1988-12 – DOE – Hazard Assessment for Exposure to Radioactive Fill Dirt Use for the Parking Ramp of the St. Louis Airport Parking Garage

1988-12-doe-hazard-assessment-for-exposure-to-radioactive-fill-dirt-use-for-the-parking-ramp-of-the-st-louis-airport-parking-garage

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O.S. nepartment of Enerqy
oat Ridge Operations
Post Office Box 2001
Oak Ridg~, TN l78)1-8723
‘ · . .
OSS609
Dsil831
Bechtel National. Inc.
S…..~s-~~ ~~
~fill= Taa: .
ICIO Ota “-TwrfiOiiU .
O*IW;Llec•erM ~7130
.,….._,. . .D..lf.l nI 0 … act 0-~ l’lr J)UI OJ50
~~· l –
Attention: Andrew P. A vel, Site ~tanager
Technical ServicGs Division
Subject: Bechtel Job No. 14501, PUSRAP Project
DO! eontract No. DE-ACOS-810R20722
Hazard Assessment for Exposure to Pill Dirt used for the
Parkinq Ramp of th& St. Louis Airport Parkinq Garaqe.
Code: 7340/WBS: 134
Ref~rence: National Council on Radiation Protection an~ .
Measurements, Exposure of the Population ln the United
States and Canada fro~ Natural Back9round Radiation,
Bethesaa, MD, Decemher ~~~ 1987. .
Dear Mr. Avel:
In response to your request, a hazard assessment usjnq conservative
assumptions was developed for workers performing activities {n the
vicinity of the St. Lou!s Airport Site (SLAPS) (see Enclosure A).
The hazards to a laborer and truck rlriver involved tn lnad1n9 and
hauling the conta~inated soil to the ramp site and to a potential
road vorker performinq rP.pairs on th• ramp slopes was assessed for
radiation ~xposure to the contaminated soil taken fr~M Coldvater
Creek bed. The methodoloqy and parameters for the dose
calculations and tahles of the dos~s are shown in Enclosure A.
!~ su~~ary, the maximum dose to a laborer loadinq the soil was
estiaated to be 0.16 nrem, and the maximua rlose to the truck driver
haul i ng the soil to the ramp slte w.as estiruted to l’\~ O, 12 mre”.
The doses were fro• external gamma only since the soil was wet and
no airborne activity was likely. The total dose to the road ~orker
engaged in making repairs on the ra~p ~as estimated to be
0.42 mrem, a total of the cofthined ext~rnal qaftma and inhalation
doses. ~he hi9hest dose of 0.42 mre~ to any of tho ~orkers is ~nly
0.42\ of th~ DOE basic limit of 100 mrem for the ~nnual radiation
dose receiv~d by an indivioual ~e~her of the qeneral puhlie and
only about 0.14\ of the normal back9roun~ ra~ ia tion of JOO mrem/yr
for the area freferencP.d above).
058509 ouen
Andrew P. Avel 2
Since the conservative estimate ot the doses ~o the workers are
vell belov the DO! radiation protection standard, th~re is no
hazarc! to personnel who may coJle tn contact w~i th the ·tamp or to the
general public in leavinq the fill material in place. I
CRH:djw:89l4A
Enclosure: ~ stated
Very truly yours,
I
~~ .I
S. o. Liedle
Project Manager – PUSRAP
I
. . ”
nssoo9
BEHIND lHIS SHEET
IS TSD BACKUP ·
MATERIAL FOR FlllNG
PURPOSES ONLY – NOT
TO BE DiSTRIBUTED
878CIA
050609 oseen
. ENCLOSURE A
t. EXPOSURE SCENARIOS
I
A. Lab_Q,Jer f.temovi ng soil From Coldwater ‘1 creek
lt is assumed that the laborer s?ent1one week (40 hours)
during the year removing the soil tojbe used as fill dirt
from the ereek be~. lt is conservatively assumed he was
1 standinq on the c:ontamina ted soi 1 dur tnCJ. the soil removal,
thus if he was usinq a mechanical loader no shieldin9
factors for reducing the exposure rate ~as taken into
consideration. Since tho soil was wet, an inhalation dose
due to airborne dust particles was not considered li~ely.
B. Trucker Hauling the Soll from Coldwater creek to the Ai re.ort
Pa!kinq Garage Ramp {A Distance of three miles)
1
PI
It. is assumed that the trucker spent! 30 hours exposed to the
contaminated soil while the truck wak being loaded ond
I
enroute to the ramp •. No shiP.ldinq factors wer~ considered.
I
Thus, his dose ~oul~ be three-fourths that of the laborer.
I
SincP. the soil is wet or damp# no in~alation dose is
considered likely.
c. Road Worker tlorkinq_on the Ramp
8914A
12/23/88
It is assumed that the worker spends 40 hours during the
year workin9 on the ramp slo~e repai1ring drainage, etc. 1t
iR also assumeo that the ~or~er is e~posed to dry soil that
I
would beco~e airborne durin9 excavation. A maximu~ mass
loading factor of 4 x 10 -4 g/m 3 ~as pI sed to estt•m ate th e
air concentr~tion of resuspenderi con~aminate~ dust particles.
t t • SOURCE TERMS .
The source terms used for dose calculations are the avera9e
concentration of the radionuclides in th• top foot of soil
~aken neat the bridge over coldwater creek at Menonnel
Boulevar
Dose Conversion Paelors
Radionu.clide
Uranium-234
Oraniuii-23S
Urantum-238
Rad·i um-226
Thorium-230
‘:’horiura-232
External Dose
(mrem/ yr eer pCi/?J
l, 4 0 X 10-3
~ ,4 4 X 10-l
1.30 X 10-l
1.58 X 101
1.90 X 10-l
1.26 X 10-l
in area
2. Methodolo9y for caleulatin9 external ~am~a dose
(Ref. l)
Dose fmrem/yr) ~ {concentration of radionuclide in soil
( pCi /g) (depth factor J ·{a rea factor 1 (occupancy factor)
[dose conve~sion factor (~r~m/yr per pCi/g))
4 —————————- –· -· .. – – ·-
1111!1111——— -·-“”• ·.· ·.. ….. – =–7″” · ·- •.• •.- . ·.. “. .. .. .. l .:. ; . –·–.- ~ .. ; .. –. ;-,”, ,”.;:·-~ ,,. ..- · ..;: . ·.. ·.~ … · ::-~ ..


osa;).-og
! asees,
IV. Ma:Jt isua Dos& to -Workers
89l4A
12/23/88
‘l’ABLt 1
TOTAL DOSE tO LABORE~ REMOVING SOIL
FROM COLDWATER CREEK !.
Radionuclide
Uranium-214
uranium-235
Uranium-238-
Radium-226
· ‘I’horium-230
‘I’horium-232
Total
I External Gamma Dose
(mreuVyr)
TAElLE 2
TOTAL DOSE ‘1’0 TRUCKER HMJ!.l Nq SOIL
TO R””‘P Sl ‘t’E
Radionuclide
uranium-234
uranium-23S
uranium-238
Radium-226
Thorium-230
Thor i um-2 l 2
Total
External damma Dos~
(mrerit/yr)
s
2.8 X lo-S
1. 2 x lo-4
2. G x , 1o-l
1.2 x lo-1
2.1 x lo-4
5.1 X 10-6
1.2 x 1o-1


1
•• ,., • , I , • • •• • ,; ~ ,,l) •. •. • : • • , •, i , • • . • \~’I t’ , • … \
IV.. Mil”inm Dose to Workers
89l4A
12/23/88
‘l’ABLf! l
TO’rAL DOSE TO LABORER REMOVING SOIL
PROM COLDwATeR C~£2K
External Ga1!una Dose
Ridionuclide Cmr~m/yr)
Urartium-234 1.8 X 1o·S
uraniura-235 4.3 X 1o·t
Uranium-238 3.5 X 1o-J
Radium-22’6 1.6 X 1o·l
Thorium-230 3.7 X lQ-4
Tho ri Utn• 2 3 2 7.0 X 1o·6
Tota! l.6 X 1o-1
TABLE 2
“TOTAL DOSE TO TRUCKER HAUi..lNC SO[L
‘t’O RAMP SI’l’E
External Gamma
Rad ionucll de (mrem/yr)
Uranium-234 2 •. 8 X lo-s
Uranium-23S l. 2 X Io-4
Uranium-23B 2.6 X 1o-l
Radiuaa·226 1.2 X 1o-1
Thor ium-230 2.7 X l0-4
Thorium-232 S.l X 1o-6
Total l.2 X 1o-1
5
nose



Radion\lelide
Ot’anium-234
tJraniutrt•23S
or ani um-238
Radium-226
Thodum-230
Thocium-232
‘rotal•
05S609
TABLE 3
TO!AL DOSE TO ROAD WORKER ~!PAIRING
SLOPE OF GAJtAG£ RAMP
£x~ernal Gal!lla nose Inhalation oose
(mr~r.t/yr) (mrem/yrl
3.8 I lo-s 1.2 X to-2
4.l X lo-4 1.9 X l0-4
l.S X 1o-J 1.1 X l0-2
1.6 X 1o-1 2.9 X to·4
l. 7 X lo-4 2.1 X to·l
7,0 X 10-6 l.O X l0-2
1.6 X 1o-1 2.6 X to·l
•rhe combined dose from external gamma and i nhalation
a 4.2 z lo-1 ~rem/yr.
891~”
12/21/88


OS86D9
1’ABLE 3
TOTAL DOSE TO ROAD WORKER REPAIRING
SLOPE OF CARAGE RAMP

Ext~tfi&l Gllnl!ta Dose Inhalation oose
Radionuelide Cmrei”‘\/yr) {lfttem/yr)
uranium-23ot
uraniu~n-2l5
oranhull·238
Radium·226
Thorium-230
Thorium-232
l.S .x
4.3 X
3.5 X
1.6 X
3.7 X
7.0 X
lo-s 1.2 X
lo-4 1.9 X
10•.3 l.l X
1o-1 2.9 X
lo-4 2.1 X
lo-‘ l.O X
Total* 1.6 X 1o-1 2.6 X
*Tne eo~ined dose from external 9am~ and inhal~tlon
· • 4.2 :r lo-l mrera/yr.
8914A
12/23/88
l0-2
10_,
l0-2
lo-4
l0-1
lQ-2
l0-1
..


I .
05I 81.\ ng ~
Qt~~wnas a •
1. GiltH!rt, ‘r. L., et at. A Manual for Impller~ent.inCJ Residual
Radioactive Material CUid~lines, Washington, D.c.,
I
Jan&l~tY 1988 (In press). A Sllpplement to o.s. Department of
Ener9y Guidelines for Residu~l Radioact iJitr at Formerly ·
2tili:ed Sitea Remedial Action Program arid Renote surplus
Paeilities Manageme~t Pro9ran Sites •
89l4A
l:l/23/&S
..,