ML20198F100
| ML20198F100 | |
| Person / Time | |
|---|---|
| Site: | Satsop |
| Issue date: | 10/10/1974 |
| From: | Tedesco R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Muller D US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-1237 NUDOCS 8605280412 | |
| Download: ML20198F100 (20) | |
Text
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. OCT 101974 i
l - Docket Noe. SIN 50-508 l and STN 50-509 l Daniel Muller, Assistant Director for. Environmental Projects, L RADWASTE SECTION FOR THE WASHINGTON NUCI2AR PROJECT 3 & 5 DES i Plant Name: Washington Nuclear Project, Units 3 and 5 Licensing Stage: CP l Docket Numbers: SIN 50-508/509 Responsible Branch: EPB #1 Project Leader: J. Norris Requested completion Date: October 11, 1974 Review Status: Complete i Description of Response: Radusste section for DES Enclosed in the radwaata section for the Washington Nuclear Project 3 and 5 Drsf t Environmental State:r.ent. The liquid and aseeous source terna were informally transmitted on September 20, 1974 to the Radio-
, logical Assessment Branch. . Drawingr will be provided later.
We find the gaseous, liquid, and solif radvaste systems meet our "as low as practicable" guidelines and, therefore, find them accept- ,% able. Mdnal s!gned by Victor Daaarsya i
% Robert L. Tedesco, Assistant Director for Containment 5.sfety Dir2ctorate of Licecsing
Enclosure:
V itri$dtion:
, As stated :ke t Aeading cc: w/o enclosure CS Reading A. Giambusso ETSB File W. Mcdonald ETSB Staff w/ enclosure S. Hanauer J. Kastner 8605280412 741010 P. Schroeder PDR ADOCK 05000508 R. DeYoung D PDR J. Clynn
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i e WA';Tr: T!u:! GENT SECTIC; FOR EhVJ EC.'::I :!'TAL STATrC *C WAh!;II;GTON I!UCLEAP. PROJECT, U'. iTS 3 /J:D 5 DOCKET I!OS. STN 50-505/509 During the operation of Washington I;uclear Project, Units 3 and 5 :adio-active raaterials will be produced by fissicn and by neutron activation of corrosion products in the primary coolant. Froia the radioac tive - materials produced, small amounts of gasccun and liquid radiccctive
! wastes will enter the waste strea.ns. These streams vill be proc e.c c e d and monitored for radioactivity within the station to reduce th?
i
; quantitics of radionuclides ulthtately relened to the anaosphere c.nd
, to the Cheballs River. The wacte handling and treatncnt systems to f be installed at the station are discussed in rbe: applicant's Prelininary t
Safety /calysis Report dated July 15, 1974 and the applicent's Ltviron-l mcz.tel Rcport dated .iugust 2, 1974. Thece dcetc.cnts contnin en analycis of the treatment systems g:nd an estimate of th(.,e::pected ..anual releane i
; of radioactive, effluents.
s j t.
! In the follouing paragraphs, the vaste treat.aent sys t e. ," r.re described I
and an analysis is given based on our codel of the appli.unt's props.ed radioactive waste systems. Our model has been developed from a review of available data frca operating nuclear pouer placts, adjusted to al',dy over an assoned 40-year plant operating life. Our li.;uil source terne are calculated by means of a revised versica of the 0::1CEI; Code which is described in OPJL 4620, " Oak Ridge 1.;otope Generaric a and Dep!etion s D N
c t' Codc." Our gescconc scurce ter.nc are calculated by tuunc of the STi::TD; Code an described in the report, " Analysis of Power Reactor Gascous Waste Systems", F. T. Binford, et al 12th Air Clevning Conference. '1h e principal paran'eters used in our source term calculations are ;;iven in Tabic 3.5.1. '1he haacs for diese parameters are ;;iven in WAsii-1258, Vol. 2, Appendix B. Based on our findings, we conclude that the liquid and solid vaste treatment cyctcas are acceptable and e.ect our "as low as practicable" 1cvels in accordance uith 10 Cra Part 50.34(a). 3.5.1 Liquid Unstes The liquid radioactive uaste will be processed on a batch basis to permit optimum control of releaces. Prior to being telcased sanples will bc analy:.ed to determine the types cnd a:.wunts of radioactivity present, nased en the results of the analysis, the vaste vill be
, recycled for plant use, released ut"ler controlled condi tions t.o the cooling touar bloudm:n or retained for further proccccin;;. Radiation monitors will autoniatically terminate liquid waste discinar;;es if radi-ation ratasurements creced a predeter:rined icvel in the discharge line.
Simplified diagrzras of the lic,uid raduaste tre itacnt systcaa are chm:n in rigute 3.5.1. The Chemical and Volume Control Syste'a (CVCS) will process prinary coolant from the letdown heat exchangers. In our evaluation of the radionuclide remeval provided by the CVCS, the principal components considered were tuo uixed bed demineralizers. The Boron Recovery
a
. . .l 3-System (EPS), a CVCS subsystem, vill precess a portion of the CVCS flow i (shim bleed) for boron control along with equipment drain vastes collected inside the reactor containment in the reactor coolant drain tank and I outside the teactor containment in the equipment. drain tank. The principal BRS components considered in our evaluation vere a mixed i
i 1 bed dcmineralicer, an evaporator, and an anion dcmineralicer. i Miscellaneous radioactive wastes vill be processed through the Liquid I 11aste Processing Syste;a (UJPS). The UiPS will segregate and process l
- vastes according to their chemical mahcup. Miscellaneous wastes will
}
.' be processed through a subsysteu consisting of a ficor drain tank, a
?
I
; filter, an evaporator, a mixed bed denincralizer, and a vaste monitoring i
; tank. Turbine building equipment and floor drain vastes vill bc l
filtered and recycled fcr reuse in the plant. f I I t glowdoun wastes fror. the stema generators vill be treated through 1
, the condensate demineralizer systeu and recycled for use in the secondary l
i water system. Detergent (laundry and decontaminution) wastes are processed i I
-l through a unste trectuent systen which includes a holdup tank, a filter,
[. j a reverse osmosis unit, and a waste monitoring tank. The following para-i graphs contain our evaluati$n of the liquid vaste system and our calculated I liquid source term. f 3.5.1.1 Chemical and volwne control systen (CVCs) A Ictdown stream of approximately 84 gpm of primary coolant vill be ren,oved from the reactor coclant system for processing ti. rough the
~
9 e e
}
CVCS. lhe retdo.:n strea:a vill be cooled through th.? !.tdeto best I, exchangers,' tedaced in preccurc, filtered, and proces: ed through one of tuo mi::ed bed A.mineralizers in the L13m3 fon n .h anko bed demineralizer will be $r.ed durir.3 the last 10% of the fuel cycle for boron control. The processed letdown stren= uill be collected in the voltmie control tank and reused in the plant. In our tvaluation of the purification provided by this portion of the CVCS, ve accumed an input flou of 8'. gpm at prir.ary coolant activity and applied the deconteminatica factors listed in Table 3.5.I for the CVCS mixed bed demineralizer. The CVCS vill be used to control the primary coolant boren concentra-tion by diverting a portion of the treated Ictdcun strec.n to the r,or on p.ecovery Systcm ec shim bleed. Approximacely 1. 3Z of the puri fied I letdown Llow vill be' processed through the n' S fer boron conn.ol. Ue ca.timated the purified uns input fre.n the CVCS letdo;;n s trean to be 1603 npd at approximately 0.1 primary coolcut activity (PCA). Primary cociant i grade water from estuipment drains, equipm nt leakoffs, and froci relief t valves inside contcinment wilI be collected in the reactor coolr.ut drain tank. Primary coulant grade rater from nource.; outside contain:aent will be collected in the equipment drain tanh and vill also be procesacd in the P.ns. He estiriated the URS input from the reactor coolant drain tank to be approximately 200 Lpd at PCA. We estimated the t'is input from the equipment drain tank to be approxiuctely 50 gpd at PCA. The s L
r I 1600 gpd shia bleed and 250 gpd reacror and equipment drain tand. vastes trill be collected in one of four 112,000 gul recycle holdup tanks. 17e applied the deconcataination factors Ifsted in Table 3.5.1 for the I preholdup mixed bcd demineralizer to the s treams entering the recycle holdup tanks. 1?c calculated the decay tirr.e provided by the holdup tanha to be approximatcly 56 days based en 1850 gpd input flew fillina one tank to 807, capacity. Liquid collected in the recycle holdup tanks will be processed batchteise throur.h a 20 gpa evaporator. The concentrated bottoms vill be either pumped te the botic acid uakeup 1 tank for reure in the plant or to the solid uns Lc nsnagement sys ten. (SI.'. S) for disposal. In our evaluation ve considered the concentrated evaporator bottoms to be processed through the r.olid waste rysten. The evaporator condensate will he processed thicugh an ar' ion ?nineralizer to rmove i
!' radionuclides cutrained in neisture carryerer, and of ther collected l
i
, in the reactor naheup water storage tank for rcuce in the plant or i
diverted to the ucate recycle tanks in the Lt?PS for samplin;; and dis-i
; charge. In nur evaluation ue used the decontanination factors in l Table 3.5.1 for the n!!S cvaporator and BRs condeusate dcainerclicer.
11e calculated the holdup time due to processing to bc 6.3 drya based on proccasing the c'ontents of one recycle tank filled to 80s ccpcity throu;;b the ImS evaporator at 20 gpm. tie assumed that 904 of the evaporator condensate vill be recycled for reuse in the plant while 10Z will be dis-charged for trition control and to naintain the plant unter balance. The applicant assuacd total recycle of the nits strena in his evaluation, m
I ~ 3.5.1.2, Linu!d ins te procenning Sv<:t em
- !!iscellaneous vastes primarily f rom floor drains, ncn-detergent decon-tauination operaLions and radiochemis try lab draina vill be collected I
in cne of two 30,000 gallon floor drain holdup tanks, sampled to deter-mine the degree of procesning required, processed as necessary through a filter, an evaporator, and a mixed bed polishing demineralis:cr, collected and monitored in a 15,000 gallon vaste maaitoring tank and recycled to the condensate storage tank for reuse in the plant. If the radioactivity is above a predetermined level the waste vill he recycled for additional treatment. In calculating releace:. fran the LWpS we assuced all vaste is processed once through the evaporator and detaineralizer before release. Based on information submitted by the appifcant and our parameters for liquid vaste volumeu enri activitice given' in WAsil-1253, vol. 2, Appendix A, wo esti:nated the total ficu i in the syste:a to be 1300 gpd at 0.022 pCA. Uc calculated the collection time in the floor drain tank to b2 la days based on the time needed 4 I
, ; to fill one of'the two floor drain tanks to S07. capacity at 1300 gpd.
, 'l Uc calculated the system processing tiac to be 0.83 days based on the evaporator design flow rate of 20 gpm. 1:vaporator bottcra and deminern-li,zer recins vill be disposed of as solid waste. There will be no regeneration of dcmineralizer recinc.
The applicant proposes to recycle all of the processed wastes to the plant unter systemn. In our evaluation wa assumed 10/. of the processed unstes will be discharged. On thic basis and using the paramcters given s
in Tabic 3.5.1 wr calculate relences f rco t he Ir. S to be approxinn t..ly 0.00014 Ci/yr/recctor, es.cluding tritium an t diccolved taccc. In hin evaluation the applicant calculated LUPS re'es ce to be 0.0014 C1/yr/ reactor. The differcuce bet cen our calculated relr.ases, and those of the applicant are due primarily to differcnees in estir.ates of short lived fission product release. For calculationil purposec, the appli-cant has ascumed a 17, release frem the miscellaneous vaste c" stem. "Th e applicant did not assume a release frc:a the MF.S or frcra the stcam Cenerator bloudoun system. i 5.3.1.3 Turbine Building Floor Drnirs and Daterren' Usster l Uastes collected by the turbiac building floor drain system contain radioactive materials reculting from ceconda. y c; ite.n le:.k te.. The appil" nt hat, indicated that these vastes vili Se rc ycl:'. Our cvaluation, houover, as.7 emes a 101 Jischcrac of e.trertce . n te f r. . i th is systcm based on anticipated operational . cearrcnces. nased cn i our nauuuption of a 5 gre Icah rate at main tem activity (0.001 i secondary coolant concer.tration) u.. calculate a release of appre::inately l l 0.002 Ci/yr/re:.etor, excluding tritium, fec:a this source. Detergent i wantes generated fro:n laundry and decontcm.inction operaticnu wil.1 ha processed through a reverse osuosis unit and, if necessary, the ISP3. In our calculationa, we casumed all vaste vill be proccsced through thc reverse onmosis unit only prior to release of 100'4 of the processed strean. 11aded on our nnsumption of 450 gpd of detercert t.aste rit 10 uci/cc and a DP of 30 for the reverce ob;.osis unit, tc calculate a release of 0.002 Ci/yr/ reactor, cncluding, tri tina, f rc:r. tbir .murce. 4
. . 3.5.1.4 Steen Cencratur niredo.vu Blo. doun f rua the Lleam generaLors will nen.: ally be reLurned to tbc condensate denincraliner detras tream of the condenur r. Thera vill f>e no provisions to discharge tl.e ble.;deten directly to the envirencwnt and therefore there u!.11 be no contribution to the scur.:e term f*:cu this source.
3.5.1.5 T.1 uid I,'as te Sur.= cry 3 Based on.our evaluation of the liquid vaste spters .re calculated the releases of radioactive natori.als in liqui.:: vastes to be approxinately
~ 0.01 Ci/yr/ reactor, excluding tritica and dit solved r,cscs. This rel eaco nuc nonc.nlized using the parameters in 17/C.I-1253, Vo'. 2, App. l to 0.1 C1/yt/ reactor to account for equipar;at du n iac auJ anticipat.:d c; cratiouril occurrences. 1lc calculated the tritica rclecae to be appro::imately 350 C1/yr/rcactor. The applic:mt eccin-eed rim 11. .:f d relcccc to be appro::imately 0.0014 Ci/yr/ tecctar, cn :luding tritten and dissolved gases, and 11 Ci/yr/re.:etor for tritiwn.
Lased on our evaluation of liquid radcaste rel,c.tces ue c al cula ted that the whole body and critical organ doses will be 1e .s than 5 rzen/yr at or beyond the si te boundary, and that the proposed systems util ha capabic of limiting the release of radioactive catericls in liquid efflu-ents to less than 5 C1/yr/ reactor. lie Ciud the propo.:cd liquid raducste system to be capahic of reducing crituents to as low .n prac-ticable levels in accordance uith 10 CFR pert 20 and 10 Cpa part SU.36c. based on our-findings, uc conclude that t h r; preposed I i rinid rcdott. t e *
~
syn tetu 1: acceptabic. 4
e-3.5.2 casocau 1.'as t e . The principal cource of radicactive caccor:s ::astcu will be gases stripi.c d fro:n the prinary coolant in the Uns. Additional sources of gescous wa tes will be main condenser evacuctica rystem offgases, ventilation c::hausts froat the auxiliary buildings, and gascc collected in the reactor containment building. The principal cyc tent ter tre:.t in:; :;anceus wastes uill be the gsscous vaste processing syste:a (GNPS). The CWPS uill collect and store gases stripped frcn the prisory coolant and gases vented fren tanks and systems cont::ining radiocerive fi t.c len
; geses. The CUPS consists of two compressors. Lua ca talytic rc eo..-binern 4
l and nine gas decay terks. Ventilation cir frca the au::111ery buildine, j and offgaces frem the main coadenner ci; ejecter:> t;Ill be procer,6ed i th roug t charcoal cdsorbers prior to release. Th. reactor ecatein;.2nt 8 atnosphere will be recirculated through 11 EPA filcer and charm r.1 adcorbers prior to relecco. Ventil::tien air fru.. the tuichin > ba f I din; vill oc relcased uithout treatment. Ventilation i.it fron cha contain-ment r.nd au::iliary buildiage and gascoau wastes frc= the con.tcucer evacuation sycten vill be e:diancted through the vents atop the auniliary building. Ventilation air f ro:a the tuthf ue building aill be enhct.sted { through the turbine building roof vents. The gaseouc waste and ventilation treatcent systems are shocu schematically in l'igure 3.3.2. 3.5.2.1 Gascons !? ante Procensinq_ System (GUPs ) The CUPS uill be designed to collect c.nd procca.s goces stripped it w the prire.ary coolant along ui th cover gr.r,e: fre.n niccellnnecur. L :.ni. s . L
I
- 8 10 - ,
1 f i l Caseous input., wil) inclivle a vativble 1.5 to 20 sc &a hydre;:en parte l i of the CVCS volene centrol tank and sraller r;ucati t les of radiocctiec f gas from the baron recycle evaporator, react.or conla.nt <!:cin Lauk and the recycle holdup tanbr,. Inpu t gases will bc procer.n >d in a c1rised loop containin;; tuo vaste gas compressors, two catalytic hydrogen
- recom.biners and ninc 700 f t gas decay tanlu. The systen vill be designed for ccatinuous recycle of radiosctive cases; houcver, in our evaluation un assur:ed the r:dioactive gaces vill be released to the atmosphere af ter a 90 days holdup in the cys tem based on a uuste gas input flow rate of 140 ucfd. On this bct,in uc calcub ted the CWS relccces to be approximately 1100 Ci/yr/teactor for noble r,:res cnd negligible ( <10~ C1/yr/ reactor) for iodine-131.
I f
=
I
e -~ > 3.5.2.2 Con t e. : .m t ?ra t i b:: f oa S . i a 1:adioactive gerim vill be r: lem;cd ir : h the r. uctoc cont,i n ' st 1 I uhen prir.ary cynten ca.oponente cre opened or when ladup ocean f ro . the prb.ary systeri. The gn ecus activih. "lil be valtd within the contaiencot durine,norrcl operation bur vi u be relonsed deriur, containment purges. Prior to purgin;; the containr cat, the containacnt ntre.ouphere will be rceirculated throut.h the centahnant et:.c vheric control systera (CACC') at appror.iuatcly 11,0 T cu.. The CACS .7111 consist of tuo parallel trains, each cetttainicr, i IP.; filters and an activated charcoal adcorbec. Purj.c efflue,t i'l be ro.1c urd fron the pinat vent at'ter paes!ng throrn' IIPA fi't cre and chm c o d ndnorbern and heit.a r.onitored for radf nactivity, Pe calculat.:d tia containment nirborne activ ty based en ?40 lbs/e- pri::J.r y c 11n.it les';cce to the conreinnent and a partition :: ::t e) e f 0.1 f or rt.diu to'i:.. . Ue al so assened t'our p irpon of the ccca nit : en. ; e vear. Ca t r:i 5 basin we cciculated relences frot' the containr ist f.o 1 e :.p a o:Irntely 22 C1/yr/ reactor for nobic gacca and r.c311;;i nl e f or iod i: e-3 . The applienut d.id not provide a separate ac.aunl relcare calcul::: Joa for this cource. 3.5.2.3 Vent 11ation Gyrtem for othm !!n n d N: lbdioactive material will be introduced int.o the plant ctuawber< due to leahage fron equipt cut procecuing or holding radiocetive en t e r.: n13. Ventilation air f reu the :.u:.111ary Lufid '.n ; rill be proccrew:' throu.r,h IlhPA and chareoni filters, noultored for radionet iv:t y and rele: ;cd through the pl.nt vent. Ve.stil; tion ear fro.2 t.he rautar.tc arc, of the auxillary buildinl,Uill be procc r.dnd in t L< <
. re #.r.e v and re le:.ac.!
through the in;1 int eno r ve,1t. . Ven t i ; a . J e r. n:r i n t- 10 <. i nrb .ie i
12 - building w W 2 men"ored fo' redicactivit y ' relected ulthcat treat ent.
!?a cerittate that J C'1 lbo/dc.y of prl .rtry coal. .:t ui!.1 Imd to thc.
nuxiliary buildint;. Since the letd rm heat e a br.ngert, rH1 he
- located in the a n:.iliary building, ce ason; cd ail loab:;u to tha ouxiliary building vill be hot end applied a partition facter of 0.005 for radiciodine. Da thic basic re calculated the au:lli.try building releases to be appro::ir:4;itc]y 170 Ci/ir/r: actor for nobic cases and 0.053 Ci/yr/ reactor for iodine-J3L. The applienat calculated the auxiliary buildin:; releases to be appro&at21y 270 Ci/yr/rcactor for noble gancs and 0.000 Ci/yr/reacter fos: iodine-131.
L'u estinate thet 1700 lbs/hr of secem wil] le:O to the turbine building at.~ouphere rod all noLic g:n.es un 1 r:.dioicd.inc relerred eith the cteam vill remain airborno. Ca thin benir, t-o ca.let0 2tc the turbire buiJding vent release to be 1e::n th n 1 C1/yr/r:rctor f.cr noble naces cnd 0.025 Ci/yr/rcactor for to:13 m . ". 'U . tlc. ...t lf.cr..r t calculated the turbine building releases to be 7:ecligif'.lo for nobl.* gases and Jodinn-131. 3.5.2.4 Stern Pelenc:ce to the '.t rioc nh e re The turbine hypens enpacity to the condenser vill be ":ppr '*:!'u t el;- 55%. Our c.nalysis indicates that stecr. releav:n to the cuviroartutL due to turbine trips and lou pouer physic:; test.fug vill have a negligible effect on our ca]culated naarce tocan.
- 3. 5. 2. 'i "afn Cnadonner offenn it:1 ea c e r.
Offgas from the taain condencer air ejectora vill conteln rMior.cti.e ganes resulting fron primry to vocondary : -t en J eat:.in . Ted f n.' v '.11
~
}k I! Ib % ) .k [k .5 04 k .k
..L 5 4 ( . 4 j *] h
- . h[. -.!!
IJ U L Ut ;'.:ll LItc cUndt'll.%if t;,' hnfl MOiltfulldt n<,lij p, pI . I ' *;0 ?' in til? 'Jiill CO.1dC'12 s e m
1:ain condenacr offr,as vill be procer,wd through a cF rc<in1 oh.orher prior to relera:e. In our evaluation re ecaciderud 110 lbs/dny pel .; to cecont'ary ayut en leakage, ,partitica factors: fer r.dioiciine of 0.01 and 0.0005 in the stear.t nencrator and r aia cen&ncer, rc cpectiv+c, and an iodinc decontaninatina factor of 10 for the charcoal edcorher on the offgas line. On this b:mia, un calculated the mia ecnc'ent,c c offgac relec.sen to be appro::Juately 3 80 C1/yr/ reactor for nob i.c nanen and U 050 Ci/yr/recctor for iodine--131. The applicant calculaLed the relcancs from the r'ain condenser to be approxicately 125 C1/yr/ reactor icr acI;1.c r., aces cad 0.007 Ci/yr/ecueror f o r J cdin c -131. 3.5.2.7 Cancous Paite Su ery raced on. cur evaluation of the gaseous oncta trc itrent syster:s, ra calculated the total releases of radcoactive natcrialn la cancour canten to be approxhately 1500 Ci/yr/ reactor for i.u';.1 e r:ser and 0.0$3 Ci/yr/rcactor ror icdine-131. In his eve.imt ion , t'ic :.pplienr.t entinated the gasecuc releases to be cppron h:'ateJy 400 C1/yr/ reactor
~
for noble nacen and 0.009 C1/yr/renetor for iodine-131. The applJ. cant han proposed to inctnll , tate -of-cha- are n.uw.'s effluent treatment equipnent.' Daaed on our evaluation of the applienat'n proposed gacr.ous raduante treattent t.ystem, ve calculated thr.c the annuni air donc due to enr:na radiatieo at or beyord the cd.te boon:'ary vill not exceed 10 millirada and the aanual air do:., dua to ieta e radia: Jon at or beyond the sit e boundary trill not e :ee:d 29 t 11)iradn. Ue calculate that the total annual qu: ntity of iodine-13] rele uM ifil m
r .r not exceed 1 Ci/ reactor vnd th :t tha nnnon t c'coc to .m und ivJd ' .! I by all pr.tlwayn an evalunted in Section 5.4 ull1 not n:cced cl." I "an low as practicable" guideJIn: , o f Resp.d n t o r) G u it':' ].l.2, end therefore, find the prepoacd gaseous vaste treatm.cnt r31.Leci sceept: ble. 3.5.3 Solid '.7astos The solid uante r:anager:ent systen (S'.-:MS) ui]l be desi;;ccd to proces. two general types of solid uantas, "uct" usares which require nolidi-fication end pacLagin,a, and " dry" r,olid vaster culch rcquita pach q;1ug only.
"iiet" colid vacten elli concii,t reain1;. of cpent filter cart ci<ic:n, decinvalizer resins and evaporator end RO u .it concevucaten and u'll contain radienctive .utcrialc rer.. val fron Uquid nt: c.. du ring procescia ,.
"l'ry" solid easte ulll wncist m: . ly of lou activit;.
. ventilation air filtern, contar.cnnted clot hin ;, p ger, cod p13:en32 v m I
-'teun such ac Jaborat ory ?.Inssuarc nnd tec1. . :fi s e. 211 mem, " a". ir.
vactes n;ch us irradiated pri::ary synt om comuneatc, u! Al 1,e ha.41 M i on a ccLa-bi ccco banJn boccd on their cire end ceti"It/. The principal uources of opeat deuinera'tirer resins vill bc four 22 f.t"s CVCS and 1CS d.ninoralL:ern, and tua 4 ft3 IA M do."Iccratinc.cc.
%ut resian fron thoce deninorali::ers vill be collected in the 3000 r;nt.
L1:US spent resin storage tank, slu tced to a noJ idific.,tica haldup t.ud-for devatorina, mixed with a colidification ngent and catalyst und no]Idified in 50 f t. or 150 ft3 linera. Concentrated unacen f rom the 20 apa 1,';t S c enporat or .nd t bv 20 gp-- CYCS bor te ac ht evnpocal or u!11 he pur;>cd f rr :' th::tr re g ecti"c. ceccont rat.e b.4 h'op t:nd : to t'.e 3000 ;M . w l i.r' i . fST h n concoorrt: e
holdes tank. Concentrates fren the rolidiricatica Iv;1 dup tanh, s) and nolidificatien ai,ent vill be pte.p;d simulnmecir:1y to the shJpping containers for rolidi'Jic:ition. Cctalfre il1 ~be :ded in the nJxing nor.zle used for fillin'; the conttiiners. i Eased on our evaluations of Pic.s t,*ith similar lLquid waste sycte.nu, uc have deternined that arproxinately 4500 ft3 / reactor of t eclid uant es u111 Le 0,cnerated anni ally. Uc catiuna these to ccatc.in approxirautely 6000 Ci/ reactor of radioactivity, principnJ 1y Ca--13i i and Cs-134. The appliecut estiuates the uct e,o!id unntea chipped t off. mite por racct.or to be appro::i:nn Lel;> 2 4,C003 ft /y. e m .'h N 7,00;) CJ. of activity. Dcy nelid u.uten vill be peelw;cd -In 55-;,al. dru ~ . Compr m ible
; unstes, e.g. , clothing and contaninated rar;c, vi).1 he cc:.: pre ncd I
t,a in3 a hydraulic haler. Uc catinate the dry % lid unhten p.c reactor to be appro::Inately 450 dre:c.n/yr conta),dnc a tot:.1 of ' C1. e The at.plicant estin:stes dry nolid uaston to be eppm::fintel*, 373 f t"/ yr/rcactor an 1 did not pro.>ide n sepm: ate estitate of activity en:.'.<ent. f
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i Daned on our evaluation of the colid vaste nyatu. ue conc 3trde th.it the i systen design vill accon.nndat. the vasten expectc<! durin;; nomal operatienc includin;; anticipated operat!cnal e ccurrcnces in accord:: w. Vilh cxicting A1:C, local and Federal h.mulstLon:, The cantec uill be pceFar,od cud nhJpp:J to a ,1tecased burInt r,1te in accordance ulta AT:C vnd Dop.trt:r.cnt of Trali:rprirtativa !!c,: ult.;Ic in. Ihm' o,t thane [ iinI I "[' 1, CO L oDl' ) tle'. ' ' [ bilt [bC bol bl I .sCe * :tL $f PCCeplPh)e.
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. Teile 1.5.1 Princip 'l l'arameter7 t.Sd cooli t inn + !'wd .in Calciti .,t inn it.d "' w j of 1:adio .c t.iv. M rrial Rt Linu M. c.nd Gaseout ' if.iuei,e .
I from t'c sh!natoc. II;cl ear Proj t et , M. 3G5 l Reactor Pover Level (J:L) /,000 Plant Capacity Fector 0.83 Failed Fuall 0.2S% Primnry Systea
!!acn ot' Coolnat (Iba) 5.45 x 105 Letdo9a Rate to CVCS (>;pn:) Cl.
Shita Elte :d fatt. ( r,p.'a) e 1.1 lam aca ' late f.o Sneradaty _yatam (ihn/iay) 110 Lanhone Rate to Ac::iliary Buildin;; (lb: /:.y) 160 Lc.akcca Race ta Contain: -t Euilding (ib :/c ny) i 240 Secondaty Systcu 7 Stenn rica Rt.te U.ba/hr) 1.72 .: 3 0., thsn of Stec:a/ Pean Cuncrotor (1bn) 16.5 z J 0" 7' ann of I.iqujd/Sceca Gucr.u ar (Ru) J.65 : 105 Seccadar y rea t uit '!asn (Ib c) 2,8.1 y li /' Rate of Ctem L .9. y ta Yurbin %ildin;: (Ibn/hc) 1.7 :- 103 Stcrin Generator ble.idow hatc (,qpa) 20 Dilution Flo:- (gpt") 2.2 x 103
- . Cou taint.:en t .' .:11 <'in g t/,li.m (fc3 ) 3.4 x 100
; Frequency of Cent: law at Forres (per yerr) 4 .
Iodine Partir.ica Tactorn (; :m/lic u.id) l.cahane to Ccato k:xat r.ull.dirig 0.1 Leaf st.e to Auniltery Build!n:: 0.005 Stem; Lenhv.c to Turbitte Eu!1 ding 1 j Secan Ocnerator (carryover) 0.01
. ifain Coadenner Air Ejector 0.0005 i
11eco itamination Pnecewn (l . it,u l.d q ).-
, .I .cy r;: '., _.o_ z.7e Y ctbara Doron Recovery Synte:n 104 103 105 105 103
!!incelletienus Liqu td Marte Treateent 6 yg5 Systen 100 105 106 10 Stenia Cenerotar U1.ou-dova Tren: r.cu t Syn':en 2
, 10 1 10 302 10 3 Thin valuc is c mntalit and cortc .;pon.in t n 0.25" of tiie ope ratio,", l'0 W T Il3dIon PI$.d.tct rout et ter a. .
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