ML20054G604

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Final Deficiency Rept Re Use of Incorrect Soil Characteristic Value as Design Input to Computer Model for Developing Bldg Response Spectra.Facility Design Adequate. Deficiency Not Reportable Per 10CFR 50.55(e)
ML20054G604
Person / Time
Site: Clinton Constellation icon.png
Issue date: 06/14/1982
From: Gerstner W
ILLINOIS POWER CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10CFR-050.55E, 10CFR-50.55E, 1605-L, U-0498, U-498, NUDOCS 8206220127
Download: ML20054G604 (2)


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/LLIND/S POWER 00MPANY 9

500 SOUTH 27TH STREET, DECATUR, ILUNOIS 62525 June 14, 1982 Mr. James G. Keppler Director, Region III Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Dear Mr. Keppler:

Clinton Power Station Unit 1 Docket No. 50-461 Construction Permit CPPR-137 On February 29, 1980, Illinois Power verbally notified Mr.

Frank Jablonski, NRC Region III, of a potential reportable defi-ciency per 10 CFR 50.55(e) concerning the use of an incorrect soil characteristic value as design input to a computer model for developing building response _ spectra.

This initial notification was followed by four interim reports:

L.J. Koch letter U-0136 to J. Keppler dated March 31, 1980; L.J. Koch letter U-0158 to J.

Keppler dated July 15, 1980; L.J. Koch letter U-0230 to J.

Keppler dated April 24, 1981; and W.C. Gerstner letter U-0460 to J. Keppler dated April 13, 1982.

Our investigation into this matter is now complete and this letter presents a final report on this subject.

We have completed our New Loads Adequacy Evaluation and the results confirm that the Clinton Power Station (CPS) design is adequate to withstand the seismic and hydrodynamic loads combina-tions specified for CPS.

The analysis showed that our design had sufficient margin to accommodate the increased loads resulting I

from the modulus correction.

No design changes were made as a result of analysis, utiliz-ing the correct soils modulus.

The plant would not have posed a hazard to the health and safety of the public whether or not we had discovered the error.

Therefore, we conclude that this problem is not reportable per the requirements of 10 CFR 50.55(e).

Sincerely, A_

h4Y l

W.C. Gerstner Executive Vice President 820622o127 820614 gDRADOCK05000 $

JUN 17 EBI JLl'/

I J.G. Keppler June 14, 1982 NRC Page 2 cc:

H.II. Livermore, NRC Resident Inspector Director Office of I&E NRC, Washington, D.C.

Director-Quality Assurance Illinois Department of Nuclear Safety