ML20032C267
| ML20032C267 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 11/02/1981 |
| 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, NUDOCS 8111090572 | |
| Download: ML20032C267 (2) | |
Text
1102814006
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A u..OVO 6 L981>.W SERVICE INDIANA
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S. W. Shields N
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Senior Vice President -
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November 2, 1981 S81-07 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 Clen 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). While surveilling Cherne Contracting Corporation (CCC) welding on safety related embedment plates, PSI Quality Assurance Personnel observed spalling of the structural concrete in which the plates were embedded. PSI questioned if this had been caused by heating during the welding process and if the spalling might reduce the load bearing capacity of the embedment plates.
Subsequent investigation revealed that CCC welding procedures did not directly control concrete temperature during welding at concrete-steel interfaces, however, their procedures did include controlb on maximum embedment plate temperature.
CCC demonstrated their welding processes for observers from PSI and its architect-engineer, Sargent & Lundy.
Measurements made during the demonstration indicated the concrete temperature adjacent to the embeds did not exceed acceptable levels during welding or flame cutting operations.
It can therefore be concluded that embedment plate temperature controls in CCC welding procedures give adequate assurance that local concrete strength will not be reduced.
Sargent & Lundy has also evaluated the effect of the existing spalling and has determined that it will not affect the plates' and shear pullout capacity. As a result it has been concluded that this condition will not affect adversely the safe operation of the plant and is not reportable under 10 CFR 50.55(e).
8111090572 8111'12 DR ADOCK 0500 Ea7 P. O. Box 190, New Washington, Indiana 47162 812. 289.1000 NOVI 48 0
1102814006 PUBUC SERVICE INDIANA Letter: James G. Keppler November 2, 1981 S81-07 If you have any questione on this matter, please feel f ree to contact me.
Sincerely 9
S. W. Shields TDG/bak cc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 E. R. Schweibinz, P. E.
J. J. Harrison
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