ML20197G097

Forwards Request for Addl Info Re Design Verification Program Pertaining to Structural Engineering Aspects

ML20197G097
Person / Time
Site:	Columbia
Issue date:	11/25/1983
From:	Lear G Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
References
CON-WNP-0690, CON-WNP-690 NUDOCS 8312070468
Download: ML20197G097 (3)

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MS 5 33 11EliGRAf;Dul! FOR: Thomas it. fiovak, Assistant Director for Licensing Division of Licensing TilRU: James P. Knight, Assistant Director for Components and Structures Engineering Division of Engineering l FR0ll: George E. Lear, Chief Structural and Geotechnical Engineering Branch Division of Engineering SUGJECT: SGEB REVIEU OF KflP-2 DESIGli VERIFICATI0fi PRCCRAll

References:

(1) l-temo to R.11. Vollner, R. J.1:attson, J.11. Taylor dnd I. U. Bishop from D. G. Eisenhut dated October 31, 1963 (2) Attachment to Reference 1 - Washington fiuclear Plant 2, Design Verification Progran, Vol.1, Final Assessment Report dated September, 1983 .

(3) An Independent Evaluation of the Plant Verification Progra at the Washington fiuclear Power Station (;o. 2, Vol. II, TAA Report 1126-F2, dated October,1983 In response to the request of Reference 1 nsnarandun, the Structural and Ceotechnical Engineering Branch has reviewed the portions of References 2 and 3 that pertain to the structural engineering aspects.

Our review has identified a need for additional information which is provided in the enclosure. This review is conducted by Dr. K. C. Leu of Structural Engineering Section A of the Structural and Geotechnical Engincering Dranch.

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M G312070468 831121 Ccorge L. Laar, Chief SP ADOCK 05000397 ,, Structural and Ceutechnical

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Engineering Branch Division of Engineering

Enclosure:

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EtiCLOSURE ,

RECUEST FOR ADDITI0fiAL INFORMATI0ti - WNP-2 DESIGN

'sERIFICATI0tl PROGRAM The staff has reviewed the audit results of the selected samples provided by the applicant. The following additional information is needed prior to our completion of the review.

1. What are the bases used in the selection of structural members Which were examined to determine if loads applied to these members were adecuately considered in the design process? Also provide a

. detailed discussion to justify that the audit results from the limited selected samples are sufficiently representative of the entire plant to be used in judging the overall adequacy of UNP-2 Category I structural design.

2. It was determined that for the main steam tunnel north wall, the use of a cracked versus uncracked wall section for the computation of dynamic deflection did not affect the final acceptability cf the structure. Describe the procedures and assumptions adopted for both the cracked and uncracked section analyses, also provide the design margins with respect to the code allowables cbtained from the analyses.

3. Referring to Section 3.5.4.1 of Reference 2, the imposed pipe whip restraint design loads are comprised of equivalent static loads due to high energy pipe break, jet impingement loads, and missile impact loads due to the postulated break. Provide a discussion as to how these loads are considered in the design of adjacent structures. If the method used to assess the combined effects of these loads is different from that given in the SRP Section 3.8.4, provide a discussion of the basis for deviating from the SRP load ccmbination procedures. -

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