ML17341A249

Low Level Radwastes in Fl

ML17341A249
Person / Time
Site:	Turkey Point
Issue date:	03/31/1981
From:	FLORIDA, UNIV. OF, GAINESVILLE, FL
To:
Shared Package
ML17341A248	List: ML17341A247 ML17341A249
References
NUDOCS 8106190311
Download: ML17341A249 (153)

Text

UNIVERSITYOF FLORIDA ILIA-ILeVQI RacHoacBve Wastes JB. Box'EBB.

&o4 6~44 pie&

e+@5.

rW REPQRT:

8106 1903lly.

PROGRESS REPORT UF LLRM 4

0

li. Emmet t Bnlch, Pl>.D.

)'rof'es or

)'.nvlronmentnl En8ineerinp Sciences Princip;~3 Tnvc.'i) at< r C)>aries E. Roesslcr, P)i.D.

)'rofessor Hnvitonmcn Lal Zn~<:ineerin;!

Sc> oncet Co-Knees tiga tor Jn))n A. 1!ct):in~ton, P)>.D.

Professor Nuclear Engineering Sciences Co-Investigator Ttiomas L Voy Graduate Assistant Herein Bortez Graduate Assis tant Linda Sc';.'cll Grac)uatc hs..is tant Joan Pisarcii.

(lory Eaplan Jim ):eelcr Graduate! Assistant Gracluatc hs istant 8fudcllt AssQ.S tan t Shirley J o))nson Haul Podriquc z Pedro Salas Sccrcta j y Indep.

Study 1)oak Study Bradley Dixcndor'ave Hall Joel Case 1!or):

Stubbly Grad.

Ass t. (7/1/80 l0/8/80)

(>1 Id Ass t

( 7/l/80 l/l3/8l)

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~e to the. United State" e):pl ebs BQ f>1'a tr'i 'uc ceno "nQ t)>o >'lo."ida Dopart.cont of Health and

!'.o)':>Liiitati ve,Sor '.i co': f 0J'rovicl:in/ t)'.e funo in@

os Qlo Iioà anQ i'o the 3"lorida Power E Light j~ovc

.a(i(.

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> v.ex Corporation for their Co@:.",-".n.

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1ik& to than)c Dr. Fmmett Bolch, E'~ri a". "-""neo..J'.

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".'n)c'o Dv. 13ol'ch.for

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3ur:in<<, the cour e, n my ii'i." as" ~.st ince QnQ Bat:i once

ABSTB!'tCT The State of,i'lolida curre>>tly ha(

four (tpcrationu3 commercial nuclear poL)er plant'.

Xn 19'f9t, over 91,000 cu'u.ic t

feet of 3o:>-level

) a(liri~i <;i v(; L'UlStQ(L) i{3!'! Lt' f".erlCL ate(1

!))

I-lox id:-..

86 percent.of that by nuclear Ao':.'er o3.ants.

~

Hb T:"..- Aer Lt Lo) of LI Vi

) in Auclc ll po'.'" plants

."el'ves '0 protect th e)lvironmcnt At., r the plant: ite and to px(ttect She personne" 3:.'Or 1(i>>f; irt thc plant.

Bct(iioacti ve contarr.L))ants ar(

-e re))loved from ti!e plant '

1 iqLLid syst('rt!s bef'ol'e ti)e liquid-a) e di::chal "t'd to ti)'e environment.

Ti)e LLPhl rcsu3.ting~

Pro)rt procc:.."-

in/ the liqu"ds t!')e") pac)(ap'ed t'o py'ev nt the radioac1,ivit~,:

'I fl"om bei>>f" "lc;:se.: to the enviro) tmcn'c for and at tcx 43))'

a3.

LLP:;? is also pe)'t'::";.Lied'>> a 1)uc3( <<r po":(.r pl-:.'>>t duri))p i!OL)sc-

/

1(ccpinc;;.Lnd r'.ai)'t:enanct; act:iLvit;1cs; Ti)is LIZtH i." the rz:-;LL3.t 0 'c 'ilnel pro"( ot.'L(tn 1"88

~

~ urges

.3) LGA cL;t'cL.'Lnst tl)e rad:io:.!ct'e

(:onta)n."rtatior) h;! zar(1s '1.))i)crent.to a Auclca)'la)'Lt.

I,

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'i.'")e primary:-:,eti)od,of reduc <np the vo3um.. of' LB!! j.n. the"'.

nuclear poL)cr;>lants in 1"3.ori.da is romp.Lction.

Th(," p'1 ant h

pc..on>>el are also trained in wo)"): practic<<s,which rc(1vce I,L1~U volumes.

-1>> addition to th1s, both of th utilit;ic" cpe)'atin,.;

)'lucleal poL'ler plaA in 1'lori(ia,. LL'(.'l)vo3 ve(l j n

.". bud L(.'." of ti (.ir c>>rrent LLE'I manas>cmenb practic(;s arid are e.:a)nin:t.ny. th(:

fcasihilit>> of e)nploying <<dvanccd volu)roc )"e(1LLct:i.on.tecitn:<<iu(:::.,

sL:c'r) as incineration to fur the)

) ed>>cc I,l,! ':! vo3 umcs.

To date, over 391,000 cubic f'e.".4 o.[') 8;t'):.!:~ be(.A f.-Q'-'tcrAt'(;(3 bv the AL)cleax poL!er plant() jn I'3.oride.

Ti)(. annual volu'me Ag r( acitcd a pcai( i)) 3.978 B>>d llas sin('c si to!')'3 a (1('c3,:LL)e

'L l)i(,'i!

'hould continu(;

t.))roL)gh 3.'.)80.

On(. ol'l!>>

) 3o)'id:L plant i) 3s Vi

h Ld a nuAlt>er 0f s i!',nifi.cant

~>> ol> lc.:->s thr".uphout its s hort C

operating history w!iicii contr.iL>ute(i to the above Bol

~1>f>.l LL!<1!

E volumes.

Xt is holi<.vod that those

!>robloms have been res<>levied a>nd lower T.,i,B!) volumes are ex!iocted in tile 'futul e.

'I'wo other oper"tin>.. plant" h'ive 'hown dec3.i.":in~

vo3.umcs in z ccent year-"-

but due

..o necessary ma:intenance, the LT!51 volumes from these

~~

~

plant:

w l incr ease from 1981 through, 1983.

'J>hc ot;her nuclear

'.>o> er pl-"..nt J>a:

had except:i.onally low LLR!> volumes in the past and uocreases are ant:ic:i!i ted for thc immediate future.

3:n 198"-, "he fifth nuclear

!~ower plant is expected to begin opo: ation.

3t 's anticip: ted'hat'is plant will generate.

relatively s>na3.1 volumes of LLE'.

y 198~~, it; is ",.rogocted th".t t!!e volume of LLB<1 from nuc." ear po 'e. plan' in )"lorida will b about 7>~000 cubic

'eet p.".r year,

'n,.'a;"-::d. to a J.most 9),000 cubic feet genera.ted 19 j8.

7!>c projected value in"lu.'cs the effects of an additional plant an;1 ci ed>t.

volume re">>ction methods which are current3.y planned.

0

I'HVliO))tJ( l'lOl)

Thc t!r!iversit'y of i.LoI'id' Urldcr a co!!tract f)'0;rj t ilia Un:Lt6.".

. tat.e" Depar:t!o(.nt of Incr(-.", i" con('duct:i.n, a study on ln!i lcve3. radar.ohct J.ve 1'JG. tc (JIRi'I) t.;enerati.on v!:i.th:i.n t,he Stat,e of ""'i:.d:-;.

'.i'he (:o.:;~".:ere'a.3>>uclcar

>o;,ex plar!t;: in i'lorida const.'(tute s major soux ce of LL1'lJ in thc 'ate, accoun'-i!'!

~ fo."

68 por er"'<. op t;h'..

I:o<'ai.

J.T.in'l vol<<n><'

n l<)78 an<1 for 86 <ier cont

'J !(u p(:s

~ of th s

> ortio!l of t!..::: igni.v('.r:-:it;y of ! 10>'.d'\\,

8 I.:.i',;.'sou'>y 's t.o provide a t,.;r!(iral de: clx'pti.on or ].I,rit 1'!all ip'0,;:ent J

!!uc3 (!c~r pol"f:i';. 1 a"!t'::!1!c3u(i.in<< l'l",.e BpDla chb 1 e spec:i.f i c

."i.n. Ori!: '.'Ion

': e'. to t'e Bucleax'3 a)'it'" in )'lorida.

'J"le top'c."

!ih:ieh;~'ill b= 'ii.=cu::s(.d in this report: are I,TiIOJ sources,. 3iq!" d p-oce.",.:-.:i.n~~;

y...t(,"., pa( i:Being;,";;et;hod', volun!e rcduct3 on t.echn'i.oue.".,

(;ua i i.

Coiltrol l:"()rra!!s, and ons;i.t 'i:(ir<'.l",(; (:Bpacl t:ies f>('(i'~tl0'l<llv I...; vol i!8!'

I st:or'i'e" "!!;i pr()J (~(:t".>ons f 0:;

i'.<":. i > 0 t t)!c r!uclea!

po;:

~lar!ts an I'3.(>ridd;"i1.3 he pre.".cnt(!(i.

'lhe J.r>f o.......,~on i.x(.~~nt ed

(.3.~t,ant.. p(. >f.!,ca.lly to t..c nuclear pol;e." plant s in J"lorica",..

l;a."; oota.oned i.hrou;;h 'questiona:i) es

uh?n5!:tc(l to tile }'lori,da, ob '!'!)d I;ifight; Co!'.()Qng

(]'PPI,) and t:he 1"lox i(!a Po;;er "Co~"porat ion (j'PC).

Th(

ac<.ual que:

t.adonai>."-'!n:i the ut.i.litotes' esponse.".~

<<re en".lose(i:i.n h'i;t:i!(:h!;icrA l.

'l'h5s

'inX'o> nation ilas supplement,(:d thrnut-h tel(.phon(.

conversatl.on.",

!..i.th t;hc l'PPI, <<nd I'PC

= Il'8!t'manat-e>r!Cnt; per.".o:>>>cl.

3..

0 0

1'lozid i's nuclear.

ponoL pl;.nA;: are all of th>> pressurized 4ate d

'.i gn. 'ichu)'e l l.s a."iplp2,0 schematic 0

a pre 'suriTQQ

> at.ez': -.";"ctor

{PMR).

lnstc:ad of a coal, o:ll or p,as heat our ce, a

. u,""-c=.. r;>>ter plaiit fix"ions nuclear fu<:3. to produce the ho:it..

A'i.l '"our t;pcs, coal, oil, jas an'uclear pl.an<:s must produce

."t>>"m to drive a turbine which turns an electric generator.

l.o.'3 aria;.~:ater reactor

{9';lH) generates stcam'ithin the pressure vessel-cox'e unit, thus eliminatin~:. the steam generator and secondary 10 )p, P".'H 3n'qe PblR r."..-

a rv coo" "nt

\\

'T'h':. steam pas."es directly to the turbine in a s.i....:n in 1'incur<< l, i'ater, of.'ten termed the h

i.

r:u.;;, "d in 'a closed loop to trans "er the heat f'ro tl e c'.0> (: to

e "1 i f.'.enorator.

'this 1:el'it under high pi es."us:o to prevent boilin~

pr imary coolant in the core

~ i ~ e

~

a Pi Vho 1'i~"'i':'i~;:n to the st>>a;~ eenerator "j.s transf erred t'o a secondar>>

coo3.ant sy.tern.

After t.hc enerpy of the steam is utilized to the.maxiii;um possible, it must be condensed back to

~;ater by an external cooling source in order to romnter the s team genera t.1 on loo:>.

Ti>r..e U.S.

compariies rnanufac'rc P\\!P,'s:

bestinghou e'

rico@ Co.

Although 1 lori.da has only four operate.ng nuclear tio;ier plants, all three manufacturers aro represented.

i::lectric Cor p.

Conbust;i on 1!npi neering, Inc., and the Babcock and

PizUve

~

f.

C" i

~

~ ~

PPBSSUP]ZQ<+j I

f

~r.

I f'f fL Ier

~

p e

-'ontainrn"=nt structure

~

~

I stBBTn

~i '.3 SXMlTlferne

/g-xc -~'

- -'=c-".':I=---i<<- ~c-m""'x""=

>>,e<<e<<err 4<<e <<eI ff

<<4<<ree eeffeff<<II<<a<<<<

4eee<<ee l

t <<

I I

I 'I

'P

<< ~t

~r

~

.control rov Q

'i,~R pl GssUl 0 I fee.

~ ~ I:.I>>l<<

I]

I II <<..

\\ ~ II ~

~ J

~

~

ae ID

~ 'I

~ ~

<<V ee) << ~ g

~ 4,, le e

~

~

4'I7'l P >II ~ 7

~ ~ e

~

e<< le ~

Pl

<<ee

. V ~

t t<<I~ I rle I Ie [

lr

~ I e<<ei el 7 II

] 'Ir 4>>.

>el III e4~<<'e (:

ee Iet IltOEffffeW

~ e,'7 I'<< ff <<>>ff~>>ff<<>>>>rr4<<efflrwrII P I r~j. "

e a, '<<er<<'~

<<re ' 4'b4 a I el I'I purr.p,,

t r I.

~N. '4 Cftt

.I, re

~ I I;f IV

~ e C

~ Ie I

L.!-'I C

re IV

~I

. ~

e'e t

/I'g I ~re f

~I

<>I<<IV.

'<<ra ee'e'47>>It<<'e 'e....,r

~

.QfPii!ig

~ >ff ~

~

~.

~

~

~

~

I I

turbine gcnara".or condenser COO 'Ag

.v,".'.e-4'

0

1)~lorida is cu r z er!t 3.y ez'v '.d by fol))" nuc3.ear po4'eI'lant '

p)'oducinp over

.<000 )))op;!.';;)tts of'l(:ctr'.ical en(.~ }.v (}'~)':!o).

}':}.g;u) e 2 shol~s the loc~tions of these foui plants.

>"9.p;ur(.

2

~3':o

."ho'::s a n<)clear ro~cto)" 3(>cat.ed at

'~})e University of

!'1 o "..'

'he

f. L}1'i'J ~

i')e f'at io)') f1"o)ii th 'i.s lo',i'oli>e!'

ea(l1 o) >.'il1 no.'e

<iscusseQ in th:}.;- rcpo)"t.

} ! 0 ol)el lt".!s one r!u 3.ear pov Br plant, C)"ystal River Unit 3, 1'!Oa" Cr'y'8 1 Hive?1!>)"ida.

Thi s plant is R 797

}'5'ie

}3abcoc}:

and '.3c(i>:

P'-.'J-;.

Ci.,";t.al }3i.ve)'nit 3 b pan commercial operation ini i!-irch 19"<7.

T'!>".L ori~ rates t)): ee nu 1(.ar pol)er plants.

nea) j'o!re;-.trad i'lo:i(ii!. Doth nf'hese units aro 728 R!1e, j

I +

~

'"u key Poir)t Unit 3 began comme).cial

():>t."f'Qtiu)l 1)') J:Qce)l)ber',

1972 and.liriit ! in Aupust, 197*3.

) i(:..!'.u~;.

~ l":s ". '

FPH

} l':G 0 these p3 sr:t;., "'uri(ev Point Unit s 3 and

}, are located (it})(i) ))ucleav p(ilv.) }i3a.":t...t.. Lucie Unit 1, is.located near

'~'o9"t }~i(~gee

'i'3.Qadi

(}SI or! ';luI c})5 nso)$

Tsla))Q.

J op(:)aL.ion in })ecc).~be),

1976.

}'PRL also

})as a second, similar; This unit is ur!it ur)de:

constr>>ctior) at the St.

Lucie site.

(!j pected to b( f>Jn coNN( rc Bl opo) c tioi') 3)) 1983.

84. Lucie Unit 1 II is a

83.0

} >i'}e, Co)!!b"st'i oii }.!'le,".ln('.c) ini; 9'illa')hich began,corn!ner cial

~

~

a' L

L Figure 2

~ ~

Ca Jl)f~

~

Qt' rt~ ro4 vaaooaa lt'I rod) ~

D Lfl

~ al ~ ~ '

1~

~

I a

L\\

r CO) I~

Calv)

'a

~ ~ CLID t

1 J-

~ a ~I\\fl

(

tlttfr)OI VCD)OL l Ol

~are I c ILLUra

~art~

LC\\l vafor

~ta I I

Ctaworo al aftra J

Dt'I V'Lllal

(

~

~

t Cv

)V\\t J)UL)

~vIa lr

~LLCLIU P) U C C. E.P f(

. R 5 i' T 0 Pa S O pa",'

ga T>C;"Li.;-,

?a]

FLUMP; to(a fat ra)

)UU)'CO Llaf LfVVVVL

)ICCOL ~

~a)4LO

~ '

~

l,.(~

'I',")i

'La>C rat) VI

~

vat) I art I )OCO

+4av) 1

)a)ffra at'QYSTAl RD'4R 3

7c'!7 Hv

2. St:: 'LUCIE '1 810 N:<

I":)'St."I.UCIE 2-..

810 lie 3. TUM'.Y I'OiitT 3 728 Ifv

'TURM~Y:I'Oltl1 4 728 l.!r<

M 'UNIVERSITY of T'f,ORIDA TRAIHDlC 1<EACTO., (Ul'Tl')

100 la!

~fafa ~I fCLllla I

la)a O IIat aIa I~ trav vc aao DfLat) I v r

~ I~

~

~

~

~

lO Vfaria CfaILCV

~

~

a l St'ucia 2 is sck<e<lulc'.8 to 1>ag'f.u opazatioA i11 1983

~ "'.

5.

The 'it;ial sou) c>>

o fL)6!:i.n a nu 3 ear po1!c!r plan' s

)',.(i':.o."':.'

=-

I roducT;s or corit;aminant;s proQuced by the f'i'::i.on Q i r<.'.(:t, T i':-.'to?i )r Uprri(.'n' and corr'oslon pl odvct.s r(lp)l'>t ~ rQv

\\

t?)(.

)'CBCto)" CO)'C

~

)AOPe speCi f3.cally, i.t:iS the J'i: SiOA

) eaCt:i.On r'liicl) ooc:ins in ~hc roast o> core.

'!"..'er'e ere C>~ocr cc of act.'.vc! ':(;d ry t:h(: neut:1ron f3.ux

~

l"i:::::.";Or) !'Io(iuc!::: az e t?)e rndinact..v(;

at'oms pr(iduced vrhen t)ie 1.!) an."=u,".: ato:!is of';h(. fu 1 sp3:l.t.'ome typical fission product,s " "oduced b.',

"'ho fi.ssion reaction are krypton-85

.",trn.".'u!;i-90, i'()dine.L33, arid c<.siv!..-137.

Core struct;ures do not, ilIovide

{:o!:.'..)let.e or'" ".i.!'Im(1"it'5 the is

~ Ao)) proQuct s anQ traces o " '.h(:

)':::~:..'.o)).: <<c r!Cr."~.= c;nt;er l.n';.o T:n= 'oolant surrounding the I'eacior' uei

~

'I'hc p"i );iary coola)lt,.;.ter also cont;ains various t)'a(:e nol'i.'-(ci'w(:T:ive'l...;<<ent:s.

So)i.e of T;?! se elements are 1ril)(:l"eni.'o 1="le 1 a+~ r, some BY'e delib -) ate3.v added as chemical cont.rois:ind ot:h-...) -:)re e3 ement,s "::hi <:?. h vc co)")'oded and/or 3 ('a(:?!od

(

0'll T i" !Aa3. 'Burf'aces o f'he primary coolant syst;em.

tlhen t;he non) a(3ioactivo atoms:in t?re pri)vary coolant are exposed T:o T;l)e high ne1!-:"On flux oi'he x.eactor

core, some are transformed

i.nt:o

) ad: oact;l.v(.

at'orr;.

by a process called neut:ron act:i.vation.

'I'l)e::< r adl onuc3 ines are ref('.rred T:o as t:?)e activated corrosi 'on pl"oducts, F30,'ri'.

t yp3.(.'R.l hydroLc.n-'tri.t;iu)ri), i

-6'0.. Tabl.e l 1:i'T;.. t:he fis:::i.on '.nd act::ivat:cd corrosion product>>

ce!)t;rat::i.or)s found i n T'h(: primary coolant nnd the eppr @xi mate con a(:t:iv;.t;(-.d. co rosi.on products are r

Poll-5+

a.".i(: -$ ~>

> Kine-6$ z Bn(l cobal t-$ 8 and o f a t:.vpl.(:al I't'l]f )luc3.ear pori'o) plant;.

Table 1

Concentration>> of Hadioact,ivy. tlat;erial in PllB Priiliary Coolant; Concent, '3 on Conccntratd oil t!uclide gCi/cc Nuclide ljCi/cc Huclide 1"ission Pr oducts Conce".it x <<"'n liCl./cc m.i-85

)r-BG

~cr op Sr-91 v Y-90 Y 9il..

Y-91 Y-93 f.l Ci 1!b-9,5 r:;o-~l9 9'c-<<.rL flu-103 0.00017 0.0007 0.000019 0.0013 O.pu003>

0.00075

0. Qo 3.-'.

0. 000".i

n. 000>i 0

~Arlil,

~ %t Q

89 0.7t 0.00009 Hu-105 Bh-1 0 3m Ph-106

'Ze-125ltl Te-12 l l!l e-127 Tc-129m

~lr-- i?9

'C'-3 3".Ill Te 132

'I qo-

~ i-131 0.000021 0.00009 0.000021 0.000058 o.oon56 0.0017 0.002(

0.0031 O.ppiig 0.002?

p p>il Q.ppll2 0

5)l I-132.

I-133 I-135 C.".-13>l C~-136

~('s-137 B~-I~'rm.

Da-14.0 La-1!IO Ce-1'>t 1 Ce-1!> 3 Ce 1J) l)

Pr-1!t 3

0. 19 0-75 o.38 0

P5 0.025 0.035 0-033 0.000>lJI

0. 0003

0. 0001.3 0.000089 0.000066 O.Q001 0.000066 P,c'~" v:-.'.. d Corxo.sion Products Cr-51 hn-54 O. 001:=:

55 0.000'l Pc-59 0.0016 0.003

('o-58

(:o-60 Hp-? 39 0.016 0.002 O.OQ12 All others Tot Ql.R 0.075 Jt.7

~'

f 1:;vcept t:ritium <<nd noble pase"

" <<1'en from NUB78a

s'l)c r,"~(1ii.):!ct;). i" cont'amin ()lt.': !;)'L<<)'at;(: J!., t;h(.

J)) imar'oo)ant

':.v. t ('m l.lit;0 suppo) t:in'; aux'i.ll;!)'

.:,!.;t (!m.:.

'I'1) ~ ra(l i oac t't v i ( $

'v v t:h('n deposit'n 2 he int:(;rlor ur face." of';ho 1)ipirp, valves, and pum,'is of'!!e auxil3..!are systems.

When s)rail loa)(s occur t.!'n, a<<-:oa: r,ivo cont:caminant;s

.".eep ont,o the exterior su)'aces of'h ~:.'.:;";.")=.

the sur).ou))ding e(,vJpment

<<nd building su)'faces, an(i v;".:".;..".ily intro Lh>> plant.'s n clear relat:('.(1 drainage systems.

'J'h(. rJd9 ~;= ~ive cont;amin:.tnt:s NQ~/

Ac t ran.

( Orred t0 ot'hei

!)at: r"al~

.-.vch asi v.i;:inc. rags, prot.ective clothing, and tools when perso~"'ne";;.o

!'. on t.h

. s>ist:e;v. co;;.nonent;s.

ln order to reduce t:h(.

con.(! ~:.P.t'!.'8 of t.hol:e radloact'ivc cont:Bminants at t;he source a!!d t;o c-.n~a.'n an(i dispose. of';h(: cont;aminant;s wi)ich migrate o"..h ~> s';s ~(i;,-is <<";d i.'rea3 o f'. t;h" nlan

~ nucl(.a) pok"('r plant s

~.. ~i I>ki

< ~ o~

~

I Ca

.,C Iy

!~ave:

J.'J.i:.

m-:na!(..m;:nt; svst,om.

'!'!j.i.s 6>>st;em cont,ains, collects, proce': e:, s"".res,'

6 pac!(~p(-.s all. t;!le J,T,B;1 s hich is generated.

"i"v.":; i ) ll!!st;) 8t;:"-.:: 'e t: Voice)3 J,lrjt!.'a)la@em(.ntloi!pat:h for a

!r".'Jl !)v"l("<>>

'>oui(-

'ilanl;.

Tn t;he upcominir, sections, each part nf the J,L! ';! )rana('.",.:ent; syst;em u:ill be discussed.

8.

SYS t EVtS SOUP.CES

'VNAGTE FO.A";S D)SPOS)TlON

. Purifict!tion Systems Liquid Radioactive I'taste Svs t(!ms Reactor Ccolant Clcanun Sy tc.".

Spent Fuel Pool Cleanup System

."lisc. ii'astes Trc.utmcnc Systccm S Leam (:c.nc rater Blonde!~n and Condcnsat'.e Polisning Ca rtridp c 1'llters Demi uc ralirer Resins Fvapora tor Slurries Treatment aud Pocket@'I.u~<<

Ji, Qinp{~sa 1 I

Solid liaste Sys t('e".ls Used Equipmcnt Ventilation Systems Operat:ion, ?faint.

and Housc-kcepi!lg Wastes.

IQ Trash Used Equipment HHPA riatcrs

-Charcoal Filters Trcatm(.nt aud Paclcag 'ny.

FIGURE 3.

L

t'~fgbfJG.-V~;2NT PATH FC~ri A I=EVi"! t '..~LEAR POVf-t=; I=i Akt'7

LIQUID LLRN'OLLECTIOH AND PROCESSING There are basically four radioactive waste processing systems which remove radioactive contaminants from liquid waste streams in a nuclear power plant.

Typically these systems generate approximately 50 percent of the total LLRlf volume of the plant; however, the actual percentage for any individual nuclear power.plant depends upon the operating characteristics of that plant.

Reactor Coolant Cleanup,(orChemical and Volume Control) System The reactor coolant cleanup system processes the primary

'oolant to remove the radioactive contaminants.

In this system, as in many non-nuc" ear industrial applications involving closed circulating systems, the concentration of contaminants is controlled by "blowdown".

This process involves continually or intermittantly removing a fraction.of the circulating fluid and replacing it with a similar volume of "clean" fluid.

Unlike non-nuclear industrial applications, the, displaced f3uids in a nuclear. power plant may nat.be discharged directly to the-environment.

The "blowdown"'primary coolant is stored in large tanks, commonly called reactor coolant bleed tanks, until the plant management desires to process it.

The coolant is then routed through.a combination of filters and demineralizers to remove the radioactive contaminants.

The processed coolant, called makeup water, is then stored in '.tanks until it is necessary to feed it back into the primary coolant system.

The plant also has the option of discharging the makeup water to'he environment 10.

0

prov 3.ng id the radionuclide concentrations are below federal regulations.

The LLRN generated by this system is in the form of filter cartridges an em ner d

d de ineralizer resins.

The volume of LLR'v1 generated b

this system is estimated to be 370 cubic feet per year for

(/os q8~)

a 1000 1'&le PNR plant.

Another system incorporated into the reactor coolant cleanup system is the boron recovery system.

In a PNR lant p

the boron in the primary coolant acts as a chemical control rod for the nuclear reaction.

By varying 0he concentration of boron in the coolant, the plant can "finetune" the power level of the reactor.

.As the fuel, "burns up." during extended operation, it becomes necessary to reduce the boron concentration of the primary coolant.

This is done by'removing coolant through the reactor coolant cleanup system and replacing it with makeup water having a

ower 1

e boron concentration.

It also occasionally becomes necessary to increase the boron concentration in the primary coolant.

In order to have a ready supply of boron concentrate for that purpose, the primary coolant is processed through

a. series of deborating demineralizers and evaporators L

to provide a boron concentrate.

The boron concentrate may then I'e stored in tanks until needed.

The boron recovery sysem.also generates LLRll in the form of evaporator concentrates and demineralizer resins.

The volume zs estim em

'ted to be 690 cubic (jfuSqg~)

feet per year for a 1000 Nr.'e PMR plant.

e Polishin, Systems Steam Generator Blowdown and Condensat As described previously, a PllB nuclear power plant employs an indirect cycle to generate steam which turnms the turbines.

11.

0 0

0

Transfer of Che heat energy of the primary coolant to the secondary coolant system involves several large heat exchanger called steam generators.

The number of steam generators in a nuclear pow'er -plant and their design varies amoung the three.

PÃR manufacturers.

The Mestinghouse plants at Turkey Point use three steam generators, while the Combusti'on Engineering and Babcock and klilcox plants at St. Lucie and Crystal River utilize two steam generators.

The primary coolant from Che reactor enters the primary.

side of the steam gener'ator at a temperature of about 650 degrees Fahrenheit and a

ressure of 2250 pounds per square inch.

The f lofti rate of. the primary coolant entering the steam generator can exceed 60 million pounds per hour.

The primary 1

coolant is directed 'through from 4000 to 8000 small diameter, thin-walled, heat exchanger tubes in the steam generator.

Th thermal energy of the primary coolant is trans ferred to the secondary coolant which surrounds the heat exchanger tubers.

The heated secondary coolant

{steam) leaves the secondary 1

lt side of Che steam generator at a temperature of ab'out 550 degrees Fahrenheit, a pressure of 1000 pounds per square inch and at a flow rate of over.5 million pounds per hour.

The steam travels through the turbine and then is condensed back to a liquid before returning to the steam generator.

The secondary coolant system also goes through a

"blowdo~

process to control the level of contaminants in the =system.

=

Unlike the primary coolant "blowdown" system, the contaminan of. major concern in-the secondary system are nonradioactive atoms which could form mineral deposits within the turbine

~ system.

The "blowndown".secondary coolant is replaced with 1,

12 e

water which has ueen purified using filters and demineralizers.

The secondary "blowdown" system does not pose a serious LLN1

(

problem unless there is an inordinate amount of coolant leakage from Che primary Co 0he secondary side of Che steam generator.

I If this occurs, secondary coolant cleanup systems can produce

, a substantial amount of LLE1.

~

J'i'hen primary to secondary lea!<age does occur, it is generally due to small hairline cracks which develop in Che walls of the steam generator heat exchanger tubes.

The cracks form because of the tremendous stresses which the heat exchanger tub s are exposed to during Che operation of the plant.

Nuclear power plants do several things to prevent tube leakage and to control Che discharge of radioactivity when it does occur.

The prevcntativ measure taken involves a process

=0 called eddy current testing.

In eddy current testing, a

magnetic probe is

> un through Che individual heat exchanger tubes to detect any cracks or thin spots in the walls of the tubes.

If any indications of cracks or thin spots are discove

'in the tubes, the tubes are clo ed.

Fddy current Aesting is performed on a percentage of Che steam generator tubes during each ref'ueling outage as a part of the nuclear power plant's-E inservice inspection pz ogram.

Despite preventative measur es, it is possible that some primary Co secondary leakage will develop in Che steam generator during plant operation..

The plants use gamtna spectroscopy to check for any leaks.

Samples of the secondary coolant'are taken"periodically and analyzed 13.

i V

for fission and activated corrosion products.

If the secondary coolants contains any radioactive contaminants, the "blowdown" secondary coolant could'equire some degree of processing to remove the contaminants before being discharged frox the plant.

There are two methods of processing this secondary coolant, both utilizing a series oX filters and demineralizers.

The first involves only processing the "blowdown" coolant.

Recently, PNR designers, in light of the potential for steam generator

leakage, have incorporated a full-flow secondary coolant cleanup

system, called a condensate polishing system, into plant; designs.

A condensate polishing syst'm processes all Che secondary coolant which passes through the steam generato Xt is these filters and demineralizer resins from these systems which mav contribute to Che plant's LLRP, vo3.umes.

Estimates of the LLRlJ volume genera" ed by these systems range from 1000 (HUS1Fir) to 2000 cubic feet per year for a 1000 I%le PNR plant.

The actual volume of LLRlJ generated by these systems for any particular plant varies tremendously, as can be seep by examining the nuclear power plants in Florida.

FP&L's St. Lucie plant has never had any significant primary to secondary leakage problems or LLRN resulting from secondary coolant processing, The St. Lucie plant does have a condensate polishing system available for use in the event

~ this should become a problem in the future.

FPKL's Turkey Point plants have had problems with cracks in their steam generators heat exchanger tubes for several years but. the resulting primary to secondary leakage has not contributed to Turkey Point's LLRPJ volumes.

The reason for this 10.

'Aguac ~~et'r~

z.'A<

4 W o+ ~

M

~88 4~rs Non> ak)~ C~~~ g is, that the leakage occurred slowly over the years and has neve been. severe enough at any one time Co cause the radionuclide concentrations'n the steam generator "blowdown" to exceed the plant's discharge limits.

Turkey Point'nerator problems will produce a

LLRN roblem of a different type in the future.

Because so many of. the steam generator tubes have been plugged, th heat transfe efficiency of the steam generators has been reduced.

Xn the near future, the faulty steam generat will have to be replaced, adding an estimated one time producti of 37 000 cubic fe C

Co Turkey Point's LLRN volumes; FPC's. Crystal River plant has also had primary to secondar leakage problems with their steam generators.

The problems started when a control rod in the reactor shattered.

The fragm traveled through the primary coolant ystem producing punctures in some of the steam generator tubes.

The incident occurred in early 1978 and forced the Crystal River plant to be shutdown from"?'larch to September of Chat year for repairs and testing.

During 1979 the volume of water processing LLRH, i.e. filters, demineralizer resins, shipped from the Crystal River plant

.increased by 50 percent.

Xn the first half of 1980 the volume of water processing LLRN has declined to the same level as befo

'he control rod incident. lf it can be assumed this increase N

was due to increased secondary coolant processing, the control'od incident led to the generation of an additional 8500 cubic feet of LLRN for Crystal River Unit 3.

Miscellaneous Naste Processing System The miscellaneous waste proces ing system collects and processes the waste liquid from drainage sy Cems in Che 15.

0

nuclear portion of the power plant.,

such as floor, equipment, laundry, decontamination

station, and chemical drains.

The input to the floor drains is from solutions used to decontaminate areas and from draining system piping to the floor drains.

The equipment dr'ains handle any liquids which leak from the pumps and other equipment during operation.

The laundry drains receive Che det rgent solutions used in cleaning protective clothing worn.by plant personnel.

Decontamination of equipment also.

contributes to the volume of liquids processed through the miscellaneous waste processing syst'm, as does the chemical waste liquids from chemistry laboratorie and other areas of the plant.

Each of these 'liquid. waste streams is collected, sampled for radioactive contaminants, and, if necessary, processed through filters, evaporators,'and demineralizers, then discharged'rom the plant.

The contribution ot the LLRY volume from the miscellaneous waste procesqing syst'm is estimated Co be 7800 cubic feet per QJ<szeg year for a 1000 If;le P)JH plant.

C

. Spent Fuel Pool Cleanup= System The spent fuel pool cleanup system removes radioactive 1

contaminants from the cooling water in the spent fuel storage pool.

After the fuel bundles are removed from the reactor, they are placed in the spent fuel storage pool.

During storage, some of the. radioactive contaminants in and on the fuel leach into Che surrounding.cooling water.

These contaminants are removed by a filter. and demineralizer.

The LLRN contribution from the spent fuel cleanup system is estimated to be 180 cubic

(~.~ve feet per year for a 1000 YiNe PNR plant.

16.

LIQUID LLRtd PROCESSIIJQ TECfiHIQUES Each of the liquid LLRM processing, systems discussed uses a combination of filters, demineralizers, and evaporators to remove Che radioactive contaminants from the liquid waste streams.

Filtration is used to remove suspended solids from a solution'.

Any radioactive contaminants contained in the suspended particles are removed by this process.

Nany types of filters are available for use in nuclear power plants;

however, the predominant type used by nuclear plants in Florida is a disposable, cartridge filter.

A cross-sectional view of this, type of filte. is shown in. Figure 5.

The filters units are replaced when the pressure drop across the unit becomes to large.

It is the individual filters which constitute LLRtl.

Demineralizers utilize an ion exchange process to remove radioactive ions from a solution.

A household water softener operates on the same principle.

A solution is passed through a

resin bed containing anion resin, cation resin or a mixture of both.

The atoms,and molecules having a negative ionic charge, i.e.

an anion, are attracted to the anion resins, and the positively charged atoms and molecules, i.e.

a cation, attach to the cation resins.

The chlorides,

borates, cesiums, and nearly all of the other fission and activated corrosion products in the liquid waste streams are removed in varying degrees by this process.

The efficiency of a resin for removing a contami is referred to as 'the decontamination factor of the resin.

The decontamination factor is defined as the ratio of the conce~

trations of a radionuclide in the solution entering the system 17 '

i e

I I

Ql SP RING HINGED LID SWING BOLTS INLET TYPICAL WOUND FILTER ELeMENT (FLOW FROM OUT-SIDE TO INSIDE) r~t P1 rr

~ 8

~t P ~

~ ~

f C)

I Q

f 0

0 I

I

~ ~

~I

~ P

~ ~

~ ~ e

~ ~

~r

~ o t ~

~ 0

~r b ~ 4

~ gt0 BASKET LIFTING RING REMOVABLE BASKET (CONTAINING.SEVFRAL FILTER ELEMENTS)

PRESSURE VESSEL GASKETS

'ESSEL SUPPORT

]Q OUTLET Figure it.. Typicat Disposabte Cartridge Fitter Taken from NU.'>79 lory

its concentration in the effluent.

The decontamination factors for a demineralizer used in a PWH nuclear plant is shown in Table 2.

The majority of the LLRW generated by demineralizers is in the form of ion exchange resin A cross-sectional veiw of a t:ypical demineralizer is shown in Pigure 6.

The function of an evaporator is Co produce a condensed

vapor, as free of 'the original contaminants as possible, by boiling off the liquid radioactive waste solution.

Xn simple terms the unit is a still, producing distil'led water and a concent:rat;ed slurry.

The contaminants in the slurry may then be disposed of as L'FI.

Evaporators are used in PNR plants to concentrate Ch boron in Che boron recovery 'system and to remove radioact;ive contaminants from miscellaneous waste solutions, whic because of their chemical properties, may not be processed using demineralizers.

Evaporators provide.the best; overall decontamina factors of any single piece of process equipment used for, the removal of radioactive and nonradioactive contaminants 'from liqui process st;reams.

Table 3 lists the accept'ed decont'amination I

factor-for evaporators in P>lR Plants.

There are.many types of evaporators used in nuclear power plants.

The evaporator shown in Pigure 7 is similar to the one used at the Crystal River plant Co process miscellaneous wastes; an evaporator similar to the one in Figure 8 is used to process borated water at the St. Lucie plant; and t'e Turkey Point; plants use both types of evaporators for liquid waste processing.

Table '2 Demineralizer Decontamination Factors for Pl)Hs emin ape Anion Cs Hb Other Mixed bed (Li3B03)

Mixed bed (H

OH

)

10 10 10 lp2(lp)(1) 10 Condensate Badwaste Boron recycle system feed.

(H3BO3)

Steam gener'ator 10 (10) 2 bio@down 2

2(lo) 2 lo(lo) 10 lo (lo) 10 lo (lo)

Cation bed Anion bed l(1) lo (lo) lo(lo) i(i)

.10(10) 1(1)

Note:

Decontamination factors in parentheses are for evaporator polishing and second Qemineralizer in-series..

Taken from NUS79 Table 3

Evaporator Decontamination Factors Application Miscellaneous rad>>~aste Boric acid recovery Laundry wastes All nuclides except iodine 104 10 lp2 Iodine

'L

. 103 lo 10 Taken from NUS79 20.

IHLET D ISTRI8UTION PLATE

RESIN, r /i PRESSURE

=

VESSEL 1

1 h g k

VESSEL SUPPORT SPEIJT RESIIlJ OUTLET OUTLET I

I VJATER PICKUP DISTR I BUT IOI'J HEADER 0

Taken from NUS79 Figure 5.

Yypicaf Deep Bed Oemineralizer 21.

0 FLASH C U TA'+4( y IE~

CH AMB E R OF U-TUBE HEAT FXCHANGER

(/p VAPOR

~

~I ENTRAINMENT SEPARATOR APPROXIMATE LIQUID LEVEL (ABOVE HEAT EXCHANGER)

STEAM (CON D ENS ING INSIDE TUBES)

THICK LIQUOR~

EVENT CIRCULATION I

PUMP DRIPS Figure 6.

Submerged u-Tube Evaporator Taken from NUS79

~

~

CUT~Vg Y Vt <<VJ OV SHELL-AND-TUBE HEAT'XG,HANGER

~j VAPOR

( =-i~i=~i

)1 ~

I I

~j DKlgt STER ll t,'-.,'~= FLASH CHAMSKR I:)~tMPIHGEMKHT BAFFLE LlQUOR BOlLtt)G lgS)DZ VUBLS V~AT-~-

!,I S TZAM

-~I

{ COHDEHSl 8 e OUTSlDE TUBFS)

J~

DRlPS l~

C3 C3

~

~

Ill

-!-,C~>'J Ll+s S

"J"l i i /))/

I 4 PP ROX l @AT E LlQUlo LEVEL Fiquoa FzED Figure 7.

Long Vertical-Tube Evaporator arith External Heater I

and.Natural Circulation

~

'" i Taken from NUS79

VOLUYiE REDUCTION IN LIQUID TLRH PROCESSING There are two basic approaches to reducing the volume generated by a nuclear plant's liquid LLRM processing systems.

4 The first approach involves reducing the volume of liquid which must be processed.

By reducing inputs to the processing

systems, the volu'c of evaporator concentrates is decreased and the effective lifetime of filters and demineralizer resins is increased>

decreasing the LLRM volume generated by the systems.

However, many of the liquid LLRM proces'sing systems are related directly to plant operation and the input volumes to the.systems are not easily re"uced.

The second m thod of reducing the 'volume of liquid processing LLRh involves reducing the volume of the filters, demineralizer

resins, and evaporator concentrates after processing has taken place.

This approach uses advanced volume reduction systems to incinerate the liouid processing s;astes.

The section on advanced volume reduction systems discusses the types of systems currently-r.

available for this purpose.

FPAL and PPC -are currently conducting deta'iled studies of their nuclear plants'LRM manage'ment systems.

A portion of these studies is devoted-to examining the various input volumes-to the liquid LLR</ processing systems and the feasibility of employing volume reduction systems to reduce their LLRIJ volumes.

PACKAGING OF LLBN FROM LIQllID HASTE PROCESSING The filters, resins, and evaporator concentrates from liquid waste processing must be properly packaged prior to shipment for burial.

The.primary objective of the packaging process is to convert the LLRN into a stable, monolithic form to minimize the possibility of any radionuclides being released to the environment during interim storage, transportation, and burial.

To obtain a stable, monolithic form the processing wastes are combined wit?. a solidification agent.

The most common agents used by'uclear.

power p'lants in the United States are cement and ureaformaldehyde (UF).

Solidification agents such as these im;obilize any free tanding liquids in 0he processing wastes; but they also contribute to the LLRN burial.

The volume increase for ranges from 1. 2 to 2. 0 times the the type of waste, i. e. resin or volume which is shipped for solidification with cement (NvS~M original volume, depending upon evaporator concentrate, which is solidified.

In the case of UF, t'e. volume increas'e from solidification is. about a factor of 1.9. greater for all,types of (Qv~

't i) was tes.

FPC '

Crystal River nuclear plant currently uses UF"to solidify liquid processing wastes; however, in the near future a

switch to cement for solidification is anticipated.

Some nuclear power plants in the United State',

including those of FPRL, do not solidify their. processing

wastes, but ship the wastes in a dewatered form.

In dewatering wastes, the

. freestanding liquid is removed by either centrifuging or decantin The dewatering process has the advantage of not.contributing to the original volume of the processing wa"tes.

The disadvantage o

dewatering is that it is nearly impossible to remove 100 percent

of the freestanding liquid.

Because of this, dewatering may become an unacceptable practice in the near future.

The Nuclear I

Regulatory Commission (NRC) has ruled that, as of January l,.

1981, the volume of freestanding liquid in a shipping container can be no more than one-half of one percent of the volume of the container; and by July 1, 1981, no amoUnt of freestanding liquid will be acceptable.

As an alternative solution, the NRC has given specifications for a high integrity shipping liner which could be used for shipping dewatered processing wastes which have small amounts of freestanding liquid.

These liners should be available for use in the near future.

The containers used to ship liquid processing wastes are normally 55-gallon steel drums or steel liners of various..volumes sized to fit a particular shield cask.

The volume of these liners can vary from 50 to about 200 cubic feet.

Xn some

cases, l

the steel liners are, loaded and transported inside a reuseable, shield cask, such as the one shown in Figure 9.

The shield cask reduceS the radiation exposure levels to which the driver of the

'transport vehicle and the general public are exposed to 'during transport to the burial site.

At the burial site, the liners may be removed from the. shield cask and buried.

Some nuclear facilities also use large liners around which a disposable concrete shield has been cast.

With this type of container,'he liner and the'shield cask are buried as one, unit and thus the shield contributes to the LLEW volume.

26.

WT. = 36,000 LB

<GYES 44V.+

SECONDARY LIO 83 Yi 38 OIA.

PRIMARYLID 0

7S 80>/>

~e 74 DIA.~i l

73 SHIELD Y

I t

la

>l r

= r A SHIELDING THIC'>>>.NESS (LE STEEL L3-18'I Transport Cask Taken from -NUS.79 27

~

LIQUID PROCESS XNCi LLR!J VO] UNI'.S Xn e'ach of the previous discussion" on liquid LLR':,'rocessin~

systems, volume estimates were given for a '1000 hoyle PVR nuclear power plant.

The values given were obtained by combining data given in:

final safety analysis report" for a typical 1000 ICHe PNR plant; the proposed standard by American Nuclear Societ" Committ e N55.1, draft 1 of ANSX-N198, "Solid Radioactive lfaste Process'ng System for Light Mater Reactors";

American 'Nuclear Society Commit tee I>55. 2, ANSI-N199, "Radioactive llaste Processing System for Press':.-.ized.Hater Reacto and from 'two NUS Corporati (lQoS (Bc-)

sur:eys of op =ating nuclear power plants.

The estimated LLR'H volume from a'1 the liquid processing systems for a 1000 N&le P4R (tuu" "LS< }

pl nt ranges from 10,100 to 10,900 cubic feet per year.

However,

.these values are for unpackaged LLR11. If a factor of 1.5.is applied to the values to account for packaging effects, the valu become 15,100 to 16,400 cubic feet. of LLR)/ per year.

'I

, The values listed in Table,3 are the.LLRN volumes from 1iqu waste processing report;ed by St.

Lucie Unit 1 and Crystal River Unit

3. in their "Effluent and Haste.Disposal Semiannual Reports The'se values. are displayed graphically in Figure 10

~

The LLRL volume re o

kev Point Un'id not distinguish between li uid

. ocessing LL1'H and other types o

Because of this all the data concerning the Turkey Point plants will be present;ed in the discussion on each plant's total volume history and volume projections, Crystal River '

liquid processing LLRM volumes decreased from 9888 cubic feet shipped during the second half of 1977 to 780l) cubic feet during the last half of 1978, a level which is

. 28.

Table Liquid Processing LLR(7 Volumes St. Lucie Unit 1

Reporting Period Volume(cubic feet)

%%u of Plant's Total LLRN Voli 7/1/76 to 12/31/76 1/1/77 to 6/30/77 7/1/77 to 12/31/77 1/1/78 to 6/30/78 7/1/78 to 12/31/78 1/1/79 to 6/30/79 7/1/79 to 12/31/79 1/1/80 to 6/30/80 860 689 820 3482 777 293 170 285 15/

6%%u Total to Date

733t, Crystal Rive" Unit 3

Reporting p riod Volume(cu"ic feet) g of Plant 's Total LLRN Vol 7/1/77 to 12/31/77 1/1/78 to 6/30/78 7/1/78 to 12/31/78 1/1/79 to 6/30/79 7/1/79 to 12/31/79 1/1/80 to 6/30/80 9888 9500 7800 12,784 13, 3" 9 7981 95.%%u 85'85 62%%u Total to Date 61,306 29.

3 ~,000 CRYSTAL RIVER UNIT 3 o

. ST. LUCIE UNIT 1 32,000 0~ 8000

~ 6000 U

$ 4ooo O

<Typical 1000 Kfe PNR NOTE:

1980 values are two times She Jan.

to July values.

2000 l 977 3980 i vie Processinp LLRW Volumes

considered average for a 1000 I"'e PtrR plant.

However, in the early part of 1978, the Crystal River plant 'developed control rod problems which resulted in steam generator primary to seconda leakage.

This increased the liquid processinp; LLRtl volumes for 1979 to over 26,000 cubic feet for the year.

The LLR'i~ vo'ume for the first six months of 1980 show a decrease to the level seen prior to the control rod incident.

As far a" future liquid processing LLRN volumes from Crystal River, it is doubtful that.there. will be any significant, long-term increase 4

in volumes as een in 1979; however, it remains to be seen vrhethe or not the decreasing

'trend shown during the first 18 months of plant operation 11 resume.

For the purposes of this report,-

future LLRvl volume projections vrill be ba ed upon 8000 cubic feet semiannually or 16,000 cubic feet per year of liquid processing LLRll from Crystal Riv r Unit 3.

The liquid processing LLR:r volumes shipped from St. Lucie Unit 1 are drastically, lower than both Crystal River's volumes and volume estimates. given'or a 1000 HÃe PMH'plant.

St. Lucie's liouid processing LLR':J volumes have been cons'istantly under 1000 cubic feet semiannually and recently gone below 500 cubic feet.

The only exception to this i;as during the first half of 1978 when the volume increased to 3>I82 cubic, feet.

It is beyond the scope of this study to perform a detailed comparison of the St. Lucie plant's liquid LLRif processing sy"tems to other nuclear plants';

however, the nuclear industry in the United States could not f'in better plant to study and learn from regarding of liquid LLR<1 processing.

Volume projections for St. Lucie Unit 1 and, after

,1983, from St. Lucie Unit 2 will be based upon 1000 cubic feet ll of liquid proce.,sing LLBN semiannually or 2000 cubic feet per ye 31'.

SOLID LLRlJ SOURCES The solid. LLRii generated in a nuclear power plant ca e

~i divided into three basic categories:

'ventilation filters, fail or used equipme and trash.

Approximately 50 percent of a plant's total LLRN'olume consists of these types of materials.

The venti"ation filters are used to remove radioactive particuiates and airborne contaminants (primarily iodine radioisotopes) from the plant's ven'tilation systems before rele

. of Cne air to the environment.

The filters.are composed of a cellulose or charcoal filter bed in a wooden or metal frame.

Because of the'r construction, the. filters are not readily sub'o volume reduction techniques such as compaction or incinerat iJentilation, filters account f'r approximately 500 cubic feet o

{gUSQB )

LLR':.'.per year f'r a 1000 J%Je PHR plant.

The failed and used equipment contributing to the LLRN vol'ume is composed of a wide variety of materials and sizes.

A cross-section of this material might include items such as'valves, valve parts,'piping, pump component,s,

motors, hand too air lines, water hoses,

ladders, scaffolding, and wood.

These materials originate from or are used during maintenance-in the W

plant's.contaminated areas 'or on contaminated systems.

The materials are normally not compactable or combustable.

Failed and used equipment accounts for an estimated 800 cubic feet of (HUS 18a)

LLH)J annually= in a 1000 Nile PLJR plant.

Contaminated trash makes up the bulk of the solid LLR(J generated in a nuclear power plant.

Xt is, estimated tha a

m that aim 90 percent of a plant's solid LLRYJ volume is composed of

'ontaminated trash.

Some typical m'aterials and their uses wh 32 '

~ polyethylene sheeting

~ polyethylene bags to cover areas, equipment, and construct tents for contamination r

control; r

to contain contaminated

waste, tools, and equipment for contamina control;

~ disposable protective clothing for personnel protection against contamination;

-worn-out reusable protective clothing

~ respirator filter for personnel protection against contamination; cartridges for personnel respiratory

-wiping rags and mops h

protection; for area and equipment decon-tamination.

All of these materials are directly related to the protection'of plant personnel from the radioactive contamination present in the workplace.

)lhether the materials are used directly by personnel, such as protective clothing and respiratory equipment.,

or benefit personnel indirectly, as with materials used for contamination. control of areas and equipment, the materials provide the only barrier between the plant personnel and the contamination hazards inherent to a nuclear power plant.

The majority of the contaminated trash volume is both compactable and combustable.

Contaminated trash accounts for an estimated 33,

(N>>'~ l4cs.)

10,700 cubic feet of LLRtl per year in a 1000 YAIe PMR plant.

VOLUME REDUCTION OF SOLID LLRM The predominant method used by nuclear power.plants in the United States to reduce solid LLRtl volumes is compaction.

It is est'mated Chat 66 Co 80 percent of Che solid LLRM generated f8~'t) in a nuclear plant is compactable.

All of the nuclear plants in Florida use compactor" to reduce the volume of solid LLR(l prior to shipment for bu. ial.

The type of'ompactor in use at St.

Luci>>

Unit 1 or Crystal River Unit 3 is a 55-gallon drum compactor similar to the one'hown in Figure 11.

A drum compactor such as this will give a uncompacted to compacted volume ratio of (gus~)

about 2.5 to l.

The Turkey Point nuclear plants use a box compactor for.volume reduction of solid LLRM.

A box compactor compresses material into a 110 cubic foot plywood or metal box with a force of more than 82,000 pounds.

The compaction ratio for this type of compactor i" about 4.5 to 1.

Turkey Point's box compactor was installed in June,

1980, so volume reduction from it will not be noticible until 1981.

At the time of P

installation, FPSL conducted a test of the compactor in which material which had been compacted with a drum compactor.was recompacted in the box compactor.

The box compactor. achieved an additional 37 percent decrease in the volume of the material.

Compaction of. olid LLRtI into boxes instead of drums also provid more efficient use o'f storage space.

Storage of drum" wastes percent of the total storage space volume (e.g.

12 cubic feet o

storage space is needed to store a drum having a volume. of 7.3

wg4

. ~ ~ ~

t

~

p>~U~

QQ.

DRY RADLVASTC DRUh1 COMPACTOR 35 '

cubic feet).

FPRL will also be installing a box compactor at the St.

Lucie plant in the near future.

Most of the solid LLRM generated in a nuclear plant is generated by plant personnel during the performance of their work.

Because of this, it, is important that the plant personnel have an understanding of the problems facing nuclear power plants in regard to LLR>l and know how to keep the amount of LLRN generated to minimum.

FPEL and FPC both provide some amount of LLRN'training to personnel.

The training. given to FPC employees stresses e

keeping all unnecessary materials out of contaminated and pro"essed as LLRl).

includes:

FPFL burial allocations at Barnwell; regulations on LLE handling, transport and disposal; discussion on keeping radiation control areas

.where it might become contaminated and be FPGL's general employee training on LLRll unnecessary mat,erials out of areas where it could be processed as 'RH; nuclear housekeeping practices; and proper decontaminatio techniques.

It is not possible to measure the amount'f volume reduction achieved through programs such as these; however, the training does increase employee awareness of the LLEJ problems which benefi+s the utility.

There are some work practices followed by the FP8L and FPC nuclear power plants which also help reduce solid LLRN volumes.

The practice of keeping all unnecessary materials out of areas where it might end up as solid LLRM i;as previously mentioned.

An example of this practice would be uncrating equipment outside

'f the plant's radiation control area to keep the containers and packing materials from eventually being processed as solid LLRM.

Another plant practice which helps reduce LLRN volumes is good housekeeping.

If areas are contaminated, they require protective 3'

4l

clothing for access which adds to the LLR11 volume.

N Nuclear plants are also discontinuing the use of disposable protective clothing wherever ossible and are substituting

.h.

V reuseable protective clothing.

y 4

'4 The possible use of incinerators o reduce solid LLRN volumes.'s also being studied by FPRL and 'FPC as a part of their LLFi'anagement studies.

The section on volume reduction systems discusses"one type of incinerator available.

I 37

~

SOLID LLRll. VOLUYES The average volume of solid LLRN generated in PNR plants is (r~vsi~i) about 8800 cubic feet per year.

This figure includes both compactable and noncompactable LLE?.

The values li ted in Table are the solid LLRN, volumes reported by St. Lucie Unit 1 and Crystal River Unit, 3 in their "Effluent and Naste Disposal Semiannual Report.s".

These values are displayed graphically in Figure 12.

The Turkey Point LLR'? volume reports did not distinguish solid LLRN volumes from liquid processing volumes.

All the data concerning the Turkey Point plants will be presented in the discussion on the plants'o al LLRN volume history and volume projections.

The solid LLRi? volumes shipp d from St. Lucie Unit, 1 have been slowly increasing since initial startup.

The only large increase in volume ':as during the second half of 1977 when over 8000 cubic fee'f solid LLRN'as shipped for burial.

That large increase was due to i",.odifications on the plant's.spent fuel racks The old rack" shipped for burial accounted for 5763 cubic feet.

Had the modifications not been necessary',

the solid LLRN volume would have been about 2400.cubic feet for that period (shown by broken line on Figure 12).

One factor which affects the volume of solid LLRN generated by a nuclear plant is outage or shutdown time.

Nhen a plant is shutdown, the amount of maintenance performed increases dramatically, increasing the solid LLRN volume.

St. Lucie Unit 1 was shutdown for refueling and maintenance activities for a. period of 6 to 8 weeks during the first half of 1978,

1979, and 1980.

During each of these 38.

Table 5

Solid LLB';1 Volumes St. Lucie Unit 1

Reporting Period 7/1/76 to 12/31/76 1/1/77 'to 6/30/77 7/1/77 to 12/31/77 1/1/78 to 6/30/78 7/1/78 to 12/31/78 1/1/79 to 6/30/79 7/1/79;to 12/31/79 1/'1//80 to 6/30/80 Volume(cubic feet) 2190 3709 8141 4909 3461 5686 4661 6215 g of Plant >s Total LLE/ Volume 72%

Sog 91$

595

'25

'5$

95$

97$

.Total to Date 38,972 Crystal River Unit 3

Reporting Period Volume(cubic feet) g of Plant 's, Total LLEW Volu 530 1640 7/1/78 to 12/31/78 1/1/79 to '6/30/79 7/1/79 to

~ 12/31/79 1/1/80 to 6/30/80 Total 5191 9394 8087 7204 to Date. 32 020 7/1/77 to 12/31/77'/1/78 to 6/30/78

. '15%

39$

38$,

39

~

9 l 0,000 B CRYSTAI RIVER UNIT 3 o ST. 1UCIE UNIT 3 cc 8000 0 6000

~ 4000

~~ 2000 Typical

<1000.YWe.

PWR

///

///

0 NOTE.

l980 values are two times the Jan.

to July values.

1977

'1 978

! 980 Picture ll.

Solid LLRif Volumes

periods there were increases in the solid LLRU volumes shipped for burial.

FPEL estimates that LLRH volumes increase as much as 32 percent per month during shutdown periods.

Xt follows that if a plant can decrease the amount of shutdown time the volume of solid LLR>l will also decrease.

Xn the near future, the St.

Luc:

plant will 5e converting an 18 month fuel cycle instead. of their present 12 month cycle.

That means a refueling shutdown will only be required about every 18 months.

FPRL estimates a 10 percent reduction in St. Lucie's LLRh~ volumes because of the decrease in shutdown<< time resulting from the extended'uel cycle.

~

a<<

The installation of a box compact<<or will also help reduce solid LLRlJ volumes at the St.

Lucie plant;;

As much as a

37 percent decrea e in the volume of compactable LLRN will be achieved by use of the box compactor.

r If the period from.Tuly 1978 to July 1980 is used as a

baseline for projections, the volume of solid LLRll generated by the St. Lucie plant will be about 5000 cubic feet semi. annually or 10,000 cubic feet per year.

The volume reduction effects of a box compactor and the extended, fuel cycle could reduce that volume to as low as 2800 cubic feet semiannually or 5600 cubic feet of solid LLRN per year'.

Similar volumes should also be generated by St. Lucie Unit 2 after s'tartup in 1983.

The solid LLR<l volumes reported by Crystal River Unit 3 do not display the consistency seen in the values reported by St. Lucie.

The reason for this is the amount of time Crystal Riv has been shut'-down for repairs and refueling.

During, the 36 month period cover'ed by Figure 12, the Crystal River plant was shutdown about 40 percent of the time.

That has had a major impact on Crystal River'" solid LLBl< volumes.

During the last 12

months the volume of solid LLR';I being shipped has been steadily decreasing.

Except for minor fluctuations, the decreasing trend should continue to a level similar to St.

Lucie 's current generation rate of 10,000 to 12,000 cubic feet per year.

F 02.

VOLUME REDUCTION SYSTEMS In the previous discussions on volum reduction of liquid processing and solid LLW, it; was mentioned that FP5L and FPC are investigating the possibility of using volum reduction systems in the future.

'Ihere are several volume reduction processes current;ly available for use in nuclear power.plants.

'lhe volume reduction systems currently in use are:

incinerators, fluidized-bed dryers, bitunm systerrs, evaporative crystallizers, and high-pressure compactors.

Incinerators Incinerators ar 'used to reduce t'e volume of combustible. solids.

'Ihere are several fuel-fabrication facilities and laboratories iri the United State" which have used incinerators to process LL%l for several years.

Incinerator~ are also used in nay o0her countries for LLH< applications.

A exam,""e of an incinerator used. in a cormercial nuclear power plant is the Tree~-'i incinerator which is op.rated=by Ontario Hydro of Canada.

'The Trecan incinerator is a 'st'arved air'at'ch-type which u es two combustion cha.-he...

Figure 12 is a simple diagean; of the Trecan model.

The combustible L' enters the prinary chanher and is pyrolpsed at temp-eratures uo to 1100 degrees Fahrenheit.

".he offgases from the priory up chamber enter the afterburner chanber.where they are burned at temperatures up to l800 degrees.

%he flue.gases are processed through a heat exchanger for'ooling and then a baghouse filter unit.

Ihe Ontario kgdro incinerator can process batch loads of LLRd up to 700 cubic feet;.

'Ihe burn cycle for each load ranges from o

fro 30 to 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.

The volume reduction'(including packaging effects)" achieved by this incinerator zs ab u o t 25 to 1 although 4

l

. some manufactures claim to obtain as hzgh as some u

a 40 to 1 volum. reduction F

ratio.

In 1978, the Ontario Hydro operat;ion processed over 5,

over 65 000 cubic feet 43.

N I

I l

I

+

~

I

~ ~

I I

~

S

~

g

~

Tnat involved an average of two burn cycles per week.

The total activity released out of the stacl< for 1978 was 2.8 millicuries of iodine-131 (oil l I) and 2.1 millicuries of particulate radionuclides.

Xt should be noted however that &tario Hydro limi.ts the radiation dose rate. of the materials to be incinerated to 5 millirem per hour.

During 1978, the incinerator required. 10,311 manhoure of mechanical maint nance; 4050 manhours of control neintenance; 7500 manhours of technical suoport; and 750 manhours of supervisory support.

The incinerator was shutdown for maintenance about 39 percent of the tim.

Tne total cost for 1978 to operate the incineration facility and a con@actor was

$2,335,000 (Canadian dollars).

The incinegator started operation in 1977.

During the first two years there were unexpected problems and a si~ficant amount of testin= involved with the operation.

Ontario Hyoro expects tho perforpance of th Trecan unit to Mprove greatly (wl'l'0 I

in future years, i-ressure Co~actors Another volum.reduction system used for processing solid LL%1'is the high-pressure co~actor.

This con@actor will provide a volume reduction (g go~'s ~)

ratio of about 0,to l.

I'i>st compactor used in nuclear power plants today have about 2 to 1 ratios.

The box compactors which FPM, is installing at their plants are high-pressure comoactors.

Evaporative Crystallizers Evaporative crystallizers are basically a very efficient evaporator.-

They will concentrate boric acid solutions Up to about 50 percent solids by weight, where as a typical nuclear 'power plant evaporator achieves only, about 12.5 percent sol'ids by weight., After solidification and paclmging of the LZBr1, an evaporative crystallizer will reduce the volum of evaporator (gvsafa,)

concentrates vjith a ratio of about 0 to 1.

Fluidized-bed Dryers(Calciner~)

A fludiized-bed consists of inert particles which are continuously

agitated by a stream of hot air in a vertical chanber.

'lppically, concentrated liquid solutions, such as evaporator slurries, are sprayed onto the bed, where the liquids are evaporated, leaving the solid particles to be 1idifi d and d

~e~

After packaging, calcination of evaporator

(,Nv 184) slurries can give a voluve reduction ratio of about 5 to 1.

Fluidized-bed techniques can also'e used to incinerate coabustible solids as well as evaporate liouids.

Cur ently, two conbined calcination/

incineration systems are being marketed in the United States.

A flow diagram of the No,gert ll is Industrial Corp. WR-1 system is shown in Figure 13.

'ibis system cap process derdneralizer resins, evaporator slurries, and combustible solids.

All processed materials are reduced to an anhydrous granular solid.

After the mterials a~=" processed at temp ratures from 750 to 1800 degrees

~ O Fahrenheit, the solid residue is rerroved by a dry cyclone, then solidified and pack ged. i¹ offgmes iram the system are processed through a venturi scrubber cond nser, do~~ster, iodine filter, and several particulate filters before bein= vented. 'I¹ calciner/incinerator systems achieve a volu,.

reductio.. ratio, after packapP~g, of about 5 to 1 for evaporator (zu~~b4) slurries and abo t 40 to 1 for conhustible solids.

Bitunmn Systems Volume reduction with bitumen systems is accomplished by introducing concentrated 1iquid solutions into hot aaltem bitumen.

Jhe heat from the bitumen drives off the excess water and the solids are retained in the bitmen.

'Ihe bitum n mixtur'e is then extruded into containers for shipment.

Bitumen systems originated in Fu".ope and have been used there for several years.

% yet, there are no bitumn systems in use at comnercial nuclear power plants in the United States.

Figure 14 shows the basic arrangement of a Merner

& Pfleiderer Corp. bitunen system.

Bitum n systems have the advantage of providing volume reduction and solidification of LLR'1 46.

ff' I

'R I

I I I I

I

~

I I I

I 8

I I

I I

S I 'I I

I I

I I RSI

LIOUID OITUMEN ANTIFOAMING AGENTS EMULSIONORAKES WETTING AGENT I

I I

,itM CLEAItlt<G SOLvENT

~g

~ g

~ RADIOACTIVEWASTES FROM PRETREATMENT AND P RECONCENTRATION pnocEssEs HOLDTANKFOR RADIOACTIYESLURnIES HEATED TNN PUMP

. IIC VPLVE PUMP MOTOR DIIIVE J

HEATED FEED LINE l,I

'1 STEAM DOMES o

o CONTAINEns TwlN scnEw on FOUR SCREW hIIXER CONCENTRATOR CONDENSATE DRAIN WATERCONDENSERS

'IF PLASTIC hIATflIXhIATERIAI.IS USED INSTEADOF OITUh'IEN, TMEARRANGEMENTIS ONLYSLIGHTLYDIFFERENT.

TURNTAOLE Fl ure 14 ~

General Arran WP(

F ruder Fva orator

t ll all in one step.

A bitumen system will give a volume rc uc zoll (NCSlQ b) ratio of about 5 to 1 for LLR>1 such as evaporator slurries.

Xn Table 6 the effect that these volume reduction systems.

can have upon the anneal LLRN volumes of a 1000 1%le PMR is illustrated.

Although a high degree of volume reduction is achieved'by these

systems, they.are not without problems.

Installation of.a syst m such as an incinerator requires engineering design reviews, existing system

changes, and possibly construction of a structure to contain the system.

Along with this there are NRC and other agencies which must review the proposed system and p'ant modifications.

The systems are expensive to purchase and operate; dep nding upon the volume of'LP<

to be processed, it may not be economically feasible for a utility to in tall a volume reduction system without tax incentives or.electrical rate increases.

Even if all the. problem are resolved and the sy tern installed, the increased specifxc activity of ~he LLB~i can produce radiation shielding problems for the plant sta"f and personnel at the burial grounds, and could possible increase the alpha radionuclide specific activity a level which would not be acceptable at some burial grounds.

All in all, there are many things, which m"st be considered b<<or-installing a volume reduction system.

49.

Table 6

Effect of Volume R duction Systenr on a 1000 NJe FMB's Annual LLPv1 Volume.

Shipped Haste Quantity(PackaP,'ed)

P'ant Descr'ption Genera".ed.,

01aste

'u..rent quantity Practice

{Unpackaged)

(a)

Hipg Ev:-~poratox Press' Calciner Incinerator/

Crystalliz r Corpactor.~ Pitumeq with Incinerator Calciner w/ Cerocnt

{b)

Sy-tern Cement with cern nt with cement Pl1R with D.ep Bed csin CPS System Volune: ft 22,080 Packaging Factor 1.00 31,650 20,120 1.43 91 23,250 17,670 18,610 21,010 1.05

.80

.84

.95-4250

.19 F:1R without'PS 22,920

. Volume ft3 Packaging Factor 1.00 32,880 21,350

,86

..80 24,480 18,510 19,840

.21,960 1.06 95 4440

.l9 (a) Under current practice, the waste is packaged without volume reduction processing.

(b) A packaging factor of 0.25 has been used for packaging of dry bulk solid ~astes with high pressure conpacto CPS = Condensate polishing system.

Taken from NUS78b

QUITE LLR:) SK)RAGE Each of, Che, nuclear power lants in Florida has storage space set aside, for short term storage of LLRN.

The 'storage "pace is used primarily. to hold'LLRN until such time when it can be shipped. for burial.

In the event of a, shutdown of one or more e amount of onsite torage space available as the plants would be critical.

Recognizing this potential problem, FPC and FPEL are conducting studies to determine how much onsite storage space is needed to overcome any short term shutdowns of burial sites.

The onsite storage available at FPC's Crystal River Unit 3 is approximately'00 cubic feet for LLRH f'r. items such as demineralizer resins and filters.

These areas require shieldh.ng.

For LLRN such as compacted trash,,there is about 8000 cubic feet of space available.

This amount of storage space at Che very

best, would only hold about 4 months worth of Crystal River's LLRN.

FPGL's Turkey Point plants have about 10,000 square feet of floor space available for LLRN items that require shielding, thus r

a maximum of 100,000 cubic feeS of storage for demineralizer P

'I

resins, evaporator concentrates, and filters.

Xn contrast to the. Crystal River plant, Turkey Point plants store their compacted LLRN outdoors.

In the event of a burial ground shutdown, Turkey Point's major concern would be providing a storage, building for the compacted trash to prevent any deterioration of the 0

containers due to weathering.

II FPEL's St. Lucie plant'as about 250 square feet of floor space available for that LLRN requiring shielding and about 800 more feet of floor space for-compacted Crash.

These area~

would 51.

provide a maximum of 2500 cubic feet of storage for filters demineralizer resins, and evaporator concentrates, and 8000 cubic feet for storage of compacted, trash.

Under ideal conditions, this would hold about 10 months worth of St. Lucie's LLBN.

52.

LLRll YiAHAGENENT AND QUALITY'OHTROL The number of regulations and guidelines governing the packaging and shipping of LLRll is staggering.

The NRE, the Department of Transport;ation (DOT), and t;he invididual burial grounds all have specific requirements to be. followed for ship LLRll.

Attachment; 2 is a flowchart on shipping LLRll from a nuclear power plant.

The complexity of shipping LLRM compels utilities to have a

LLRV management staff cognizant of all current and p.oposed regulations.

As an additional check against inadvertent violations of packaging and shipping regulations, nuclear poi er plants should have a.LLRN quality

'control program.

Both FPRL and PC.have fulltime LLRN manageme staffs and quality control programs at; their nuclear power plan E

FPc L has one ind'vidual on'the corporat'e staff and one at each of the nuc" ear plants whose primary responsibility is LLRM management.

The LLR"i management staff is assisted=by other department managers who also have LLRl< responsibilities.

'The LL quality cnnt ol program ate FPEL plants covers certification of shipping cont'ainers, inspection of t;ransport vehicles, and.

inspection of waste packaging and loading operations, FPC's LLRll management staff includes

'seven individuals at

,the Crystal River site and one person on the corporate staff.

The LLRll quality control program at the Crystal River plant cove wastewater movements,,

i~ater chemistry, radiochemistry analysis, and cert;ification of LLRH shipping containers.

53.

LLRH VOLUME HISTORIES AND PROJECTIONS The volume of LLRN shipped by the nuclear power plants in Florida f'r each operating year is listed in -Table 7.

To date, the plants in Florida have shippe'd over 391,000 cubic feet of LLRN for burial.

For perspective, this is about the size of a residential lot 200 feet x 100 feet. stacked to a height of 20 feet.

Turkey Point Units 3 and 4 shipped 64 percent of that

volume, 12 percent from St. Lucie Unit 1, and 24 percent from Crystal River Unit 3.

The Turkey Point plants accout for a large percentage because of the longer operation time'(since 1973). and the larger electrical generation capacity (1455 IRe combined).

For this reason, it is more realistic to compare LLRi! volumes in terrors of cubic feet per. I'H!e.

Figure 16 sho>>s the cubic feet generated per 'Yi:!e for each of the nuclear plants in Florida.

Surveys of. operating PWR nuclear power plants in the United States show an average LLF! generation rate of 21.5 t, N'V(l't) cubic f'eet per iP!e. Since 1977; theour nuclear.power plants in Florida have averaged 25.5 cubic feet of LLRt! per NMe.'he LLRN volumes listed in Table 7 and volume progections.

f'r each plant are displayed graphically in Figure 17.

The LLRl! volume projectionsr Crystal River Unit 3 are based upon

,the generat'ion of liquid processing LLRN continuing at the current rate of about 16,000 cubic feet per year; and an anticipated decrease in solid LLRH generation to about 10,000 cubic feet per year.

The decrease.

in solid LLRN volumes should be brought about as the plant's shutdown time per year lessens.

4 Because of the Crystal River plant's short operating history and the problems

>which have caused a large amount of'hutdown time, 54.

~ 9.

Table 7

LLRW VOLUMES FROM NUCLEAR POWER PLANTS IN FLORIDA PLANTS MHe 1973 1974 a

1975 4

1976 a

1977 i 1978 w

1979 w

1980 0.

TOTAL Turkey Point 1456 8200 Units 364 100 15,900 100 31i400 100 50 p 125 94 37 t 710 6l 62g032 3 32'3 37 3,0 St. Lucie Unit 1 810 3062.6 13,576 22 12,636 13 10,884 13 6385 18 46,54( 3 Crystal Rive Unit 3 797 10,418 17 24,271 24 43,613 50 15,185 93,407 H

~

4 3063 8200 15,900 31,400 53,787 61,704 90,939 06g980 3 (,630 1Data for 1980 is for January to July only Taken from FpaL and FpC "Effluent and Waste-Disposal Semiannual Reports"

(

(

ic

0

Figure 15.'ubic.Feet of'LMR per Nle versus Year.

0 CRYSTAL RI.YER UNIT 3 A TURKEY POINT UN)TS 3 8 4 o ST. LUCRE UNIT I

/t 2Q 98 1

8 8

1 1

'"'8991 1

1 9

81 ~ 918.

8 56.

d d

II ~

'L Ol l

h. TURKEY POINT UNITS 3 8 4 G CRYSTAL RIVER UNIT 3 o -ST. LUCIE UNIT <

60,000 Steam Generat'or Replac cment' 40,000 20,000 0

p lq H--Q-W-~~-M St'. Lucre 2

p~~

///

1976 1980 l984 ure 16.

Nuclear Power Plants in Florida:

LLRÃ Histories and Volume Progections.

is very difficult to make accu a."

long term projections.

Disregarding any significant problems in the future for Crystal Ri 26,000 cubic feet per year should be a reasonable upper limit,'stimate for LLRÃ generation St. Lucie Unit 1 has consistantly generated from 10,000 to 14,,000 cubic feet of LLRIJ per year:

Projections for the St. Lucie plant are based, upon a continuation of the 2000 cubic feet or less of liquid processing LLRL1 per year, and a decrease

'in the current average solid LLRH generation rate of 10,000 cubic. feet per yea.

to about '000 cubic'eet per year by.1982.-

The anticipated decrease is due to the use of a box compactor and the 18 month fuel cycle.

The increase shown.for St. Lucie in Figure 17 for 1983 is due to the startup of St". Lucie Unit 2.

Unit 2 is of the same design as Unit 1 and should generate a

similar amount of LL%/.

The startup of St. Lucie Unit 2 could, be delayed somewhat;

but, by 1985, the St. Lucie plants should be generating about. 16, 000 cubic feet of LLRN per year.

The LLR'J volume history of Turkey Points Units 3 and 4

has been somewhat erratic reaching as high as 62,000 cubic feet in 1978.

The high volumes seen in 1976 and 1978 were due to

'"~ ~

extensive maintenance activities and were not used to establish a baseline for roj ections The LLRbl volumes from 1975,

1977, 1979, and the first half of 1980 yielded an average volume of about 32,000 cubic

-feet per year.

Proj ections were based upon this value; the effect of Turkey Point 's box compactor; and the steam generator replacement outage scheduled for October 1981 through June 1983.

Xn calculating the effect of a box compactor, it was assumed that 50 percent of Turkey Point 's LLRM volume was compactable.

FPEL estimates that an additional 37,0 cubic

~

~

~

aug

~ 0,5' 4M'eet of LLRW will be generated during the'team generator work.

Xf that volume is distributed proportionately over 1981, 1982,'nd 1983, it would increase Turkey Point's LLRW volume by 5000, 21,000 and 11,000 cubic feet, respectively.

In Figure,18 the data and 'projections of Figure 17 are combined to show the total volume of LLRW shipped from the nuc1car power pl@)its in Florid'a from previous years and the anticipated volumes throut h 1985.

100,000 9 80,000 60,000 a

LU

~~ 40,000

~~ Z0,000-I984 Figure 17.

Nuclear Power in Florida:

Total LLR)/ History and Volume Projections.

CONCLUSIONS Xt is a fact that nuclear power plants generate LLR>l.

To some extent Che volume of LLRil generated can be controlled; however, situations do arise in which the LLRtJ volumes increase as-a result'of maintaining the operation and safety, of Che plant.

The nuclear power plants in Florida have had in 0he

past, and will have in the future, times when LLRM volumes increase.

The reasons for the increases are relatively short term problems which do not result in increased levels through-out the operating history of the plants.

Overall, the LLRN volume.from Tlorida.'s nuclear power plants is decreasing.

By.

1985, the volume should be lower Chan in 1980, even with an additional power plant operating.

FPRL and FPC are interested in maintaining the LLRN volumes as low as possible.

This is shown by the existence. of their LLRl1 management staffs; the LLBU training programs; and the inplant LLRi< management studies being conducted by the utilities.

In planning for the future, each of the utilities is looking at the.feasib'ility of volume reduction systems.

The systems available can reduce LLRiI volumes to a fraction of the current levels.

Mhat these systems cannot do is reduce the amount of radioactive material contained in Chose volumes.

The questioned to be answered for the future is how much time and money should'be expended to place the same amount of radio-activity into a smaller space.

61.

REFEREE CES

@US 78a NUS78b r

NUS Corporation,

1978, "Low-Level Radioactive Haste Ilanagement," Volume I:

Current Power Reactor

. Low-Level Radwaste",

California Energy Commission Report CAEC-007.

1<US Corpox ation,

1978, "Low-Level Radioactive Haste Management, Volume III: Feasibility of Volume-Reduct:ion Pro esses",

California Energy Commission Report CAEC-007.

Is US79 HUS80 OH79 HUS Corpor ation,

1979, "A Naste Inventory Report for Reactor and

$'uel-':-'abrication Facilit;y tlastes",

United States Energy Research and Development Adm'nistration:

Office of >laste Isolation Report Ob",vlI-20.

HUS Corporation, 1980, '"Preliminary State by Sta e Assessment of Low-Level Radioactive Wastes Shipped to Commercial Burial Grounds".

Ontario Hydro, 1979, "Volume Reduction of Low-Level Radioactive Solid ':!aste in Ontario Hydro".

62.

ATTACHNENT l Questionaires and Responses on LLFill from Florida Power 5 Light Company and Florida Power Corporation 63.

LLRiJ PRO J ECT Nuclear Power Plant guestionaire Florida Power

& Light I.

Radioactive waste volumes

1. List the radioactive waste volumes generated, for each FP&L nuclear site, during each six month period of operation.

List the data for each of the following categories:

1; Spent resins, filters and evaporator bottoms 2.

Compactable and norcompactable trash(LSA) 3.

Irradiated components Note:

Copies of data from the plants'emiannual waste disposal reports may be, substituted.

2. Estimate the radioactive waste volumes (LSA and irradiated components) that will be generated during Turkey Point's steam generator replacement outage.

Include anticipated start/stop dates for the outage.

3. Llill the radioactive waste volumes generated from the St. Lucie Unit 2 pIant be 'similar to the past history of St. Lucie Unit 1?

When is the anticipated start up date for, Unit 2.

II.

Yolum reduction

1. Enclose any copies of FP&L policy statements issued regarding volume reduction of radioacti ve waste.

2. Briefly describe the training given to radiation workers

~ as to how they might reduce radioactive waste volumes.

3. List the. types of compactors and the compaction ratios (or lbs. of force} for the equipment in use at the FP&L plants.

4. Estimate the amount of volume reduction, if any, that is attributable to the,.l8 month fuel cycle.

5. Oescribe any future plans of FP&L which will lead to a

reduction'in the radioactive waste volumes being generated.

64.

III.

Niscel 1 aneous

1. Briefly describe the quality control steps in use during the processing and shipping of radioactive waste.

~

2. Estimate the amount of on-site storage available at each site for LSA and high-rad type materials.

Does FPEL have any plans for increasing the amount of storage available on-site?

.3.

How many individuals are. envolved in radioactive waste management at the corporate level and'the operational level?

65.

UNIVERSITY OF FLORIDA LLH PROJECT LL1< Yolume Copies of Turkey Point 3

E 4 and St. Lucie 1 Solid llaste Disposal.Peports are provided-This data is submitted to the NRC semiannually as part of an effluent and waste disposal report.

The period covered by this data'is January 1976 through June 30, 1980.

Sh-di,d*f tg1":,G,E~Ri LLllV The anticipated dates or the Turkey Point steam generator repair outages are as fol 1 o>>s:

Unit 4 Unit 3 Oct.

81 - June 82 Oct.

82 - June 83 He estimate the total additional LLW generated as a result of both unit steam generator repair outages (e.g.

18 months) will be as follows:

1 Dry com ressible

waste, contaminated equipment etc. - approximately 26,000 ft.

Spent resins, filter sludges, etc. - approximately 11,000 ft-I Th'e estimates include approximately 1620 ft.

of concrete p r unit which

<;ill be removed from the containuent internal walls and floors as. discuss d.

in FPL's Steam Generator Repair Report:,

Turkey Point 3 5 4 but is exclusive of the steam generator low r assembl.ies themselves.

St. Lucie, Unit 2 Starts lte antici pate waste volumes generated from operation of St. Lucie, Unit 2 to be similar to tho amounts which w will be generating at St. Lucie 1 at I

the time St-Lucie 2 becomes operational.'ur current anticipated startup date for St. Lucie, Unit 2 is early 1983.

Radiation Morker Trainina Personnel who will be working within a radiation controlled area,{RCA) receive extensive t, atning in health physics and radiological control practices.

At Turkey Point 3

t'c 4 new employees, contractor p rsonnel and visitors vnth duties in the ACA are'iven 5-24 hours of training.

Additionally, 8-10 hours of requalifi=ation training are. given at two year intervals.

Ai. St. Lucie initial training consists of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and requalification training consists of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

R portion of each worker's initial 5 requalification training is dedicated to radioactive waste management.

The training is designed to'heighten I

awareness and produce results with respect to overall better individual waste manageirient practices.

Nore sp cifically each worker is instructed and advised in the following areas:

67.

The Oarnwell, S.C.

volume allocation plan and what it means to Florida Power 8 Light Company.

Regulations and restrictions that govern the handling, transport and disposal of low level radioactive waste-The individual as a contributor to the generation of radioactive wastes.

His responsibilities for continuously striving to minimize the amount of 'loi( level radioactive piste that he or his co-v<orkers generate.

Plant administ, ative procedures and policies for materials control within the RCA which are designed to minimize LUf generation-The importance of good nuclear'housekeeping practices Proper decontamination techniques, and controls-In addition to the above formal training, frequent discussions of:radwaste management related, topics are held with all FPL workers during monthly safety meetings.

68.

(.

9 LL'II Volume Reducing Corn~actors Currently at Turkey Point 3 5 4 we are employing a

CGR box compact'or.

The CGR compactor packages both compressible and non conpressible LLH directly into a 110 ft-3 LSA box.

The unit develops more than 82,000 lbs-of downward force resulting in an overall compaction ratio of approximately

4. 5:1.

At. St. Lucie we ar'e planning to procure a

CGR compactor.

The unit I

currently in use is a,drum compactor rated at 25,000 lbs-of'orce.

Extended Fuel Cycle Ihe per month quantity of LLlf generated during normal plant operations is

\\

~

~

S

~ 'C anp o-irately 32/

o that. which is g nerated during an outage, thereiore; it can be calculated that the extended fuel cycle at St. Lucie can result in reductions of LLH by. approximately.10$.

.k~

E

(~

gal'

~

p Future Plans for Volume Reduction

FPL.has already taken'several positive steps towards achieving volume reduction in LLl%

At each nuclear 'plant, a radioactive waste coordinator J.

has-been assigned to directly,supervise the activities associated with radioactive waste management.

Plant 'and corporate i

i 9

Iaste mana ement reviews were conducted.

FPL promptly instituted administrative procedures, 69.

material controls, and training; all designed to heighten aMareness and achieve an end result of reducing LL!l generation.

A consultant was retained to study low.level solid waste operations and make sp cific recommendations regarding radioactive waste management practices.

Mith an eye towards the future, FPL asse.i,bled a

to initiate a study'oncerning th feasibilit of em 1 o in hi h technolo volume reduction equipment (e.g. incinerators).

The study is scheduled to be completed in approximately one. year-gual ity Control FPL has in force a'umber of equality Control checks associated with A

processing and shipping of radioactive wastes.

equality Control is achieved in process'ing and shipping of LLH by the direct participation of plant health physics p rsonnel in the packaging and

/

loading of radioactive waste's.

Haste containers are certified prior to use to insure they conform to applicable

DOT, tsRC, and burial site regulatory h

requirem nts-Transportation vehicles and containers are given arrival

/

inspections.

Hugo/erous gC checkpoints are conducted during laoding and again prior to release for transportation to verify that regulatory requirements and good practices are all being adhered to.

On Site Storage 1

~

ppL's t)lo nooi ear plants're limited oith respeot to storage, <ao>l~t>es LLH.

At Turkey Point 3 and 4

a radwaste building contains an area of 70.

approximately 10,000 square feet in which storage of high activity LLH is suitable.

serves as shipment-Outside and adjacent to the Rad Haste Building, a fenced area a p1ace in which loiv activity LLH is p1aced >>hile awaiting

.At. St. Lucie, facilities are even more limited.

An area of approximately 250 square feet is suitable for storage of high activity LLH.

An additional area of approximately 800 square feet could be used for other los> activity LLH storage.

FPL plans to constru t a facility at Turl;ey Point and St. Lucre which will b

suitable for temporary storage of low dose rate LLiJ containers in the event it becomes necessaly to retain the LLH at our sites.

I In addition, FPL plans to further study the LLtt on.site storage issue with respect to lorg range planning.

This study is expected to be completed in approximately one year.

~LLtl II t

The Health Phy" ics Supervisor and Radwaste Coordinator at each nuclear plant have direct and day to day responsibility for supervising and.

managirg radioactive waste operations.

In addition, the Operations Superintendents and Plant Vianagers have management responsibilities in th management of radioactive wastes.

71'.

Within FPL's General Office, the Corporate Health Physicist and Radwaste P

Radiochmiistry Specialist have day to day activities and responsibiities in 4

radioactive'waste management.

The Hanager Power Resources,

Nuclear, Assistant Hanager Power Resources, t/uclear; and Power Resources Department Head each have Direct management responsibilities associated with the

'anagement o! radioactive waste at the Turkey Point 3 and 0 and St-Lucie Plants.

72

LLP;/ PROJECT Hucl ear Power Plant. guestionaire Florida Power Corporation I.

Volume reduction of radioactive'aste

l. Enclose any copies of FPC policy statements that have been issued regarding volume reduction of radioactive

.waste.

r

2. Briefly describe the training given to radiation workers as to how they might reduce radioactive waste volumes.

3. List the type of compactor in use and the compaction ratio

( or'bs of force).

r

4. Estimate the amount of volume reduction, if any, that is attributable to the 18 month fuel cycle.

5; Descry=-'any future plans'f FPC which will lead o a reduction in the radioactive waste'volumes being generated.

II.

Miscellaneous

1. Briefly describe the quality control steps that are taken during the processing and s'hipping of radioactive waste.

2..Estimate

-the amount of on-site storage available at

'rystal River for LSA and high-rad-materials.

Does FPC have.any plans for increasing he a>.aunt of storage available on-s 1 te?

3.

How many individuals are envoi ved in radioactive (taste management, both at the corpoate level and the plant level?

73 ~

LLRM PROJECT

.,uclear Power Plant Questionnaxi e Florida Pow r Corporation I. Volune Reduction of Radioactive Haste.

Presently there exists no hard'copy policy statement regarding volte reduction of radwaste.

2.

Rad>>aste reduct'ion techniques such as work area preparation don't take

.any unnecessary materials in the RCA and philosophy is presented in general employee training.for r"diation protection and is further cov red during job planning, and radiation work permit generation.

'Jhe waste compactor is a vertical piston type, designed for 55 gallon druns and compacts up to 15K lbs.

4.

Pres ntly it is considered that an l8 r,".onth fuel cycle >ould have no significant impact on waste volunes.

5.

FPC ha" develop d 'an in-depth plan for waste management, which includes:

1 a.. Entire waste stream study by our Architect Engineering firm and other consultants.

b.

Hast sch me operator training.

c.

hapl fied'eneral employee training in wast generation control.

~L+

II. Vis ellaneous t

]. 'ast Quality Control Steps Include:

a.

H~ tcwater movanent control.

~

~

~

~

~

b.

tlater chemis try.

c.

Radio Chemistry (scanning).

C rt fication of shipping casks supplied by vendor. and approved by 1;:RC.

Tnes qualifications are verified by Plant Compliance Sect'on during shipment preparation.

2.

The estimatM anount of on-site storage space for high rad. materials is approx"-..=t 'y 800 cubic ft. and LSA storage capacity is approxinately SOOO cubic ft. "Increased storage areas are a prime part of the overall v~aste engineer'ing study.

3.

Individuals involved in radioactive waste mana. ement are:

Plant Corpirate 7

TOTAL'

~

7'

ATTACHMENT 2 LLRM Shzpping Flowchart; 75 '

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~

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PWi

..(I'MPi1 sa "8

'. FEDERAL REGISTER a463 Done at sVnsh)vtiton.

D.C.. thh 6th nor of the Stale, acting in behalf'of the

~~(<.". s).':. "

. ~.s e~,." ~ ( dny,of Ju)y.)964.

State. asfollo:<s:

."-'<4'<W 'EIISKY '. <'-'< "

a-h'avrLzzf, page<<~ '..:,'rt!c!e f.

Subject to the exceptions ided in Art!~I~~ II, III. and IV,

j; "~V()oz for,Em<<rgcncy. '

s Comm!ss!On shall discontinue, as o! the

'ipLvch ~,'

g....

~ c..< !PJ'S ~.

6&6669;

Fnec, s&y 9.

19M;

~ ccfec.i..e

date, o( this Agrcemcnl thc

~: ". ~v; regu!ntory authority of thc Commission

. -,la the S:ate under chap'ters 6, 'I, and 8.

! IITog~g p~~pqp po Ig~ g~gyI dsecJon!6! of the Act<vithrespect to

)~tie Qf c ccl Q<e".hereinafter AGREEMENT B ET YlE EN AT0 MI C EN-

-. B. Source ma <ter)ais; and

,'rc's '!>,'i> p:<<

b<tc< of ~~e v J<J-.':

= ERQY COM)cc<ISSION AND STATE QF,-

C. Special nuclear nsnter!n)s In quan-

'>. I'.sJ caused'a need,, '.:;FLORIDA

-.:. titles.not suScient to 'form a critical

.Pi;.f><<<gifru< read!)y avaII- ',

mass.

". Disconiinuoncc of Ceric<in Commission ',

Arfic)e fl. This Agrccmcnl, docs not r ~...-,.<

~ h...

< -.",.Rcg<<lo)ory A<<lhoriiy and Respon-.* pro:ide for dlsconthiuancc of. any au-

~ -.=,, thorlty and the Commission shall retain '

~ authority and responsibility <vlth respect

.":-."~:~?!."gk~~<~6-.',

-:.".~'Vhereas, The United States Atomic to regu)ation of:

',~~~.;~.v~<<.~",~~ <i;':;. ":".. Energy Commission (hereinafter re-A. The construction 0nd operation of ferrcd to as the Com<sslon)

Is au-.,any pad ctlon or util!Cation facility;

-L.,j'.~.">> su(I:or!Lyc set forth, thorlzed unde: sec<Ion 2<4 of the Atomic-.

B. The export from or Import into the.

<;<=.g~jup ul)) not be mad -'Dcrgy Act of )954. as arne:ided (herein-

~ UrJted States of byproduct. source, or

-><.'<jk,~count!es a.'ter June 'after rcfcrred to as the Acti, to enter:.special nuclear mater!al, or of any pro-c;,.~~~(O, ppl!cants =ho pre-,'into agrccment

<vI.'h thc Governor of; duction or utillzntlon facility;

.js.-.~<4.~asrzcncy".Or spec!a): any State provld!ng for,discontinuance<.

C. The dtsposn)!nto thc ocean or sea

..'<<'-stbance and s."ho can.: of the regulatory authority of thc Com-.so.'yproduct. source,'r special nuclear

,'.":,-'. <~;~',<.<<Cd 'po)lc)es 'and, mission ">>'!thlv. the State under chapters

~

'a-".e mater)a)s cs define In regu!atlons

<",~".,6'.~ '(,

.:,6. V,.and 8, rend section 161 of the Ac', or orders of the Commission;

,Pi

')cJs 6 h da

. >')Lh resp -ct to 'byproduct materia)s. D. The d!-posal of such other byprod-ial nuc!car uct. so" ce, or special nuc!Cnr materia

"-;!.>.".; ~

~ '.'

. ':.mater!n!s ln quantities not sufhcient.to as theCo.. +Issionfromt!me tot!mode-

. '!;;.~,-"'(+++~ @<, ', forin a cr)ticnl mass: nnd

~

. tcrmincs by regulation or order shou)d.

,":;,!'::.<:Is:."

~':hereas.

Th>> Go'cr>>or 'of the Sta c 'ecaus~

of the

)<nzards or po!entlal of Florida!s aJ'.horizcd under section hazards

'.here of. not be so d!sposed of 2<90.)3 of the Porlda

)huc)ear

.Code

>'ltho 1 a )lccnse from ti<e Commis:ion.

~

(Chapter 290. F'or)dn Statutes, 1961) to

~

A.f!cl. Ilf. )hnt<vl(hstanding th ls enter into lh!6 Agreement svith thc'Com-Agr.emen'.,

the Comm!salon may from

.:,.);;. (.T"-X'<5 '.<<.." ~,..". ': 'mmion; and

z..c to t<". e hy ru)c. r(gula!)on. or ordc.,

XVhc:cas, Tnc Governor (cf the SLate of requ!re that th mwrufacturcr, pro-r

~

I d

c r

)<

r e

e e

L s

t

)

f c

<<-:c".su1 tor..E<<<

I) nty-rior!di ccr!c".e on Ap <I 2, )99$, that cessor, of producer of an)'qulpmc 1, ~

.*'1:c<<s 'I '<,:hr:.

'he s:zt o(.".'6:Idn'hcretnaf>cr rc-i'ev!C~.commodity. or other produc(, con-

"eme

<c C

ferred IO aS '".e S" IC) )n<S a prcgrun fOr tain!ng SOurCe.

byprO(l;iC!Or'peelnl

~ p

~<

1 6

~34) I o "tl,c"Co>'hc contro!

Cf rod~a'.Ici<

)<azards ede- 'uc!ear mnl r!nl s <a)l not trnnsfc". pos-quate to pro!est t)ic pub)!c health and sess!onor control of such product egccp>>

~i.<i 9 c

~ ci a

cc

< ss

~

scafciy 0'I h r spect

'to thc P<atcl'I<1!s

. pu 6 'a n! !o n )Iccnse or c<

1 c'scmp

<on ln thc Sta. Covert d hy this Agree-ron)!!cons!:<g !as<<cd by Ihc Coma)!ss!Cn.

v".der Subscct!on 161 b. or i. of Lh. Act

'.'! C.ens. Th>> Coma<!salon found on lo!ssue rules. re,".uln'Io:<s.

o.".

orders!o'.

S'.atc for t) 9'rcgulnt!on of thc r<ntcrln'.s c":!ty, to protect r 'strlctcd dat.'( or co"er(a b'.h!s Ag<cc:ncnt Is comPat!bce guard a,"alnst trc loss or divcrsbn of svI:h thc Core.n!salon's program for thc spec!n! nvclcar mdi(rial.

'c',"cs

'c"0!a'.Lan nf such n(a<erin)- and!s adc-Ar'!Cie V.

The Co..ui<ission v<iI usc c'j:...'"c c'.'"" "

'u~ate to protect, the pub!lc health and I!s best cc or'.s Lo cooperate sv!th t);c safety; ard

~

~

S:ate nnd other agrcemcnt States "ln t):c

,~rc.':.;.'<: ~q,!".!<<. ',,',-.

~

V'herc:<6, The Stoic nnd the Co<nmfs-'orn"'!at!On of stnndar(is and regu!C(ory s!on recog<1!ze thc dcs!rnbl)!t)< a)<d im-prog.rms of the Stoic n'nd the Condom!S-hcc"<.Jc'-.",;x..-.~)~o::<ia. "'

portnncc u!

coo>><ration betaccn th sion for prelection aga!nst hazards of

.:s'-'.":;c... '::<. ':

~

Comtnl "sion nnd thc S!alc ln the forr<u-r.diat!on nnd to ns:.urc thai, Stnic an I

)nt!On, of s.andnrds for protection Cou:m!ss!on p:ograins for prolccLion

<<:'";",'i< "'.,'I".o'.~',: ~ '; ~, <<qninst hazards of radlat!o.< and ln as-against hazards of radintion s<'!!I be co-s'r!ng that Slalc:cn 'on<!nis."inn pro-ord!na;ed and con<pat!bin.

Thc S:.ntc grams for protection ago!nit hazards of

":I!)vse!cs best el!orts tn cooperate s<<ith radiat!on scil) bc coort!inntcd nnd co:n-(hc Comm!66!on an.l other agree:nc:.t

~.."." c h'c I".(c nu.bor!Ly sct fo-.'.h pat Mc; and States!n thc fo:inulnt!On of standards

.'><~..-"...>';Iru;S-..l)I nat bCmadC XVhrrCJS, Th" Cum:nlSSion and the end regulatOry Pro"ran>S Of thc Slate

.': c;h>:;"...,h<i coun'.!cs after June Stale rcccgicdze thc des!ra! ilit<'f rc-nod I..C Cc n:n!ssion for pro cc':cn

-.; ".i"6".pilcanls svho prc-clprocal rcco"nltlon of IIccnscs nnd cx-aga!nst har.;rds of rad!<<Lion and to x~-

.;<<.;<<q".. "C.=ergcncy or spec!al c apt!on fro~

I I c e ns In g of those: svrc 1! nt tl c State'6 program w!!I con-

.<,",.P~) 1;:c'...agee and SVhO Cnn mn!Cria!S 61<h.'Cot !O ihlS <c<grcen<cnt:

. tinue tO be CO:npnt!b)C <Vllh thC prcg:cnm

>.'.<.".(i.e.".r -"Q.~~ po<Jc!cs and

)(osv, therefore, It ls hereby agreed.

of thc Coma.sslon for the regula:!on of betsvecn the Commis:!on and thc Govcr-.'<~e materia!s.

Thc SLnlc and Lhc Com-e c

'S ';:: "....,

~ '.'".

4 c

I ~

Li<

. ~ I

'i ci

'-A:I:

lg

~ <)j c~'.g;:

, )I'~t y'

)

~ <a

't,I re

~

I<

" '. ~

i w<

cc

~ c cc c

~ <.I c( c ~

'c<

~

...t:i '",;

it

c c

.c '<hc"

.j,g/cjoy

~'

c8 > ~'J<

'iI <<~<~+

3-'--;::-:

,f.. <<f'(i~c Cf" c.rt-A

~ ~ <<

t!::;."::;.:.::-.

)

~ 0- ',

sm.>

A

. mlsslon will use their best efiorts to keep

'ach oc>er informed of proposed changes ln their respective rules nnd regu!ations

.',and licensing, inspection and en'orce-

~:... ment policies and criteria. and to obtain the coinments and assistance of the other

'party thereon.

Article V/.

The Commission and the

,'~,-.,:.~ -. State a ree that It ls desirable to provide for reciprocal recognltlon of licenses for

-':~.".;:'Lhe materials listed in Article I I!censed

~ by the other party 0: by any agreement State.

Accordingly. the Commission ard

.!'.~'.":'he State agree Lo use their best ef:orts

. to develop appropriate rules, regu! at!Ore, and procedures by which such reciprocity willbe accorded.

Artie!e V//.

The Coinm!sslon.upon ILs own initiative after reasonable notice

~ and opportunity for hear!i.g to the Sta:c.

NOTICES application on file b; Ress on Au~t 12.

1 Rscc a conf)ict neces)Ital:

an appUcnt!on on th!

with Inte)lm criteria ance of sLandard br<

'et fo"'5) ln thc fo)7 cr)1<souci

>>c',eh\\,

'AX)

~

~ ~

)ic,) X<V~s=.!. ccc<<<c-Of the COnim! <SIOn ri iicci)1 so Ysu)o io LIO!I.. conipleite an<ti Nc>> Ycc)c.

<5,35 ccou pcc hllo<csco, a! thc OQices of t Iulo<mum>><<she, 0!Q QVash!ngton, D.C.,

<ice<)1 IC)>>oos

• ice, S ear er:

a ie c sue h<ro<cs6coco Nc>>

August 12, 1964. or (i Yoca.

I

<5/35 c

<c Pcc L<le<cccu, t!vc cut-off date w.ii muumccco "cishL Xnl t!On Or any Other COi may have by virtu

<<cc<,"I Ducroc hfccs <o New %'Oc?,

Si'Lating a

hcarlng 33 cciiu Pcc hliciscsco, appearing on prcvini miiii.=ucu <<clsh<, isol i k!!Cciou:.: MoccccT<i)co 'he attefitiOn Of 0'o Nc"'oca.

desi>>ing to fi)e p]eiadi.

~pending standard br IATh memo cln6iim irCII Recce Con ~

rcoin7 ii,cc C.h.)5 i.Qi

,'l;-:i': t.

~ ];/C) '

cc r..'

<g~."...

)c.i'-'"

~

Pi.".I".

~%i 1i

~.'i 'i F.&5..

2<02 2<o)

. or upon request of thc Governor of th

State, mav terminate or suspend this

.'=;. ... Agreement and reassert the llcenslrg and regu)awry au'thor!!y vested ln it under

'the Act if the Commission finds that

~

.: c'.such termination or suspension is re-

-quired to protect the public health and

';,;:;--.:.'. ",.safety.

~ '

Arffcfe V///. This Agreemcnt shall become e Cectlvc on July 1, 1964, and shaB pursuant to section Cor.".munications

amended, is direct(

the CommLcs'on r governing the time c

requir e<nents rclatin.

Adopted July 1

1 The Board, act!ng pursuant to sections 102. 204(a), and 412 of the Act. does not find Lhe subject agreement to be adverse to thc public Interest o. In slclation ot the Act. provided that approval thereof is conditioned as herelnaf!er ordered.

'ccording/y, ft fs ordcrcd, That Agree-ment C.A.B. 17666, R-42 and R-43, be and hcreb is e roved. provided

that,

~

FEDESAL Cohi:i fSEAC,?

BCW F.

c y

pp s ch approval shall not cons:!tule ap-proval of the specifiic commodity descrip-t!ons conta!ncd therein for purposes of t-riffpublica! ion.

i

'".yair ca)7lcr party to thc agrecmcnt, cr a::y interest.d person, may. within 15 days from the <!ate of ser'ice of this or-.

de;. cubinit statcmen!o in will!ng con-tain'.Iig reasons deeincd np;)roi). Ia!e. !0 gether with supporting dahn, iii support o.'r In opposition to the Board s action herc!n., An 0:".gi:inl and nineteen copies w irc ff')./ i<a'i '

~

hppucstions From th>>

Ll BP-'1507i 7New. 'Bu ci John

<V. Si bsn Bco<<r peq 800 ) r BP

~ i0i7

) RcD Cali!orhhs

)Iss:

)480 Peri )450:

~ i A i Ci

~

~

xi ~

4 ',;

1

~

I

~ i

~

~

~

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o. any such s!a!c-mcn'6 fl!ed, me<i!!y or res"ird lits ac'lion here!n by subsc<fucnt order.

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By t!ie Civil Aeronautics Bohrd.

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EJ'>JL Mi",Ij(b)L~T(II,'3 IIOrgb BP-16035 IDoc'eet 13777; Order.'(o. E-21034,c INTFRi tATIONAL AIR TRANSPORT

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ASSOCIATIOiV Agreecnenl

)Iclolcng Io Speci."ic Cocnnodily Poles Adopted by the Ci: II Aeronau:ics

~.,Board at lLS oi"cc iti V;ashiilg4>n, D.C.,

oin Lhc 69 I diivof Jul) 1964:

There has been fil!d ivith tho Fcard.

purs 8:it to sec!inn 412(a) of !hc =;4!-

eral fiv!at!on Art of )353 (the Act) and Part 261 of t!)c Donrclis Trconom!c P%gu-

'- )at!ons.

an agrccnicnt between va."!ow nir ca.ricis, foreign a!r carr.'0<<,

and other carrie:.". cinbodied in thc rose!L'-

ionss of Tra(T<c Coiifcrencc 1 of thc In-ter."ntcnn1'<r Trapec".crt AC~Xca"0" (TATA). nnd n<ioptc<i pu:su<nit Lo th proiic!ons 0( Pcsolutio:I 590 (Copxode ity Pa(cs Board).

Tl'ic ngrccmc it ajjop!ed pufsua

)pro~>!cd not!etc w tlic carriers and romuigated In ZA1'A n)cmormda.

an)cs additional rates as sc t forth

'OWI E

BP-16083 I:EOEIIiit, tlOIIi)IUV!CATt0jH CIItI':tIMlkII (List 56: )Y C61 603!

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BP-16150 Ju Y7.1964.

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remain ln effect unless, and until such

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Z)one at Tallahassee, State of F)or!dh, in trip'1!cate, this 1st day of July 1964.

Coin)rfssion:r.

For 'the S:aic of Florida. "

STATE OF FLORIDA DEPARTMENT OF Health 8 Rehabilitative Se;.vices Bob Graham. Governor l3I7 IVINE~VOOD BOULEVARD TALLAHASSEE, FLORIDA 32301 March 31, 19 81 C

IIs. Joette Lorian, Executive Director Floridians United for Safe Energy, Inc.

7210 Red Road Suite 208 Miami, Florida 33143

Dear Ms. Lorian:

Ne have your letter o

March 23 concerning'low-level radioactive waste being generated at Turkey 'Point nuclear power stations.

I will respond to your questions as you have numbered them.

1; The Nuclear Regulatory Commission (NRC) is responsible for all on-site activities and will approve or disapprove. the construction of any facility to store nuclear waste on-site.

'I t

2.

In Article II of the 'NRC-Florida Agreement, it.is clear that NRC retained authority over nuclear power plants.

Any waste site outside the confines of a nucl'ear power plant must, be licensed by the Department of Health and Rehabilitative Services.

The land. must, be owned by the State or the'ederal government and the applicant for the license must meet.a host of other requirements designed to protect public health, drinking water sources and the entire environment.

3.

Since the licensing of a nuclear waste building on-site is the responsibility of NRC, I would assume that NRC would require an Environmental Impact Statement, (EIS) if they,felt it necessary.

Although I follow the Federal Register rather closely, I do not recall seeing any mention. of a nuclear waste building at Turkey Point.

If we can be of further service, please let us know.

Sincerely, Ulray Clark Admin strator Radiological Health Services

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of FLORIDA POWER 8 LIGHT COMPANY (Turkey Point Nuclear Generating Units Nos.

3 and 0)

Docket Nos.

50-250-SP 50-251-SP (Proposed Amendments to Facility Operating Licenses to Permit Steam Generator Repairs)

CERTIFICATE OF SERVICE I HEREBY CERTIFY that a true and correct copy of Intervenor's Posit'ion as to Action that Board Should Take Regarding the Disposal of the Solid Waste Resulting from the Steam Generator Repairs was mailed. on this the ~ day of June, 1981, to the following addressees:

Marshall E, Miller, Esq. Administrative Judge

Chairman, Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.

C; 20555 Dr. Emmeth A. Luebke, Administrative'Judge Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.

C.

20555 Di. Oscar H. Paris, Adminstrative Judge Atomic Safety and Licensing Board Panel

- U;S. Nuclear Regulatory Commission Washington,'D.

C.

20555 Mr. Mark P.

Oncavage 12200 S.

W. 110th Avenue Miami, Florida 33176 Harold F. Reis, Esq.

Steven P. Frantz, Esq.

Lowenstein,

Newman, Reis 8 Axelrad 1025 Connecticut

Avenue, N.W.

Washington, D.

C.

20036

Steven C. Goldberg, Esq.

Office of the Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D.

C.

20555 Atomic Safety and Licensing Board Panel U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555 Docketing and Service Section Office of the Secretary U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555 Burt Saunders, Esq.

Assistant Dade County Attorney 1626 Dade County Courthouse Miami, Florida 33130 Henry H. Harnage, Esq.

Peninsula Federal Building 10th Floor 200 S.

E. 1st Street Miami, Florida 33131 Norman A. Coll, Esq.

STEEL, HECTOR 8 DAVIS Co-Counsel for Licensee 1400 S.

E. 1st National Bank Bldg.

Miami, Florida 33131 LAW OFFICES OF NEIL CHONIN, P.A.

Attorneys for Intervenor Suite 1400 Amerifirst Bldg.

One S.

E. 3rd Avenue Miami, Florida 33131 Telephone:

377-3023 By 0

N il one.n

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