ML19220C385
| ML19220C385 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/03/1977 |
| From: | Tan C Office of Nuclear Reactor Regulation |
| To: | Shapaker J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905010052 | |
| Download: ML19220C385 (1) | |
Text
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RIBUTION:
Docket File:
50-320
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NRR-Rdg SEB-Rdg MAR 0 31977 MAR 05 1977 Cocket No, 50-320 MEMORMOUM FOR:
J. Shapaker, Section B Leader, Containment Systems Branch, DSS
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FPDM:
C. P. Tan, Structural Engineering Branch. OSS THRU:
I. Sihmeil, Chief, Structural Engineering Branch, DSS
SUBJECT:
THREE "i?.E ISLAND 2 REACTOR CAVITY ANALYSIS (SEB:1113)
PIFERE lCE:
Februi 1977 Letter from J. Shapaker to K. Kapur In accordance with the infomation contained in the referenced letter, the Structural Engineering Branch has reviewed applicant's data con-i tained in the supplement to FSAR, through Anend:::ent 51. We found that the brea'c node peak pressure computed by the applicant (See Fig.
042.3-24), Amendment 48) is higher than that shown in the attachment i
, to the referenced letter, and there is hardly any difference between j
the two for the pressure beyond the peak. On the basis of their calculated peak pressure at beeak node, the applicant stated that i
the reactor cavity wall has a factor of safety of about 3 to the ultimate shear capacity of the concrete wall. On the basis of this infor: nation, we conclude that the design of the reactor cavity wall is adequate. However, the Structural Engineering Branch has not evaluated the effects of these breaks on other systems within the cavity such as the reactor ECCS systest:s and reactor supports since these are within the areas of review of Mechanical Engineering Branch.
9 1
C. P. Tan Structural Engineering Branch Division of Systems Safety
Contact:
CTan X27807 cc:
G. Lainas R. Bosnak H. Silver I. Sibweil m,.
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