docket no: 40-3392 · scrubber 11 8 11 top hydrofluorinatol' filters 11 8 11 top...

57
... 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 UF 6 conversion plants used for produLtion of U1R fuel. The All fed Chemical facility is a UF 6 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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Page 1: DOCKET NO: 40-3392 · scrubber 11 8 11 top hydrofluorinatol' filters 11 8 11 top hydrofluorinatur scribber -UF 4 dusl collcctur Uf 4 dust collector Ash vacuum cleaner Contam1nate

...

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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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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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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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 #')~'

.. --~,

'

Page 27: DOCKET NO: 40-3392 · scrubber 11 8 11 top hydrofluorinatol' filters 11 8 11 top hydrofluorinatur scribber -UF 4 dusl collcctur Uf 4 dust collector Ash vacuum cleaner Contam1nate

=-: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.~

r-· .....

Page 28: DOCKET NO: 40-3392 · scrubber 11 8 11 top hydrofluorinatol' filters 11 8 11 top hydrofluorinatur scribber -UF 4 dusl collcctur Uf 4 dust collector Ash vacuum cleaner Contam1nate

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Page 29: DOCKET NO: 40-3392 · scrubber 11 8 11 top hydrofluorinatol' filters 11 8 11 top hydrofluorinatur scribber -UF 4 dusl collcctur Uf 4 dust collector Ash vacuum cleaner Contam1nate

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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

Page 31: DOCKET NO: 40-3392 · scrubber 11 8 11 top hydrofluorinatol' filters 11 8 11 top hydrofluorinatur scribber -UF 4 dusl collcctur Uf 4 dust collector Ash vacuum cleaner Contam1nate

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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Page 33: DOCKET NO: 40-3392 · scrubber 11 8 11 top hydrofluorinatol' filters 11 8 11 top hydrofluorinatur scribber -UF 4 dusl collcctur Uf 4 dust collector Ash vacuum cleaner Contam1nate

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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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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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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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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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 ..