ML19220B780

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Forwards Info Requested at 770218 Meeting & Requests Addl Info Re Equipment Qualification & Main Steam Line Break Accident Analysis
ML19220B780
Person / Time
Site: Crane Constellation icon.png
Issue date: 03/10/1977
From: Tedesco R
Office of Nuclear Reactor Regulation
To: Vassallo D
Office of Nuclear Reactor Regulation
References
NUDOCS 7904270341
Download: ML19220B780 (7)


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D. S. Vassallo, Assistant Director for Light Water Reactors, OP:t FRC9:

R. L. Tedesco, Assistant Director fer Plant Systems, DSS

SUBJECT:

THREE MILE ISLCD, UNIT NO. 2 (TMI 2) MAIN STEA9 LI"E BREAK ACCICE.'!T ANALYSIS The our:ose of this memorandum is to for<ard the infomation requested at the February 1S,1977 aceting with the applicant to expedite cne tneral analysis of safety related equiptent under postulated main steam liw break accident conditions. Also, attached is a request for additional infomation regarding equipment qualification.

With.egard to the main steam line break accident analysis, we previcusly stated in our memorandum from R. Tedesco to D. /assallo, dated December 17, 1976, that we calculated a containment temperatura 65'F higher than that calculated by the applicant.

In the February 18, 1977 meeting with the applicant, we reiterated the results of our confimatory analysis, and the cethodology for an acceptable analysis. However, the applicant does not have the ccc:puter code capability to calculate tna containment temperature transient in a manner that we would find acceptable. Therefore,

the applicant agreed to use cur temperature profile in the themal analysis of safety related equipnent. Witn regard to eqpigment qualification, we will require the applicant to identify the safety rels"d equianent and discuss and justify the acceptability of tne qualificatiu testing that has been or will be dene.

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5-b b N k b.ctC9 Robert L. Tedesco, Assistant Director for Plant Systens Division of Systems Safety

Enclosure:

As Stated cc: See Page 2 790427034(

82 274

Contact:

F. Eltawila, CSS

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