&EPA
United States
Environmental Protection
Agency
Environmental Monitoring
Systems Laboratory
P.O. Box 93478
Las Vegas NV 89193-3478
EPA 600/4-91/031
November 1991
Research and Development
Environmental Monitoring
Report
Radiation Monitoring
On and Around the
Tatum Salt Dome,
Lamar County, Mississippi
April 1991
1238mPB91 rpt
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Radiation Monitoring On and
Around the Tatum Salt Dome, Lamar
County, Mississippi
April 1991
by
D. J. Thome*
S. H. Faller
C. A. Fontana
C. F. Costa
Environmental Protection Agency
P.O. Box 93478
Las Vegas, NV 89193-3478
prepared for the U.S. DOE
under Interagency Agreement
DE-A108-86NV10522
ENVIRONMENTAL MONITORING SYSTEMS LABORATORY
OFFICE OF RESEARCH AND DEVELOPMENT
U.S. ENVIRONMENTAL PROTECTION AGENCY
LAS VEGAS, NV 89193-3478
1238mPB91.rpt
-------
NOTICE
The information in this document has been funded wholly or in part by the United States Environ-
mental Protection Agency through Interagency Agreement DE-A108-91NV10963 from the United States
Department of Energy. It has been subject to the Agency's peer and administrative review, and it has been
approved for publication as an EPA document.
Mention of trade names or commercial products does not constitute endorsement or recommendation
for use.
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ABSTRACT
In 1964, and again in 1966 a nuclear explosive was detonated approximately 2700 feet underground
in the Tatum Salt Dome located in Lamar County, Mississippi. Drilling and cleanup activities have resulted
in tritium contamination in close proximity to the surface ground zero. The Long-Term Hydrological
Monitoring Program conducted by the U.S. Environmental Protection Agency consists of annual water
sampling on and around the Tatum Salt Dome. In 1991, in addition to water sampling, a gamma-ray
characterization study was conducted.
As in past years no radioactive materials from the Tatum Salt Dome were detected in any water
samples collected offsite. The highest tritium concentration found in water collected in the offsite area was
48 pCi/1. This is from natural sources and is 0.24 percent of the National Interim Primary Drinking Water
Regulations (40CFR141) which places the maximum level of tritium in drinking water to be 20,000 pCi/1. The
highest tritium concentration found onsite was 14,000 pCi/1. This concentration was detected in water samples
collected in two wells, Well HMH-1 and Well HMH-2. These wells are both less than 10 feet deep and they
are located very near to the surface ground zero. The water from these wells is not available to the public nor
suitable for drinking due to its brackishness.
The gamma-ray characterization study consisted of eight locations onsite and four offsite. The study
showed good agreement between exposure rates derived from in-situ gamma-ray spectrometry and those
measured with a pressurized ion chamber in all locations surveyed. Variabilities of gamma flux contributed
by radionuclides in the soil were small with the exception of 137Cs, which was lower than expected in all onsite
locations. The 137Cs is the result of global fallout from atmospheric nuclear testing.
in
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CONTENTS
Page
Abstract iii
Figures vii
Acknowledgments viii
Introduction 1
History 1
Monitoring Results: Historical Summary 1
Calendar Year 1991 Monitoring Results 5
Water 5
Sample Analysis Procedures 8
Water Analysis Results 8
Gamma-Ray Characterization Study 11
Gamma-Ray Characterization Results 11
Conclusion 12
References 13
Appendices
1 Abbreviations 14
2 Glossary of Terms 15
3 Summary of Analytical Procedures 16
4 Results for Water Samples Collected in April 1991 17
5 Exposure Rate Inventories at all Survey Locations 24
6 Soil Sample Study 25
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FIGURES
Figure Number Page
1 General site location 2
2 Topographic map of the Tatum Dome Test Area showing the Surface Ground Zero and
outline of Salt Dome at 2,700 feet below land surface 3
3 Test cavity and aquifers 4
4 Plots of tritium concentrations vs. time 6
5 Locations in the vicinity of surface ground zero sampled and monitored in 1991 9
6 Offsite locations sampled in 1991 10
VI
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ACKNOWLEDGMENTS
The authors would like to acknowledge Mr. M.G. Davis for his dedication to quality and his tireless
work in the design and execution of the sampling effort. We also want to thank Ms. D.J. Chaloud for her
suggestions, editorial expertise, and for bringing this document to fruition.
VII
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INTRODUCTION
Under an Interagency Agreement with the U.S.
Department of Energy (DOE), the Environmental
Monitoring Systems Laboratory (EMSL-LV) of the
U.S. Environmental Protection Agency (EPA) located
in Las Vegas, NV, conducts a Long-Term Hydro-
logical Monitoring Program (LTHMP) to measure
radioactivity concentrations in water sources near
the sites of underground nuclear explosions. The
results of the LTHMP provide assurance that radio-
active materials from the tests have not migrated into
drinking water supplies. This report presents the
results for the samples collected in April 1991, on
and around the Tatum Salt Dome, in Lamar County,
Mississippi.
History
Project Dribble, consisting of two nuclear ex-
plosions, and Project Miracle Play, consisting of two
non-nuclear gas explosions, were conducted in the
Tatum Salt Dome, near Baxterville, Lamar County,
Mississippi, between 1964 and 1970. The general
area is depicted in Figure 1. This area is called the
Tatum Dome Test Area (Figure 2) and contains
approximately 1470 acres located in Sections 11,12,
13 and 14, Township 2 North, Range 16 West.
Event Date Name
10-22-64 Salmon Nuclear
12-03-66 Sterling Nuclear
02-02-69 Diode Tube Gas
04-19-70 Humid Water Gas
Yield
5.3
0.38
0.32
0.32
These tests were part of the Vela Uniform
program of the U.S. Atomic Energy Commission
(now the DOE). The purpose of the tests was to study
the decoupling principle, i.e., to measure and evalu-
ate the phenomena of seismic waves that are induced
from the explosions as compared to those that occur
naturally from earthquakes.
The first explosion, the Salmon Event, created
a cavity in the Tatum Salt Dome that was used for the
other three explosions. The top of the cavity is 1,160
feet (360 m) below the top of the salt dome. The top
of the salt dome is another 1,500 feet (460 m) below
the land surface (Figure 3).
At the Project Dribble site, disposal of drilling
muds and fluids near surface ground zero (SGZ)
resulted in onsite contamination of shallow ground
water and the surficial aquifer with tritium (3H). The
shallow ground water, between 4 and 10 feet (1.2 and
3 m) deep, and the surficial aquifer that is approxi-
mately 30 feet (9 m) below the surface both consist
of non-potable water.
Tritium contamination has also been detected
in the potable water Local Aquifer which is 200 feet
(62 m) deep. The 3H appears to be migrating down
the exterior of the sampling well (HM-L) casing
from the surficial aquifer above. Well HM-L is
located very close to the SGZ and the well casing
penetrates the contaminated surficial aquifer. No
contamination has been detected in a second Local
Aquifer sampling well (HM-L2), located down gra-
dient from HM-L. All 3H contamination is less than
the concentration specified in the National Interim
Primary Drinking Water Regulations (40CFR141).
There is no indication from ground and surface water
monitoring that any radioactivity is presently escaping
from the test cavity.
Following each explosive event, the near-offsite
area was closely monitored by the U.S. Public Health
Service (PHS). The radiological monitoring became
the responsibility of EPA at its inception in 1970.
The EPA radiological monitoring is a continuing
responsibility. From 1964 to the present, neither the
EPA nor the PHS has detected any contamination
offsite resulting from the Tatum Dome experiments.
Monitoring Results: Historical Summary
After site cleanup activities in 1971-72 the
LTHMP was instituted. In this program, all potable
aquifers, many individual wells, public water sup-
plies, and some surface waters in the Tatum Salt
Dome area have been sampled and analyzed for
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Prentiss
•***_
Monticello
Brookhaven
Seminary
Bassfield A f Moselle
Eatonyille
Runnelstown
Bunker sumrall
Hill
Columbia
^
Cheraw
Purvis
Talowah
Beaumont
Brooklyn
Tylertown- I Pinebur w
MISSISSIPPI I Baxterville
7 \ ^Lumberton
LOUISIANA I /
Varnado ^ /
— Major Highway
(•) Test Site, SGZ
Figure 1. General site location.
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All tritium contamination found
within this circle with radius of
1400 feet (430m)
DRIBBLE SITE
BOUNDARY
T
W
_0>
1
CM
X
2
Q.
Q.
CO
I
approx. 1 1/2 miles
Baxterville
M^_
N
SCALE IN FEET
1000 2000 3000 4000 5000
_m
500 1000
SCALE IN METERS
1238GR90NRD-2
Figure 2. Topographic map of the Tatum Dome Test Area showing the Surface Ground Zero and outline of
Salt Dome at 2,700 feet (830 m) below land surface.
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I
3
w
a
i
s
I
i
/Well HT-2
Surficlal Aquifer
^Anhydrite
1160' ^ STA.1A ps-1
Salt Stock
PS-1W
PS-2W
Test
Cavity*
Highly
Radioactive
Zone
Recrystalized
Melt Puddle
SANDSTONE
Ground Surface
Local Aquifer
Aquifer 1
iifT Aquifer 2A
Aquifer 2B
Aquifer 3A
Caprock Aquifer
•!•!•!•!•!•!•!•!•* Aquifer4
i|i|i|;|i!i!i!Ji|1 Aquifers
*The test cavity contains fission and activation
products from the detonations plus 10,770
cubic yards of radioactive, contaminated soils
and 1,305,000 gallons of contaminated fluids
and water from surface cleanup.
1238GR90-3nnJ
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tritium and for any detectable gamma-emitting ra-
dioisotopes.
A special study was conducted in 1977-78
because of irregularities in tritium results in onsite
samplings from a pond near SGZ (Half Moon Creek
Overflow). To determine the source and extent of
contamination, a grid design was used to locate 171
shallow holes that were drilled into the surface ground
water. From the tritium results of the samples collected
from these holes, a set of LTHMP holes was selected
and added to the LTHMP sampling design. Tritium
levels in the surface ground water have shown large
fluctuations due to local rainfall. In general the
concentrations continue to decrease. Decreasing
trends, representative of those sampling wells with
the highest tritium concentrations, from the Local
Aquifer (HM-L), the Surficial Aquifer (HM-S) and
the surface ground water (HMH-1, HMH-2, HMH-
5) are shown in Figure 4.
Concern regarding possible health effects at-
tributable to the two nuclear detonations conducted
in the Tatum Salt Dome caused EPA to increase the
scope of the radiological monitoring activities in
1990 to include the following:
a. Urine samples from nearby residents.
b. Vegetables and soil samples from local
gardens.
c. Water samples from additional residen-
tial wells.
d. Milk samples from goats and cows.
e. Atmospheric moisture monitoring.
f. Atmospheric paniculate monitoring.
g. Deer, turkey, catfish, and turtle from the
vicinity of SGZ.
h. Soil, sediment, and vegetation sampling
in the vicinity of SGZ.
i. Water samples for non-radiological analysis
(volatile organics, semi-volatile organics,
pesticides, and heavy metals).
j. Cow tissue samples.
k. Goat tissue samples.
1. Five additional onsite shallow ground-
water monitoring holes.
For 1990, in all of the offsite samples, including
human bioassay, no radioactive materials from the
Tatum Dome Test Area were detected. Tritium
contamination was detected in some water samples
taken close to SGZ but the concentrations met the
EPA criteria for drinking water. No other radioac-
tive material above background was detected in any
sample. All tritium contamination was detected
within a 1,400-foot (430m) radius of SGZ. The
analysis of water samples taken in the vicinity of
SGZ for nonradioactive hazardous materials revealed
very low level concentrations of a few organic
chemical contaminants of unknown origin. No health
effects would be expected from the contaminants at
the concentrations found.
The 1990 study is described in the EPA report,
"Onsite and Offsite Environmental Monitoring Re-
port: Radiation Monitoring Around Tatum Salt
Dome, Lamar County, Mississippi, April 1990
(Thome et al., 1990). All analytical data resulting
from the LTHMP and other radiological monitoring
programs are published annually in EPA's "Offsite
Environmental Monitoring Report: Radiation Moni-
toring Around United States Nuclear Test
Areas,...." These reports have been published each
calendar year since the tests were conducted.
Calendar Year 1991 Monitoring Results
In April 1991, EMSL-LV conducted sampling
on and around Tatum Salt Dome. In addition to the
routine monitoring, a gamma-ray characterization of
the Tatum Dome Test Area was performed. The
locations of all sampling and gamma-ray measure-
ment sites are shown in Figures 5 and 6. Sampling
also included three locations in Columbia, MS, not
shown in Figure 6. The sampling results are dis-
cussed in the following sections.
Water
Much emphasis is placed on tritium analysis of
ground-water samples. Following an underground
nuclear test most of the radioactive materials that are
created decay away very quickly. Most of those
remaining are captured in the molten rock created by
the explosion and in the surrounding rock itself.
Tritium, which is naturally occurring and is also a
product of nuclear explosions, is a radioactive form
of hydrogen. It becomes incorporated in water
molecules and moves with the ground-water flow.
For this reason, tritium is used as an indicator of the
migration of radioactive materials created from
nuclear explosions.
In April 1991, the HMH holes were sampled
and then pumped dry. On the following day tritium
samples were again collected. Also, according to
standard procedure, one HM well (Well HM-3) was
pumped steadily and five samples collected at one-
naif hour intervals. The other HM wells were pumped
steadily and two samples collected at one-half hour
intervals. Two samples were taken on successive
days from Half Moon Creek, Half Moon Creek
Overflow, and the Pond West of GZ. All other
locations were sampled once. Additional water
samples were collected at the request of nine resi-
dents.
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Tritium in Water, Well HMH-1
Tatum Dome Test Area
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Q.
s—'
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to
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450000 -
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350000 -
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.
. 250000 -
i
200000 '
.
150000 -
100000 '
50000 -
n -
q
\
\
\
\
b
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1978 1979 1980 19811982 1983 1984 1985 1986 1987 19881989 1990 1991 1992
Year
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200000 '
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a.
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"• 100000 -
50000 -
Tritium in Water, Well HMH-2
Tatum Dome Test Area
a..
-n—-a,.
a—-a
0 1978 1979 1980 19811982 1983 1984 1985 1986 1987 19881989 1990 1991 1992
Figure 4. Plots of tritium concentrations vs. time.
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Tritium in Water, Well HM-L
Tatum Dome Test Area
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u
a.
c
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2600-
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0 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992
Year
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10000-
5000-
Tritium in Water, Well HM-S
Tatum Dome Test Area
"•n.
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0 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992
Year
(Depth = 30')
Figure 4. (Continued)
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Tritium in Water, Well HMH-5
Tatum Dome Test Area
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0 1978 1979 1980 1981 1982 19831984 19851986 1987 1988 1989 1990 1991 1992
Year
1041GR91-4A
Figure 4. (Continued)
Sample Analysis Procedures
The procedures for analyzing samples collected
for this report were described by Johns et al. (EPA
1979) and are summarized in Appendix 3. These
include gamma spectral analysis and radionuclide
analysis for strontium, tritium, and plutonium. The
EPA procedures are based on standard methodology
for given analytical procedures. Two methods for
tritium analysis were performed—conventional and
electrolytic enrichment. The samples were initially
analyzed by the conventional method. If the tritium
result was less than 700 pCi/I, the sample was then
analyzed by the electrolytic enrichment method which
lowers the Minimum Detectable Concentration
(MDC) from approximately 300 pCi/1 to 10 pCi/1. In
the data tables (Appendix 4), results obtained using
the conventional method are denoted by "3H" and
results obtained by electrolytic enrichment are de-
noted by "3H+". Sample results are corrected for the
background radioactivity in the laboratory. Occa-
sionally, negative results are obtained for extremely
low level samples due to slight fluctuations in the
background or analytical variability.
Water Analysis Results
No gamma-emitting radioactive materials were
detected. The highest tritium concentration above
the MDC in water collected from the offsite area was
48 pCi/L. This is from natural sources and it is 0.24
percent of the National Interim Primary Drinking
Water Regulations (40CFR141) that places the
maximum level of tritium in drinking water to be
20,000 pCi/L. The water samples from Wells HMH-
1 and HMH-2 both had the highest tritium concen-
tration, 14,000 pCi/L, which is 70 percent of the
drinking water regulation. Wells HMH-1 andHMH-
2 are located near SGZ and the water is not accessible
to the public nor suitable for drinking due to its
brackishness. In addition to the tritium and gamma
spectroscopy analyses, water samples from locations
sampled for the first time were analyzed for '"Sr, 238Pu
and 239+24°pu. All of the water sample results are
shown in Appendix 4. . Strontium-90, 238Pu, and
239+24opu were not detected at levels above the MDCs
of approximately 3 pCi/L, 0.05 pCi/L and 0.004 pCi/
L, respectively.
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HMH-16
Decontamiation
Pad
HMH-6
Water Lilies xx —HMH-4
200
Location/water sample
Survey Location
N
[WellHT-2C
'HT-2
1238GR90NRD-5
Figure 5. Locations in the vicinity of surface ground zero sampled and monitored in 1991.
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3
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3
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o
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s
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to
Little Creek #1
T.S. Saucier -
Yancy Saucier -
erman Gipson —
Lower Little Creek
GIN Ray's Crawfish Pond
Hugh Gipson
r-Willie Surge
I r~Joe Burge
Hattiesburg
•
A ©CD©®
Young s Dairy
M
u
Salt Dome Timber Co.
Donald Beach
A.C.
Mills
ujRoy Mills
B. Chambliss R. King
Anderson's Pond
v)©(u)B.R. Anderson
Dennis •
Saucier
Hulon Lowe Tatum Hunting
Club
Howard Smith
Rita Moree
Sylvester Graham
Lee L. Saul
P.T. Lee
H. Anderson (
J.R. Nobles
G.W. Anderson©
Noble's Pond
Rita Smith
Purvis Well
* *13
Regina Anderson
,.,„ . .
W. Daniels
Noble's Quail
House
Ray Daniels
Daniel's Well #2
• Location/water sample
0 Vegetation
I) Soil Goat
u) Urine
5) Milk
* Non-Rad Water Sample
A Atmospheric Tritium
Lumberton
i W
'u
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Gamma-Ray Characterization Study
This study was undertaken to inventory the
amounts of surficial gamma-ray emitting radioactive
materials and to determine the gamma-ray exposure
rates on and around the Tatum Dome Test Area.
Field measurements and soil core sampling were
conducted at eight sites on the Tatum Dome Test
Area and four locations in the surrounding areas.
The locations of the eight sites located near SGZ are
shown in Figure 5. The remaining four sites are the
B.R. Anderson residence near the Tatum Dome Test
Area, Purvis Elementary School lawn, Purvis High
School lawn and the Hattiesburg Fire Station #4 dirt
lot.
Gamma-ray spectra were collected in the field
with a high-purity germanium detector (HpGe) and
a desktop multi-channel analyzer. Power was sup-
plied to the electronics by aportable gasoline-powered
generator. The spectra were later interpreted by the
methods described in Beck et al. (1972) and Heifer
and Miller (1988). During the data collection time,
pressurized ion chamber measurements were made
around the individual sites and at the exact location
of the HpGe detector to determine the overall exposure
rates.
In addition, soil core samples were taken from
the sites to determine the distribution of radionuclides
with depth. The samples were separated into depth
intervals of 0-2.5 cm, 2.5-5.0 cm, and 5.0-15.0 cm
and packaged for shipment to the EMSL-LV labora-
tory, where they were prepared and analyzed.
Gamma-Hay Characterization Results
Appendix 5 lists the (one meter above ground)
dose rates measured in this study. Under the head-
ings of "Total" and "PIC" are listed the sum of all
nuclide and cosmic-ray contributions, and the pres-
surized ion chamber readings at the same locations
for comparison. Under the heading of "Other PIC
Readings" are given the readings taken in the vicinity
of each site. In addition to the pressurized ion
chamber readings listed, the following locations
were surveyed: south bank of Half Moon Creek
Overflow (5.5 u.R/hr), 20 m southeast of the surface
ground zero (SGZ) monument (5.9 |J-R/hr), 40 m
southeast of SGZ monument (5.7 ^iR/hr), 120 m
southeast of SGZ monument on access road (7.0 jiR/
hr), near Well HMH-11 approximately 40 m south-
east of SGZ monument (6.1 uJR/hr), and inside
REECo Pit near sampling location B (6.4 |iR/hr).
The gamma-ray contribution sums and the
pressurized ion chamber readings at all surveyed
locations are in good agreement. In most cases the
summed value is slightly less than the pressurized
ion chamber value probably due to attenuation of
radiation by surrounding trees (Miller et al. 1990).
Appendix 6 lists the 137Cs inventories calcu-
lated for each site surveyed with the germanium
detector. The table shows the depth distribution
parameter expressed as 3/p (Miller and Heifer 1985),
137Cs activity per unit area, and the MDC. No other
manmade radionuclides were detected. The 137Cs
inventories at all onsite locations are much lower
than those at offsite locations where the surveys were
taken on lawns. This is expected because dense grass
cover is known to strongly retain deposited global
fallout (Beck 1979), and the onsite locations were
generally bare or partially covered. Also, all of the
onsite surveys were made at locations where covering
material was put down in remedial clean-up opera-
tions. The presence of sand or gravel and the lack of
humus causes a reduction of 137Cs retention and
promotes a deeper dispersion of the cesium that
remains, resulting in the low values of 3/p .
11
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CONCLUSION
Njo radioactive materials from the Tatum Dome
Test Area were detected in any of the offsite water
samples. Onsite, tritium was the only radioactive
contaminant detected. The tritium contamination
was found in brackish water collected from shallow
wells located near SGZ. Although this water is not
available to the public nor fit for human consumption
because of its brackishness, the tritium concentra-
tions are well below those defined in the EPA Na-
tional Interim Primary Drinking Water Regulations
(40CFR141).
The gamma-ray characterization study showed
good agreement between the exposure rates derived
from in-situ gamma-ray spectrometry and those
measured with a pressurized ion chamber in all of the
locations surveyed. Variabilities of flux contributed
from radionuclides in the soil were small, with the
exception of 137Cs fallout, which was lower than
expected on all onsite locations. The 137Cs inventories
on cultivated lawns were the highest measured in this
study, but were within the range observed at other
locations with similar annual precipitation. Vertical
distributions of 137Cs in soil cores were found to be
extended, likely because of the large amount of
precipitation and the characteristics of the soil used
as backfill during cleanup and decommission
operations. No other manmade gamma-emitting
nuclides were detected in laboratory analyses of soils
or in spectra collected at any locations. A comparison
of the open-field pressurized ion chamber
measurements in this study showed no significant
difference in gamma-ray flux at onsite and offsite
locations.
12
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REFERENCES
1. A Guide for Environmental Radiological Sur-
veillance at U.S. Dept. of Energy Installations, July
1981, Office of Operational Safety Report, U.S.
DOE(DOE/EP-0023).
2. Beck, H. L. 1979. The natural radiation
background of Utah - Preliminary report on radio-
nuclides in soils in populated areas. New York: U.S.
Department of Energy, Environmental Measure-
ments Laboratory; EML-362.
3. Beck, H. L., J., De Campo, C. V., Gogolak.
1972. In Situ Ge(Li) and Nal(Tl) gamma-ray spec-
trometry. New York: U.S. Department of energy,
Environmental Measurements Laboratory; HASL-
258.
4. Federal Register, Vol. 41, title 40, Part 141,
July 9, 1976, National Interim Primary Drinking
Water Regulations.
5. Heifer, I. K., and K. M., Miller. 1988. Cali-
bration factors for Ge detectors used for field spec-
trometry. Health Physics 55:15-29.
6. Johns, F. 1979. Radiochemical and Analytical
Procedures for Analysis of Environmental Samples.
U.S. EPA, (EMSL-LV-0539-17-1979).
7. Lowder, W. M. and H. L., Beck. 1966. Cos-
mic-ray ionization in the lower atmosphere. J.
Geophys. Research 71:4661-4668.
8. Miller, K. M. and I. K., Heifer. 1985. In situ
measurements of 137Cs inventory in natural terrain.
In: Proceedings of the Health Physics Society mid-
year topical symposium; (6-10 January); Colorado
Springs, CO: Central Rocky Mountain chapter of the
Health Physics society; 1985:243-251.
9. Miller, K. M., J. L., Kuiper, and I. K., Heifer.
1990.137Cs fallout depth distributions in forest ver-
sus field sites: implications for external gamma dose
rates. J. Environ. Radioactivity 12:23-47.
10. Shleien, B. and M. Terpilak. 1984. The Health
Physics and Radiological Health Handbook. Nucleon
Lectern Associates.
11. Thome", D. J., C. F., Fontana, and C. F., Costa.
1990. Onsite and offsite environmental monitoring
report: radiation monitoring around Tatum Salt Dome,
Lamar county, Mississippi. Las Vegas, NV: U.S.
Environmental Protection Agency, Environmental
Monitoring systems Laboratory; EPA/600/4-91/005.
13
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Appendix 1
Abbreviations
cm centimeter = 1/100 meter = 0.39 inch
DOE U.S. Department of Energy 24IAm
EMSL-LV Environmental Monitoring Systems 3H
Laboratory - Las Vegas 3H+
EPA U.S. Environmental Protection Agency ^Co
FDA U.S. Food and Drug Administration 137Cs
HpGe High purity germanium detector ^Sr
keV kilo electron volts = thousand electron 238Pu
VOltS 239+240^
kT kiloton (TNT equivalent)
LTHMP Long-Term Hydrological Monitoring
Program HMH-1
L liter thru 16
m meter HM-L,
MDC minimum detectable concentration HM-L2
MeV mega electron volts = million electron HM-S
volts
mL milliliter = one thousandth of a liter HM-1
NIST National Institute of Science and
Technology HM-2a
ppb parts per billion
pCi/L picocuries per liter = 10~12 curies per HM-2b
liter = 1/1,000,000,000,000 curies
per liter HM-3
pCi/g picocuries per gram = 10'12 curies per
gram HT-2c, 4,5
PHS U.S. Public Health Service
SGZ surface ground zero
Americium-241
tritium
enriched tritium
cobalt-60
cesium-137
strontium-90
plutonium-238
plutonium-239 andplutonium-240 (in-
dividual isotope not distinguished in
analysis)
Hydrological Monitoring Hole
Hydrological Monitoring Well - Local
Aquifer
Hydrological Monitoring Well -
Surficial Aquifer
Hydrological Monitoring Well -
Aquifer 1
Hydrological Monitoring Well -
Aquifer 2a
Hydrological Monitoring Well -
Aquifer 2b
Hydrological Monitoring Well -
Aquifer 3
Hydrological Test Hole
14
-------
Appendix 2
Glossary of Terms
Background Radiation
The radiation in man's natural environment,
including cosmic rays and radiation from natural-
occurring radioactive elements, both outside and
inside the bodies of humans and animals. It is also
called natural radiation. The usually quoted average
individual exposure from background radiation is
125 millirem per year in mid-latitudes at sea level
(Shleien and Terpilak 1984).
Curie (Ci)
The basic unit used to describe the rate of
radioactive disintegration. The curie is equal to 37
billion disintegrations per second, which is ap-
proximately the rate of decay of 1 gram of radium;
named for Marie and Pierre Curie, who discovered
radium in 1898.
Isotope
One of two or more atoms with the same
number of protons, but different numbers of neutrons
in their nuclei. Thus 12C, 13C, and I4C are isotopes of
the element carbon, the numbers denoting the ap-
proximate atomic weights. Isotopes have very nearly
the same chemical properties, but often different
physical properties (for example 12C and 13C are
stable, I4C is radioactive).
Minimum Detectable Concentration (MDC)
The smallest amount of radioactivity that can
be reliably detected with a probability of Type I and
Type II errors at 5 percent each (DOE 1981).
Offsite
All areas exclusive of the Tatum Dome Test
Area.
Onsite
In this report refers to the area within the Tatum
Dome Test Area.
Shallow ground water
Water found near the soil surface, caused by
rain water saturation of the soil. This shallow ground
water is not an aquifer.
Surficial Aquifer
The ground-water layer located closest to the
surface, generally at a depth of approximately 30 feet
at SGZ.
Tritium
A radioactive isotope of hydrogen that decays
by beta emission. Its half-life is about 12.5 years.
Type I Error
The statistical error of accepting the presence
of radioactivity when none is present.
Type II Error
15
-------
APPENDIX 3
SUMMARY OF ANALYTICAL PROCEDURES
TYPE OF
ANALYSIS
ANALYTICAL
EQUIPMENT
COUNTING
PERIOD (MIN)
ANALYTICAL
PROCEDURES
SAMPLE
SIZE
APPROXIMATE
DETECTION LIMIT*
IG or Ge(Li)
Gamma
Spectrometryb
IG or GE(Li)
detector calibrated
at 0.5 keV/channel
(0.04 to 2 MeV
range) individual
detector efficiencies
ranging from 15%
to 35%.
Individual air
filters, 30 min; 100
min for milk, water,
sus-pended solids.
Radionuclide concen-
tration quantified from
gamma spectral data
by on-line computer
program. Radionu-
clides in air filter com-
posite samples are
identified only.
3.5 L for liquids
and vegetables.
Generally 5 pCi/L for
most common fallout
radionuclides in routine
milk and water samples
in a simple spectrum.
Low background
thin-window, gas-
flow, proportional
counter.
50 Chemical separation by
ion exchange. Separated
sample counted succes-
sively; activity calculated
by simul-taneous solution
of equations.
LOLformilkor
water; 0.1 to 1 kg
for tissue.
2pCi/L
3H
Automatic liquid
scintillation counter
with output printer.
300 Sample prepared by
distillation.
4 ml for water; 10
ml for urine; 50 g
for tissue.
300to700pCi/L
3H+
(Enrichment)
Automatic liquid
scintillation counter
with output printer.
300 Sample concentrated by
electrolysis followed by
distillation.
250 ml for water. 10 pCi/L
238,239+240pu /^ha spectrometer
with silicon surface
barrier detectors
operated in vacuum
chambers.
1000 to 4000
Water sample or acid-
digested filter or tissue
samples separated by ion
exchange, electroplated
on
stainless steel
planchet.
1.0L for water; 0.1
to1 kg for tissue.
In water samples
0.08 pCi/L for ^Pu, and
0.05 pCi/L for 239*240Pu.
For tissue samples, 0.05
pCi per total sample for all
isotopes.
The detection limit is defined as the smallest amount of radioactivity that can be reliably detected, i.e., probability of Type I and
Type II error at 5% each.
Gamma spectrometry using either an intrinsic germanium (IG), or lithium-drifted germanium diode (Ge(Li)) detector.
16
-------
APPENDIX 4
RESULTS FOR WATER SAMPLES COLLECTED IN APRIL, 1991
SAMPLE
LOCATION
COLLECTION
DATE 1991
CONCENTRATION ± 2 S.D. IN pCI/L
(MINIMUM DETECTABLE CONCENTRATION [MDC])
"°Sr
2MPu
Anderson, Billy Ray 04/22
Anderson Pond 04/22
Anderson, Regina 04/22
Anderson, Robert Harvey 04/22
Anderson, Robert Lowell 04/22
04/22
Burge, Joe 04/22
Chambliss, B. 04/23
Daniels, Webster, Jr. 04/22
Daniels - Well #2 04/22
Half Moon Creek
Half Moon Creek Overflow
Hudson Quail House
Jr. Green Creek
Kelly Gertrude
King, Rhonda
04/21
04/22
04/21
04/22
04/23
04/23
04/22
04/22
Baxterville, MS
19±5*
(7.7)
13 ±6*
(9.8)
18±6*
(10)
16 ±5*
(7.4)
14+5*
(7.5)
26 ±6*
(9.9)
18 ±7*
(11)
-4 ±5.5
(9.1)
14±6*
(10)
24 ±5*
(7.1)
19 ±5*
(8.3)
31 ±7*
(10)
120 ±7*
(8.9)
280 ±8*
(10)
48 ±8*
(12)
Not Sampled - Could not locate sampling point
-3.6 ±4.4
(7.3)
20 ±6*
(10)
(Continued)
17
-------
APPENDIX 4 Continued
RESULTS FOR WATER
SAMPLES COLLECTED IN APRIL, 1991
SAMPLE COLLECTION
LOCATION DATE 1991
Lee.P.T.
i
Little Creek #1
Lowe, M.
Lower Little Creek #2
Mills, A. C.
Mills, Roy
Nobles Pond
Noble, W.H., Jr.
Pond West of GZ
Ready, R. C.
REECo Pit Drainage-A
REECo Pit Drainage-B
REECo Pit Drainage-C
Salt Dome Hunting Club
Salt Dome Timber Co.
Saucier, Dennis
04/22
04/23
04/23
04/23
04/22
04/22
04/22
04/22
04/21
04/22
04/22
04/24
04/24
04/24
04/24
04/22
04/22
CONCENTRATION ± 2 S.D. IN pCI/L
(MINIMUM DETECTABLE CONCENTRATION [MDC])
3H 3H+ MSr ""Pu *wMopu
Baxterville,MS(Cont.)
44±6*
(9.1)
21 ±7*
(12)
Not sampled - On City Water
20 ±6*
(9.8)
0.50 ±4.6
(7.5)
20 ±5*
(7.3)
21 ±7*
(11)
36 ±7*
(11)
8.9 ±5.8
(9.4)
9.9 ±7.6
(12)
37 ±5*
(7.4)
20 ±6*
(9.8)
240 ±11*
(15)
290+8*
(10)
33 ±8*
(13)
26 ±6*
(9.4)
40 ±6*
(9.9)
(Continued)
18
-------
APPENDIX 4 Continued
RESULTS FOR WATER
SAMPLES
COLLECTED IN APRIL, 1991
CONCENTRATION ± 2 S.D. IN pCI/L
(MINIMUM DETECTABLE CONCENTRATION [MDC])
SAMPLE COLLECTION
LOCATION DATE 1991 3H 3H+ *>Sr ""Pu 2~»s«pu
Saucier, Talmadge S.
Saucier, Wilma & Yancy
Smith, Rita
Well Ascot 2
Well City
Well E-7
Well HM-1
Well HM-2A
Well HM-2B
Well HM-3
Well HM-L
04/23
04/23
04/22
04/23
04/23
04/23
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
Baxterville, MS(Cont.)
28 ±6*
(9.2)
1.1 ±6.7
(11)
Not Sampled - No One Home
Not Sampled - No Access
33 ±6*
(9.7)
8.5 ±6
(9.7)
1.9 ±5.4
(8.9)
0 + 5
(8.3)
-2.9 ±5.2
(8.6)
-2.8 ±5.7
(9.4)
-0.63 ±6.67
(11)
-1.2 + 5
(8.3)
-0.1 9 ±5.93
(9.8)
-4.1 ±5.4
(8-9)
2±5
(8.1)
-0.19 ±6.18
(10)
-2.5 ±7
(12)
1300 ±280*
(450)
890 ±280*
(450)
850 ±13*
(12)
(Continued)
19
-------
APPENDIX 4 Continued
RESULTS FOR WATER SAMPLES COLLECTED IN APRIL, 1991
SAMPLE
LOCATION
COLLECTION
DATE 1991 >H
CONCENTRATION ± 2 S.D. IN pCI/L
(MINIMUM DETECTABLE CONCENTRATION [MDC])
"°Sr
Baxterville,MS(Cont.)
Well HM-L2
i
Well HM-S
Well HMH-1
Well HMH-2
Well HMH-3
Well HMH4
Well HMH-5
WellHMH-6
Well HMH-7
Well HMH-8
04/22
04/22
04/21
04/23
04/23
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
7500 ±340*
(450)
7600 ±340*
(450)
7400 ±340*
(450)
5000 ±320*
(450)
14,000 ±390*
(450)
7200+340*
(450)
14,000 ±400*
(450)
_
2200 ±290*
(450)
2700 ±300*
(450)
0.91 ±5.76
(9.5)
-3.4 ±7.2
(12)
41 ±7*
(11)
44 ±5*
(8.2)
18±6*
(10)
14 + 6*
(8.8)
210 ±8*
(10)
170 ±7*
(8.7)
Not Sampled - Under Water
16 ±6*
(10)
22 ±5*
(8)
20
-------
APPENDIX
4 Continued
RESULTS FOR WATER SAMPLES
COLLECTED IN APRIL, 1991
CONCENTRATION ± 2 S.D. IN pCI/L
(MINIMUM DETECTABLE CONCENTRATION [MDC])
SAMPLE
LOCATION
Well HMH-9
Well HMH-10
WellHMH-11
WellHMH-12
Well HMH-13
Well HMH-14
Well HMH-15
WellHMH-16
Well HT-2C
Well HT-4
Well HT-5
COLLECTION
DATE 1991 3H 3H+ "Sr
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/23
04/23
04/23
Baxterville,MS,(Cont.)
130 ±8*
(11)
150 ±7*
(9.4)
91 ±8*
(11)
35 ±7*
(10)
22 ±5*
(7.5)
21 ±7*
(11)
16 ±6*
(10)
17 ±5*
(8.2)
18±6*
(10)
19±7*
(11)
16 ±6*
(8.9)
11 ±6*
(10)
18 ±6*
(10)
8.9 ±5*
(8.2)
31 ±6*
(8.8)
38 ±6*
(8.6)
18 ±7*
(12)
7.6 ±6
(9.8)
4.216.5
(11)
2MB it 23ft+240B|]
(Continued)
21
-------
APPENDIX 4 Continued
RESULTS FOR WATER
SAMPLES COLLECTED
IN APRIL, 1991
CONCENTRATION ± 2 S.D. IN pCI/L
(MINIMUM DETECTABLE CONCENTRATION [MDC])
SAMPLE COLLECTION
LOCATION DATE 1991 3H
Dennis, Buddy
Dennis, Marvin
Well 64B City
Anderson, G. W.
Anderson, Lee L.
Beach, Donald
Bond, Bradley K.
Cox, Eddie
Daniels, Ray
Gil Ray's Crawfish Pond
Gipson, Herman
Graham, Sylvester
Moree, Rita - House Well
Powell, Shannon
Rushing, Debra
Saul, Lee L.
04/23
04/23
04/23
04/22
04/22
04/22
04/22
04/24
04/22
04/23
04/22
04/23
04/23
04/22
04/24
04/23
3H+
Columbia, MS
14 ±4*
(6.7)
26 ±6*
(8.7)
17 ±6*
(10)
Lumberton, MS
27 ±5*
(8.2)
26 ±7*
(11)
28 ±6*
(9.3)
36 ±7*
(11)
27 ±5*
(7.7)
13 ±5*
(8.6)
21 ±5*
(7.3)
-2.616.7
(11)
4.8 ±4.5
(7.4)
18 ±6*
(9.5)
34 ±7*
(10)
-1.3 ±6.5
(11)
•°Sr ^Pu
0.21 ±0.63 0.0048± 0.0096
(1.4)
0.36 ±0.61 0± 0.0094
(1.4)
0.27 ±0.60 -0.0027± 0.0121
(1.4)
No sample - residents moved,
-0.088 ± 0.71 3 -0.0039± 0.0079
(1.5)
0.077 ±0.573 0± 0.0066
(1.3)
0.51 ±0.60 0± 0.0065
(1-3)
0.93 ±0.63 0.01 6 ±0.032
(1.4)
231*240pu
0± 0.0068
0± 0.0094
0.0054 ±0.01 08
well down
-0.0020 ±0.0039
0± 0.0066
0.0068 ±0.01 21
-0.0080 ±0.01 60
(Continued)
22
-------
APPENDIX 4 Continued
RESULTS FOR WATER SAMPLES COLLECTED IN APRIL, 1991
SAMPLE COLLECTION
LOCATION DATE 1991
Smith, Howard 04/23
Smith, Howard - Pond 04/23
Well 2 City 04/23
Burge, Willie Ray & Graco 04/22
City Supply 04/22
Gil, Ray -House Well 04/22
CONCENTRATION ± 2 S.D. IN pCI/L
(MINIMUM DETECTABLE CONCENTRATION [MDC]}
3H ^ .«* ^ _pu
Lumberton, MS, (Cont.)
0.073 ±4.598
(7-6)
18 ±5* 0.44 ±0.59 0 ±0.011 0.0075 ±0.0151
(7.7) (1.4)
4.7 ±5.9
(9.6)
Purvis, MS
15 ±5*
(7.7)
6.4+5.8
(9.4)
2.6+6.2
(10)
* Concentration is greater than the minimum detectable concentration (MDC). Where gamma spectral analysis was performed, only
collection dates are shown.
23
-------
APPENDIX 5
EXPOSURE RATE INVENTORIES AT ALL SURVEY LOCATIONS (Other pic readings taken near the location
are also given.) A discussion of uncertainties is given in the following section.
COSMIC WK
ONSITE
(1 ) Surface Ground Zero (12m
northwest of monument)
(2) Postshot No. 1 Slush Pit
(3) WellHT-2
(4) WellHT-2M
(5) Decontamination Pad (20 m
north of beaver pond)
(6) REECoPitA
(7) REECoPitB
(8) REECoPitC
OFFsrre
(9) B. R. Anderson Residence
(lawn 30 m west of house)
(1 0) Purvis Elementary School
(lawn 100 m southwest of
school)
(11) Purvis High School
(lawn 150 m north of school)
(1 2) Hattiesburg Fire Station
#4 Lot
(13) Hattiesburg Hotel Room
3.6
3.6
3.6
3.6
3.6
3.6
3.6
3.6
3.7
3.7
3.7
3.6
3.6
0.2
0.4
0.3
0.6
0.2
0.4
0.5
0.4
0.5
0.3
0.4
0.2
1.0
Th
0.9
1.6
1.2
1.5
0.9
1.5
1.7
1.5
1.3
0.9
1.1
0.8
1.8
U
1.1
1.0
0.8
1.1
0.8
1.0
1.1
0.9
1.4
0.9
0.9
0.9
1.6
EXPOSURE RATE friR/HR)
Rn "Be 1"Cs TOTAL
0.1
0.1
0.1
0.1
0.1
0.1
0.1
0.1
0.1
0.1
0.1
0.1
—
„
0.01
0.01
0.01
0.01
._
0.01
0.01
0.01
0.01
0.01
0.01
—
0.02*
0.02
0.03
0.06
0.01*
0.03
0.01
0.02
0.1
0.2
0.1
0.1*
™
5.9
6.7
6.0
7.0
5.6
6.6
7.0
6.5
7.1
6.1
6.3
5.7
8.0
PIC
6.0
7.0
6.9
7.2
7.0
6.5
6.7
6.7
8.0
6.7
6.4
6.4
6.6
OTHER
PIC READING
6.2,
7.2,
6.4,
6.8,
7.1,
7.2,
6.6,
7.0,
7.0,
6.8,
6.3,
6.0,
5.9, 6.1
6.5, 6.1
6.8, 6.4
7.5, 6.8
6.0, 6.4
7.3, 6.8
6.0, 6.4
6.6, 6.9
6.7, 7.2
6.4, 6.8
6.7, 6.5
6.5, 6.3
*—•
'Assuming <*/p = 0.5 (no cores taken)
24
-------
APPENDIX 6
SOIL SAMPLE STUDY
IN-SITU SPECTROMETRY
«/p" (mCi/km2) MDC
ONSITE
(1) Surface Ground Zero (12m
northwest of monument) 0.05a 10.611.5 (5.2)
(2) Post Shot No. 1. Slush Pit 0.081b 7.311.0 (5.4)
(15m east of monument)
(3) WellHT-2 0.13 7.811.7 (3.8)
(4) WellHT-2M 0.060 25.213.5 (7.7)
(5) Decontamination Pad 0.05a 6.512.1 (4.1)
(6) REECoPitA 0.17 7.911.7 (3.7)
(7) REECoPitB 0.10 4.710.2 (4.7)
(8) REECoPitC 0.032° 15.514.2 (10.7)
OFFSITE
(9) B.R. Anderson Residence 0.065 42.613.7 (7.3)
(10) Purvis Elementary School 0.068 89.113.5 (7.8)
(11) Purvis High School 0.052 56.814.6 (8.4)
(12) Hattiesburg Fire Station #4 Lot 0.05a 4.412.2 (5.8)
'Estimated value.
''Derived from result of combined six core samples.
c Derived from result of one core sample (all others derived from combined three core samples).
"x/p = x Corresponds to surficial deposition, <*/p = 0 corresponds to uniform distribution
25
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