DRC-1998-001121 - 0901a06880aea579

REG,LA*,.":#,,:*n?*T",1- oil},srEM ( RrD s )
ACCESSION NBR:9806250135 DOC.DATEz 98/0e/L2 NOTARIZED: NO
FACIL:40-8681 International Uraniu.n USA Corp.,
DocKET #
04008581
SUBiIECT: Inf orms that
FUSRAP wasteg
of Engineers
AUTH.NAME
THOMPSON,A. J. ,,KIM, D. A
RECIP.NAI{E
REHMAIiIN, M. R.
AUTHOR AFFTI,TATION
Shaw, Pittman, Pot,te
Shaw, Pittman, Potts
RECIPIENT AFFII,IATI
Shaw, Pittman, Potts
for source matl
Trowbridge
Trowbridge
Trowbridge
RECIPIENTID CODE,/NA!,IE
NMSS/DWM /DEPY2
oclLFMB
RGN 4
International U rp is considering processingthat are curr Iy managed by US Army Corpsontent.
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DISTRIBIITION CODE: NI-,05D COPIESTITLE: Standard Distribution for
NOTES:
:LrR_Lr*"o \ srzE, bRecovery (UR) Docunente
RECE
Ur
COPIES
LTTR ENCL
RECIPIEMT
ID CODE,/NAIIIE
PARK, iT
occ/REGD/SPFC
NRC PDR
COPIES
LTTR ENCL
I}iIITERNAL:
EXTERNAI,:
101111
111011
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NOTE TO ALL NRIDST RECIPIENTS:
PLEASE HEIJP US TO REDUCE WASTE. TO HAVE YOIR
OR REDUCE THE NI'MBER OF COPIES RECEIVED BY
DESK (DCD) ON EXTENSXON 41s-2083
OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS
YOUR ORGNIIZATION, CONTACT THE DOCT'MENT CONTROI.
TOTAL NT,MBER OF COPIES REQUIRED: LTTR ENCL
Jun-12-98 03:l6pm From-SHAll PITT
I
:
2026638007
COR?OE^TIoNs
T-317 ?.t2/03 F-542
POTTSA
I
Michelle R. Rehmann
Anthony J. Thompson
Drivid H. Kim
I
SHAW PI
^ P^RTNEtrsilT INCLIIOINC
MEMOIU UM
TO:
FROM:
Processiog of FUSRAP Wastes at Ti
Iatemarional Uranium (U SA) Corporation ) operates rhe White Mesa Uranium
Mill neiu Blanding, Utah, and is considering Formerly Utilized Sires Remedial Ac-
rion Program (F[{SRAP) wastes rhat are currently
necrs for their soiuce material coment. These wa were primarily generared during processing
by the U.S- Army Corps of Eogi-
of ore to recover,uranium and thorium and rhus
Atomic Energy dc (AEA).
as I le.(2) byproducr material under rhe
Radiaiion Conuol Act (UMTRCA or the
lI (active) uranium mill tailings sires such
as IUSA's White,Mesa mill can reProcess I Ie-(2)material. However, UMTRCA d-
lows reprocessinp of I le.(2) byproducr material at
for rheir source marerial conteil:
I (inacdve) uranium mill tailings sites
[T.lhe Sedreary [of Energy] shall request of interest from privare par-
ries regarfling rhe remilling of the residual materials ar rhe [inacdve]
Neirher +e AEA nor rhe Uranium Mill Tai
Milt Tailings Act) explicitly addresses whether Tit
sirc and lpon, receipt of any expression of i
amoog o*rer things the mineral concentrari<
aI each designared site ro derermine whether
pracricable. The Secrelary, with the conc
rhe recovpry of such minerals. . . .!
u42 U.S.C. g 79tg(bxemphasisadded) Whrlcrhis
ucl marerial present al acrive (Tirle II) sites litcely can be
lates ransfer of cusiooy of nill tailings and lands rrecessary
or srares upon tcrmiirarion of license and provides in pan:
the Secreury shall evaluare
of rhe residual radioacrive materials
. . recovery of such minerals is
of the Commission, may perfiur
ooly ro tnacrivo (Tilte l) sires, I Ie'(2) byprod-
under secrion 83 of AEA. Thar secnon rogu-
their drsposal Io U.S. Depanmcnt of Energy (DOE)
1r; t,5 f,
lf rhe Commlssion determines by order tbal use of surf'acc or subsurface estatcs, or both, oflhe
land ransfpred ro the Unied Srates or to a SIare subparagraph (A) would not Rndaoger lhe
Footnote conrinued on nexl
23oo N STRErr, N.WI4/ASHINCToN, DC. 2oo37-1,128 TELEPHoNE 2c26638C,00 Fnx 2c2-663-8oc7
FBH"',iB38i ffi8|fu't-- PDft
Jun-l2-98 03:l6pm Frpm-SHA$l PITTl!2026638007
As used above, rhe lerm "residual radioacdve material" is defined broadly ro include
,,waste' -: i in"form o/'nilings resuhing Jiom rhg processing oJ'ores fc.tr the_exftctction of ura-
nium and other valuabli consliruerls of rhl orcs."3 This rerm would *rus include I le-(2) bY'
product marcriar ivoich is defined as"tailmgs o7 wusrcs produced by the extraclion or
,on rnoorton of Uranium or thorium from any ore processed pnmArily for its source mArcrial
cowenl."! ,
I
Moreover, rurder rhe 1996 amcndmenrs Io rhe Mill Tailings Act, 1le.(2) wasres from Ti-
rle I srtes can be directly disposed of ar Title II sircs:
Residual radioacrive marerial from a processing site designated under [Title I pro-
ir"*f *ay u. disposed of at a facility licensed under [T]irle II. . . .Disposal of
such material ar such a sire in accordance wirh such requirements shall be consid-
ered ro have been done in accordance with rhe adminisuarive and rcchnical re-
quirements of this subchaPrcr.g
Given rhe fact rhar rhe MiU Tailings Acr explicirly authorizes reprocessing of I le.(2) by-
proao., *u*.iJ ,from Tirle I sites for rhcii source marerial coileil and direcr disposal of such - -
marerial ar Tirle l[ sires, there is no reason why Title II sites such as the Whire Mesa mill should
;il;b*.J r,i pr"cess FUSRAp wasrcs rhar already qualify as I le'(2) byproduct marerial and
dispose of any ,"tutring wastes on-site. The mere fact thar such marcrials originared from non-
ii,il r sites should norlrevenr rheir recycling for enraclion of additional ruanium when such a
,*y"iirg furrh"ri."duces rhe radioacri"i conient of the wasles and resuhs in rhe recovery of valu'
able source material. we also nore thar any wzrsrcs generared ctrrring such reprocessing remain 6y
i"p"irii r re.tz) byproducr material, fully etigible for disposal at 11e.(2) tailings impoundments
mainrained by Tttle ll facilities'
Foomore continued from provious pagc
public heal*r, safery, welfare, or environmonl rhe Coromssion . ' . shall permir lh< rrsc of rhe sur'
face or su$surface estatcs- . . .
42us.c.gzrtr(HxtxBl.
I
z +z u.s.c $ zl::k:;te)(cmphasis added).
I
1+2 U-S C. $ 2014i(c)(2)(emphasis added).
3 42 U.S.C S 79tt(a)(l).
1-347 P.03/03 F-512
2-
Jun-l 2-98
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T-347 P.0l /03 F-54?
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25OO f, STREET, t.L{. wASHttcTOt, D.c. 20037.1129" FAX IIUUEEB: 2O2.665.E0O, milil ilUllBEE: 2O2.665.6000
FAX TRATSUISSIOT COVER PAGE
FOLLOWTNG PTGEIS): DTTE:
+-
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F.r\ r.-L}IBER:
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TOTrL \L.vBER dT P.rCUS. INCLUDI.\G THIS COVER:
FRO!['
DIRECT DLrL,
CO}I.}TEITS:
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OPEReTOR:
TIME T&TITISMITTED:
*p7 +^ fi ort io.S r* **rtz
tF yoii oo f,oT Btcgvt AtL pAcEs, CALL 202.e65.9613
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Tht /acs,aule a.esiat. $|iea4ed onlv lor tlu uc ol tle ucltvrduols to thorl t s drcsscd aad acy colzrto,a ofuaeuon than s prwt.
le$d ad conlidcnol lt rhc rcdtr o/ ris mc*agc q aot ilrc uten4C ractgtou. toy ct G lurcay aottftctl tr@t cny 4$ssI|.trr4,noa. 2t,strt.
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RE eur,At -*S#T-E",ncr9#frr*1*t rs rEM ( R rD s )
aceEssroN tlBR:9806250153 Doc.DATE z 98/06/LL NoTARTZED: No
FACIL:40-8581 International Uranir:nr USA CorP.,
AI]:THOR AFFII,IATION
Shaw, Pittman, Potte & Trowbridge
RECTPIEMT AFFIIJIATION
SUBifECT: 'rlntroduCtion to FormerJ.y Utilized SLteE Reuredial Action
Progran (FUSRAP)."
COPIES RECEIVED:LTR O ,*.O I sIzE, lA
DOCKET #
0400 8581
AUTH.NA!{E
KIM, D. .
RECIP.NA}{E
DISTRTBIITION CODE: Nt05D
TITIJE: Standard Distribution for UranLusr Recovery (IrR)
NOTES:
Docu.urents
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occ/REGD/Sprc
EXTERNAI.: NRC PDR
RECIPIENTID CODE/NAUE
PARK, iT
Ir,e crNT-rR-\ll
MsS/il{Ns-frfrOE
COPIES
I,TTR ENCIJ
RECIPIENTID CODE/NAIITE
NMSS/DWrrI /OnpVZ
oclLFMB
RGN 4
COPIES
LTTR ENCL
1
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NOTE TO AIJIJ iRIDSi RECIPIENTS:
PI,EASE HEIJP US TO REDUCE WASTE. TO HAVE YOI'R NAIIIE OR ORGAIIIZATION REI'IO\IED FROM DISTRIBUTION I'ISTS
OR REDUCE THE NT]MBER OF COPIES RECEIVED BY YOU OR YOI'R ORGATiTIZATION, CONTACT T}TE DOCI'MENT CONTROT
DESK (DCD) ON EXTENSION 415-2083
o
TOTAL NITITIBER OF COPIES REQUIRED: LTTR .y ENCL
06-l l-tg 02:58pm )Fl^,yv fll lMnl\O lo-%tPOTTS =TRO\^ENDCEl r/lltltr {p lErr,oig rlE ESI]I! coarotanott
I 2300 t STiEET, t.W. wAsHrIrCTot, D.C. 20057.1128, ier ilurBEE: ZO2.ee!.aooi mAtr ruirEei: 202.663.8000
i __ FAx rnArsmtsstoil covER pAGE
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T-757 P.0t/13 F-755
PLE*SE SE}TD,TEE
TO:
F.rY .\t IIBER|
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FROM; ;
DIBECT DLrL: I
colt}lEr-TS: :
FOLLOWTNG P.TGEISI:
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TOTrL \UltBEt OF FTGES. tyclUDt.\c THIS COVER:E
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REeuEsr rx iv'
VERTFY NO.:TI}IE TRTfiSMITTED:
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:
-- --.Laa-....a.i------.....-----r!---..-----
06-l I -98 02:59pn
!t!IF
F rom'
i
T-757 P.02/13 F-755
nrpr/rl*1r.sm oc govrbcu9&fung lul
FUSRAP
Introduction to Formerly Utilized Sites
IREMEDIAL ACTION PROGRAM (TUSRAP)
PROGRAIU MISSION
Is l9?{ &r Atolaic Eqcry Coonisooa ct bliEid tb Feracrly Udtizcd Sircs Rrocdial actios Prqnu (FIJSRIPI
uuder aurboriries gnsicd b, &. AtoEic Eacrpr A6 d 195{, as aacndcd. FUEBAP caqmpas aS dtcs ia la sarct aud is
O.L TE
ctcas up or reEaiuc too rhe car$ rcars of the
oauos's aourc eucrgypogrur or othcr srtcs assigrd ro thc Dganncar of Eacr6r by Congrcss.
NATIONAL TIAP
ENVIRONMENTAL RESTORATION
(
Durug thc 1940c, 1950s, .nd 1960s, worl b stppon ofthc *onic cErsr6/ psograD *as pcrforocd ar siree &nugDour rhc
Uutcd Srarcs" *criviucs at soEG siree rerc oadrlC Cutilg World War II uads tbc t{adaoaa Elgiaeer Disric-c orhcr
srtes were involved Ur inccUne acivilics uldtt tDG aooic Eacrp Cornnisiou Botb the ty|aDlsnaD Eagiaecr Drsrncr
ud rhc Atomic Enerry Coararission wrre predccceson of tbe Dcpa,runcnr of Eucrry. During rbc lglo1 BraarurB ore was
stupped to thc lr{anbadan Eqiner Disicr tou rbc Eclgia! Coago or aiocd ia &c wcsrsro UBitC Serca aud Anada
Mosr of Oe Nofii Aatrica! orc *cor dIurly ioo pesiag Tba A&icau oEE r.r placcC rB remporary srorate and was
Ocn scnr crthcr dirccrly rc a prmiag frofiry or ut e sanptiug and assapug fasility bcforc bciug proccsscd ancr
procrssrng; IIe ore sas senr b c[her a uruiusl euriclrust tctlity or a urauiun neral uastiaiog plaur Wucs &om
unoium processiag wase ralspone.t ro stora& altl disFsal Ecitiuca Esnchd urardum was sertr direcdy ro wcaFoas
development sues, aod Eachrn€d unuum ras seBI rc produstiou tcactor* prioarily du tlrnford Rrservatrou ra thc Srarc of
Wasbngon rn thc t9il0s .Dtl ths Savrnnah Rivcr Plaar tn Sottlr Carolina in &c t950s. Tbcse reasors produccd basic
marcrials u.scd in ma&ing nuctcar rrcnF[s; rDc oarcnElE *crt lbto shrppcd &ou tbc produsriou rBrcrors ro vc.Eons
dcvcloprcnt facilipcs.i
i
Gcnerally, sircs used for Manbanao Eogioer DitticuAlooic Eacrgr C.omroission-rclucd astivrtics wctc dontarniured
ud nleased for usc uq&r &c clornup guiddi!.s ru c8cr c Us due. Eccause rhose Suidditrcs serc less srtageu Oao
roday'E guirtelincs, smatt aoouos of radioactivc trarctialt rcanirpd at some dtlrc sitls. Ovcr tc ycarl mneminauon
soccrurlEr ryrca{ pnnanly Orou$ tlc soil orair, ro nciairy poptricr as tbc rcault of rclcascs frorn opcrung fasilides or
*han buildings werc di$nasded or marcnals rcrc uowd-
ID t971 rhc Arotrlic E4crg Courmrssron estabbcbcd zuSRAP to snrdy and ctcan up tbcsc ntcs. Wbca lrfadranau Eugrnccr
eu3illFItm
crte8
loft2 t0a0t97 t9.t235
I
.06-l l-gB 02:59pn From-
*",
T-757 P.03/r3 F-755
iqr'/wrtt crrt dc ao'6cmr96rfu*+ bsrt
DisEicf-relucd radioafiivc marcrill is rhoueht tob3 pr6!0r, hisroncal tcoorG arc rEYicnE4 radrologcal suneys of the stte
are perforuEq urd conrncnul lrabitrry is est0lishcd. U radioafiive sulcnd rclatcd to lv{arlaEa! Eogner Drsnqor
irohi. Encrg Coruniisioo rcriviscas forurA clcanup s arrlonzcd uDdcr FUSRAP Congres lus dso added to FUSRAP
some sires *1tr ioOgstript oo111rgiDauon slnrilar ro &ai prodrrced by ]fanba.ren Engnccr Drgnct ol ADmrc EncrB/
Comrnispn acgvttics.
Tbc Depanncar of Erirgy conriaucr to iaprcve iu FUSB.AP oDJesov€E ano mdry Us scope dIDc prograu.s r lEaros
fi;-d*"* rsti",ri35,[er ruSner anit cntrer narionat clcanup progaos. It. 9oo of Enviroancnral Rc*orauou'
*rrlii rlc o6ce dgnvironucnrrl lvtaugsneor u rhe Dcpangrlrr o(Eoarg/ *aa+arcrg io wasbiaEoB D'c'' P-rov.tttcs
o-o,aa ,uidans. U nlinef anO orlcr-Eavironmcoral ti{augeocar pmSIsEr aad providcs for dcsigu,son anrviucc.
6;]iff!, *t*-t, ilr.inisrradvj ard fnarciat naoagemcnt of FUSIAP aeriviries is tbe rcspasibiliv dtbe Fornsr
Si165 nesronrioo Dividon dr1c DepannsnI of EBerE/ Opnrarioos OEce in OaI Ridge, TeBncsrEs.
o[rer federal agcocies, srap rad local govcruncou, ald prryq owaes also play tcy roles i! FUSRAP. FdcEl agenctes
s,r.[ u,h. U.S]Envrronm.nul Proresion Ageocf provi& o,.CIgh, arrd regularory dirccriou for Dcpnncnt of Energr
aari"ioo at soEB FLrs? ,rt sitcs Sarc goverrnenriensute compliancc virh srarc regulrdoru. [.mI gorcrnrnents wort to
;;]f;FrJ"; olrle .*.,*ry-ana u.p io{o1m ne pubiis abou cleaaup acoviEes. Eopqt y ovncrs rruv provrde
cntical iaforuauon Oiur p.n *riririis ar FUSitrP sircs aai curtot coumrurisy coooems. nr Dcpattocat of Eaergl
actiyely soticirs rnpur tom dtc* afir orher salcholdeE at FUSR^P sites.
STATETTOT.DER INTERACTTON
s Euoag pannenbips ber*cen tbc Dcpannenr of Encr6l rnd iu $albot&rs is r u4jor gosl of
?G'#[*i. d iiformarlon ccnrs-rhrougb roaoy clrauclr. For exaupla asovc citizcn adivis
" fo*}i* o.iovidisg inprr ioro rtc Ocganocat of Errgr rl*isiouroaliag pres' aod-muv
la.n piru.ie.,.in re9rtldy'sctcaUod.wortstrons, 3qtaU{ry Try9g-:ircrous Io addidoru
pip.rrrodu of irurey uai isra[tirtcO rclarionsbipc wirb educarioual syscus_wi$i! the afrTld
*,irrtit. rusn+pGaf.ohavcsporen ab$ calty in rhe cnvironmearat !*,._13-?lt:9:^g;;il.r], ;b;"1 rruO.o" ro FLlSRAP'commuairics. Otbcr snrdcas have puriopalcd tl.dcooasrrauous of
rnoniro"i,g cqriipuent ar,Opron*r. ctothing Higb Ecbol scuion *.t o*-1lllf.-t-tt pantciftod wi$
D.dil.*;,f Eactgr ii a urocl puutic neun8- Sonc dtbc l6ls rhar &cilinrc iarer.ction witb
i1ifaej5 idctu& mgr pgttic infofoorion ccnters thal rewe as raforuarion rcsqlrccs ad mccting places.
;, eit stoo, aiO Urocburea. a FUSRaF vidcotapc is availabh-on rcql1tr anasecalars af
6, Cut. anO Lrvicc clpla erd eooouniry orguribtioas. A 2d-tou roll'&cc public rcccss linc ts
for sialeholrtcn sho hevc qucsrtou or conncots. Tts uumbcr ir t't00-253 '9159'
were no.Basetiru Repon-spoci6c ga&cbolrbr efioru oadrrctcd for FUSRAP- Itrmcvcr, if yut would
adrliuoneli ooDurl:
l.
2.
3,
4.
5.
F-U S NAP TAIO R O BIECTIYES
I
Rnat 13d cvalu13 sircs rlar srpponC t{anbaca! Engiaccr Di*ncvArcnic Eacr5r Coosiceion urlcar *ort (or
orhcr nrcs ac4iDsd by Coa3rcsil aDd &tc oiDE vbahcr tlry lcgl clcaury alilor cgBEol.
Clcarup or aaianiorlcsc stss to thattbry ocs cutreut E i&ti&r'
Dirycc-dor SabilizE Ediossriw oardsl ia a nay tler is safc for lD3 FDlic lDd Oc envirounrnr.
Fertrn rlt wort rn conplianccwirbspprqriaa fcdcral la*: aad lt8ruadoas aadcooplyrrosarc 8od lel
erwirotcoral hm and lrud<rsc requiruatg.
Ccrd$ rlrc sircr for aprqriaa fuuue urc.
l0r30D7 19 12'40
06-l l-98 02:59pm
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Thc Cooprehcnsrve Epvironarenral Bcsponsc, Compensadou ald Ltsbili$ A$ 0f 19$ (also knovrt u Supcrfirod) is tbc
nau las goveruDt clpanup of mury FUSRAP sitcs- Reooval acuons undcr this acr involve ruouroriD& cleaniog up. aod
rcmovrng conamrnerioo. Thc prcss for rcocdial acrions isvolvrs Efinty, desip, aod oonstnrsion of longer+erm rerrtcdial
resDonscs.
i
Srx of rhs 46 FUSRAPIsircc are oo Or Esvlroagtennl Ptopsrion AtsDcy Narionet Priorigcs Lis. Ar thcse srtes, Federal
Faciliries Ageemen6 ber*ees Ua Dcpanrenr of Energt utd the Envuonocntal Protstion Agency gui& clcanup Thc
T-757 P.01/t? F-755
htp//w*r.crD 6c gov,l411p6/fuEp Iutl
fdcrd fasrligcs atrccEsEI seu ctcanup prioride4 drfncs respotuibtlitier rnd mE acdoos, utd cstsblisbcs a sctraluls for
nort u a suc- Tbe Dcpanncnr of Eacrry inrcgratcs thc Cooprchcasivc Eavirolocanl Rcrpoorc, ComFnradon, ant
Lisbdiy Acr asdviry wftl orbs lr*s r]rar appty to tbe cic. Potcotially applicable lars inctudc tls Narioaal EnWoamcuulI Ltagutly allcr sgYlry wllJl srlr,sa rar:, aaEr sl/yry E 5 DrE. f vEr.qrJ .vavw.. Err BDs
I potiey Acr of t969, *hicb cers basrs rulioaal poticy on euvuonmeud protoctroD; thc Rmrucc Conscnarion rnd Recovery
I e.q rhi.tr is rbc principal fc&ral $a!rc govcmiug lueosgcocil of hazafious chcoicat *aas: rbe Toxic Subcaaces
I Couol Asq &e Ctraq Air Asc tbc Clcas Warcr As; tbc Safc Driuliag Wets Asg aod stc ad lcl rcgulrtions. Thc
I Vecs of msrc forud a eact $lc Prunanly (EI.rElDc os E*! tDa[ aPPty.
Jft **.t FUSRAP sircs ousias priogdly dlov couumtioos of rrradno. radirro, aad rborirrn oa buildilg srfsccs
f ald rn sil. Mucb of rhis rcsiduat radiouivc raatrial rcordEd too presiag orc to neooycr uranium ud tboriuo. Tbis
| *asr ir 'ADy-prodrrcr: uarcriat Lncnro as tl(c)2 (dcfisC by rbc Atohic EuergT Art of 1954, ec arrrdcd by rlc Urauus
I Uitt totiags naaiadon Courrol Acr of l9?t). Vcry low lctrtr of uraniun ton rhc EtdtiltDg of uaaitm nsrrl a,rc fouad
I ar setcral FUSRAP $d5. Tfus *aste is clasc$od as lo*-llcl radietirc uasrc and is $ored or diryod of according to
J rmhcable fedsrd, sratF, rnd local regularioru and grirlclinc. Tls Deperutcar of Encrgr anncndy uccs both comgtersal
I Orporat faciliries and fdcral $tcs ro tlispor of rbe *anc. Tbc ceioarcd rcral volu-. dmsc ar &c 1]6 FUSRAP sttcs ts
I t.s miUion cubic metcrs @I
EacU ruSnep sue raiuires a sire.specrfc yaste miuagemeot flrirre$/ tha appropnately addresscs pollution sonuol; *a$c
'ucament, sroragc, disposat, and tnn-sporadon; iarcrface lEqurrencnls: and impleurenErion of nar rccbaolory. Pollwion'couuol mssrucs includr rsing vcuularion connols that capnuc firncs ard panicrdarcs insutlhg air cleaning €qupmeDl
mth a higtr dcFcc of oollecrroi e6ciew; applyirg uater iris to supprEfs irre Onriag onsnucrion aad deconranrnariou
urd rsing scdiraeorauon and eroaion ooaupls stch as srlt ftasio& hay balcs, srooc riprap, and vegcarive grouudcover to
c nrn oD aDd TtrloE
, TECTTNOLOGY DEYELOPAWT SACCE:SS
I
I
ncw wasrc Eeauneu rcchnolog7 anrrcutly bcing escd rrces tr s{-elshrng mrchiae ro scParale clean sotb
sorls conhmrrurad abwe Aridetiaes, rhcreby rEdrrcrng tlrc voluoe of wasrc requirurg ttisposal
tAP is abficryed ro wisrE muumizaUon o rcrluce rbe volumc of r+asc for disposal. This rcductiont.rhe enirronmcnr rnd reduccs cosrs. Aoorhcr exa,ruplc of rcchaologr developrncnr rs &c usc of a
mct.cnsbrng raachirr ro rcduce rhe arnou[t of ra$c rcquiring shiptacnt to a comncr]cittl disposal
tliry Burldipt nrbblc and debris are fed rhrough thc ruachine and rre reduccd rc r soil-lilc uetcrid that
a much to*er unit cos for
Uoder FLSRAP, eashlsire is rcrnqliapd to e staadard rhqt eea5i@6 possiblc fitnue uses for rbe laart. Clcaning up FUSRAP
sires nor oaty eliainalps porenrid hcaltb tr8urds and pruccts rbe cnviroruneuL but alto oay allw prwiost, runrsaDle or
rcsurcrcd proFfty ro tic renuaed to uscs that bcne6r rDc comnuairy. Ar stcs sleorud up ro levels rhat dlow uruesrrised
land gse, pcople can h,rc safely on tbc propcrty, driah narci too onsirc seUs, or grsw crgF or livesocL for food. At $lcs
wherc irturc-rcsiacns5 or agnorlnual usc would not h liLcly, rndusrial clcaoup sandards aray apgly, ary! {Fr_tnrr be
fresnaions on ho* lhc property can bc developed. Tlc D+ancnl of Errry nureuly csioars tal8ll FUSBAP sucs *rll
\be cooptercO W rhc yqar 2016, ar a ntal cost of apprcxinrrcly 32.S billiou Thc ovcrall cost ald durason of the prognm
tarc conlisrcnt nn& rhd 1995 e$matc. llowo/er, changcs due to rc<$madog thc sircs and rcscheduliag Ur pnonry of wort
mrhin 0r: progran bave lcd to diEercnces bcr*ccn the 1995 a^od t996 cstilEIcd costs wi6in cash srare. Thc followiag
hblic Prdciprdoo
Mclvssa Ne I
{23) 241.3315
ln,ln/o? rq la at
i
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taDle &?ic$ tlrcc &frcrenccs.
I
Couperison lVirb Previoug E*imrre
I I srrrr-l
-
Ttqnntr of DoBrn
lrralfr.l,anl|DlErnfhr lfiE*rr PorcrrCtr;
Corrrrcra 1-t7l 2:t321
-
.lJ I
UnDir 2-0IO L$q 33
MrRlrrn ,.D1 2r.493 H9
, Murrdrurcnr I 5.56t u.?62 ( lt)
Ml1prjn stt:20 6t2t7t t2
NanJg**4lt.7t5 39l.elt (6)
Ncr Yqt 3{9r{l nLoTe (J l)
Olrio 2Jt.S9.tt3,ru 1rl)
Bass cass co6l ssurrrlr+ and couplcdon daIEE in Ih$ Ba.sline Envimaneatal Manageurcor Rcpon suppon rtr prcsenl
scopg of repcdul actiou assuurptiolu based on plaas IDar rrc ormody uadcr reuicw aod o.y rccurrc iwisioa. For cxanpte.
th: planncd or propoead rcrucdics for sone siret havc not basl implcmeucd bcaau$ &cy nerc uor acceprablc to evctyooc in
thc agcflcd comlrntritrcs. Ttr DepanneDl of Enctg couturuas to *ort wfub Oc* cosununiucr ro idcnr$ rlErnagve
rclocdiec: cost csdmat$ may noed to bc a4iustad appropriatrly wlrn an ageeesu ia cachod oo rhe cleanrp opuon,
Selcniou of clcanup opporc ts taore complex at sonc of Oe larger FUSRAP siE6 &ar at slaalbr silce Sirc nanarivcs&r
&e lugcr, more complir 3it6 or troups of srtss (MayrvoC lrlrrllle*x Sampling PlurL ard Wapc m Nerr Jcrscy; &e foru
sitcs io St. louis, Missoun; thc foru Tonawarda Sirc propenics rn Ncrv Yo*; urd Vcouoo rn lt{assachusens;, inctudc a
&scussion of the ourcnr-ecopc assurnptions on *Nch rhe Basetils Envimnncntal Managemor ttcpon cost esrinares were
bsscd ald a Enge of cost estitrarcs associaEd with rcmedial opuons un&r corsidcr*ion. Tbe Depanmcnr of Encrry r
csrefirlly as8es$ng atternarve remedial opdons, including errirgsg tstitturent rcchmtogics, ionoiorive onrracunf
iururgemcuE, ttEzerd a5scssrnenl of inaccessible marenal, applylEt slcanup srarrdarCs for continucd in&fldal use, and
or[er approacbc to addrcssing envrronuennl cLalleagss morc rapidly aud cfiecrively ard at lets crpcnse rc dre rargayer,
wlule sult prouding a iemcdy dur prorecrs human hcalrh and rhc environmenr
l
FUSRAP ts dedicarcd t$ conrolling coits iud rraximizing productivuy and eficicnsy. A formd proEras is ia placc rhar
enoourages dl cmployets !o panicipar iu the FUSBaP cfioil to inprove productiviry, rc&roe c6ls, and iucreasc qulrty
aad valuc Thc FUSRAf Productrvrty lroprovcmcnr Prognm providcs a slsrcuratic nay ro quaadS cmploycs rudadva aad
ensues iDdividusl rccogniEon for asN*cmcnl Simc ts incepuon io 19t9, thc Producoviry loprovcoeru Program, rn
conluacuou with Ute Cost Saving Iniuasves Prograra has producerl docuarcnrcd sirytuEt of 374.5 million Thc frrll-ume
equvalenr pcrsonncl csiimatc for FIJSR.+P ts.pproxiuarly 30o druing ilr ocxt tlscr ycan. This esrimarc dcs not bclude
I{eadquaner pcrsonnel, or field subconracr labor.
t
DESCRIPTION OF PERSONNEL
i
Current Composi,hon
The surrent sca$ng reqlrUemcns ia rhe able bctow rcprc-ar trc sb[ mtx rEqulrC ro conduct rhc wort for tlc overalt
FUSRAP protratn Thc,coaranor work force is mosly a mrx of profcssiorul ard labor that plaas and perforurs rhe
remediaUon dilu vanci,ts ntes. The tb&rd sraf arc cagrrrert in rlc Oat Rrdge Opcnrioru OEce nanarive, Dcscnpuon of
Personocl sccuon. i
I Full-fimc Equivelcnr Couporirion Tebtcr
i
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tTt- prdrcerro fs Full-Tgrr Equw.ld crplcara lr br:d ql FY 1995 plrrral bulitE (a.c Eer(crrr Cnrroc!
Site Msnagemcht Smrcnrre
Tbe Depargneur of Encrg hucs conpanies tom rhc privuc sccror ro melegc ed perfqm FUSRAP acuvitrcs. As rbe
projefi taalatemcDr coDnitst,ri Bcchtcl Nadonal, Inc. oondusts sire iavcsigadons ad clcalrup ad managcs 0re field
astiviric ald oon$rucgon n cessary for remedial asdon. As 6e euvironulul snrdics coauaclor, Scicrs Applicauou
Inreraarioaal Corpondpn belps rhc DeDaTgIEu! of Ensrry plan stc iuvcsrigauons. evaluars cleaoug alteraarivcE alld
eusutts rhat all FUSRAP activiries comply widr enWonnenrat re4uircmeos. Bcchtel's coDlfircl is a progna managemcnt
conuacL while Scieoce Applicationr lntcrnauoral Corporauon is a nrppn *rvis congast, artd both luvc expranon dares
of 199t. Orher orgaaizarions, srch as OaI Ridge Nadoaal laboanory, r.hk B.idge Insrinrrc hr Scicocc and Erlucauon aad
Aryorur Nagonal hborarory provirle prcElarn tnanagcmc$ srrpport fiucrions rmluding dcsignadon aad vcrificarion
scrnces. i -
CON TR/tC tl NG o PF2RTWITIZS
you worrld lilte morc nforuauon about pcrformrng wort for tbc Dcpanocnt of Ena5l's Environmenql
at this srtc, plcase conpct:
COMPLETED FUSRAP SITES
;
Since FUSRAF began, he Depannenr of Energr has cxrmrncd rccortls or prfornal $weys oD motc thar 100 sires. To
dare, {5 Elrc6 m l{ sarh have beco designarcd for imlusion in FUSRAP. nr Depnnncot of Eoergr bep l lieitC clEuluP
ar some $rcs ra 1979, dnd n4pr re.arerliat asdon bas ben uaCs v.y nBce l9tt. Thousaods of cuDic yartlr of tadio.sive
marcrial have bccu rcriovcC ftom rcsidrndd and commsrsial proFrlrcs tnd slorcC at the Depanmeor of Ensrponsolled
and morurorcd iucnm Foragc sires in !'{ayrroo4 Middlesex and hync, Nar Jerrcy, Coloaic, Net Yort; andl{azelwo4
Mssoun. ftc pepanmcnt has conpterC clenup al2l of lh. {6 FUSRAP $Ict oalioDwide (s€e map). Infonuation ou
cooplcrod sircs s suoftnzcd m thG lisugg by starc bslorr Scsrious oa iudividual statcs discuss &c zuSRAF sircs thar arc
curreuly asrvc.
I
ICalifomia r
a,pd Conrracrs Division., AD-42 Uuitcd
ral Ridge Opcradoas OGe
.O. Box 2001 i
aL tudge, TN 37t31{?55
: (423) 5764195 f: ({23) 576-9tte
rntl Conncu Division., AD-{2 Udtcd
EL Ridge Opcn6ous OGee
.O. Bor 20Ol
Ridge, TN 37t31{75s
Jof12 t08,0t91 t9.t2'45
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Universiry of CalifornA Be*eley, Ca
I
t.lrlt, lercrl * *.Uqr.nrry_of Califonua-Berketeycanpus. rus t[e src of auctear rcscarch involvrng plurorurrm
and uranrum tn $PPon of !,{anhattan EngrneuDrnncUAtomic Energr Comrarssron aqrviric drurng rhe lga6s]'
Rcsearchen bombardcit small amounu of rrrani-usr wirtr cycto-u-onaroduod ocuuoru ro produce minire quanriucs of
pluronirrm. Rarliologidt $rrvcys in t975 ald lgt t ruroer FUSRep'idcntrfied lo*.lcryet rldroar:nvc conrrnrnadoo in scvsral
areas of thc byldrns,, i*,iy all of dre conraminarion rcsulrcd from uraruusr compounds tar h8d ser[ca ia15 Amrs anavatls. A fct, lctions conBtlcd higben<ucrry gamna emiccts. Thc Depanmeai of Erurgr ruiriaicC rmedisl ast;o(ucluding decoaarunarion, removal, ard shielrlint) iD tgSl and complcerl rcmcdiarion of aU mnUraa EagnccrDEria-rclaEd ra0oadive coaunrinedon iB lgt2 A toBI of 23 subic mercrs (30 cubic yards) of tow-lcvcl ndoacrive wase
was shippcd o lladorfl for Osposal.
I
Conaecticut :
I
Seymou Specialry Wirc, Sqruoru, CT
Septoru Spgo.tty lYirc rn Scymou, Connerricur, is a 2{.hecrare (60.acnl sirc lered on Fran}tin Strcst aloug &e wcsr
sjtlc of tDc Naugatuck Biver qd jun nonh of Slarc Route 67. Reasivc l'{eala, Inc.. a ruDeirliary of Bridgepon BrassCoapsay, larer known'as tbc Scymonr Spcialry wirc Compely, forucrty eupied rhs sic. from 1962-rd lr6a, RlagsveMcals rrc€d sls buil&ng.at rhc.sre for rlc*elopgcnalcnnsion of nanrnl uraninn utstal ,rndcr ur Aomic Ercrp,Connission coutlrEsl and for rclaroC asivitics Ora rncludcd urarlu& ruacbrning $oragt of radioactive mareriat,-audanatflcal suPPgrt Charascnzauon of tbc bruldias confirrncd ilni urauun ana iu rlccay produas *cre &c prirnary
contarunarBs. ReEedi4l rtion was complacd h 1993 undcr ao crpCrrcd prorcol urd consr*cd prtearily 6f Urutiias
sttrfacc deconemuauoh rvi& sorne milor soil cxcavauorc. In 199i, 2t crldic rmtenr tf Z crrUic yartsl of lor-level
radioasivc wa$e sas $anspond ro Envirmre dUE! for disposal
Iltinois i
I
Granirc Ciry Sreel, Gnprc Crry, IL
The Grarute Ciry Srcel stte, arreruty o*acd by Naronal Srccl Corporarioru is tercd u l4L7 $arc Succr in Grznire Crry,Illinoir aonheasr of &e Missrssippr River urd acrps Oc rivcrtom Sc. L.uis, Misorui. Frcm l95t lo 1966, Cnneral Srcct
Casrngs Corporauon (rhc previors sitc ccupanQ x-rayed uraniun ingou for [re Atomrc Encrg Cornmrsspn under
purctrasc or&rs isarcd by MallincLrodr Cbcmical Company, a prime &omic Eoergy Commission conracbr. Thc sue
inclutlcs a nuo-sloty mo,al and concret€ building wbere uraniuB u€oLs wcre x.rayed, x-ny Etm rras dcrctopc4 ard rrro
EoverD.Benl.oe/ned betluotu lmagnaic mdusron elecgon acselerarors) wcrc bouscd. Badiologicrl survsys rn l9t9 urdl99l denufied small aEouDIs of residual radroactivrry rn seryeral discrtrc arcss in rhc buildrng. Tbe sirc was
decontamrnated in Junq 1993, and 1.5 cubie to$crs Gwo cubic yu&) of low-level Edioactve rre$e wils uaasponcd roEftirers of Utah for Sisporl.
i
Nauonal Guarcl Armoq, Chicago,IL
Tbe Narional Guard ^r*" is letcd ar 52nd Sscq and Coaage Grovg CNcago, Illinois. In rlr l9a0s, 0re L{antraran
Prolcct tcascd the nre fiom the Snte of llhnois for uraruun prcessiug and songe of radroacrive marerial Tbc srrc was
rerurncd ro rhe SBre of lllinois rs 1951. DuriBt rlte tgtos, riOotogical survcys airt charastcrizadon idc1dfieal rad.rouctivc
conamtnarion in thrcc smrll arcas on Oe gruuds on soaE iorcrior hulding sur&ccs, and in sludgcs ftom thc carch basra
sy$ss& wNch were alsg fourd ro conain Rssosce Consepadoo Rocovcry ncr bazardors chcmical consnlgns.
Rcmcdrarion of radroacpve conaurinadon (roulint lt cubrc rnsrcrt 12{ ct$ic yantsl of low-lcrel radioacuvc tra$e) was
complaed in lgtt. In July ard Augux lgtt, tarx€d wa$c conuuBsng rgnirablc Rcsourcs Conscnauon and Rccovery .tcr
heza'dsus w8!ilc was ucatcd to rcBwe tlre rgnrnble chancrcrisric. tg *as drcn shippca ro Argourc Narlonal taboralory for
lntcnlt sorage Xfor; d;l drsposl at thc t{anford faciltry iD AgrU t9t9 atong wirh rle otber radioacrive wlstc
Universiry of Chicago, Chicago, IL
6efl2 10r30t91 19 12{7
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lbe Uaiv_ertrry of Clucago sia includes scvcn buildingr Cnc net Cheursay labontory and Aaaex, Wesr Srands, Ryerson
Phyrrcal laborator], EcLna[ ]IdL Kcnr Ctremrcal l*boretory, Jones Chcnical kDoraiory. uld Rickeas Ubonroryi :har*tre assctarcd witl Manhara! Engrnccr DinncUAromic Enerry Commissron nuclear researctr and dcrelopm.o, [.ooo
1942 aDd 1952. Whcn Ihc !{anhanan Enginctr Drsns/Atomic Eo.rg Comnussion oFr.Eons at Oc rrarveiriry ccascd. rhe
Ecitirics wcrc tlesonainilutcd to meer hA$ and sfcty cnrlta r[cni e$ecq ana $a'6rst-tlrr* buillings *.niitrn*,,f.a.
Radrologcel $weys ul tgzo a$d 1977 ideodfied rcsutnal radioactive coneminarion in rhc rEmaining foir Uru6ings. fnDcpanoeutof Encr6r oompla{ remediarioa of mos onsia radiouivc coDrErniDarion in 19t4. ID litz, Ure Dcpaimenr ofEnerry condustcd clraraserizarion urd remcdial rction for rbc dua sy*em of 0re Joaes Cberucal lrbonrcry Rjmcdrauon
rras complered in 19t7. a roal of 34 cubic mercrs (4S orbic yuds) of lou.lerel radioasrvc ryasrc nas shippod ro Blanford for
disPogal. Thc cnifcauon dockcr rclcasmg thc sircfor usc wul oo ttdrologcal resnicrions vas is$r€d rn l99o
Mrssachusetts '
i
Cbapmaa Valvc, lodiah orcfur( It,[l
F! Ch"pPry-Valvc strc is lmlcd in Indian Orghar4 a stqry! of Spnngfel4 lv{assachrrsens. The Crar Compray, which
had eupiod *f |i* lpcc 1959, vacarcd thc buildiagp u t9t7. Druiog 194t, Chrpoaa Valve engagsd ra a prigri;
involviug oacbiahg of uraruust roCs for Eroktravcn Naioml laboruory. Ururium oFrations rcrc rernrinircd
io Norcmbcr t9€. At tl1t1 doe, Chapman Valta pssesed aorc thaa l2,l5o litogr.EE (27,m0 pouds) of maal scrap,
oxidca aad s*tcpiags. This maarial was rcmovcd from rhe sue s:veral mosths afier rhe conrrrst vas conpler4 urd rie
building vas dccontaminacd rc sandards rn efiect at drc rioe. A l99l $r"c, coadusrd by OaL Rirl6e Naironrl kborarorl
indicated dut tDc rtndual ut snrm couranrinauoo .t th. site excceded rdayl morc $nDg$t clcanup cnlena and \r€s
ry?ical for lvtaabanan $nginccr Di$ris/Aroaic Erurgr Cornnrssion opsarions.
I
The Depanment of Energ coaducrcd sirc ctrarancnzation in la,rc 1990 rarl arly 1995. tD Iuly 1995, rr begrn reruedial
acdon-" *htch consst4 of removal of conenirratcd masedal by bnuhingrrrrtting aad vacuusring- TbB Dcaannsnr
coutplctcd rbe rcmedial acrion in Augut 1995. h shippcd a rcat d 15 subic trcrcxs (20 crtbic yarOsl of low-leccl radiorrive
ua$c to Envirocarc of Uran for rliryosal.
Michigrn
Creueral Morors, Arlfiad" MI
Tbs General Morors srre consisrs of a targe manufassruing plaar lered ar l{50 Bccctrer Snecr ia Adria[ Michit31
apProxmBEly 4t hloulaers (30 mrles) nonlrsest of Tolcdo, Ohio, ald J6 kilopern (35 Eilcs) eoutbwcst of Aln Agor,
Mictugen The plutt one of many tar& huldrngs lcatc.t s rDc Gencral ![otors complex, orrcoily graau&cuucs planrc
Parts for automodve o[ utrcL drvrsiolu urd employs toorc rlan 1,000 pplc. Durhg rte l940sr rhs sirc *as opcrircd as an
aluanrum enrusion plqq Ehil rude parrs for rhe U S. Arny Au Force. The Bridgcpon Brass Cornpany, a diviiion of
Nauorul Distllen and ehcmical CorponEon, oprratcd rhe plsDr rro&r oouras ro tr Aromic Encrgr Conmission in the
1950s. OFrauons uclrtded producrion of uranium fucl etemens for 6e llanford and Savaanalr River planr rcacton and
developmcual cxtrusiop work on thorium aod dcplctc4 natttral, and digbily caricbcd urauum. lv{ania Marieaa
Corpondon larcr ormed Oc srte. The crurenr oeuBr, Ctrqtolq Maanfecturiug Division of Gcncral lt{onrs Coryonrion,
purchased rhc sire ia 19.?+.
Connrunedon consi of uranium rcsrducs logrC prerloninaorly is drau lincs benca0 rhc &ci}ry. Earhcr ctcaaup aod
dccoauarinauon eEors removd tbe n4joriry of thc contasunation ar rhc fasitiry. Connminared clay pipc uas rcnoved
from undcr thcEel = -'--'.: ::xrp area in thc nid-l98os: s*erd dnros of couraninercd ruarcrirls wer- rransponed ro ldeho
for disposal uatb the onirtc assixancc of Argonnc Nauornl Laboratory. Pactiog and shipprag eostE wcrc piC by rle
Depanment of Energ h 1995, the Depenmcnt of Energ condused addirional rcncCial rriou consiaiag of
dceontaminarion of drah pipc, Soorr ard srmpr. Wase gsnerawrl rtging rhc drronranriDalioo etroru rasllrdld
dcoooraminaion waBr fnd oonnmiaarcd onp oils and oily sludges. Wasre nininizarioa urd cos eaviugs iaidarivcs
trrludC tbc ttsc of nrgitcmenal slandar& for buncd dninlins and former cnnrsion press piu, rhe onsire uetacil asd
relcasc of dcsontarunadon wawr, asd Oc solidrlca0on of oils aad durlgcs Clcanup bcgan in April and ms oooplercd ia
July 1995. A rotal ot22l crrbrs nctcrs (175 eubic yards) of low-lwcl radroasrive vase uas shippcd to Envryere of Uah
for disposal.
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New.!ersey,
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Kcllcvherpoor JerseY CitY, NJ
!
The Kellcx/Pierponr Sire ls locard ar $s uErtcston of Nct Ja:cy Roure 4aO and lkllofs Sucet in tetsey City, Netv
Jcrscy. This sirc onpnally consrscd of appronmatcly 17 tstarcs ({3 ases) srth morc tttan 20 buildings. Thc }tttW.
KeUoffi Company esraUtrshed tbc Keltcx Corporadon as a aSsidiary iD 1943 fos drs PttrPos of dcsigntng rud cotxnrcung
rfrc 6fr'sascdus Ofiriion uranrum cruich.srcnt plalr (oc K-25 Planl iu Oak Ridgc, Tennesscel utder consact lo ttre
Manhanan Engner Dr4ncr- Wort for rhe lrrtanhanan Endrpr Drstncy'Atomic Energr Coroaisioo drung tbe l9t0s and
earty 1950s rnit,rd.d reecarch and dacloprocat of fud rcprcsulg and omponery lesllnE wirh uranrum trcxaiuoridc as
wcll as dr:velopncnr qM usc of uraniun presitg ald rccovery Echoiques. In [95 I, the Viuo Corpora0on of Amenca
assl6erl atl rhe righd and obligedogs of KeUex. Tla eromieErcrgy Commrsioo cosuzct rvort rras Osconunucd a thc
Ier:cy Ciry sr iu 1953, and rhe laDoruoly building whcre moS of thc AIoEic Eacrry Commission wort was oon.ltactl
yu iecorianinarod utd dcmolrsbcrl. All othcr ongrul builCings *erc dso sr@usnily demolishcd. Jerscy Ciry and
Pierpont Ass6iagr, tnc.. tarer pruchasat poluors of rbc sitl. Varioos brsinesser aurently Gtlpy thcru Radiologrcal
"*ryr and chars::-i:::ion rn 1977 and 1979 r&ntrfed a auubcr of areas of aboc+a*g!0tt[d radioacovtgy in thc
oonlrlra urd rresrem,Fruoos of tle ntc. ad t[e sirc was asslglcd to FUSBAP. TUe D+anrtcnt of Encr8r coopleted
rcmsdial rcrioq consihng of rcaoral of ccntsrtri.oalcd soU aad Ctrir io l9tl. tt sNppcC a roral of 20t cr6tc osrcr
(273 cubis ylrfi) of ten-level r.dioasdvc w.src to Barawell Sowh Casolitt , for dinoal.
Mddlsscx Mutrisipel lrtttEll, Mddlccr' NI
The Middleser lrr{gniCipat t rdfll sire s letcd winil rle Borougb dtr{iddtescx ra Middlc*x Cornty, Ncw lcrscy, -
approximarely 25 krlorircrers (16 rnrlcs) rou_rhwes of Ncr6*" Tbe sirc consisl,E of approxuarU olE hccare of a lS'bcnarc
(ihrec acres o?a 37.acre) unimprwcd taDdffl rtra was uscd &om l9at to 1960 for qisposal of pzstc from tbc Middlcscx
ifunpfing Ptrnr, locaricd one kiiourcrcr (0.5 milc) ro dr south-sotth*tsr I! t960, elcrarcd tia$ura radndon levels
anri6uraUtc to conrarqinariou m rhc sorl uursponcd &om rlre Middlcsex Sanpting Ptant were &tcstcd ott a ponion of the
Mddlescx Municipal,hndfilt sire; rhe Arcmrc Eucrgr Commisstor rsmoved ap$oxrltEEly 495 cubic lDetent (550 cubic
yarcls) of con6nunu& sorl o thc Nar Bnrnsrick Iaboratory in Nclrr Jerscy. A cbtuJh-wa, coastnrdld il 1963 oa a-r*o,necrare (fivc.acr() par,cet of the fonner landfiU propctly. Badiologrcal sufte$ i! l9?4 and l97t idcmitrcd a
conaninatcd arca of'aiproxirancly one bcsrare (thrus asrcs) bor&nng als_llrursh ProPcrt![ thc primary-cooaminanr was
,aAiun-ZZe. wrtr tessei'amorurs oiuraoium.2lt. The maioriry of tbc iand6U silc renaias rhe properl of thc Borougb of
Mirldles*. i
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The Middlcscx Munrcrpal LEndqu sir was kEtudEd i! zuSRAP in 1980. Cleanup of radioacrive coaraornauoa at Or
Middlcscx Mgnrcrpal t:ndfill, *Nch coosisred of excavrtion of contamrnared soil, rvas ininat'd ra I9t4 uttl complaed rn
tqCe r toral of Zi,g24 cubrc mctes (3l,2t0 cubic yards) of wasc was gencnrcd drrring remedial acuou and plrcd h
inrenm *orage at thC Middlescx Sarplins Plail
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New Merico
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AcrUhcblo Canyonr Los Namos, NM
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Thc Acid/hrcblo Cadyoas sirc ia las Al3mos. Ne* Irilexico, is a Inlf-bectarc (ors8c-re) are borgrdcd W a rcsideusal
orbOirision and rlre rb*n of Los Alanu, wbsrc deep suryorc rere rhe discbargc area for urureatcd radioscrive ltguttl
,*snr from rescarcb The $E nas rhe legon of rf,c te-rS wasrc Etatmcnr plant and *as owred by ths rYrr DepanDepanmenru€srel from rescarcb The $E nas the legon of Ua TA45 wasrc Etelmcol
aruing Oe iniUa Friod of wa*e dirposd. Io 194?, cougol of lbe tan&s uar ransfenC rc rhc Apmrc Enerry_ Commisston.
en*?rr*"ii*riuqn urA dccommissiorunB in t966 and 1957. omesNp of rbc Ecatmcu plant site, Acid Caayon' and
rhe porrion of hrSlo Cenyon easr of Acid Crnyoo ras rrandencd ro las Narnoc Coqnry
The Dcpansrenr of Encrg complercd reracdiarion of the radioacuve conruoinarion in 19t2. A lolel of 29t qrbtc mcrn
A9o orLic yardsl of iowft;"er riOoastiyc *a$c ras gcocrated druing rcuradral acrion; all coatsrliDa,l€C nerenals gcrt
Irp.r.a if.iiou eij1oos Narional l*borarory Radi&sive wase Digosal Alca G G.s{). A6oal ccruficadou dckcl
ccniryiag &ar r[e slqe wEs u compliance wiD applicable radiotogical Si&tinEs rras issred ou Auguil 2t' l9t{'
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Bayo Crayou tas Alfnroo, NM
The Bayo Canyon siG u los $amos. Ncrr lr,tcxico, tr lgted m los Alamot asd SasE Fe counrics ud is borraded by
Kwage ltlcsa ro the nu\ Otona lv{esa ro thc north, urd lhc TomsNp of los Alamos on 0r rre$. Thc Bayo Curyon srrs rs
a &hesare (l S-acre) rrase brural area t0 kilomctcrs (25 mtles) nonhnes of Suta Fe ard 99 blomean (62 mlcs)
nonhcast of Nbuquequc pbere dcbns from dcconrarrurnauon aad dccosmissioning of buildiot", ssrcr facrlirics, and
strrface arcas *irs Ospose4 Ttre U.S. Crverunent owned rhc strs from 1943 w 1967 and ongually uscd rr for cxperinens
mvolvrng convenilooal hig! explosives urd radioacrivc souces in co4iunaion witb nuclcar weapons dcrclopmcnt On
July l, 1967, the Atotptc Encrgr Commsson un*rcctssfirlly acsmptcd to trant'er land for nncondruonal u:c, rnslrrdrng rhe
ponion lercd in So'i. Fe Cou$ry, to thc iocorporarcd counry of Los ,+lrnos Thc l)cparsnenr of Encrgy complercd
remcdiaionofrheradioasrivscolramiturdoninl,gt2 Itremcdtarrlatoulofl,160suhc&crrs(l,520subrcyuds)of
low-levcl wase and dFiSlraled it to rtrBin u sro.
Chupadcn Mcsa, Whirc Sands MssrlcRange, NM
Tbc Chupadcra Mcsa,utc ls pan of Oc fallort arca froE tlte fir* anmic bosrb rsr condusrcd for rhc lt{aalraran Eaginccr
Digricr on IuIy 16, 1945. er ths Whirc Saade Provrsg Grouade ia Nctr l,rGxlco. Thc Chupedcn !'{eca are was aad
conusues to be borh pnvately and pblicly owled. The arca is used for nisirg canlc ud produciag alfrIh tnd row crop.
Easd ou results of a ndrotogical srr,rvcy prrblisbsl m [9t4, the Depanmnt of Energr dEremdncd rlar rhis sitc rlid nor
requirc radiological ramdial Ecuo&
New York
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Bats 8!d Wilharas Wartbouses, Neu Yort, l$f
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The Baker aad fVrliams Warchorses flte consrsts of 0ucc a4Jacent warctrouse buildings oo rhc rrcs sidc of cearal New
York Ctty. Druing tlrJ earty 1940s, thcas narehouses were uscd by drc f4anluuao Enginccr DixricUAtomrc Erargy
Comraissioa for shon-rrm sor:rge of uranium conceRuares produocd in Pon Hope, Canada tou .dticaa orcs The
buildrngs iu? tuue, seten, urd eloen stoncs hth. Each burtirng has a bassmsn:, a roel area of t2t squ.E rDctsns
(9,200 square feet), arid is consnqed of fueprof matenals includiag stecl, soncretet asphalt renir-corra, and brid( A
vancry of rnarenals, iqcludrng palnl succo, plascr, and a black foam marcrial corercd tJtc nall surfaces. Wrth few
excepuorur. tlors arc irurenrlV uscd for srotilgs.
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Oak fudge arso"rarci Uarversiries pcrfonned rltc rtesignarioD srvey in l9t9 aad dereced rcsidual radioacrive material rn
excelrs of gurdchncs on the 0or urd lowcr *rlls of the eag W of Oe hesemcar and oo over t0 petccnl of tlu ures bay Erst
flor area u one of rhf rhree *arebous6. The dcsguarcd rarchorrsc *as rcncdiarcd and verifid io 199t, and tlc wrr
genenred was stuppeC to llanford for &spocrl. Duriag the rrund dceignauon $rrer, De third *archou:c was not
accessiblc Wlren access was graorcd in 1991, the rhird warebouse was also fonnd ro connn residual ndioarove matend
above guirlcUnes. Cte4up of rhe thud warehousc was completcd tn August t992, a&l Oc uane wcre shpp€d u,
Envirocare of Uratr foi drsposat. The remcdid action gencrarcd a nnl of l0 cubic mctcrs (I3 orbic farls) of low-lcvel
radroacrlve **., *hl.b was Ospoecd of at liccascd outd-sur rlisposal fasiliric.
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NiugaraFatls Storagc Site Vicinlry Prqcnies. l,erison ].IY
Thc Nragan Falls Stoiage Sitc is a Deparrrncnt of EucrE facility loted io t evisott, Net Yort, approximately 16
Eitooerers (10 miles) Ronh of Niagar Fdls. It rs cunendy uscd for noragc of raAoasive residucs, soite, and nfible The
$rrc rs a rconanr of rlrp U.S. Army's orig[ul 3,036-hccpre ( ?.500-acrc) [a]e Ontano Ordnance lYorls, ponrors of wNch
ncre iruended for useDy rhs Amy for T}IT producrion early rn World War II and later wcre usod bv thc Manhanan
Engncrr Drsna for irorage aarl na.osshipmenr of radioacrive matcnals. As a rcsuh of rhc stongc opcrurors. othcr
ponioru of rhe forgledl:ke Onrano Or&raDEc tYorls also bccarne contaminarC 8s some of rhc radioasrivc rnarcrids $orcd
at &r sirc nigralcd av-ay from dr *oragc ledorc, pnrnaruy rhrough onsrs or ofrsite drauage ditchcs, as &c result of
watcr and wird crosion. eicr ilu area of rhe strs was rcduccd froa 3,036 hcctarcs (7,500 asr6) b thc 77 bcdarEs
( 19l acres) currendy gcctprcd tU thc Nragrra Falls Storagc Sir, radioasdvely coaramrnated arcas a{acent to or nca, ths
sitc werc rdem.rl ro al rhe NiaglnFalls Storagr Srtc Vicrnrly hoFnics. 8IoEl of 3t,l6t cttDic neret:
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iEP //vt* ctD.Oc tot/bcmdo, tlrsrrp.lulrt
(50.000 orbrc yards) otlow-&cvel wass. pbtch vas disposed of by placcocnt in an entrrctred nas These 25 propcnres
cover aploxuallr J26 trcstares (t,30o acres)
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Rcmcdial acdon for thp Niag,ara Falls Storagc Sitc Viciairy Propcnies, coruisung of clearuag ald rcflonnt ofrsite orarnage
dirches and cxcavaEng conaminarcd sorls and rubble, was completed in 1985 The clcanup gencratcd c conurtrmenr
$rucrurc ar rhs Nra;j-:alls Storage Srte.
Ohio
Nb. Crafr, Ofor4 OtI
Thc Alba Craft sire, tobar€d ar l0-ll Wea Bo* Avcaue, Odor4 Ohio, *as ur operuing mrlune shop where uranium
slugs wcre machiac4 fhc foraer Alba Croi laboratory facility nas a U+hapodbuilding (open on thc soutlr srdc), wrrh a
total area of approxrmlrcly 530 ro 720 quare m€rers (?,000 to t,(X)o squrrc fcsl).
From t952 to 1957. Alba Cr.fi prouded a variery of machiu shop scrncce oo uanual uranium orcral for NaEonal [.earl
Company of Ohio (a pnnrary Abmic ErcrBt Comnission contncror). Earty nort inslu@ $Derd aod developmend
Etachiling of 6rcad!.1tcasror firct slugs for usc ar &c Depsnncw of Eaerg/s Savaalllr B,ivttr SiE. Sub*$Enl
prdrrrion-scale opraious corursrcd of hollow dtillitg and nrraing of slugs for thc Salalnah Rivcr urd llaaford rcasors.
Dutug machining opqrarions, equipmenr ud pnlons of the buildin8; grouE$ and four viciniry propcnrc bocarrte
cooaminarsd *rth t*i lcvels of ,adio8ctivity Aficr Atomis Encrgt Cornmission operadoru cDd€4 he qrc was
rlecootanirurcd to Ecet gut&Ults then in eficcrt-
In t992, rrdiological clurascrizarioo rcvealcd Esidral uraniua conaninaoon of tDc 0or, rof srppon bcsss, rnd draus
and in r*o isolarcd arqs ourdoon. Bcmcdiat actiort which includcd drcontaminatron ard derolirion of Oe l&ruory
buildiag dccouramrnairon at vierusy propcrtes, aad excavuioa of coaumioated toil, nas iniuated ia Augusr 199{ aDd
complacd rn Febnrary,1995 Tbe cleanup gercratcd a nul of 2.394 qrbic ncren (3,136 oDic yards) of los-le,r/el
ndioasive sase, whicb was shrpped to Eovirocarc of Ueh for dispsal.
Assocrarc ArrcralL Fairfel4 OH
Tbc formcr essociarc lircran fool urrl lvlanuecnrrng Company hluy, aa opcrariag aachrne slnp *rrh a loEl area of
appronrEtely t,t@ ro 2,250 quare mctels (20,0m rc 25,fiX1squatc &.t). is letcl at 3660 Dxie Highway, Fai6cld.
Otuo, ncar Crrcinnari.;Thc hulding E a ors-$ory rD,Ltouy blat snrctue yhcrc Ascclate Aircrrfr trachitr€d lnllow
uriuuum slugs for thc tlanford aryl Wannab Rwcr reason io 1956 tttdcr coouag !o 0tc Aloxorc Ensrg Conmision ano
Nadonal l,.cad Compa.ny of Ohio. lhstorical rccorG nole &ar thc machnrng wort ms confasl to oac ponion of 0re
building; rhc ponion ol the sirc rlar was us€d in uruliun operilioru has not bccn $bsEutally rcuodeled. efrcr rhc Atomrc
Energr Comnrssion oprarions ende4 Oc sirc was deconuaururcd to Ectt g$lslincs thcn rn cficcr
In Junc 1992, a radrolti.gtcat survcy vcnfied tbat urasrum couaminauon wrs Dot prcscnt on Oc fioat ponron of ths propeny
but rndrcatcd cooannuriauon in csnsete orpansion joins anrl ou the upper $ficc of tof supon bcans Io Seprember
1992, a radiologcal suvcy of the remarnder of tbe propcny ideuified addirioaal ttcidual ruariun iadmn.nd limirC
connrnrnadoa ousrde the buldi'!8. Rcudid acrioq urluding building dcconemiaadoq, crcavadon of couamuated coil,
drau lracs, ptpug, u{ deDns; and removal of leadsutaiarng painr utd asE$os Omr dte+ was iardercd in Dcaembcr
1994 and compktcd iri lrtay 1995 The clcanup gencrared a roal wasre volumc of 125 qrbic aclcrs (16{ subis yards)
(iocluding 122 cubic melen 1160 cubic yardsl of low-lcvel ra&ogmve kasre and I crbic tnErers lforu obic yarGl of rured
wrstc), which was st ippe0 rc Envrroca.re of Ulah for drryosal.
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H![tlt Safe Co..lhnultou OH
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The I{HI,{ Saf,e Co. UuitCng in Hamitroru Ohio, is z.large recren6ulu buildfug that was uscd isErudrrurty rn macbnrng
ruauurn slugs from unuum billes rn the 1940s and 1950s rrnrle3 5s!p669161to DuPoot asd th. Uaivmiry of Chicago in
$ppon of lvlanlranan Engneer Disrnc/Aomic Energt Comnissioa *ort. In l93t E rd 19t9, radrologrcal nuvcys renfed
rhar radioasrivc connrninarion lgl bscn rcmovcdfrom rhc 6rs and sccood 0on druiag previors dceonamiaadon e8ortr
l0 of 12 1nr16,97 ru tJ (0
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Horcver, a survey ta 1993 idcodfed areas of cooramirudon above gurdeliaes ia pontons of the 0oring aod walls m many
areas on,Oc rlurd floof of thc brutdtng. Retncdral acuon" *hch corunpd of build$g deconramuugon mvolvrng rhe rhrnl
tlor, rncludiag removal of sesrioru of floriag coouroing lead urchor bolr sleeres. vas iniriard ia Deccmber 199{ an6
omplercd rn Fcbnraty I99J. Tbe cleanup gcncratcd r rcuI wasre volurne of lt cubic merrs (23 orbrc yards) (iucludiog 15
crbrs metc6 [20 crbic yardsl of low-lcrcl radioacUve naste and 2 cnbrc mets$ [3 subic yarrlsl of mixcd uasre), *hch nas
sHppcrt to Eoramcare of Utah for drsposal.
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Albray Rcsearch Ccnrcr, Nbaay, OR
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Thc Albany RescarchCcarer sirc, letcd in Albury, Or6og u aa lt'hcarc ({S-acrc) parUatly fcnccrl areawi$
39 bul&sts wbcrc rhc U.S. Buceu of Miacs conduecd maallurgical oFftutoos involving trantnl radioacutc marcnals
berwcen l94t ard 197t. TIte slrs ts bouDdsd on tbc uonlr by Qcca AvcBug on rhc wc$ !y Brord*ry Succt on rhc casr by
Lrbcrty Strcsq asd oo rltc sourh by r tauis club. Thc Fcd.tal Govcrn&cot ovos tbs burldings ard the AJbany Rssearch
Ccntcr conuols rhem.
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Frosr l94t ro 197t, tlp Bunau of Mises conduacd mcallurgi(A rcs€arh Oa iavolvcd rrcltiug, machning welding and
dloying of uranium and rhoriuo for rtrc Aromic Encrg Commission ard tbc Eaergr Rcsearch and Developocnr
Adatinislradon: resca{ch on alloys of uanrurt and thonum began in 1955 unde, art Atomic Encrp Corasrission conuas.
At various rimes dundg these operuions, prsess bul0ngs urd srrounding areas sere decontauunared o mcct grudclrnes
Oen rn e6ccr A radioiogical asicssmcnt rn tgzg aart rarliologc8l ch8ractcrizadoa in lgt{ rndicarcrt UE nccd foiaddrsoual
stte rempdiauon.
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Ptusc I of rcatediat airion under FUSBJ{P, conduscd in l9t7 .!d lgtt, rnchdcd hulding dccontaninarion, cxcavadoa,
baffltiag and scedinE of excararcd areas, and sansponadoo of 2,290 crbic mcrcn (3,000 ntbrc,"d0i) of soil urd rubblc
ro rlre Dcpanmcnt of Encrry llanford Bsserarion for disposal. During remedirl asriort norters founC polyclorinarcd
biptrcnyt conanuudon u aa ousire limc pt formerly uscd to st cgar bcar? mculc from rragc rEsiduB. Addruonal arcas
of nadioacrive conraminasoa excceding gur&lincs (prinerily io building iulas not ptwiorsly orycycd nndcr FUSRAP)
also were rdensfied rn lgtt: thcsc arcas rycrc tctEcdiatal i! l99O urd l99l drrriog Pbase Z of rbc clcanup A toEI wa$c
volurac of 2,t57 cubic merers (3,7{3 arbic yuG), ncludmg 2,t17 cnbic meters (3,690 orbic frds) of low-level radroacrive
wase and 69 crrbic mqrers (53 cubrc yards) of mixcd wast , wrrc shipped o llanford for disposal. | 6n'l ccrtrficauon dockct
ccni$pog rhar rhe sircris u compliancc wrth applrcable ndiological guidelines *as is'ued iD April 1993
Pennsylvania
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Alquippa Forge, Niquippa, PA
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Ths Nrqurppa Forge $r, locapd ia Aliguippa, Pennsylvania ts r 3-bEctarB (7.5-qc) nts lcarcd just west of thc Ohio
Rjvcr. [r is bordercrl of rhe easr B Beaver Aveouc a$d ou thc Eouth by Fr.rsr Srecu ln rhc lap l9.t0r, UE Alomic Energ
Commisstoa operarcd;a rolUng mill. two fi$races, and cuni$ antl exndiag equrpmeDl for sonvening uranium btllcts mto
rods at tbc srre, wbichrwas owacd by rlre Vnlcan Crrrcible Stccl Company druing thB Atomc Er*rp Cornmrsrion coilrast
psriod. [a 1950, rhe si[e *as dcconra,nr:narcC to mcst gnidcliocs thcn io cfierr. Tbe crurefl sire o*let is the Bcaver Corrnry
Corporauoo for Economic Developmeot"
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ln t9?8, a ndiological suwsy r&ntrficd radioacrivc coaamiaarioa excecdiag curEil Ru&!!no on flors rad *alls of one
ofthe onsrtc burl&ngf oo overhead beamr above frraaces fonucrly uscd to hcar uraanua bilters, aad beside the cooling
basrn ousr& rlre burldrng. Thc sire qas includcd rn FUSRAP ra 19t3. The Oeprnmcnr of Ener6i cbarascrizcd a ponion of
rhe sue rn l9t6 ard isi l9tt rr condrrcrC aa inrcrin remCral rsrion in tta building rhcr radiordivc coouminauoo tud
been r&nrified. Wascs gerErard Uy rhs phasc of remedial acrion were shippod o thc Dcpann nr of Enarg rlanford
facrliry for dispog. Thc Deparuneil of Enerry er€cred r fsnce to enclosc a poruon of UE tcmcdiercd htildiag and prcvent
acc6s to ucai whcre coilasrinadoo exceedcd applicable clcaaup Aridehrcs. Thc sccond phase of renedial acuon
(inslu4ing addirional builrling dronramrnarion and erqtvauon of sorl and conctae) was inidaed in 1993 and completed m
Seorember 1994. The iorat volume of low-lc*cl radioocrive wa*e remediatcd v"s726 cubic mecrs (951 orbic yarG). Thc
rorh urcturlcd 3aa cuulc mercrs (451 o&lc luG) uansponcd rc Envirerc of Urah for disponl lnd 3t2 cubic mclcrs
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(g00 subic ,.1, rfuiwu snrstrcd and rscd as fill marcrial onste by agrccmcnt rvio slatc rcgUlaron.
C H. Sclraoor, SPnogdala P.r
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The C tt Schnor silg is kared ar 54C Garfickl Srcer rn Springdale, PennsylvUria. Rcoords ittdicatc Oar thc a&c locauon
*.i nfen a lo u 6+i Radroad Srrecr in 1943, strn C H. Sctrnor& Comprny bcgan povtding ncal &bncauon seFlcss
,n-*ppon of lr,{anlranan Engrnccr Drgricr operarons. Tlr arrcpr owrter rs Conviber, Inc., a nanufacnrrcr of iadrsnd
csny;or bdg. TI13 srr ongnatly consncC of a concreG bloct buildinB EhcF enru@ utit[tutB metal rods werc
rof"r,.a a,uing rhclls+Os-ro produce slugs uscd asfilrd! rna,rerrrl for produaioD tqlslot!, and r load,ing dak' wherc
urirruut sprtts arav brve eurrcd. TLe buildiug *as larcr ealarge4 and a nav loading docl was added
I! l9t7, e radiologisil stn/q i&nrifiart clevarql radiadon lwels orrer a suall .rtt itlsidc Oe brutcting nhere uraruun was
nrashincA Addid;Dal srr"eri in l9t9 uld t990 confirmed rlr prcscnce of radioasr&e coauniaarion u excess of
Srr,&tioo b.nca6 rti UuitCing 0or *nalysis of soil saurplcs tbou,Gd conccnsndons of uradum-Zlt ranBng from 90 to
iqom pl*,irlrs fr g;n- Tie analysis Ad nor dcrcst coirrgururrou outsrdc rbc building, Rcacdial acuoa' sorsrsrrag of
uuiro,i dcconus;*j-n urd rcooval of consrere, war uudarcd in Augrrsr 199{ 8ld-clmplelcd in seprlmber 1994. The
ront urise volune wps 516 cubrc mctcrs 1576 orbrc frds). Thc ry4 iosludes 47t eubtc metels (525 obic yanh)
,rno+"nrO pioriroi* of Ureh fer rlispoaat ead spproximarety 38 cubic msrrE (50 q$ic yards) rier uras cnrshed and
nrcd as Elt marerial onsire by agrccmcil witi nar regularors.
Tenuessee I
l
Elza Garc, OakRrd,ge, TN
i
Thc Elza Crate sir oogitElly corsiseC of 6vc warchotrso and ouer smaller tuusnuEs used by ttc tvlanlurran E-ngineer
Disrna !o $ore pircdtenOe-anO prrcsscd rcsidues gencntcd io wort rclared fo rbc ltlaalraaao Proirr Nonc of the ongnal
srru.r,ues remair; rt i ooc sxisririg orsirc burtding was erccred on oE! of tltc concrerc pads renainingrfier disroanlcmeot
of rhe orieuEl buildi[F Deparui-cnr of Eoctgr p-rcdeesor ageacic larer used the sltl to srctl eleflrical cquPtB€Dt ,et
arr. roc iiso uscO rtri-srrc ai a nrsulalaring facitiry. Io l9tt, the proFrty was sold to a developucEl comPeny that plans ro
dcvelop rhe stc as uiraausrid P.*.
i
Elza Garc uas included in FUSRAP rn l9tt. urd rhe Dcpanncat of-F*tg condlctld^$ts chrrad.rizauon io l9t9 and
rigo rraaiorogel +d chcmical clrarasenzarron ideadied clewrcd levcls of raditun 225, urasium'2lt' lead' and
pofv.nfort**[ Uipninyts rn nte soile. Site cteanup *as complaed il phaser. Tbc &8 pbase, whicb involved removal of
iU-r.Aioasrivety coniariunarca @tErere flor and htsoit Aom rtc onsuc hllding, rras complercd in tbc spnag of l99l
wrrh rcmporary o1sls $oragc of conrarrunarcd rcil arrl concrctc nrttlc. Tlrcsccood plrasa which coasislD.l of removing dt
rcmainrns conrarninrred micrial Fom exerior lcatrors, *as complercd m 1992. e roral volurus of 5.9t5 cubtc mcrcrs
(7.ZSO cuiic yar&; -,:5I.ISRAP wasre conninint by?rodusl trBlcrial-nas remcdiarc4 Polycblorioared
irinenyt<oniaruraarea soil was !E tspotledro a commcrnat factltly forduposaL aldUe remainug unEnal uas
rrinsp[ncO ro r[e Depannc.nr of Energ OaL Rirl$ Besc1ation for sorage'
Posted 08/19/1996 (fr)
REcuLAt, -*":*T,*",?,T."**1t,srEM ( RrDs )
ACCESSION llBR:9805260198 DOC.DATE z 98/06/LL NoTARIZED: NO
FACIL:40-8581 International Uraniun USA Corp,,
DOCKET #
0400 85 81
AUTri.NAlrF
REHMANN, M. R.
RECIP.NAI{E
HOLONICH, J. if .
DISTRIBUTTON CODE: NL05D COPIESTITLE: Standard Distribution for
NOTES:
AUTHOR AFFILIATfON
RECIPIEMT AFFIIJIATION
Iligh-Level Wast,e & Uraniusr Recovery Projecte Branch (!BIS
SITBiIECT: Subsrite supplemental info re fntl Uranium (USA) Corp a.rrend
requeet re Aehland 2 matle.Description of propoged on-eiteconfirsratory earrpling of eubJect siEe,provided.
RECEMD: LTR I ENcr,O srzE, ?'Uranium Recovery (UR) DocunentE
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PLEASE I{EI,P US TO REDUCE WASTE. TO HAVE YOUR NAII{E OR ORGA}IIZATION REMOVED FROM DISTRIBUTION I.ISTS
OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOt'R ORGANIZATION, CONTACT THE DOCT]MENT CONTROI,
DESK (DCD) ON EXTENSION 41s-2083
TOTAI, NT,MBER OF COPIES REQUIRED: LTTR 8 ENCI,
IxrrnNarron,P
UneNrurvr (USn)
ConponeuoN
4c-P*O t
Independence Plaza, Suite 950 . 1050 Seventeenth Street . Denver, CO 80265 . 303 628 7798 (main) o 303 389 al25 (fax)
June ll,1998
VIA FACSIMLE A}.ID OVERNIG}IT MAIL
Mr. Joseph J. Holoniclu Branch Chief
High Level Waste and Uranium Recovery
Projects Branch
Division of Waste Management
Office ofNuclear Material Safety and Safeguards
U.S. Nuclear Regulatory Commission
2 White Flint North, Mail Stop T-7J9
I1545 Roclville Pike
Rockville, MD 20852
Re: Amendment Request to Process an Alternate Feed at White Mesa Mll
Source Material License SUA-1358
Ashland 2 Amendment Request
Dear Mr. Holonich:
The purpose of this letter is to provide supplemental information concerning the International
Uranium (USA) Corporation ("IUSA") amendrnent request regardrrg the Ashland 2 Materials. As
discussed earlier this week with lvft. James Park, the NRC Project Manager, IUSA proposes to
conduct on-site confirrnatory sanpling ofthe Ashland 2 lvlaterials, as they are delivered to the White
Mesa Mill, at the frequency detailed below.
IUSA proposes to conduct this verification sampling in addition to requiring that the confirmatory
sampling results obtained under the Remediation Contractor's (ICF IGiser) sampling program be
transmitted to IUSA in advance of shipments being received at White Mesa MIl, as per our letter to
the NRC of June 3, 1998.
Details ofthe sampling and analysis protocols, including analytical methods, will be documented in
a Sampling and furalysis Plan ("SAP''), prior to receip of the Ashland 2 lvlaterials. The data quality
objective of the SAP will be to collect data that will allow ruSA to independently venfy that no
rnaterials containing listed hazardous wastes are received and processed at the White Mesa Mill.
A:\SAP06l0.doc
fBf;ffiaffiFk'c
i\
Joseph J. Holonicb, Chief
Samole Freouencv
June 11, 1998
A two-phase approach to sample frequency will be applied:
Ptnse I
One sample per each of the first 100 cubic yards C.Cy'), up to 1,000 CY (i.e., 10 sanples for phase
D
Phase tr
One sample per each additional500 CY.
I can be reached at 303.389.4131.
a
Sincerely yours,
(
h.;-'r*@
Mchelle R Rehmann
Environmental ldanager
MRR/smp
cc James Park
WilliamJ. Sinclair
David C. Frydenlund
Earl E. Hoellen
Harold R Roberts
WilliamN. Deal
*,nu*'t",*ff.T*:3*I*lr,srEu (RrDs )
ACCESSION NBR: 9806120329 DoC.DATEz 98/06/03 NOTARIZED: NOIFACIIJ:40-8581 International Uraniun USA Corp.,
oocrsr #
04008581
AUTH.NAME
REHI{A}iIN, M. R.
RECIP.NAME
HOIJONICH, iI . if .
SITBiIECT: Submite
Proceea
AIITHOR AFFII.IATION
RECfPfENI AFFILIATIONj ttigh-Leve1 Wastse & Uraniun Recovery ProJecte Branch (UtlS
reBponEe to NRC 980501 RAI re anend request to
altsernate feed at lllhite Meaa U MiIl.
DTSTRIBIITTON CODE: NL05D COPIES RECEIVED:LrTR I t*"o
TITITE: Standard D:lstrj.bution for Uraniun Recovery (IIR)
NOTES:
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IMTERNAL:
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PLEASE HEIJP US TO REDUCE I{ASTE. TO IIAVE YOI,'R NAME OR ORGA}IIZATION REMOVED FROM DIS"RIBUTION LISTS
OR REDUCE THE NT'MBER OF COPIES RECEIVED BY YOU OR YOI'R ORGA!{IZATION, CONTAET TIIE DOCI,MENT CON?ROIJ
DESK (DCD) ON EXTENSION 415.2083
oGC/REGD / SP?C
TOTAI, NT,MBER OF COPIES REQUIRED: LTTR 8 ENCII
INrrnNerro*ol
UneNlul,r (use)
ConponerroN
IndependencePlaz.a, Suite 950 o 1050 Seventeenth Street . Denver, CO 80265 o 303 628 7798 (main) r 303 389 al25 (fax)
June 3, 1998
Via Facsimile and Overnieht Mail
Mr. Joseph J. Holonich, Branch Chief
High Level Waste and Uranium Recovery
Projects Branch
Division of Waste Management
Office of Nuclear Material Safety and Safeguards
U.S. Nuclear Regulatory Commission
2 White Flint North, Mail Stop T-7J9
11545 Rockville Pike
Rockville, MD 20852
.
Re: Amendment Request to Process an Altemate Feed at White Mesa Uranium Mill
Source Material License SUA-1358
Response to NRC Request for Additional Information dated June l, 1998
Dear Mr. Holonich:
Thank you for your letter of June l, 1998, in which the U.S. Nuclear Regulatory Commission
advised International Uranium (USA) Corporation ("IUSA") of completion of the NRC's initial
processing, &d administrative review of IUSA's application dated May 8, 1998. In that
application, IUSA requested an amendment to Source Materid License SUA-1358 to authorize
receipt and processing of material from the Ashland 2 Formerly Utilized Sites Remedial Action
Program ("FUSRAP") site in Tonawanda" New York, at IUSA's White Mesa uanium mill.
As was stated in the May 8 application transmittal letter, expedited review by the NRC of this
application is essential to meeting the FUSRAP objectives and contractor's schedule for the site;
therefore, we appreciate NRC's prompt transmittal, together with your administrative review
letter, of the NRC Request for Additional Information regarding this amendment application. It
is our hope that this prompt response to the NRC's Request for Additional Information will
further enhance completion of NRC's review and approval of the Ashland 2 amendment request.
RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION
The following discussion responds to the four items listed in the NRC Request for Additional
Information, which was transmitted to IUSA with the June 1, 1998 acknowledgement of May 8,
1998 by NRC.
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Mr. Joseph J. Holonich June 3, 1998
NRC Comment
1. Insufficient information and data were provided to adequately characteize material at the
Ashland 2 site.
In this comment, the NRC notes that the information and characterization data provided by IUSA
appeared to deal predominantly with material at the FUSRAP Ashland 1 site, which was the
original location for the disposal of Manhattan Engineering District (MED)-related ore
processing residues. While observing that the data concerning the Ashland I material provide
some indication of the potential radiological and chemical constituents present at the Ashland 2
site, the NRC requests that IUSA provide data and supporting information specifically
addressing the radiological and chemical composition of materials at the Ashland 2 site.
IUSA Response
IUSA requests that the NRC please refer to the Record of Decision for the Ashland I (Includine
Seawav Area D) and Ashland 2 Sites ("ROD"), which IUSA transmitted to the NRC on May 29,
1998, and to the enclosed Sampline and Analysis Plan ("SA1"'; for the FUSRAP Ashland 2
Remedial Action (May 29,1998). The ROD describes the areas and degree of contamination at
Ashland 2, and states that there was no evidence of hazardous waste contamination at the site
where radioactive wastes were found. In addition to the general characterization information
contained in the ROD, the Field Sampling Plan ("FSP") portion of the SAP contains a summary
of the sampling results from the Remedial Investigation ("RI") conducted at the Ashland 2 site.
The summary of the RI investigation data is contained in Subsection 1.2.3 of the FSP, which also
states that "the RI focused on radioactive contaminants; metals related to ore processing
activities; and chemicals whose presence could classi$ the site wastes as RCRA-hazardous, or
be a potential safety concern if workers involved in site remediation were exposed to them". The
sampling results from the RI are summarized in Tables l-l and l-2 of the FSP, in Section 1.2.3.
For purposes of characterizing the presence and concentrations of natural uranium at Ashland 2,
the RI assumed that it would not be necessary to measure uranium-235 and uranium-234 levels,
because the ore processing conducted at Linde did not affect the isotopic ratios of the natural
uranium isotopes. Therefore, as stated in the FSP, it was assumed that 47.3 percent of the
radioactivity of natural uranium comes from uranium-238; 2.2 percent from uranium-235; and
50.5 percent from uranium-234. Thus, citing the RI, the FSP indicates that uranium-234 and
uranium-235 activities in soil samples can be calculated from measured uranium-238 activities.
For example, Figure l-5 of the FSP shows nine samples of material that would have to be
excavated (i.e., the corresponding thorium-23O content exceeds the site-specific cleanup level of 0 pCi/g) with uranium-238 activity in the range of 100-200 pCi/g. Given that the uranium-238
activity represents just under half of the total activity for natural uranium, these values imply a
natural uranium activity, for these sarnples, of approximately 200-400 pCilg. This range of
activity levels corresponds with an average uranium content in excess of 0.05 percent (with 582
pCi/g equal to approximately 0.1 percent uranium, see 40CFR Parts 302 and 355, Administrative
-2-
F :\USERS\STAFRMRR\LETTERSWNCASH62.DOC
Mr. Joseph J. Holonich June 3, 1998
Reporting Exemptions for Certain Radionuclide Releases: Final Rule, March 19, 1998,
Technical Background Document, October 1997, L02RQ-RN-2-2-3, U. S. EPA).
The RI data also show samples with greater activity levels due to uranium-238, as well as some
with lower activity levels than the 100-200 pCi/g range; however, those materials with lower
activity levels, which contribute to the averages listed at the end of Table l-1 of the FSP would
not contribute to the average uranium content of the material to be excavated and sent for
processing at the White Mesa mill. That average uranium content, although not reasonably
predictable with current data, is expected to be higher than the average in Table 1-1, because in
accordance with the Excavation and Restoration Plan and the Site Operations Plan (ICF Kaiser
for USACE, May 22, 1998) (copy enclosed) only materials containing thorium-230 activity in
excess of the 40 pCilg guideline are to be excavated. All materials with lower levels (and
correspondingly lower levels of uranium) will be Ieft at Ashland 2.
NRC Comment
2. Information and data were not provided to assess the potential impacts of the nearby Ashland
Oil landfill on the Ashland 2 property.
The NRC points out that from 1957 until 1982, Ashland Oil operated an industrial landfill on a
portion of the Ashland 2 property. The NRC further states that it is not clear from IUSA's
submittal what impacts this landfill may have or has had on the Ashland 2 site, or on the material
that may be removed from Ashland 2 and sent to the White Mesa mill for processing. The NRC
requests maps clariffing the locations of materials to be excavated for transport to the mill, and
the relationship of the areas to be excavated relative to the former Ashland Oil landfill.
IUSA Resoonse
The enclosed map provided to IUSA by ICF Kaiser, U.S. Army Corps of Eneineers Ashland l.
Ashland 2. and Seaway Existing Conditions Plan. Drawine No. 66723-RDl, shows the area
where the radioactively-contaminated soils and processing byproducts are to be removed, as well
as the location of the previous industrial waste disposal area. As the map shows, and as ICF
Kaiser confirms, the area where the radioactive soil was disposed at Ashland 2, and which is the
area to be excavated, is separated from the industrial landfill by a creek. In addition, ICF Kaiser
reports that the area in which the byproducts were placed is clearly definable from the ground
and maps, and no excavation is currently anticipated to take place at the industial landfill. In
any event, such excavation would not be included in the current removal action.
NRC Comment
3. Information and analyses were not provided to support an environmental analysis of the
potential impacts associated with the excavation of the material from the Ashland 2 site.
The NRC explains that in accordance with the National Environmental Protection Act of 1969,
as amended, NRC is required to assess the potential environmental impacts associated with its
licensing actions. For purposes of the Ashland 2 remediation, the NRC notes that potentially
-J-
F:\USERS\STAFRMRR\LETTERS\HNCASH62.DOC
Mr. Joseph J. Holonich June 3, 1998
significant impacts may be associated with the U.S. Army Corps of Engineers' ("USACE's")
excavation of material from the Ashland 2 property for transport offsite, particularly with regard
to wildlife habitats and wetland areas. The NRC requests that IUSA either (l)provide an
environmental report addressing the information identified in 10 CFR 51.45; or (2)alternatively,
if an environmental analysis has been performed by either the U.S. Department of Energy
("DOE") or the USACE, IUSA should provide a full description of the analyses conducted and
the conclusions reached by the DOE or the USACE.
IUSA Response
IUSA requests that NRC please review the ROD discussion of the environmental impact of the
removal action. In addition, IUSA provides the following description of the environmental
analyses conducted and the conclusions reached by the DOE and the USACE concerning the
selection of the remediation option for Ashland 2.
Under its authority to conduct the Formerly Utilized Sites Remedial Action Program
("FUSRAP"), the DOE conducted a Remedial Investigatiotr ("H"), Baseline Risk Assessment
("BRA";, and Feasibility Study ("FS") of the Tonawanda Site. All of these investigations
conformed with the CERCLA process for collecting suffrcient data in a remedial investigation to
assess risks to both human health and ecological receptors, with the results being used to select
remedial actions in the FS. As is consistent with CERCLA process, as in the NEPA process,
community involvement was a key component in remedy selection; in fact, it drove the selected
remedy of oflsite transport of the materials which were found to pose a risk to ecological
receptors.
In November 1993, DOE issued a Proposed Plan ("PP") for cleanup of the Tonawanda Site.
Numerous concerns and comments were raised by the community and their representatives
regarding the prefened alternative identified in the November 1993 PP and the proposed onsite
disposal of remedial action waste.
DOE listened to these concems, and derived a site-specific cleanup guideline for the site based
on values important to the community and in compliance with CERCLA, as amended, and the
NCP. In September 1997, DOE prepared a revised PP for the Ashland sites. On October 13,
1997, the Energy and Water Development Appropriations Act was signed into law, transferring
responsibility for the administration and execution of FUSRAP from DOE to the USACE. As a
result of this transfer, the revised PP was not issued by DOE.
On November 10, 1997, after reviewing the history of the Ashland sites and potential remedial
alternatives, USACE issued the revised PP developed by DOE for cleanup of the Ashland sites.
The selected remedy for the Ashland sites, based on the studies and community input defined
above, is referred to as Altemative 24, in the PP issued on November 10, 1997. Soils exceeding
the site-specific derived guideline of 40 pCi/g thorium-23O will be excavated and shipped offsite,
to an appropriately licensed or permitted facility, and the site restored with backfill, loam, and
seed.
-4-
F:\USERS\STAFRMRR\LETTERS\HNCASH62.DOC
vtt. roseph J. Holonich O June 3, 1998
USACE determined that the selected remedy is protective of human health and the environment,
complies with Federal and State requirements that are legally applicable or relevant and
appropriate to materials which are the subject of this response action, and is cost-effective. None
of the practicable remedial alternatives identified for the Ashland sites provided for onsite
treatment for the materials to be removed. Section 8.2 of the ROD details the advantages and
disadvantages of each of the alternatives, based on CERCLA criteria, as they were evaluated in
the FS.
In summary, as stated in the ROD, the intent of the selected remedial alternative, which is a
removal action, will result in the site having contaminated soil and residual processing materials
removed, and then clean fill being retumed and the natural, pre-existing drainage pattern
restored. The soils will be revegetated to match the existing vegetation on site. There will be no
impact on wetlands, and the site will be improved environmentally when the radioactive soils are
removed and clean soil emplaced. There is no requirement for an EIS, because other ecological
assessments had been performed. One such ecological assessment, which meets Federal
guidelines, was the Ecological Risk Assessment for the Tonawanda Baseline Risk Assessment.
The Ecological Risk Assessment conformed with the U.S. Environmental Protection Agency's
general procedures for ecological assessments under CERCLA (USEPA, 1989), included
characterization of habitats and biota, screening of chemicals of concern ("COCs"), and
assessment of potential impacts to biota, based on measured environmental concentrations of the
constituent and toxicological effects reported in literature. The ROD, in Section 6.3, cited the
results of the Ecological Risk Assessment as a basis for concluding that that remediation would
reduce potential risk to Ashland 2 wildlife and natural habitats.
NRC Comment
4. It is not clear what analyses will be conducted to ensure that materials containing listed
hazardous wastes are not received and processed at the White Mesa mill.
The NRC references NRC's alternate feed guidance issued on September 22, 1995, which
requires that license applications will not be approved to receive and process materials that are or
contain hazardous wastes listed under 40CFR 261.30-33 (or comparable Resource Conservation
and Recovery Act-authorized State regulations). Although, as NRC points out, there is at present
no indication of listed hazardous wastes at the Ashland 2 site, the NRC requests that IUSA
provide a copy of the sampling and analysis plan developed by ICF Kaiser for the confirmatory
sampling plan referenced in IUSA's application; and, that IUSA discuss any additional analysesit will conduct and the record keeping procedures it will implement to ensure that materials
containing listed hazardous wastes are not received and processed at the White Mesa Mill.
IUSA Resoonse
As stated above, a copy of the Sampling and Analysis Plan ("SAP"), which includes a Field
Sampling Plan ("FSP") and a Quality Assurance Project Plan ("QAPjP"), is enclosed for NRC's
review. ICF Kaiser will take additional field samples to confirm the absence of hazardous
wastes as listed in RCRA. Also, all soil being shipped to IUC will be tested and manifested in
accordance with the SAP, to confirm the absence of hazardous wastes in the soil. The
-5-
FTU SERS\STAFF\,IRR\LETIERS\}INCASH62.DOC
'Mi.
Joseph J. Holonich O -6-June 3, 1998
duplicative check will ensure that no hazardous materials are fransported in the materials
excavated and shipped to the White Mesa Mill. IUSA has reviewed the SAP, and considers it
acceptable for purpopes of ensuring that sufficient data are obtained and that quality control and
quality assurance mpasures will be in place to ensure that no materials containing hazardous
wastes are transported to the White Mesa mill. As the SAP is satisfactory to IUSA, IUSA would
not propose that additional independent sampling or analyses be performed. IUSA will require
that confirmatory sampling results be included in the material transfer packages, which IUSA
will require be provided to IUSA in advance of shipments being received at White Mesa Mill.
SUMMARY AND CONCLUSION
Again, IUSA appreciates NRC's timely response to the Ashland 2 amendment request. We
sincerely hope that the information provided above is suffrcient to allow the NRC to conclude
this review. Should your staffhave any questions regarding this information, I can be reached at
303.389.4131.
( SincerelY Yours,
)-r'"/,,t/*///L/{L\*----
Michelle R. Rehmann
Environmental Manager
MRR/mrr
cc Ron E. Berg
William N. Deal
David C. Frydenlund
Earl E. Hoellen
Harold R. Roberts
James Park, U.S. NRC (with enclosures)
Bruce Howard,ICF Kaiser
William J. Sinclair, State of Utah
F:\USERS\STAFRMRR\LETTERSU{NCASH62.DOC
CATEGORY
INFoRMATIoN DISTRIBUTION ISYSTSM (RIDS}
-. ACCESSION NBR:9805190096 DOC.DATEz 98/05/08 NOTARIZED: NO DOCKET #
Oml:ik;"'"'"iffi;ilTl"Y;iriH*'sA corp" / ffi,""REHI[AI[N,M.R. Affiliation Not Aesigmed /[4ru/7'' '
RECIP.NAIT{E RECIPIENI AFFILIATION /
HOLONICH, iI. iI.High-Level Waste & Uraniunr Reco'rery ProjectE Branch (mAS
SUBiIECT: Fonrrarde application for amend to license ISUA-1358 toauthorize receipt & processing of U-bearing natl resuJ.tingfrom processing of natsural ore for extraction of U.
DrsTRrBIrrroN coDE: Nr,05D coPrEs REcETvED:LTR --l urcl -.1 srzu, 4+78TfTLE: Standard Distribution for Uranium Recovlry (TJR)5ocusrente
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PI,EASE HELP US TO REDUCE WASTE. TO HAVE YOI'R NA}TE
OR REDUCE THE NT]MBER OF COPIES RECEIVED BY YOU ORDESK (DCD) ON EXTENSTON 415-2083
OR OREA}IIZATION REMOVED FROM DISTRIBIITION LISTS
YOT'R ORGAI{IZATION, CONTACT THE DOCIJ}4ENT CONTROI
TOTAI, NT,}TBER OF COPIES REQUIRED: IJTTR ENCt
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IsrrRr-lrloli-{Loui.=
Independenceplaza,Suiteg50 o 1050SeventeenthStreet o Denver.CO80265 ' 3036287798(main) '303389{125itrNt
MaY 8, l99t
Via Overnicht Mail
Mr. Joseph J. Holonich Branch Chief
High Level Waste and Uranium Recovery
Projects Branch
Division of Waste Management
Oil. of Nuclear Materi-al Safety and Safeguards
U.S. Nuclear Regulatory Commissio-n
2 Whitc Flint North, Mail StoP T'7J9
I1545 Rockville Pike
Rockvillc, MD 20852
Re: Amcndment Requcst to Process an Alternate Feed at whitc Mesa uranium Mill
Sotrce Marcrial License SUA-I358
Dear Mt. Holonich:
International Uranium (usA) corporation ("[usA").hereby submis the enclosed request to
amend So,rcc Matcriar License sun-ifig io authorizc *d.tpt and processing of a .'anium-
bearing matcriar rcsulting fro.T fu pfrJJ,L;oirr"t*t.ore for the e:ctraction of .ranium. For
ease of reference, this material is refeJio-t.r"io as the "uranium Material"' The uranium
Materisl is being rcmoved by ICF Kaiscr, ,nder " .oi*, with the u.s. Army corps of
Engineers (*USAC;;;;', tt" ;Corpr-ffi* a slc being managed tutder the Formerly Utilized
Sites Remedial Action Program ("FUSirAP;;i ittio**"iae Neu yoar' known as Ashland 2'
The volume of thc uranium Matcrial to bc removed and tTpp"d-l-".1flaj 2 will range from
approximately zedi to.pp.*i."t"ty zs,ooo arr tons' nverage *"ttitP content is difficult to
estimate, artho.gh sitc history ana avaitaule data suggest that recovcrablc r-'anium is present'
Analytical d"," d;lJto'IUSA indicate uraniurn-content ranging from nondetecuble to
approximarery 1.0 percent, or^ g*,"i -lusa anarysis or ,nr". r*f".. samples indicated
concentrations ranging from <0.00r to'o.oc p"i..n . Eighteen corc samples showed uanium
contents above 0.05 Percent'
In addition to recovery of the uranium content of the urt* Material' vanadium may also be
recovercd using the secondary vanadium recovery circuit of the Mill that is used when
vanadium/,ranium feedstocr is procesJ. However, insuflicient ore grade data arc available to
estimate the potential recovery of uanaaium or other *"or materials. This Uranium Material
will be pro""rJ .irt", togith., wittr or separately from' and in the same manner as our
;BH*ffi-t?8ffiq,L- PDft
^ Mr. JosePh J. Holonich 1 May 8, 1998
conventional ores, and will contribute significant economic benefits to IUSA, as detailed in
Section 1.3 of the application. Because we have asked that this application be expedited, in
order to facilitate NRC's review, we have decided to include in the regulatory considerations
section of our application more detail than in past submissions.
The processing of the Uranium Material will not increase the mill'r; production to exceed the
License Condition No. l0.l limit of 4,380 tons of U3Os per calendar year. As production will
remain within the limits assessed in the original Environmental Assessment, and as the process
will be essentially unchanged, this amendment will result in no significant environmental
impacts beyond those originally evaluated.
The disposd of the I le.(2) byproducts resulting from processing the Ashland 2 mateial will not
change the characteristics of the Mill tailings from the characteristics associated with normal
milling operations. In fact, processing of the Ashland 2 material, which is an I le.(2) byproduct
material, to recover the uranium it still contains, is expected to make the resulting lle.(2) tailings
less contaminated, as radioactive uranium will be removed from the Uranium Material.
Complete details are provided in the attached request to amend, which includes the following
sections:
INTRODUCTION
1.0 Material Composition and Volume1.1 Radiochemical Data1.2 Hazardous Constituent Data1.3 RegulatoryConsiderations
2.0 TransportationConsiderations
3.0 Process
4.0 Safety Measures4.1 Radiation Safety4.2 Control of Airborne Contamination4.3 Vehicle Scan
5.0 Other Information5.1 Added Advantage of Recycling5.2 Reprocessing of I le.(2) Byproduct Materials under UMTRCA
CERTIFICATION
Attachment I Ashland 2 Material Description, Process History, Flow Diagram, and
Analytical Data.
Attachment 2 White Mesa Mill Equipment Release/Radiological Survey Procedure
F:\USERS\STAFRMRR\LETTERS\HNCH0598. DOC
o
Mr. Joseph J. Holonich May 8, 1998
Attachment 3 U.S. Army Corps of Engineers Value Engineerirng Proposal for Ashland I
and Ashland 2
To ensure that all pertinent information is included in this submittal, the following guidelines
were used in preparing this request to amend:
o U.S. Nuclear Regulatory Commission ("NRC") Final Position and Guidance on the Use of
Uranium Mill Feed Material Other Than Natural Ores (Federal Register Volume 60, No.
I 84, September 22, I 995).
o Energy Fuels Nuclear ("EFN") request to the NRC for the amendment to process uranium-
bearing potassium diurinate (KzUzOz) in a solution of potasr;ium hydroxide/potassium
fluoride in water ("KOH Amendment").
o NRC and State of Utatr comments and requests for information relative to the KOH
Amendment.
EFN request to NRC for the Rhone-Poulenc alternate feed amendrnent.
NRC and State of Utatr comments and requests for information rr:lative to the EFN request
for the Rhone-Poulenc alternate feed amendment.
o EFN request to the NRC for the amendment to process uranium-trcaring material owned by
the Cabot Corporation.
o EFN request to the NRC for the amendment to process uranium-trcaring material owned by
the U.S. Department of Energy.
We believe that use of these guidance materials, supported by our discussions with the NRC
concerning these amendment requests, has allowed us to prepare a complete, concise submittal.
Therefore, IUSA requests that the NRC please attempt to reply to this request within 30 days of
this transmittal date. The established schedule calls for removal actions for Ashland 2 to take
place during the summer of 1998. The contractor, ICF Kaiser, will begin excavation in early
June, 1998; start shipping the Material; and be completed by Septernber 30, 1998. Removal
actions at the two other FUSRAP locations near Ashland 2, Ashland I and Seaway, will follow
in early 1999. Early review will allow material from the Ashland 1! site to be transported to
IUSA in lieu of other locations. I can be reached at [phone]
Sincerely,
-J-
Michelle R. Rehm,ann
Environmental Manager
F:\USERS\STAFRMRR\LETTERS\HNCH0598. DOC
a
Mr. Joseph J. Holonich
MRR/tay
Attachments
cc James Park
Earl E. Hoellen
Harold R. Roberts
David C. Frydenlund
William N. Deal
May 8, 1998
F:\USERS\STAFRMRR\LETTERS\HNCH0598.DoC
Source
Request to Amend
Material License SUA- 1 358
White Mesa Mill
Docket No. 40-8681
May 8, 1998
Prepared by:
International Uranium (USA) Corporation
1050 l7h Street, Suite 950
Denver, CO 80265
Contact: Michelle R. Rehmann, Environmental Manager
Phone: [phone]
Submiued to:
United States Nuclear Regulatory Commission
2 White Flint Norrh, Mail Stop T-7J9
I1545 Rockville Pike
Rockville, MD 20852
'uffit
c
Amendment Request
Ashtand 2
License SUA-1358
May 8, 1998
Page i
1.0
TABLE OF CONTENTS
Paee
INTRODUCTION .......1
MATERIAL COMPOSITION AND VOLUME ...... I
1.1 Radiochemical Data .........21.2 Hazardous Constituent Data . .... . 31.3 Regulatory Considerations . . ..... .4
TRANSPORTATION CONSTDERATIONS ........... 8
PROCESS ..........9
SAFETY MEASURES ..... ..........104.1 Radiation Safety .........104.2 Control of Airborne Contamination . . . . . ..1 14.3 Vehicle Scan . . .. ..1 I
OTHER TNFORMATION ..... 1 15.1 AddedAdvantage of Recycling..... .......115.2 Reprocessing of 1le.(2) Byproduct Materials under UMTRCA ....... .12
CERTTFICATION
List of Attachments
Ashland 2 Material Description, Process History, Flow Diagram, and
Analytical Data
Energy Fuels Nuclear, Inc. White Mesa Mill Equipment
Release/Radiological Survey Procedure
U.S. Corps of Engineers Value Engineering Proposal for Ashland 1 and
Ashland 2
5.0
2.0
3.0
4.0
Attachment I
Auachment 2
Attachment 3
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Amendmcnt Request
Ashland 2
License SUA-1358
May 8, 1998
Page I
INTRODUCTION
Intemational Uranium (USA) Corporation ("IUSA") operates an NRc-licensed uranium mill
located approximately six miles south of Blanding, Utah. The mill processes natural (native,
raw) uranium ores and feed materials other than natural ores. These alternate feed materials are
generally processing products from other extraction procedures, which IUSA processes at
IUSA's licensed uranium mill, primarily for the source material content. All waste associated
with this processing is, therefore, l1e.(2) byproduct material; or, as stated in the alternate feed
analysis noticed in Federal Register Volume 57, No. 93:
"The fact that the term 'any ore' rather than 'unrefined and unprocessed ore' is
used in the definition of I le.(2) byproduct material implies that a broader range of
feed materials could be processed in a mill, with the wastes still being considered
as I le.(2) byproduct material".
This application to amend NRC Source Material License SUA-1358 requests an amendment to
allow IUSA to process a specific alternate feed, and to dispose of the associated 11e.(2)
byproduct material in accordance with the Mill operating procedures.
Yellowcake produced from the processing of this material will not cause the currently-approved
yellowcake production limit of 4,380 tons per year to be exceeded. [n addition, and as a result,
radiological doses to members of the public in the vicinity of the mill will not be elevated above
levels previously assessed and approved.
1.0 MATERIAL COMPOSITION AIID VOLUME
IUSA is requesting an amendment to Source Material License SUA-1358 to authorize receipt
and processing of certain uranium-containing byproducts resulting from the processing of natural
ore for the extraction of uranium. For ease of reference, this byproduct material is referred to
herein as the "Uranium Material". The Uranium Material is located at a site being managed
under the Formerly Utilized Sites Remedial Action ("FUSRAP") Program in Tonawanda, New
York, known as Ashland 2. The Uranium Material is not a residue from a water treatment
process.
The Uranium Material will be transported by ICF Kaiser, under contract to the U.S. Army Corps
of Engineers ("USACE", or the "Corps"), * part of the FUSRAP Program, from Ashland 2 to
the White Mesa Mill.
Ashland 2 is one of three sites located on the Linde Property near one another in Tonawanda,
New York: Ashland l, Ashland 2, and Seaway. The regional setting of Linde, Ashland l,
Ashland 2, and Seaway is shown in Figure l-2 of Attachment 1. Figure l-3 shows the locations
of Linde, Ashland l, Ashland 2, and Seaway.
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Ashland 2
License SUA-1358
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From 1942 to 1946, portions of the Linde Property in Tonawanda, New York were used to
separate uranium from imported pitchblende and domestic ore, under contract with the
Manhattan Engineering District ("MED").
Figure l-8 shows the process used for domestic ores; the process was modified somewhat for
African ores, as is footnoted on Figure l -8.
Residues from uranium ore processing at the Linde facility were disposed of (in trenches) and/or
stored at the Ashland 2 property. Uranium ores processed at Linde included domestic ores and
African ores, containing uranium in equilibrium with all of the daughter products in the decay
chain.
In addition to these maps, Attachment I includes the following items describing Ashland 2
materials, process history, flow diagrams, and analytical data:
1. A complete history of uranium processing at the Linde property is provided on page 2 of
the Prooosed Plan for the Ashland I Ashland 2 Sites-Tonawanda- New York (U.S. Army
Corps of Engineers, November 1997).
2. Portions of the Radioloeical Survev of the Ashland Oil Companv (Former Haist
Propertv). Tonawanda New York (U.S. Department of Energy, May 1978) describe
uranium concentrations in core samples and approximate distributions of tailings stored
on the Linde property.
3. A portion of the Prelimina{v Assessment Site Investisation and HRS Scorine for Ashland
2 Tonawanda. NY (U.S. DOE, June 1987), which describes the content of the residues,
including 8,000 tons of residues containing approximately 0.54%o uranium, that were
deposited on the Linde property between 1944-1946.
4. A Portion of the Preliminary Assessment and Site Investigation for Linde Air Products
(U.S. DOE, September 1987) describes Linde operations and processes.
Over the years, leaching has spread contamination from the Uranium Material to adjacent soils,
increasing the volume to be removed. The Corps estimates that the volume of the Uranium
Material is approximately 24,000 to 25,000 tons (dry basis). Physically, the Uranium Material is
a moist material consisting of byproducts from uranium processing operations (ie., "tailings"),
mixed with site soils.
l.l Radiochemical Data
Process history demonstrates that the Uranium Material results from the processing of natural,
mined uranium-bearing ores. [t is currently being managed, and would be disposed of (if not
reprocessed) as 11e.(2) byproduct material.
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Ashland 2
''*"'ir'"lt, lii!
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Average uranium content is diffrcult to estimate, although site history and available data suggest
that recoverable uranium is present. Analytical data provided to IUSA indicate uranium content
ranging from nondetectable to approximately 1.0 percent, or grbater. IUSA analysis of three
surface samples indicated concentrations ranging from <0.001 to 0.06 percent.
1.2 Hazardous Constituent Data
NRC guidance suggests that if a proposed feed material consists of hazardous waste, listed under
subpart D Section 261.30-33 of 40 CFR (or comparable RCRA authorized State regulations), it
would be subject to EPA (or State) regulation under RCRA. To avoid the complexities of
NRC/EPA dual regulation, such feed material may not be approved for processing at a licensed
mill. If the licensee can show that the proposed feed material does not consist of a listed
hazardous waste, this issue is resolved. NRC guidance further states that feed material exhibiting
only a characteristic of hazardous waste (ignitable, corrosive, reactive, toxic) would not be
regulated as hazardous waste and could therefore be approved for recycling and extraction of
source material. The NRC Alternate Feed Guidance also states that NRC staffmay consult with
EPA (or the State) before making a determination on whether the feed material contains
hazardous waste.
The Corps, based on its analysis of the Uranium Material and process knowledge, believes that
the Uranium Material contains no RCRA listed wastes. Process history and analytical data are
described in Attachment 1.
ICF Kaiser, the contractor for the Corps, has indicated that to date, no listed hazardous wastes
have been discovered at Ashland 2. Upon excavation, additional chemical testing will be
accomplished to verifu existing dat4 prior to any shipment. Any material that such testing
would indicate contains listed hazardous waste constituents will not be included in the Uranium
Material. ICF Kaiser has prepared a draft Sampling and Analysis Plan ("SAP") for this
confirmatory sampling program. The SAP is currently under review by the Corps. ICF Kaiser
will at NRC's request provide NRC with a copy of the final SAP.
The Uranium Material contains metals and other pararneters which already are present in the mill
tailings disposed of in the Cell 3 impoundments. Generally, the composition of the Uranium
Material is very similar to the composition of the materials currently present in the White Mesa
Mill's tailings impoundments, because the Uranium Material resulted from the processing of
uranium-bearing ores for the extraction of uranium, and should not have an adverse impact on
the overall Cell 3 tailings composition. Furthermore, the amount of tailings (a maximum of
approximately 25,000 tons) produced by processing the material is not significant in comparison
to the total amount of tailings currently in the cell (approximately 1.4 million tons). Additionally
IUSA is required to conduct regular monitoring of the impoundment leak detection systems and
of the groundwater in the vicinity of the impoundments to detect leakage if it should occur.
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Ashland 2
Lice nse SUA- t358
May 8, 1998
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1.3 Regulatory Considerations
Uranium Material Oualifies as "Ore"
According to NRC guidance, for the tailings and wastes from the proposed processing to quafiry
as I le.(2) byproduct material, the feed material must qualiff as "ore." NRC has established the
following definition of ore:
"Ore is a natural or native matter that may be mined and treated for the extraction
of any of its constituents or any other matter from which source material is
extracted in a licensed uranium or thorium mill."
The Uranium Material is a matter from which source material will be extracted in a licensed
uranium mill, and therefore qualifies as "ore" under this definition.
Uranium Material Not Subject to RCRA
As described under 1.2 above, the Uranium Material is not subject to regulation as a listed
hazardous waste as defined in the Resource Conservation and Recovery Act, as amended, 42
U.S.C. Section 6901-6991 and its implementing regulations, or comparable State laws or
regulations governing the regulation of listed hazardous wastes. In fact, the Department of
Energy, as predecessor to the Corps in managing the FUSRAP sites, has consistently classified
the FUSRAP materials, including the Uranium Material at Ashland 2, as I le.(2) byproduct
material. If Ashland 2 material were to be shipped to a waste disposal facility, IUSA
understands that it would be accepted and disposed of as I le.(2) byproduct material.
Justification of Certification Under C,ertification Test
In the Licensee Cenification and Justification test set out in the NRC's Final Position and
Guidance on the Use of Uranium Mill Feed Material Other Than Natural Ores, the licensee
must certiff under oath or affirmation that the feed material is to be processed primarily for the
recovery of uranium and for no other primary purpose. IUSA makes this certification below.
Under this Guidance, the licensee must also justiff, with reasonable documentation, the
certification. The justification can be based on financial considerations, the high uranium
content of the feed material, or other grounds.
Uranium Content
As stated above, average uranium content is diffrcult to estimate, although site history and
available data suggest that recoverable uranium is present. For example, analytical data provided
to IUSA indicate uranium content ranging from nondetectable to approximately 1.0 percent, or
greater. IUSA analysis of three surface samples indicated concentrations ranging from <0.001 to
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Ashland 2
''**ir:yi:lill
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0.06 percent. Historic reports indicate that residues were both spread over and buried at the
property. One report containing core data listed eighteen core samples that contained uranium
above 0.05 percent.
The site history indicates that 8,000 tons of process residues containing on average
approximately 0.54 percent UgOs from processing at the Ashland I property, were spread out
over roughly two thirds of that property. Some of these residues contained as much as 5.57
percent vanadium (VzOs). The majority of the residues, and associated contaminated soils, were
transferred to Ashland 2 and Seaway. It is not clear how much of these residues remain on the
Ashland 2 property; however all that do remain will be included in the Uranium Materials.
Additional radioactive residues were removed from Ashland I and were also deposited in an area
of the Ashland 2 Property.
Based on the information available, IUSA estimates that the average grade of UEOa contained in
the Uranium Material could be approximately 0.05 percent, but that this number could be
increased or decreased depending on the extent to which pockets of higher grade materials exist
on the site. However, IUSA believes that, based on the history of the site, there is significant
potential that the average grade of the materials could be substantially greater than 0.05 percent
UlOs. For example, if one half of the Ashland I residues described above remain on the Ashland
2 site, the average grade of the total Uranium Materials could be in the range of 0.10 to 0.12
percent UlOr.
These grades of 0.05 percent to 0.12 percent U3Os are on the low end of the scale to justifu
hardrock mining and conventional milling today, although these grades of ore have been mined
under conventional methods in the past and are currently being mined by in situ methods today.
However, there are no mining or transportation costs payable by IUSA in connection with these
ores, and therefore, these grades can justift conventional milling on their own merits in certain
circumstances. When the additional Financial Considerations referred to below are taken into
account, IUSA has concluded that milling the Uranium Material for its source material content
provides a net benefit to IUSA, without taking into consideration the recycling fee referred to
below under Other Considerations.
F inancial Cons iderations
For a number of reasons, IUSA believes that the ability to process the Uranium Materials in the
same fashion as conventional uranium ores either alone or commingled with such ores during the
same mill run provides a number of production and production scheduling benefits to IUSA that
have the effect of significantly reducing the incremental cost to IUSA of processing the Uranium
Materials.
The White Mesa Mill has a nominal capacity of 2,000 dry tons of conventional ore per day. Themill cannot operate at less than its nominal capacity, without making certain capital
modifications to the mill. This equates to approximately 680,000 tons per operating year, or
57,000 tons per month. This far exceeds the mine production from IUSA's currently operating
mines, which is approximately 10,000 tons per month, and significantly exceeds the historic
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Amendment Request
Ashland 2
License SUA-1358
"* ti"?::
daily production available for processing at the mill from all sources. As a result, the mill has
almost always been run in campaigns, where sufficient ores are stockpiled to justiff a minimum
length mill run (which should generally be at least eight months of continuous operations); the
mill is run until the stockpile together with ores that have been delivered to the mill during the
mill run have been milled; and then the mill is put on standby until a sufficient amount of ores
are again stockpiled to justifu the next mill run, and so on.
There are several economic costs associated with this type of operation. First, several millions of
dollars of valuable ore can be stockpiled for months, before offsetting revenues are realized.
This has the effect of increasing the real cost of mining, as the cost to mine this ore must be
financed during the period. Secondly, the longer the period of time that ore is sitting on the pad
waiting to be milled, the higher is the risk that commodity prices will decrease during that time
period, with the result that the yellowcake or vanadium will have to be sold at a lower price than
expected. This risk can be partially offset to the extent that the resulting commodities are sold
forward at or prior to the time that the ore is mined. However, IUSA, like most producers, does
not sell all of its production forward in this manner. Thirdly, it is difficult to maintain a trained
workforce at the mill during the downtime. As a result, there is a cost, both direct, in the form of
training, and indirect, in the form of decreased operating efficiencies and recovery percentages
over the initial months of each mill run, associated with training new operators for each mill run.
This is one reason why it is important that each mill run be at least eight months or so, to
minimize this type of start up ineffrciency during each mill run. And of course, the longer the
continuous mill run the better.
By making certain capital modifications to the mill, IUSA has the ability to decrease the nominal
capacity of the mill, to allow for a lower throughput per day. This has the benefit of reducing the
amount of time necessary to stockpile ore, as the number of tons required to be stockpiled
between each mill run would be less. However, reducing the nominal throughput of the mill has
the unfortunate effect of increasing the milling cost per ton, as certain cost components such as
labor and utilities qmnot be reduced proportionately. Therefore there are economic limits
inherent in reducing the nominal capacity of the mill. As a result, the more ore that can be fed to
the mill the better. A greater, faster, supply of ore will result in longer mill runs at higher
nominal capacities and lower milling costs.
The ability to process the Uranium Materials along with conventional ores, or separately, in the
same mill run, will provide IUSA with the ability to commence its mill run earlier in 1998 than
otherwise would be the case. IUSA currently expects that, depending on various circumstances,
the mill run could commence approximately two and one half months earlier as a result of
processing the Uranium Material. IUSA views the Uranium Material the same as if it were low-
grade conventional ore. The resulting ability to thereby increase IUSA's stockpile of ore by the
addition of the Uranium Material and the ability to process such ores during the same mill run
and in the same manner as conventional ores, is expected to provide the following benefits to
IUSA:
(a) the financial cost of stockpiling ore (i.e., the interest cost of the ore on the pad) is
expected to be reduced by approximately two and one-half months;
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License SUA-1358
May 8, 1998
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(b) IUSA would expect to be able to produce more U3Os and VzOs in 1998, which can be
applied to reduce advance royalties payable in 1998, which advance royalties cannot
be recouped from production in subsequent years;
(c) By reducing the time between the mining of ore and the production and sale of UrOs
and VzOs ,IUSA is able to reduce the risk that the prices at which the commodities
are sold will have fallen, thereby reducing the rosulting resulting risk of the
possibility of production at a loss. Only a portion of IUSA's UrOs is sold forward;
the remainder must be sold on the spot market. At this time most of IUSA's V2O5
must be sold on the spot market;
(d) An earlier conventional ore mill run should make it easier for IUSA to attract
purchased conventional ore from independent third party miners, because the interest
cost to such miners of having mined the ore without having received full payment for
the value of the ore should be less, and hence the cost of mining would be less.
IUSA's purchased ore program is an important part of its business;
(e) The price of VzOs is crurently close to a seven-year high, and the ability to produce
vanadium earlier reduces the risk that IUSA will miss this high in the market;
(f) Having the ability to commingle Uranium Materials with, or to process the Uranium
Material during the same mill run as, conventional ores should provide some ability
to use Uranium Materials to smooth out variability in the production and delivery of
conventional ores to the mill; and
(g) The ability to start a conventional mill run earlier this year may reduce the risk of
losing trained mill operators due to the possibilities of downtime between IUSA's. current alternate feed run and its next conventional ore run. Or, alternatively, an
earlier mill run may reduce the cost of retaining qualified personnel on staff during
downtime, due to the possible shortening of the downtime period.
Finally, if circumstances at the Mill change such that ore supplies from IUSA's mines and other
sources increases over the arlounts currently expected, and the conventional mill nrn can
therefore be started earlier than currently expected, then the ability to process the Uranium
Material during the same mill run will either allow the Mill to be run at a higher nominal
throughput than otherwise would be the case, resulting in lower costs of processing each ton of
ore during the mill run and a more accelerated output of yellowcake and vanadium, or allowing
for a longer mill run than would otherwise be the case, thereby allowing for lower average
operating costs per ton due to the spreading out of startup and shutdown costs over a larger
number of tons of ore milled during the mill run.
For these reasons, IUSA has determined that the ability to process the Uranium Material for
uranium in the same manner and during the same mill run as our conventional ores has
significant financial and commercial benefits to our uranium milling business, even at low grades
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Ashland 2
License SUA-1358
"* til;::
of uranium contained in the Uranium Materials. And of course, these benefits have the effect of
reducing the incremental cost of processing the Uranium Material. To the extent that the
Uranium Material contains higher grades of uranium, this added uranium recovery will add to
the financial benefits to IUSA of processing the Uranium Material.
In addition to the foregoing, the Uranium Materials may contain some vanadium. If the Uranium
Material is processed in separate batches during the mill run, it may be possible to recover this
vanadium if it can be isolated in batches of 1.0 percent or higher. Historic data suggest that
vanadium-bearing residues of over 5.0 percent may still be included in the Uranium Material. If
these pockets of vanadium can be identified, then they can be run through the mill on a batch
basis geared toward maximizing the co-product recovery of vanadium along with the uranium.
If, however, these vanadium grades are commingled within the Uranium Material, they may still
add to the recovery of vanadium at the mill if commingled with other vanadium-bearing ores. It
is diffrcult to quantifu what if any recovery of vanadium is possible, but there is definitely the
potential for the recovery of some valuable vanadium at little incremental processing cost.
Other Considerations
In addition to the fact that IUSA will retain all uranium and vanadium produced from the
Uranium Materials, and will realize the financial and commercial benefits described above,
IUSA will receive a recycling fee for recycling the Uranium Materials to remove uranium and
thereby reduce the radioactive component of the materials. However, recycling of the Uranium
Materials for uranium and the disposal of the resulting tailings in the mill's tailings
impoundments as 1le.(2) byproduct material is not the primary purpose of processing the
Uranium Materials. The primary purpose of processing the Uranium Materials is for the
recovery of source material in a manner that is economic to the operation of the mill in its
processing of ores for their uranium content. By processing the Uranium Materials for uranium
in the same fashion and during the same mill run as other conventional ores, the mill is able to
enjoy significant financial economies and commercial benefits. The ability to also collect a
recycling fee is merely good business practice, in light of market and commercial considerations.
2.0 TRANSPORTATION CONSIDERATIONS
The Uranium Material will be shipped by train and exclusive-use trucks from the Ashland 2 site
to the White Mesa Mill in intermodal containers. The sealed containers will be loaded on
railcars and transported cross-country to the final rail destination (expected to be either near
Grand Junction, Colorado; Cisco, Utatr; or Green River, Utah), where they will be transferred to
trucks for the final leg of the journey to the White Mesa Mill. It is expected that four containers
will be shipped per rail car, for a total of approximately 290 to 300 cars. ICF Kaiser expects that
60 truck loads per week will be used to transport from the rail transfer site to White Mesa Mill.
The Uranium Material will be shipped as LSA (low specific activity) RadioactiveHazard Class 7
Hazardous Material as defined by DOT regulations. ICF Kaiser will arrange with a materials
handling contractor for the proper labeling, placarding, manifesting and transport of each
F :\users\stafl\mrr\REVAS U B. DOC
Amendment Request
Ashland 2
''*'T,?Yt iiil
Page 9
shipment of the Uranium Material. Each shipment will be "exclusive use" (i.e., the only material
in each container will be the Uranium Material).
For the following reasons, it is not expected that transportation impacts associated with the
movement of the Uranium Material by train and truck from New York to the White Mesa Mill
will be significant:
r The material will be shipped as "low specific activity" material in exclusive-use containers
(i.e., no other material will be in the containers with the Uranium Material). The containers
will be appropriately labeled, placarded, and manifested, and shipments will be tracked by
the shipping company from the Ashland 2 site until they reach the White Mesa Mill.
o On average during 1996,370 trucks per day traveled the stretch of State Road l9l between
Monticello, UT and Blanding, UT (1997 NRC personal communication with the State of
Utah Department of Transportation). An additional 60 trucks per week traveling this route to
the mill represents an increased traffic load of only 2 percent. Shipments are expected to
take place over the course of a limited time period (three to four months).
o The containers and trucks involved in transporting the material to the mill site will be
strveyed and decontaminated, as necessary, prior to leaving the Ashland 2 site for the White
Mesa Mill and again prior to leaving the mill site for the retum trip.
PROCESS
The Uranium Material will be added to the mill circuit in a manner similar to that used for the
normal processing of conventional ore either alone, or commingled with conventional ores. The
Uranium Material will be dumped into the ore receiving hopper and fed to the SAG mill before
being pumped to Pulp Storage. The leaching process will begin in Pulp Storage with the
addition of sulfuric acid.
The solution will be advanced through the remainder of the mill circuitry with no anticipated
modifications to either the circuit or recovery process. Since no physical changes to the mill
circuit of any significance will be necessary to process this Material, no construction impacts of
any significance beyond those previously assessed will be involved.
Tailings produced by the processing of this material will be disposed of on-site in an existing
lined tailings impoundment (Cell 3). The addition of these tailings (a maximum of
approximately 25,000 dry tons) to Cell 3 will increase the total amount of tailings in the cell by
approximately one to two percent, raising Cell 3 to a total of approximately 69 percent of cell
capacity; therefore, no new impoundments are necessary. The design of the existing
impoundments previously has been approved by the NRC, and IUSA is required by its NRC
license to conduct regular monitoring of the impoundment liners and of the groundwater around
the impoundments to detect leakage if it should occur.
3.0
F : \users\staff\mn\REVAS U B. DOC
4.0
Amendment Request
Ashland 2
License SUA-1358
Ivlay 8, 1998
Page l0
SAFETY MEASURES
Mill employees involved in handling the material will be provided with personal protective
equipment, including respiratory protection, as required. Airborne particulate and breathing zone
sampling results will be used to establish health and safety guidelines to be implemented
throughout the processing operations.
The Uranium Material will be delivered to the mill in closed containers via truck. The Uranium
Material will be introduced into the mill circuit in the same manner as conventional ore. The
material will proceed through the leach circuit, CCD circuit, and into the solvent extraction
circuit in normal process fashion as detailed in Section 3.0 above. Since there are no major
process changes to the mill circuit, and since the extraction process sequence is very similar to
processing conventional uranium solutions, it is anticipated that no extraordinary safety hazards
will be encountered.
Employee exposure potential during initial material handling operations is expected to be no
more significant than what is normally encountered during conventional milling operations.
Employees will be provided with personal protective equilment including full-face respirators, if
required. Airbome particulate samples will be collected and analyzed for gross alpha
concentrations. If uranium airborne concentrations exceed 25 percent of the DAC, full-face
respiratory protection will be implemented during the entire sequence of material dumping
operations. Spills and splashed material that may be encountered during this initial material
processing shall be wetted and collected during routine work activity. Sample material of the
Uranium Material indicates it is a neutral material. Therefore, it is anticipated that no unusual
PPE apparel will be required other than coveralls and rubber gloves during material handling
activities. Respiratory protection will be implemented as determined.
4.1 Control of Airborne Contamination
IUSA does not anticipate unusual or extraordinary airborne contarnination dispersion when
processing the Uranium Material. The contamination potential is expected to be less than what is
normally encountered when processing conventional uranium ore. The successive extraction
process circuitry from grinding, leaching, and CCD through solvent extraction and into
precipitation are all liquid processes, and the potential for airborne contamination dispersion is
minimal. Uranium extraction proceeds through the mill circuit as if the Uranium Material were
uranium ore. The material is a moist solid or in a slurry form once it has been introduced into
the SAG mill. Normal dust control measures will be utilized prior to the SAG mill.
The efficiency of airborne contamination control measures during the material handling
operations will be assessed while the ore is in stockpile. Airborne particulate samples and
breathing zone samples will be collected in those areas during initial material processing
activities and analyzed for gross alpha. The results will establish health and safety guidelines
which will be implemented throughout the material processing operations.
F:\users\staff\mrr\REVASUB. DOC
Amendment Request
Ashland 2
''**i,:yi:lill
Page I I
Personal protective equipment, including respiratory protection as required, will be provided to
those individuals engaged in material processing. Additional environmental air samples will be
taken at nearby locations in the vicinity of material processing activities to ensure adequate
contamination control measures are effective and that the spread of uranium airborne particulates
have been prevented.
4.2 Radiation Safety
The radiation safety progam which exists at the White Mesa Mill, pursuant to the conditions and
provisions of NRC License Number SUA-1358, and applicable Regulations of the Code of
Federal Regulations, Title 10, is adequate to ensure the ma,ximum protection of the worker and
environment, and is consistent with the principle of maintaining exposures of radiation to
individual workers and to the general public to levels As Low As Reasonably Achievable
(ALARA).
4.3 Vehicle Scan
After the cargo has been offloaded at the mill site, a radiation survey of the vehicle and
intermodal bin will be performed consistent with standard mill procedures (Attachment 2). [n
general, radiation levels are in accordance with applicable values contained in the NRC
Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted
Use or Termination of Licenses for Bvproduct. Source. or Special Nuclear Material, U.S. NRC,
Muy, 1987. If radiation levels indicate values in excess of the above limits, appropriate
decontamination procedures would be implemented. However, these limits are appropriate for
materials and equipment released for unrestricted use only, and do not apply to restricted
exclusive use shipments. As stated in Section 2.0 above, the shipments of uranium material to
and from the White Mesa Mill will be dedicated, exclusive loads; therefore, radiation surveys
and radiation levels consistent with DOT requirements will be applied to returning vehicles and
c.ugo.
5.0 OTHER INFORMATION
5.1 Added Advantage of Recycling
The Value Engineering Study Team of the U.S. Army Corps of Engineers has proposed that the
Corps use recycling and mineral recovery technologies at a uranium mill to reduce radioactive
material disposal costs (See Attachment 3). The Corps notes that the White Mesa Mill has the
technology necessary to recycle materials for extraction of uranium, vanadium, rare earth
minerals, and other metals, and to provide for disposal of treated waste in the Mill's fully lined
and NRC-compliant existing tailings impoundments.
F:\users\stafl\mn\REVASUB.DOC
Amendment Request
Ashland 2
''**i,':yt:lill
Page I 2
The Corps has found that recycling will add value to the FUSRAP program, and lists the
following advantages of recycling, over disposal:
1. Conforms to Congressional and regulatory mandates which encourage use of recycling.2. Reduces radioactivity of the material to be disposed of.3. Recycles uranium and other minerals.4. Reduces cost of disposal of byproduct from recycling operation.5. Treatment and disposal are performed at one location, and by-product from recycling is
disposed of in an NRC-compliant disposal system, meeting l0 CFR 40 design criteria.6. I le.(2) by-product is disposed of in existing tailings impoundment which is consistent
with l0 CFR 40 Appendix B intent for nonproliferation of small sites.7. Actual cost savings for treatment and disposal versus cost of direct disposal only could be
greater than projected, depending upon quantities of recoverable uranium or other
minerals.8. This technology has been demonstrated on multiple waste streams, and has potential
applicability to other FUSRAP sites.
5.2 Reprocessing of f le.(2) Byproduct Materials Under UMTRCA
From a legal point of view, there is no reason why IUSA should not be able to accept and
process the Uranium Materials as alternate feeds since UMTRCA itself allows such remilling of
I le.(2) byproduct material:
"[T]he Secretary [of Energy] shall request expressions of interest from private
parties regarding the remilling of the residual radioactive materials at the
[inactive] site and upon, receipt of any expression of interest, the Secretary shall
evaluate among other things the mineral concentration of the residual radioactive
materials at each designated site to determine whether recovery of such
minerals is practicable. The Secretary, with the conclurence of the Commission,
may permit the recovery of such minerals. . . ."
While this provision applies only to inactive (Title I ) sites, lle.(2) byproduct material present at
active (Title II) sites may be reprocessed under section 83 of the Atomic Energy Act. That
section regulates transfer of custody of mill tailings and lands necessary for their disposal to
DOE or states upon termination of licenses and provides in part:
"If the Commission determines by order that use of the surface or subsurface estates, or
both, of the land transferred to the United States or to a State under subparagraph (A)
would not endanger the public health, safety, welfare, or environment, the Commission . .
. shall permit the use of the surface or subsurface estates . . ."
F :\users\stafl\mn\REVAS U B. DOC
o
Amendment Request
Ashland 2
License SUA-1358
May 8, 1998
Page 13
Certification of International Uranium (USA) Corporation
(the "Licenseerr)
I, David C. Frydenlund, the undersigned, for and on behalf of the Licensee, do hereby
certiry as follows:
l. The Licensee intends to enter into a contract with ICF Kaiser Engineers, Inc.,9300
Lee Highway, Fairfax, YA2203l-1207, on behalf of the United States Corps. Of Engineers (the
"Material Supplier") under which the Licensee will process certain alternate feed material (the
"Material") at the White Mesa Uranium Mill for the recovery of uranium. As demonstrated in
the foregoing amendment application, based on the uranium content and financial considerations
surrounding the Material and the processing transaction, the Licensee hereby certifies and
affirms that the Material is being processed primarily for the recovery of uranium and for no
other primary purpose.
2. The Licensee further certifies and affirms that the Material, as alternate feed to a
licensed uranium mill, is not subject to regulation as a listed hazardous waste as defined in the
Resource Conservation and Recovery Act, as amended, 42 U.S.C. Section 6901-6991 and its
implementing regulations, or comparable State laws or regulations governing the regulation of
listed hazardous wastes. The Licensee is obtaining the Material as an alternate feed, consistent
for the uranium recovery process being conducted at the White Mesa Mill.
Mav 9- 1998
Date
David C. Frydenlund
Vice President and General Counsel
International Uranium (USA) Corporation
F:\USERS\STAFRMRR\REVASUB. DOC
ATTACHMENT 1
Ashland 2 Material Description, Process History,
Flow Diagram, and Analytical Data
o LINDE
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usAcE/olt/:zr9sGr029
PROPOSED PLAN FOR TIIE ASHLAND 1
AI\DASHLAND 2 SITES
o TOr{AVltt\NDA, NEWYORI(
NOYEMBER 19Y'
Pt P.t dby
U.S. nrmy Corps ol Enginron, Bullelo Oistrbt Officc, Forrnody Utilized Shcc Rctrrdi.l Action Prognam
with tahnbal rp,cbt tr,o lrom
Scicncc Applicadotii tntcmational Corpordion ESGFUSMP
undcr ContrEi No. DE-A@$91OR21950
ffi*ffitffi8ffie,C_ PDft
,]}rt
UNITED STATES ARMY CORPS OF ENGINEERS
ADDENDUM TO PROPOSED PI-AN
FOR ASHI.AND I AND ASHT.AND 2 S]TES
TONAWANDA NEW YORK
o
A revbed proposed plan forthe Ashland I and Astrland 2 poqerUee andAr-ea D of the Seaway
r""ng3,l'[it*1i;[*inr*'""mT.i',U!lltffi lfffi Hilllffi n'B?*l_-_^
ir",ii'ripirJ"t."rt"in sito in;hrdirg ttrese sitca. on octobcr 13, 1997, thc Encrgy and Water Development
#ffi "tr**jn[*;:lml'm'ry"9"1'6#iUS4i:':5[H"ff **
ffi;;d; rouo pro-poecJ-ir"n *o not iacued by oc DoE and thc rceponiHllty for fitb Proiect was
bansfencd to USACE.
USACE ofilcialr recognize thc necd for r tmely rnd cflldcntbamilon of thb ProJocl and the need
for necessary and "pp;;p,i"t;topont"
actons to proceed atqf. siter ln accordance wi61 the
;;;;fi;ir; enriii'n,fi"nuiii"pon"c, compensatbn and LhullU Ad"lzUnited Statec code 9601 et
seq. (cERCrrl. rne[ioi",'UsAcE nas deaoel to procced tog^oposc tfic recponsc acdon recommended
in-frd S"pt"mder t9e7 revtrcC Proposed Plan preparcd by the DOE.
USACE doeo hereby proposo thatthc llnal remedhl acfron forthc Ashland 1 and Ashland 2 and
Seaway lre" O ,*e" bc f," ifts.alivc declgnalcd a1 etlrtlP- ?A and dcccdbed on Pagc 10 of thc
,-"GJp.posec pran.- Ttrb attcmativc b dnsidered by he -us49E b bc adcquatcty coc eflecdve while
iiii"t"g-udnine drtteria prcecribJt cERcut and thi National contngcncy Plan, 40 code of Federal
i"gri"ion" part 300 fNiCl, ino r piotcctve of human hcelth and wpthre and thc ctwlronment ln
pa-ftcut"r, gfdng clmldcration b thc community acceptance criterh, altematvc 2A appcarr llkely to be
iioij a""Litaui to uJ community than urc othlr aftcinat]yec conrHercd for tlrb rltc, bcrcd on extensive
communlcagom betrvecn DoE rnd rcprcentolivc membctt of thc loce! community, althotrgh hb cdteria
*llf not U" finally dctermlncd unfil aftcr rcccipt of commentr from tho publlc'
USACE notee thatthc ranlsed proposod plan prepered by DOE rcllc3 ln ltr ana\pb ln partuggn
certain DoE gutdeltnea wtrich arc not promugateofdudq* and wldch arc not applbable to USACE-
1693| *" g;"d" guktellni OevotopeO uiUril OOg O fovilc grddancc rvl0rh Ont eg.ncV: They are
known as'DOE Order 5{00.5.' ln addition, the revised proPoccd plen preparcd-ry-qgF relles in its
anaryrr upon e Ncwyort stab Deparunentof Eruironmentrl Comcrvrtlon (NYSDEC) guidclinc known as
Tecfinicat AdrInEfrilrp Grfiance lrlemorandum'OAGlt0 Numb.r4003 (198) tttLfi b nd a promulgated
regutatbn and b na.ppdurJo usecg. Byad;p0ng-ano propo*re thc-c.lccilon of thb altomalive as
thc finat rcmedia! "aJrifortrcec Ctco, UsAiE tatiee no pocitonc end meko no rcprcccntatlon, for
purpos.s of 61b r"rg5[ *f"omn or any ohcr, regerdhg thc epgropdatcnctl-of consirlcraton of hese
bOE or NySDEC guUe1nec h *etuatrig orOiaOirU upon trc setecilon of a frnal remedial acton.
USACE knilil mcmbc]t of Utc publlc to rcvlcrvthc fopoccd plan andlhe urppo]tttg documenB
'^fiich further dcccrbc thc condilom at thc sito3 and the badee ior thb popcd. Thoso doc{ments may be
found in tre Adminhtt0vsf,ccod forthccc sites atthc Tonawanda Pub{c lnformatlon Center, 70 Pearce
Avenuo, Tonewanda, N 1a150, or thc Tonawanda Public Ubrary, ln Tonawand!, W:]ktbers of the
public wtro udsh to commcnt upon thb proposed plan may submil their commenB to USACE at the
following addrecl:
U.S. Army Corpc of Englnecs
Buffalo Dh'tld
FUSRAP lnforma0on Center
70 Pearce Avcnuc
Buffalo, NY 1/1150
FUSoi7Pflr0797
o ptease refer to thb proposed plan or to the Ashland 1 and Ashland 2 sites in the comments. All comments
*iii-u" ,"ri.*"a ani consi,er;d by USACE in making its fina! decision upon the remed-ial ac'tion to be
lJijral "t
thce sitee. Comments shoutd ue submitted no later than 60 days afier the date of this
addendum.
After tre cloee of the pgbllc comment pedod, USACE will review all public commont3, as well as .
tne information contrained in thc Adminbfrativo hecord for theae siter, and eny now informalion developed
lirri*rJouring the couso of thb publlc commont perlod, in llght of the requirements.of cERCLA and
td;nCF, A" aufiorized offidal otu3:ncg wifl then make a llnal selccdon of the remedialaclion to be
Iiri,irlal itthesa itos. Thb dctir{on witl bc documentcd ln a Record of Dccicon, h'hich will be bsued to
f,i prOfi", along wih a r6pons. to all commcntr submi[td rcgarding thb popoaed plen.
lf there are any quesdons regarding the comment Pr1oo38., or the propoced plan, please direct
them to the address noted ebovc, ortelephone O16) E71-9660 or 1{fi}'253-9759.
ilfichacl J. Conrad
Ueutenant Colonel
Commanding
U.S. Army Englneer DiiEict, Bufialo
Novsmber 10, 1997
FUSfi7Pnt0797
TABLE OF CONTENTS
RBUISED PROPOSED PTAN.
S|TE BACKGROUND
Descriptlon of he lmpacted Propertes
SUiTSIARY OF SITE RISKS
Radiologlcal Health Rbk .
Chemicel Heallh RbI .
Ecoloeical Rbk. .
sUirnrARY OF REMEDhL ALTERMTI\r/ES '
AMLYSISoFALTERMTN,ESFoRASHIINDIA[.IDASHt^No2....
ALTERMTME COMPARISON . .
ASHI-AT.ID 1 AND ASHUND 2 PREFERRED ALTERNATN/E . .
COiN/IUNITY ROLE IN SELECTION PROCESS . .
REFERENCES ..
o
1
2
2
5
5
5
5
6
7
E
10
11
11
LITIT OF FIGURES ANO TABIES
Fgurcl. TonawandaSltcshowingLocalionsof Ashland l andAshland2.. " " ' 3
niurc2. DetailedVlcrvofAstrnndt @cludingscarvayArceD)andAshland2 ... ""' 4
Tablel. lmplementathnCocillbrAshlendiandAstrland2. .'" 10
FUSOiTPrirOT9T
o REVISED PROPOSED PI-AN
This revised Proposed Plan describes the
prefened alternaWe resultttg from the United
States Depaffnent of Energy's (DOE's)
discussions wi0r the community representalives for
Ashland 1 (vvhich includes SeawayArea D) and
Ashtand 2. A Proposed Plan forthe Tonawanda
Site was issued in November 1993 (DOE 1993a)
for public commentwltich degcdbed the DOEb
prefened altematve for c-leanlng up eleveted
levets of radionucliJes at the Tonawanda Site in
the Town of Tonawanda, NawYork. Numerouc
concorns and commentswsre rabad bythe
community and thelr representatives regarding tfte
prefened altemalive in that Proposod Plan and the
onsite dbposal of any remedial acton waste.
DOE has listened to these oonooms and has had
numerous interacfions wth the communityfs
representralives in Congress (Congressman
LaFalce and hb staff), repreeentalivee locally
[Coali[on Against Nuclear ltiatedalr in Tonawanda
(CANID and their consultantsl, and tfie NewYork
State Department of Environmental Conservation
(NYSDEC) overthe pastyear. The primary
objective of these meelinga rvas to wort together to
reach an agroem€nt on a cleanup approach that
would be proteclive of human health and the
environment allowthe Town of Tonawenda to
move forward wih planned propedy developmentr
without resffidions, and be economically feasible
forDOE.
Thb revbed Proposed Plan (PP) addresses only
the Ashland 1 and Ashland 2 properdes and
Area D of he Seaway propcr|. The Seaway
(AreasA, B, and C), Undc (crnenty Prarair), and
Unde Mcinity Propertel wil! be addrecsed
separately. W'rtr thc ercepdon of buildings located
at the Linde prop€rty, thecc will bc addressed in a
separate Propoced Plan rnd Recod of Decision
(ROD). Romcdh0on of thc lJdc buildings has
been addreesed lcperatc! rdng Engineering
Evaluatons/Cost Analyab (EE CA) documentation
and public revlowr.
Thb plan provilcs background lnformaton on the
Tonawanda site, describa tho altemaWes
consklered in the original November 1993
Proposed Plan to clean up the site, presenE the
rationale forthe selecdon of the prefened
alternative, and outines the publicb role in helping
DOE make a decision on a cleanup approach.
DOE b conducling $is evaluation of the
Tonawanda Site under its Formedy Utilized Sites
Remedial Ac{ion Program (FUSMP). Congress
has authorized DOE to remedlate areas with
elevated tevels of radionuclkles that are a result of
aclivilies athe former Unde proPerty associated
wi[r the separalion of uranium ores ftom 1942 to
1946 under conbact to the Manhattan Engineer
Disfrict (MED).
The 1993 prefened altemalive has been revised
b.sed on the following: lnputftom the community
atbr bcuancc of the predous drafi ProPosed Plan;
dbctoslom wl0t tfie communitfs representatives;
e new deenup gtddeline derivation specilic to
Ashland I and Ashland 2; and three key
documentc asodatcd udth the orlginal Proposed
Plan. The three key documentg were tha
Remedial lnvedgaton (RD repod (BNl 1993)
wirlctr describc thc natura and ertent of arsas with
elevated levels of radionuclftles;the Baseline Risk
Assessrnent (BRA) (DOE 1993b) which assesses
thc riststo pnHic health and thc environmant
posod bythc slte; and the Feasitility Study (FS)
(DOE 1993c) wttlch desctibeg howthe cleanup
odone dbcuased ln the original Proposed Plan
rverc developed and cvaluated. ln devuloping he
altomatlvcc br thb Proposod Plan, DOE has traken
into consUereton the follouving addiUonal
lnformatlon: 1) thc doec obfedives stated in TAGM
,l(XE (10 mrcmrllea0 be$d on lntended land use;
and,2) the 1992 Town of Tonawanda Watertront
Dewlopment lulectar Plan which deecribee the
intcnded futurc land uscs fortfie Ashland 1 and
Ashland 2 sltec. Theeo consUerations aro known
under Comprehcnive EtMronmental Response,
Compcncatbn, and tiat ffyAct (CERCLA) as'To
Be Consilered (IBCs)'.
It b DOE pollc, to incorporatc the values of the
National Environmental PolicyAc{ CIEPA) into the
requhementr of CERCIS for remedhl ac'lion at
sites forwhlch it has authotity. The RI/FS
conducied under CERCII b thc pnmary Procsss
for environmenta! compliance associated with DOE
remedial aclione. Under an integrated CERCLA
and NEPA policy,the CERCIA process b
supplemented, as appropriate, to incorporate
NEPA values.
Thb plan summarizes information that can be
found in greater detail in the reports named above
and in other documents contained in the
administrative record file for the site which can be
FUSo17Pn 10797
found at tre Public lnformalion Center and the
Tonawanda Public Ubrary. DOE and tto U. S"
Environmental Protacthn Agency (EPA)
encouraga thc rublic to revbw tiese documents
for a more comprehensive dbcussion of the
altematlvec tratwere consilered in the odginal
Proposed Plan.
The finatdecision on hs remedYto be
imolemented will bo documented in the Record of
Decision, ROD, onty alier conslderation of all
comments recoivcd and any nswinformalbn
oresented. DOE may modifythc prefened
lncmatrn preconted hcre orselec{ another oplion
from thb ilopooed Plan bassd on newinformation
or public andlot agencry commenb. Thereforc' the
pu6tic b cncouraged b rwiew and comment on all
of the altemalives Hentifed.
SITE BACKGROUNO
From 1942 to 1946, portons of the Unde sitc
(cunen0y Praralr) and a fewsclec{ buildlryr
locateO at Undc in thc Town of Tonawand!' NotY
Yort, wgre usod for sepanton of uranium ores.
These procesCng ecfrificc, conduc'ted undcr e
MED contact, reculted ln clcYatcd lovcls of
radionuclidco ln por0om of lhc propcfi and
buildings. Subosquentdbposal and relocation of
processing waster ftom thc Undc ptopcily reeulted
in etevated levels of ndionuclHes athrce neafi
propedict ln the Town of Tonawanda: the Ashland
I property, the Seaway propoily, and thc
Ashland 2 propefi. Togcthcrthcc four propedicc
are refened to as the Tonawanda Sltc. Thc
localion of Astrtend 1 and Ashland 2 wih rcspect b
theso four properto b strown in Figurc l. A morc
detailed vlew of the Astrlend 1 and Ashland 2 arear
b prodded in Figurc 2. As shown ln Flgure 2, a
smallarea of Seawry, known a Scarvayfuea D,
has elevated levcb of r*nucSca at or nearthc
surfacc. Thb ara b hdudtd h the scope of
Ashlard 1 duebthc c.lcoprorimtty and relatve
ease to remedlato whilc remcdbtng Ashland 1.
W'lthin thb Ptopcod Plan, any reference to
Ashland 1 udth respcctb clcanup Ecope, cost,
and/or volumeo includes thc matelhl located at
SeawayArca D.
Description of thc lmpacted Properties
MED leased a 4 hectare (lGacre) tract known as
the Haist proporty, now called Ashland 1, to serye
as a dbposal site forwastes ftom the uranium ore
separaton process. Wasta were deposited at
Ashtana I from 19*rt to 1946 and consided
prlmarity of loraradc uranium ore tailings.
ilecords indbate ttrat approimately 7,300 metic
tonr (E,0fl) tons) of reetsuec were spread over
roughtytrro{rirdg of the proPerty. !n 1960, $e
Foporty was Eansrcned to Ashlad oil and has
been useO as pail of thb companfs oil refinery
acfird0o cince thettmc.
tn 1974, Ashtand Oll consfruc'ted a bermed area
for trvo pctdeum produci stor.gc tanks and a
drainagc dilch on thc Ashland 1 Prgpcrty.
Appro:dmatcty 4,600 mt 10,000 yds) of soil,
containing radioactlve redduoc and commlngled
MEtlredted inorganic conrfitrentr, wsle removed
during consfirrcfion ac{rd0ea Thc malority olthe
excarnted soil vuas trarcpoiled to Ashland 2 and
Searyay fordbpcal. Thc rtoragc tankswere
removed byAsnnnA oil h 1969.
A porton of tro Astrland 2 ptopcrtyrnc used by
RstrnnA Oil eee lmdllllfordbpocal of gcneral
plant rcfusc and lnductlal and chcmlcal bp
productr. Thc radloactvc reclducr and
tommingled inogmlc comdUcntr remoled from
Ashland 1 were depoCted in an area of Ashland 2
adfolnlng thc Astrland Oll landlllt area. The
industlal landfil! podon of Astrland 2 rvas closed
and covtred nttr day loil ln 19E2 by Ashland Oil.
Cunen0y, thc Asirland 2 propclty b vacant and is
corercd by e vegetatw growh (e.E., grasa'
buslrec, and rveeds); no oommercial operations
arc atncnty bcing conducned.
Hkilorlc.llnvecdgatbns of Ashlard I and
Astrland 2 dbcwsed in thc Rl lndbatc trvo sources
of elevatcd leveb of radlonuclldes at each of these
propertct: sudaco and subcurfacs soils. The
primary radionuclileo ln thc coib arc Ll'23E,
Ra-226, Th-230, and their recpecfrvc decay
producls, and the associated MED'releted
chemica! consfituenB (c.9.. copper, lead,
vanadium). Thcsc matcrials arc thc pdndpal
Constituents of Conccm (COCs) for Ashland 1 and
Ashland 2. There were other conslituents
idenlillcd and consirlered forverbuc modas when
performing the &k assessmenB (DOE 1993b).
o
\\\
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I
+ FSrffEEr
-- iDlurEhtrtlt.-- thr.aCtrIla
Iffi6q
&)
slrEFlD llAr/E.
l\a
!ilrEHO N nP{rir(r/lrcl'l
Figun l. Tonawande Sitc Showlng Loc.tlon3 of Ashlend 1 lnd Ashhnd 2
FUSotTP/'ti0797
irlrErrt tn^$l3cil
!IIi
E
o
-.---4----
rt
TaatI
t
-!I
!
tt
I
Figurr 2. Dctelhd Vhw ot Ashhnd I (lncludlng Scewey Ane D) and Arhhnd 2
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SUMMARY OF SITE RISKS
The BRA was prepared to evaluate tre rbk to
human healh and tho environmentfom he
radioac{ive and chemkal conslifuenE at the site.
ln accordance wih EPA guUance, the primary
health rbks invedigated rverc canoar and other
chemical-related illnessoe as well ag the ecologlcal
rbk. Thb ass*ment evaluated the potenlhl
ftkr that couH dsvolop in the abcence of cleanup
and assumeo that no contsob (e.9., fencing,
maintenancc, protoctive dothlng, eb.) are, orwill
be, in place. Thc purpocc of the BRAwasto
detsrmlnc thc nccd for cleanup and proville a
basellne againstwttlch tfte remedhl ac{on
altcmatlveswcre oompared. Thc complete repofi
b ln thc admlnhfratire record llle and a brief
summery of the radiologlcal and chemical health
riskr as well as the ecologlcal rbks b provUed
herein.
Thc BRA Hcntilled the means by$rhlch peofle and
the environmcnt may be exposed to conslituenE
present atthc Tonawanda sitc. ltlathemathal
modelswere rced to predlc'tttrc possibla effecls
on human hcalth and thc cruironmentfrom
erposure to alcveted lwcb of radlonuclHea and
chemicals for both present and futrre uses at he
site. Thc modelcd rU< eetimatec rvere then
comparcd to an EPA-eltablbhcd trget &k
range- for cancgr inddenco (.e., the oxcess
probaUlity that an individual would dwelop cancer
over a llfclime as a r6ult of being e:eoaed to the
contiaminants atthc site). EPA hs establbhed the
generally acceptable terget ilrk range for exccas
cancer incilencc from a fgw h 10,000 to 1 in I
million.
Rrdlologlcrl Hlrlth Rlrl
Thc BRA proddo rblt ee0mabc for average
(mcen) oxposut condlthm undcr hpothelftrl
scenarbr for qrrcnt and prolcciled fufure land
use. Thesc €€ffii.tld rkftr erc calctlated usilp
the average redonuclldc concenbatlons present at
the propertcc. The reaulb predlciod that, for the
cunent land utcc, no onc rvould be oposed to
unacceptable rbks. For assumed future land uses,
the mean radiologkxl risk, aswa! reported in the
odglnal 1993 Proposed Plan. was predicted to be
wihin thc EPA range of acceptatitity at all
properlies.
EPA requires that the modeling also include what
is called a Reasonable Marimum Exposure (RME)
scenado. These calculatons assume that an
indivirJualwould be exposed to the constituenE on
the propedies for prolonged periods. For current
land uses, he modelpredicled that exposura
would not erceed the EPA range of acceptability
for the Ashland properlies. For some future land
usc acenerios, calculated RME rbks erceeded the
brget risk range at both Ashland 1 and Ashland 2
propertes wlrich served to support the need for a
remedhl acilon.
Ghomlcel Horlth Rlrk
The BRA evaluatod cancer and chemicaltorici$
rbks. The rbk of developing cancer over a7O-year
lifetime fiom chemical carcinogens attfie site was
evaluated for both averago (mcan) exposuro and
for RME. None of the eslimated cancer rbks
erceeded thc EPA ftk range of acceptatrility for
cunent or future land uses. ln addi[on, no
unacceptable efrects nould bc expected for non-
cancsr chemical illnesses under cunent land uses.
The potanthl for chemhat noncarcinogenic haalth
efiectc b e:gressed as chemical-specillc hazard
quolients Gas). HQs were tabulated for all
chcmlcab of concem where reference dosas or
refercncc concenhatlons ar6 cunenty avai! a ble.
HQs are summed for each pathway to provide a
totalhazad indcx (HI) forthe pathway. The
calculated Hls for all erposure pathways for all
scenarlos emluated atAshland I and Ashland 2
are muc-tr les tfian 1 thus lndhaling that no
unaccc@Uc efresls nould be opccted.
Ecologicel Risk
The Ecological Rbk Assassment for the
Tonawarda BRA follorvs EPA's general
procodurea for ecological asseasments ln the
Superfund program. The characterizaton of
habitaB and biota at ftk are semlqualitralive, and
screening of COCs and assessment of potenlial
impacts to biota are based on measured
environmental concenf alions of the constitue nts
and toricological effects reported in the literature.
The Tonawanda Site b located in a highly modified
urban, industdalarea. Unde, Ashland 1 and
Seaway provile minimal urban wildlife habitat
I
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I
FUSo'|7Pnl0797
suDoolling only cosmopolitan speciec of tirds and
"niirf
m.mmab such 6 crows, gulls, and rats'
GrrlanO 2 supPorc a more divese animal
"ommunity
Oocause il contains a mosaic of
veoetated traHat typos including woUands
ivtioroqically connec'ted to RaUesnake and
iGmin Creeks and the Nlagara River'
Based on publbhed aquaticand oml toricity data
il hJ;"Ufity and porsidence-properlles' 33
I*r*icaf COd rverc ilcnlifcd: 3 radbnuclilel'
,i-;;t b, 7 volalile and 2 semlvolalile organics'
ilil"ry meteb, eepct*rlly cop.P"t: 1"3td'
iiii"irt,.r.r, Yanadlum, ind dnc ln Tonawanda
;;;;td' lolr and utrfeco rvatcr rucre thc
;;;I&--rr* of ecoloobal rbk b tenesfrial and
;;r"& D"rd.lbn3'erQcura bylrueslion of *ilr
il didl i"ntact wih surface wates' Although
no threabncd or endangered spedes were
UinUrf"O, h the absenco of remediation, both
*sit" and olhile organixns and populations at
ionrrvanO" properti-es uill contnue b be at rbk'
;ffil"tty dt nlrrano 2, wlrere wildtfe and natural
hatitatr arc more extencivc.
SU IIiTARY OF RETEUAL ALTERTiI.ATTVES
Detailed dccrip0ons of hc remedlaldtemaWes
for the Tonawa-nda sitc, includlqg the Ashland I
and Ashhnd 2 propcrlhc, can bc bund in tic FS
nhlch b aralade tir trc admlnhfratve record' ln
thc 1993 FcadUliU Strdy end Ptopoeed Plan'
referencc b made to DOE guHelinea for cleanup'
Thcac ar5clnc wcrcthc gcncrlcguile-t!9a in
DOE O-rdcr54OO.5 (rtfiicfi llmltBth€ Ra-226 and
Th-230 conccntsatonrb 15 pCilg, each, in tie
subsurfacc) and can b. u!.d without further
evatuallom. Stte+pe* gt#cllncl arc also
allotvcd lf addilonal anallna arc pcrformed to
demomffir thetthc dcc obfccfirm dated in the
DOE Or&r lc mct Thc lb{g.dfrc guilellnc
estabfirhcd brthc A.hhnd 1 and Arhland 2 sltrc
pursuantblhc DOE Otdt mdthc docc
bU;cctra o[lh. DOE Ord.r b] rclcllc wih no
raitotog&a raficilonr end thc docc obJectvec of
the i$fSDBC TAGM 4003 br thc mndsd ftrture
lard usa adellncd ln thc 1992 To*n of
Tonawanda Watcrftont Danlopnent Mader Plan'
Both thc genedc and Ctc+pctillc guUelines will
meetthe appllcable or relannt and appropdate
requircmelilr (AMRI). As a pofrrtof c{arificatbn,
wlrere the DOE Order generic guidelines were
used for an altcmalive, they are refened to as
'osneric' guidelines. Where the site-specific
o-uideline b used for an altemalive, ilwill be
iefened to as the'Sile-specific'guideline' The
following are summaries of those altematives
consUered.
Attemetivo 1: No Action. The no-action
afemalive b required under CERCI-A and NEPA
reoutation to provide a baseline for compadson
v,fri other altematives. Under thb altemalive, no
i.ton b trken to imptement remedial aclivilies'
Perlodlc monltorlng of the levels of the COCs in
approprhto medla b contnued.
o
Altrnrrttvr 2: Compbtr Excrvetlon with
Ofiftr DlrPorL Cbmplete excava0on of MED-
relatcd soili containlng radionuclHee above
grHif lncs (generlc guHellnes) and oftsite dbposal
ioutd rcm&s the source of elevated levels of
radlonucliles ftom the site. Remonal of material
containing radionuctHec above guUclines- in or
near ws[iM areas rvouH bc performed during the
dry season to minlmize the need for diks and
U"*t; compensatory wetands would bc created
for th*o we'Uardc desfroyed, lf any, under this
altomativc. Thb altcmatlve would protcct human
healtlr and the cnvironment and wouH meet
"ppll""Ut"
standarde rcgadlng acceptsble leve ls
of resHual radionuclHer.
Altrrnrtivo 3: Complde Ercrvrtlon with Onsitc
Dlrporel. Slmltarto Altematlvc 2 regarding
ercirnton of sollg, how€vcr, allercavated soils
nouH be placed in an on'stte dbposal-cell'
ingttr0onif contsolrwould bc amPoEcd to conbol
."""to to the onsite enginecred dbpooal cell and
thc cell would bc darbned to minimlze lirture
oxposutes or release! to the environment'
nfomU" Sandards regardlng accepbble levels
oi iesilual radionuctiteg vrouH be met
Altrmetlvo 4: Prrtlel Ercrvrtlon wlth Offsitl
Dlsporet. Similar to AltemaWo 2, ercgpt
"idomn of MED{mpecied coilswouH involve
only troso soils contrining radionuclHes above
suii"fln"" (generb guideiines) that a1e accessible
I.e., not under landflll materlal, buiHlttgls' or
Lrmanent structur6). Thb altcmatlve does not
[r""t ",O"tng
applicable standards for levels of
r""Uu.f raoioniritUos acceptable for unrestricted
use. Thereforc, resfficfions would be required on
the continued uso of areas of these propeilies' or
;i6"t" concentalions woutd have to be iustified
for soils left in place containing radionuclkles
above quUolinc h areas to be released for
,r,i""tri-a* nsc. For the Ashland 1 and Ashland 2
orooerlie, il appears that all lmpacted soils are
L"clssiUte thus making thb altemative the same
as Altemalive 2.
Alternetivc 5: Perthl Ercevetlon with Onsito
Disoosat. Same as Alternalive 4, ercept all
excavated xils rvould be placed in an on-site
enoineered dbpcd cell, al discussed in
Rttimatv-c a. Tltb altemathlg doeg not meet
ari$ng aipmeUc standadr for acceptablo levelr
oi resiiuiinOlonudHes for unretfiic'ted ugs at the
o*lite dbposal cell. Therefore' rostictions would
be required on lhc ftrUro uso of areac of thecc
propertea, or attemate concentalions would have
io deJu*neO forsoils lefr in placecontaining levels
of radionuclHes above guileflnes in areas to be
released for unresfricted use. For the Ashland I
and Ashland 2 propertes, it appears that all
impacted soib ire accessible thus making this
altimatlve the same as Altemativc 3.
Alternetlvc 6: Gontllnmcnt with lnrtltutlonel
Conttolr. ContahmentwouH involve capping all
acceadUe soilr. Removal of any matcdal
contalnitp radlonuclHes abole guilellna (generlc
guklelinec) from rYstand areas would be
pertormed dumrg the dry season to minimize the
heed for dlkes and berms; compensatory wetands
would bc creabd for thoce wetandc desfroyed' il
any, undertib altemativc. Thb altcmalive wouH
pr6tea human hcelth and thc cnvironmcnt by
eliminaling axposuro pathrvayt. lnst'tutional
conEolswould be requircd to preventfuUre
accessto and dkfrrrbancc of thc Contained wastc.
ApplicaH. gtendards regad&rg rcCdual levelg of
ridbnudHeowould not be met Therefore,
resfriofionswouH be required on lhe frrfure use of
arear of these popertes, or altcmatc
conccntsatons ruould havc to be Jus0lled for
inaccesiHe sols l6lt h Placr.
Alternetlur 2A: Comphtl Eravetlon with
Offsitr Dbpocrl (urine rlb'cpcciflc
guidclinc). Thb altemallvc, although not
ipecificallydbcurs.d in thc 1993 ProPoaed Plan'
istre same asAltemaWc 2, excreflthe guideline
used was devoloped speciltcally for the Ashland 1
and Ashland 2 sltes, Yollus the genedc guidelines
used in Altemahre 2. The sitetpeciflc guHeline
was developed lo safsfy the 10 mrem/year dosc
objeclive dated in NYSDEC Technical
Ad-minisfratVe Guilance Memorandum OAGM)
4003 for the intended land use as delineated in the
1992 Town of Tonawanda Waterfront
Development Master Plan. Soils erceeding the
site-spicific derived gukletine of 40 pCi,/g Th-230
(DOE 199D woutd be ercavated and shipped
irffite for commercialdbpoaal and the site
restoreO wiUr backfill,loam, and seed to condilions
wtrich achieve the NYSDEC TAGM 4003 dose
oblectvc of 10 mrem/year for the inten{ed tuture
taid uso as dellned ln the 1992 Town of
iona*anOa Waterfont Development Master Plan'
AMLYSTII OF ALTERNATTVES FOR ASHI.ANO 1
AITIDASHI-AND 2
Tho altematlvcc described ln the prcvious section
*iie iv"tu"ted using CERC|Acriterla and NEPA
otr"s to determine tho most favorable aclions for
cteanup of the Tonarvanda site. These crfteria are
described below. Theywere establbhed to ensure
fr* t e remcdy b Proiectlve of human health and
tftc cnvironment, mactl rcgulatory requirements, b
ofo cfiectve, and utlEcc permanent solu0ons and
tseaEnent b tire maldrnum extent practcaHe' The
recutE of the detailed oraluatlon of altemativesto
remedlatc the Tonawanda Cte arc summarlzed ln
the following sec{on. Key elemenE of the
evaluaton are dbcussed.
Gtosery ol Evrluetlon Crltrrir
M ftotocilon of Humtn Hotlth tnd thc
Ervtrcnmolll - addrcssos whetfi er an
altcmatlvc proddcc adequate protecton and
dactibc ]iow rBkc arc eliminated, roduced, or
contollod through teatnent, engineering
contols, or insfitutlonal contols.
Cotrptltnco wlth Fcderril end Slrtc
Ermdronnrrrthl Rogulrlfrorc- addresses if a
remedywould meei all of the ARARs of other
Federil and Statc environmental larvt'
LongrTrrttt Eficctlvonoss tnd Pcrmtncnce'
"OOri.s""
the remaining rbk and the abili$ of
an altemalive b protecl human health and the
environment ovei 0me, once cleanup goals
have been met
Sho rt-Tum Effccllvcn*s tnd
Envlronmsrttt ltrpr,cts - addresses the
impacts to the community and site workers
FUS0i7Pfit0797
during cleanup including the amount of time it
takes to comPlete the aclion.
, Ro&tcdon ln Toxlclty, lfioblllty, or Volumo
through Trodrnuil' addresses the
anlicipated performance of teatnent that
permanenUy and s[nillcanfly reduces torkity,
motlilitY, orvoluma of wade.
, ltngfunutt bltifi-addresoecthctechnlcal
anb aOminhta0na feaJUlfi of an altcmatlvc,
includlng thc availabiliU of matorlals and
sswices required for deanuP.
. Cod- comperos the dlfrcrences in cost'
includlng capltsl, opcratlon, and maintenancc
costg.
. Slltr A ccqttnco - erraluates whether the
Stato agreec wiUr, oppocer, or hae-no
commeht on the prefened altemallve.
. Contntntty Aecqtillnct- addresses the
issuec and concerna the puUlc may have
regarding each of thc altsmallvcs.
ALTERNATTVE COIIPARTSON
The purpose of the following analyds b to weigh
the aOvantagec and d&ndrnntaeo of thc
altematvcs, when comparcd witt each other,
besed on the evalualbn criterh. Thb informatbn
b us6d to select a prefened altemahlre. The
Feasltili$ Strdy Altemallvc 4 and 5 arc not
included-Cncc irey are tho temc a3 Altematlva 2
and 3, respodivoly, forthc Ashland 1 and
Ashland 2 proPertlca.
Ow'atl furedln of Hunarn tteaffi arld ttc
Errilorunq* Thc altsmallva provldktg complete
excoatton of cdb contrHm rrdlonuclldec aboo
guklelineo, spcdllcallyAltometvc 2,2A and 3'
prwirlc thc grc&C dcglco of protecton to human
healh andthc cruironment hduding thc
ecologbal ryCcm, bccaurc thc materlals
containing radlonuclldo aboo guldellnes arc
removed ftom tlrc rftc and pcnnencnUy bolated ln
a dbposa! hdllty. A dcgrcc of rUr to rvofiers b
involved with implementng thcc altemative3, at
well asthe other remedial acton altemativee,
because the associated rvofi involves intusive
aclfuiUes for handllrq and moving all materials
containing radionuclkle above guklelines at the
Tonawanda site. These risks can be minimized by
using safe$ procedures and equipmenl .
Alteirative 6 provirles protec-lion by reducing or
eliminatng certain oxposuro pathways. lt ralies on
insitutonil conEols to provUe protecton of human
treamr and the environment Altemalive 1 proviles
no increased protecdon over the cunent site
conditions and will not be protecllve of human
heatth and the environment orertie long-tarm for
forcceeablc lald usca.
@milrrrn wilh ARARs. AltemallYs 2,2A arld 3
mceinnenc bccaurc all soil contahittg
radbnudHa ercccdlng thc guilelinc (genedc
end cftc<pcdllc) ruould be crcavated and
permanaity boiebd ln a dbpcal coll or fltility.
The otrcr aitamalivcc, allof wtricfi invohr€ leaving
somc soil containlng radlonuclida above
guHetiner tn placc, would not comply wiUt ..
iecfrictbm on recUual conconbellom in soils
unlcss crfterla sdfoili h /30 CFR 1{2toc
e$ablbhlng dlffercnt finderds are met
Ntemallvc 6 rvould abo rely on cCab0ehlng
diFerentdandardr ndng hc criterb sdbrth in
40 CFR 192. Altcm.firc 1 b noncomplhntud0r
AR/Afu bccaus rllrvailc contahhe rrdbnucldes
abolc guHalines rcmelm ondta tfh no additonal
protecilon prwUcd.
Lorg&rm Efledveness nd PemslprrcP. A
pdmlry mcaaurc of thc longrbm cficcdv.elass of
Ln aftehatve b [re magnihrde of psilual rbk to
human hcallh aller remcdhtion. Thc adequacy
and relhtility of engheering and/or insfitrtonal
contob uccO to menagc residual matedals that
remaln oncib must aho be consHered.
Altcmetlvu 2,2Aard3 havrcthc hlgheddegree of
loryrlcrm efiectlvenccc and permanence because
all aolr contalnhg radlonudHee abole genedc
guHellncc, orthc sib+pecific guilefna, are
&cavatrd and rcmond from tre sib, or Placed in
an engineered dbPocal coll.
Altema0vc 6, contalnmont has a hlgh degree of
efres{ivcness, but rcllsg on long-tcm management
to cnsure that erpoeurc pattrwaya remain blocked'
Thc magnlEdc of rcilual rU<and crPcurecto
human health and thc envlronmentbdirecdy
relatedtothe adequacyand rellaUfryof the clay
cap and insfilutonal contsob.
For Altematves 2,2A,3 and 6, dsk calculated for a
worker involved in maintenance ac{iYt'lies at any
FUSOrTPrtrOTST
disposal cell or capped areas for a pedod of 25
veas b similar to he general public's health risk
ituring remediatbn and b wihin acceptable levels.
Alternalive 1, no ecilon, has low long-term
effecliveness because he pod{mplementaton
remedial risks equal hose now at the site.
Shoillem Effe&eness md Envircnneilal
lmpads. Short-term effec'lhrunesa b measured
wiUr respectto protec-lion of community atd
workes as well as slrort-term emironmental
impacG during remedhl acdons and tmc un0l
remeOiat ac{ion o$ecfuee are achieved. An
increase in the complerlty of an altemathn tydcally
results in a decreaso in short-term efiec{fveneas
because of increasod handllng and processiltg.
Also, attemalives invoMng oftite dbposal of
wastas would result in a decreasc in short-term
effediveness because of the incraased tme
requirad and bansportaton<elated ftks.
Altemative 1, no ac{ion, btrc mdefreclhru ln
protec{ing the communtty and workers and
contolllng impacts during implementation since no
ac{ions that could craatc impactr arc undertakcn.
Altemative I requiree he shodesil 0me to
implement The short-term effecliveness of thc
other altematives rank ln thc folloving orden
Altemalive 6 (containment), Alttmehru 3
(complete excavatlon and on-eite dbposal),
Altemalive 2A (complete ercatnlion end ofrite
dbpoeat using site+petillc guilellne), and
Altemalive 2 (complete excavaton and oftite
dbposal using genedc guilslinee).
Redudon in Toxlcfi, filiffiy, q Volmp through
Trefrnerrd. None of the altcmallves providec
treatnent on site br the matarhb to be remorcd.
Altematives Z,?Aand 4, u,hldt proddc for some
degrec of offdte dbpGel, will hdtdc contalnmant
atthe final dbpoc.l loc.0on and enyEea[nent
h'hich b raquhed to mcctthc dandadc of the
ofrlte facillty. Thco atEfnatws thus will achlew
reduc[on in mobltry, allhorph no teatnent b
planned which will rcducc ttcto:dcffy orvolume of
the dbposed materhlc. Thc rcmaining altematives
would provirle eiher no removal of materials, or
disposal onsile, wtrich rvouH also limil motility
through desfin of he dbpooalfadlity. The
Feasitrili$ Study evaluated ctnen0y aveilable
treatnent technologies for Eeatnent in the couse
of removal and found nont ero economically and
technologically feasible atthb time. Thus the
prefened altemative achieves the best possible
result in regard to thb criteria.
tm pleme ntability. ln reg ards to im plementa bility'
the altema&es were evaluated with respect to the
following:. aUliU to consfrttct and oPerate he
technology,. rellaUlrty of the technology,. oase of undertaHng addltonal remedial
ac'lion:,. atrility to monltor effec{iveness,. aHlityto ohin apprwals and coordinate
wtth reg ulatoly agencies,. aveilabiliV of ofislte dispoeal seruices and
capacity, and. avallabiliU of necessary equiprnent and
specialbts.
The degree of dfficulty in implamcnling an
altemative increasestvith the complerity of the
remedhtlon activity. The design, engineering, and
admin$atfue requircmcntrof Altemative 1, no
acdon, arc eseentally negllgiblc. The remaining
altemalivec are all tcchnically and adminbfiatlvely
feaiHc. The enginccring, dedgn, and
admlnbfatlvc requlrcmentc increase wih the
complerity of the altcmativa in the following order:
Altemalive 6, containment wiUt insfitrlional
contots; Altemative 2A, complete excavalion and
ofisite dbposal (us&tg Cte.specillc guHeline);
Attomative 2, complete excavaton and oftsite
dbpcafi and Altemathn 3, completa elcavaton
and onsite dbposal.ltlatedals and seMces forthe
varbtts altemalhros are rcadily availablo. The
degrec of difficuttyin implementng these
altcmallwc lncreas€swith thc amoutil and type of
soils b be excavated, thc level of permiHng
required to consfrtrct new dbposal facililies, and
thc distanco to the selected dbposal facility.
Cost Thc comparative analysb of cosils compares
the differcnccs in capihl, operations and
maintenancc (O&M), and prescntworth values.
CosG for each of he altemalives presented in the
odginal plan have been prodded ln detail in
Appcndbr G of thc Feasitillty Study. These costs
were brthc entre Tonawanda Slte, notfust
Ashland 1 and Ashland 2. Since the complelion of
the orlginalProposed Plan, thc cosdng
methodologty has changed, primarily in the area of
assessing program management costs.
Mditionally, a more detailed analysir of volumes of
soils containing radionuclHes above generic and
FUSOi7Pflr0797
sile-specillc guilelines has bean conducted using
threc{imenebnal modeling. These new
estimat6, bac.d m 1997 dollas, have been
mado tor tfte Ashland I and Ashtand 2 propertes
only. Table I pcents hc cunent cost estimates
forthe Ashland I and Ashland 2 altematives.
Sfafe Accey'ance and Comm unity Acce ptance
These criterion are not evaluated formally until
comments on the Proposed Plan are reviewed.
o
ASHIAND I AND ASHLAND 2 PREFERRED ALTERNATIVE
DOE prcfer Altomatfoc 2 , @tn&te Ercavafiottwitt O/Eita Dlsryd (ushrg sfb,specflrc
Ottdr#pg. Tldl altomathlc meoEthc
commiEnentr med. b thc communi}
reprecentatvcc and b bclar.d b provklc the bod
batancc among thc consldcrud albmatvecwi[r
respectto tfic evaluetlon crilrh, wilt protect
human hcelth and trc cnr&onmcnt and will
complywi0r ARAfu wfiilc prorddtrg forthc releasc
of propcrty for lirtro ur rvtrrout rny rrdlologicrlresfrlctom. Spccl0c componarb oi thc prefined
altemallvc arc hd bclog-.
. Brcavatc rolr contrhkrg h crccre of lhc
40 pGtg Th.230 guilcllnc etAshland I(ncluding SoweyArce D) end Ashtand 2,
ac dccdb€d ln thc sftc epcdtb document
entUcd'Radonucllde Gleanup Guideline
Dedwtlon forAsland l, Ashland 2, andSeawaf.
. ShlpoGite forcommerdal dhposal
excayeted soils cxceedlng 40 pCUg Th-230.
. Restore the sites with backllll, loam, and
sa€d to condittbnr tt'hlch will acfilow the
NYSDEC TAGM 4003 dosc obJedive of
10 mrem/ycarfortfie iilondod ftrture land
ulto as delined in thc 1992 Town of
Tonawanda Waterfront Development
Mastcr Plan.
Alttough notthe lea$ expensive altemalive (no
acdon, and containmentwere ecfrmatcd to bo
lower cost altcmatlvue), it b thc lcast ergensive of
thc optlonrwhich are proteclive of human heatth
and thc clMronment and moet DOE!
commi[nentc of using ofrrle dbposal and allowing
forthc dwelopment and ftrture use of the
remediated propertec.
Tebh t. tmphmentetlon Cortr forArhlrnd I end Ashhnd 2
Comflete Ercavaton and Oftite tIspcal
(Generb Guileline)
Complete Ercavaton and Ofrrte Dbposa!
(using slte-opecific guidellne of 40 pCUg TIF23O
GuUeline)
Complctc Ercavaton wih Omite Dbpooal
(Genedc Guldeline)
E- /ss87
Formerly Utilized MED/AEC Sites
Remedial Action Program
Rdiologlcal Suwey of the &hland Oil Company
(Former Haist Propertyl, Tonmsrda, lllew Yorlr
May 1978
Final Repon
Prepared for
U.S. Department of Energy
Asistant Secretary for Environment
Division of Environmental Control Technology
Washington, D.C. 20S4S
Under
Contrast No. W-7405-ENG-26
7
E,
I
iii
CONTENTS
LIST OF FIGURES.
LIST OF TABLES
ABSTMCT .
INTRODUCTION
RADToLoGICAL suRvEY TECHNIQUES '
Irleasurement of External Gamna and Beta-Gasma
Radiat,ion Levels
Measurenent of Radium in the Soil'
Measurenent of RadioactivitY in Surface l{ater'
Radon Daughter l'leasurenents'
Background Radionuclide Concentrations
SURVEY RESULTS
in Soil
External Gauuna and Beta-Gamna Radiation Levels
Results of l{ater and }tud Sanple Analyses ' '
Concentrations of Radionuclides in the Soil'
8
9
10
t2
a
1v o
7
7
I
8
Radon Emanation.
Radon Daughter Concentration in the NFG Building 16
16
SUMI-IARY.
REFERENCES
20
5l
59
63
APPENDIX I -.
APPENDIX II.
APPENDIX III
o
155"
'\
was 8.3 PCi/g, in a sanP1t : Fig . 7), which also
containsdrainagefrontheresiduesonSeaway.nllot,hersamplestaken
fromdrainagePathsleadingfromthefonterHaistProPerty(andcrossing
the Seaway ProPerty) showed less than I pCi/S radiuo' and the radium
concentrationinsanplescollectedwithinSooftoftheboundaryofthe
site averaged abou t 2 p}i/g' Since nost of the drainage fron the
formerHaistProPertyiscarriednorthwardtowardtheNiagaraRiver,it
aPPearsthatonlysnallquantitiesofradiumatecarriedfronthesite
in surface nur-off'
Aconcentrationofnaturaluranirrmofapproxinately25pCi/gwas
found in a m.rd sanple taken near the Haist property (M9) and in a
sampletakeninadrainagePath(M8)over2000nfronthecenterofthe
Haistsite(seeTablelandFig.6).Thehighesturaniumconcentration
found in the mrd sarnples (32.5 pci/g) was from a sanple (M5) taken near
the residues toweld the east boundary of the Industrial Park'
Theconcentlationofuranium,radiua,andthorirrninwatersanples
from Ashland and Seaway and from drainage paths leading to the Niagara
RiverisgiveninTable2,whichalsoshowstheconcenttationguidefor
each isotope considered. Locations at which the sanples were collected
areshowninFig.6.Ineverywatersarylc,theconcentlationofeach
isotope considered ras at least an order of magnitude below the cGr'4
co,i""t""tions of Radionuclides in the Soil
Concentrationsofradionuclidesinsoilsarnplesfroncoreholes
collected on the site are listed in Table 3; locations are shown in Fig' 5'
InTableS,thepartofthesamplenrrnberprecedingthedashgivesthe
location; for exanple, sample 15-C is from core hole 15' Gamna radiation
1I t{Ta /
levels in core holes are listed as a function of depth in Tab1e 4 for
core-hole locations at which no soil samples were taken. These scintil-
lation probe readings are used only to give an approximation of the
depth of contanination in the soil'
The average concenttation of radium in soil sarrples taken from
section Nl{ was approxinately 13 pC;i/g. Highest radiun concentrations in
section NW were found.near the surface at location 66 (137 pfii/d and in
a region including,locations 47,48, and 49, where there aPPears to be
tailings extending fron the surface to a depth of 4 or 5 ft. The
concentration of uranium at location 49 is 0.24N by weight between 3 and
4 ft deep. At location 66, the uranium content near the surface was
O.OBI by weight ot 2.57 pCL/g. The average concentlation of radiun in
sarples taken at depths of 0-4 ft at locations 47, 48, and 49 was
about 37 pli/g,.
rt appears that nost of the residues have been reuoved fron Section M' O
Radiunr concentrations in the 50 sa.urples collected fron this section
averagedapproxinate1y18pCi/e;however,inWu'.
depth of 4 and 5 ft cont"in! _1. 2!g3gi llost of these samPles were
taken from dike I which was built using soil fron the site. Ttre remain-
ing sarples were taken fron locations 40, 42, and 43. Sone sanples from
several feet below the surface at locations 40 and 42 showed radiun
concentrations of'50 to 160 pCi/g.
' Radir.m concentrations in soil sanples fron section SE averaged
approximately 35 pc;i/g and were as high as 508 pci/e. Highest concen-
trations were in a nearly rectangular area estimated to be about 200 ft
o
L2 ft5$1
o by S0 ft and including locations 1, 2, 3, 4, 6,--.19 19, and 37 (see
Figs. 4 and 5). In this same area, the concentration of ry: *"t
found to range fron normal terrestrial concentrations to-399.9-Pg!l&g
0.g3so by weight. The depth of contamination ranged to aPProxinately
7 ft. Records indicate that sludges frol uranium ore Processing were
dunped in this area (see Fig. 1). According to soil sarnple analyses
(Table 5) and core-hole loggings (Table 4), at least part of the sludge
renains; it is covered by 2 or 3 ft of relatively uncontaninated soil
and extends to a depth of 6 to 7 ft in ,nost Places. sanples fron several
other parts of section SE contained over 100 pC,i/g radium; these sa^uples
were usually taken from depths of 4 to 8 ft. The NFG building is near
the edge of a tailings or sludge pile which has been covered with clean
fill dirt.
Radiun concentrations as high as 259 pCL/g (at locatioa 27 at a
depth of 2 to 3 ft) were forurd near the building.
Radon Ernanation
The average radon emanation at the surface near locations at which
soil saruples were taken can be estinated fron data in Tab1es 3 and 5 and
Fig. 13. As an illustration, the radon enanation fron a tailings pile
containing locations 47, 48, and 49 was estinated. In this area, the
cont,arnination is, for the most Part, fron the surface to a depth of 4 or
5 ft. The average concentration of radium found at locations 47, 48,
and 49 at depths of 0 to 4 ft was about 37 pCi/g. Assgning that the
tailings are moist for nost of the year, it nay be seen fron Fig. 13
that a 4-ft Layer of these tailings would release radon at the rate of
22
aa
alt
l',oI
2
E
dxu't })c,r l..-a C,qco.a t{Ax.r9kl^Ol '.io.(l6tr.0.tro
2
PlnP.r{ h(ll0
=S";c4tnoor}r,ruttooo .c,9 c.;ado.-r tr .d.'< O +rql! Orr(ltJt,l+a th
" b'EC O'rt.et€Pvr<-3. ,;.atOt{(!O
6E >..{PkE ,-. O)d(aO' Q'+r:I:*1d6t.=..bXOtrooQf.t (J
Er.5iro o<cn P
-:
n
t'l'
raGui9,
iisl"ieieEpeeJtll-GTJJ
EMN U
iti3l!>
-o9i:d|aa.it:
2eE<)Grl
25
oo(\,
I
@
(9
=o
I
zGo
oo
o
ot{oo
(+a
o
o
o
c,UoJ
s
a0
l&
N
(\tN
38
Table 5. concentration of "6*^,in core hole samples
232h, ,ttu, 227 A", "nd
4oK
Sample Depth(ft)
238u
lpci/ e)
227 .AC
lpci/s)
4ox
lpci/s)
226_RA
232Tn
lpci/s)lpci/s)
0 - 0.5
.0.s - 1.5
1.5 - 2.52.5 - 3.5
5.5 - 5.05.0 - 6.0
6.0 - 7.0
-0 - r.0
1.0 - 2.0
2.0 - 3.0
5.0 - 4.0
4.0 - 5.0
s.0 - 6.0
6.0 - 7.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
4.0 - 5.0s.0 - 6.0
6.0 - 7.0
7.0 - 8.0
0 - r.0
1.0 - 2.0
2.O - 3.0
3.0 - 4.04.0 - 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
4.0 - s.0
5.0 - 6.0
6.0 - 7.0
0 - 1.0
1.0 - 2.0
2.0 - 3.03.0 - 4.0
4.0 - 5.0
5.0 - 6.06.0 - 7.07.0 - 8.0
1.3
1.0
1.4
15
ss
130
82
L.2
1.3
140
280
r00
130
81
3.2
1.5
I6
100
2t
50
5.0
1.0
L.7
1.7
2L0
2L0
180
530
3.6
1.0
1.5
1.4
1.5
1.9
1.7
1.3
L.7
L.7
6.5
9.2
86
220
160
l3
r.2
NDA
1.0
ND
ND
6.6
ND
ND
0.8
0.9
ND
6.8
ND
ND
ND
0.9
0.7
L.2
5.3
ND
ND
1.0
ND
0.8
0.9
ND
ND
ND
55
1.5
1.1
0.7
1.0
0.9
ND
1.1
1.0
0.9
0.8
0.8
t.2
ND
l2
10
ND
I.0
ND
2.5
ND
ND
890
ND
ND
2.9
ND
ND
2,100
ND
ND
ND
ND
ND
44
7ta
130
150
20
ND
ND
3.3
ND
230
1,200
2,900
40
26
2.6
2.4
ND
ND
4.4
ND
ND
ND
1, 100
820
ND
l3
ND
ND
ND
ND
130
ND
ND
0.5
1.5
ND
120
ND
ND
ND
<0. I
ND
ND
t20
ND
0.s
L.7
ND
ND
ND
0.1
ND
ilo
1,500
3.5
0.4
0.6
ND
ND
2.3
ND.ND
ND
ND
1t
ND
ND
390
260
0.2
0.6
ND1A
1B
1C
ID
1E
1F
1G
2A
28
2C
2D
2E
2F
2G
3A
3B
JL
3D
3E
3F
3G
3H
4A
4B
4C
4D
4E
4F
4G
4H
5A
5B
5C
5D
5E
5F
5G
6A
6B
6C
6D
6E
6F
6G
6H
t2
ND
ND
ND
ND
ND
l1
16
ND
ND
ND
ND
NDll
l5
l8
ND
23
l9
2l
ND
44
ND
ND
ND
ND
ND
2L
19
4.0
L7
20
2L
2L
23
20
ND
16
20
ND
ND
ND
ND
2l
o
28
2L
ND
39 /1587
Table 5. (cont'd.) Concentration of "UO^, 232h, 238U , "'O", "nd
40K
in core hole samPles
Sanple Depth(ft)
238u
6pci/s)
227 Ac
lpci/s)
4ox
6pci/s)
2?6na 232Th
lpci/s)lpci/s)
7A
7B
7C
7D
7E
7F
7G
7H
8A
8B
8C
8D
8E
8F
8G
114
r18
1lC
ltD
LIEllF
llG
tlHllrrlJ
l5A
138
13C
13D
13E
l3F
13G
r3H
l3r
13J
l5A
15B
15C
15D
158
15F
r5G
15H
15r
15J
1.6
1.5
4.5
15
19
23
1.2
5.9
1.8l.s
30
90
29
0.9
2.0
2.2
1.4
2.3
23
2S
3.7
L.2
6.4
1.0
1.3
1.6
0.8
2.4
83
64
45
2.2
1.7
0.9
L.2
1.1
2.L
150
72
25
72
3.5
1.0
.1.1
0.3
0.9
0.9
ND
L.2
ND
1.0
1.6
0.9
1.1
2.9
4.4
ND
ND
ND
ND
1.0
0.7
L.2
4.7
I{D
ND
0.9
0.9
ND
1.1
0.9
ND
s.5
ND
3.7
ND
ND
0.9
1.1. 0.7
1.1
7.9
ND
ND
ND
ND
ND
ND
6.8
4.4
ND
ND
58
85
11
6.5
ND
ND
r70
370
L70
ND
ND
ND
2.3
ND
7.3
38
ND
13
27
ND
ND
3.1
1.5
ND
2t0
ND
150
ND
ND
25
2.8
ND
ND
370
ND
ND
ND
ND
ND
ND
ND
2.3
0.1
ND
30
33
ND
4.2
ND
ND
45
160
52
t20
ND
ND
ND
ND
ND
ND
t7
l1
t7
ND
l8
16
23
ND
16
16
ND
ND
t4
ND
ND
ND
16
14
I5
16
ND
19
18
2L
ND
l5
L7
ND
ND
ND
ND
ND
ND
18
18
14
t7
0 - 1.0
1.0 - 2.0
2.0 - 3.03.0 - 4.04.0 - s.05.0 - 6.06.0 - 7.07.0 - 8.0
0 - 1.0
1.0 - 2.02.0 - 3.03.0 - 4.04.0 - 5.0s.0 - 6.0
6.0 - 7.0
0 - 1.0
1.0 - 2.0
2.0 - 5.03.0 - 4.0
4.0 - 5.05.0 - 6.0
6.0 - 7.0
7.0 - 8.08.0 - 9.0
9.0 - 10.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.04.0 - 5.0
5.0 - 6.06.0 - 7.0
7.0 - 8.0
8.0 - s:o9.0 - 10.00 - r.0
1.0 - 2.0
2.0 - 3.0
5.0 - 4.04.0 - 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.09.0 - 10.0
ND
ND
ND
ND
ND
31
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
87
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
20
ND
r(D
Table 3. (cont'd')
40
concentration of 226Rt,
in core hole samPles
z32Th, ,rru , ,r, o., "nd
40K
Sample Depth(ft)
238u
(pci/e)
227 Ac
(pci/g)
4ox
lpci/s)
226Re 232Tn
(pci/e)lpci/s)
27L
278
27C
27D
27E,
2'iF
27G
27H
277
27J
284
288
28C
28D
28E
28F
2SG
28H
28r
28J
294
298
29C
29D
29E
29F
29G
29H
304
308
30c
30D
30E
30F
30G
30H
31A
3lB
31C
31D
318
3IF
3lG
3lH
31I
3tJ
1.7
2.6
79
260
73
L20
r00
1.4
1.3
1.0
2.2
1.6
1.0
1.0
1.0
29. 0
42
4.6
1.6
1.0
2.L
L.2
2.0
37
40
1.0
1.4
1.2
1.8
2.2
9.0
1.4
7l'' 143
42
2.0
1.9
2.3
1.3
1.3
24
160
3l
3.0
1.1
1.0
1.1
1.0
NN
ND
ND
ND
ND
1.0
1.0
1.0
1.0
1.0
1.1
1.0
ND
ND
1.2
liD
1.1
1.0
0.9
0.7
ND
ND
ND
1.1
ND
1.0
ND
NI)
1.0
ND
3.9
8.2
ND
I.0
1.0
0.8
1.0
ND
1.1
5.4
2.4
ND
1.0
0.9
20
6.5
ND
ND
510
ND
550
l4
ND
2.4
ND
5.4
ND
ND
ND
68
89
ND
10
ND
7.4
ND
ND
70
ND
5.4
ND
ND
ND
ND
2t
ND
2t0
230
100
l1
3.6
ND
ND
ND
32
200
81
ND
2.4
ND
ND
55
ND
ND
ND
ND
ND
ND
ND
50
ND
ND
ND
ND
ND
ND
3.4
ND
92
190
ND
1.3
ND
4.5
ND
ND
20
t22
3l
22
20
l9
16
ND
L7
ND
19
ND
20
ND
ND
19
ND
ND
ND
L7
l9
17
16
16
ND
13
ND
15
ND
0 - 1.0
1.0 - 2.0
2.0 - 3.0
5.0 - 4.0
4.0 - 5.0
s.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.0
9.0 - 10.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
4.0 - 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.0
9.0 - 10.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
4.0 - 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
0 - 1.0r.0 - 2.0
2.0 - 3.0
5.0 - 4.0
4.0 - s.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
4.0 - 5.0
s.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.0
9.0 - 10.0
L7
2l
ND
ND
NDND
91
ND
ND
ND
ND
ND
ND
ND
ND
49
t7
13
2L
2L
2t
ND
l9
20
20
18
ND
ND
20
2t
ND
ND
ND
ND
2.6
1.4
/f5< /
TabIe 3. (cont'd.)
4I
concentration of "u^^,in core hole samPles
232Th , ,rru, ,r,
^r, "nd
4oK
Sample Depth(ft)
232Th
(pci/e)
227 Ac
6pci/s)
4or
6pci/s)
226Ra
6pci/e)
238u
(pcL/ g,)
324
328
32C
32D
32E
32F
32G
32H
32r
32J
32K
32L
334
33C
33D
538
35F
33G
33H
54A
54B
34C
34D
34E
34F
34G
34H
35A
3sc
35D
35E
35F
35G
35H
364
368
36C
36D
36E
36F
36G
36H
36I
36J
39A
39B
1.4
1.0
L.7
1.5
1.5
2.7
20
160
130
2,7
11
1.6
1.0
76
58
39
s.7
1.3
1.1
L.4
L.4
1.6
52
110
2t
7.0
1.0
1.5
9.3
1.5
11
92
1.2
9.1
1.1
1.2
1.3
1.7
1.5
7.2
36
66
9.6
l3
L.2
0.9
0.9
0.9
0.9
NDl.l
0.9
ND
s.7
ND
1.1
ND
ND
0.9
ND
5.0
ND
ND
1.0
ND
1.2
ND
0.9
ND
ND
0.6
ND
ND
ND
ND
ND
ND
7.6
1.0
ND
r.0
1.0
1.1
ND
0.9
ND
ND
ND
ND
1.6
ND
1.0
ND
2.4
ND
ND
ND
1.5
ND
200
2L0
ND
ND
ND
2.0
ND
290
ND
ND
6.7
ND
8.1
ND
4.3
t20
ND
ND
0.7
ND
0.5
ND
ND
94
ND
31
11
ND
ND
ND
ND
ND
160
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
16
ND
ND
20
ND
ND
ND
18
1l
ND
ND
ND
2L
ND
ND
16
2t
ND
19
t7
19
ND
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
4.0 - 5.0
s.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.0
9.0 - 10.0
10.0 - 11.0
11.0 - 12.00 - 1.02.0 - 3.0
3.0 - 4.04.0 - 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
5.0 - 4.0
4.0 - 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
0 - 1.0
2.0 - 3.0
3.0 - 4.0
4.0 - 5.0
s.0 - 6.0
6.0 - 7.0
7.0 ..8.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.04.0 - s.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.0
9.0 - r0.0
0 - 1.0
1.0 - 2.0
ND
ND
ND
ND
ND
ND
ND
100
81
ND
ND
ND
ND
ND
100
ND
ND
ND
ND
ND
ND
15
ND
20
14
ND
ND
2L
hID
ND
ND
ND
ND
ND
ND
ND
32
ND
ND
ND
ND
ND
330
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
358
ND
ND
2.7
13
ND
ND
ND
15
15
ND
i8
42
Table J. (cont'd.) concentration of "u*^,232Th,238u, 227Ac,
"nd
40K
in core hole samples
Sanple Depth(ft)
238v
(pci/e)
227 Ac
(pci/ e)
4ox
(pci/ e)
226Ra 232Tn
lpci/e)(pci/g)
39C
59D
398
59F
59G
59H
39I
39J
59K
591
404
408
408
40F
40G
40H
it0I
40J
40K
401
428
12C
42D
42E
42F
42G
42H
434
45B
43C
43D
43E
43F
44A
448
{4C
44D
44E
44F
44G
44H
44I
44J
45A
45B
45C
4SD
2.0 - 3.0
3.0 - 4.04.0 - 5.05.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.0
9.0 - 10.0
10.0 - 11.0lr.0 - 12.0
0 - 1.0
1.0 - 2.0
4.0 - 5.0s.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.0
9.0 - 10.0r0.0 - 11.0
11.0 - 12.0
1.0 - 2.02.0 - 5.0
3.0 - 4.0
4.0 - 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
4.0 - s.0
s.0 - 6.0
0 - 1.0 ''
1.0 - 2.0
2.0 - 3.03.0 - 4.0
4.0 - 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.09.0 - 10.0
0 - 1.0
1.0 - 2.0
2.0 - 3.03.0 - 4.0
0.9
1.1
1.1
1.3
150
3.0
1.9
1.1
1.0
1.2
L.2
20
1.6
1.0
57
200
48
14
1.3
1.0
1.6
2.6
4.S
130
31
1.3
26
5.6
1.1
1.0
1.1
1.0
1.1
2.6
5.6
2.5
l0
15
l1
6.6
l6
7.3
0.9
6.5
s.7
7.5
33.6
1.1l.l
1.0
0.9
7.7
1.1
1.1
0.9
1.0
1.0
1.0
1.5
0.9
1.0
ND
20
L.4
ND
ND
1.0
ND
1.3
1.8
5.6
0.7
ND
L.2
1.0
1.0
ND
ND
ND
1.0
1.0
1.3
ND
ND
ND
ND
ND
ND
1.1
ND
ND
ND
ND
ND
2.4
ND
3.4
2.7
960
ND
2S
6.2
3.3
ND
ND
580
ND
ND
ND
ND
90
39
ND
2.3
ND
6.0
ND
4,300
1,300
ND
560
18
9.0
ND
ND
ND
ND
7.6
11
ND
L.7
2.0
ND
190
<0. I
ND
ND
ND
ND
ND
2S
ND
ND
ND
380
77
l6
ND
ND
ND
1.4
2.6
110
18
ND
19
4.0
ND
ND
ND
ND
ND
ND
4.S
ND
ND
23
ND
ND
ND
5.4
ND
ND
ND
ND
ND
2L
2l
20
ND
ND
48
ND
ND
ND
27
ND
ND
ND
ND
ND
ND
ND
20
)7
2L
19
20
L7
ND
L7
20
ND
ND
ND
;:*o
ND
14
29
ND
ND
ND
15
19
2t
ND
ND
ND
22
18
ND
ND
ND
15
ND
t{D
ND
l9
ND
ND
xlO
TabIe 3. (cont'd.)
43
concentration of "u*^,in core hole samPles
232T1r, 238u, 2271,.,
"nd
4oK
Sample Depth(ft)
226Ra
lpci/s)
238u
(pci/e)
227 Ac
lpci/s)
4ox
lpci/ e
232fr.
(pcile)
458
45F
45G
45H
45r
45J
46A
468
46C
46D
46E
46F
46G
46H
46r
46J
474
478
47C
47D
47E,
47F
47G
47H
48A
488
48C
48D
48E
48F
494
49B
49C
49D
49E
49F
49G
49H
50A
508
s0c
50D
s3A
53B
4.0 - 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.0
9.0 - 10.0
0 - 1.0
1.0 - 2.0
2.0 - s.0
3.0 - 4.0
4.0 - 5.0
s.0 - 6.0
6.0 - 7.0
7.0 - 8.0
8.0 - 9.0
9.0 - 10.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
4.0 - s.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
4.0 - 5.0
5.0 - 6.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.04.0-- 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
0 - 1.0r.0 - 2.0
47
1.3
13
5.6
l3
1.1
L2
3.0
3.3
4.4
1.8
3.5
2.6
L.7
88
1.8
36
78
39
55
0.9
t,2
1.0
1.0
37
50
35
23
49
1.1
36
30
l8
13
2.5
0.9t.l
1.0
5.3t.2
1.0
1.1
1.1
I.9
ND
ND
1.1
I{D
ND
1.0
0.9
ND
ND
ND
1.0
1.1
t.2
ND
1.6
ND
ND
ND
2.6
ND
1.0
ND
}ID
ND
ND
ND
ND
2.4
ND
1.0
5.6
ND
1.6
ND
1.0
ND
0.9
1.0
L.2
1.0
1.0
1.0
ND
ND
ND
ND
9.7
ND
40
1l
6.1
ND
ND
ND
4.6
ND
5.4
ND
6s
110
ND
ND
750
ND
820
840
73
33
6.9
5.6
60
17
2.6
2.5
ND
ND
13
ND
4.2
ND
ND
ND
2.2
ND
ND
ND
0.8
1.9
ND
ND
ND
1S
22
ND
18
ND
ND
18
t7
ND
ND
ND
ND
liD
ND
t7
ND
ND
47
ND
ND
ND
ND
ND
ND
ND
ND
33
ND
ND
47
ND
18
l3
ND
ND
ND
ND
ND
t2
ND
ND
ND
ND
ND
ND
15
NT
NT
NI
NT
Nt
19
NI:
NT
NT
NT
Nt
Nt
l1
Nt
20
NT
Nt
Ni
NT
ND
ND
ND
ND
3.9
ND
ND
0.8
ND
ND
19
20
NI
19
20
19
20
2t
rabre 3. (cont'd.) :;"::*,f,:i:",Sill*,"'r'lr, "tr, 227 Ac, "nd
4oK
Sanple Depth(ft)
258u
(pci/e)
227 Ac
(pcL/s)
4or
(pci/e)
226rg.232Tn
(pci/e)(pcL/e)
s3c
53D
s4A
548
54C
54D
55A
55B
55C
55D
56B
56D
56E
56F
56H
60A
608
60c
60D
614
6tB
6lC
63A
65C
63D
63E
63F
63G
63H
64A
64B
64C
64D
648
64F
66A
668
66C
66D
0.9
1.1
2.5
1.5
0.9
1.6
6.1
1.3
1.2
1.5
1.1
5.6
1.0
1.3
0.8
7.3
0.9t.l
1.0
22
1.9
3.2
2.6
2.5
0.9
2.6
L.2
2.3
1.3
2.5
4.5
2.9
1.1
1.4
0.8
t37
1.4
2.9
t.8
1.0
1.0
1.1
L.2
0.9
1.1
1.1t.l
1.0
1.0
ND
ND
L.2
1.0
0.9
ND
0.8
0.9
1.1
1.0
0.8
ND
ND
ND
ND
1.0
1.0
0.9
ND
ND
ND
ND
ND
ND
ND
ND
1.1
ND
ND
ND
2.7
38
2.6
2.2
1.5
s8
6.5
3.7
ND
ND
ND
2.2
4.62.t
ND
4.1
ND
ND
150
25
18
20
18
22
ND
2l
17.5
19. 4
l9
19
2.0 - 3.0
3.0 - 4.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
1.0 - 2.0
3.0 - 4.0
4.0 - 5.0
5.0 - 6.0
7.0 - 8.0
0 - 1.01.0 - 2.0
2.0 - 3.0
3.0 - 3.50 - 1.0
1.0 - 2.0
2.0 - 3.00 - 1.02.0 - 3.05.0 - 4.0
4.0 - 5.0
5.0 - 6.0
6.0 - 7.0
7.0 - 8.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
4.0 - 5.0 -5.0 - 6.0
0 - 1.0
1.0 - 2.0
2.0 - 3.0
3.0 - 4.0
ii-'o
15
ND
ND
ND
ND
ND
ND
ND
ND
0.7
ND
3.8
1.9
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.1
7.9
0.4
ND
ND
ND
ND
ND
0.4
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
9.7
ND
ND
ND
ND
ND
ND
ND
ND
ND
260
19
ND
ND
ND
ND
24
22
19
ND
L7
2t
2L
22
ND
ND
ND
ND
ND
ND
ND
23
ND
ND
ho = not determined.
PRELIMINARY ASSESSMENT
S ITE INVESTIGATION
and
IIBS SCORING
for
ASHLAND 2
TONAWANDA, NY
JtttiE 1987
PrePared for
UNITED STATES DEPARTMENT OF ENERGY
OAK RIDGE OPERATIONS OFFICE
Under Contract No. DE-ACOS-81OR20722
By
Bechtel Nat ional, Inc..
Advanced TechnologY Division
Oak Ridge, Tennessee
Bechtel Job No. 1450I
the caui I Ius Shale has total dissolved sol ids concentrations
rangingfron2,OO0toS,OO0uiIIigraosPerIiter'Sulfate
concentrations of l,oo0 to 1,500 nilligraos Per liter' and chloride
concentrations of I,5OO to 2,000 nilligrans Per liter' This hish
level of salinity Precludes developoent of this water for donestic
consuuption without extensive and costly treatncnt' Use of this
water is restricted to certain industries that can tolerate highly
sal ine r+ater. (Ref . 1)
The nearest wells are greater than 0.5 nile fron the site' It
is assuned that the wells only serve between I and 100 PeoPIe
between 0.5 and 3 uiles because of the high salinity of the water
in the vicinitY of the ProPertY'
6.0 l{.{sTE
Residues coEpriseiJ essentially of low-5rade uraniuu ore
t .iIings, 3D unconsolidated soIid, were deposited on the Haist
propert-v during the period 1944-I946. Records indicate that about
g0oo tons of residues containing approxinately 0.54t uraniun were
spread out over roughly two-thirds of the foroer Haist Proerty'
The waste placed on thc forner Haist ProPerty frou a site EaP dated
February 20,1946 is as follows:
t-I9 Sludges (Wcstern ore tai I ings
froi 19431 l '232 Mxaoe
?-78 rron cake 3:3?l TI;:"
Pi lot Plant S ludges t ' l6f MxsOe
t-tg Taitings 0'52t MxaOe
TabIe I I ists the coDPos i t ion of the colorado ore raffinate '
raffinate uay'be sinilar to the coEPosition of the tailings
o
L'
075t57
o,.
o,
T^BLE I
COMPOSITION OF THE COTORADO
Alz0s
Ca0
Co
Fea Oe
Hal ides
MgO
MnOz
MoOe
Na
Ni
P:0s
Pbo
SOe
SiOz
Th
TiOa
U
Vz Os
Loss Ignition
RAFF I NATE
z
2.1
41.8
0.13
8.7
0.2
2t .2
0.8
0. 05
0.5 - 5.0
0. I0
L.Z
0. 05
15. I
5.4
0.1 1.0
0.2
0 .62
t.l
76. L7
Alt. As, B, Ba, Be,Sr, W, Y, Zn and Zr , Cd, Cr, Ga, In, N, Nb, Sb, Sn,
all less than 0.It cach.
on
Bi
The nitrate content of the Colorado raffinate is sinilarto that of Pitchblende raffinate.
Daterial PIsced on the forner Eaist property'
Inlg?4'goDeofthereetdues(PerhaPs3o-40r)werenovedfroro
theforoerHaistProPertytotheadjacentSeawaylndustrialPark
SoncoftherelainingresidueontheHaistpropertyhasbeen
relocated by earth-oovinE equipoent and by natural surface water
run-off. (Ref' 3) ^"-'"ft"-'"
g"""tit ated eoil
and residues have been uoved onto the thl"'d 2 "it"'
AttachnentEcontainsfigureswhichghowthcaPProxinate
076 t57
and
the
location'msandtheextentofcontaninationin19?6
lgS6,theIocatioa'ofsanPlestakeninthelg?63urvey'and
locationsofradiunconcentrationsinuudsauplesinl9T6.
6.1
Bbcrl
uode l
being
hi gh,
Suouarv of Contauination
Areas scanned during the 19g6 walkover, were scanned usinE
ine ratcuet ec/scaler uodel PRS-l and NaI scintillation probe
SPA-3. Paths of scan were l0' 15' aPart with the probe
passedabout2u.-6,,abovetheg:roundlevcl.Soneareas.of
thickbrushwerescannedaswasaccessible.(Ref.7)
TheoriginalsreadesiEnatedAshland2isoutlinedonacoPy
ofanaerialphotoSraph(sca]eI''=500'),andDeasure31600'by
800r. Thc cntirc-arce was not accetsiblc to scanninS due to heavy
bruch,and3waDP.oncportionisdesignatedbyAshlandoilas
,Fill Area,, on tbcir ProPerty uaps. AlthouSh other areas have
obviously had 3oDe'dunPing, only the designated "Fill Areas" showed
cvidcnce of contauination' (Ref ' 7)
.,Fill Area,, is noted as 60o' x 5oo, on the Ashland oiI EaPs.
:": :::..,:.:::.T:: : ::"::.:" ":::":':.:':.;::, .:"::,:':.1. I I ;' :,O
I
I !,
t
.O
0/blrt
PRELII'IINARY ASSESSMENT AND
SITE IT{VESTIGATION
FOR
LINDE AIR PRODUCTS
DIVISION OF UNION CARBIDE
TONAVIANDA' NY
SEPTEMBER 1987
PrePared for
UNITED STAIES DEPART!{ENT OF I'::IERGY
OAK RIDGE OPERATIONS OFFICE
Under contract No. DE-AC05-81OR2O722
By
BechEeI National, Inc'
Oak Ridge, Tennessee
BechEeI Job No. 14501
u75t5 7,
2,OOO ll8/L' These high levels of total dissolved solids and
salinityPrecludetheuseofthiswaterforpotableconaunption
withoutextensiveandcoatlytreatoent.Itsuseisrestrictedto
certainindustriesthatcantoleratethehighsalinltyandtotal
dissolved solids' (Ref ' 2) The nearcst residentlal well is l'25
uiles frou the site' (Ref' I)
7.O trNDB ArB PROIlucrs oPBFATToNS
7.L Back(rouud
TbeLindeAirProductlcoDPanyoPcrated'fortheMBD'a
facilltyknownattheCeranicrPlant.Thcplantpcrforuedthree
procelle!: in the stcp I proccss, orct and, occationaliy' residues
fronthestcpllopcrationwcrcproccrrcdtoproduccuraaiuuoxidc;
:: ":::",' ::.' :.' ;:':. :,: ;' ;:"::::: :""i""":::::.:"::""::t :": o
into uranlun totrafluoride' Procesc flow sheets and uraniuu Eass
balencegforboththcAfrlcanoreandtheDongsticoreareshownin
Attachnents D-I through D-4' The'discucsion here wiIl consider
onlytheSteplprocelasinccitHatthllProcGltwhichgeocrated
thewastes.ResiducrfronSteplfprocesaandSteplllProcess
wore rGcyclcd. (Rcf' 1)
7.2 StcP 1 Proc}r
SteplbesanghakcdownoperationcinJune,/July1943and
continued operatlonr untir nid-July 1946. (Ref' r)
SulfuricacidwasaddedtothcoreclurryuntilapHof.0.Tto
o.Ewasreached.PyroluciteorEasn€citc(Mnoz)rasaddedto
oxidizeanyreduceduraniuto.Thenixture$,aSdigestedat90oC
for3houreandthencooledwithweakrashgolutionat60oc.
o
I
I
I
A-13
urolJ/
o.., ,n. uranium was in solution as uranyr sulfate, and Eany of the
iupurities(ironrsilica,phosphorous,vanadiuu'alunlna)HereaIgo
partiallY in solution' (nef' l)
SodaashwasaddeduntilthepHreachedaboutg.2.Soueofthe
sodiun bicarbonate waa also added, which Preclpitated uost of the
iuPuritiesandlefttheuraniunineolutionasrodiunuranyl
trlcarbouate. The slurry was filtered in the Moore ftlters' and
the cake hauled to the tailings pile' (Ref' f)
TheliquorecontaiaedvanadiuuandPhosPhorourag
obJectionable iuPurities. These were reuovcd by the addition of
ferrouc and ferric sulfates, resp€ctively. The resuLtant lron cake
was filtered off in Plate and frane Preasea an.d hauled to the
tailingr pile. The llquors were treated with caustic soda whlch
.:. resulted in the precipltation of the uraniun a3 sodlun diuranate'
The filtrate fron this step waa dichargcd as wartc efflucnt'
(Ref. r)
The phosphate cakc was a siuilar cake that resultcd frou the
precipitation of phocPhorous and lead (during thc processing of 3t
pitchblende ore!) by the addition of codiuu sulfide and ferric
sulfate. cobalt, nlckcl, and uolybdenuE colPoundc and euaIl
anounts of radiur wGrc Preccnt in the cake in addition to the
phosphate. (Bef. '.1)
The vanadiuu cake (donestic ore processing) $ras produced frou
the addition of lead sulfate to Precipitate the vanadlun as lead
vanadate. Liquids (containing the uraniun) frou the Precipitation
went to the lead renoval tanks, and the elurry was transferred to
the lead recovery tanks before disposal. The Proceas was reviged
in 1945, when ferrous and ferric sulfate were added to the dourestic
A-14
ore soutions to reEove the vanadiun and phoephorous' These wastes
were atored at the tlaist property' (Ref' l)
ThesodiuEdiuranatecakewastreatedwithsulfuricacidand
annoniuusu}fateandwaeconvertedtoanaBEoniunuranylsulfate
gg,agrenovedinafilterPresa.Thecake(acidleachconPlex. Thit
cake) was fed to a calcioer to drive off the aunonla' sulfur
dioxide and trioxlde, and water' leaving the black oxide of
uranlun. (Ref. 1)
TbetreatnentofAfricanorewaaverysimilartothatof
donectlc016,whlchisdercribedabovc.Thedigertionctep
requircdnorepyrolucltcbecauseDoreofthcuraniunwasina
reduccdgtate.Alao,bariulchloridehadtobcaddcd.toactaaa
rrgtther€F,lforthoradluu.TheAfrlcanorecontainad}ittle
:....vanadiunorphorphorouSrtothcironaulfatcrtcPralonitted.
InateadrsodiunsulfidewasaddedtoreDovethelead'The
renalnderoftheProcegsHasthc!!Ee.ThelolybdcnuDEtayedin
solution when the uraniun was precipitated' (Ref' 1)
tablec2throuSh4prescntthcrcrultsoftheassayoftypical
oret and Products fron thc Linde Plant as welll a! the results of
sclcctcdanal.yrelofrcaidues.ThcaevaluclarGfronhistorical
rccordr aod arc all prc-1955' the analycic' of collda frol the
liquid cfflucnt iav" the following valucr (baccd on one set of
liquid cfflucnt iav" the following varuct \uEEss v-
II
sanplel): (Rcf' I F,-I
Sodiun 43 ' 64t /sutfates 37 'zl,5 icalciun l'o5l Iiiif i'xide [,iii I
?.3 Liquid Bffluents in the Step I Process
cipitated ,.ra
During the initial oPerations' uraniun was Pre(
A- l5
u/otJ/
Table 2 :Typical' AnalYses of Selected Ores Processed by Linde
Danrtlc 0rsc
Forrlgn 0rrr
Pltcibl rn6.
lcrcrn: of
!crposno
Toltcrn{tc
0'20
L-19 6Ul L-501.30 R-10
uloa
Yzos
tt03
pDo
Pzos
Sl02
3r0
xl0
r{90
cd
;czo3
Al 203
Cu0
coz
llr20
R.
!5.t
2.5
0.02
0.01
2.5
13.0
u.0
0.3
12.0
5.0
12.5-2.0
2.35
2.65
n.6
10.5r
0.2
0.35
0.9
0.2
50.0
!.0
13.0
(23.7 X/tonl
6.' 3.53
2.2 0.26
0.3 0.3
L7 .12
0..0
0.31
..62
51 .1.
0.t
55.r
' .52
I1..1
0.2
t. rl
13. 6t
.2.1,
0.23
0.1.
5t.r
1.0
13.53
0.55
1.97
9.12
a.2 2.2
9.0
5.16
0.23
1.92
6..5
2.79
2.n
ill
tTrctr vrluca a"L gr9lcrl j3tlyl rnd 6 not n ctSsrrlty lndlcrtt ln lre?lir'' Ihe L'30
rnd !.-5O rrf rr'ry -ririip Orri rnd at sucfr r.Fl aot rcarrrtad la. ur trOler ln
icpcnalr 3. Strilrrly. L'19 rnrt 6Ul rn not ltp.rrt'd'
Ref. 1
A- 15
o
rable 3: Tlpicat Analyses- ^oJ
Product From the Linde Step
OPeration
pr.oduct Fra Procc$lng
?erclnt of
CorDonnd L-l!, (Br3).L-lt (DL)"L-tr'F
97 .7
ulos
Acl6 SoluDlc3
Sl02
lcltt Sulf{rlr lttrll
( lH.)Z C03 lnloluDlr
HlO3 Inrolublr
Al 203
Fe203
?zos
lrzo
Yzos
sor
A9
3
C6
cl
Hn
Rrrr Errtnl
97.0 (dn)
0.5 (url
0.05 (rrl
0.6 (rul
0.5 (url
0.! (nrl
0.2 (ul
0.3 (rrrl
0.05 (lrrl
0.03 (url
0.O10 (rrrl
0.0002 (ur)
0.0005 (rrr]
0.05 (lrrl
0.005 (rul
0.O15 (rul
0.058
.027
0..2
)0. ,
0.63
0.24
0.05.
0.29 (S03)
gt.2-
0.52
I 0.31
0.t
0.0t
0.lt
0.05
I
I
e Thr vrluet of L-19 (19a31 .rl 39'G{flct3lont fol-!h' prorluGt rlrlll tlr €ttr'r ro lrt
:i]eiiii;-riioi'aii-.ri tnt tte'.3'nt'n'r'rr9''
.' L-19 rrl rot 6lff.?rntlrtr6 frlr GIJI' lnd L'! rrt Vglcll of L-50'
Bef. 1
I
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I A-17
076157
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0?5157
3o}utionusI'ngaProcedurethatinvolvedaddingsulfuricacidto
the uraniuu tricarbonate-rich solution aod heating it to drive off
carbon dioxide; this was followed by adding relatively suall
anounta of caustic to cause this Pracipitation' The effluent frou
thisprocedurehadapHthatalloweditsdisposalintotheeanitary
sew€r. This uethod of Precipitation was abandoncd ln 1943'
however, becauee it was relativcly rlow and allowed Eore uolybdenuu
andotheriupuritiertocontanlnatetheproductthanthedirec.t
caustic nethod of precipitation. Linde developed the direct '
cauctlc ucthod, whlch rcrulted ln a bctter Product io lcer tine'
The netbod was esgentlally a brute-force reroval of uranlul through
the direct addltion of caurtic to the pregnant rolutloo' driving
thepHtolcvelcathlshatll.S.Aaarcrult,thcuranlun
Proclpitatedasdiuranate,dcspltctheprercDcGofthccarbonEte.
(Ref. l)
one drawback to thls ucthod was tbat tbc cffluent had a high
pHandwacDolonSeracccPtablefordlrcctdiapoaallntothe
sanitary sewer. Ac an altcrnatlvc, two options coDsidered wcre the
u3c of dlsposa[ wclIr or diachargc tato Tro-'tllIc Crcek' Although
the discharge into thc creck was agproved by thc stats of New York'
a decls.loa war lakc to urc dlsporar wcrlr rhcncvcr Potltblc and to
rely on the fwo-tiilc Crcek option only whcn necc'lary' (Ref' I)
.The effrucnt dlcpoaal wcrls wero approxiuately 40 ! (150 feet)
deep and pass through a clay foruation, into a gravel and sand
layer and a varigated carbonate fornatlon, Po38ibly a ulxture of
DagDesite, and dolonite or Iinestone. t{eIl logs for three of the
disposal weLIs are presented in Attachnent F-5 through F-7 ' The
groundwater in a gection'of the carbonate fornation was identifitO
A- l9
075157
as saltwater, 6Dd the water fron the particular aquifer involved
was found to be unacceptable for use by Linde. rt was believed by
the coEpany to have been contaninated prior to 1944 and before the
injectionofanyStepleffluent.TheaquiferwhichLindeinjected
itsfasteintoistheCanillusShaleasdiscussedabove.It
aPPearsthatthequalityofthewaterintheCauillusShalein
l944nav have been siuilar to current conditions' (Ref' 1)
Two-trlileCreekflowgthroughtheLindefacilityandapark,
whereiticdauuedtocreateepond,.andthenintotheNiagara
River. The storm sewer discharged into the creck via a storu
dralnageditchthatcntcredthccreckdornctrcarofthcdau
(AttachuentF-3).oneuenorandunsuggeststhatthecreekuayhavc
diluted the effluent 10 to I; however, analysir of pE data frou
other uemoranda sugScet that the creck nay havc had a flow rate uP
to IO0 tines greate.r then that of the effluent drainage rate' Tbe
average pH of the creek, Iealured over-an 8-day period in March
1946, idas about 8.3 uprtrear of the rtorl sewer diccharge and 10'3
downstrean of the discharge. Bccent estiuateg of creek flow rates
during the sutrEer ru8tcat that, Et a uiniuiur, creek flow rates
would have bcen 15 to 40 tiues the aver.age effluent discharge
rateg; the flow ratcs tn thc creek w6ro luch grcater in. the 1940's
because iuduetrial-operatlonc dlscharglcd Plant water into the
creek. ( Ref. I)
?.4 Characteristics of the Filtrate
The filtrate diccharged to the sewerc or welIa wa8 a high-pH
solution (usually above pH of l0' however' during June 1943 and
Decenber I943 the pH was probably closer to 7> coDaistingl nainly of
ions fron excess iodiun sulfate, sodiun carbonate, and sodiun
A-20
076157
j,
...i chloride added to enhance radiuo recovery' would also have been O
Pregent,alongt{ithasEallanountofavarietyofcouPlexanions
ofnanyuinoreleuentssuchaSvanadiun,nickel,andcobalt(Table
2 Iists the constituents of the ores )' Anooniur sulfate frou the
washoftheuraniunprecipitatewouldbeexPectedtoreactrapidly
withthecausticandreleasesotl6anuonia.Thlst{a!probablythe
causeoftheincidentsinwhichPuEPhouseoPeratorewerebothered
byaanoniaealslioosfrouthcwellclocatedinthcpuLPhouse.
(Ref. r)
Thiscouplexsolutionwouldalsocontaingnallquantitiesof
uraDiunandradluu.Atthelowconcentratlonfoundlnthese
effluentl,itiadlfficulttoprojectwhichuranluuandradluu
specicc would be favorcd and what thclr solublllty would bc' The
uraniun and rsdiuu would be preeent in rolutlon a3 well at in
colloidalforl,andthcrelativeaoountofeachlcdifflcul.tto
aaaets.Thciupactofthlsisnotrignificantforuraniuubecause
standards for ircolublc and colublc uraniuu are the tale' HoHever'
etandardgforlolubleandinsolubleradiundiffcrbyafactorof
1000. It ir bcllevcd that the analytical techniquer uced at that
tinewouldnothavcdiffercntiatcdbgtwegnthcrolublcand
insoLuble fractfoir; hcncc' thc conccntratlour of uraniun and
radiur in the efflucntr' (based on the tcchniques used) ' t'ould be
total uraniuu and radluu. An analygig of the colubility of various
radiuu conpounds euggests that a significant Portion of the radiuu
andprobab}yuranlunintheeffluentwouldbesoluble.(Ref.r)
7.5 Voluue of Effluents
As indicated Previously' the liquid waste frou the Step I
A.2I
0iblb/
process' the filtrate frou the Precipitatioo of the sodiun
diuranatewhichfollowedtheadditionofcausticsoda,sodiuu
hydroxide(AttachuentD.l),wasinitialllydischargedintothe
sanitarysewersystem.ItappearsthatLindebegandisposingof
theeffluentsinonsitewellgduringorafterApritlg44andthat
fron1944to1946,threewe}lslocatedintheareaofPlantNo.
andfourwells}ocatedneartheCeranicsPlantrereuseddurin8
varioug per.iods for this PurPose' Froo tine to tine' tbe wells
wouldbeconeclogged'overflor'andhavctobecleaned'Duriug
theseperiods,theeffluentswouldbcdivcrtcdtoastornlewer
thatconnectedwtththeNiagaraRiverthroughtwo-MileCreek.
Baeed on the infornation in Progrcsa reportr and varioua oPerating
ueloranda,it.:estiuatedthatliqqidwaltcvolunecgcaeratedby
theProceaaduriusthePeriodthcwe}lcrereinugcwasagfollows:
April to Deceuber 1944 - 121 x l0c L \92 x 1gc gal)
Januray to D;;;;;";1s45 isi; io" r (sr x loc gal)
January to Jurv 1946 i08 ; io" t izg x tos rar)
TotaI 4ZZ x 10c 1 (111 x 10c gal)
Bared on the ectlnatca of ltquld effruent fron the ore
Processingfroulg4Sto1946,itaPPearsthataboutS0rof.the
effluentwasinjcctedlntothewellgandthcrcualnderlntothe
storuaewcr.AlcuningthatarilulardurPingratloexistingin
1944 and early r6es, 1t appearr that aD addltional ?o x 10c I (18 x
Ioc6a1)layhavebeendisposedofinthewells.Itistherefore
agsuned that, during thc Period fron April }944 to JuIy 1946, about
2lO x 106 I (55 x 106 gal) of waste was dispoaed of in the wells
andtbereuainderinthestorusewertoTwo-MileCreek.AlI
effluentspriortoAprillg44(8o1oox106Ior2030x106
g8I)areassunedtohavebeendischargedtothesanitarysewer.
,
I
A-22
(Ref.I)
7.6 a o
The concentration of uraniun in the effluent or the
uraniuut lost varied depending on extraction efficiency;
rate (wash rates' filtering rates); and' to soEe extent'
of ore Processed' (Bef' 1)
Duringlg43andthefirsttwouonthsoflg44,uraniuro
extraction efficiencies generally ranged around 93 to 94 percent'
Throughthereuainderoftg44,efficiencicagencrallyexceededa
96ruraniunrecoveryrateaodoccasionallyrcrearhi8ha'98r.
Extractionefficenciegoverlg4savcragedaboutg8landwere
sonewhatlowerin1946,Probablydueto.thelowerSradcuatcrial
bciriS Procelsed' (Ref' l)
Uraniuulossecin.theefflucntsialg43(duringthclower
extraction efficiency pariod) aPPear to be on the order of 2 to , o
Percentoftheuraniuuintheore.Thirnaterialwatlosttothe
sewersyatem.Inlg44,hoHevcr,thedatalndicatcthatlocceswere
generallyavailableProErea!reportrindicatcthatlaterlosses
Herenaintainedbelow0.Slofthcuraniurintheor€.(Ref.1)
TheweeklyeveraEetofuraniunoxideconcentrationsinthe
effluentr analyzed fror Aprlr 1.944 to July 1946 rantcd bctwcen
0.OlI "od 0.064 g;"' of "t"t t ol cffluent'
:ltt
theavcragebclnSabouto.026gran,."rltcrlgTl):Thigwould
inplythattheProcesglostanaverageofabout-26kSofuraniuD
oxidePerni}lionlitersor22olbofuraniuuoxidcpernillion
gallonsofeffluentdurinStheperiodwhenthewellsandstorn
sewerwerebeioSused.concentrationsofuraniunoxideinthe
effluent during the period when the sanitary sewer wa3 used for
ulbr)/
percent of
product i on
the tYPe
A-23
o
disposaloftheeffluentwassonewhathiSher.Itisestiuatedthat
theconcentrationsaverage0.lSg/Lin1943and0.03g/Lduringthe
firstthreeuonthsoflg44,oFaboutl2o0andzsolbofuraniuu
oxide per nillion gallons' respectively' (Ref' f)
Assumingtheselossratesandfron2l0x106lofeffluent
disp.osed of in the wells ' about 5 ' 4 x 103 kg of uraniun' oxide
(aboutSciofaaturaluraniuu)weredischargedtothewells.The
reuainder of thc process effluents dischargcd to the storm sewer
durinS!thisperiod,about2L2xlo.lrouldhavccontainedabout
5.6xlO3kgofuraniunoxide.Thereforerbagedonthc
available data, the total uraniuu oxide contalned ln the effluent
releasedfrouAprilIg44toJuly1946wagaboutllxlosktf,or
about 6 Cl of natural uraniun' (Ref' t)
i.Z Radiuu Concentration in the Bffluenta
Soueestinateeoftheuaxiuuuauountofradiuudiccharged
duringtheProceasingofthet-30andL-Sooreacanbenade,based
on the fact that contractg rith African Mctala called for the
return of at leagt 95r of the radiuu in the Procecsed ore' Actual
processingoPcrationrsupposcdlyhel.dthcloaceatolecsthan3x
(g7:. of the radiun reuained in tre resldues) ' assuuing a total of
.
986 netrlc tonr of UoOr produccd frou thc t-30 lod t-50 orca and a
uraniuu extracti6n efficlency of about 9?3, there were 862 netric
tons of uraniun, or less than 595 Ci of oatural uraniuu (about 290
ciof238U)inthe.ore.Thiswouldiuplyabout2gociof226f,6(in
equilibriuu with 2sau) and uaxiuun effluent lossec auountin6 to 8'5
ciof226Ra.AsimilaranalysisforthR-loore'butassuuinga
g'x extraction efficiency, would suggeet that a Eaxiuun of 2'7 ci
ofradiuDwaslos.tduringtheproceesingloftheore.(Ref.1)
A-24
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ATTACHMENT 2
International Uranium (USA) Corporation
White Mesa Mill
Equipment ReleaselRadiological Survey Procedure
I
t.l Rdcrc of Eouiomcnt
All mucrirlr, cquipmcnt ud mrp *{tlch rn immdcd for rclcrre &om thc mill dtc for
unre*riacd ur, rr. rurvrnd for ndiologicrl comlninrtion lwdr in rccordtrcc wrth thc
lirnir g forth in liLC docurnraq '(fuiddhcr frr Dconunrinuion of Frcilitio lrd
Equipmrnt Prior to Rdcrrc forUnrguiard Ur c Trmimtion of Licarr for Blryroduc
o[Sornce Mrtqrdr', drtd S4snbr, lgtl. Tlu irunniolu h thir $idc irt
cdnjunctlon wirh Trblc t tpcdfy thc rdo.civity ud Rrdlaioa aporrrr rus linftr which
rn urd in rcconrplirhinl thr doaratuha rnd unry dnrri... rnd rquiprrt prior
tq rblttdonmltt or rdsg &r unrrrtriad ur
2,1.1. lfttuirh rnd Scnn
Scnp mrtrrid u( cryip,na nrh s pump prtcsrt equiprnarq ac.
which rquirc rsplir !6yicr! aE cland mmpriudy in u cfrn n
diminrtc rrddurl coilrniniiol pric rc rlrrt,urt 6r rrdiologicd
contsninrtion lcvdl Rrdioraivity oa tlr ertlcr of quiprna urd
rnercidr ir mrurd b, rlrrc,h| fo? dDhr ornnnfotrdm, uira tlr.
rppritFug potrrHq ol&ud dpir urey iaguacr ldr u fuinr
Mod.l ESP-I ?oirll. tunnnr' rtnrqfig hrrumc qrdFp.d sidt
ur AC-!.7 dpb driltdol prt , or otir .quivrlcat insrnt !.
Rrdiuioa Gpornt il. tturilnnr rrr rmdr oa ttto rart:idr udnj
crlibntod egorrl ?!t imtflrna[t rrctr u e Ludhm l\{odd I
Bar'.Gm rrn ty rnar ud pmbr c lquinlcrtr inrtrnar. Musidr
md quipmct rc rdcrd fioar thr mill dr for unnedad ur if rhc
roul rlpltr cqrt]nindm cou rtrion ud crpoen ilc mcunmaB
rrr hr fun thc rpgli€.bL lidtr comriard in TrU. t of th: ltRC (fuidr
2.1.2.tsds
l. Ohdn ryptoptLl eErud lptr rnty irnm 0on ndiolo$crl
lo.
2. Ctrt nua pcfonnrm ud furcifi ud{ Ih230 cdibrdiort
toutB.
Surwy itau on errtcr e. dplr. corrdrrtiot ! rutrarr locrdor
nrftcirr rc d*anin lvcrat rnd potaid rnrrinm coonmiardoa
ladr
Slilty rlrr orlr nlttc. of..dt han (f I crn lddl rad drrdr
rvGrtr ud rnuiaun qgorm nr lnrlilnrill
o
2 1.2 contirrurd
5. Conunination lcrdl crmild a thc millir for rdo* of quipmcnt
for unrerriqcd urr ir r tml dphl oontlnirudoa lard of 1000
dientigndonr pc minrtc ps 100 ctd (dp"vl00 snt), rtd urdirtioa
cxpo$rc limit of 0.2 millind pr lrcur (ntdltt) wi0t r mmmun not to
qcrrd 1.0 malr.
6. h thr wm tho linrhr rn cc.dtd. thr itrn ir dmmmimd by
rpgttpriur nrrar nd rrnnqnd'
7. if thr linirr for r rod rlph conurinukn it {t&t ocdd' ra dPhr
.n ., rlrrlry ot, l00 cllr lr ir nha o dminr runonblr
dphr ontrminuirn In dditktq I frGd dph nrurrmcm of $c
rce I mrdr urilg ra dglr nrc. If th.li!fu of trUo t I'[RC
ftidc uc ctcccdd, t mn rigotqrt dcutllnittltion mahd ir
lpplicd.
2. 1.3
VdricLod rmbih qripr:rr.h..etoc..& or rinilrrbrt u
rnuid ud ryptncil ldat An JDh $ttt, it tmd! ud u crpo$tr
$rvs, ir r& m tr ingis ud mrior ufrca of thc vdticlc'
ptiehly fu titt! ud apood udtclriql if tp cmanm b
nos{dic[ql fr croiwrrr uuupoo Ptyitg ptttiolu rucmion to
thdra nrd undasriry&rilrlrwy ddfitir wltthr r vd[dr
hu bcqr: cmrurimd iUc cluliq i! td thtors tlE rill Rlstiqd
fn 1tr rypfdLotrrirtrqrrni$o thtiq dsnufdotf
foclc rrnry,l/ ruInryr grd ulthl.tdc ur khuicrl to 6o
tn fnnph 2.1.1
If r u{i& il &rdficd I a6ducut3 whlc dtdt urnrort Frpotl
h idrd fGdfirll, ftr lnbq ndiodw ruai& o r omirud
briq th.t\ only th til.tb rtfo. rtd titr of 6r rurfon wlidr rr
twty.d whl lrrin8 dn niicr.d ur Ennda of tlcr ttutlrtr
vdri& includc on trertrfrtrucfr !t clotd bull tnnfoc tralrr'
Applicrlt rlphr corutrlar lrd eorrn lo hrt rn dror P'o6"
itr'49 Cfl l7t...t .d la..a& lb !i[ dr rrtir o dpb
coatuilda cqrrol tGd d l@ qdl00 d paool Q, fi
ruraontffi &r odyupa dd{ h nU dt . No iilmd dplt'
rnry ur donr or thr iarlnrl rtacr ofdotad trmtpct tlthrt
ddiciad br sclsdw ur undl rtran vd{dr b-oit dcotmileotd'
o
ATTACHMENT 3
U.S. Army Corps of Engineers
Value Engineering Proposal for
Ashland I and Ashland 2
COMMUNITY ROLE IN SELECNON PROCESS
Public input b sncourag€d by DOE to ensure thatthe remedy eetec.ted 1oi ure i";"".-.;d;'lIe meetsthe needs of the tocat-rrrn-iiyii-"jo'iu.t tobeing an effecdvc soh.r[on 60r;';;;ffi:'
The administative recod llle contrins all of thedocumentradon used to support til';;;;;;
l"-T gyt l" "tudins r.' " rit*'td,r";['dt";
Trlvaqon anagsea performed punsiuantto DOEprde154@.5, and i avefiaole Sturi;;til;sloca6ons:
Tonawanda publlc lnformelion Center70 Pearcc Avenuc
Tonarvanda,l.ly i4150
l91ryada pubtic Ubrary
333 Main StseetTonawrnda,l.Iy i4lSO
f3 a!di0on,lnformaton rcpoCtoricc are set up atthe following toca0ons:
Kenmore publlc Ubrrry160 Delarvarc Avenuc-
Kenmore, t{Y i,1217
ParlcirJe Vrllagc publlc Ubraru169 SherUanfarksirtc Drlve'Town of Tonewende, fW iiOzZ
Grand lsland Memorhl publb Ubrary1715 Bedeil Road
Grand laland, tly i4072
The.?ublic b encouragcd b radcw and commenton att attcma0vcr dc:cftcd r, iirf iioiilro pl"nand thc supportng fearUmy Ctrcy.' -rw
9^"3yF on thc-propccd romrdht ecilon atthelonawenda t b wlll bc rcccpfrd forGOA;fgttowtng hsurno oror. -;fr; ffiffi, eun.Thb 60{ay portod hd,rd; $";;ffi0 c"v,for revicw undcr cERct4 pil "itIlo]r"r soday ertenston. n ruurc mL& wiftili, durinsthe commont per6d to rccclvc'Iny;;;"commenF thc grOtrc ulstra f mitc-.- Wlru"n
99tr:nts.utc pubilc rv{shcs r maii-oi sulmitregading the prefencd,r"ov *iii-d'ril"ir"o "t$:-T_"_"!ry.or during ure eo<-iv peli. --'
,:1.?:1"." to pubtic commcnb *[ bc prcsantedn a response to commenb in he nOO, nfrlrtr win
document the final remedy selected for
F!tf"n9 1(nctuding SeawayArea D) andAshland 2 sites.
Allwritten commenb should be addressed to:
9.S.. @yCorps of Engineers
Buffato Dkilrict
FUSRAP lnformaton Center
70 pearce Avenue
Bufialo, Ny l4lSO
REFERE'tICES
BNI (Bccht l Nellonel,lnc) 1993. Renpdratktwstgt&n brfnc Tonawanda sd-OoEtoRnlg4T3oo, oaf nugi, ii.li rru."ry.
DOE 199_3e ._propscd plen for the TonawaNaS.ile, OO9O Rn1 ESolZ}3, Oak nUgc-,- iru,November.
DOE 1 993b. BasefineR/sk /lssessm ed for theTonawen& Siile, DOE/OR zlgaGOdi,'Oak RHge, TN, August
DOE 1993c. fuastblllty Study for tte TonawendaSfia, CNN i10104, Oak ildge, fru, f.i*"ru"r.
DOE 1997. Ra&nudi& Cteanup GuldelineMvebn for Ashland L esniena Z, iaSeaway, OoE/ORt21 gSGl 023, o"i iiJg",TN, Scsembcr
FUSoITP/tr0797 ll
,:a .
'o VALUE ENGINEERING PROPOSAL
PROPOSnL NO: C-11 PAGE NO: 1 OF 4
DESCRIPTION: Recycle Uranium, Rare Earth Minerals, and Other Metals
ORIGINAL DESIGN:
Ship material offsite for disposal, or perform soil washing (offsite) to reduce volume; then,
dispose of resultant waste streams by shipment to disposal facility(ies).
PROPOSED DESIGN:
Use recycling and mineral recovery technologies at a uranium mill to reduce radioactive
materialdisposal costs. An operating conventional uranium mill, such as the one operated
by lnternational Uranium Corporation (lUC) in southeastem Utah, has the technology
necessary to recycle materials for extraction of uranium, vanadium, rare earth minerals,
and other metals, and to provide for disposal of treated waste in the facilityfls fully lined and
NRC-compliant existing tailings impoundments. Based on a preliminary review of the
materials stored and disposed of in pits or trenches at the Ashland sites, it appears that
recoverable levels of uranium, vanadium andlor rare earth minerals may exist in the
materialto be excavated from these locations as well as other FUSRAP sites.
Since the characterization data is limited, it is difftcuft to quantiff the uranium content and
recycle value of this material. lt appears, however, that significant portions of the material
could be recycled so as to reduce the Corps0 total remediation costs. Untiltreatability tests
confirm the levels of recoverable material, which would reduce the processing cost, a not-
to-exceed processing cost is assumed, based on a very low content of rerycleable uranium
and other minerals of value. This proposal should be revised to indicate larger savings if
more favorable data becomes available.
ADVANTAGES:
1.
2.
3.
4.
5.
o.
7.
Conforms to Congressional and regulatory mandates which encourage use of
recycling.
Reduces radioactivity of the material to be disposed of.
Recycles uranium and other minerals.
Reduces cost of disposal of by-product from recycling operation.
Treatment and on-site disposal are performed at one location, with the by-product
from recycling being disposed of in an NRC-compliant disposal system, meeting 10
CFR 40 design criteria.
11e(2) by-product is disposed of in an existing tailings impoundment which is
consistent with 10 CFR 40 Appendix B intent for nonproliferation of small sites.
Actual cost savings for treatment and disposal versus cost of direct disposal can
only be greater than projected in this proposal, depending upon the actual content
of recoverable uranium or other minerals found in the waste stream .
;H,[l'#J?.:: rl,il,::il,l"# Ptt'$-"S J*:J'* o re wa ste st re a m s' a n d h a s O'
VALUE ENGINEERING PROPOSAL
PROPOSAL NO: C-11 PAGE NO: 2 OF 4
DISADVANTAGES:
1. Transportation by rail is possibleto a railhead located within approximately 100
miles of the IUC Mill. However, rehandling of materials for truck transportation via
dump bodies or intermodal containers is necessary to transfer materials from the
railhead to the IUC Mill site.
Z. The Mill has in place an NRC license to possess, store, and dispose of source
material; however, an amendment, similar in content and format to previous
routinelygranted amendments, may be necessary to accept this material under
terms of NRC guidance.3. Cost estimate for treatment and disposal cannot be refined until further
characterization data which indicates the content of uranium, and other minerals of
value, is available.4. NPL status of Ashland 1 and 2 sites may present regulatory hurdles.
JUSTIFICATION:
This proposal will provide a cost effective remediation option. Recycling is a means of
meeting Congressional directives to treat waste streams, when possible, and to potentially
reryclJuranium or other minerals (as mandated under RCRA), while meeting the Public0s
and Statefls preference that the material not be treated on site, and that is be disposed
offsite. Although the cost savings in this proposal are conservatively based on an
assumption that only tower levels of uranium or other metals can be recovered, greater
cost savings could be projected if treatability tests demonstrate higher content and levels
of recovery. Processing at the uranium mill operated by IUC in Utah is used as the basis
of this proposalestimate because of its proximlty to Envirocare, providing a fiair comparison
of costs based on locali$ handling issues and transportation costs.
Nob that two cost estimates arc provided for this proposat, Estimate A based on the
current proiect estimate which use rates derived from the Bechtel estimates, and
Estimab B based on the rabs for the cunent Kansas City contract for RAD disposal.
Proposal C-l addresses this difference.
a.,o COST ESTIMATE WORKSHEET (ESTIMATE A
PROPOSAL NO: C-11 PAGE NO: 3 OF 4
DELETIONS
ITEM U/M QTY COST
Disposal at Envirocare
Ashland 2(FY98)
Ashland 1(FY99)
Ashland 1(FY00)
Loading Facility
Ashland 2(FY98)
Ashland 1(FY99)
Ashland 1(FY00)
Loading Facility
Ashland 2(FY98)
Ashland 1(FY99)
Ashland 1(FY00)
Loading Facility
cY 19,500cY 21,750
cY21,750cY 1,500
cY 19,500cY 21,750cY 21,750cY 1,500
UNIT
TOTAL
"$215.00
215.00
215.00
335.00
$4,192,500
4,676,250
4,676,250
502.500
$14,047,500
cY 19,500cY 21,750cY 21,750
CY 1,500
Additional Transportation and Handling Cost
TOTAL DELETIONS
ADDITIONS
ITEM U/M QTY COST
Process and Dispose at Mill CY
UNIT
TOTAL
**$110.00 $2,145,000110.00 2,392,500110.00 2,392,500428.00 642,000
$18.00 $351,00018.00 391,50018.00 391,50018.00 27.000
$8,733,000
$5,314,500
fr28.625
$6,643,125
TOTAL ADDITIONS
Net Savings (Deletes - Adds)***Markups 25o/o
TOTAL SAVINGS
'Unit cost is from the current proiect estimate and is based on Bechtel0s disposal
rates.
**Unit cost based on uranium content s0.5 percent, and no recovered minerals. A credit
of as much as $1Ofton could be given for each 0.1 percent incremental increase in uranium
content above 0.5 percent. Given the variability of value of other minerals, rare earths, or
metals, credits due to such elements would be a function of the market value and content
of the particular element. Cost of treatment via processing could be refined and reduced
based on the results of treatability tests or other relevant considerations. Addition of these
variables all serve to increase cost savings
*** Markups: lncludes Contingency (25o/o)
Note: Additional transportation and handling costs, compared to transportation to
Envirocare, of $ 18/CY, include costs of off-loading from gondola cars atthe railhead,
loading into dumptrucks or container trucks, trucking to the site, and offloading/delivery
at the IUC site.
cosr ESTIMATE WORKSHEET (ESTIMATEB)
oF4
o'
ITEM UIM QTY
Disposal at Envirocare
Ashland 2(FY98) CY
Ashland 1(FY99) CY
Ashland 1(FY00)
Loading Facility CY
TOTAL DELETIONS
ITEM U/M QTY
Process and Dispose at Mill CY
Ashland 2(FY98) CY
Ashland 1(FY99) CY
Ashland 1(FY00) CY
Loading facility CY
UNIT
TOTAL
.$167.00 $3,256,500167.00 3,632,250167.00 3,632,250428.00 642.000
$11,163,000
UNIT
TOTAL
.'$110.00 $2,145,000110.00 2,392,500110.00 2,392,500110.00 165,000
$18.00
18.00
18.00
18.00
$351,000
391,500
391,500
27.000
$8,256,000
$2,907,000
u6150
$3,633,750
DELETIONS
COST
19,500
21,750
cY21,750
1500
ADDITIONS
COST
19,500
21,750
21,750
1,500
Additional Transportation and Handling Cost
Ashland 2(FY98)
Ashland 1(FY99)
Ashland 1(FY00)
Loading facility
TOTAL ADDITIONS
Net Savings (Deletes - Adds)**'Markups 25o/o
TOTAL SAVINGS
cY 19,500cY 21,750cY 21,750cY 1,500
* Unit cost based on the Kansas City RAD waste dispoaal Contract rates.
**Unit cost based on uranium content <0.5 percent, and no recovered minerals. A credit
of as much as $1Ofton could be given for each 0.1 percent incremental increase in uranium
content above 0.5 percent. Given the variability of value of other minerals, rare earths, or
metals. credits due to such elements would be a function of the market value and content
of the particular element. Cost of treatment via processing could be refined and reduced
based on the results of treatability tests or other relevant considerations. Addition of these
variables all serve to increase cost savings
*** Markups: lncludes Contingency (25o/o)
Note: Additional transportation and handling costs, compared to transportation to
,. .-
'l
!Io Envirocare, of $ 18/CY, include costs of off-loading from gondola cars at the railhead,
loading into dumptrucks or container trucks, trucking to the site, and offloading/delivery
at the IUC site.