ML19312C824

Forwards B&W Re Vibration Analysis & Test Program for Prototype Reactor Internals

ML19312C824
Person / Time
Site:	Oconee, Arkansas Nuclear, Rancho Seco, Crane
Issue date:	08/29/1972
From:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
To:	Thies A DUKE POWER CO.
Shared Package
ML19312C825	List: ML19312C824 ML19312C838
References
NUDOCS 8001100735
Download: ML19312C824 (1)

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Duke Power Company PWR Branch Chiefs ATTN:

Mr. Austin C. Thies RWKlecker Senior Vice President, OGC Production & TranM asion Ro(3) 422 South Church Street Project Leader P.O. Box 2178 Licensing Assistant Charlotta, North Carolina 28201 DDavis j

Gentlemen:

e The Final Safety Analysis Report for Oconee Nuclear Station Units 2 and 3 references a vibration analysis and test program for prototype reactor internals.

Enclosed for your information is a copy of our letter to the Babcock & Wilcox Company concerning this subject.

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Please contact us if you desire any discussion or clarificacion of the material requested in the enclosed latter.

l Simeerely, Original signed W R. C. DeYoung I

R. C. DeYoung, Assistant Director i

for Pressurized Water Reactors Directorate of Licensing

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