docket no: 40-3392 · scrubber 11 8 11 top hydrofluorinatol' filters 11 8 11 top...
TRANSCRIPT
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DOCKET NO: 40-3392
.t.PPLICANT: Allied Chemical Corporation, Nuclear Services Division
FACILITY: Uranium Hexafluoride Conversion Facility, Met~opolis, Illinois
:t;.1-r. ·• • . .;:;:
SUBJECT: RADIOLOGICAL ASSESSMENT OF INDIVIDUAL DOSE RESULTING FROM ROUTINE OPERATION FOR THE DEMONSTRATION OF COMPLIANCE OF 40 CFR 190
I. Background
The EPA uranium fuel cycle standard specified in 40 cm 190 limits the total
~ose to an individual from radiation and radioactivity (radon and its
daughters excepted) associated-with the nuclear fuel cycle facilities from
routine opAration to 25 mrem/yr to the total hody or any organ and 75 ~rem/yr
to the thyroid. 1
The standard became effective on December l , 19 79, for a 11
the UF6 conversion plants used for produLtion of U1R fuel. The All fed Chemical
facility is a UF6 conversion facility subject to the EPA standards. Based Jn
the most current plant operation, emission and monitoring data and supplemental
information on the solubility tests on uran.ium compounds collected in environ
mercal samples, the NRC staff has carried out the following radiolo~ical
assessment to determine if the licensee is meeting the EPA's stand~rd on fuel
cycle facilities. As a resul•. of this assessment, an action level to limit
radioactivity in the environment from routine operation of the facility is
established and other additional license conditions are required to provide
assurance that the licensee shall comply with the standards during future
plant operation.
'~ .. ,, . . - . ~:.,
-
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2
Il. Discussion -----
A. ~-scription of the Fac!..U.!.z
1. ~lant Operation
,'lllied Cilerrliccll Co,-poration 0perates a privateiy owned UF 6
urani;;m ore concentrates ari:i ca•1vert:e'1 into :1r.1riiuir: llP•,1fluorii1e
. 'IF I
'· v 6 J'
DOE's gaseous diffusion pldnts fo,. enrichment of the 23::,;
isotope.
The UF6 f3cility, which uses the fluoride vo!Jtility process,
has the caracit:,- to corwert i:1nproximately 14.000 short ~,ns of
urani'.Jr,; P•=r year from ore concentrates into ur6. The r,·,:
concentrate feed assays approximately 75'. uranium, an<f the
dis ti I led UF6 product contains Jes~ than 300 ppm impurities.
The anticipated operating life of the plant is Jn additional
30 years. A flow chart of the process tised for the conversion
of uranium ore concentrate (U 3o8) to uranium hexafluoride (UF6
)
is shown in Figure 1.
2. ~aste Confinement and Effluent Controls
(a) Gaseous Effluents
The principal gaseous contaminants that are generated in the
UF 6 facility a·re hydrogen fl uo ride, uranium, armion i a, and
sulfur dioxide. Relatively larqe quantities of carbon dioxide
and water vapor and small amounts of H2 are also ~enerated .
)
.,... ' C C. • • ~ • • • - 11' • 0 • • •
. ' .()." ... '*" .. , • • ·'. ~!!··.· . · ... ,.
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'-
I ' I I
" .. ~ ., I
• I
•• I ..
;, ., I
· .. · .G::Ji. =-~·-·' .1i IC: T ,, .: J-----
3
fl(;URE l UF0
FACILITY FLOW CH,\RT
RE,:E:iVi~~:--: S~c~.:1··,~
...,L ·-------RECO'.'f. ~E J Jf?Mi; ~J M ,._ _ ___,
: . ~A~~l~A;~;;; l ... ·-·-· .J ... ,,_,, ________ · CRE CONCENTRATE
f.lP[P:lR.l TION
. .t
,-·-·- ·---· J ....... ,- .. ··-· HYORO
FLUORINATION
FLLJ(jRINATION
GASES VEtJTf D
t " ,,_ . · CFF-GA'.:TS FILTERED
AND .3CRU8BE:D
I LIQUID AND SOLIDS _______ .....
··- -·--·. ·-· ··- .. i. .............. ......... . .... J .. ·--·· -
DISTILLATION
PRODUCT LOADING ANd SHIPPING
I
WASTE TREATMENT AND U RECOV£RY
~OLIO RESIDUt: LIQUID TO TO BURIAL EFFLUENT
. i
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4
All areas in the UF~ process that procl11ce dusts, mists, or b .
fumes containing uranium or other toxiL materials are
provided with dust collectors, scrubbers, or ventilation
equipment to reduce the release ot air effluents to the
i:''1'/ir·onment. A :i:-tinq 1)t' t:1,? l1JCJtio11, f1,;,., .. 'Hid ,'3Lt?d
etficiencv ot J:?ach qaseous cleanup s:1st.em is pr·esente,! in
T Jb le I.
The ventilation system used ir the UF6
process area consists
of a ;eries of Dravo fresh-air intake units and 3 5t:1ries
of window and ro·of exnaust' fans for cleaning workroom ,:iir.
Table I (continued) The total air· flows throuqh the process
building is SL1fficient to ensure a ccmplete air chan{Jeout
approximately once every 5 minutes.
Additionally, the main control room and a process l.:1bo,·atory
have separate air-conditioning systems.
Each i~ maintained under a slightly positive pressure, and
each has a separate fresh air intake located outside tne
~F6 process building.
The few open hoods used for dust, fume, mist, or gas
_control in the process area and all analytical laboratory
hoods used for samples of radioactive materials are checked
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Table l. Gaseoi1s C 1 eanup Systems
Stack Contaminate S}:'.stem Used Rated Number Identification removed Primari'. Control Secondar}:'. Control Tertiar}:'. Control efficiencl (. 1-3 Drum dumper dust collector Particulates Mikro-Pulsaire
baghouse 99.9 Mi kro-Puha ii·e baghouse 99.9
1-11 Drum cleaner dust collectcir Particulates Mi kro-Pu Isa ire baghouse 99.9
Mikro-Pul:..aire baghouse 99.9 1-1 Wet-dust collector Particulates Mikro-Pulsaire
baghouse 99.9 Mikro-Pulsaire haghouse 99.9 1-1 Dry dust collector Particulates Mi kro-Pu l sa ire
baghouse 99.9 Mikro-Pul~aire Laghouse 99.!i 1-4 Oxide vacuum cleaner Particulates Spencer· cyl 10111± YS Mikro-Pul~aire haghouse . 95
Spencer Turbine baghouse 99 1-5 IIAII reduct.or f i Hers Particulates Porous met.al
filters <99.9 Porous metal ti I ter·s ·-99. 9> 1-48 "A'' H:!S incinerator
(replaces stack!'. l-5 H:!S, s Sulfur condenser lncinerat.ur· 99 and 1-6)
l-6 "B" reductor filters Particulates Porous metal tilters '"':19. 9 Porous met.:il
filters <99.9
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Table {continued)
Stack Number
l-48
1-23
1-23
1-24
1-24
1-10
1-7
1-12
I dent it i cat i ori"
11 811 H2 S incinerator (replaces stacks 1-5 and 1-6)
"A" top hydrofluorindtor filters
11 A11 top hydrofluorinator scrubber
11 8 11 top hydrofluorinatol' filters
11811 top hydrofluorinatur scribber
-UF 4 dusl collcctur
Uf4 dust collector
Ash vacuum cleaner
Contam1nate removed
Particulates
HF
Particulates
HF
l'.Hl icul.ttes
Particulates
Particulates
Primary Cont!'ol . System II~~---=--..----=----,---=- Rate Secondary Co_n_t_,_·o_l __ T_e_r_t _1 a_r_.y ___ C_o_n_t_r_o_l _e_f_f_i_c_i_e_nc~y_
1
Sulfur condenser · Incinerator
Two porous carbon filters
lwo 11e11tur i jeb ( 11~0)
Two porous carbon filters
Two venturi ji:ts (H~O) .
~ 1 kro- !'11 I:·,., 1 , ...
h.Jgli,111:-t·
Spencer eye ltrne
Spencer eye.lune
fwo porou~ ca1·b0n f i} tffS
Venturi jet (KOH)
Two porous carbo1i filters
Venturi jet {KOH)
Mi'kn,-l'11l~ .. 11 ,,.
l1;1ghcoil!>t'
Mi k. n.1- Pu I :c- ,1.i n~ baghuuse
MH:.rn-f'u I:. .i i r e Layhuust:
Packed tower (KOH)
Packed tower (KOH)
Spencer baghou~e
Spencer baglwu~;::
99
,·99_ 9
·-99. 9
88 85 99+
. .-99_ 9
88 85
.99+
99.9 BiJ
99 .. 9 99.9 80
99.9 99.9
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Table 1 (continued)
Stack Number
1-12
1-13
1-14
I-13
1-14
Identification
Ash dust collector
Fluorinator filters
"A" and 11811 systems identical
Fluorination scribbers
11A11 and 11 811 syst~ms identical
11 C11 fluorinator filters "C" fluorinator scrubber~
Contamrnate Sys tern ll'.:.ed ____ Rate removed . Primary C~!!t.rol Secondar.!! Control Tert1art Control et ficiency
Particulates Mikro-Pulsaire 99.9 baghou!>I:! Mi kro-f'o.1 l sa ire 99.9
bagtiouse Particulates Twoporou~ metal
filters <99.9 Pa,·t iculates Two porous metal
filters <99.9
F2' HF, and Spray tower 80
UF,;- Packed tower 99 Cuke tJox 99
Will he identical to "A" and "B" filter syst,·m. .Will be stand-Ly fluorinalor - ~-iill use "A 11
,11· "U" :;u·ubbing system 1vlien operating. 3-2 11 U11 recovery dust collecto,· Pdrliculates Wheelabrator
4-2 Pond muds calciner scrubber vent
Parti cu 1 ates, UF, 502
baghouse
Mikro-Pubaire baghouse
S~,ray tm-,1?t'
99.9
99.9 95 ---------------------------------·------------. ··-·---··· -- ----------------·
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periodically to ensure that the face vel0city i~ greater
than 150 linear ft/min.
At present, there are ab_out 46 stacks releasing uranium
compounas to tile en·.- i r•onment from t11e ::., i .mt ; :~01·~.3 i
operation. Table 2 summarizes the various staCks' release
data includir,:J release nt.: of r·adioacti,.dt.i,. 57.ac ... uiame:.t:1',
height. exit velricity and temperature.
(b) Liquid Effluents
All liquid wastes containing raaiological ana nonradiological
c0ntaminants from the facility are discharged througn the
main effluent (002 sewer) via natural drainage into the
Ohio River. Figure 2 depicts the current waste-water
disposition scheme:
An environmental protection facility is usecJ to remove
chemical pollutants (primarily fluoride) from the main
p)ant effluent stream. The facility process uses :alcium
hydroxide to precipitate fluorides as insoluble calcium
fluoride. Precipitated solids are separated in settling
basins and are retained onsite. The effluent stream from
the settling basins has a pH of approximately 12 and is
automatically adjusted to a pH of approximately 8 using
H2so4. This stream is combined with treated sanitary
waste and is.continuously monitored. This combined stream
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. I I
~
F'IGURE 2
Current Wastewater Dispositil,n, :,t = Monitoring St,:ition
F'~-~C.PIC'f. ~~ '.'·.J·-.,\L,. REGE':E;-:~ 7:~:-~ .lt-;O l'tECY;: •• E
C~.;~,1-:-~ REUSE )
-· ~.-.: .... : . .-.~ - ;;.~r..~ L,-: 1
•• CRS ···1.__~_,... ~-=.,.. :f~::::·.:=.:=ii~ c.·, ··-· 11------------,
' .. il S~EL.L ..:.-N t::u~ ~·L·..,CR:SE ,\'ASTE
-- -· .... -·· -· --, ··- ~------
F~~CR1~E SP!LL cc~Jiqc,l. PCr,DS ( .? '.
--·-- ., .. _____ .... ---·----.. --. - .... _ .. _ i.JRAN!UM SP!:..L
CO~TROL PC~DS f2)
1------------------,
1 IMHOFF TANK AND S,'\~J".".lRY WA$ ... E i---.. • SECONDARY TREATMENT
UNCC'NTAMINATED S1'0R\1 WATER
I l_M
,---.. ---_ ----. -.. ·----· i ; OHIO R1VCR
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MT\oJ Sample P. Number
'
~J
j ~ i) ! I I;
12 13 !-l ,.s ' .. ' ,, . ; ;,-,
1~ •')!";
23 24 25 27 28 26 & 29 30 31 32 33 37 38 39 40 41 42 43 44 45 46 50 53 54 64 55 56
10
TABLE 2
METROPOLIS WORKS 19h STACK £MIS5l0NS - URAll!iJ/·1
MTW Stack
'Number
1-7 1-4 1-18 1-45 1-22 1-21 1-17. 1-27 1-28 1-30 1-3 I I- I 5 1-34 J-35 1- l l-26 l - 3 7 l--18 1-1 u 1-40 J-4 I 1-42 i-43 l-2 1-48 1-12 1-13 1-14 1-J J-29 1-32 1-'l'l .., .., 1-36 l- 39 1-20 1-19 1-16 1-47 1-49 3-2 1-11 4-2 1-46 17-1 L-50 1.:.. 51
Pollutant Rate (mg/sec)
0. 1401 0. 1220 0.0069 0. 12.l": 1). 0533 !). 11322 ;j. :j~~05 .......... '
~) • .::... IC. L
0 ,, ~ r. 4 ... ..,:,_
0. 3113 0.1370 0.0448 o. 1378 I. 141 G. 1498· 0. 1850 0.37G2 ,j. 5669 •j, 0, 11 iJ.0000 0. 4271 0.0525 0. 1425 0. 0635 0.0303 0.2179 l. 570 3.231 0.4756 0.0979 0.2004 IJ.4617 0. 2779 0.5504 0.0251 0.2828 0.2218 0.0027 0.0000 0.0003 0. 1525 0. 0296 o.·1240 0.0119 0.0078 0.0450
Sta::k He i :Jtlt ( m)
3.66 2'j.i37 ·~ .;,:;
~l.! 'J. ; .i ·, I ,l l 1 - ) i J I -
4. 7 ·I ·e -t. I
13. 72 13. 72 ·1·) Q -t.. t.. • . ,I)
l 8. 2') 1 \) ·,q ,, .... ..... 2'J. :~7 l~. 29 ~2.d6 2:.?. ~36 2~1. 67 ?.7. ·U 27.43 27.43 26.21 26.21 47.24 26.21 32.tJO 32.tJO 12. 19 '3. 14 . l 3-. 72 13. 72 18.29 22. ~:6 1-: ..,,., . ~.I~
11. 54 22.86 9. 14 5. i9 12. 19 12. 19 8.84 29.87 10.21 20.30 20.30
Stack Diameter ( rn)
1j
Cl o"l
1) . ., I) ,, 1_,
•)
·J
)
I)
u
.w
,j. fj .3 ,j
(l
u. Sb 1j, 6 J
1), ,j ]
0.61 ()
0 0.56 [J 0. 14 o. 14 0. 36 0 1)
0 0 :j
0 D 0 0 I. 04 0.30 0.30 0.36 0.36 0.65 0 0
Stack Velocity ~,1rnp. (m/sec) C
O.Jti 0.30
, ,·. I.' •• ,:.1 .. :
.. _ ... ;;
·,.;. 3 ,~1
;'1 }(.:
ij. ] i~.
;) . .5u c,. Ju ,) . 30 .·1 ., "
'J •. :.LI :J. 31.i fj. Ji) (j. J t) LI. 30 9. 75 u. ~~.~.i ,:~. ~ !.J l ' -· ., . '. J, ..
40. s.i 40.54 40.54 ,j. 30 0. 30 6.% 0.30 I l. 5d l l. 53 27. 74 0.30 0. 30 0. 30 1]. 30 u. 30 0:30 0.30 0.30 0 . .30 12.09 27. 74 27. '.:l5 16.25 6.35 10.35 0.30 0. 30
:! l. 1 21. 1 ·) I .....
'·'I' -~ • • I
·""I I
~
:.. I, •"It , ...:_I, r
·11 1 :. i. j ., .. , .;: i • I
'l) I L·,'
'l J ' , ... I ., 1 - .. '., ..Jt.. ~
~ 1 i 'I ·-
·> I I - I' t
>l ,, .;. ' I ., 1 ,
~ I I 1 I .... '. :.:. ;
·"'1 I ...: I I
~!.!5. ,:i ., . - . ·l· ' ... I. I
21. I 21. I
. 21. l 21. I 21. I 21. 1 ·) I I .... '.; •) I I
~ I . I JI , ~ 1. I
21. I 2 l. I 21. l 21. ! 21. l 21. l 21. l ·.>1 1 ... '. 57.tJ 5 7. O
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11 '
is mi <ed 1-J i th the uncon tam i na ted cool i ng ·.va te r and the
effluent from the uranium settling.ponds and again monitored
before being discharged into the Ohio River.
A11 waste1vc1ter· ttiat ma·.: contJin lJl',:rnium, ~xci:•pl t.!1P. Hf'
water scrupt)er 1 i quo rs and tile uranium recovery I f?,Kh
li4uors, is ,·outetJ l/11'ou911 two of four -;ett!i11g ponds,
depending on the cflemic .. il composition of the 1vaste: · Ponds
No. 1 and No. 2 provide particulate uranium recovery and \
fluoride spill control for wastewater containing excessive
concentrations of flu'oriue. The effluent from tl1ese, t1v'o
ponds i~ pumped directly to the environmental protection
facility. Settling ponds No. 3 and No. 4 are used as
uranium spill _control ponds. These ponds receive spent
(NH4)2so4 solutions from the pret,·eat;:,ent. facility and all
other uranium-contaminated water that does not contain
significant fluoride.
The HF water scrubber liquors are routed directly to the
environmental protection facility for HF neutralization.
The ura~ium content of this stream averages Jess than
5 ppm uranium. Uranium recovery leach liquors are recycled
for additional leaching. (ontaminate concentrations in
these liquors prevent total recycle; consequently, approximately
10 percent of the 1 iquors are withdrawn and pumped to tile
environmental protection facility for fluoride removal.
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12
rt,e pH of the uranium settlinu ponds is. maintained sliqMly
basic to minimize dissolved uranium loss. Existing data
indicates that greater than 90 percent.of the uranium loss
from these ponds is soluble ur.:rnit,m. A-; the ettluent
li>av,~s th,~ ·,;econcl uranium pond, tile l,~·,el is :ne,E,H' 11d t..)
determine flow rate and a prl)pol'tional samJ)le is ·taken for
J 24-hoLH' compositi~ sample. iilt:> pd 3rn.J 11,·anit1m cunt.ent dt
the composite sample is analyzetl <1aily. The ,werage fl(1w
from the:.e two ponds is approximately 40 qpm. The effluent
from the uranium settling ponds is then miAeJ ~ith the
remainder of the facility e.tt'luent !Jefore (1ischarginq into
the Ohio River.
The fluoride s~ill control ponds (No. 1 and No. 2) discharge
directly to t.h.e environm~ntal protection facility. The
·average flow from these ponds is approximately 10 gpm.
This stream is not sampled; however, the discharge from
the environmental protection facility is monitored and
averages less than 0. 1 ppm uranium.
The solids level in each of the four ponds ·is measured
periodically; an individual pond is removed from service
\<ihen the available 11 freeboard 11 is reduced .to appl'oximately
2 feet. The solids removed from the ponds during a cleanout
are pumped into the pond muds calciner for <lryin9 and are
packaged into.drums. The dried solids are processed in
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13
the uranium recovery unit for recovery of the contained
utanium values. Upon decommis~ioning of the facility,
these ponds will be emptied and u~contaminated. All
radioactive residues recovered at that time will De dried,
packJged into Jrums, and disposed of by shipping to J
licensed burial ground.
Each time a pond is emptied and cleaned, a tnorough
examination is made of the asphalt and burlap-lining
membrane. New lining is added as required due to degra
dation of the existing lining; however, in the event a
pond liner should develop a leak, seepage drains are
installed under each ~ond to provide means to,· rapid leak
det~ction, at which time corrective action would be taken.
(c) Solid Wastes
Radioactive solid~ ,stes are generated· from routine operation
of the UF6 facility. The routine wastes generated consist
primarily of contaminated blotting. Approximately
400 55-gallon drums of contaminated trash are generated
annually. Disposal of this contaminated trash is
accomplished through a licensed radioactive waste disposal
firm.
The solid radioactive wastes generated in the uranium
recovery facility consist primarily of inorganic fluorides
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3.
14
that contain residual natural uranium (maximum dry concen
tration of 0.5 percent), natural tho~ium, and daughter
. products separated during the fluorination process. These
wastes are dried, packaged into 55-gallon drums, stored
temporarily in 5pecially designated waste storage areas.
and then shipped to a licensed waste disposal. Approximately
1,500 net tons of this material containing,, calcuiated
maximum of ~6.9 Ci of total activity is produced yearly.
Contaminated pieces of process equipment ana piping being
aiscarded are decontaminated where feasible to recover
uranium values; they are theri loaded directly into a scrap
metal railroad car for delivery to a scrap reprocessing
company duly licensed to handle radioactively contaminated
material. Noncontaminated scrap metal is s0ld to various
scrap metal dealers. Thoro1.1~,i radiation monitoring is
done to assure that the residual radioactivity level is
below applicable NRC guidelines.
Semiannual Effluents Emission Data
Section 40.65 of 10 CFR Part 40 requires that the licensee
submi~ effluent .~onitoring reports on a semiannual basis.
Tables 3 and 4 summarize the results on the radioactivity
measured in air and liquid effluent for the past few years
(1976-1979).
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15
r ab 1 i: 3
Semiannual Radiological Ai,· Effl11ents Rel1?ase
Period Uranillm (i1atural). Th-230
(pCi)
,Ju I y-Dei::. 1976 130 • uno l61.: .11)
,; J n-J u n1! , .. , ,., • t. 130 ,u,:,u '.}t,v ·l·i
July-De~. 1977 160,000 1 , tiOO ') (i '- :.
,J,rn- ,June l 1)78 170,000 l , ,jt.iO ·F .)
• ~ July-Dec. 1978 120,000
-·--- -----·-
Tab I e 4
Semiann11al Radioloyical Liyuid Ef f luenl Release
Period Uranium {Natural) Th-2.30 Ra-226
(Ci) (Ci ) (Ci ;
July-Dec. 1976 l. 24 0.0052 U.022
Jan-,June 1977 0.95 0.0032 0. OJ l
,July-Oec. 1977 l. 19 0. 0030 ;_). 0 I J
Jan-June 1978 0.95 0.0023 0.026 * * July-Dec. 1978 0.96
* The licensee did not measure and report Th-230 and Ra-226 values
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B.
16
Description of the Site Environment Related tu Radiological
Assessment of the Nearby Residence
The following description on the site environment provides specific
information that will be used to assess the radiological impdct from
radioloqical eft!uent releJse<.I trom tt,e plant's r,o,·mal (>pent.ion.
Other· general information concerning the site environment can be ' ') referred to in the Environmental Lnpact Appra;:;a;- is5LJed by the
Commission on August 1977 in connection with tne applicant's license
r·enewa 1 action.
1. Site Environment and Nearby Resit.Jenee
fhe Al I ied Ct1emi1:al Metr"opol is Plant is located in the extreme
southern part of Illinois~ As shown in Figure 3~ the plant is
located in Massc:1c Ccunty and is approximate!:· 1.8 mi-les north
west of downtown Metropolis, Illinois. Tile Metropol-is and tile
plant are situated on the north bank of the Ohio River.
Figure 4 shows the surrounding facilities, i.e.,. the Paducah
Gaseous Diffusion Plant (DOE), about 5 miles SW of the Allierl
Chemical Plant and the Shawnee Steam Plant (TVA) about 25 miles
· SW of the Allied Chemical Plant that may have additiona!
impact on the Allied Chemical Plant. --
Approximately 70 percent of the land in Massac County is used
for agricult11ral purposes. Although much of the land in the
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17
FIGl'RE 3
Loc.-1ti.on Map of Allit!d Chemical C;,rp,.1ratl,,n ~k·tr,~;wli-; P~ant
JOHNSON COUNTY , I ~--·---------
~ ! MASSAC COUNTY ". >- / : 0 '\. :::: (. \ 0 BIG BAY • : NEW COLUMBiA '\.
0' \ uj \
\
'· \ Q ROIJNll
>OiCl'I
' KENTUCKY.
0
ALLIED CHEMICAL "\.
IIEEOMORE Q ./ METROPOLIS FACILITY "
. RAGLAND
0 GRAHAMVILLE
N I
0 I 2 ~ '4 !I
~--- J__~ Mil.ES .
tlASE ... AP vSOA,r.ENERAL SOIL MAP
PO;>E, HARDIN ANC IIIASSAC C:OUNTIE 5
-LINOIS, 19n
Du (:.'1.,:--\ r. -'1 j1 ! ; ; l • • 1
IIJ.'l' if: i ,, 1·' • .. ,Y .'..I J/ \ I I', ...
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.. ,I
' .. ;
-~
.,
... ..
'·
~ . , i r i I I
I I I ...
I
L
18
FIGURE 4
Allied Chemical Corporation netropolis Plant and the Surrounding Ar~:1
.. ,..
-, (~
~HAWt~EE SiEM~
PL,,.NT (TVA)
........
f'.... I I
I
i I
I
I ':'-- '-I r-·AOUCAH "
GASEOiJS '-. / DIFFUSION '-.
PLANT / ( ERDA) /
0
4 i N
1/2
MILE"'>
.... ~ +-0 •f;: .. ,... a: • t::! ·r-
-1;
1
,- -- - ~
l
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19
immediate vicinity of the Allied plant is still essentially
rural, some industrial development has occurred, probably as a
result of its location on the Ohio River and the proxi_mity of
the Paducah Gaseous Diffusion Plant.
Approxi~ately 70 percent of the farm income in Massac County is
fl':rn the sale of livestock and iivestoc.< p1·0Jucts. Hugs antJ
cattle are the important livestock. The major cash crops are
soybean:i, corn, and wheat. In the vicinity of the Allied
plant, much of the floodplain immediately adjacent to .th~ Ohio
River is cultivated. c, the Allied site, an estimated 200 acres
of the property along the river is used for grain farming.
There are also cultivated fields about 800 m northea~t of the
Allied property across U.S. Highway 45.
Water use in the area mainly· re 1 i es on we 11 s. · Public water use
is obtained from the Massac County Water District (county
residents) and the City of Metropolis. Both of these sources
withdraw their water from wells in the Mississippian limestone
aquifer.
The Ohio River, which bounds the site on the south, is used for
barge transportation, commercial and sport fishing, and as a
source of water supply for Paducah, Kentucky, eleven miles
upstream of the site.
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20
The nearest residence is located at about 1383 ft NNE from the
plant. The staff conducted a site visit to the plant in August
1979 and observed that therewereno cattle grazing, milk cows,
crop field or garden plots at the nearest residence. (The
1 i censee I s s ubmi tta l to NRC on February 12, 1980 i ndi ca ted that
there is a new residence at 1306 ft NE from the plant: however,
the residence at 1333 ft NNE from the plant is under the pre~ailing
wind direction and has a higher impact).
2. Diffusion Climatology
A prolonged observational record is not a,vailable for the site
meteorology; however, prolonged meteorological data is available
for Paducah, Kentucky, about 9 miles southeast of the Allied
Che~ical plant. Since the nearest residence is only 1383 ft.away
from the plant and may be under the effect of building wake 3, the
staff has to rely on actual environmental concentration measurements
of radioactivity rather than calculations based on measured source
term and meteorological models. However, the meteorological data
from ·1955 through 1964 at Paducah, as sumr.iarizad in Tables 4a-4f
and 5, were used to estimate the atmospheric dilution factors
which would ,11ow the staff to evaluate the area of maximum impact .. resulting from the Allied Chemical plant release. Estimates of
the annual average atmospheric dilution factors (X/Q) at various
distances in each compass direction are shown in Tables 6a, 6b and
6c. Table 6b may be applied for the Shawnee Power Plant which has
a stack of 800 ft.high.
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~-~) ·= ::?:.) ·-··--.. · =- :_,_
--. ~-. /
'.:;,~
'~:·:::_:~)
.. ·.:.·:)
..... . ....... ·····--
.:..:· .. .-: ..
Table 4a
Dltt[CIION 0-3
. - ~
Annual ave1age joint frequ1mcy distribution of vinJ ap.:eJ 1111d wind direction: Paaq·~i ll II Labil ity class A
Paducah, Kentucky, 1955-196~
sPrro ct<t!;> 7 - I ft l l - 1 E. · l 7-21 1G IAL
----------------------- --------------------------------- -----------------------N 0 .·(JG 05b o.ono22 n • c1 n r, 1J c, O.(Jlif10i1 r1. ra o o o o u.ubOOIJ 0. U .) 111 ti NNf 0.00053 0. 0 OO'il •, l'.uoooo o.oooi:.o o.ucooo a • .:a,utlO . (I • ti l'l u 2 N£ O.OOO'Jl U.COOll II• (1111100 0.000011 0. OltO&O 0 • (1 (I (J (I (I o.u111 .. ~· (Nf 0.00060 0 • 0 II O f.h (J • CICtOOll II • (, II O (1 0 O.OOlll:O [J. (,i,(J(lb o.~~·li1: [ 0.00011'1 o.0001t1 O.OfiiJOO 0. (If· (l(JO o.ocoou (I O {1 :I{,(\ Ii o.ao1.·.1 L St 0.000:>'t 11.[,J(l't't £, • U ll l• ') 0 U • 0 (;t, O&) O.OOl!lJ('; 0. (; (1 0 (J (; u.c.oc·,t: Sf ll. llOO't!> o.0001•i u.oonoo D.f,Cli,UO u.(JOtJilO Ci • 1111 0 (, Ct 0. h,,Ot,,. ssr !).OOUU n.1.:ou2 .. o.ouooo O.lil'OOll n. o ou,, n u.00000 O. t (' 0 •• 1 s U.00079 II • (· II O 5 !:.. O. Oll UUO 0 • 0 l (I U U I~ • u (Jll {I (J o .,.uoou· 0. I: 11 l .\ It SSlo: 0.0,,01"'. o • '"' 0 ~ 1 0.00000 0. 0 CU ,10 o.ooot,o o. c1,oo o £1.Ubl ~~· SU o.uoon 0. u tJ OH 11 ll.liOllllC 0 • UI, 01, ii c, • ll c o r• 11 U.(·!tfJ'lU u.'11111.{J "~-~ U.OOO:\Cj O.!JOO'tli u.'10lkl0 O.l!llllOO o.oooou o.uhOOU 0.:, h (1 t• I
" (1. 0 R Ot,lt O.IIOO't~ !I • I, !J IJ (J 0 (I • C. 1, 0 lJ U (1 • £, 0 lJ ll 'l {J • I! !I O O (J 0 • 1\ 11 l :, .. UNIJ 11.000;·6 C! • !I l, 0 I •, L.OC,(100 0 • LI I' L (11! (J .. C, 0 IJ (, (• O.ll!Ol,11 II • (.i lJ ll 11 !, N·J n.tJOO't5 II • i: II O 2 ;• (, • (Jf11li)(j n. ( r, c, no (J.ooorio 0 • 0 11 u (J ,. O.J.J(II I HN:,1 O.OOO~'l 0. 11 ll O I 1 O~IJ(Ji)0(! 0 • (,a• 0 11 IJ h. OOlll•IJ \} • ll l • U tJ (1 0 • t t. u •11·
1 o IAl. O.OU'J05 O.IIOf.11~ r, • r, 111, o o 0 .1H11ll11I 11.uoi1no L.t1uuuu u.ua~ .• ,,.
N
•
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~ f: L ··: .. •
···:3" ··- . __ ,,,.
- ~ .. __ .,
Table 4b
D IR[C T JC,N 0-l
Annual average joint frequency distribution of wind apeed and wind directioui Pasquill stability claaa B.
P~ducah, Kentucky, 1955-1964
SPf[D C~J$) 7-10 U-16 11-n ).d l111AL
. . ---------------------------------------------------------------------------------N NNf Nf [NE [
[S[ sr ssr
SS\I SY ~s·u V ~NI.! Niil NN.:
1011.L
0. 00 lllfl O.Onl'IO 0.002',7 o.0020~ U.OOJ!l9 (J.002't2 0.00222 0.00 .. 16 D.OO?~O O.liC.:?18 o.0021to 0. OfJ I l l 0.i)Ol'tll 0.000'31 0.001~!:. O.OOJ(l1
O.ORl'tR u.OOl~lt o.0021t2 0.00220 0.110:>:H O.OOlf.1 IJ.flll117 ll.Df:15(1 0.00200 o.uoJ15 O.OUJIJ', D.Ol'l'JO 0 • ll fl l l 7. o.or,Ju, C.OOIOft n.lJOlU'l
0.0:- 1120
••·on 1,CJ£ 0.0~116 I,. Oi.l lot 2 D.Olil37 r.ooa10 IJ.OOll't7 it e O (I IJ .S 1 0. 0 0 l•.:',f. (l.OJOll7 <.,. C•,i.~3ll n.011222 u.ur.1:n I: • (I (I u Ii CJ U. Oi1 r,::.O o. r, !:f•'t 6 P.OOOH
n.00000 o.or.ooo O.DhllllJ 0 .CIIIIJOO
D. '"' 060 o.t1ucoa o.orooo 0 • 'll, 11 Ul, o.ouooo o.orooo o.uuuoo 0 e lH•O 00 o.llhuliU 0 ellCOfi'j 0. IH1D l. l; 0 • 0 OU Ol•
o.uonoe,
n.oonnn CJ.OOUalO C1.00(lf10 {1.00000 (I.OOOilO c:.r..0000 0.00000 (!. ooouu ll. 0 0 0110 ll • 0 {11\ !I O . tie llOUCIO :1.uou;,o. I!• ll O O j, 0 o.ouO(·O U. OflfJlJO o.oor.ou
u.CJOCiuO
0. ld,0() 0 o.oc,oou O.OliOiJO (J • UtlllO II o.r,roo,1 o.ula6Lll o.ouooo 0. Oi. DO 0
0 • {, ii O il (J
II. l: i1 CJ Of l' .1111 flO f, :>. fJ 11 Oh 0 0 • l: 1100 t,
r,.nuuuo U .• ! (I fl O l'
(J • " (1 0 0 ll
0 • £1 r .. 0 II ll
c, • 0 "" j;·, U.OC.bUo;' U • (• 06~ I o. a ll~f.O O.flfl(,11 O.tO'tltO o.ou~u. O.DO't(;;.a O .u c1:..H o.:?u711 u.uCl771 fl • lt fl 't ·~. ll 0 • (i II .:Pt t,
o.oa21~ I) • (I (. c' ·1 •, U • [j (l;H,(i
0, 0 111.J
N N
..
..
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=@ E=?) '--·
c-~ ~ (===;-1. ·.:.-=::::: ... · ~-··-~:::::: ... _ .... ... ·------··
-.-·..:._·: .
.. . ~-- ~-
Table 4c
O~R[ClJON o-,
Annual average joint frequency Jiatribution of wind 11peed and wind direction: Pasquill stability claaa C
Paducah, Kentucky, 1955-1964
f.rrrn c1<15> 7-10 11-u. 17-:'1 )~l TOUL
--------------------------~------------------------------------------------------N 0.011079 0.11(1162 n.110~.ti& 0.01.0.\tl o.OOOfJO 0. 0 fl O O 0 0 .11 Of,;. 7
NN[ c,.00019 0.00203 II .1)0'1~7 0 • 0 f; (I 'IL o. OU(lt•O O.(!,jOOf' 0 ~ t: (l ii: ~.
NE o.Oill5'1 O.OCl7fl n.r.o:rn'I 0 • ll l• 11 ll. ;). 0 0 (1(10 u.c.110011 O.IIOt'tt.
£NC tl.OOIO'J u.0021t1 u.r.u~!>~ o. r,r, n 2l - O.OOIJ:tfl O.uQl\(lO 0. 0 lJ l .~ h [ O.OOllR 0. 0 020 f, 11.t02!:il o.Gr,010 C!.OOOLO 0. l.ul t, 0 U 0 .1H!f ... ~
l SI 0.001 H O.Olll'H O.UOl.3b O.Ot,003 o.oonuo O.OOOOlJ 0.011 .. n·, ~[ D.OOll'J O.(jOI)..\ CollllCb5 o. uo r,o;· &oODOh'l o.uooo(I c.o,1.s1-: ssr 0.00100 0.00150 (J.001 ... 6 O.OC!OIII O.DOOIIP D.OliOOO U.C!,HO't
~ 0.0111~6 0. 0 (• 2 'l ~ u.uo.~116 o.011tJ'a5 {l.oor,,•u fJ • ,, .. 0 0 0 u.11,,id-t:: ssu 0.001'6') n.ootlO {'.OC.1'161 o.uu;;,~~ (•. 0 0 U Jc, Cl.('i(IU.' !).fl171 .. SU 0.001'18 0.11(,J;>'I lieODll't'J 0. 1.1 •11 f •. ~ ti. u r, o o 7 0 • 11 f• 0 U ll o.!ll't'J.~
wsu o.ooo~l D.OlJJtO 0 • CJ l• ~HilJ o.or;o111 C,.OUtil.1 (J • f' I, {I fl (J C • f I ;1 t, ., I u 0.00012 D.t1Cll2 o.on;o,. u.oro,;o O.llOOOl O.i1Ulif,O ·lJ .ufl't .! l
UNU 0. Ol1D!Jlt o.on1n, li.l'li:''tL o.noou, O.(lh1Jl-.!) 1).0J0,10 , •• ti •l'I ~~.
NU 0.(10013 0. U O I?!. c.00;.,,,5 O.OUlJ2~ n. o o o :t !. · u.UilOUH o.Clft .. 11 NNU o.ouo~.5 U. 01, 11 7 i1 • (I lJ \ (j ft C • 0 (, 0 ~ 7 u.OOllUl ll.111.0:JO n.un~1't
101.\L 0.01120 O.O.HO? 0.057H o. or,u Yl IJ.fiUlljJ_ o.cil,OO.! 0 • I l •1 l.:.·
,1
N (..J
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-~ €L__j) r=:.=--;,,L-J;
~
t---·::D ::::-.:-.:::1 :;:.-:. ::.: ___ ; .---·-~ ~--·-.. - ..
. --·-··-
Table 4d
OIRCC.IION 0-3
l,
Annual average joint frequency distribution of wind apeeJ and wind direction; Paaquill stability claaa D
Paducah, Kentucky, 1955-1964
SP[[[) OlS> 1-HI ll-16 11-?.I ),li ll\lAL
---------------------------------------------------------------------------------N o.nllv,1 0 •Pr.·, 51 n.n1H'l 0.01001, ll. OC,Rf>'t o.ooou:> 0 • (1 2 '3 " ?.
NN'" o.oon't 0.00£!7 ti.012\6 D • CH,9 l'J ll. 0 lJ O :\A u. 01, 00 I 0.6.UO~ NE 0.00326 O.OCJ672 D.OOhtl'j o.ot:rno u.oouul o.onoot o.r.~1c;1 EN[ 0.00291 D.OO't~'I c. GOti:1 1 0.002')1) o.uoorin 0 • r, i· C ll r, l.l. !? 151! 1 [ 0.0029£ D.0(;502 O.DO't~6 O.blllCJh 0.000!)~ O.OCJUOO O.lll't~~ rsl r,. 002'11 O.OD31lj il.Ol'HO O.OC-Olf, o.uoou~ O.OOOlt(J l\. 0 l O 'I.\ SE 0.0026't o.r.ll267 0.00201s O.ltl'O't!> r, • o o o ,; o O.ld·UO(: 0 • 0 ll (Hl(l
S'i r 0.002-13 O.OO'l51S O.CJOBh O.liCJj,H r,.r.0010 O.tJLOOO o.01rno ~ 11.002.H O.LIO'tql O. OJ ~'l't tJ.(1120~ 0.001[5 c,.01.01.~. u.u.·,3'•!. SSII 0.0111118 DeOOf.27 e.c,2~j!> o.c,1tr·5'l C. U Li ~.ts'l U.l.lJIJ'J't 0 •• 11;-''t;• SY 0.00222 o.uo~H, {J • li 1 :•.:•fl (J.lll!llJf. u.uo11t2 0.111111:;> Cl. :I H· ~.,. YSll O.OOfl'i!: O.il021J2 t). 0 {J !lf. .! 0.011137.? O.OOl'tJ · O.U:lO~tt 0. (· 1 •1111
" O.OOll'9 l).uo2Jl P. 0 0 .HII c,.on'tf.'J LlaOOllt,l 0 • .; C fJ ti 'J O.rl !O't VNU o.0011t 0.00237 u.OO~IH O.ii!lh57 !l.OOl'll O.LlOIII G.01·)">9 NU O.OOl!lf o.oo:-'.91 ,1.IJ07?1 0.01111 0.001,u! O.f,0021 .J.O~'t'tll NNl,I 0. (10 l ll, o.oc~~7 (, • (J l (IHH 0.017115 o.oo~~•u CJ.(.,j(Jl"I o.r.~l>'t!,
TOTAL 0. C. .$It 10 0 • CH, I' 9 'i t,.l'tlJt, O.El2l I•. 0 l 6UU o. (l n ~~ lj n.'tlH2
N ~
•
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,.-----~. I ... -.··- • ~ .. --
Table 4e
UIHfCTlllN
N NNf. N[ n,r [
Uif r.[
SSf s SSIJ SIJ vsu V ,mu
"'" NNIJ
TQHI
0-3
11. 000{10 u.'uoooo 0.00000 0.00000 n.00000 0.00000 o.uoooo 0.00000 o.oooco 0.00000 0. 001)00 t). ooouo o.rir,ooo o.noono 0.00000 0.00000
0.00000
Annual average Joint frequency distrib .. !:ion oF winJ apeeJ anJ wind direction: Paaquill stability class E
o.00111t 0.00~1:? 0.00316 o.0021~ O.OOl22 0.00;;27 O.l'.l~l22 D.C.031! f.l.Oli5f.t. c..01,!'1;1j o.uo39l Do0f.i1}3 O.CIDO'l7 O·o (!(IO 76 0.0[1107 0 •. o O 11 !;
Paducah, Kentucky, 1955-1964
SPHIJ CKJSl 7-IG 11-16
11. no ·s.u r,.0021t6 O.OtJ1 1,n &>.uuuH fl • !I O !Hi 5 o .• oc,o:\7 ll.001117 tl.Ol,J•H 0.00796 ,, • fJ l 7 J l O.OOH02 o.on .. S&J (J.001'17 o.001u. o.t.1113'.lt O.Ol1'tt.'t
0 .Ol,1Jllr1
O.OOGOO ~. 00001) o.otooo 0. 0 !l O IHI U • ti 1: 0 00 0.00000 o·.oJOOO 0.00000 D.IH•OOU o.or,0110
·o.OQC011 o.l'aouo O.OJOOO 0 • fi iHi G ll o .. ouooo
IJ • (1 II O IJ U
17-21
t.oooan 0.000110 ll.OOJ('O
u. OCJflilO ,1.0001)(1 u.coc.100 0.00000 r,.O~illlO 0.000'10 Do00{100 L.oua•10 fl• 0 !I U 110 lJ.00000 0.00000 ll.0000!) n.oooor,
o.unooo
o.oooou o.ecooCJ 0 • (j ., 0 0 fi O.£,j000 o.uoooo ll.UlJOOO o.ncoor, U. 0 i, uu 0 0.(:0000 o.uuoou O.f:1'000' 0 • L II O £10 ll.(JC!OOO o.ouuuo n. ,. ~· o c, e u.c.11011D
O.(JIIOOC1
101 AL -
O.OCl!:.117 O.:>O't:iH 0. !.J 04-:,lt 0.002~\•J o.vc:::o·,'
N o.uo~E.,. u,
[I o ll ll 2 .. 'I l:.;JIJ~b't 0.111.,f,3 CJ.t.:.!2~'1 O.Ull'J~ o.oo.u2 c,.r,oi,.,. o.uo2~2 IJ.IIU't~·l 0. ;10~ 7,;
r.. J ·JJ l<'
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"7 - • . 'Iii: . . . . . . ;,,'
Table 4f Annual average JOlnt frequency distribution of winJ speed and vind direction; Paaqui 11 atabili ty claaa F
Pa.ducah, 11:entucky, 19'55-1964
Sf'fEO CKT5l fJIR£CllCIN 0-l "-f., 1-Hl 11-16 11-21 );>} TOI Al ---------------------------------------------------------------------------------N D.OHJ'aO 0.00 ... ,0. o.onuoo o.or,oon o.oooro 0 • OlJOO (J O.O)ltHO
NNC ll.01182 0 •. 005,! o.coooo O.C!l!OOO t.OOOt:O O.lJUOO(J D.Ol72f, NE D.Ol!l6~ 0.00~21 0.00000 O.OfiOl.tfJ O. 0 DOf, 0 O.l-000(! O.O;')Ottt, EN£ o.o ... 1n,. o.oo~ul o. oot•no O.hl~lJtll c.11our.lJ li.lullOU o.a1uf.7 N
en ( 0.01110 o.0022~ u.oooco o.ouooo G • IJ (J (Hi O D .1111 0 II 0 O.OHftl rsc 0.010'19 li.lll.1231 O.OUOilO o.OIJOOO o.ooono 0 • (1 ~Ht O {J o.r.12t•.r, S[ 0.01.Hft 0.00221 ri.CJt:iillJO u • 0 i1 ,, (f o) (! • 0 0 0 ,. f· 0 • I: IJ O (I (r O.!Jlf,tll ~SL O.Ol'lilh . o. oott5r, 0.(1 0000 u.ouooo O.UOOLO 0 • Ii h Ii U 0 o. o ;~ .h,r, !i 0. ll ~·., 1 fa O.(Jll3f. II • (! (I II O 0 u.r•O(IOO u. 00(11}0 t,.!l!IOOO . 0. u \(. '1 :• 5SLI D.Oltill 0.011'62 CJ. (10LOO o.ouooo 0.00000 (I • (:I.I u (J (I 0. I.! :C'J ~.·J SU D.02125 o.,rn9b'I ,,.,10000 0.0011011 O.OC,0110 0.(JlJOOfi c.o:n 12 u~u o.onntt9 Ci.OO't2!J 0.00000 O. (ICOOO o. ooouo o.cuuuo O.hJ2H ii o.0019~ o.CJ:lll~ C.. llO 1100 O.OOJOO 0.00000 (j • (I i1 U O 0 0.01101
•-19 .,N:.J O.Oll'tll 0 •(III? J •) ~:.001,00 0 •I.JO (J {I I! O.OOO!!'l o • e ,.i ,. u C! 0 • Cl 1115 f,
C-~2> N':J 0.005~!. o.ooJo~ li.000110 n.oooon 0.0001:,r, 0 • U I' U (Ill 0. 0 I; U 1,1 NNU O.OOL'ift t • Cl O .! l 1! (I • 0 I) (t 1) 0 O.C:tiOOu r.uoor:u (I• l ~10 IH.1 C.!rlOH, ;--·-~
··-·
~-:: __ ,S) l01AL U. l"JHf.9 r,.0111u.~ tJ. o o r,o o O.DlllJOO 11.00000 u.11,1000 0. ,'7 #')~'
.. --~,
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=-:0 ·. --···) ,.-::..-::--..:.:. .-:.:::_=:3) ·-- -· i:·._.-:51 ___ __,.
. ,·· ---:-:-:--.
--..
Table 5
DIRCCllON 0-l
•
Annual average joint frequency distribution of wind spe~d and vind direction: all Pasquill classes
Paducah, ~entucky, 1955-1964
Sf'ffD CKT~I 7-10 11-H, 1-7-21 )?I 101 AL
---------------------------·------------------------------------------------------N o.OJ5'H O.Ol3'J7 0.01921> IJ.OIO'i't 0.0005'1 11.r.uoo::· O. Oi,O ;> 7
NNL 0.01768 O.UI03h 0.020£.7 O.Uii')C.5 o.ouo,H o.1·0001 o.Ofit.17 Nr 0.021,3.3 0.02100 o.oJ!>E,3 0.00~30 Ci.OOUOl O .-o (1 00 I o.OE.'t!.C, [N( O.Ol.H.3 O.Ol't'J2 O.Oll'iJ 0. IJ O .H .~ il.OUO'lll 0. (,!.10 0 fl O.O,'t!t.•, [ 0.02UCj5 U.Ol'tH O.OOh!O o.uo::>ilc. P.0000~- 0.11000(\ U.0'15711
c~r 0.01120 0. 1112 30 Cl. II O ~if, Cl 0 • (I !J lJ 7 'J o.ooc,03 0 • t 1) u O I} o.,u~<f;, M O.U20't't O.OO'll,~ G.f,O~'tl o.contc1 o.ooc,ou (l • !I :1 II (I (I l, • iJ ~ ' ,·, '•
ssr U. (j,2!)06 O.!Jlt.13 0.01101 0 • ,, fd 't J 0.01101(1 0 • II 1.1 Cl O IJ u.L~~/":'. s li. ld2JII u.c;;!70:t L;.IJU .. lfl (! .1.1 :!:>;J G.1,u1u5 a-.(; :l U l 3 . 0 • II '·, :; °'.' ·1 SS:J 0.02Hl (I. U.?')'.J't u.t;!i'l'15 o.o .. :Hl fl. 00(,0!j o.tiuo·n {I. 1 h l 1l ~
Shi !J.021101 0.0261i7 li.lJ\?fll o.ol7~1 !I • fl O l 'J 1·1 0 • ( ,) 0 .1 ::' O.l1i~t17 1,1$1,1 0.011'19 o. u 12 3ls O.Ul2'Pl 0.00~15-J U • 0 0 1 't-~ O.LJIIIJ!.(I O.J'IU~~.
" ll.Oll'Jl o. 0·091 c; II • 1111 f~ :> 1 0. :J !J ~·2'' O.OIJU{f. 0 • 11 !! (I fl c. CJ • O 1 ~. 't I UNU 0.001,,'J Cl. 0 ,, U ~ ! U.OlOE.j o. (It• tu.n tJ.001':.'t O.LOOlll 0 • J :. ·, 't 11.
N•, 0.009!.'t tl.OJ.-,!->E: ll.01"1~6 0. u l l .% O.DOl"il II • I· II fl~' I CJ • (J 't ~. ~. (. t,mu 11.0llll!> 0.01011 u. l l '1.~0 0.1.111,~;'. ,, • C, I) 2 1 ') 1} • I. tl II l CJ ., • !1 '""· ;>
lOTAL D.2'Hll O.?~J't~7 o.;•1?,~3 C, • lf, 1 f,f, D.Ul'/;-'r, :1.1:.,~~• u.•1•1'-J•1.~
•
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Tahle 6c
Allied Chemical UF5 Pl ant, Annual Average x/Q (sec/m3) (Stack Hei']ht -=-~(f.Bm
Direction from Site Oi 5 tarice in Meters ·------ -----·- .. -----
430m 500m 600m 700m 800m CJOOm 1200m ---N .269E-05.Y .259£-05 .257E-05 .259E-05 .259E-05 .256£-05 .230£-05 NNE .404E-05 .381E-r5 .355E-05 .334E-05 .314£-05 .296E-05 .244E-05 NE .297[-05 .278E-05 .264E-05 .256E-05 .250E-05 .242E-05 .211£-0·5 ENE .137£-05 . 126[-05 .117£-05 .112(-05 . 107E-05 . lOJE-05 .881E-05 E . 119£-05 . 109£-05 . lOlE-05 .960£-06 .925E-06 .891[-06 .766E-06 ESE . 118£-05 . 108£-05 .974[-06 .897£-06 .831E-06 . 777E-06 .629£-06 SE .146£-05 . 135£-05 .122[-05 .112(-05 . lOJE-05 .965[-06 . 725[-06 .-, SSI: . 175[-05 . 164[-05 . 150E-05 . 138£-05 .128£-05 .1 l'lE-05 .952[-06 s . 198[-05 .184(-05 . 170£-05 . lb0[-05 . 151(-05 . l 43[-05 .119£-05 SSW .224£-05 .208E-05 . 192(-05 .180E-05 . 170(-05 . 162E-05 .135£-05 SW .25lf.-05 .230£-05 .212[-f}i:; .201[-05 . l92F-05 · . l 83F. -05 . 156[-05 WSW . 180E-05 . 162£-05 .144£-1.JJ .131[-05 .121£-05 . 113£-05 .919E-06 w .218[-05 . 195(-05 . 174£-05 .161£-05 . 150£-05 .142£-05 .118[-05 WNW . 163[-05 .148(-05 .135(-05 . 128(-05 . 122(-05 . l17f -05 .993(-05 NW . 145[-05 . 136£-05 . 130(-05 .129[-05 . 128E-05 .125[-05 .112[-05 NNW .181£-05 .174f-fl~ . 172(-05 . 175[-05 .176E-05 .lHE-0~ . 158£-05
l/ E-05 =- 10-5
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3. Environmental Mani taring Data
Since 1977 the applicant has jnstalled five environmental air
monitoring stations (Nos. 8-12, see Figure 5) and an additional
two (Nos. 6 and 13) were installed in 1978 to continuously measure
uranium concentrations in air. The locations of these air.samplers
are summarized in Table 7. The most current monitoring results.
as summarized in Table 8, are used for dose estimation. Since
the nearest residence is .subtended between air sampling prints
Nos. 8 and 11, the higher concentrations of nuclides at sampling
point No. 11 were used for dose estimation at the nearest
residence; however, it is noted that the actual concentration,
·at the nearest residence at the NNE direction could-he hi~her,
based on the X/Q estimation as sho\'ln in Table 6c. (See staff's
recommendation on adding an air sampling station at the nearest
resid1:.·1ce in later section.)
The solubility classification of the uranium compounds in air
particulates collected at air sampling station No. 11 was
studied through a contract of NRC with BNWL. Air sampling was
conducted continuously at this location for about? weeks and
t~e uranium particulates collected in the air samples were
analyzed for their solubility classification according to the
methodology established by the BNWL. 415 -Preliminary results
from BNWL11 indicated that the uranium particulates consi~t of
an average of about 60 percent Y compounds~ and 40 percent D
*0, W, Y correspond to biological half-time of 0-10 days, 11 to 100 days, and >100 days.
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Table 7
Locations of Environmental Air Sampling Stations
Air Sampler No. Location
No. 6 5300 ft. NNE (Metropolis Airport)
No. 8 l 035 ft. NE ot UF6 Bui laing
No. 9 775 ft. NNW of UF6 Building
No. 10 720 ft. SW of UF6 Building
No. 11 1240 ft. N 0r UF6 Building
No. 12 590 ft. SSE of UF6 Building
No. 13 755 ft. NE of UF6 Building
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Tahle 8 -----Sunvnary of Environmental Air Monitor~!l9 Results in 1979
1979 Data Average Concentration (1::Ci/ml) Sample
Point 1.1-234 U-235 11-238 Ra-226 Th-230 6 2.64 E-15 1.22 E-16 2.64 E-15 4.57 E-17 2.79 E-16 8 8.99 E-15 4.13 E-16 8.99 E-15 6.08 E-17 3.08 E-15 9 1.42 E-14 6.51 E-16 1.42 E-14 * *
10 1.72 E-14 7.91 E-16 1.72 E-14 * * 11 1.42 E-14 6.51 E-16 1. 42 E .;..14 4.20 E-17 1. 70 E-15 12 1. 36 E-14 6.27 E-16 1.36 E-14 * * 13 1.53 f-14 t.os E-16 1.53 E-14 * *
*The licensee only analyzed the air samples at stations No. 6. 8 and 11 for RA-226 and TH-230. The analysis showed high concentrations of Th-230 in air samples that the ratio of TH-230 to natural uranium is much higher than the yellow-cake feed average aver 33 mills (Th-230/U-natural=0.005 (See staff's recommendation in later section on analysis of Ra-226 and Th-230 on all.environmental air samples.)
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compounds*; however, a split sample analyzed by the ·licensee
showed 51.5% D and 48.5% W compound.* This shows a substantfal
difference affecting the dose calculation based on the two
different results. The difference in the results has not been
resolved and further sample spli.tting and analysis by hoth
parties is recorranended by the staff. ti.t tf-ie present time,
results from BNWL (NRC consultant) are usec1 to calculate the
dose received at the nearest residence and this would result in
a hi ghe r dose.
In addition, the licensee had conducterl air c.ampling at station
'fo. ·11 to s;:udy the particle size distribution with a cascacie
impactor during peri~ds of 2/5/79 to 3/5/79; 3/5/79 tn 3/21/79;
· 3/21/79 to 4/18/79; 10/30/79 to 12/4/79 anci_ 1/15/80 to 2/~/80.
·The results and additional information were submitted to NRC
on February 12 and February 15, 1980. The results of the
licensee's cascade impactor studies are summarized in Figures
6-10. From the curves as shown in Figures 6-10, the average
activity median aerodynamic diameter (AMAD) was derived to be
about 4.5 um for the air particulates collected at Station fllo.
11. The dose conversion factors generated by the Task Cirnuo L11ng
Model based on this AMADwereused for dose estimation.
*O, w. V correspond to biological half-time of 0-10 days, 11 to 100 days, and >100 days.
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C. Environmental Impact from Routine Plant Operation
1. Methodology for Radiological Assessment
The general approach for the demonstration of compliance with
the do~e limits of the standard is as follows:
(a) Monitoring of effluents released from plant operation to
determine the quantitites ot radionucl ides uiscr,arged into
the env·i ronment.
(b)· Utilizing envirqnmental dose models developed to estimate
dose commitment rates from all significant pathways.
It is only when there ·is a potent i a 1 for noncompliance that a
detailed environmental monitoring program is required to supple~ent
such effluent monitoring. The above approaches to demonstrate
compliance are i,, conformity with the recommendation specified
by EPA in their Final Environmental Statement (FES) for Environ-:
mental Radiation Protection Requirements for Normal Operations· - 1 of Activities in the Uranium Fuel Cycle.
Because of the special situations as destribed above at the
Allied Chemical Plant, the staff used-actual measured air
concentration as determined by the established environmental
monitoring program, rather than a source term and meteorological
models to calculate the air concentration at the nearest residence.
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,. :r.·,.ironr~e:r~.:i: : ,:r:t.~·.'a~:s ~m<: r:lC(!elt: ... c'e J:,.·:t~_;et! on ?e~. '::.1i,.:e l.: '::~ ·· :-1it:: the excerrticn that fer iri~lati.on, t:-ie dose conversion .:C-cict0rs
for various organs are r:enerated using the TC'P.P '.:'as}: ~roup Lun::r,
. . . . ,-:.' .... -· .. ..:-:._ ~-·~t:!
-3!1<.: solubilit:..- a.s Jiscussec in -~ec:kr. ,, ... ,... ',ll,::·. uSi-::•.:; caicu~ati..:n.
: ... ...... '.·ZIT:: o~ the ?lant. r:<i::ept •.,;here specified, the tem ''drse!'
referre<..:. to in this assessment is actuall'l a SO-year r!ose co~trr.ent,
that is, the total dose fron 1 :,ear c= :11take of radionuclides to
:-he reference organ that will accrue dlll"inr,: the reriaining lifetime
(Sf) years) of the ind.:.v:c!ual.
':'he nearest ~sic!ence is locatec! bet',;een a:!' samplinr.: stc1ticns
:•cs. :3 anc '!.l, the rm.xfour.i concentrations o: nuclices ,.t sar.:pEn9.;
:,c :.."1: : :o. 11 ~s usec'. !.'or r~cse ca.2.culatfon.
~or air ef:luents r-eleased into the envirornnent, the :-1c1thwa,,1s
ccnsit~ered in the individual dose estL-na"L.::.on :..nclu,~e (a) ,:::il."ect
irradiation, {b) direct inhalation, ·(c) inhalation fron resuspension.
•:)th~r ingestion ::iathways, i.e., ·,egetation, r.-.eat and cilk patht-1c1ys,
are considered to be negligitle or unrealistic. for liquid ef:luents
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water, shorel:ine deposit and .ingestion of ,:1c::ua-t:~.c :ocd: other
r,.:1th~,,a:m, ·i.e., ingestion of ,Jrinkinr; water or vegetation due to
:: . .:::-t:.:. ::-.:,1:::~~·nvs c.:1:i be ~rurY! i.n 'TY'e-'lt r!et: .. ,.:l in ~egulatory Guide 1.1rig'··.
,,d.rt,0rne and lic;uid ef~u~r.ts tc the neAreGt residence.
:'.:.; ~hc,.,_n in '!'able 9, the critical pathway is due to dir<:?ct inl:alation
:ind :::ieeul ts b an mc~i vidual dose to the .:.unr. of 2 3 . G ::'...'"'e.".1/ ·,'Y'. '.Jw
·.:'.:llculation ~ssumed ,:! r.o:rr.1ai ,1,:!ult: the staff abr., ccnsic:ered ,i
critical. ir.divic!ual at the ne.n~est residence. ':'he critical .:..'1Ji.•;icual
is an infant (0-1 age). If there 1s an infant at the nearest resider.ce,
the lunr; dose ttJ the infant: wil 1 he increased by a factor of about , ...
1. 8,..... i.e. , 4 2. 5 l!1I"eITll;rr, which will exceed the environmental
' standard substantially. TI1e licensee indicated that at the present
t:ur.e, there is no in:ant at the two above•men tioned nea rhy
• I res1uences. It is ncted that the liquid r.a-chways are not significant
to t~e individual dose calculation.
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A.
B.
Tab 1 e 9
Dose from Airborne and Liquid Effluents to the Nearest Resid~nce
Pathwais Organ Dose Total-~~
Air Effluents
1. Direct Irradiation 8.8 X 1 o- 3
2. Direct Inhalation* 0.28
3. Inhalation due to** 1. 2 X 10-3 Resuspension
Liguid Effluents
1. Shoreline Deposit and Submersion in Water
1.2 X 10-9
2. Aquatic Food (Fish) 2.2 X 10-4
Total 0.28
(millir~.!!1211!.l*** Lung. Bone
23.3 8.6
0.3 0.02
3.0 X 10-3
23.6 8.6
*Assume 80% resident time.
**Resuspension factor used= 10-9m-1
***The organ dose is calculated based on the annual average concentrations of radionuclides measured at Air Sampling Station No. 11 l'lhich is located at about 1240 ft Hof the plant. Based on the X/Q estimation as shown in Table 6c, it is noted that the concentration of radionuclides at the n~arest residence located at 1383 ft NNE in prevailing wind direction from plant could be higher. The estimation was based on lO'years meteorological data; however, each individual yearsmeteorological record could change somewhat.
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.:\.
'
:;olubili t·,· o: ?ac..:.cacti ve :·'.,:1.ter•.:.c.11 i.n
(''Y"""':1-":" .... J .. :J ...... ,
.. .-, . .:..r .::ffluents
. . .. ., ,-:~
C::)
errors asscc.i . .1tec::! in -:::r.e "'.:easure.r.:er.t:J, er selec-:ive che::..::.c.1.l sc;v-i.!:-at:.on
in the :1lant' s upP.ration prcce:-mes and release ::.n scme c,: "':h~ stac:ks
or directly from outside sources. If ms-: of the ':"n-2YJ is asswed
~ro!"l the ".lEoc Che.1"'..:i.cal pl211t. it is e:~ec-:ed that t~e Th-210 ·,:ould :,e
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Tab 1 e 10
Inhalation Dose Conversion Factors (Task Group Lung Model)
Compound & Lung-Dose Conversion Factor (Rem/11Ci. inhaled) Particle Nuclide
Size 0-238 U-235 0-234 'fh-230 Ra-226
Y Comeound* AMAD
0. 3 um 610 650 690 680 1,600
1.0 .. m 390 420 450 440 l ,000
3. 0 um 240 250 270 270 610
5. 0 :Jin 180 200 210 200 . '
470
10. 0 :,m 120 130 140 140 310
H co;ound*-A D
0. 3 :Jm 62 66 70 69 160
1. 0 (Jffi 40 42 45 44 100
3.0 um 24 26 27 27 62
5.0 um 18 20 21 21 47
10.0 um 12 13 14 14 32
D co;ound* A b
0. 3 -um 1.0 1. 1 1. 2 1. l 2.6
1. 0 1,m 0.7 0.7 0.7 0.7 0.7
3. 0 .im 0.4 0.4 0.4 0.4 1.0
5.0 um 0.3 0.3 0.3 0.3 a.a 10.0 um 0.2 0.2 0.3 0.2 0.6
*D, W, Y correspond to biological half-time of 0-10 days, 11 to 100 days, and >100 days. AMAD = Activity median aerodynamic diamet~r ..
1 .
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Table 10
I nha 1 ati on Dose Conversion Factor (Task Group Lung Model)
Compound & Bone-Dose Conversion Factor {Reml~Cf inhaled} Particle Nuclide
Size U-238 U-235 IJ-234 Th-230 Ra-226
Y Compound* AMAD
0.3 lJffi 5.3 ~.S 5.8 1200 31.6
1 • O µm 3.6 3.8 3.9 820 33.9
3.0 µm 2.6 2.7 2.8 600 43.2
5.0 µm 2.2 2.3 2.4 520 47.8
10.0 µm 1. 8 1. 9 2.0 430 S?.. 4
I~ Compound* AMAD
O. 3 iim 9. 1 9.5 10.0 2300 37. 8
1.0 µm 8.9 9.3 9.7 2200 41. 9
. 3.0 µm 10.0 11.0 11.0 2500 53.8
5.0 µm 11. 0 11. 0 12 .o 2700 60.0
10.0 µm 11. 0 12.0 12.0 2800 66.2
D Comeound* AMAD
0.3 µm 37.8 39.5 41.2 10136 77. 5
1.0 µm 36.4 38.0 39.7 9780 80. 1
3.0 µm 41.0 43.0 45.0 10000 98. l
5.0 µm 44.7 46. 4 48.8 · 11945 107. 1
10.0 µm 46.5 48.5 51. 5 11000 115. 3
*D, W, Y correspond to biological half-time of 0-10 days. 11 to 100 days, and >100 days. AMAD = Activity median aerodynamic diameter.
. • . " t
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46
in its oxide or halide forms. In the dose estimation it was assumed
that all of the Th-230 was Y (insoluble) compdund16 ; however, ff
some fraction of the Th-230 was a W or D compound, it will cause
a rather high bcine dose (see Table 10 for comparison). The staff
therefore recommends that future uranium solubility studies include
Th-230. In addition, the licensee should investigc1te the source of
these high Th-230 concentrations detecte<i in its environment.al air
samples.
B. Particle Size Distribution in Air Effluents
In the dose ~ .. sessment, if no information is obtainer! on particle
size c!istrfbution, the staff would assume an average -AMAD of 1 um for I
. the air effluents7
. Since the licensee had conducted particle size
distribution measurement and found that the average AMAD in ambient air
collected at air station No. 11 was 4.5 1Jm, th;s infonnation was used for
dose calculations. The BNWL also found, from its inrfependent air samoling
at station No. 11, that about 42~ of the air particulates were about 5,5
i.;m. The AMAD of 4.5 1.1m appears to be higher than other ambient air studies
at suburban, rural and seashore areas (where agglomerization of aerosols is
significant in the seashore area) 17 ... (The above studies showed that:
suburban air: MMED* 1.0-1.4 um, TSP concentration: 44-104 ug/M\ rural
air: ~"1ED: O. 7-1.2 µm, TSP concentration: 34. 3-43. 8 ug/M\ seashore air·:
MMED: 1.4-2.9 µm, TSP* concentration 34.3-41.l µg/M 3). The fly-ash
released from the Shawnee coal-fired power plant may have some effect -on
the particle size distribution in the ambient afr around the area; however,
the BNWL air samples showed TSP concentrations of about .5.7 µg/M3 (21 days
MMED = Mass median equivalent diameter TSP.= Total suspended particulate
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sample) and 16 µg/M3 (2.7 days downwind sample) which indicated
that the air was cleaner in TSP than the above studied ambient air.
Therefore, the staff recommends the continued studies on the
partfcle size distribution .at the nearest residence at NNE ·direction
from the plant. From the licensee's particle size study, the fraction
of air exceeding 15 ~m was small and the concentration of uranium under
10 ;Jffi as measured by the cascade impactor was about the sar,e compared
with the high volume air sampler at station No. 11. Therefore. no
credit was given for non-inhalable particulates in the dose
1 l . 18 ca cu at1ons.
C. Maximum Impact on Critical Individual in the General Public
As disctissed in Section C-2, the critical individual at the nearest
residences would be an infant (age 0-1) if there is any in future. The
1 ung dose to an infant wi 11 be increased by a factor of about l. 8
compared to a normal adult. From the X/Q calculations as a function
of distance from the plant, the staff estimated that if there is an
infant at residences in future within the sectors N, NNE, NE and up to about
900 meters from the plant, the tung dose may exceed 25 mrem/yr based on
the existing information and parameters. In addition, the dose
estimation does not include other ingestion pathways (milk, beef;
vegetation) as outlined in Regulatory Guide t .109. Therefore, the
licensee should evaluate realisti'cally the above parameters which are
considered to be important in future dose assessment for the demonstration
of compliance of 40 CFR 190.
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4. Conclusion and Recommendations
The normal operation of the Allied Chemical UF6
plant results in the
release of some quantity of radioactivity into the environment. Based
on current operation, the annual radiological effluent releases
include about 291,000 1JCi of alpha (mostly uranium) in air effluent
and about 2.0 Ci of alpha (mostly uranium} "in ·liquid effluent. The
annual average concentration of radioactivity in air measured in
1979 included:
Uranium: 2.9 x 10- 14 ~Ci/ml,
Th-230: 1.7 x 10-15 uCi/ml, and
Ra-226: 4.2 x 10-1 7 1:Ci/ml.
The above concentrations represent the measured cumulative impact,
if any, to the nearest residence from other nearby facilities such
is the Paducah Gaseous Diffusion Plant and the Shawnee steam plant
within 5 miles from the plant.
Based on the above concentrations and the preliminary uranium
solubility studies conducted by the Battelle Northwest Laboratory
(BHWL}, the staff esti~ated that the dose to an adult at the
nearest residence at NNE from the plant would be 23.6 mrem/yr to
the lung which is at the borderline of the 25 mrem/yr standard. The
lung dose to a critical individual, an infant, if there is any in
the future, would be abou_t 42.~ mrem/yr.
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49
The staff has evaluated the impact from the nearby Paducah Gaseous Diffusion Plant which releases about 900,000 1jCi of uranium in air effluent annually1 3. The release is about 3 times higher than the Allied Chemical Plant. The Gaseous Diffusion Plant is located about 5 mil~s SW from the nearest residence of the Allied Chemical Plant. The contribution of uranium concentration at the nearest residence from the. Gaseous Diffusion Plant is estimated to be only about 14:·,. of the total uranium concentrations because of a much greater distance away from the nearest residence from the Allied Chemical Plant. The estimated solubility of uranium compounds released from the Gaseous Diffusion ~lant is about 36: insoluble and 64% soluble13 . Therefore, thi release of uranium compounds from the Gaseous Diffusion Plant is estimated to have a contribution of about 7':~ to the lung dose to an individual at the nearest residence from the Allied Chemical Plant. The additional impact, if any, would be from the nearby 1750 MWe Shawnee Steam Plant located about 2.5 miles SW of the nearest residence from the Allied Chemical Plant. There is no stack release information of radioactivity from the Shawnee Plant. However, it is estimated that the alpha activity (from U-2~8 and Th-232 and their daughters) released from a 1000 MWe coal-fired power plant would be on the order of 47-150 liJCi/yr (radon and its daughters excluded) depending on the fraction of fly;.ash released. 14 Using the conservative release rate, the staff estimated that the contribution of radioactivity from the Shawnee Plant would be less than 1% of the total concentration of radioactivity at the nearest residence because the Shawnee Plant has a very tall stack which enhances the atmospheric dilution substantially.
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Therefore, additional impact from the nearby coal-fired plant to
the nearest residence is expected to be insignificant.
The staff realizes that the dose calculation and estimation are
subject to uncertainties involving (a) the representativeness of the
sampling time for the uranium c;olubility test, (b) the particle size
di:;tribution of.the radioactive particulates at the nearest residence,
and (c) the representativeness of air sampling station No. 11 near
the nearest residence at N~E from the plant. Therefore, the
following recommendations will allow the staff to conduct a more
accurate assessment of the dose received by the maximum nearest
resident from future operation of the Allied Chemical Plant:
(a) The licensee shall continue the existing environm~ntal air
monitoring program. Continuous air sampling shall be conducted
at all the stations and the air samples shall be composited at
each station and analyzed at least monthly for uranium ind
quarterly for Ra-226 and Th-230. All analyses specified dbove
shall be performed with an analytical sensitivity of.at least
.10- 16 uCi/ml.
(b) Samples taken at station No. 11 shall be composited quarterly
and analyzed for uranium and Th-230 solubility. The solubility ' .
analysis shall follow the methodology and procedures established
by Battel le Paci fie Northwest Laboratories ·(BNWL) 1 •2 or an
equivalent method acceptable to N·Rc. If a laboratory other than
BNWL is used for the analysis, the licensee shall -provide NRC . .
with a split sample· so that NRC· can perform a verification analysis.
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51
acceptable to NRC. If a laboratory other than BNWL is used for
the analysis, the licensee shall provide NRC with a split sample
so that NRC can perform a verification analysis.
(c) The licensee shall promptly install a new air sampling station at the nearest residence NNE of the p'ant. When the new station is operable,
samples collected at tll·: new station will be used for the solubility
determination required in items (a) and (b) above in place of samples collected at station No. 11.
(d) The licensee shall determine the particle size distribution of
radioactivity in air at the riew sampling station using a multiple
stage_cascade impactor capable of fractionating particles in
the respirable and non-respirable size ranges. The impactor
shall be operated continuously except for those periods
required for disassembly for particle size distribution analysis.
The particle size distribution analysis shall be performed once per
month as a minimum and more often if necessary to assure effective
particle retention and fractionation.
Based o~ tfte current available information, the staff concludes that·
the operation of the Allied Chemical Plant is at the borderline of
exceeding the EPA standard. Further measurements of the important
1. Solubility Classification of Airborne Products from Uranium Ores and Tailings Piles- D.R. Kalkwarf, BN~lL, November, 1978, USDOE Contract NO. EY-76-C-04-1830
2. Second Quarterly Report on Solubility Classification·of Airborne Products from LWR-Fuel Plants- D.R. Kalkwarf, BNWL, October, 1979.
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52
parameters for dose calculations as. recommended by the staff \•dll
provide a more accurate assessment of the in.dividual dose. In
addition to the above recommendations, the following licens·e conditions
are recommended in order to ensure compliance of the EPA sta11dard
as specified in 40 CFR 190:
(e) If t~e ~verage concentr~tion of radioactivity in air measured
from samples collected from existing stations No. 8 and No. 11
exceeds 3.0 x 10- 14 uCi/ml over a calendar auarter, the licensee
shall, within 30 days, prepare and submit to the Commission a
report which i den ti fies the ca•::,..: for exceeding the 1 imit and
the corrective actions to be taken by the lice~see to reduce
radioactivity release rates. 3 If the parameters important to a
dose assessment change~ a report shall be submitted within 30 days
which describes the changes in parameters and includes an estimate
of the resultant change in .dose commitment. 3
(f) In the event that the calculated dose to any member of the public
in any consecutive 12-month period is about to exceed the limits
specified in 40 CFR l90. l0, the licensee shall take immediate
steps to reduce emissions so as to comply with 40 CFR 190. 10. As.
provided in 40 CFR 190.11, the licensee may petition the Nuclear
Regulatory Commission for a variance from the requirements of
40 CFR 190.10. If a petition for a variance is anticipated, the
3. The report for petition should be submitted to the Director, Office of Nuclear Material Safety and Safeguards.with a copy to the Director of the Regional Office of Inspection and_ Enforcement.
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.-~ 1()(" , "':. ,_ • ~ ........ I. - I.
\
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54
REFERENCES
l. 40 CFR 190, Environmental Radiation Protection Requirernents'for Normal Operations of Activities in the Uranium Fuel Cycle. Final Environmental Statement. Vol. 1 USEPA. November 1976.
2. Environmental Impact Appraisal of the Allied Chemical Corporation Nuclear Services Division UF5 Conversion Facil.ity, Metropolis. Illinois. Docket No. 40-iJ92. August 1977. US NRC, Office of Nuclear Material Safety and Safe~uards, Division of Fuel Cycle and Material Safety, Washinqton, D.C. 3. Re9ulatory Guide.1.111. Methods for Estiriatinq Atmospheric Transport and Dispersion of. Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors. us rrnc. July 1977.
4. Solubility Classification of Airborne Products fron Uranium Ores and Tailing Piles, D. R. Kalkwarf, BNWL, November 1978.· US DOE Contract No. EY-76-C-04-1830.
S. Second Quarterly Report on Solubility Classification of Airborne Products from LWR-Fuel Plants - D. R. Kalkwarf, BNWL, October 15, 1979. 6. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.109.- Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the rurpose of Evaluating Comi)liance with 10 CFR Part 50, Appendix I. March 1976. 7. Task Group of Committee 2, ICRP, Task Group on lung Synamics for Committee II of the ICRP, Health Physics, Vol. 12, 1966. 8. Task Group of Comrnittee 2, ICRP. The Metabolism of Compounds of Plutonium and other Actinides, ICRP Publication 19, Pergammon Press, Oxford, 1972. 9. J. R. Houston, D. L. Strengh, and E. C. Watson, DACRIN - A Computer Program for Calculating Organ Dose from Acute or Chronic Radionuclide~ Inhalation, BNWL - B-389, Battelle Pacific Northwest laboratories, Richland, Washinqton, 1975. ..
10. M. H. Momeni, Y. Yuan and A. J. Zielen, The Uranium Dispersion and Dosimetry ( UDAD) Code, NUREG/CR-0553, ANL/ES- 72, Version IX, 1979. J
11. Correspondence from Dr. D. R. Kalkwarf (BNWL) to NRC, Mr. W. T. Crow on January 11, 1979. Docket No. 40-3392.
12. NUREG-0172, Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, BNWL, Nrivember 1977.
13. Environmental Monitoring at Major U.S. Energy Research & Development Administration Contractor Sites, ERDA 77-104/2, 1976. 14. Final Report-Activities, Effects and Impacts of the Coal Fuel Cycle for a 1000 MWe Electric Power Generating Plant. Prepared for US NRC by Teknekron Research, Inc. October 1919. ·
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55
15. Correspondence from Dr. D. R. Kalkwarf (BNl~L) to NRC Mr. W. T. Crrn on January 11, 1979, Docket No. 40-3392.
16. "Inhalation Risk from Radjoactive Contaminants," IAEA Technical Reports Series No. 142, Vienria, 1973.
17.. L. Van Vaeck et al. . "Differerices in Particle Size Distribution of Major Organic Pollutants in Ambient Aerosols in Urban, Rural, and Seashore Areas." Environmental Science?. Technology, December 1979, P. 149J.
18. F. J. Miller et al. "Size Considerations for Establishing a S~andard for Inhalable Particles." J. of Air Poll~tion Control Association, 1/ol. 29, ~fo. 6, June, 1979. P. 510 ..