ML20032C234
| ML20032C234 | |
| 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, 10CFR50.55E, 79-04, 79-4, NUDOCS 8111090533 | |
| Download: ML20032C234 (2) | |
Text
1102814005 4
,g T4 PUBLIC pn kuu SERVICE NOVO 6198M,.
INDIANA y-u.s. m S. W. Shields c awnson b
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Senior Vice President -
[
Nuclear Divis!on November 2, 1981.
79-04 1
Mr. Jacos G. Keppler, Director Docket Nos.: STN 50-546 1
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 June 1,1979, Mr. F. R. Hodges of Public Service Company of 4
Indiana, Inc. (PSI) notified your office of a potentially reportable i
item as required by 10 CFR 50.55(e). During the placement of concrete in Pour No. 1CW-Ext.-2 the specified pour rate of 3 to 3 1/2 feet per hour was exceeded. A pour rate of 10 feet in 70 minutes resulted in the breaking of a whaler on the lower portion of formwork and possibly created a gap between the concrete containment well and containment liner.
Chicago Bridge & Iron (CB&I) performed dimensional measurements on the subject liner. Sargent & Lundy reviewed the results of these measurements and concluded that all dimensions were withir tolerance and no repair of the liner was necessary. Non-des tructi-testing by the. Portland Cement Association indicated that a gap of up to 5/8 inch might axist between the containment liner and containment wall. Hols.s were cut in the containment liner by CB&I to permit examination of the concrete consolidation and any possible gap between liner and wall. Examination revealed
' hat the concrete was properly consolidated and that separation between the liner and wall was within acceptable tolerances.
This condition therefore would not have affected adversely the safe operation of the plant and is not reportable under 10 CFR 50.55(e).
8111090533 811102 PDR ADOCK 05000546 PDR S
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P. O. Box 190, New Washington, Indiana 47162 812. 289.1000
r 1102814005 4 G PUBUC SERVICE INDIANA Letter: James-G. Keppler ' November.2~, 1981 79-04' If you have any questions on this matter, please feel _ free to contact me.
Sincerely
/
b 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 i
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