ML20041A534

Forwards Synopsis of Proposed Buckling Analysis Approach for Facility Containment Vessel Per 820120 Action Item 32

ML20041A534
Person / Time
Site:	Catawba
Issue date:	02/17/1982
From:	Parker W DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
820212-02, 820212-2, NUDOCS 8202220265
Download: ML20041A534 (2)

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DUKE POWER COMPANY ,

Powen Dennnno 422 Sourn Cnuacu Singer, CnAHIhrTE, N. C. esa4a q

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WCF Persectut TELt>woht' Anta 704 su.- eaoovcno= February 12, 1982 373- on Mr. Harold R. Denton, Director " c3 -

Office of Nuclear Reactor Regulation g U. S. Nuclear Regulatory Commission --

^ t Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief FEBI'91982> -Tr Licensing Branch No. 4 D

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mc Re: Catawba Nuclear Station G>

Docket Nos. 50-413 and 50-414 j y e

Dear Mr. Denton:

My letter of January 20, 1982 transmitted a list of the Action Items which resulted from our December 15-18, 1981 meeting with the Structural Engineering Branch. Per Action Item 32, attached is a synopsis of the buckling analysis approach that we propose to use for the Catawba con-tainment vessel. Please advise, as soon as possible, of the acceptability of this approach, Ver truly yours, u,_ -

q, William 0. Parker, Jr ROS/php Attachment cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station Mr. R. Guild, Esq.

Palmetto Alliance s ol 5,f I

I 8202220265 820212 PDR ADOCK 05000413 PDR A

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APPROACH FOR STABILITY ANALYSIS OF CATAWBA CONTAINMENT SHELL The Catawba containnent is a class MC vessel subject to the requirements of the ASME Code,Section III, Subsection NE. The Code of record is the 1971 Issue through Summer 1972 Addenda. However this version of the code does not specifically address stability analysis. Therefore, the most recent issue of the code,1980, has been examined to determine the requirements for a stability analysis. Article NE-2222 addresses the allowable stress values for buckling and presents three methods for determining critical buckling stresses: 1) rigorous nonlinear analysis, 2) classical linear analysis reduced by kne;x Jown factors and 3) tests of physical models.

(Note: while Article NE-3133 provides design guidelines for shells under external loading, the loadings to which the Catawba vessel are subjected preclude the sole use of these methods.)

An alternative to the requirements of. NE-3222 has been proposed by ASME as presented in Code Case N-284, " Metal Containnent Shell Buckling Design Methods". This case details acceptable stress analysis procedures and methods for determining stress components to be used in the stability analysis. The buckling capacity of the shell is determined by methods based on linear bifurcation analyses with capacity reduction factors and plasticity reduction factors to account for geometric and material nonlinearities.

Duke Power proposes to perform the stability analysis of the Catawba containment vessel by the methods and procedures presented in ASME Code Case N-284 (Paragraphs 1710 thru1730) in lieu of the manner currently documented in Section 3.8.2 of the plant FSAR. This section of the FSAR will be revised to reflect the change in the methods used to satisfy buckling criteria. -

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