ML19345C322

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Final Deficiency Rept Re Potential Deficiency Reported 800923 Involving Secy Y-21766 Stainless Steel Liner Work. Matl Substitution Submitted by Cb & 14 Ae Sargent & Lundy, Found Not Reportable Per 10CFR50.55e
ML19345C322
Person / Time
Site: Marble Hill
Issue date: 11/19/1980
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, NUDOCS 8012040394
Download: ML19345C322 (2)


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  • Senior Vice Presdent - lovember 19, 1930 Nuclear Onnsion g e 3 Mr. James G. Keppler, Director Docket Nos.: STN 50-546 U. S. Nuclear Regulatory Commission STN 50-547 Region III Construction Permit Mos.:

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

Dear Mr. Keppler:

On September 23, 1980, Mr. T. D. Geib of Public Service Company of Indiana, Inc. (PSI) notified your office of a potentially reportable item as required by 10 CFR 50.55(e) . Review of documentation packages associated with specification Y-2766, Stainless Steel Liner Work, revealed the substitution of certain types of materials for those allowed by the specification. It was not apparent upon preliminary investigation whether or not these material substitutions were allowed by previous review and approval of the architect-engineer or through reference in the material standards specified in Y-2766.

PSI has subsequently investigated this matter through its architect-engineer, Sargent & Lundy, and the contractor involved with specification Y-2766, Chicago Bridge & Iron (CB&I) . Research of correspondence over the last several years has revealed that all material substitutions

, except one were previously reviewed and approved by Sargent & Lundy.

CBI has since submitted a request for deviation to allow the use of the one unapproved material. Sargent & Lundy has reviewed this material substitution and approved its use. In conclusion, all material substitutions originally questioned are acceptable and will not require any corrective action. This item would not have adversely affected the safety of operations of the plant and therefore is not reportable under 10 CFR 50.55(e) .

If you have any questions on this matter, please feel free.to contact me.

Sincerely, S. W. Shields j TDG/cg b

l 3 IO P.O. Box 190, New Washington, Indiana 47162 812. 293.4441 803204o 3cM

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.J' PUBUC SERVICE INDANA Letter: James G. Keppler November 19', 1980 cc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Con: mission Washington, D. C. 20555 E. R. Schweibinz, P. E.

J. J. Harrison

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