ML19308E286
| ML19308E286 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/22/1971 |
| From: | Case E US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003240835 | |
| Download: ML19308E286 (3) | |
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i CKhSTAL RIVrJ1 El'CfJ.AR PCLIT TLM FSAR 7CCDATIGIT ENGINEE21HG QUE3IIri.4S, W r: 3, DOCCT E0. 50-302 I.aclo::cd a o fouM2 ion enginunia:; entiens en *he mtbjact plant-for your tmanittal to the -Qplicant..
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r CRYSTAL RIVER PLOJECT OUESTIO::S 1.
So that the staff may complete its review of the foundation conditions following the foundation exploration and treatment program described in tne PSAR and later amendments, we request that you submit for review; a.
Gilbert Associates (G.'A.I.), Inc. SP-5500, Specifications for Subsurface Grouting, Crystal River Unit No. 3, Florida Power Corporation, Feb. 28, 1968.
b.
G.A.I.,
SP 5735, Proof Testing of Chemically Consolidated Foundation Elcments Crystal River Unit 2;o. 3, Florida Pcwer Corp., Jan. 7, 1970, c.
The independent entineering evnlu;. tion nade of the entire chenical grouting prtgram by an "Outsido cencultant to tne Ouncr" that uns centirned en page 2-46 of the FSA2.
2.
On page 2-35 of the FSAP. you state "Couparis,n of the impvaed load-1:n; uith the conservatively eatinated shear'ng stren?,ta of the foundation materials indicated that adecuate factor of safety o.,
against a bearing capacity failure would be achieved under the nost unfavorable conditicus u.eich could be reasonably postulated.
This ccnclusion, hcwever, cas pradicated on the assumption that all significant voids occurring above elevatica +33 uould be filled so as to ninimine local overstressing and possibic future pro-grossiva failure."
a.
Provide assurance of the predicated assu=ptions.
b.- State'the computed factors of safety for all adverse conditions analyzed, including scismic loading conditions.
3.
Page 2 of the Woodward-Clyde report states:"The Reactor Building foundation mat is reported to impose an average unit load under operating conditions of about 7.8 Kcf.
The nnximum contact presnure of tus Reactor Building mat vndar operating and under 1.5 accident pressure conditions is esticated to be 10.3 and 23.4 Ksf, respectively."
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Denonstrate how the values 10.3 and 23.4 Ksf were obtained.
b.
What is raeant by 1.5 accident pressure?
c.
Show that the foundation vill suppore the 10.3 and. 23.4 Kcf pressure frc:n the Reactor 2uilding mar.
4.
Page 5 of the Woodward-Clyde report states:"It is also pertinent.
to note that no evidence of active subsurface subsidence (sink holes) due to solution activity has been reported within the proposed plant site."
Is there evidence of active or inactive subsurface subsidence outside of the plant site, that is, witnin several ailes of the site?
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