ML19305F324

Advises of Intent to Use ASME Code Cases N-219 & N-287 in Facility Containment Design.Nrc Agreement Requested by 810430

ML19305F324
Person / Time
Site:	Washington Public Power Supply System
Issue date:	04/07/1981
From:	Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Youngblood B Office of Nuclear Reactor Regulation
References
GO1-81-098, GO1-81-98, NUDOCS 8104140420
Download: ML19305F324 (2)

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Docket Nos: 50-460 April 7, 1981 50-513 G01-81-098 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Comission Washington, D. C.

20555 Attention: Mr. B. J. Youngblood, Chief Licensing Branch

Subject:

SUPPLY SYSTEM NUCLEAR PROJECTS N05. 1/4 APPLICATION OF ASME CODE CASES N219 AND N-287 The WNP-1/4 containment design (excluding liner) is based upon the ASME Boiler & Pressure Vessel Code;Section III, Division 2; up to and including the 1976 Winter Addenda. -

Article CC-3421-6 of the code states that the peripheral or punching shear stress taken by the concrete on the assumed failure surface shall not exceed vc and the value of vc shall be calculated as a weighted average of vch and vem, where vc = nominal permissible shear stress carried by concrete, psi vch = allowable shear stress on a failure surface perpendicular to a meridional line vem = allowable shear stress on a meridional failure surface

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c Code Case N-219 states that no peripheral shear reinforcement is required i

when vc < v or vu < 0.5 X 6, where vc = nominal permissible shear stress carried by concrete, psi vu = nominal total design shear stress, psi j

f'c = specified compressive strength of concrete, psi.

Thus, Code Case N-219 establishes criteria as to when no peripheral l

shear is required.

l Article CC-3421.4 of the code states that the radial shear is caused by self constraint of a cylinder and base slab during pressurization of j

the containment. Article CC-3421.4.1 provides limits of the nominal i

shear stress vc shall not exceed.

The Code Case N-287 states that no radial shear reinforcement is required r

when 0.5 X N vc < v or vu i Thus, Code Case N-287 establishes criteria as to when no radial shear reinforcing is required.

We presently intend to use Code Cases N-219 and N-287 in the WNP-1/4 i

Containment Design and request NRC agreement with this course of action.

We would appreciate a reply by April 30, 1981.

Very truly yours, r

< O b" y

G. D. Bouchey Director, Nuclear Safety VBM:oe i

cc:

V. Mani UE&C-PA A. Bournia, NRC l

C. R. Bryant, BPA N. S. Reynolds, Debevoise & Liberman i

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