ML20210B690

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Partially Withheld Rept on ACRS 641112-14 Status Review of Hanford Reactor Re Nuclear Safety Criteria for Special Test Loads.Proposed Test Load Criteria Acceptable.Operation of Reactor at Full Power Should Precede Test Loadings
ML20210B690
Person / Time
Issue date: 11/18/1964
From: Kouts H
Advisory Committee on Reactor Safeguards
To: Seaborg G
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20210B278 List:
References
FOIA-86-346 ACRS-GENERAL, NUDOCS 8609180145
Download: ML20210B690 (3)


Text

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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS I

j UNITED GTATES ATOMIC ENERGY COMMISSION

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WASHINGTON 25. D. C.

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t1::c.2. sv<is.: c. tag. p :s .2 rn.w 'ct.r satttj crit 4.ric fur test loals.

/Jt'.e c. c!nri p-rivi of up rati.:L t.t TJ,; powcr, the Nicactor was sb t, de rt rur car-rc ::cin'ctv oc an! inspection. Operatiers hirvc .

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1. Ost.? IWwu Contr.C l C. D,u.d.of-lu,ciccr Contav! i 3 he.nl it,er). ice CLASSITICATION CANCrna:D  !
4. Co:Cira 42n t G A citANGED 70 d4' cd24 ,/i

,. II.t-IcwL.r Critictlit7 bY AUri!0RIT'Y OF ./_2f./J.::,,Gp[

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-G- Epvember 28,1964 .

( Honorshle menn T. Seaborc i

Beveral thertmi-hydruulic and yttysics epocifianths are also entlined.#

1he Ctsnaittec enn=4 dam theoc ariteria to be moed, het ausgeste that additionni specificatioco be incialed as follows:

a. 3b met paettive reactivity effect demild be erested hr the los,of coolant fru.1 a $ cat Iced; reactivity effects due to W ocemrinc in tbc test tnada durinG an sooident abould not sneeed t shutdaun margin of the control rod systen.
b. Test loeds shouhi mot trente smoessive flux or tagerature conditiono in any adjaocnt fuci solumns.

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c. he test load should be so des 16aed mal, when unosenery, gee-l' tected, that rc11atility equivnicut to ht of the standard fuel element would be expected. Test load design and operation abould act be s a h l that hich-tacperaturc @via=1 or physical effects present a any type

! of hamru.

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) bc Gencrtti Electric Company has proppood that test 1==di ws of up to 5 fuel coltzm which moet the criteria vill be subject only to interuni revice an1 appmval. Test fuel laadings acuprising up to JO solumns lesen which sect t14 critcria vill be submitted to the AEC for appfoval, l ( criteric are not met, additioen1 review by the hogulatory Staff is used-ed.

l At tbc fifty-ninth sectinC, the reproscatatives of tbc General Elmetric C(gxur/ prescated an ennlysis of the effect on resetor behavior of a this tect loadinc of tg colume, of 1.W9 enricbod co-producer fuel, inadin did not satisfy all the proposed eriterin, since some salting However, pimec in lese than 300 secomis.

on loc: of coolant could tals:

the Octurul Electric Cca: para has presented evideme that the portuinted acitaxn o:' tbc test load would not arcate an unneceptahic offsite barnrd. Wirty-eicht rather than 49 colutma arc y.weicd fcr the first tcot load.

1$, 1964 1stter that We Acro reiteraten the statawmt in its October the operaticn of the N 1kactor shcr.114 be carried out at full power be-fore any test in=Absu arc inste11sv1 h ACIC belicyco that the proposed test load criteria are neoeptahic and can be ad.pt.o1 for usc with the additionni specifications defined aboyc. k Acic also bellen s that the test in-Aind of MP to 49

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I Eanorahlm Glenn T. Seaborg .F Nunster38, $ .

oolmse of 1.2% enriched co-produoer fuel een be carried out with reasonable assurance that this operation vill apt s16mitienntly ta>

arease tbc existirlC hasanl to the health and amfet/ of %be public.

W yours, l

Origir.al cigned by IIertcrt i:aats Barbert Ecuta O mirman l

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I acterezco - ntnrerd 5-Henetor

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1. 3l.7;/P20, "Pe1~r Safety Criteria for Special SmH, Imeds -  ;

N *nctcr", datal October 14,1963(C/RDJ. i l

C. 151 POW ikiv., "Ma:;ards Itryiev - E-Heactor 1.2% Co-Producer Fuel l

Ele:.x:nt 'hst", dated July 27,19G (G/ilD). l i

3 IN-U.1'A, l

l'M. (S/10 .")Co-Pnxiuct Operation of 5-Honctor", dated Septemb I

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