ML19220C169

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Summary of 750429 Telcon Re Containment Sys Branch Questions Re Steam Generator Support Skirt & Heat Transfer Coefficients
ML19220C169
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/29/1975
From: Washburn B
Office of Nuclear Reactor Regulation
To: Kniel K
Office of Nuclear Reactor Regulation
References
NUDOCS 7904300020
Download: ML19220C169 (2)


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cril 2'), 1975 Karl Kniel, Chief, Light dater Reacters 3 ranch, 2L TEL2CO
! JIUC-'33IO:. (nPP.IL 29, 1975) CO::CT2'!!::G CO:C?,I:i't!"C SYSTE.:i3 C CISTIO:IS - TH2EZ MIL 1; ISLA!D Ii"CLD 2 STATION, bi!IT 2 (TMI-2)

Participants:

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Vann, GPUSC W. Gray, ESU J.

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D.

Shum, !iRC:TP B.

Washburn, 'IEC:FL Turpose:

Applicants' representatives recuest for additional lisucssion of Contain. ment Systen Branch questions 1.

Required pressure response analysis for the steam generator support skirt fer a postulated pump suction line treak inride the skirt -

B&W referred the staff to FSAR Figures 5.1-5 and 5.5-3 and stated that the upper edge of the steam generator react.or coolant outlet no::lo is in the s u e plane as a vertical tangent to the steam generator support skirt.

Based on this gecretrical relationship, they believe that, for a break at this no::le, the line will bicw away and that the no::::le will exhaust directly outside the shirt.

The staf f did not agree with B&W's belief.

B&W asked for the type of brea'<. to be pestulated for the analysis.

The staf f stated that the flow direction and jet shape are not established and that we cannet advise as to what type of break to postulate as we do not know the detail of the pipe support and skirt design.

IIcwever,

the staff would accept a double-ended break.

B&W indicated that they would respond to the request for a pressure analysis.

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C3B request th a Tagar and Uc'ti.la corr.elati.,-.c be n 2.

te obtain aeat transfer coefficienta for passive 3ent si:2s in the containr.ent pressure analy >is -

3rA; stated that this had been done in the rosconse t question 03.4.

The staff agreed.

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