ML19249B794
| ML19249B794 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/13/1979 |
| From: | Chilk S NRC OFFICE OF THE SECRETARY (SECY) |
| To: | |
| Shared Package | |
| ML19249B789 | List: |
| References | |
| NUDOCS 7909050368 | |
| Download: ML19249B794 (5) | |
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7 The Directer vill keep the Cc- 'ssion in."c.
ed en a periodic basis of the pregress of the inquiry.
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diate public health or safety sig.ificance will be repc:-ted pre.ptly to the Cc
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'ssien enphasizes that it will take whatever regulatory actica it deens necessary at any tine, based en infc. ation available to it at that tine.
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. Fedaral Rerister / Vol. 44. No.138 / Tuesday July 17,19 9 / Pr7 posed R:ileeT.-
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tdcen:i=fc:mati=n shan Se -
fer ce=tisned cperaden of a madear b Sdpport of I.Jaht Wasse Nuclear,. ~. 3 e-sub=itted u soc: as possibM and the ~
facility, and cocricatics between the Pcwe P'. ants," NUREG-c:IG0/ EPA 5::!2/- 1 a p;Ucast shaII permit ver:5catieu by de hcensee plan : d State and local plans.
1-7M.S. D ---M 1273.Sett 43 Fed.._
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6ternat=al A:c=ic Earrgy Ages.ry -
De re--unsion seeks w=tten -
' Reg. w'A (Dec-mbe 15.1278).see cIso.
ec=me=ts on what items thculd be -
44 Fed. Reg.3137 (A;ril ta, ig793. '.
ud take ::6 cher accan as =ay be a
tecessary to t T -- -t de US/IAEA bchded in the role.
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Safeguare.s Ag-- - -* in de ms ner ' ^ oirts: Cc-ts Ee'due nHitir than bcbing hml Maas and Public laterest Research Geoups, have res s wimi
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be" wCI g anf an Wdttes c==ents r 4-exe=ptc: frc= dis w _s.;t upon '
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g tnstallat= wC1 ot be inciaded en the c_,. m. U.S. Nadear Regulator *~
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The Part 170-. Fees for Feedtt$es and PCs rumem sciomatrriou cowracTt -
bitiate an expahtad -nf.- --W.,
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usterials ucermes and C*4er,..
.o Patrica A. Comalla. Site Designation pgx.Wm on tfar subsect cf S'aia arwP' -
Requiatery Services Urx$er the Atomic. Eranch. Of5ce cf Standanis c0.
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7 esponse p ans azad - -7._
Erwgy Act r;rf 1954, as Arunded Develc,._est. Nudear Regulate
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parte:i T the foDoormg insw-addmg a r.ew paragraph (aK10] to re'ad sum.nsrxrsn womaarxne ne NRC 1.WM,culd be the 6-w obW
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apphcasts plan for radiological a.To recare pubhc -L%,n (a) No application fees. li:ensee fees, amergences wtthm teir Siant sites and exposuref resswal fees, c; inspection fees shall be make arrangemem. 46 State and local b.To W W rdah req = red br:
crganuanens to respend 2 ac= dents m,, mr
.c.
that might have cc: sequences and
- c. 'I'o be & to a b ga 7
- *7 To what ertr *.6=1A th
-~7' (10) Ac:vities of the Co--"s=ics encertal.e=, purr: art to Part 75 cf this QQ,( **~*
h* 'If ebctyn & W M J ? ']
g c: apter, scien for de ;r:rpose of CTR Part 50. Appendx E (19'79'.see clso
- 7. What cmsh an a 4,e v. -,
- =;.eme: ate: of the US/ AEA additicnal g* e M U.S. NRC.
emegec7 rapm=se planIce State a.nd- '.
I local ager e=? Farne-*~' What are
. w.a.~.s Asm c'.e:1.
Regulate y Guir!e L101 Emeqc=cy Planmng for Nuclear Power Plasts.-
tre nsecama wwe s that c.tst be...
- ~
N#
To aid State a=dlocal. emments m enst g.E iw. ~_ m.
far
,.m.m n
Fr tse S:r.isar RegJatery Come. c.
the deveicpment acd i=pi aettatics of M
Pa Af"-
Q and.
c Samual I. E adequate e=crgency plans, de NRC. in guidasce ferStates (NI.IR.EO ;5/np cenlunc:ior wi$ seven other Federal lad any cf 6 --e! h,m 7 -'
kc":*7 W e M ~ ='n.
%. mac w w= = 4.=;
age =ces, has atte=pted, en a
- 5. ShouldNRC ermemmence in the si uas coce me-a-a coepeauve and vekstary basis, to
- 'socated,Sbs te and local m g.u.g ;.
provide for training and matructe cf respense p. ass be a i% a foe ~~
State asd local gover= ment pe sensel centsued cperation of azry nuclear Adequacy and A0certance of and to estabhah c-'ca to gdde de powe plant with an arv*t-w cperat24 Emergercy Ptamung Aroured Nuc$ ear preparaten of e=egency plans.
license? If so, wnen ahem tilia gesacral racdtes Howeve. the NRC as cet =ade NRC mquiramm+ bermne -m mrey appal iState and W eme gency CEdMM"-m6 r 10 CFR Par *. SC]
plans a conditen cf nuclear pcwer plant the associated State andiccal
~
actn:: r:".S. Naclear Regulate:y cperaccc.
e=ergency resposase plans be a Oc-- u t:=.
The accident at nree Mile Island has mqmrematfor tiwe h of any znew,
h AC90*c Advas:e Netce cf Preposed r:2 sed a nu=ber of ques:icas abcut the cp ent:3 m ae
- a smusear poi cr.
Rie=ak;.3 adequacy of raSciogical emegency. - piant?If so. whee u uld t:ns general. m m-response plass. Even befcre de reg =reme=1 becca. e&etiver,
.s
.s swswer:The Nuclear Regclatery accdent de GAO had recc=imended -
- 5. Shocid +=u f **='=r* be ---E,..,-T Cc--us:= is cenz2de.=g :he adeption that NRC not heense new power plants provided to Stain and localp---
cf adit 2e:al regulatens wh:cfr w:11 for cperation unless ef!-site e=e gency
!ct radiciote cal ezne:gezzry r estabhsh as cc dite:.s of powe reacter plans have been appted by the NRC.
plan =ing a=dprepandne=? If soaa,... -
cpeauc: c:: eased e=ergency
- GAO, Report to the Congress. "Arens wnat extent and by what awn, ey W y -
ma%+= fcr public pr +ar-- is the - Around Nuclear Fachties Shoc!d 5, shocid be the sourts ofIbe bands?...- 1: e.'
- 5. Should rur%1 rig $ cal en a pey.
-v.-
n= sty of =nciec pcwe reacices an the' Betar P epared Fe Radiclegica! -
respcssa dnT.s be a reqh WY so, 9 ' *
~
par: of be t=a her--are and local and.
F:me gent.,ca,* Mari 30.1S"2.The -
- whose author 2y:Federa! State ca 4 i E
W 1s also censider. g new ~
s.a:e act:c.nes.'Ume
4*'on is
- guadance to State and local gove-me-tu local germ me a To wi:.at arvtaret -
- .:te ested e re.m g public s
-+-
c: cbiec:ves for efInc=ve plana. -
as c=wgency p!n- 'w based o= an should Fu.ca! Saa tis, and local. 0 -'.: -
a:ceptm =.tria f::r State / local analys2s of a }ci:t NRC-epa Task Fcres seve-e and Hema =na be mqcfmd..o -
eme genry pl.ans. NRC -mee in Repart. "P'n--+ g 'c. ::s for Developme t to parte:ps247
' %.c 5:a:e and 'ocal pia =s as a %
m r. t of State and Local Gove==ast
?. How and to whn n r =, e ak,.M the ' ~~
. h..'.
Snssua ce cf as c'pcat g hca:se a Radiciogical Emerge.cy Respensa Plass pubhc be 'M "t Qio any
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414M Fedeeml Repster / Vol M. No.138 / Tuesday. July 17.12 9 / Proposexi EM-= if s -taeg 37
. _ - _._ a.
Under nac+vwc51 suf the Ptab21c Nalg-For the e--- -
.inerguccy, ccocernmg emergmey
' act2ces it =idit be caLed cpo= to tala?
w J.CWk.
Semce Act (42m F-M Typhod.,,g<!
i
- 8. What a<:trocs should be tnW in
- Secrocry af t.se t"~ w V8"r'n* n!L rad Er made, bem ce, J- ]
response to the reco=rmendaticca of the ya o.,%.xre m4s.awa me 3 exchange in h'
- mutsi be li-en=3and ma-+ certa:zt -ha*=%
b loint NRC/ epa Task Force Esport es.t.am coes no c e saferty, purityd,.
(NURF.MDQ6/ EPA 5:D/1-N16T?
that ensure its - --
-A J
d E. L'cdct what ci:en=s*=wes and -
potency, ed r6~-e-wi W-ven n usmg what emeria smould a h DEPARTMENT OF HEALTH. '
D
~%
and revtsed m2 % _brrr_ "nm
-J Ii#'t~~'"
A IES notify State. local sad Federal as -
Emum MD WELFARE o f +m A,n * = tecio6:rg cou m -w,.t 4
Ad^ ~"'* D "hme"5 W #'"#in:3 l
When, bow. to what exte=t. arzi by. ' Food andDnsg Adrenastrzsserr the Fed.armI Ra:-d-asza
- 4. 1953(34 t
whoc2 shcmd the pcbbe be zxatified cf,
these inadents?
[21 dR Part C:Cl -
- - - ~
FR 8914) M M-=4 as H e 'ad m.. y through c:an" (21 CFR et'n m Lg n, c,,,,. nan += M wm be.
conected and evalnated by the NEC in fDocketPo.7c8M4:51 ~~' F " ' * ' -
M'm), ca Nu 1-murst:saFa %
-m l
- w.....cicons ca pW rules tu Bacurtal Pruw+e Addtt$ coal -
- 3:D48). Under E rm<d of nae i.d staE. which wm. m tz:n. subm:t adA+-==_t
^- %' m Gu ts:sL14(ctk:g the cw.-me Boed ce the
~ a-starcares for Typeoed vaceme Typhoid V-.wsnot be tes=ed.br y the = =anf= c+- er d =n-nm it rece res froci the publi: and t: e Aoscy: Food ed Dr:g AM stratice.
.,,,, _, p analycs of the pzme ;=ese=:md by the A.cncee Proposed Rule.
1
~
- *' I" NRC Staf. tsec~~-'i==x2n wG received fmusthe h h.Burean aP L deter =me whethe to proceed with a suumarv:%e Food and Dr g Biologics (BOB). O'm-==1 wrmv-n rder= B A d-,istrs: ion TDA) is propos:=; to is issued only h ther ZL has. ;.
proposed rule for not=3 and m m*
and/or whether to =ake such r ia amerd the bsolopes TTphoid V.-
reviewed the PW:abaz d tested immediately efec:ve. The C'-"- i-n regdatioca to ecsure fusther the sa=2ples to -w"na the - - e - ' safety, '
anticpates completon of ils expeited a.nty =icinteg y of the Ty :: ram of punty potency,and nFL cevm-m cf rul - &? in appmxi=a:aly cx bacma used in race =e procucacn and Typhoid V=ce-a=
tocuths.
to resurre that h:ensed mar 'act=rer, On the basis of near =s-n++
ne NRC staff is pre.sently c==du:'ing obtam the U.S. Owacity Sta nda-d fmm knowledge de=md huzzai~
L.- release a ecc:preh *" eve rmew e! aH aspeca cf the Bareau of B.oegi::s.ne FDA is aise data ac- -m*=ted azmins2:alyzed by BOB the NRC - ge :7 pla--"! and proposu=g to amend these renlatocs by for the past se sexalF=m PDA is preparednes.: prept=. Therebre the estaWebs new standards for the proposmg me-w'w- += to the N s.- A Cam =:ssion is also =te ested :
performance and results of the potency standards for TyT**"d 'VF'w-receiv=g -- e:ts on ail othe aso-:3 test for each lot of m--f=e*=ed includmg the for -%--
of emerge==y p1-~- t::lt.i=g iss:es TyMoid Va -~
(1) Strain Ty2 of 2 L
,O sp&,.s raised = the Crincal Mass /PIRO ogn3. h by Septe=ber 17.19N.
is used in the "m ofTypbcmd petitio:!=r rule-ar-g and questices Vaccine.To e
=*e thee a...:n AccAzss: Writte com:lents to the such as the follow =;
integnty of the Ty s:r =m FDAis
- 10. How and to w:st exte=t shoc!d *be Heas:g C;erk (EFA-335). Food and to =W gm m m conce: :s of State smd local gemts Dr.tg W -atradon.R=. W SE 6:U.11) to requine that - w,.c te.r-Smy ashes La:e.
.He. MD m..
be mee po-ated into Fede-al be venBed by 6 =*A : - c -- of hymg radioloc:a1 e=ew ~specae PO W N I3"C8W E C88CC8C A:n ha-ten = by a Ty m ___
pia-m-e Mict.aa. !. Hoo:::. Bureau of Biou:pcs (2) To clarify due =m
, fee hird,c
- 11. Ecw abould Fede-a! ag-naes (HF
). Food and Dm8 necessary id IFDA. ~
inte-face with State and 'rocal A d""**trancc. Depar::ent of Heali.
propos-s to annend i e-n ?-* Cn CFR gover==ects and tne licensee c===g Educanos, ar.d Welfare. saac Rocryille a:=.12) to requzre that c::ae U.S. 9=~2=-d emergencies?
P.ke.sedesdaSD zm4. 3C1-443-t306-Typcoid Vaccne and the U.S. C) pac:ty
- 12. Should the 3:ensees be required to sum.zwewTm swonnunoec The Standard be ~*-a-+ fS rrn the Bureau provide rad:okgscal emergency Coc - matocer is proposmg to an e-ci the cf Bioiognes.
respacse tramng for State c2d kx:a!
bx:acpcs regulanons for-ann'ac.... g (3) Sahne is %. " for use ixt gover __ect peroocoeI? 1! so, to what Typcoid V=c-= by seta=g poten:y dilu::cca of die.--em, asWm.~
extent? Shodd the Federal gove:zment stancards ice the Ty s: ram of doses used in the y...-- -. j ree na,"na. !
a provide such tram. g? If so, to wtat G /-v a-W ypmano used in the of phoepnat: AIL.g 1 asm'- M by t
extent?
marsizcczre of Typhoid Vac=ne and by the BOB has anc --
Mhaarm
- 13. To what ment abM rwtmee be, reviseg the poteocy test unde i e :.u dewt=Me 6-~ -. inssche pacezz=y a-r. -
piaced on licensees for the as= *=~-'
(21 GR 6:L13) em eutent with new Accor4m'v.EDAis puurposurg to amew' of the =c t=1 cr potennal e" =-' =
~* howage der:ved from past I a.-n t i(b)(1) and (eg::3 to pev-mit the use of an eew t with regard to :- t=taan expenance with the ;roduct.
of PBS for ^=rhm the===.er,
. the of proteceve a::2o:? To w.at er+ -t
!= t:ne lenged States, typooid disease cha11ecce, azzi tur===nr a h efl ' '.
sbould 1:zs resprw r nihty be bcene by
- has been is daw m recent yn s and Strain Ty 2 c(M===mn-% typr n
Federal. Sute er kscal r.- -.?
rootse typhoid nec= anon is.
w-(4) N = 4 ce s : - 2 r_-t _n osed,.
f
- 14. Wodd ;r.che paracpataccin ree-wrt H., wever, n-n nei,=.
in, and
,te= desmsUz.oen ryprxnd radiciogical %wy my-d=Ls.
is merated d a pe soc has cene c:o Vacc:ne pacency testz y n _ _a t the -
a tselud: g evaa:atxac. serve a neefal conta:t wie a known typbcid camer, if BCE. FDA as im-- -gso.m
,vt
'purposa7 If sc. what saould be tme there : as actt:reak cf typhoid iever in i B::.13(e) en rnom:rse r* me ur s:cistical.
extent of :ne pubh: partepaacr!
the -ry, cr if a pe-sc: plans to methods be==,=4 fzie A- _
_.., tne n.ou : W-~w 3.0 :hm 1:a er7 cf travel to an a:za waere typcod feve-la validtry of the a -. 3 ass:. Fac %
a s.*
r b:7. in, eo ocznac.
em n=tancy. IDA m -
tas mammed j
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ATTACHMENT 20
' f, s n.:, ',
UNITED STiTES
~%
i g NUCLE AR REGULATORY COf.it.ilSSION t i e.>+
l ADVISORY COf.i'.ilTTEE ON FE ACTOR SAFEGUARDS
.L
%.s - [/
TM i
wAcmscron. o c. 2esss April 7, 1979 Henorable Joseph M. Hendrie W
Chairman E
U.S. Nuclear Regulatorf Commission h
Washington, DC 20555
{.
SUMECT:
INTERIM REPCRT CN RECENT ACCICENT AT THE TufiEE MILE ISUWD NUCLEAR STATION UNIT 2 Cear Dr. Hendrie During its 223th meeting, April 5-7, 1979, the Advisory Committee en Reactor Safeguards reviewed the circumstances relating to the recent accident at the Three Mile Island Nuclear Station Unit 2.
During this review, the Committee had the benefit of discu.ssions with the NRC Staff.
Our study of the accident at Three Mile Island has sho-n that it is verf difficult for a WR plant operator to understand and preperly control the course of an accident involving a small break in the reactor coolant system acecmpanicd by other abnccmal conditiens.
The Committee reccamends that further analyses be made, as seen as pes-sible, of transients and accidents in WRs that involve initially, or at scme time during their course, a small break in the primary syste.
'me computer codes used for these analyses should be capable of predict-ing the conditions observed during the accident at Three Mile Island, inc'uding ther al-hydraulic effects and clad and fuel tec.reratures.
Tne range of break sizes considered should include the smallest that could he deemed significant, and should consider a range of break loca-tions.
Be Cc.~r.ittee believes that the analyses recce. mended abcve will demon-strate, as has the accident at 3ree Mile Island, that additional infor ation regarding the status of the system will be neaded in order for the plant cperator to follow the course of an accident and thus be able to respend in an apprcpriate manner.
As a minimum, and in the interim, it would be prudent to censider expediticusly the provision b
4 s/.,,
441 /
aqf /y,J o n'] (ltl
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s Honorable Joseph M. Hendrie April 7, 1979 of instre entation that will provide an uns.-biguous indication of the level of fluid in the reactor vessel.
Early consideration should be given also to providing re.mtely controlled means for venting high points in the reactor system, as practical.
The foregoing recommendations apply to all pressuriced wate: reactors.
[-[
The recorrendations in IE Bulletin 79-05A, dated April 5,1979, are be-7_
lieved to be generally suitable for Babcock and Wilcox facilities, on an interim basis.
However, the Ccemittee believes that the actions listed in Item 46. under the heading, " Actions To Be Taken by Licen-sees," may pcove to be unduly prescriptive in view of the uncertainties in predicting the course of ancmalcus transients or accidents involving small breaks in the primary system.
With regard to Three Mile Island Unit 2, the Cemittee believes that decisions should be made expeditiously with regard to contingency meas-ures which may be prudent cencerning containment and reactor cooldown as a backup to the currently planned cocidown procedure.
The Committee is continuing its review of these and other concerns arising frem this accident and will provide further advice as it is developed.
Si.m 'erely, Max W. Carbon Chairman S
,e.
ese.-
9
s ATTACHMENT 21 L
L April 17, l' f.
e
/s
[..
RECC0"<ENCATICNS CF 'IHE NUCLEAR RS3ULV" CRY CCi*14ISSICN ACVISCRY CCF.4ITTEE W REACTCR SAFD3 CARDS REGARDING THE MARCH 28, 1979 ACCIDENT AT
'*iE TiiREE MILE ISUSD NUCLEAR STATICN UNIT 2 Presented orally to, and discussed with, the NRC Commissioners during the ACRS-Ccamissioners Meeting
~~
cn April 17, 1979 - Washington, D. C.
Natural circulation is an important mode of reactor cooling, both as a planned process and as a process that may be used under abnormal circumstances.
The Ccamittee believes that greater understandire of this mcde of cooling is required and that detailed analyses shoulcr be develcped by licensees or their suppliers.
The analyses shculd be suppo rted, as necessary, by experiment.
Procedures shcold be de-veloped for initiating natural circulation in a safe manner and for providing the operator with assurance that circulation has, in fact, been established. This may require installation of instrumentation to measure or indicate flew at low water velocity.
'Ite use of natural circulation for decay heat remcval follcwing a loss of offsite power scurces requires the maintenance of a suitable over-pressure on the reactor ecolant system.
This overpressure may be assured by placing the pressurizer heaters on a qualified onsite ps. zer source with a suitable arrangement of heaters and power distri-bution to provide redundant capability.
Presently operating PAR plants should be surveyed expeditiously to determine whether such arrangements can be provided to assure this aspect of natural circula-tien capability.
The plant egerater should be adequately informed at all times con-cerning the conditions of reactor coclant system opera tion which
~
might affect the capability to place the system in the natural circu-lation mcde of operation or to sustain such a mcde.
Of particular importance is that information which might indicate that the reactor ccolant system is approaching the saturation pressure corresponding to the core exit tempe rature.
This impending loss of system over-pressure will signal to the operator a possible loss of natural circulation capability.
Such a warning may be derived from pressur-icer pressure instruments and hot leg temperatures in conjunction with conventional steam tables.
A suitable display of this info rmation should be provided to the plant operator at all times.
In addition, censideration should be given to the use of the f1cw exit tempera-tures frca the fuel subassemblies, where available, as an additional indicatien of natural circulation.
n-n u s i vt a
5
. The exit temperature - of coolant frcm the core is currently measured by thermoccuples in many RGs to determine core pe r fo rmance.
Se Committee recommends that these temperature measurements, as currently available, be used to guide the operator corcerning core status.
The range of the information displayed and recorded should include the full capability of the thermecouples.
It is also recccc.crded that other existing instrumentation be examined fo r its pos;sible use in assisting operating action during a transient.
The ACRS recommends that operating power reactors be given priority with regard to the definition and implementation of instrumentation which provides additional informatien to help diagnose arad follow the course of a serious accident.
This should include improved sa pling precedures under accident conditions and techniques to lhelp provide improved guidance to offsite authorities, should this be reeded.
The Committee reccamends that a phased implementation approach be em-
~ ~
played so that techniques can be adopted shortly af ter they are 1
judged to be appropriate.
The ACRS recommends that a high priority be placed on the development and implementation of safety research on the behavior of light wter reactors during ancmalous transients. The NFC may find it apptcpriate to develop a capability to simulate a wide range of postulated tran-sient and accident conditions in ceder to gain increased insight into measures which can be taken to improve reactor safety The ACRS wislies to reiterate its previous recccmendations that a high priority be given to research to improve reactor safety.
Consideration should be given to the desirability of additional equipment status monitoring en varicus engineered safeguards features and their supporting services to help assure their availability at all times.
~9e AZ is continuing its review of the implications of this accident and hcpe to provide further advice as it is developed.
me..
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i sCLEAR RE UA RY COMMISSIO..
3 SY--%#9s [
ADVISORY CCf.'"ITTEE ON RC ACTOR SAFEGUARDS
' b I'. s.<
.f WASHINGTON. D. C. NS55 s,
,e April 20, 1979 Hcnorable Victor Gilinsky T_...
Acting Chairman F-'
U. S. Nuclear Regulatory Ccamission
~
Washington, DC 20555 Cear Dr. Gilinsky:
Tnis letter is in respense to yours of April 13, 1979 which requested that ce ACRS notify the Ccamissioners i=ediately if we believe any of cur cral recommendatiens of April 17 should be acted upon before our next regularly scheduled meeting at which we could prepare a fomnal 7- -
letter.. "he Committee discussed this topic by ccnference telephone call en April 19 and offers the follcwing comments.
All of the recommendatiens c.3de by the ACPS in its meeting with the Cc=missioners en April 17, 1979, ara ganari: in nature and apply to all FW:s. None were intended to require immediate changes in cperating pro-cedures or plant ecdifications of operating Fes.
Such charrges shculd be made only af ter study of their effects en overall safety. Such stud-ies shculd be made by the licensees and their suppliers or censultants c
and by the NRC Staff. Be Committee believes that these studies should be begun in the near future en a time scale that will not divert the NRC Staff or the industry representatives frc= their tasks relating to the cooldewn. f 2ree Mile Island Unit 2.
However, the Ccmmittee be-lieves that it wculd be p:ssible and desirable to initiate i=ediately a survey of operating procedures for achieving.atural circulatien, in-cluding the case when offsite power is 1 cst, and the role of the pres-surizer heaters in such precedures.
At its meeting en April 16 and 17,1979, the Cc=mittee discussed with the NRC Staff the matter of natural circulation for the Sree Mi.'e Is-land Unit 2 plant. te Cc=mittee belles 's that this matter is receiv-ing careful attention by the NRC Staff and the licensee.
=,
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EL J pgl5 yc/(/ o ol
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Honorable Victor Gilinsky April 20,1979 Tae Cc: nittee's own recommendations to the Ccamission en April 17 were not intended to apply to 'Ihree Mile Island Unit 2.
We plan to write a further report on these matters at cur May 10, 1979 meeting.
Sincerely,
/
b
. ax W. arben Chaiman w
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