ML19322C359
| ML19322C359 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/28/1972 |
| From: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Dopchie H BELGIUM |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001160896 | |
| Download: ML19322C359 (3) | |
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nr. II. Dopchio, Directeur
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rccaine of reallprxants of reapeanihtilty in _ cur Forulatory of f f ce, Dr. reck hcs acted ce to respond to your Intter of October 14, 1971 d ich c.iccu1aca your concern 1 nhout t'ic potential consequences of a j
losc of-coolcat accident (1/1CA) roat"latc.! to erf nf n.'to In the vapor portica of the prenwrf rer for a T'O reactor.
our Ictter cimo provided detailed inforr9tien for your P.cci unit for the cuc ernat of L'ic conscqumcen of t' o r altuinte 1 accident.
Tn t*,e norril concre of our aafety revinm, ve hava discucre ! the con ce rn for thin reci.'e,t rf th "mtinnhouce for thcie Ye"nunce r.uj rien reactor f..t,.
1:.c f r r.t ily<:c n f a nce.te tha t for all bronk nizco the reactor.is tripped, Tn those cases uM,rc the coincli ent prcanurf zer Icvel cnd presouro ci< :a l e: r ay rot be cctunted, nn overtenperature LT or lov proncuriner prenure ni:nal vill initicte the reactor trip.
in all ca,a, restinchocae rc 7crts (Lat an eccepenble irc1 of 1.33 or treater util renuit.
Per 111 break nf zca tra to on ! including the prennurizer nur.-c lire, t'catint' ouce states that thq core vill not be uncovered and that clad datage io not <spected.
ccncor,uently, there vill be no ficcion producto released frca the Tuoi to the reactor coolant, nnd the rurcing oc;'ect of the accident In no dif ferent fron any other T,0CA.
/,ccording to e vrinchuuco the offitte ceninquences of tha neci a nt ' rill ie reintively nc -11 c iM o.
l There is almificant dif ference in the fuel clea'dinr, tecperature transient i
io11cuin;; a LCCA, dependin': u;on the p n:ce level at ubich the cora is i
oNratinc at the tire of T.CCA initiatica. The higher the ret:ctor pcuer J e. el, the h i ~he r th e n u'v eqv: r ter.peratura e < cure. ion u111 be, all cico b e in e, c o u.,1.
With regard to your question cencerning the dif ference between i
a UTCA occurrInt, at hot shutdo. n and one occurring at full re me, the I
subse;uent terperaturn transient of t'e fuel an1 cinddf p fo r a h o t r>hu t 'c n If, 2; l
LACA tuald be crch lover than n LOCA occurring at full po"o r.
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ob buuMs] td Aa g.p 3 g 3;.2 Mr.11. Dopchie L'o had hoped to be able to assess the response of your facility to the pootulated accidend. This, however, vill not be possibic because of f
other rore urgent darands upon the staff. We hope that the infarcation h
we have provf.ded on other L'estinghoune reactora vill nssist you in evaluating your own particular pinnt.
" sincerely, f
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A. Clar.bunso. Deputy DLrector for i'eactor Projects.
Directorate of Licencing DISTRIBUTION EP Reading L Reading Central Files (Subject Files)
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Vo had hoped to he abh to evMs the renpe: se of your facility to the pr.:u L-N d acc h t.
'IM 9, 't +cce, rill not be pasib2c Leu. oe of other core urgent s'caands upon the staf f.
Uo hope that tho, inforention we hava provided on other Ucntint.houso reactors vill annint you in evalenting your oun particular picnt.
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Sinceroly, Tcter A. Forrf n. Firector P1visien of P.cacter Licenifrig
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Mr. fl. Dopchio, DLrecteur.
Association Vincotto 164'1 Phodo ">aint-Ceneco
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rear Mr. topchim 7ecatric of reatinnt sta of renponafhtitty in 7tte reculatory of fica, Dr. Beck ita:t r.1hed r, te rcupend to your let er of Oct<6er 14.1971 nhich tinctased your oco rns al'out t*ta rete ntini commquence. o f a lon1-of-coolamt ceci den (i.OCA) po1tulated to orie '.nnte to the vapor rtion of the prnonuriv. r for a T'.R re.'ctor and nuppt f ed Jetailed infornation for your Doel v,i t,
tinea numr, cur L'X'A crecie 1 i et i h,vc Feen contf nmtuly invm ad with cu ryncy core cooling nf w va ( i >) conce nu.
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adopted tho interi e acceptanco i. iter [1 for ECCS for li.-5t -acter parer reactors. " Thin v.m follove ' W detailed review of the FrC1 r:vnlustion rade19 includins, their. h,tn.ptions and procedures for the varinua rc.tetor vendors. ECC'i parf > unce ' ras then revie:ed with ree roct to the interirt criteria for o nud er t specific reactor planta in the courJe of processing their If ecun. c.pp. c.1tions. The Ter.ulator'/ :taf f al9o has provided testi.cny.w a nu6cr nublic herrtnna for ecc't ifcense applicotina.
Finally,4 e find ou % 1vea todav deeply Involved
.. in a public rutcra'<ing hearing. rh1ch in bei e held ti conqider t'te
- ,cncric espects of our intect-r.cceptar.cc cr u r i.t.
"c c a t. m or th e w continutap ar'andr., us he.va 1.en unahte to evt. tote the LOCA for your particular rcretor plant.
In the nerral couric of ot r nafety revlevn, va hv, di: ice.wed t*w concern
.t ned Mfan re ctor for this nceident with "e tinzhou<tc ar their Pe nn:
plante. For all break o r.cs the reaetor is trip; ed.'
fn th r e cnel d are the coincident preanurizer IcVel end prevure air,nals t ry nat he cctuatod, an overtenporature AT or 1rei pressuris.cr pressure nirnni ill iriti:.?c the rocctor trip. In all caces, '.*cntine. house reports that en acceptchie NtR of 1.30 or createt will result.
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? it c'.a ca re III me t ' e a co-e' a u.i t' tchi slara;:o is not expected. Consequently, thero vill be no fission products relonned fron the fuel to tile reactor ceolant, and f.he rurring anpact of the accident 1: no dif ferent fron any other 113C[. /.ccording to L'entinr30.sco the of fat to consequencen of ti;c acci'ent ufil be reintively nerlit;ible.
There ig n struificant dif fccence in the fuct claMiny terrerature transient folloling n I.OCA, depending open the awror level et s'iich the core In "m[hiL mr t'ac reactor pcver acera t t ag\\t the tLee of LOCA initietfon.
inet, the liN* W r the cu'ee;uent te,,crature cycursion will be, all cine NLth ver:ntd to your <;veatina, c[anc eccurrin7 nt ncecnine t')e dif ferenca I e f.ng e p:al.
n t ho t sh u t,'c'a n mij full uc tr<.cn a T/'CA c surr tnt-poner, the suWe r n..
terpcrature tr in :icnt if the fuel rW cinJ. ling for a hot shut <?o in LOCA
'ul.! 'm i:uch Irrier then n LeCA eccurrinP ct full I neer.
receu3e of t'ia coatine.=d cypccted dt. "1 ! 'pon our 1.'CC#, staff, it util not l'e ';casl51c rer us to evaluate t'.19 hlcident in Jetail for yerr
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' '. % l e this infornation for tbes cutin @cuqe reactorn d li a urint you in evaluating your own r trtic{ usa plant, Sincere y, Peter
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For infor: nation, before we dispatch.
Jeanne Cook 9/26/72 0
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ACTION f ACr E55tNG D ATES PREFARE FOR Sl3 NATURE OF
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C h oi'= a a Clifford K. Ecch
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Ic.ie r m Pepxl
__ Director of Re gulation i ' '. f
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.-;k llc ei W/l'J[i1 and bAalt2 further iufctr.ation as regusted cenccrain's centaiwat dor.ip. Also request 2 reapace to questica reinted to.2 los::.of-ccolcat, accident orir,inatitig anywhero in tha priusrf circuit
~ ~ A ETETc~E DIO DATE
?S NOTJICAllON IQ THE JCAE G E C CrAME ND E O 7 Iferris i/actica 10/n/71 r
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'DO NOT DETACH IriiS COPY D:RECICR CF REGuit itCN form l40 32 p.70)
COV /UN:C ATIONS CCN!EOt USA EC
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