Annual Water Sampling and Analysis
        at the Salmon Test Site Area

           Lamar County, Mississippi
                   April 2006

                        by
                   James R. Harris Jr.
           Prepared for the U.S. Department of Energy
               under Interagency Agreement
                  DE-AI08-96NV11969
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

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                                        NOTICE

The information in this document has been funded wholly or in part by the United Slates Environmental
Protection Agency (U.S. EPA) through an Interagency Agreement [(LAG) DE-AI 08-96NV11969] from
the United States Department of Energy (U.S. DOE).  It has been subjected to the Agency's peer and
administrative reviews, 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
The Long-Term Hydrological Monitoring Program (LTI-IMP), directed by the EPA, conducts
annual water sampling on and around the Salmon Test Site Area. In 1964 and 1966, nuclear
explosives were detonated approximately 2,700 feet (823 m) underground at the Salmon Test Site
Area located in Lamar County, Mississippi. Drilling and clean-up activities have resulted in
tritium contamination in close proxiimty to the surface ground zero.
In this report, the 2006 annual water sampling at the Salmon Site is described, and the analytical
results of the collected samples are given. The highest tritium concentration onsite was 7.2 x
pCi/L in water from well SAl-lI-I (see Appendix B). No radioactivity attributable to the test site
was found in any offsite water sample The highest tritium concentration offsite was 9.4 ± 3.5
pCi/L at the James D. Lowe pond.
Negative values for tntium aie obtained when the counts registered on the liquid scintillation
counter for a regular sample are less than the average counts obtained for the fossil water samples
used as background samples. The average background counts are deducted from the sample
counts to correct for background radiation affecting the detector in the scintillation counter. It is
normal to get some negative values for samples with little or no tritium in them due to statistical
counting vanations; hence environmental samples are at background levels.
The incidence of negative results is slightly higher this year than in past years due to a change in
the scintillation cocktail used for counting. We are no longer able to use the Beckman ReadySafe
scintillation cocktail used in previous years because a change in the formulation has substantially
raised the background counts from around 3 5 to 12 counts per minute The result is to ncai ly
double the detection limit and the 2-sigma error for the samples is unacceptable. All of the
replacement scintillation cocktails show a slightly greater variability in counting resulting in more
instances where the average background counts exceed the counts for the low activity samples
We are now using EcoLume liquid scintillation cocktail
All samples were also analyzed for the presence of gamma-ray emitting radionuclides. None
were detected above the minimum detectable concentration (MDC) (see Appendix B).
iii

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This page is left blank intentionally.
Iv

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CONTENTS
Page
Notice . ii
Abstract iii
Contents v
Figures vi
Acronyms and Abbreviations vii/viii
Acknowledgments ix
Introduction 1
History
Historical Monitoring Results 2
Sample Collection 9
Sample Analysis 10
Water Analysis Results 10/11
References 12
Glossary of Terms 13/14
Appendices
A. Summary of Analytical Procedures 15
B. Gamma/Tritium Results for Water Samples Collected in April 2006 16/17
C. R&IE’s LTHMP related SOPs 18
V

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FIG URES
I Figure Number Page I
1 General site location of Project Salmon Test Site Ai-ea 3
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 4
3 Test cavity and aquifers 5
4 Tritium concentration vs. sanipling year for HM-S (depth 30 fl) 6
5 Tritium concentration vs. sampling year for HM-L (depth = 200 fi) 6
6 Locatioiis on the Salmon Test Site Area sampled in 2006 7
7 Offsite locations sampled in 2006 .8
vi

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ACRONYMS AND ABBREVIATiONS
AEC U.S. Atomic Energy Commission
Bq/L Becquerel per liter
‘ 37 Cs Cesium-I 37
60 Co Cobalt-GO
CERMER Center for Environmental Restoration Monitoring and Emergency
Response
CRQA Center for Radioanalysis and Quality Assurance
DCG Derived Concentration Guide
DOE U.S. Department olEnergy
EPA U.S. Environmental Protection Agency
Frac Tank storage container
gram
Tritiurn
3 H+ Enriched Tritium
HpGe high purity germanium gamma detector
HM-L, HM-L2 Hydrological Monitoring Well - Local Aquifer
HM-S Hydrological Monitoring Well - Surficial Aquifer
HM-l Hydrological Monitoring Well - Aquifer I
HM-2a Hydrological Monitoring Well - Aquifer 2a
HM-2b Hydrological Monitoring Well - Aquifer 2b
E-TM-3 Hydrological Monitoring Well - Aquifer 3
lAG Interagency Agreement
ITC international Technology Corporation
Iodine— 131
keV kilo electron volts = thdusand electron volts
kg kilogram, 1000 grams
kt kiloton (TNT equivalent)
L liter
LTHMP Long Term Hydrological Monitoring Program
ni meter
MCL maximum contaminant level
MDA minimum detectable activity
MDC mi i ii mum detectable concentration
MeV one million electron volts
miii minute
mL milliliter = one thousandth of a liter
MT megaton (one million tons TNT equivalent)
ORI A Office of Radiation and Indoor Air
pCi/L picocuries per liter= lOi2 curies per liter= l/I,000,000,000,000
curies per liter
PHS U.S. Public Health Service
REECo Reynolds Electrical & Engineering Company
vii

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ACRONYMS AND ABBREVIATIONS Continued
R&IE Radiation and Indoor Environments National Laboiatoiy, Las
Vegas, NV
90 Sr Strontium-90
SA Wells Source Area Wells
SGZ surface ground zero
USGS U.S. Geological Survey
Xenon-131
Xenon-133
vii’

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ACKNOWLEDGMENTS
External peer review was provided by Vernon Hodge, Ph.D., Department of Chemistry,
University of Nevada, Las Vegas. In addition, the author would like to acknowledge
George Dilbeck, Ph.D., and Richard Flotard, Ph.D., as internal reviewers. A special
thanks to Mr. Max G. Davis, USEPA (Ret.) for h assistance and continuous support in
the outlined structure of this final product. Thanks also to Natalia Brooks, Mark Ovrebo,
of the General Dynamics Corp, IT contractors, for their assistance and significant
contributions in this reports/production.
Finally the basis of this report could not have happened without the efforts of the large
and dedicated LTHMP Field Sampling Team pictured below which made all our work
possible.
Left to right front row seated: Rose (Kitty) Houston, R&IE (EPALV, NV), Nonya Cage,
Mississippi Radiological Health Dept (MRHD), Jackson, MS, Catherine Martin,
Stoller/Navarro DOE/LV, NV., contractor, Karl Barber, MRHD. 2’ row: David Traub,
Stoller, Grand Junction, CO. contractor, Dorsey Hamlin, MRDH, Wesley Boyd, R&IE,
Erik Hadwin, Weston Corp., Baton Rouge, LA., contractor. row: Jimmy L. Carson,
MRHD, Helly Diaz-Marcano, R&IE LV., Douglas Sharp, R&IE.
• IF-
pg
ix

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INTRODUCTiON
Under an Interagency Agreement (JAG) with the DOE, the EPA’s Radiation and Indoor
Environments National Laboratory (R&IE) located in Las Vegas, NV, conducts annual
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 potable drinking water supplies. This report presents the results for
samples collected under EPA’s LTHMP in April 2006, 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 (354 m) below the lop of the salt dome which lies 1,500 feet (457 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
EPA 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 selected surface waters in the vicinity of the Salmon Test Site are sampled
on an annual basis and analyzed to determine the presence of tritium, gamma and other
radioactive contaminants.

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Histoi-ical Monitoring Results
The disposal of drilling mud and fluids iiear the surface ground zero (SGZ) is responsible
for tritium ( 3 H) contamination of the soil zone and underlying shallow aquifer. These
waters lie at depths of 4 to 10 feet (1.2 to 3 rn) and 30 feet (9 m), respectively, and ai-e not
potable. Tritiurn contamination is also present in the potable water of the local aquifer
which lies at about 200 feet (61 m). The observed 3 H concentration in the local aquifer is
significantly below the 20,000 pCiIL guideline specified in the National Primary
Drinking Water Regulations; Radionuclides; Final Rule (4OCFR9/141/142), and is
thought to be due to drilling activities at the site (Fenske and Humphrey, 1980; Fordham
and Fenske, 1985).
2

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La u re
OakvaieS
EtIisviIie
S Bassfieid
SartinvilIe
McComb
Runne lstown
MISSISSIPPI
LOUISIANA
Baxterville
Vamado
Bogalusa
Poplarville
Wiggins
McNeil
McHenry
— Major Highway
Test Site, SGZ
L L !t
MkU
LAMAR
COUNT(
LOCATiON MAP
u I. ( eiwra I site location of Project Sal mon Test Site A rca .

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ffik a M m m n
—, bad *i i a railis
4
& MON TEST 1E A
I
I
4
N
0
OOALIR4PI,
0
i:
011 JW
4

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‘j
LIMESTONE
SANDSTONE
*The test cavity contains fission and activation products fro
10,770 cubic yards of radioactive, contaminated soils and
contaminated fluids and water from surfac. cleanup.
m the detonations plus
1.305000 gaHons of
Figure 3. Sn
irnon Site Test C
avity and Aquifers,
CITRON ELLE
AOL) IFER
HALF MOON CREEK
ALLU VIAL AQU IF ER
/ HOLE
P.5.1
LOCAL AQUIFER
2A
28
3A
RECRYSTALLIZED
MELT PUDDLE
5

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4S
ja.
2.
mll flIHmu
Figure 4. Tritium concentration vs. sampling year for HM-S (depth = 30 ft).
N
,so
I
— — — — — — — — — — — — — —
CaIeridat Year
Figure 5. Tritium concentration vs. sampling year for HM-L (depth = 200 ft).
6

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M$.7.Il •
•Mi441
M$-4-H•
•&êd$ 1 $
• &M u
• sr Ii LA, mh .
Ii ure 6. Onsite sampling locations sampled 2006.
7

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uc--- - ,
• ro
. ur ii L , dons
k
Figure 7. Offsite sampling locations sampled 2006 .
8

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Sample Collection
According to standard operating procedures agreed to by DOE (U.S. DOE 1981), the
shallow wells are first sampled, pumped-down, and resampled on the following day.
Wells HM-l, 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 minutes
intervals until the pH and conductivity of the water stabilized. A final sample was taken
from each well 30 minutes 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 from previous years. Well HM-L2 was first sampled and
then pumped for one hour before a second sample was taken and shut down.
For wells with operating pumps, the samples were collected at the nearest convenient
outlet. If the well has no pump, a truck-mounted or a submersible pump is used. Using
this truck mounted unit, it is possible to collect three-liter samples from wells as deep as
1829 meters (6,000 ft.). The pH, conductivity, water temperature, and sampling waler
level was measured and recorded as each sample was collected. Waste water contained
from wells HM-3, SAI-7-H, and SAl -2-H, SAl-I-H was contained in a Frac Tank and
then disposed of offsite by DOE, contractor Stoller Navarro.
In November 2000, the U.S DOE awarded a grant to Lamar County, Mississippi. The
grant provided an extension of the current drinking water system around the Salmon Test
Site. The water system eliminated the need to sample residential wells in the area and
around the site. However, the EPA and the State of Mississippi will continue monitoring
wells and surface locations onsite and offsite annually. The offsite sampling sites will
consist of city wells in Purvis, Baxterville, Columbia, and Lumberton, as well as some
local residents, ponds and streams.
In 2002, the U.S. DOE plugged 33 wells on the Salmon Site. There are 28 wells, 3 mud
pits, 1 pond, and 2 creek locations remaining in the LTHMP that will be sampled
annually onsite. If the reader would like more information on the plugged wells, they
should contact the U.S. DOE in Las Vegas, Nevada.
The locations of all sampling sites are shown on pages 7 and 8. Sampling results are
discussed in the sections that follow.
9

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Sample Analysis
Radiochernical laboratory procedures used to analyze the samples collected for this
report are summarized in R&IE’s SOPs (see Appendix A and C). These include
standard methods to identify natural and man-made gamma-emitting radionuclides,
tritiuni, plutonium, strontium, and uranium in water samples.
Two types of tritiurn analyses are performed: conventional and electrolytic
enrichment. The enrichment method lowers the mini mum detectable concentration
(MDC) froni approximately 300 pCi/L to about 5 pCi/L. An upper activity limit of
800 pCi/L as specified in SOP RQA-603 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 protocols 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 analysis and a full-suite of other
radiochemical determinations including assays for strontium-90, plutonium, and
urani urn.
\Vater Analysis Results
No radioactive materials from the Salmon Test Site Area were detected in any water
sample collected offsite; nor were tritium concentrations above normal background
values detected in any offsite sample. Gamma-ray spectral analysis results indicated
that no man-made gamma-emitting radionuclides were detected in either onsite or
offsite samples.
The highest tritium concentration found onsite was 7.2 x10 3 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.
Long-term decreasing trends in tritium concentrations are evident for onsite locations
that have shown detectable tritium activity since monitoring began under the LTI-IMP
in 1980 (wells HM-S and HM-L, depicted in Figures 4 and 5). in all, seven onsi tc
sampling locations exhibited tritium concentrations above the MDC (Well HM-L,
Well HM-S, Well HMH-5R, SAI-IH, SA-l-2H, SAI-3-H, SAI-5-H).
Tritium concentrations in the offsite samples ranged from less than the MDC to 9.4
pCi/L ( — 0.3 Bq/L). These results are typical of background tritium levels and do not
exceed the tritium activity expected in local precipitation.
10

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Water Analysis Results Continue
Due to the high rainfall in the area, the sampling procedure for selected onsite wells
was modified as follows: after collecti n of an initial sample, wells were purged and a
second sample is collected the following day after the well has recharged. The
second sample is representative of water that has infiltrated through the soil zone,
where as the first sample may represent a mixture of direct rainwater influx at the top
of the well and infiltrated soil zone water.
A total of 21 of the 34 onsite locations were sampled in this manner (pre-and post-
sampling): 10 yielded tritium activities greater than the MDC in either the first or
second sample. Of these, 10 yielded results higher than normal background
(approximately 25 - 40 pCi/L [ 0.9 - 1.5 Bq/L]) as shown in Appendix B. The
locations where the highest tritium activities were measured generally correspond to
areas of known contamination.
In summary, tritium concentrations in the water samples collected this year at the
Salmon Site are consistent with those of past studies: Onsite tritium concentrations,
were all below the 20,000 pCi/L maximum contaminant level (MCL) defined in
EPA’s National Primary Drinking Water Regulations; Radionuclides; Final Rule
(4OCFR9/141/142); and, the highest tritium concentration found offsite was 9.4 ± 3.5
pCifL which was at the James D. Lowe Pond, (<1/10 of 1% (0.05%) of EPA’s MCL.
All samples were analyzed for presence of gamma-ray emitting radionuclides and
none were detected (see Appendix B on pages 16-17).
11

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REFE RENCES
Final rule on Dec. 7, 2000. Code of Federal Regulations, Vol. 65, Title 40, Parts 9,
141, and 142, December 7, 2000, National Primary Drinking Water Regulations;
Radionuclides; Final Rule.
A Guide for Environmental Radiological Surveillance at U.S. Dept. of Energy
Installations, July 198 l,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 Monitoniig Data
Analysis, Las Vegas, NV: U.S. Department of Energy, Nevada Operations Office;
DOE/NV/10384-03; 1985.
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 millireni per year iii 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 ( tCi) is one millionth of a Ci.
Isotope
Atoms of the same element with different numbers of neutrons in the nuclei. Thus
‘ 2 C, ‘ 3 C, and 14 C are isotopes of the element carbon, the numbers denoting the
approximate atomic weights. Isotopes have very nearly the same chemical properties,
but oflen different physical properties (for example ‘ 2 C and U C are stable, i4 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 800 pCi/L.
Minimum Detectable Activity (MDA)
Minimum detectable activity.
Minimum Detectable Concentration (MDC)
The smallest amount of radioactivity that can be reliably detected with a probability
of Type I and Type TI errors at 5 percent each (DOE 1981).
o ITs ite
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

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GLOSSARY OF TERMS (Continue)
Surficial Aquifer
The ground water layer located closest to the surface, generally at a depth of
approximately 30 feet at SGZ.
Triti u in
A radioactive isotope of hydrogen that decays by beta emission. Its half-life is about
12.5 years.
Pre Sample
First sample taken from wells onsite (before pumping).
Post Sample
Last sample taken from wells onsite (after recharge).
Type I Error
The statistical error of accepting the presence of radioactivity when none is present.
Sometimes called alpha enor.
Type II Error
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
Counting Sample Appro’ inia Ic
‘l’ype of Analysis Analytical Period Analytical Procedures Size l)eectioiu Liiiiit
Equipment (Mm) counted
1-lpGe Gamma b HpGe detectoi 150 Radionuclide 3 5L Vanes with
calibrated at concemi ation quantified i adionucl ides and
0 5 flom gamma spectial data cletectoi used,
keV/channe l by online computel noi mally counted
(0.04 to 2 P 1 ogi am to a MDC of
MeV iange) appiox 5 pCi/L
Individual fbi Cs-137
detectoi
efficiencies
ranging fiom
15 to 35%
3 H Automatic 300 Sample piepared by 4 mL 300 pCi/L
liquid distillation
scintillation
counter.
Automatic 300 Sample is distilled 5 mL 5 pCi/L
Enrichment liquid concentiated by
scintillation electrolysis followed by
counter re-distillation.
The detection limit is defined as the smallest amount of iadioactivity that can be ieliably
detected, ic, piobability oflype I and Type II eiioi at 5 peicent each (DOE 1981)
(b) Gamma spectiometiy using a high put ily intiinsic germanium (l-lpGe) detectot
Typical MDA
Values for Gamma
Spectroscopy
(100 minute count time)
Marinelli
‘atci•
3.5 liter
Model
l)eusity
Units
430G
1.0 g/mL
pCi/L
Isotope
MDA
Isotope
MDA
Ru-106
4.76E+0l
Be-7
4.56E+01
Sn-I 13
8.32 13+00
K-40
492E+01
Sb-125
l.65E-i-0l
Ci-51
588E+01
1-131
828E+00
Mn-54
4.55E+0l
Ba-133
9 1613+00
Co-57
965E+00
Cs-134
6 12E+00
Co-58
471E+00
Cs-l37
64313+00
Fc-59
1.07E+0I
Ce-144
7 59E+Ol
Co-60
5.38E+00
Eu-l52
286134-01
Zn-65
1 24E+01
Ra-226
I 58E+Ol
Nb-95
5.64E+00
U-235
I OIE+02
Zi-95
9 06E+00
Arn-24 1
6.6013+01
15

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OtT-Site sa,iipliiig locations
Ba.tciville City Well
Lowci Little Cieck NI
Lower Littic Crcck #2
Lunibcrton City Vcll #2
Puivis City Supply VeIl
City Well 46-003-5-6-7
James D Lowc Pond
Ilowaid Smith Pond
Thompson l3luc Stoic
Gieeiwillc Comm Ctr 4-17
Noblcs Pond 4-17
13 R Andeison Pond 4-17
Indicates results arc less than MDC
(bI No gamma radionuclides detected above MDC
ND - Non-detected, MDC for ganima represents ‘ 37 Cs (pCu/L)
MDC — Minimum Detectable Concentration
Gauim ia
Spcctu-oiiic l iv
Coiiiuiieiits (b) —
pCu/l_ Ml)C
NI) (4 9)
-48 ± I39 (231) NI) (30)
NI) (4 6)
NI) (49)
NI) (4 8)
NI) (4 8)
NI) (4 9)
NI) (4 9)
Ill ± I43 (231) l3ackgiound NI) (4 9)
sample ioi
I-lUll w,iIci
4-17
4-17
4-18
4-I l
4-18
4-17
4-18
4-17
4-18
4-17
4-18
4-17
4-17
4-17
4-17
4-17
4-17
4-Il
4-17
4-I l
4-I l
4-li
4-17
-24 ± I40 (231)
-72 ± I40 (231)
2130 ± 167 (222) 3 1l(only)
2710 ± 175 (222) 3 1 1(only)
45 ± 35(a) (222) II (only)
21 ± I 35 (222) I-I (only)
400 ± 149 (231) si-i (only)
534 ± 152 (231) si-i (only)
142 ± l36 (219)
222 ± 137 (219)
177 e 136w (219)
III ± l35 (219)
187 * l36 (219)
20 ± l34 (219)
-21 ± l33 (219)
-28 ± l33 (219)
80 ± I35 (219)
28 ± I33 ’ (219)
NI) (50)
ND (47)
NI) (4 8)
ND (49)
ND (49)
NI) (49)
ND (43)
ND (48)
NI) (4 9)
ND (46)
ND (47)
NI) (4 9)
ND (50)
ND (47)
NI) (46)
NI) (49)
Snun 1 ilc Location
Appendix B
Gamma/Tritium Results for ‘ater Samples Collected in April 2006
Ti ilium
pCiIL ± 2 SD MDC
Collection
I)ate
2006
4-18
4-Il
4-17
4-18
4-18
4-18
4-Il
4-Il
4-17
Enriched
Tritiuni
pCiIL ± 2 SD MDC
70 ± 30 (50)
60 ± 30 (50)
94 * 35 (50)
85 ± 39 (62)
-87 ± I 38 (231)
-58 ± I 39(i) (231)
67 ± l42 (231)
-43 ± I39 (231)
119 ± I4l (231)
77 ± I39 (231)
NI) (50)
NI) (4 6)
NI) (50)
Appendix B
Cainma/Tritium Results lot- Vater Samples Collected in April 2006
Eiiriclicd Trituiiiii
Trititi in
pCUL ± 2 SD MDC pCiIL ± 2 SD MDC
Gaiiim.i
COIn iIICIll , Sped i U unetry
1 iCi/L MI)C
Sample Collection I)ate
Localiou 2006
Oiisute Miunliluuig locntion
VcIl E-7
Ila lf Moon Pre
Cicck Post
llalfMooii Crk Pre
Ovci how
Half Moon Crk
Ovei how Post
Well IIMII5R Prc
Post
Well IIMIII6R Pre
l’ost
\VcIl IIM-S Pie
Post
VclI hIM-L Pre
I ” 30 Miii
2 d 30 Mm
3 rd 30 Mm
4 th 30 M in
5 th 30 Mm
Post
Wcll IIM-l Pie
lu 30Mm
2 30 Miii
3 30 Miii
Post
-09 ± 40 (60)
75 ± 40 (60)
82 * 40 (50)
212 ± 60 (50)
123 * 50 (50)
ND (49)
16

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Appendix B
Gainma/Tritium Results for Water Samples Collected in April 2006 (Continued)
Sample Collection I)alc
Location 2006
Oimsite so mupliimg locations (Continued)
VcII HM-2A Pre 4-17
la3OMiil 4-17
2 30Mmn 4-17
3rd3OMlil 4-I l
Post 4-17
\VeII IIM-2 13 Pie 4 17
la3OMmn 4-17
Post 4-17
WcIIIIM-3 l’rc 4-17
lu3OMIn 4-17
2 30Mm 4-Il
3rd3OMin 4-17
Post 4-17
RE Co Pit Diainage-A 4-19
RECCo Pit Drainage-B 4-19
RECCo Pit Diainagc-C 4-19
I IM-L2 I’mc 4-18
Post 4-18
Pond West oIGZ Pre 4-Il
Post 4-18
SAl-I-Il Pre 4-Il
SAI-8-L
SAl-I 1-3
SA 1- 12-Il
SA2-I-L
SA2-2-L
SA2-4-L
SA3-4-Il
SA3-l 1-3
SA4-5-L
SA5-4-4
SA5-5-4
Frac Tank
Frac Tank Filici
Post
Pre
Post
Pie
Post
Pre
Post
Pie
Post
Pie
Post
Pre
Post
6 ± 31° ’ (50)
15 ± 31°’ (50)
92 ± 33 (50)
76 ± 54°’ (90)
86 ± 50 (80)
128 * 72 (90)
125 ± 69 (80)
52 ± 48 (80)
62 ± 58 ’ ’ (90)
SI * 54°’ (90)
91 ± 50 (80)
23 ± 4901 (50)
61 * 48°’ (80)
50 ± 47 (SO)
-22 * 4 0°’ (6 7)
42 ± 47ia 1 (76)
-34 ± 40°’ (68)
57 5 3°’ (9 0)
37 ± 49° (90)
35 ± 134° (219)
10 th l33 ° (219)
14 ± 133111 (219)
Ii ± I34° (219)
31 ± 134 ’° (219)
-17 133°’ (219)
35 ± 133 (1 ) (219)
10 ± 133°’ (219)
62 ± I34 ° (219)
-197 + 144°’ (245)
-130 ± 146 ’° (245)
7170 ± 227 (222) 3 1-I (only)
925 ± ISO (222) ‘II (only)
744 & 147 (222) II (only)
216 ± I 38°’ (222) H (only)
251 ± 139 (222) II (only)
—70 ± I 34°’ (222) II (only)
122 + I 37(1) (222) H (only)
ii (only)
ii (only)
ii (only)
H (only)
ii (only)
ii (only)
No Sample
56 ± l36 ° (223)
136 ± I 37° (222) ‘ II (only)
56 ± 136°’ (222) ii (only)
84 ± 137°’ (223)
ND (50)
ND (50)
ND (50)
ND (50)
ND (48)
ND (50)
NI) (50)
NI) (47)
NI) (50)
NI) (4 9)
ND (47)
ND (50)
Nt) (4 7)
NI) (4 8)
NI) (50)
NI) (4 9)
ND (50)
NI) (50)
ND (50)
ND (49)
ND (49)
NI) (50)
ND (49)
(4 9)
(4 9)
(7 6)
Enriched ru—u (I I I Iii
l’i itiului
pCiIL ± 2 SD MDC pCi!L ± 2 SD MDC
Ca nina
Coinuimeuuts Sped 1(1111(11 5’
1 )Cu/L MI)C
37 ± 52(1) (90)
No Sample
No Sample
No S mpIe
SAI-2-ll
SAI-3-ll
SAI-4-II
SAl-S-Il
SAI-6-Il
SAI-7-H
6450 ± 219 (222) 3 1I(only)
4-IS
4-17
4-IS
4- 17
4-18
4-17
4-I8
4.17
4-18
4-17
4-18
4-17
4-18
4-19
4-19
4-17
4-18
4-19
4-19
4-19
4-17
4-IS
4-20
4-20
4-20
4-20
4-20
4-20
Pie
Post
Prc
Post
II (only)
II (only)
Indicates ucsults arc less Ihan MDC
(b) No gamma radionuclides detected above MDC
ND - Non-detected, MDC for gamma represents ‘ 37 Cs (pCu/L)
MDC - Minimum Detectable Conccntuatuon
No Sample
NI)
ND
Ganiuiizm SL1SpCi1dC(I ND
Only watci liltem
17

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Appendix C
Standard Operating Procedures for the Center for Environmental Restoration, Monitoring &
Emergency Response
CER-203 Standard Operating Proced tire for the Long-Term Hydrological Monitoring Program
Standard Operating Procedures for the
Center for Radioanalysis & Quality Assurance
RQA-302 Standard Operating Procedures of Gamma-Ray Detector Systems.
RQA-602 Ti-iti urn Enrichment Procedure.
RQA-603 Standard Operating Procedure for 89Sr and 9OSr in Water, Air Filters and Milk.
RQA-604 Standard Operating Procedure of Convention Tritium in Water.
RQA-606 Analysis of Plutonium, Uranium and Thorium in Environmental Samples by Alpha
Spectroscopy.
18

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