ML19317E090
| ML19317E090 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/23/1970 |
| From: | Hendrie J Advisory Committee on Reactor Safeguards |
| To: | Seaborg G US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19317E087 | List: |
| References | |
| NUDOCS 7912130747 | |
| Download: ML19317E090 (5) | |
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ADVIE ON C.. '.i'l n:i CN l UCTOR SM u.1:DL
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1;i: PORT ON OCo..!:f; thfCLFAR STATION ITNIT ?:0. 1 Dec r Dr. Seaborg:
thu i nc. :: > 125th verting, September 17-19, 1970, the Advisory Comittee on 1:cact tu SaiccuavJ: (capleted irr teview of the appliention of the i
Dula Power Ca::pany f or a license to operate Unit 1 of the Oconee Futlear St.- t ion at potn r levels up to 25M: !U(t).
Th e Co cn i t t e e ine t with the appliernt durin;,it-12/-th necting. August 13-15, 1970 and Subcor.ai t t ee no. t i n;
- vere held on June 23, 1970, at t he site and on July 31, 1970 and Sept t bei 9, lo70, in War.hington, D. C.
In the course of the review, the Co:. i t t ee h.id t he benefit. of di scussions wit h reprer.entatives and corsnitrut> of the a ppl i cant, the Labcock and Uilcox Company, the nec' tel Cor porat ion, and t he A):C Pegulat ory Staf f, and of study of the documents listed.
'l h r Oconet Stat i o.' i s locat e d in a rural area of Oconec County, South C:n olina.
The nearest papulation cent er is Anderson, 21 miles south, with a p ipalat ion of about 41,000.
The ninimum exclusion distance for the c ompl et ed tins c -unit power station vill be one mile and the Lou Popu-lation Zone radiuc will be r.ix miles containing about 3,400 people. The wat er sepply for the plant is taken from Lake l'ecuee uhich was created by the applicant.
The lehe and associated recreational f acilities are ex-pect ed to at tract a transient population to the area.
The applic.ition covere. Oconec Unitt. 1, 2, and 3, but this report applies only to Unit 1, which vill c~. ploy the first of the Babcock and Uilcox Lt;e-loo;, f our-put.p, pressurized water reactor, nuclear steam supply 3.ysteu. The threc units are desif.ned to be nearly identical, but some f acilit ies and services are shared in various arran;;caents. The Committee I
he revit wed the t e.nporary arrange:nents necessitated by operation of Unit while Ur.its 2 and 3 are still under construction. It is belicved that the prepot;ed physical measures and administrative procedures to isolate the operating unit f roa construction activities are adequate.
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-2 Sept ember 23, l'n D The Comi t te e repmtid to you on the con.truction peroit application for this po./er r.Lation on July 11, 1967. At that t ime t he propor< d operat ing power war. to have been 2%2 M.1(t); the current proposal for operating at powc r:. a:. h i gh a r-2%8 F.,(t) is justified by the applicant, priraar ily on the b.u,ir. of a flat t er power distribution.
Prior to operation at the higher pmcer level, reactor operation should be revicued by the Regulatory Staff.
1he prer.t essed (oncrett containment building is similar t o those for the Palisades and Point geach plants which have been reviewed recently for opera t i c.n.
The Cor. ai t t ee rec o: raend o that the applicant accelerate his studies of means of preventiny, com,on failure nodc< fi o.n negnting scrani action and of design f eat ures t o meshe t olerable the consequences of f ailure t o scran when required during ant icipated transients.
/.s solutions develop and are evaluat ed by the i
llegulatory Staf f, appropriate act ion should be proposed and taken by t he g
applicaot on a re.it.onable time scale.
The Conmittee uishes to be kept in-formul.
'J h e appliennt has propos(d using a power-to-flow rat io signal as a diverse i.e..n s to cause slmtdo.in of the reactor if cmcrgency core cooling action rhould he initlated.
ihe Corai tt.ee believes it is necessary that either the equip nut. ssoci:
- ed with this signal be demonstrated to be abic to survive the accident envitenment for an adequate time or a different, diverse trip signal be employed.
This r.atter should be rc solved to the satisfaction of the Reguletory Staff.
1h.> Cemi t t re suggest s t hat developmental techniques, such as neutron noise analyris and use of accelerometers, be considered as an aid in ascertaining s' i s pl a c c rac u t s, changes in vibration characteristics, and the presence of loose p.ir t s in the primary systems.
"Ihe Corrnittee notes the desiraallity of the continuing use of some thermocouples in the core.
The Com'ait t ce has cement ed in previous reports on the development of r.yst eus to control the buildup of hydrogen in the containment which might follou in the unlikely event of a loss-of-coolant accident.
The applicant proposes to nahe use of a purging technique af ter a suitabte time delay sub-sequent to the accident. Relat ivcly high off-site doser, possibly could r er.u l t foilo. ing purging of the containment. The Corxnittee recommends that purging systems be incorporated in the plant but that the primary protection in this regard should utilize a hydrogen control method which keeps the hydrogen concentration uithin safe limits by means other than purging.
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Winorahl. C l,. m "I. S ea', o g
- September 23, l'1/0 hyd r i.:.' o i on t i ol :.y:.t e m and provi nion:, for contain..ent-at wasphere nixion and
..o pl ing.hould have r ednn,lancy cool J ust.ru> ien t a t i on suitable for an engira ei ed.aiet y it.o ure; Ihe a should be raade available vi thin t he first tuo ytro of power o;v. ration.
the r(rmlotion of this natter. The Commit t ee wishes to be kept informed of
- lhe vppl i t aa t st ated t hat the amount of radioactivity in liquid wastes nor-mlly vill not be y,r mter than one percent of 10 CFR Part 20 limiting con-centrations after dilution uith th: uinimum flou (30 cis) belou the Keonce dam.
1.rc La flova uii1 have proporLlonat ely annller limiting concentrations.
'1he sean annnal dim hai re from the Keouec dam is cuptettd to be 1,100 cu. ft./
see.
- fbe of f-pa r lease rata, are notsynt en han holding t ank cnd filt ering cap,bility and p,as re-exp< c t e.1 to exc eed a feu perccat of 10 CFR Part 20 li'iits.
In order t o protect against the post ulated consequenc es of the accident al diopping of a f uel clcra nt, the applicant has st at( d that either, he will i
install filters in t he f uel pool building exhaust syst en, or the equivalent coat r ol and prot ect ion vill be assur(d by vnother reethod.
This mtter should be resolved to the satisinct ion of the Regulatory St aff uit hin the first year of p.r.rer operatinn.
Improved cal (ulat ional t et hniques are being applied to the analysis of the ef ficacy of t he emerr.ency core cooling syste.a in the unlikely event of a loss-o f-cool an t accident..
3nteria results appear to bc acceptable, but further calculat ion: are needtd and some phenomena it..portant to the course of the r.c c i d r a t re peire f urt her cLudy. This mattcr should be resolved in a manner sat i sf act or y to the Regulatory Staff prior to operation at power. The Conrnit-t(e uisher to be kept i n f o rn.ed.
The react or i n calculated to have a positive uoderator coefficicnt of react iv-ity at poner which will becoue negative as boren is removed from the coolant uit h build-up of fission product s and fuel burnop.
The applicant concoirent plann to perform tc st s to verify that divergent a zinathal xenon oscillations canuot occur in this reactor.
The Committ ee recer.;a(nds that the Regulatory St af f folleu the rueasurements and analyses related to these tests.
A conservative method of defining pressure vessel fracture toughnet.s should be e:iployed that i s v.atisf act ory t o the Regulatory Staff.
Other problems relat ing to large uater reactors ubich have been identified by the Regulatory Staf f and the ACRS and cited in previous reports to you should be dealt uith appropriately by the Staff and applicant in the Oconce Unit 1 power plant as suitable approaches are developed.
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f.: a bo s y, Sept ( sober 23, 1970 Tite Advinory Co,vni t Lee ou React or Saf eguards believe:
that, if due r er, o <l i f 1:iven t o t he it ems mentioned above, and subject tory ceuiplet ion of const ruction and preoperational test itin ther to satisfac-reasonable ast.orance t he Oconee !!uclcar Plant e is psaer lavelt, Unit 1 can be operated at safety of the public.up to 2%C IU(t-) without undue ri:1 t o the health and Sincerely yours, l
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i Joseph !!. Hendrie Chairman Addit ional contents by Dr. U. R. Stratton are presented below:
"The hidt of f-sit e doses which are stated to acco npany the proposed purp,ing operation are based on calculctions which include a number er assumptions which I believe t.o be overly conscivative.
It is my opinion that the situation, should it ever arice, would be rauch less severe and that the pro-posed purge systeu uould provide adequate protection for the l
health and safety of the public in this regard and therefore the additional hydrogen control equipment required by this letter is net necessary."
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Attachment:
List of References l
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sej,t iul,c, 2,g, 19 f g,
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!!onoralil (;l eno T.
S e.tlio r g I;cierence: :
7 t o inihe l'ower Company Application for Oconce Nuclear 1.
Arnemlaent. fio.
1, 7, and 3, con::ict ing of Final Safety Analysis St.it i on, Uni t :,
I and II, received June 4, 1969 Itepsir t, Volo. ic:
13 to the Ammnh..ent s f'on. 8 through 21 and l<cvised Amendiacnt No.
2.
1.1 re n.;c Appli cat lon.
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