ML20214G843

Advises That Design Criteria/Methods in Util Jul 1974 Rept & Re Drywell to Wetwell Leakage & Testing & Inservice Provisions Provide Reasonable Assurance That Structural Elements Will Withstand Design Loads

ML20214G843
Person / Time
Site:	Columbia
Issue date:	05/01/1975
From:	Maccary R Office of Nuclear Reactor Regulation
To:	Deyoung R Office of Nuclear Reactor Regulation
References
CON-WNP-0039, CON-WNP-39 NUDOCS 8605220555
Download: ML20214G843 (2)

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Docket No. 50-337 N

I R. C. DeYoung, Assistant Director for Light Water Reactors. Group 1 Division of Reactor Licensing WPPSSNUCLEARPROJECT#2(FORMElt.YHANFORD92)-(A)TECHNICALREPORT WPPSS 2-R5 "DRYWELL 10 WETWELL LEAKAGE STUDY" D4TED JULY 1974, (B) APPLICANT'S LETTER DATED FEBRUARY 25,1975 " RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION" STRUCTURAL EVALUATION (TAR-1167)

Plant hane: WPPSS #2 Docket No.: 50-397 Licensing Stage: Post - CP Review Branch and Project Leader Requesting Assistance: LWR 1-2; J. Orndoff Requested Completion Date: May 5, 1975 Technical Review Branches Involved: Structural Engineering Containnunt Systems Description of Request: Memo dated October 16,1975 (LWR 1-2; TAR-110)

Review Status: Coglete In accordance with your request the Structural Engineering Branch, Division of Technical Review, has reviewed and evaluated structural sections of the applicant's report: WPPSS-74-2-R5 dated July 1974, and of the appitcant's letter dated February 25, 1975 listed above, which provides the structural information requested in our previous evalua tion.

The design criteria and methods presented by the applicant and the testing and in-service provisions provide reasonable assurance that tw structural elements will withstand the design loads without igatraent of structural integrity and the performance of required safety functions.

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