ML20010F608

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Interim Deficiency Rept Re Spalling of Structural Concrete During Welding on safety-related Embedment Plates,Originally Reported on 810330.Data Gathered During Investigation of Vendor Welding Procedures Under Evaluation
ML20010F608
Person / Time
Site: Marble Hill
Issue date: 09/01/1981
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, S81-07, S81-7, NUDOCS 8109100421
Download: ML20010F608 (2)


Text

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PUBLIC SERVICE

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SR 09198N 9 INDIANA @O ug*%* 6 S. W. Shields

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Senior Vice President - g y Nuclear Division $$

September 1, 1981 S21-07 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 March 30, 1981, 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). During welding on safety related embedment plates by Cherne Contracting Corporation (CCC), PSI Quality Assurance personnel observed that a few plates were heated sufficiently to cause spalling of the structural concrete in which they were embedded. PSI questioned if such heating might reduce the strength of the concrete locally and consequently the load bearing capacity of the embedment plates.

Subsequent investigation revealed that CCC weieing procedures did not control concrete temperature during welding at concrete-steel interfacer, however, their procedures did include controls on maximum embedment plate temperature. CCC has demonstrated their welding processes, adhering to procedural temperature controls, for observers from PSI and its architect-engineer, Sargent & Landy. The data gathered during this demonstration is presently under evaluation to determine if the present procedures are adequate to protect structural concrete from excessive heating.

This letter is intended to fulfill the requirements of an interim report as defined in 10 CFR 50 55(e). A further report will be filed on or before November 2, 1981.

8109100421 810901 e

rf PDR ADOCK 05000546 gf S PDR

.' . O. Box 190, New Washington, Indiana 47162 812. 289 , 1000 SEP 3 1981

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PUBUC SERVICE INDIANA Letter: Mr. J. G. Keppler September 1, 1981 If you have any questions on this matter, please feel free *o contact me.

Sincerely,,

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, 7 S. W. Shields TDG/bak cc: Director of Inspection and Enforcement U. 9 Nuclear Regulatory Commission Washington, D. C. 20555 E. R. Schwe'ibinz, P. E.

J. J. Harrison