safety system actions will occur as required in One safety analysis for Onis plant. The analysis is beir.g per fcmed as ex:enditicusly as pessiole, the results should be available witnin a very snort period of time.

H. Other information:

We feel tnat no imediate action is required at this time, a final report should be available as a part of the 30 day report on this item.

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3 Should you require further infonnation, please contact this office. .

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= SeniorVict/ President-Powerstayo Enginering and Construction

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