ML19345A821

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Final Deficiency Rept Re 800919 Notification of Installation of Approx 600 safety-related Component Supports W/O Procedural Controls.Reinsp Determined No Corrective Action Necessary.Issue Not Reportable Per 10CFR50.55e
ML19345A821
Person / Time
Site: Marble Hill
Issue date: 11/20/1980
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 8011250289
Download: ML19345A821 (2)


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PUBLIC M

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SERVICE M INDIANA ~1

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o S. W. Shields 'N ' ._

  • Senior Vice Presdent- S 3 ~l,;

Nuclear Division Nove'.;ber r 20, 1980 ?

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Mr. James G. Keppler, Director Docket Nos.: STN 50-546 U. S. Nuclear Regulatory Commission STN 50-547 Region III Construction Permit Nos.:

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 19, 1979, Mr. J. U. Bott of Public Service Company of Indiana, Inc. (PSI) notified your office of a potentially reportable item as required by 10 CFR 50.55(e) . Prior to the suspension of safety-related construction activities, Cherne Contracting Corporation (CCC) had installed approximately 600 safety-related component supports without procedural controls for such installation. This work had been performed in accordance with CCC's welding process sheet for NF welds and approved architect-engineer hanger design drawings.

Since that time,CCC has written a procedure controlling safety-related component support installation which has been reviewed and approved by PSI. It was then determined by reinspection that the approximately 600 component supports previously inspected were in compliance with this approved procedure. The investigation to determine reportability of 8 this item discussed in the PSI interim report of October 26, 1979, is now complete,and based on the reinspection results,it has been determined that no corrective action is necessary. Since this item would not have affected adversely the safety of operations of the plant, it is not reportable under 10 CFR 50.55 (e) . If you have any questions on this matter, please feel free to contact me.

Sincerel;

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S. W. Shields TDG/cq \

8011250 2.1 #\

P.O. Box 190. New Wasnington, Indiana 47162 812. 293.4441

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PUBUC SERVICE INDIANA Letter: Jarnes G. Keppler November 20, 1980 cc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555

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E. R. Schweibins, P. E J. J. Harrison

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