ML20071D075

Forwards Masonry Block Wall Tests, to Resolve SER Confirmatory Issue 7

ML20071D075
Person / Time
Site:	Clinton
Issue date:	03/04/1983
From:	Wuller G ILLINOIS POWER CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML20071D077	List: ML20071D075 ML20071D080
References
U-0607, U-607, NUDOCS 8303090154
Download: ML20071D075 (2)

Text

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. . U-0607 IllH101s Power Company L30-83 (03-04) 6 1

500 SOUTH 27TH STREET. P. O. BOX 511, DECATUR. ILLINOIS 62525-1805 '

Docket No. 50-461 March 4, 1983 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Subj ect : Clinton Power Station Unit 1 SER Confirmatory Issue #7 e

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Dear Mr. Schwencer:

As requested by the NRC staff in a meeting on March 8, 1982, and as a fulfillment of SER confirmatory issue #7, the attached report on CPS " Masonry Block Wall Tests" is submitted. This report provides the results of a confirmatory test program under-taken by Illinois Power Company for the CPS Masonry Walls. The tests were witnessed by NRC Structural Engineering Branch personnel, N. Chokshi, F. Schauer, and K. C. Leu.

The conclusion of the testing program is that the average modulus of rupture value for the Clinton masonry walls is 251 psi based on three tests. As presented to the NRC staff in the March 8, 1982 meeting, the maximum allowable tensile stress parallel to the bed j oint for the CIInton masonry wall design is limited to 77 psi for SSE load combinations (4% damping). The actual masonry stress is limited to only 36 psi. Even when the truss bar reinforcing is ignored and the damping value is lowered to 2%, the actual maximum SSE tensile stress is less than 65 psi, as documented in Illinois Power Co. letter U-0469 to Mr.

J. R. Miller of NRC staff, dated April 23, 1982. Based on these low stresses and the high modulus of rupture values obtained from the test, it is evident that the design stresses for the Clinton masonry wall design are quite conservative and have an amole margin of safety, i.e., more than a factor of three over pel 8303090154 830304 PDR ADOCK 05000461 E PDR

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U-0607 L30-83(03-04)6 March 3, 1983 Page 2 SSE stresses. Therefore, we believe that confirmatory issue #7 is satisfactorily resolved for close out in the next SER Supple-ment. Your concurrence after an early review of this report is

-kindly requested.

Sincerely, E

G. E. Wuller Supervisor - Licensing Nuclear Station Engineering HBP /jmm attachment cc: Dr. H. Abelson, NRC Clinton Proj ect Mar,ager Mr. N. Chokshi, NRC SEB Mr. H. H. Livermore, NRC Resident Inspector Illinois Department of Nuclear Safety

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