ML20083D956

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Supplemental Final Deficiency Rept Re Potential for Erroneous Steam Generator Level Indications During High Energy Line Breaks Inside Containment.Initially Reported on 800116.Item Not Reportable Under 10CFR50.55(e)
ML20083D956
Person / Time
Site: Marble Hill
Issue date: 12/16/1983
From: Shields S
PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10CFR-050.55E, 10CFR-50.55E, SVP-0164-83, SVP-164-83, NUDOCS 8312280373
Download: ML20083D956 (1)


Text

'r bh18 PUBLIC December 16, 1983 SERVICE S80-03 SVP-0164-83 El A S. W. Shields Senior Vice President .

Nuclear Division Mr. James G. Keppler, Docket Nos.: STN 50-546 Regional Administrator STN 50-547 U. S. Nuclear Regulatory Commission Construction Permit Nos.:

Region III CPPR - 170 799 Roosevelt Road CPPR - 171 Glen Ellyn, Illinois 60137 Marble Hill Nuclear Generating Station - Units 1 and 2

Dear Mr. Keppler:

On January 16, 1980, Mr. C. E. Chmielewski of Public Service Company of Indiana, Inc. (PSI) provided telephone notification to your office of a potentially reportable item as required by 10 CFR 50.55(e). This item involved the potential for erroneous steam generator level indications during high energy line breaks inside containment. On February 6,1980, PSI provided a final report on this item. In the final report PSI committed to monitor the development of a Westinghouse temperature compensation modification. Since that time, plant specific analyses evaluating the magnitude of steam generator level measurement errors have shown that neither of the Westinghouse proposed compensation systems will be necessary at Marble Hill. As a result of this new information no system or equipment modifications are neccssary. This also means that this item is not reportable under the provisions of 10 CFR 50.55(e). If you have any questions regarding this matter, please contact me at your convenience.

Sincerely, l 8312280373 831216 g DR ADOCK 05000546 l S. W. Shields i

PDR

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