ML20071P186

Final Deficiency Rept Re Mechanically Cracked Embedded Box Beam Plate.Initially Reported on 830503.Alternative Welding Methods Investigated.Similar Embedded Plate Welds

ML20071P186
Person / Time
Site:	Marble Hill
Issue date:	05/31/1983
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, S83-24, SVP-0096-83, SVP-96-83, NUDOCS 8306070377
Download: ML20071P186 (2)

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PUBLIC SERVICE INDIANA S. W. Shields May 31, 1983 senior vice President .

S83-24 Nuclear Division SVP-0096-83 Mr. James G. Keppler, Dacket Nos.: STN 50-546 Regional Administrator STN 50-547 U. S. Nuclear Regulatory Commission Construction Permit Nos.:

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

Dear Mr. Keppler:

On May 3, 1983, Mr. L. G. Yeager of Public Service Company of Indiana, Inc. (PSI) notified your office of a potentially reportable item as required by 10 CFR 50.55(e). In an attempt to straighten a box heam in Unit 2 containment, Marble Hill's civil contractor mechanically cracked the embedded plate that the box beam was attached to. After removal of the box beam other cracks were discovered in the lug to embedded plate welds.

A reinspection of similar lug to embedded plate welds also revealed some cracking. The subject embedded plates and box beams act as part of the structural support network for safety related piping systems.

PSI engineering persennel determined that the weld cracking was due to the welding method being used. Alternative welding methods were investigated and thoroughly tested. One nethod has been found to be  %

acceptable and the civil contractor has been released to work in accordance with this new method. Another method is currently being tested and if the results are acceptable the contractor will also be allowed to use it. All similar welds on embedded plates in Unit 2 containment done to the superseded method have been removed and the areas will be rewelded using a PSI approved method, as mentioned above.

This letter is intended to fulfill the requirements of a final report as required by 10 CFR 50.55(e). If you have any questions regarding this matter, please contact me at your convenience.

Sin erely, 9306070377 830531 . / I/Z PDR ADDCK 05000547 S PDR S. W. Snields y/, g I[rb SWS/LGY/bak P. O. Box 190, New Washington, Indiana 47162 812. 289 .1000 JUN 2 1983

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.PUSUC-SERVICE

- INDIANA Letter: J. G. Keppler .riay 31, 1983 SVP-0096-83 cc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Comission Washington, D. C. 20555

-J. E. Konklin

J. F. Schapker i

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