ML20024G295

Requests Listed Info Re Interim Acceptance Criteria for Performance of ECCS in light-water Nuclear Power Plants

ML20024G295
Person / Time
Site:	Monticello
Issue date:	07/19/1971
From:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
To:	Dienhart A NORTHERN STATES POWER CO.
References
NUDOCS 9102080500
Download: ML20024G295 (3)

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On June 19, 1971, the AEC adopted interim acceptance criteria for 4

the performance of emergency este cooling systems (BCCS) in light--

J water smaleer power plants. A copy of the Coundesion's interim policy.

f statement as this matter is enclosed for your taformation. In aseerd-j ance with Bettien 1Y C.1(a) of the policy statsment.yes are requested -

to outait an analysis of the performenee of the ROCS presently ip ' : '..

~j stalled ta' the Meetieelle plant estas methods agaivalent to the salmJ'

, f.yr stien model'in Appendia A Part 2 of the policy.etatement as esen'es/

practieehta, but not later then October 1, 1971, to esafise thsticha i,

performenoe of the E003 is la esopliance with 'the eriteria.eOSesttahi IT '

A and B et tho'e'.atement. We have.diseassed this, request',with represse-

,'.o tatives of the Seancal'Elastria Company and solanderstandithet smalyseis j..*

j fjp using this,model beve been er are being performed for your plast h y

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l g-The informaties that we need regarding these analyses is estlined f.

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1.

Provide curves of peak clad temperature and percent clad

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! M, metal-wter reacties as a function of break size for the j[f various combinations of ECC subsyetens evaluated by using jg<

the single failure criterien indicateid la Table 1-1 of _the topical report; " Lose-of-Coolant Accident and knergency '.

W Core Coeling Models for General Elsetric Boillag Water 4g.

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fp Renators",' WID0-10329. e A 'discussies'should be. taeladad ?"w. '.w".. $j l4 i

showing the justification for'the ECC sobeystem' combine ~ ^

I tiens iased in the evaluation.

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JUL 19 1971 2.

For several breaks that typify small, intermediate and

./L large breaks, provida curvr of (a) peak fuel clad ten-perature for various red grrjs, (b) core flow, (e) fuel eht inlet and outlet ge=LLty, (d) heet transfer eoeffi-cients, (e) remeter vessel wt.or level, and (f) miasmusi critical heat flant ratie Oscarm) as fumettene of time.

Indiasta the time that effective ecre cooling is initiated, the time the fuel cha==al beeanes wetted based spee item 4 of Appendix A, Part 2, and the time that the temperature transient is terminated.

3.

For the analyses performed in 1 and 2 above, discuss the range of peaking factors studied and the basis for select-ing the combination that resulted in the most severe thermal transient. Curvas of peak clad temperature vs time for the range of peaking factors studied should be included.

4.

Discuss in detail say deviations in the evaluation model used in the foregoing studies from that described in Appendix A, Part 2 of the Commaission's Interim Policy Statement.

When this information has been prepared we would appreciate your sending ue 60 copies. When we have completed our review of the Monticallo plant's gCCS we plan to contact you regarding the results of our evaluation.

Sincerely, orig w sise d M Peter L #4 Peter A. Morris, Director Division of Reactor Licensing Enclosuret AEC Interim Policy Statement cc: Cerald Charnoff, Esq.

Shaw, Pittman, Potts, Trowbridge and Madden 910 17th Street, N. W.

Washington, D. C.

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