ML20151X755

Submits Nm Newmark & Wj Hall Formulated Questions Resulting from 671003-05 Meetings in Bethesda,Md & Washington,Dc Re Plant Reactor Internals,Piping & Vessels.Requests Answers to Subj Questions to Finalize Rept on Util License Application

ML20151X755
Person / Time
Site:	Diablo Canyon, 05000000
Issue date:	10/06/1967
From:	Hall W NATHAN M. NEWMARK CONSULTING ENGINEERING SERVICES
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
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References
FOIA-88-156 NUDOCS 8808260096
Download: ML20151X755 (2)

Text

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. NATHAN M. NEWMARK CONSULTING ENGINEERING SERVICES 1114 CIVIL ENGINCEntNG DUILDING UHDANA. ILLINCIS 6teol 6 October 1967

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% j Dr. Peter A. Morris b G Division of Reactor Licensing .

U. 5, Atomic Energy Commission f A h gfgl F :. .,

Washington, D.C. 20545

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Re: Diablo Canyon Site Nuclear Plant 9 .- "{,

Docket No. 50-275 N M).['..,

wp , .a Wgulatdf Suppl Elle Cy. *

Dear Dr. Morris:

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As a result of the meetings held in Cettesda and Washington on l October 3, 4 and 5 concerning the Diablo Canyon Nuclear Site, Dr. Newmark and I formulated two questions for which we should like answers. The first i question is a rather IJngthy question rnade up of many parts and will obviously require considerable documentation. It deals with the reactor Internals, piping and vessels. Two questions follow:

1. For the reactor Internals, piping, and vessels, separately, provide the following criterla type Information:

(a) the loading combinations to be ervloyed in the designs and the reasoning for selection of the loading combinations (b) the stre's or deformation limits for each case (a)

(c) the margin of safety between (b) and the expected collapse or failure conditlon.

For particular cases where calculations of maximum limits of deformation or stress (at wnich inability to function orcurs) have been made, please supply such data. Also in such cases supply the maximum design limit value, and the expected deformation or stress where this has been calculated.

In all such cases the applicable loading combination should be identified.

and any amplifying discussion of the margin of safety presented.

In cases where only stress Intensity criteria are to be employed, as outlined in WACP 5890-1. provide a realistic estimate, based on appropriate material properties at the applicable terrperature of the strain in order that an estinate of the margin of saf ety can be made. Especially for those cases which fall outside the code-ba:M "boxes" and in the region between the boxes ano' the limit curves it is imperative that the margin of safety be identified.

8808260096 800721 C 'o My PDR FOIA MCMILL AOS-156, PDR ,,

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i ,I 6 October 1967 Dr. Peter A. Morris s

Confirmatory test data should also be supplied. If available. with Interpretative discussion. With regard to WACP 5890-1, provido additional discussion regarding the applicability of the derivations In the report to the st rain hardening domain.

In connect ion with the above, provide infornution that will permit evaluation of the effect of welds. Irradiation. corroston, accidental Imperfections, etc., in the design approach.

To the extent ovallable, supply criterla or specific deformation and stress Information connected with the relative motions between the reactor vessel and steam generators or other large items as well as Interact ton forces. Indicate how these relative notlons will be cont rolled by snubbers or other means, and what reaction forces (and corresponding stresses) will be t ransmitted +o the pipes.

2. The containment structure will be founded on bedrock and surrounded by sore 30 feet of overburden. Describe how the forces crising from any soll-st ructure Interaction arising f rom nornal and selsmic loading will be evaluated and handled in the design.

The answcrs to these questions should permit us to proceed with finalizing our report on the Olablo Canyon application.

Sincerely years, W. J. Hall bj w Cc: N. M. Newmark