ML19259C801
| 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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c ATTACHED IS A PART 21 REPORT FROM IE t%IL UNIT-- ROEM 359E/W J
PART 21 IDBfflFICATION 10.
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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.
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.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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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.
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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.
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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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Should you require further infonnation, please contact this office..
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