ML20040F659
| ML20040F659 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Limerick |
| Issue date: | 09/10/1970 |
| From: | Case E US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20040F238 | List: |
| References | |
| FOIA-81-385 NUDOCS 8202100042 | |
| Download: ML20040F659 (3) | |
Text
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Peter A. Norris, Director g
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LIHERICK CDIERATING STATION UNITS 1 AND 2, DOCRET NOS. 50-352/353' Q
IS Enclosed is an addition to the list of DRS Structural Engineering.
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s tb Branch questions sent to pu on, July 2,1970. Eis is a formal
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g question covering the subject of deterrAnation of contaimt design Q
-5 adequacy as discussed with the applir,nt in the August 19, 1970, p, -a.
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Edson G. Case, Director g
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Enclosure:
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R. DaToung, DEL SK R. Boyd, DEL D. Knuth, DRL
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ADDED QUESTION
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In order to permit svaluation of the adequacy of the containmant design 1,
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expected to be. imposed,on the contaimment during normal operating
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conditions, including startup and shutdown, and during the course cf the L
LOCA, furnish the following inferiantion:
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(a) A discussion of the long term (through 10 seconds) thermal y
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r-and concrete porticus of the contain:nent following the design
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basis LOCA and based upon the operation of the sainirmun tn=her j
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,i of systems required for containment heat receval, which assures
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(b) An evaluation and identification of the nost critical containment 6
loadings over the long term period (through 10 seconds) for a 4,
spectrtan of water and steam breaks up to and including the largest
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break areas which spvern the design of critical areas of the
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containment, such as (but not limited to) the vn118, base mat / wall j
joint, drywell floor /un11 joint, concrete supports for reactor 4
vessel and steel containnent head. Si ilarly, evaluate and identify 2-the critical loading combinations at the above locations for normal,,
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manner in which tbs pacific critical loading combinmHnna derived;f,Q.,
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