United States Office of Radiation and EPA-402-R-01-012
Environmental Protection Indoor Air November 2001
Agency Washington, DC 20460
Annual Water Sampling
and Analysis at the
Salmon Test Site Area,
Lamar County, Mississippi
April 2001
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Annual Water Sampling and Analysis
at the Salmon Test Site Area
Lamar County, Mississippi
April 2001
by
Max G. Davis
"-
<:>
Radiation and Indoor Environments National Laboratory
Office of Radiation and Indoor Air
u.s. Environmental Protection Agency
P.O. Box 98517
Las Vegas, NV 89193-8517
""-
'-
Prepared for the U.S. Department of Energy
under Interagency Agreement
DE-AI08-96NV11969
t'-.
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'-
'-
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RADIATION AND INDOOR ENVIRONMENTS NATIONAL LABORATORY
U.S. ENVIRONMENTAL PROTECTION AGENCY
LAS VEGAS, NV 89193-8517
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NOTICE
The infonnation in this document has been funded wholly or in part by the United States
Environmental Protection Agency (EP A) through Interagency Agreement (lAG) DE-AI 08-
96NVl1969 from the United States Department of Energy (DOE). It has been subjected 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.
11
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ABSTRACT
In 1964 and 1966, nuclear explosives were detonated approximately 2,700 feet (823 m)
underground in the Salmon Test Site Area located in Lamar County, Mississippi. Drilling and
clean-up activities have resulted in tritium contamination in close proximity to the surface
ground zero. The Long-Term Hydrological Monitoring Program (LTHMP), directed by the EPA,
conducts annual water sampling on and around the Salmon Test Site Area and monitors
radiological sampling equipment on the site throughout the year.
In this report the 2001 annual water sampling at the Salmon Site is described, and the
analytical results of the collected samples are given. The highest tritium concentration on site
was 2.67 x 104 pCi/L in water from one of the new wells added in 1997, see Appendix B, page
16. No radioactivity attributable to the test site was found in any offsite water sample. The
highest tritium concentration offsite was 9.8 :t 3.4 pCiIL at the Bill Ray Anderson residence.
All samples, with the exception ofHMH-1 through HMH-16 and the 15 new wells added
in 1998 (see Appendix B), were analyzed for the presence of gamma-ray emitting radionuclides.
None were detected above the minimum detectable concentration (MDC).
111
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This page is left blank intentionally.
IV
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CONTENTS
Page
Notice. . . . . . . . . . . . . . . . . .
Abstract
Figures. . . . . . . . . .
Acronyms and Abbreviations. . . . . . . . . . . . . .
Acknowledgments. . . . . . . . . . . . . . . . . . . . . . . . . .
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.. . . . . . . . .
Introduction. . . . . . . . .
History. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Historical Monitoring Results. . . . . . .
Sampling Collection. . . . . . . . . . . . . . . . . . . . . . . . . .
Sample Analysis
Water Analysis Results
Conclusions. . . . . . . . . . . . . . .
References. . . . . . . .
Glossary of Terms. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
. . . . . . . . . .
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V111
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Appendices
A. Summary of Analytical Procedures. . . . . . . . . . . . . . . . . . .
B. Tritium Results for Water Samples Collected in April 2001
V
. . . . .. . . . . .
. . . . . . . . . . . . . . . . . . . . . . 15
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FIGURES
Figure Number
1
2
3
4
5
6
7
8
9
10
Page
General site location of Project Salmon Test Site Area. . . . . . . . . . . . . . . . . . . . . . . .. . .2
Topographic map of the Salmon Test Site Area showing the Surface
Ground Zero and outline of Test Area at 2,700 feet below land surface. . . . . . . . . . . . . . 3
Test cavity and aquifers. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Tritium concentration vs. sampling year for HMH-l (depth = 10 ft) ................ 5
Tritium concentration vs. sampling year for HMH-2 (depth = 10 ft) ................5
Tritium concentration vs. sampling year for HMH-5 (depth = 10 ft) ................6
Tritium concentration vs. sampling year for HM-S (depth = 30 ft) . . . . . . . . . . . . . . . . . .6
Tritium concentration vs. sampling year for HM-L (depth = 200 ft) . . . . . . . . . . . . . . . . .7
Locations on the Salmon Test Site Area sampled in 2001 ........................8
Offsite locations sampled in 2001 ........................................... 9
VI
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DCG
DOE
EPA
g
HpGe
IAG
keV
kg
kt
L
LTHMP
m
MDC
MeV
mIll
mL
ORIA
pCi/L
PHS
R&IE
SGZ
USGS
3H
3H+
HMH
HM-L, HM-L2
HM-S
HM-1
HM-2a
HM-2b
HM-3
HT -2c
HT-4
HT-5
REECo
SA Wells
ACRONYMS AND ABBREVIATIONS
Derived Concentration Guide
U.S. Department of Energy
U. S. Environmental Protection Agency
gram
high purity germanium gamma detector
Interagency Agreement
kilo electron volts = thousand electron volts
kilogram, 1000 grams
kiloton (TNT equivalent)
liter
Long Term Hydrological Monitoring Program
meter
minimum detectable concentration
one million electron volts
minute
milliliter = one thousandth of a liter
Office of Radiation and Indoor Air
picocuries per liter = 10-12 curies per liter = 1/1 ,000,000,000,000 curies per
liter
U.S. Public Health Service
Radiation and Indoor Environments National Laboratory
surface ground zero
U.S. Geological Survey
Tritium
Enriched Tritium
Hydrological Monitoring Hole (1-16)
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
Hydrological Test Hole
Hydrological Test Hole
Reynolds Electrical & Engineering Co
Source Area Wells
Vll
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ACKNOWLEDGMENTS
External peer review was provided by Vernon Hodges, PhD, Chemistry, University Nevada Las
Vegas. In addition, the author would like to acknowledge Ken Giles, Dennis Farmer, Richard
Flotard, Pat Honsa, Rose Houston, and the staff of the Hydrological Monitoring Group, EP A, for
their dedication to quality and their tireless work in the execution of the sampling effort. The
author would also like to thank Terry Mouck for her outstanding support in preparing the
graphics and for providing the desktop publishing in the production of this report.
Vlll
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INTRODUCTION
Under an Interagency Agreement (lAG) with
the DOE, the EP A's Radiation and Indoor
Environments National Laboratory (R&IE)
located in Las Vegas, NV, conducts sampling
to measure radioactivity in water sources near
the sites of underground nuclear explosions.
The results provide assurance that radioactive
materials from the tests have not migrated into
drinking water supplies. This report presents
the results for samples collected under EP A's
L THMP in April 2001, on and around the
Salmon Test Site Area, Lamar County,
Mississippi.
History
Project Dribble, consisting of two nuclear
explosions, and Project Miracle Play,
consisting of two non-nuclear gas explosions,
were conducted in the Salmon Test Site Area,
near Baxterville, Lamar County, Mississippi,
between 1964 and 1970. The general area is
depicted in Figure 1. The Salmon Test Site
Area (Figure 2) contains approximately 1,470
acres located in Sections 11, 12, 13, and 14,
Township 2 North, Range 16 West.
Test Date Name Type Yield
(kt)
10- 22-64 Salmon Nuclear 5.3
12-03-66 Sterling Nuclear 0.38
02-02-69 Diode Tube Gas 0.32
04-19-70 Humid Water Gas 0.32
These tests were part of the Vela Uniform
Program of the U.S. Atomic Energy
Commission (a predecessor agency of the
DOE). The purpose was to measure and
evaluate 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 salt dome underlying the test
area. The top of the cavity is 1,160 feet (360
m) below the top of the salt dome which lies
1,500 feet (460 m) below the land surface
(Figure 3). The Salmon detonation cavity was
subsequently used to contain the next three
explosions.
Following each detonation, the surrounding
area was closely monitored by the U.S. Public
Health Service (PHS). Radiological
monitoring became the responsibility of the
EP A at its inception in 1970, and after the
second site cleanup operation in 1971-72, the
LTHMP was instituted. In this program, all
potable aquifers, several wells, public water
supplies, and some surface waters in the
vicinity of the Salmon Test Site are sampled
and analyzed to determine the presence of
tritium and other radioactive contaminants.
Historical Monitoring Results
The disposal of drilling mud and fluids near
the surface ground zero (SGZ) is responsible
for tritium eH) contamination of the soil zone
and underlying shallow aquifer. These waters
lie at depths of 4 to 10 feet (1.3 to 3 m) and 30
feet (9 m), respectively, and are not potable.
Tritium contamination is also present in the
potable water of the local aquifer which lies at
about 200 feet (62 m). The observed 3H
concentration in the local aquifer is well
below the 20,000 pCiIL guideline specified in
the National Primary Drinking Water
Regulations (40CFRI41), and is thought to be
1
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. Bassfield
Oakvale.
Bunker Sumrall .
Hill
. Improve
. Oloh
98
Sartinville .
MISSISSIPPI
--------------------
LOUISIANA
- Major Highway
EB Test Site, SGZ
~
MILES
~
LAMAR
COUNTY
Figure 1 General site location of Project Salmon Test Site Area.
2
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Wells with significant tritium contamination
are found within this circle with a radius
of 1400 feet (430 m)
SALMON TEST SITE AREA
BOUNDARY
x
e
c-
o.
CtS
approx. 1 1/2 miles
CJ)
Q)
E
~
T"""
,-
~
N
SCALE IN FEET
1000 2000 3000
4000
5000
o
I
I
o
500 1000
SCALE IN METERS
Figure 2 Topographic map of the Salmon Test Site Area showing the Surface Ground Zero and
outline of Test Area at 2,700 feet below land surface.
3
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CITRONELLE
AQUIFER
HALF MOON CREEK
ALLUVIAL AQUIFER
WELL
HT-2
I
... .
.. .
.:; ::: ::::;,' ;::.;,:::::::;::::::::;:::::.:-:.;:::::::;:::.:: :::
TEST CAVITY
SALT DOME.
.. .
. . .. .. .. .. .. .. .. ~ .. .. .. .. . .. ..
............... ............
. .... ...........
GROUND
SURFACE
:;;;;,,;:,;,::;;:,;,:;::,i:i:i::'::;:::i:::i,:::':;:::::::::.:.::::;:::::;:,;:::: LOCAL AQUIFER
~-:.:.:.:..-:.:. . -:. . AQUIFER 1
[[[j,!:!: AQUIFER 2A
[[[i::::::::::::::;::: AQUIFER 28
AQUIFER 3A
AQUIFER 38
AQUIFER 4
AQUIFER 5
FLUID LEVEL
HIGHLY
RADIOACTIVE
MATERIAL
III LIMESTONE
EJ SANDSTONE
RECRYSTALLIZED
MELT PUDDLE
*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.
Figure 3 Test cavity and aquifers.
due to drilling activities at the site (Fenske and
Humphrey, 1980;. Fordham and Fenske, 1985).
Of the 55 wells sampled on the Salmon Site,
five regularly have tritium values above those
expected in surface water values. These include
three soil zone wells near the SGZ (wells
HMH-l, HMH-2, and HMH-5), well HM-S in
the shallow aquifer, and well HM-L in the
underlying local aquifer. Plots of tritium
concentration vs. time for these wells are shown
in Figures 4 to 8. The solid line in the graph
represents the normal radioactive decay of
tritium. Surface water collected from the Half
-------
;J'"
(5 -g 50
Co co
~'"
C") 5 40
'.c
II-
90
+
80
70
+ Measured
-....... Predicted by H-3 decay
60
+
+
30
20
+
+--T--+---:'---_':_-------_._._~----~--~--_.- ~-------_._------- -----
10
o
~~~~~~~~~~~~~~~~*~~~~~
Calendar Year
Figure 4 Tritium concentration vs. sampling year for HMH-l (depth = 10 ft).
~ '"
...J 1:1
;:" c:
'd. ~ 20
~ '"
t') 0
, .c:
J: I-
40
+
+ Measured
. Predicted by H-3 decay
30
+""',
',,-
'''-,
",
+"~~"':-~,~~~,,~--.~~
+
10
+
+
+
o
~~~~~~~~*~~~~~~~~~~~~~
Calendar Year
Figure 5 Tritium concentration vs. sampling year for HMH-2 (depth = 10 ft).
5
-------
12
10
8
:J (J)
-- "t:>
.- c:
() 11I 6
.9: (J)
::>
C') 0
.<:
r. I-
4
2
+
+ Measured
- Predicted by H-3 decay
+.
-'t-----~~~------~~-:---+--!_~~-~
+
+
+
+
+ +
+ +
+
+
o
~~~~~~~~~~~~~~~~~~~~~~
Calendar Year
Figure 6 Tritium concentration vs. sampling year for HMH-5 (depth = 10 ft).
40
30
T,
",
"
",
"
''''''''''~
..,..,............
+ + + + +-~'------'------------------------~--
+ + + +
+ Measured
'__"H Predicted by H-3 decay
+
:J'~
:::, c:
() 11I
.9: gj 20
C') 0
r. ~
10
o
+ +
+
~~~~~~~~~*~~~~~*~~~~~~
Calendar Year
Figure 7 Tritium concentration vs. sampling year for HM-S (depth = 30 ft).
6
-------
3000
X
2500
2000 X
;;! X
(3 1500 X
.s
C") x x
:t x
1000
500
0
;, Measured
- Predicted by H-3 decay
x
x
x
x
x
~~~~~~~~~#~~~~~~~~~~~~
Calendar Year
Figure 8 Tritium concentration vs. sampling year for HM-L (depth = 200 ft).
Sample Collection
According to standard operating procedures
agreed to by DOE (U.S. DOE 1981), the
HMH wells on the test site were first sampled,
pumped-dry, and sampled on the following
day as were the 15 new wells added in 1997.
The 15 new wells added in 1998 were purged
of three volumes of water and then sampled.
Wells HM-1, HM-2A, HM-2B, HM-3, and
HM-L, which lie adjacent to SGZ, were first
sampled and then pumped steadily while
further samples were taken at 30 min
intervals until the pH and conductivity of the
water stabilized. A final sample was taken
from each well 30 min after stability was
reached. Water samples were taken from
sources near the SGZ area (i.e., Half Moon
Creek, Half Moon Creek Overflow, and the
Pond west of SGZ) before and after the
pumping operations to identify any resulting
changes in tritium concentration. Well HM - L2
was first sampled and then pumped for one
hour before a second sample was taken. All
other water supplies were sampled only once.
F or wells with operating pumps, the samples
were collected at the nearest convenient outlet.
If the well has no pump, a truck-mounted
sampling unit was used. With this unit it is
possible to collect three-liter samples from
wells as deep as 1800 meters (5,900 ft.). The
pH, conductivity, water temperature, and sam-
pling depth was measured and recorded as
each sample was collected. Disposal of water
from wells HM-3, SA-1-1H, and SA1-7H,
were contained in a Frac Tank. The water was
then transported to the Columbia Waste Water
Plant for disposal.
7
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HMH-1S.
Decontamination
Pad
. SA2-4-L . SA2-3-L
.SA2-5-L S~;'~~~.
REECe Pit ~ 1 [".
REECe Pit B
. REECo Pit A ad
Sri ~o
HMH-14 HMH-13 age p.cG8SS
HMH-12 ~.
'\ Half Moon
HMH-5. . Creek
.
-\
./ /,"
/' '" ",
/" ,
/'./. """----"
/' '" /' SA1-1-H " ~
/' ,~
/' /' HMH-10 .\~
/' /' Half Moon 8 'b
/' ~~k~e~ow \~
\~
\~
HM-2~ .SA1-2-H "
HM-3 MH-1 ~
HM-L HM-2B 8SA1-3-H /
HM-S. . HMH-11 '
HM-1 8 HMH-2 . HMH-9 (
\
,
,
)
,
I
,
,
\
\
,
.
\
.SA 1-8-L . SA 1-9-2A
.SA1-10-2b. SA1-11
~ Well HM-L2
sc!:.... SA4-1-M
8 HMH-8
HMH-7 .
SA3-4-H .
- SA3-5-H .
.
,
. SA3-8-1
. SA3-11-3
. SA3-10-2
I
N
.SA5-4-4 .
S 5-3-M SA5-2-M
8 Well HT-2C
. SA5-5-4
This map Is not to scale
Scale In Feet
o 1000 2000 MI
~
o 100 200 300 400 500
Scale In Meters
lAMAR
COUNTY
o Surface Ground Zero
. Water Sampling Locations
. Wells Added in 1998
Figure 9 Locations on the Salmon Test Site Area sampled in 2001.
8
-------
James Lowe
Res
.
. RicK Kiffee
Roswell
Thomp
James Lowe.
Pond
. Columbia City Little Creek #1
46-003-5
Lower Little Creek #2
. Surface Ground Zero
. Water Sampling Locations
4
Scale in Miles
o 1 2 3
~
o
234
Scale in Kilometers
Figure 10. Offsite locations sampled in 2001
9
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The locations of all sampling sites are shown
in Figures 9 10. Sampling also included
three locations in Columbia, Mississippi (not
shown). The sampling results are discussed in
the following sections.
Sample Analysis
Radiochemical procedures used to analyze the
samples collected for this report are described
in Johns et al. (1979) and summarized in
Appendix A. These include standard methods
to identify natural and man-made gamma-
emitting radionuclides, tritium, plutonium,
strontium, and uranium in water samples.
Two types of tritium analyses were
performed: conventional and electrolytic
enrichment. The enrichment method lowers
the minimum detectable concentration (MDC)
from approximately 300 pCi/L to about 5
pCiIL. An upper limit of activity of 700 - 800
pCiIL has been established for the tritium
enrichment method because sample cross-
contamination becomes a problem at higher
levels.
In late 1995, it was decided that a maximum
of 25 percent of all samples collected would
be analyzed by the low-level enrichment
method. This decision was based on the time
required for analysis, budgetary constraints,
and an assessment of past results. Under the
current sampling and analysis protocol for the
site, all samples are initially screened for
tritium activity by the conventional method
and selected samples enriched. At this time,
only sampling locations that are in position to
show migration are selected for enrichment.
Sufficient sample is collected from new
sampling locations to perform all routine
analyses and a full-suite of other radio-
chemical determinations including assays for
strontium-90, plutonium, and uranium.
Water Analysis Results
Gamma-ray spectral analysis results indicated
that no man-made gamma-emitting
radionuclides were detected in any onsite or
offsite samples. Tritium concentrations above
normal background values were not detected
in any offsite samples. Long-term decreasing
trends in tritium concentrations are evident for
onsite locations that have shown detectable
tritium activity since monitoring began under
theLTHMP (wells HMH-l, HMH-2, HMH-5,
HM-S, and HM-L, depicted in Figures 4 thru
8).
Only three wells were above the MDC in the
samples collected from the offsite sampling
locations. Tritium activity in the offsite
samples ranged from less than the MDC to 9.8
pCiIL (- 0.5 Bq/L), 0.05 percent of the DCG.
These results do not exceed the natural tritium
activity expected in rain water in this area. .
Due to the high rainfall in the area, the
sampling procedure for selected onsite wells
is modified as follows: after collection of an
initial sample, the well is purged, and a second
sample taken after the well refills. The second
sample is representative of water that has
infiltrated through the soil zone, whereas the
first sample may represent a mixture of direct
rainwater influx at top of the well and
infiltrated or soil zone water.
In April 200 1, a total of 21 sampling locations
onsite were not sampled by order of DOE
reducing the number of location onsite from
61 to 40. Of the 40 locations sampled onsite,
33 sites were sampled twice (pre-and post-
sampling), 25 yielded tritium activities greater
10
-------
than the MDC in either the first or second
sample. Of these, 9 yielded results higher than
normal background (approximately 25 40
pCi/L [1 - 1.5 BqIL]) as shown in Appendix
B. The locations where the highest tritium
activities were measured generally correspond
to areas of known contamination.
In 1997, an additional 15 shallow wells were
added to the annual sampling, which range in
depth of 195' to 2100', increasing the total
sampling locations onsite to 61. Five of the
previous locations regularly have tritium
values above those expected in surface water
samples; of the 15 new wells, tritium values
were all below the MDC. The water in these
wells is not accessible to the public, nor
suitable for drinking due to its brackishness.
No radioactive materials from the Salmon
Test Site Area were detected in any water
samples collected offsite. The tritium
concentrations of water samples collected
onsite and offsite are consistent with those of
past studies at the Salmon Site. The highest
tritium concentration found in water collected
in the offsite area was 9.8 :t 3.4 pCiIL, which
is typical of background tritium levels, and is
0.059 percent of the National Interim Primary
Drinking Water Regulations (40CFR141).
The highest tritium concentration found onsite
was 26,700 pCi/L. This was detected in a
water sample collected from Well SA1-1H
which is a shallow well (40') near SGZ. The
water from this well is not available to the
public nor is it potable.
The tritium concentrations, except for Well
SA1-1H, were all well below the 20,000
pCiIL level defined in the EP A Drinking
Water Regulations (40CFR 141).
All samples were analyzed for presence of
gamma-ray emitting radionuc1ides with the
exception of HMH-1 though HMH-16. None
was detected above the MDC (see Appendix
B on page 16).
11
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REFERENCES
Code of Federal Regulations, Vol. 41, title 40,
Part 141, July 9, 1976, National Interim
Primary Drinking Water Regulations.
A Guide for Environmental Radiological
Surveillance at u.S. Dept. of Energy
Installations, July 1981 ,Office of Operational
Safety Report. Las Vegas, NV:
U.S. Department of Energy; DOE/EP-0023.
Fenske, P. R.; Humphrey, T. M., Jr. The
Tatum Dome Project Lamar County,
Mississippi. Las Vegas, NV: U.S. Department
of Energy, Nevada Operations
Office; NVO-225; 1980.
Fordham, J. W. Fenske, P. R. Tatum Dome
Field Study Report and Monitoring Data
Analysis, Las Vegas, NV: U.S. Department of
Energy, Nevada Operations Office;
DOEINV/l0384-03; 1985.
Johns, F., et al. 1979. Radiochemical and
Analytical Procedures for Analysis of
Environmental Samples. Las Vegas, NY:
U.S. Environmental Protection Agency;
EMSL-L V -0539-17 -1979.
12
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GLOSSARY OF TERMS
Background Radiation
The radiation in man's environment, including
cosmic rays and radiation from naturally-
occurring and man-made radioactive elements,
both outside and inside the bodies of humans
and animals. The usually quoted average
individual exposure from background
radiation is 125 millirem per year in mid-
latitudes at sea level (Shein & Terplak, 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 the equivalent of 1 gram of radium. Named
for Marie and Pierre Curie who discovered
radium in 1898. One microcurie (pCi) is one
millionth of a Ci.
Isotope
Atoms of the same element with different
numbers of neutrons in the nuclei. Thus 12C,
BC, and 14C are isotopes of the element
carbon, the numbers denoting the approximate
atomic weights. Isotopes have very nearly the
same chemical properties, but often different
physical properties (for example 12 C and 13 C
are stable, 14 C is radioactive).
Enrichment Method
A method of electrolytic concentration that
increases the sensitivity of the analysis of
tritium in water. This method is used by R&IE
in selected samples if the tritium concentration
is less than 700 pCi/L.
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
Areas exclusive of the immediate Salmon Test
Site Area.
Onsite
Refers to the immediate vicinity of the
Salmon Test Site Area.
Shallow ground water
Water found near the soil surface, caused by
precipitation infiltration of the soil. This
shallow ground water is not an aquifer.
13
-------
GLOSSARY OF TERMS
(Continued)
Surficial Aquifer
Post Sample
The ground water layer located closest to the
surface, generally at a depth of approximately
30 feet at SGZ.
Last sample taken from wells onsite (after
recharge).
Type I Error
Tritium
A radioactive isotope of hydrogen that decays
by beta emission. Its half-life is about 12.5
years.
The statistical error of accepting the presence
of radioactivity when none is present.
Sometimes called alpha error.
Type II Error
Pre Sample
First sample taken from wells onsite (before
pumping).
The statistical error of failing to recognize the
presence of radioactivity when it is present.
Sometimes called beta error.
14
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APPENDIX A
Summary of Analytical Procedures
Type of
Analysis
Analytical
Equipment
Counting
Period (Min)
Analytical
Procedures
Sample
Size
Approximate
Detection Limit"
HpGe
Gammab
HpGe detector
calibrated atO.5 keV/
channel (0.04 to 2 MeV
range). Individual detector
efficiencies ranging from
15 to 35%.
150
Radionuclide concen-
tration quantified from
gamma spectral data by
online computer program.
3.5L
Varies with radio nuclides
and detector used, nonnally
counted to a MDC of
approx. 5 pCi/L for Cs-137
3H
Automatic liquid
scintillation counter
300
Sample prepared by
distillation.
5 to 10 mL
300 to 700 pCi/L
3H+ Automatic liquid
Enrichment scintillation counter
300
Sample concentrated by
electrolysis followed by
distillation.
5mL
5 pCi/L
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 percent each (DOE 1981).
Gamma spectrometry using a high purity intrinsic germanium (HpGe) detector.
Typical MDA Values for Gamma Spectroscopy
(100 minute count time)
Geometry*
Matrix
Volume
Isotope
Marinelli
Water
3.5 liter
MDA
Model
Density
Units
Isotope
430G
1.0 g/ml
pCiIL
MDA
Be-7
K-40
Cr-51
Mn-54
Co-57
Co-58
Fe-59
Co-60
Zn-65
Nb-95
Zr-95
Disclaimer
The MDA's provided are for background matrix samples presumed to contain no known analytes and no decay time.
All MDA's provided here are for one specific *Gennanium detector and the geometry of interest. The MDA's in no
way should be used as a source of reference for determining MDA's for any other type of detector. All gamma spec-
troscopy MDA's will vary with different types of shielding, geometries, counting times, and decay time of sample.
4.56E+0 1
4.92E+Ol
5.88E+Ol
4.55E+Ol
9.65E+00
4.71E+00
1.07E+Ol
5.38E+00
1. 24E+01
5.64E+00
9.06E+00
Ru-106
Sn-113
Sb-125
1-131
Ba-133
Cs-134
Cs-137
Ce-144
Eu-152
Ra-226
U-235
Am-241
4.76E+Ol
8.32E+00
1.65E+Ol
8.28E+00
9. 16E+00
6. 12E+00
6.43E+00
7.59E+Ol
2.86E+Ol
1.58E+Ol
1.01E+02
6.60E+Ol
15
-------
APPENDIX B
TRITIUM RESULTS FOR WATER SAMPLES COLLECTED IN APRIL 2001
Collection Enriched Gamma
Sample Date Tritium Tritium Spectrometry (b)
Location 2001 pCiIL :J: 2 SD (MDC) pCi/L :J: 2 SD (MDC) Comments (MDC)
Baxterville, MS
Anderson, Billy Ray 4-16 7.2:J: 3.8 (6.0) ND (5.0)
Anderson Pond 4-16 9.8:J: 3.4 (5.0) ND (4.0)
Vines, James 4-16 -28 :J: 136 (225) ND (5.0)
Anderson, Rhonda 4-16 29.5 :J: 137 (225) ND (4.6)
Anderson, Robert Lowell, Jr. 4-17 -.85 :J: 135 (225) ND (4.6)
Anderson, Robert Lee, Jr. 4-17 26 :J: 137 (225) ND (4.9)
Anderson, Tony 4-16 No sample city water
Burge, Joe 4-17 -63 :J: 136 (225) ND (4.9)
Half Moon Creek Pre 4-16 1.3:J: 3.4 (5.0) ND (4.6)
Post 4-17 10.3:J: 2.2 (4.5) ND (4.6)
Half Moon Creek Pre 4-16 214:J:5.7 (5.2) ND (4.6)
Overflow Post 4-17 222:J: 5.7 (5.0) ND (4.8)
Hibley, Billy 4-16 33 :J: 137 (225) ND (4.9)
Napier, Denice 4-17 11:J: 3.6 (5.6) ND (5.0)
Lee, Perry T., Jr. 4-16 -42 :J: 136 (225) ND (5.0)
Little Creek #1 4-16 -70.5 :J: 136 (225) ND (5.0)
Lower Little Creek #2 4-16 -13.4 :J: 137 (225) ND (1.5)
Mills, Roy 4-16 No sample city water
(a) Indicates results are less than MDC
(b) No gamma radionuc1ides detected above MDC
ND Non-detected, represents 137Cs (PCiIL)
16
-------
APPENDIX B (Continued)
TRITIUM RESULTS FOR WATER SAMPLES COLLECTED IN APRIL 2001
Collection Enriched Gamma
Sample Date Tritium Tritium Spectrometry (b)
Location 2001 pCi/L :t 2 SD (MDC) pCi/L :t 2 SD (MDC) Comments (MDC)
Baxterville, MS (Coot)
Mills, AC 4-16 No sample city water
Nobles Pond 4-17 33 :t 137 (225) ND (4.6)
Noble, Evelyn 4-17 -17 :t 136 (225) ND (4.7)
Pond West of GZ Pre 4-16 4.9 :t 3.4 (5.4) ND (4.3)
Post 4-17 9.6 :t 3.6 (5.6) ND (4.5)
REECo Pit Drainage-A 4-16 142 :t 202 (225) ND (4.6)
REECo Pit Drainage-B 4-16 25.9 :t 123 (225) ND (4.9)
REECo Pit Drainage-C 4-16 22.4 :t 3.8 (5.5) ND (4.7)
Saucier, Dennis 4-16 14 :t 4.0 (6.3) ND (4.6)
Well Ascot 2 4-16 Not sampled per DOE
Baxterville Well City 4-17 4.5 :t 137 (225) ND (1.5)
Well E-7 4-20 -70 :t 199 (329) ND (4.8)
Well HM-l Pre 4-16 24 :t 200(0) (329) ND (4.9)
1st 30 Min 4-16 98 :t 199(0) (329) ND (4.9)
2nd 30 Min 4-16 -4.2 :t 200(a) (320) ND (4.8)
Post 4-16 -2.4 :t 200(0) (329) ND (4.3)
Well HM-2A Pre 4-16 -18.6 :t 200(0) (329) ND (5.0)
1st 30 Min 4-16 -4.3 :t 200(0) (329) ND (4.9)
2nd 30 Min 4-16 30.6 :t 200(0) (329) ND (5.0)
3rd 30 Min 4-16 50 :t 199(0) (329) ND (5.0)
Post 4-16 27 :t 200(0) (329) ND (4.9)
Well HM-2B Pre 4-16 210 :t 202(0) (529) ND (5.0)
1st 30 Min 4-16 -0.39 :t 3.1 (5.1) ND (1.9)
Post 4-16 -3.2:t 3.2 (5.0) ND (4.0)
(0)
(b)
Indicates results are less than MDC
No gamma radionuclides detected above MDC
Non-detected, MDC for gamma represents 137Cs (pCi/L)
ND
17
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APPENDIX B (Continued)
TRITIUM RESULTS FOR WATER SAMPLES COLLECTED IN APRIL 2001
Sample
Location
Collection
Date
2001
Enriched
Tritium Tritium
pCi/L :!: 2 SD (MDC) pCi/L :!: 2 SD (MDC) Comments
Gamma
Spectrometry (b)
(MDC)
Baxterville, MS (cont.)
Well HM-3
Pre
1st 30 Min
4-16
4-16
Well HM3 2nd 30 Min 4-16
3rd 30 Min 4-16
Post 4-16
Well HM-L Pre 4-16
1st 30 Min 4-16
2nd 30 Min 4-16
3rd 30 Min 4-16
4th 30 Min 4-16
5th 30 Min 4-16
Post 4-16
Well HM-L2 Pre 4-17
Post 4-17
Well HM-S Pre 4-16
Post 4-17
Well HMH-l Pre 4-16
Post 4-17
Well HMH-2 Pre 4-16
Post 4-17
Well HMH-3 Pre 4-16
Post 4-17
Well HMH-4 Pre 4-16
Post 4-16
Well HMH-5 Pre 4-16
Post 4-17
Well HMH-6 Pre 4-16
Post 4-16
1.5 :!: 3.7 (6.1)
-55 :!: 3.8 (6.0)
-50:!: 3.3(0) (5.5)
3.8 :!: 3.7(0) (6.0)
-48 :!: 3.3(0) (5.4)
67 :!: 8.9 (5.0)
4.0 :!: 7.0(0) (5.0)
347:t 7.0 (5.0)
358:!: 7.0 (5.0)
2.0 :!: 6.0(0) (5.0)
4.0 :!: 7.0(0) (5.0)
4.0 :!: 7.0(0) (5.0)
-1.6 :!: 3.5(0) (5.7)
-1.3 :!: 3.4(0) (5.7)
1710 :!: 216(0) (329)
1620 :!: 212(0) (329)
182 :!: 202
476 :!: 204
(329)
(329)
ND (4.6)
ND (4.6)
ND (4.9)
ND (4.7)
ND (4.5)
ND (4.0)
ND (4.5)
ND (5.0)
ND (5.0)
ND (5.0)
ND (5.0)
ND (5.0)
ND (4.7)
ND (1.9)
ND (4.8)
ND (5.0)
No Sample per DOE
No Sample per DOE
(329)
(329)
No Sample per DOE
No Sample per DOE
(0) Indicates results are less than MDC
(b) No gamma radionuc1ides detected above MDC
ND Non-detected, MDC for gamma represents 137CS (pCi/L)
35.0 :!: 203 (329)
216 :!: 202(0) (329)
-133 :!: 199(0) (329)
122 :!: 201(a) (329)
373 :!: 203
708 :!: 207
18
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APPENDIX B (Continued)
TRITIUM RESULTS FOR WATER SAMPLES COLLECTED IN APRIL 2001
Collection Enriched Gamma
Sample Date Tritium Tritium Spectrometry (b)
Location 2001 pCiIL :!: 2 SD (MDC) pCiIL :!: 2 SD (MDC) Comments (MDC)
Baxterville, MS (cont.)
Well HMH-7 Pre 4-16 No Sample per DOE
Post 4-16 No Sample per DOE
Well HMH-8 Pre 4-16 No Sample per DOE
Post 4-16 No Sample per DOE
Well HMH-9 Pre 4-16 -7 :!: 200(a) (329)
Post 4-17 -139 :!: 199(a) (329)
Well HMH-lO Pre 4-16 304 :!: 203(a) (329)
Post 4-17 327 :!: 203(a) (329)
Well HMH-11 Pre 4-16 47 :!: 200(a) (329)
Post 4-17 25 :!: 127(a) (329)
Well HMH-12 Pre 4-16 No Sample per DOE
Post 4-16 No Sample per DOE
Well HMH-13 Pre 4-16 No Sample per DOE
Post 4-16 No Sample per DOE
Well HMH-14 Pre 4-16 No Sample per DOE
Post 4-16 No Sample per DOE
Well HMH-15 Pre 4-16 No Sample per DOE
Post 4-16 No Sample per DOE
Well HMH-16 Pre 4-16 1O:!: 3.5 (5.5)
Post 4-17 11 :!: 3.7 (6.0)
SA1-1H Pre 4-17 23,200:!: 415 (202) ND (4.9)
Post 4-18 26,700 :!: 328 (202) ND (4.7)
SAl-2H Pre 4-17 2520 :!: 172 (202) ND (4.8)
Post 4-18 2280 :!: 168 (202) ND (4.3)
SAl-3H Pre 4-17 886 :!: 103 (5.1) ND (4.9)
Post 4-18 603 :!:8.5 (4.9) ND (4.9)
(a)
(b)
Indicates results are less than MDC
No gamma radionuclides detected above MDC
Non-detected, MDC for gamma represents 137CS (pCiIL)
ND
19
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APPENDIX B (Continued)
TRITIUM RESULTS FOR WATER SAMPLES COLLECTED IN APRIL 2001
Collection Enriched Gamma
Sample Date Tritium Tritium Spectrometry (b)
Location 2001 pCi/L :t 2 SD (MDC) pCi/L :t 2 SD (MDC) Comments (MDC)
Baxterville, MS (cont.)
SAlAH Pre 4-17 290 :t 130 (202) ND (4.5)
Post 4-18 229 :t 128 (202) ND (4.8)
SAl-5H Pre 4-17 891 :t 142 (202) ND (4.7)
Post 4-18 879 :t 142 (202) ND (4.7)
SAl-6H Pre 4-17 33,000 :t 453 (202) ND (5.0)
Post 4-18 52 :t 124 (202) ND (4.3)
SAl-7H Pre 4-16 47 :t 124(a) (202) ND (4.7)
Post 4-17 57 :t 124(a) (202) ND (4.6)
SAl-8-L 4-18 17.0 :t 123(a)(202) ND (1.5)
SAl-9-2A 4-19 4.3:t 3.1 (a) (5.0) ND (4.8)
SAI-1O-2B 4-19 2.8:t 3.6(a) (5.8) ND (4.9)
SA1-11-3 4-19 -17 :t 122(a)(202) ND (4.9)
SA2-1-L 4-18 4.7 :t 123(a)(202) ND (5.0)
SA2-2-L 4-16 No sample per DOE
SA2-3-L 4-18 5.7:t 3.8(a) (6.2) ND (4.9)
SA2-4-L 4-18 69 :t 125(a)(202) ND (4.6)
SA2-5-L 4-18 112 :t 125(a\202)
ND (5.0)
SA3-1M Pre 4-18 112 :t 125(a)(202)
ND (4.8)
Post 4-19 82 :t 125(a)(202)
ND (4.8)
SA3-3M Pre 4-18 15 :t 3.2 (4.9) ND (5.0)
Post 4-19 14 :t3.4 (5.2) ND (5.0)
(a) Indicates results are less than MDC
(b) No gamma radionuclides detected above MDC
ND Non -detected, MDC for gamma represents 137Cs (pC ilL)
20
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APPENDIX B (Continued)
TRITIUM RESULTS FOR WATER SAMPLES COLLECTED IN APRIL 2001
Collection Enriched Gamma
Sample Date Tritium Tritium Spectrometry (b)
Location 2001 pCi/L:t 2 SD (MDC) pCi/L :t 2 SD (MDC) Comments (MDC)
Baxterville, MS (cont.)
SA3-4H Pre 4-17 16.4 :t3.4 (5.0) ND (5.0)
Post 4-18 16.6 :t 3.3 (5.0) ND (5.0)
SA3-5-H Pre 4-17 73.5 :t 125(a)(202) ND (5.0)
Post 4-18 56 :t 124(a)(202) ND (4.9)
SA3-8-1 4-20 .60 :t 3.0 (4.9) ND (4.9)
SA3-1O-2B 4-20 86 :t 125(a)(202) ND (4.6)
SA3-11-3 4-20 -8.6 :t 123(a)(202) ND (1.6)
SA4-1M Pre 4-17 7.4 :t 3.3 (5.0) ND (4.9)
Post 4-18 5.7 :t 3.0 (5.0) ND (4.7)
SAS-IM Pre 4-18 7.8 :t 3.5(0) (5.0) ND (4.6)
Post 4-19 9.2 :t 3.3(0) (5.0) ND (4.6)
SAS-2M Pre 4-18 13.7 :t 3.3 (5.0) ND (5.0)
Post 4-19 12.7 :t 3.5 (5.4) ND (4.8)
SAS-3M Pre 4-18 82 :t 125(a)(202) ND (4.6)
Post 4-19 86.5 :t 125(a) (202) ND (4.6)
SAS-4-4 4-20 2.4 :t 3.2(0) (5.3) ND (4.8)
SAS-5-4 4-20 1.84 :t 3.5(a) (5.6) ND (4.8)
Well HT-2C 4-16 No Sample per DOE
Well HT-4 4-16 No Sample per DOE
Well HT-5 4-16 No Sample per DOE
(a)
(b)
Indicates results are less than MDC
No gamma radionuc1ides detected above MDC
Non -detected, MDC for gamma represents 137Cs (pCi/L)
ND
21
-------
APPENDIX B (Continued)
TRITIUM RESULTS FOR WATER SAMPLES COLLECTED IN APRIL 2001
Collection Enriched Gamma
Sample Date Tritium Tritium Spectrometry (b)
Location 2001 pCilL :t 2 SD (MDC) pCilL :t 2 SD (MDC) Comments (MDC)
Columbia, MS
Well 46-003-5-6-7 4-17 -11 :t 136(a) (225) ND (1.6)
Lumberton, MS
Anderson, Arleene 4-18 -45.6:t 136(a) (225) ND (4.9)
James Lowe 4-14 40 :t 137(a) (225) ND (4.6)
Crawfish Pond 4-16 -38 :t 125(a) (225) ND (4.7)
Powell, Shannon 4-14 104 :t 139(a) (225) ND (4.4)
Smith, Howard Pond 4-16 -42 :t 136(a) (225) ND (4.6)
Thompson, Mike 4-16 -57 :t 136(a) (225) ND (1.8)
Thompson, Roswell 4-16 -24 :t 136(a) (225) ND (4.4)
Well 2 City 4-17 -2.5 :t 3.5(a) (5.9) ND (4.2)
Burge, Willie 4-17 121 :t 135(a) (225) ND (1.4)
Kiffe, Richie & Patsy 4-16 -6.3 :t 137(a) (225) ND (5.0)
Purvis, MS
City Supply Purvis 4-17 .89 :t 3.7(a) (6.1) ND (1.9)
Rain Sample IT Compound 4-28 No sample - no rain
(a)
(b)
Indicates results are less than MDC
No gamma radionuclides detected above MDC
Non -detected, MDC for garnrna represents I37Cs (pCilL)
ND
22
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