ML19319D409
| ML19319D409 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/13/1976 |
| From: | Bunch D Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003170542 | |
| Download: ML19319D409 (2) | |
Text
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- MEMANDIN FOR:iJ. F; Stoir[Chiet, List Water Roactor Branch'Y1,7 0PR i
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AAB has. performed an evaluation, at your request, to determine.the. limitinc
' parameters;forioperation of Cryst'al River, Unit No.:3 in view of the?recent.
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- Althouch the, applicant,Ein'his, letter of September 15,1976. (J.T. Rodcers to
~J. Stolz) requested permission lto perforn fuel loading and subcritical testing only,we haveJalso perforacd an analysis to determine whether les poster testing, and at diat level cculd be perritted. ' W acrec wits the eclicenc t%t tW muld be no fission prcducts~ or 3ctivatio7 croducts re? sat in the cw Mel primary ccolant to constitute any sianificar.t radiction Surd.
Consequently, w agree)that thcre would be little or no radioicgical consem:9res atseciated with the proposed ocerations of' fuel loadine and tutcritical testino,' and ve reer d' tha t they M "er-Itted.
He aisc ' o Dvm fn view cf tna @Wy !biw tim r-rie:i veM rv fn-
-Im rtwer testing and the lare; cycrdetica, cca city cf t'e reemrcy care coolinc tyston, tN+ the yr@bility ef an accident where sienificant "W
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- ernice.. 4.wethics.. a cu M:,tc4 th cc?urmcc ec.:
desina basis' LOCA and perforced an analysts to 9.teraine the otcetial Mic-lonicel cor,::ences under 1m ;;c.:tr.tecting Far thi. 'nalyck, c ::-.~ M that the.ralctor var oper9ed it 11 of-its etreten cre.:er ir~al (?5?1 %+1 fr.r a peried of '4 days ccntinuously.. At the ar.d of this ti period we nsred
.that a LOCA cccurred and that~100t of the noble 1ses 39 ! 2M of tM iodines in tne core decre 'availchle fer release in tN contair.m.t.
Et s is coa-
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.sistent wits hr escretient for the radioiccical consemencer
.v, civs in JPagtlatory Guide,1.4'. EIt st culd be pointed 5ut that at such e low power ECCS acceptance criteria:are f ar r. ore casily rot.. Pence, the.
p <[r.ex levelitney[oKthe radioactivity release' stipulated by:
'jg S9aenitude Regtlatory Guide 1.4, k,.M wM.noi ral,1glstnsidered c.onservative for.fullipower operation, becemos' highly,
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M:@rslileEALiccosnted forithis;phenonenon in our dose calculatiens since. #g g
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' l l tincithe poteh.tf alirutological conseque'nces we 'focuse'd upon..
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. C n ca cu a H+ 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid dose','since our' SER had.previctisly: deterainedithat.the 1 m
wnole: body dose was not controlling.. We alsa asmed that tne containsent
. f odine' removal sprays functioned and we assir.ned the :same -fedine dose' J' ~
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reduction credit as.had:been determined from our SER ovaluation..
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In our SER we assumed for tt e eyaluation cf the design basis LOCA that the centaint.9ent le !:ed at the Tech. Socc leak rato 'of 0.25t per day.
Because of the dela::inated containrent dec:c, and t:ecause the containencnt (has passed neither a structural integrity test nor an integrated leak rate
?? test. :use' of the Tech. Speci.nleak rate during proposed low power. testin<1
,3 Jmay-not be'.. justified..f Ratherethan' arbitrarily assuminta centainmant leek.
rate, we determined the'eaximum 'or. limiting Icak rate that would yield.
. radiological. consequences within the guideline values of 10 CFR Part 100.
Using.the sa :e reteorological, brcathing rate anti dose conversion factor asstz otions as were used in the SER ve comoute that a containment leak rato as high as 1500 per day muld result in 4 hour tNrnid dcu within the guideline vaines of Part 100.. This. is a leak rate which is 500 ths greater than the Tech. Spoc. led rate.
'Je !,011 eke trat a <tructure desiened and constructed as a centairmnt and with an intact steel liner umdd sw a led rrt: t.C l bel ou a value of IWT per asy, even without hrtiro estsed tFc eav.4 two t?sts.
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- nculd ce pointed cut inat sheet vital secon&.ry conuin^cnt.rchcr*
fnc v, with a differstf al preswre r.mgiac trea Deut 1/4 f ach ru wtaral k*.C.
100k at r atc! CI'"Pnd^ LOC'. M '* * '.y.
A recent t*St M l'213tT Tr ?
reac" - ntrol roc + nhich nonessed unrci doors and where r.weral indivi-cuals
.ured and exiW darts-the tes", enmi imace at rate M ai cut
' 50f per dcy.
In cenclusion, we wree with tr o aept ioni. tw fwl" leading a.V ::ccrP cal testino 4111 pose little or no radiole';ical huels ad, in addition,1.0 celieve t5st lw pWer limited durction ter.tinc (not to excud M of tM rated puer ami for a total cf 100."<guet: days) is enlikely to rasM t in radiolegical conset;utnces dich cxc0:d the cuit' elf 9e almt of 10 M Mrr
-100, even in the eve.nt of a postulated LOCA. Even for continuous operation at 1% of rated power, a LOCA with a containnent leat rete as nich as 75' f per day would result.in. doses.within the puideline values of 10 CF. Part 100.-
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