Annual Water Sampling and
Analysis, Calendar Year 2006
SHOAL Test Site Area
FAULTLESS Test Site Area
RULISON Test Site Area
RIO BLANCO Test Site Area
GASBUGGY Test Site Are
GNOME Test Site Area
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 States Environmental
Protection Agency (EPA) through Interagency Agreement (IAG) DE-AI08-96 NV 11969 from the United
States Department of Energy (DOE). This document 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.
11
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ABSTRACT
The U. S. Environmental Protection Agency, Radiation and Indoor Enviionments National Laboratory in
Las Vegas, Nevada (R&IE), operates the radiological surveillance program and monitors former nuclear
underground test areas in Alaska, Colorado, Mississippi, Nevada, and New Mexico, each year under the
Long Term 1-lydrological Monitoring Progi-am (LTHMP) The LTHMP is designed to detect residual man-
made radionuclides in surface and ground water resulting from underground nuclear test activities. This
report describes the sampling and analysis of water samples collected from six former nuclear test sites in
three western states during 2006: Projects Shoal and Faultless in Nevada; Projects Rulison and Rio Blanco
in Colorado, and Projects Gasbuggy and Gnome in New Mexico. Monitoring results for Alaska and
Mississippi are reported separately.
Radiological results for 2006 are consistent with results from previous years. No increase was seen in
either tritium concentrations or gamma-ray emitting radionuclides at any site. Tritium levels at the sites are
generally decreasing or stable and are well below the 20,000 pCi/L guideline specified in the National
Primary Drinking Water Regulations; Radionuclides, Final Rule (4OCFR9/141/142), with the exception of
samples from several deep wells adjacent to the nuclear cavity at the Gnome site. Three deepest wells at
this site Well USGS-#8, Well LRL-#7, and Well DD-#l, were not sampled this year at the
recommendation of DOE
Negative values for tritiurn
Negative values for tritium are 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, since environmental samples are at background levels.
The incidence of negative results is slightly higher this yeai than in past yeais due to a change in the
scintillation cocktail used for counting. We are no longer able to use the Beckman Ready Safe
scintillation cocktail used in previous years because a change in the foi-mulation has substantially raised
the backgiourid counts from around 3 5 to 12 counts per minute The result is an unacceptable near
doubling of the detection limit and the 2-sigma error for the samples. 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 ai-e now using EcoLume liquid
scintillation cocktail.
All samples were also analyzed for the presence of gamma-ray emitting radionuclides None wcie
detected above minimum detectable concentration (MDC) see Appendix B, page 21.
iii
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This page left blank intentionally.
iv
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CONTENTS
Page
Notice . ii
Abstract iii
Figures and Tables vi
Acronyms and Abbreviations vii
Acknowledgments viii
1.0 Introduction and Summary of Analytical Procedures 1
2.0 Sample Analysis 3
2.1 Sampling at Project SHOAL, Nevada 3
2.1.1 Sample Collection 3
2.1.2 Water Analysis Results 3
2.1.3 Conclusions 4
2.2 Sampling at Project FAULTLESS, Nevada 6
2.2.1 Sample Collection 6
2.2.2 Water Analysis Results 6
2.2.3 Conclusiomis 7
2.3 Sampling at Project RULISON, Colorado 9
2.3.1 San1ple Collection 9
2.3.2 i\nalysis l4esults . 9
2.3.3 Conclusions 10
2.4 Sampling at Project RIO BLANCO, Colorado 12
2.4.1 Sample Collectiomi 12
2.4.2 Water Analysis Results 12
2.4.3 Conclusions 13
2.5 Sampling at Project GASBUGGY, New Mexico 15
2.5.1 Sample Collection 15
2.5.2 Water Analysis Results 15
2.5.3 Conclusions 16
2.6 Sampling at Project GNO1 ’IE, New Mexico 18
2.6.1 Sample Collection 18
2.6.2 Water Analysis Results 18
2.6.3 Conclusions 19
References 20
Glossary of Terms 20
Appendix A 21
Appendix B 21
V
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FIGURES
Page
1. Project SHOAL Site map list of sampling locations for March 2006 2
2. Project FAULTLESS Site map list sampling locations for February 2006 5
3. Project RULISON Site map list of sampling locations for May 2006 8
4. Project RIO BLANCO Site map list of sampling locations for May 2006 11
5. Project GASBUGGY Site map list of sampling locations for July 2006 14
6. Project GNOME Site map list of sampling locations for July 2006 17
TABLES
Page
1. Analysis Results chart for Water Samples Collected at the SHOAL Site - March 2006 4
2. Analysis Results chart for Water Samples Collected at the FAULTLESS Site — February 2006 ... 7
3. Analysis Results chart for Water Samples Collected at the RULISON Site - May 2006 10
4. Analysis Results chart for Water Samples Collected at the RIO BLANCO Site - May 2006 13
5. Analysis Results chart for Water Samples Collected at the GASBUGGY Site - July 2006 16
6. Analysis Results chart for Water Samples Collected at the GNOME Site - July 2006 19
vi
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ACRONYMS AND ABBREVIATIONS
AEC U.S. Atomic Energy Commission
Bq/L Bccqucrcl per liter
CERM ER Ceiiter for Eiiviroiimeiital Restoration Monitoring and Emergency Response
CRQA Center for Radioanalysis and Quality Assurance
DCG Derived Concentration Guide (20,000 pCi/L for Tritium in Drinking Vater)
DOE U.S. Department of Energy
DIU Desert Research Institute
EPA U.S. Environineiital Protection Agency
g gram
tritiuni
3 H+ enriched tritium
HpGe high purity germanium ganima detector
lAG Interagency Agreement
ITC International Technology Corporation
Iodine-131
kcV kilo electron volts (one thousand electron volts)
kg kilogram, 1000 grams
KT kiloton (one thousand tons TNT equivalent)
L liter
LTHMP Long-Term Hydrological Monitoring Program
rn meter
MCL maximum contaminant level
M DA minimnuni detectable activity
MDC minimum detectable concentration
MeV one million electron volts
miii minute
mL milliliter (one thousandth of a liter)
MT megatomi (one million toils TNT equivalent)
ORIA Office of Radiation and Indoor Air
pCi/L picocuries per liter = 10.12 curies per liter = 1/1,000,000,000,000 curics per liter
PHS U.S. Public Health Service
REECo Reynolds Electrical & Engineering Company
R& IE Radiation and Indoor Environments National Laboratory, Las Vegas, N\’.
90 Sr Strontium-90
SGZ surface ground zero
USGS U.S. Geological Survey
‘ 31 Xe Xemion- 131
‘ 33 Xe Xemiomi-133
VI I
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ACKNOWLEDGMENTS
The external pcer review was provided by Dr. Vernon I-lodge, Ph D , Chemistry Department, University
of Nevada, Las Vegas. In addition, the author would like to acknowledge the Long Term Hydrological
Monitoring Program group members. Field sampling collection technicians included, Helly Diaz-
Marcano, Wesley Boyd, and Douglas Sharp. Laboratory personnel consists Rose (Kitty) Houston, Pat
Honsa, Dennis Farmer, also the dual roles of Dr. George A. Dilbeck, Ph.D., and Dr. Richard D. Flotard,
Ph.D., as internal reviewers. A special thanks to Mr. Max G. Davis foi- his support and insight in this
reports completion. Additional thanks goes to Natalia Brooks, Mark Ovrebo, of General Dynamics Corp,
IT contractors, for their contributions in the production of this report.
viii
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1.0 INTRODUCTION
Under an Interagency Agreement with the Department of Energy (DOE), the Radiation & Indoor
Environments National Laboratory (R&IE), Office of Radiation and Indoor Air (ORIA), EPA, Las \‘egas,
NV, conducts a Long-Term Hydrological Monitoring Program (LTI-IMP) to nieasuie radioactivity
concentrations in water sources near the sites of former undergi-ound nuclear explosions. The results of’ the
LTHMP provide assurance that radioactive materials from the tests have not migrated into dnnking water
supplies. This report presents the results for the samples collected in February, March, May, and July of
2006, around the following test site areas.
• Project SHOAL Test Site, Churchill County, Nevada
• Project FAULTLESS Test Site, Nye County, Nevada.
• Project RULISON Test Site, Garfield County, Colorado.
• Project RIO BLANCO Test Site, Rio Blanco County, Colorado.
• Project GASBUGGY Test Site, Rio Airiba County, New Mexico.
• Project GNOME Test Site, Eddy County, New Mexico.
Summary of Analytical Procedures
Type of
Analysis
Analytical Counting
Equipment Period (Miii)
Analytical
Procedures
Size of
Sample
Approximate
Detection Limit a
HpGe
Gamma b
l-lpGe detector —150
calibrated at 0.5 keV/
channel (0 04 to 2 MeV
iange) individual detecioi.
Efficiencies ianging from
15 to 35%.
Radionuclide concen-
traiion quantified fiom
gamma spectral data
by online computei
piograni
3 5 L
Varies with iadionuclides
and dctcctoi used, if
counted to a MDC of
appiox 5 pCi/I_ foi ‘ 37 Cs
si-i
Automatic liquid 300
scintillation counter
Sample prepared by
distillation.
4 inL
300 pCi/L
C
Automatic liquid 300
Eni ichment scintillation
counter
Sample concentiated
by electiolysis following
distillation
5 mL
5pCi/L
The detection limit is defined as the smallest amount of radioactivity that can be ieliably detected, i e , piobability of
b Gamma spectiometry using a high purity intrinsic geimanium (I-IpGe) detectoi.
C Sample distilled, and then concentiated to — 5 rnL by electrolysis.
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. &u J
• r L a Ioi
Figure 1. Shoal Site.
I n cds
KS -I
— _.
I
N
—I .
2
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2.0 Sample Analysis
Radiochemical laboratory procedures used to analyze the samples collected for this report are summarized in
R&IE’s SOPs (see Appendix A and B). These include standard methods to identify natural and man-made
gamma-emitting radioriuclides, tritium, plutonium, strontium, and uranium in water samples. Two types of
tritiurn analyses were performed: conventional and electrolytic enrichment. The enrichment method lowers
the MDC from approximately 300 pCi/L to 5 pCi/L. An upper limit of activity of 800 pCi/L has been
established for the tritium enrichment method because sample cross contamination in laboratoiy equipment
becomes a problem at higher levels.
It was decided by EPA, 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 and an assessment of
past results. Under the current sampling and analysis protocol for the sites, all samples are initially screened
for tritiurn activity by the conventional method, and selected samples are enriched. At this time, only
sampling locations that are in a 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 radiochemical determinations including assays for strontium, plutonium, and uranium.
2.1 Sampling at Project SHOAL, Nevada
History
Project SHOAL, a 12-KT nuclear test emplaced at 365 m (1,204 ft), was conducted on October 26, 1963, in a
sparsely populated area near Frenchman Station, Nevada, 28 miles southeast of Fallon, Nevada. The test, a
part of the Vela Uniform Program, was designed to investigate detection of a nuclear detonation in an active
earthquake zone. The working point was in granite and no surface crater was created. The effluent released
during drillback was detected onsite only and consisted of 110 curies of ‘ 31 Xe and i 33 Xe, and less than 1 0
curie of’ 31 !.
2.1.1 Sample Collection
Samples were collected on March 13-16, 2006. The sampling locations are shown in Figure 1 All of the
locations were sampled with the exception of Well H-3, the pump remains inoperable The routine sampling
locations included one spring, two windmills, and eleven wells of varying depths. At least one location, Well
HS-l, should intercept radioactivity migrating from the test cavity, if it should occur (Chapman and 1-lokett,
1991). Three new monitoring wells have now been completed and are to be added to the LTI-IMP program.
These wells are to be sampled for the first time in 2007. The placement and positionmg olthese three wells
are intended to also intercept radioactivity from the test cavity. Well HC-3 was sampled in March 2006, by
the EPA, and an additional sample was collected in July 2006, by the Desert Research Institute (DRI), Reno,
NV.
2.1.2 Water Analysis Results
Gamma-ray spectral analysis results indicated that ‘ 37 Cs was detected in Well HC-3 onsite. The reading for
‘ 37 Cs was 3.5 ± 1.7 pCi/L, with the MDC of 1.8 pCi/L. Tritium concentrations at all locations were below,
the MDC, except for Well HC-4, which had a reading of 266 ± 8.9 pCi/L enriched tritium method. This
however, is well below the safe drinking waLer standards of 20,000 pCi/L for tritium.
3
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Analysis Results for Water Samples Collected at the SHOAL Site - March 2006
TABLE 1
Sample Location Collection Enriched Tritiurn Tritium 2 Gamma Spectromctry
Date
pCi/L±2SD MDC pCi/L±2SD MDC pCi/L±2SD MDC
Hunts Station 3/14/06 32 ± 1362 (225) ND (4 8)
Flowing Spring Well 3/14/06 -18 ± I36 (225) ND (50)
Spiing Windmill
Well 3/14/06 46 ± 1372 (225) ND (48)
Well H-2 3/14/06 1.8 ± l37a (225) ND (4 9)
Well 1-1-3 No sample pump mop
Well HS-1 3/13/06 .79 ± l35a (225) ND (5.0)
Well 1-IC-I 3/14/06 -69 ± 1352 (225) ND (47)
Well HC-2 3/14/06 42 ± 138a (225) ND (4 7)
Well HC-3 3/15/06 21±61 (9.5) 3.5±17 (1.8)
Well HC-4 3/16/06 266 ± 89 (8.9) ND (5 0)
Well HC-5 3/16/06 4.2 ± I38 (225) ND (5 0)
Well HC-6 3/16/06 147 ± 141 (226) ND (5.0)
WeIIHC-7 3/16/06 5.5±5.0 (8.1) ND (4.8)
Well HC-8 3/l6/06 50 ± 1382 (225) ND (4 8)
l-IC-3 (Filter) 3/15/06 Gamma only (3 0)
(a) Indicate results are less than MDC (enriched or conventional method)
ND-Non-detected.
MDC-Minimum detectable concenti ation
2.1.3 Conclusions
No radioactive materials attributable to the SHOAL nuclear test were detected in samples collected in the
offsite areas during 2006. All samples were analyzed br the presence of gamma-ray emitting radionuclides
4
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2.2 Sampling at Project FAULTLESS, Nevada
History
Project FAULTLESS was a “calibration test” conducted on January 19, 1968, in a sparsely populated area
near Blue Jay Maintenance Station, Nevada. The test had a yield of less than 1-MT and was designed to test
the behavior of seismic waves and to determine the usefulness of the site for high-yield tests. The
emplacement depth was 975 m (3,200 ft). A surface crater was formed, but as an irregular block along local
faults rather than as a saucer-shaped depression. The area is characterized by basin and range topography,
with alluvium overlying tufaceous sediments. The working point of the test was in tuff. The groundwater
flow is generally from the highlands to the valley and through the valley to Twin Springs Ranch and Railroad
Valley (Chapman and Hokett, 1991).
2.2.1 Sample Collection
Sampling was conducted on February 13-15, 2006. Sampling locations are shown in Figure 2. It includes two
springs and seven wells of varying depths. All sampling locations were collected. The pump in Well HTH-2
has now been replaced allowing the well to be sampled this year.
At least two wells (HTH-1 and HTH-2) are positioned to intercept migration from the test cavity, should it
occur (Chapman and Hokett, 1991). Additionally, three new wells have been added to this site and were
sampled for the first time during February 2006. These wells are called Monitoring Validation Wells, MV#l,
MV#2, MV#3, and are also positioned to intercept any migration. All samples yielded negligible gamma
activity. These results were all consistent with results obtained in previous years. The consistently below-
MDC results for tritium indicate that, to date, migration into the sampled wells has not taken place and no
event-related radioactivity has entered area of drinking water supplies.
2.2.2 Water Analysis Results
All gamma-ray spectral analysis results indicated that no man-made gamma-ray emitting radionuclides wei c
present above MDC. Tritium concentrations at all the locations were below the MDC, well below 20,000
pCi/L safe drinking water standard (see Table 2, page 7).
6
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Analysis Results for Water Samples Collected at the FAULTLESS Site - February 2006
TABLE 2
Sample Location Collection Enriched Tritium Tiitiurn Gamma Spectrometiy
Date pCi/L ±2 SD MDC pCi/L ±2 SD MDC pCi/L MDC
Hot Creek Ranch 2/15/06 69 ± 166° (271) ND (4 9)
Blue Jay Springs 2/15/06 -21 ± 164’ (271) ND (42)
Blue Jay
Maintenance Station 2/13/06 52 ± 166° (271) ND (4 9)
\VeIIHTH-l 2/14/06 -l g 59a (9.8) ND (49)
Well l-ITI-l-2 2/14/06 -3.6 ± 4 0° (6 8) ND (4 6)
Site C Base Caii p 2/15/06 -5.5 ± 163° (271) ND (4.9)
SixMile Well 2/15/06 74 ±166 (271) ND (50)
Tybo Well 2/15/06 -3.9 ± 165 (271) ND (5 0)
Twm Springs Ranch 2/13/06 24 ± I65 (271) ND (5 0)
MV-#1 Well 2/14/06 -1.3±41° (6.9) ND (18)
MV- #2 Well 2/14/06 -3.5 ± 5.3° (8 8) ND (1.6)
MV-#3 Well 2/14/06 3.4 ± 5.9° (9.8) ND (1.9)
(a) Indicate results are less than MDC (enriched or conventional method).
ND-Non-detected
MDC- Minimum detectable concentration.
2.2.3 Conclusions
Tritiurn concentrations in water samples collected onsite and offsite are consistent with those of past studies
at the FAULTLESS site. No radioactive materials attributable to the FAULTLESS test were detected in
samples collected in the offsite areas during 2006. All samples were analyzed for the presence of gamma-ray
emitting radionuclides.
7
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2.3 Sampling at Project RULISON, Colorado
History
Co-sponsored by the U.S. Atomic Energy Commission (AEC) and Australia Oil Company under the
Plowshare Program, Project RULISON was designed to stimulate natural gas recovery in the Mesa Verde
formation. The test, conducted near Grand Valley, Colorado, on September 10, 1969, consisted of a 40-KT
nuclear explosive emplaced at a depth of 2,568 m (8,425 ft). Production testing began in 1970 and was
completed in April 1971. Cleanup was initiated in 1972, and the wells were plugged in 1976. Some surfacc
contamination resulted from decontamination of drilling equipment and fallout from gas flaring.
Contaminated soil was removed during the cleanup operations including one test well and two surface-
discharge springs.
2.3.1 Sample Collection
Sampling was conducted on May 10, 2006, from all sampling locations at Grand Valley and Rulison,
Colorado. Routine sampling locations are shown in Figure 3. Sampling included the Grand Valley municipal
drinking water supply springs, water supply wells for six local ranches, and two sites in the vicinity of
surface ground zero (SGZ), including one test well and two surface-discharge springs.
2.3.2 Water Analysis Results
Tritium has never been observed in measurable concentrations in the Grand Valley City Springs. All of the
remaining sampling sites show detectable levels of tritium, which have generally exhibited a stable or
decreasing trend over the last two decades. The range of tritium activity in 2006, was from 13 ± 5 pCi/L at
Spring 300yds North of GZ, to 27 ± 5 pCiIL, at the Potter Ranch (see Table 3). All eni ched values were less
than 0.14 percent of the DCG (20,000 pCifL). The detectable tritium activities are consistent with values
found in current precipitation and, perhaps, a small residual component remaining from clean-up activities at
the site. This is supported by Desert Research Institute (DRI) analysis, which indicates that most oIthe
sampling locations at the RULISON site are shallow, drawing water from the surficial aquifer, and therefore,
unlikely to become contaminated by radionuclide migration from the Project RULISON cavity, (Chapman
and Hokett, 1991), (see Table 3, page 10).
9
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Sample Location
Battlement Cieek
City Springs
Daniel Gardnei
CER Test Well
Pan ick McCarty
Pottei Ranch
Moritsana Oichaid
l’im Jacobs
Spiing 300yds N.
of Giound Zero
Spiing 50011. E. of
Ground Zeio
5/10/06
5/10/06
5/10/06
5/10/06
5/10/06
5/10/06
5/10/06
5/10/06
5/10/06 13±48
5/10/06
Trit iunf
pCi/L± 2 SD
94 ± 147’
94 ± 147’
89± 147’
74± 147’
69± 147’
15± 147’
Gamma Spectiomeny
MDC pCi/L±2SD MDC
ND (49)
(239) ND (4 3)
(239) ND (5 0)
(239) ND (3 7)
(239) ND (4 8)
ND (50)
ND (IS)
ND (20)
ND
(239) ND
(48)
(4 8)
(239) ND (4.9)
2.3.3 Coiiclusioiis
Tritium concentrations in water samples collected onsite and offsite are consistent with those of past studies
at the RULISON Test Site. In general, the current level of tritium in shallow wells at the RULISON site
cannot be distinguished from the rain-out of naturally produced tritium augmented by, pei haps, a small
amount of residual global “fallout tritium” remaining from nuclear testing in the 1950s and l960s. No
radioactive materials attributable to the Rulison test were detected in samples collected in the offsite areas
Analysis Results for Water Samples Collected at the RULISON Site - May 2006
TABLE 3
Collection Enriched Tritium
Date
pCi/L±2SD MDC
26±5.2 (79)
27 ± 4.8
(79)
(7.7)
(239)
(239)
15±147’
K. Whelan Ranch 5/10/06 14 ± 147a
(a) Indicate iesults are less than MDC (enriched or conventional method)
ND. Non-detected.
MDC- Minimum detectable concentration.
10
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p. *i - o
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Figure 4. Rio Blaiico Site.
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2.4 Sampling at Project RIO BLANCO, Colorado
History
Project RIO BLANCO, a joint government-industry test designed to stimulate natural gas flow, was
conducted under the Plowshare Program. The test was conducted on May 17, 1973, at a location between
Rifle and Meeker, Colorado. Three explosives with a total yield of 99-KT were emplaced at 1,780, 1,920,
and 2,040 m (5,840, 6,299, and 6,693 Oft) depths in the Ft. Union and Mesa Verde formations. Production
testing continued until 1976, when cleanup and restoration activities were completed. Tritiated water
produced during testing was injected to 1,710 m (5,610 ft) in a nearby gas well.
2.4.1 Sample Collection
Sampling was conducted on May 11-12, 2006, and locations are shown in Figure 4. The routine sampling
locations included four springs, four surface, and five wells, three of which are located near the cavity. At
least two of the wells (Wells RB-D-01 and RB-D-03) are suitable for monitoring because they were down
gradient and would indicate possible migration of radioactivity from the cavity.
2.4.2 Water Analysis Results
Gamma-ray spectral analysis results indicated that no man-made gamma-ray emitting radionuclides were
present in any offsite samples. (see table 4, page 14).
12
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Analysis Results for Water Samples Collected at the RIO BLANCO Site - May 2006
TABLE 4
Sample Location Collection Enriched Tritium Tritium° Gamma Spectrometry
Date
pCiIL ±2 SD MDC pCiIL ±2 SD MDC pCi/L ±2 SD MDC
B-i Equity Camp 5/12/06 51 ± 133 (218) ND (4.9)
Brennan Windmill 5/12/06 20± 133’ (218) ND (4.8)
CER#1 Black 5/12/06 51 ± 133’ (218) ND (4.0)
Sulphur
CER#4 Black 5/12/06 125± l34a (218) ND (4.8)
Sulphur
FawnCreek#i 5/11/06 17± 132a (218) ND (4.9)
FawnCreek#3 5/1 1/06 6.8± l32 (218) ND (5.0)
Fawn Creek 500’ 5/11/06 78 ± 133 a (218) ND (4.7)
Upstream
Fawn Creek 6800’ 5/11/06 34± 131 a (218) ND (5.0)
Upstream
Fawn Creek 500’ 5/11/06 41k 133 a (218) ND (4.7)
Downstream
Fawn Creek 8400’ 5/11/06 -54 ± 131 a (218) ND (4.9)
Downstieam
Johnson Artesian 5/1 1/06 130± 133 (213) ND (4.7)
Well
Well RB-D-Ol 5/11/06 -4.8 ± 4.6a (7.7) ND (4.9)
Well RB-D-03 5/12/06 195 ± 133 a (217) ND (4.8)
Well RB-S-03 5/11/06 -3.1 ±5.5” (9.2) ND (5.0)
Well RB-W-Ol 5/12/06 3.9 ± 43a (9.2) ND (4 9)
(a) indicate results are less than MDC (enriched or conventional method).
ND-Non-detected.
MDC-Minimum detectable concentration.
2.4.3 Conclusions
Tritium concentrations in water samples collected onsite and offsite are consistent with those of past studies
at the RIO BLANCO Site. No radioactive materials attributable to the RIO BLANCO test were detected in
samples collected in the offsite areas during May 2006. All samples were analyzed for presence of gamma-
ray emitting radionuclides.
13
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Wbid UI 2
o ab* otn1 Z.ro ___
• Sr II LOCN
l igurc 5. Gasbuggy Site.
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14
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2.5 Sampling at Project GASBUGGY, New Mexico
History
Project GASBUGGY was a Plowshare Program test co-sponsored by the U.S. AEC and El Paso Natural Gas
Co., conducted near Gobernador, New Mexico, on December 10, 1967. A nuclear explosive with a 29-KT
yield was detonated at a depth of 1,290 m (4,240 fi) to stimulate a low productivity natural gas reservoir.
Production testing was completed in 1976 and restoration activities were completed in July 1978.
The pnncipal aquifers near the test site are the Ojo Alamo Sandstone, an aquifer containing non-potable
water located above the test cavity, and the San Jose formation and Nacimiento formation Both surficial
aquifers contain potable water. The flow regime of the San Juan Basin is not well known, although it is likely
that the Ojo Alamo Sandstone discharges to the San Juan River 50 miles northwest of the Gasbuggy site.
Hydrologic gradients in the vicinity are downward, but upward gas migration is possible (Chapman and
Hokett, 1991).
2.5.1 Sample Collection
Annual sampling at Project GASBUGGY was completed during July 12-14, 2006. All of the routine
sampling locations were collected including Bubbling Springs which yielded enough for ti-itiuni results,
(see Figure 5). Well EPNG-l0-36 which was plugged in 2003 has been removed from the sampling plan.
2.5.2 Water Analysis Results
l’ritiurn concentrations of water samples collected onsite and offsite ai-e consistent with those of past studies
at the GASBUGGY Site. Prior to Well EPNG 10-36 it had yielded tritium activities between 100 and 560
pCi/L in each year since 1984, except in 1987. The sample collected in June 2003, yielded a tritium activity
of .005 ± 4 pCi/L. The migration mechanism and route are not currently known, although an analysis by
Desert Research Institute indicated two feasible routes. One through the Printed Cliffs sandstones, and the
other one through the Ojo Alamo sandstone, one of the principal aquifers in the region, (Chapman and
Hokett, 1991) In either case, fractures extending from the cavity may be the primary or a contributing
mechanism. The proximity of the vell to the test cavity suggests the possibility that the activity increases
may indicate migration from the test cavity; however, in 2003 the well was plugged, due to severe
deterioration. DOE will drill several wells in the near futuie, placed in strategic locations designed to
intercept migration of radionuclides, if they occur.
Gamma-ray spectral analysis results indicated that no man-made gamma-ray emitting radionuclides were
present in any onsite and offsite samples above the MDC. Tritium concentrations at all locations except foi
one were below the MDC. The only sampling location that had a tritiurn concentration above the MDC was
Well 28.3.33.233.South which had a reading of 10 ± 4.3 pCi/L (see Table 5, page 16)
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Analysis Results for Water Samples Collected at the GASBUGGY Site - July 2006
TABLE 5
Sample Collection Enriched Tritium Tritium Gamma Spectrometry
Location Date
pCiIL ±2 SD MDC pCiIL ± 25D MDC pCi/L ±2 SD MDC
Arnold Ranch
Spring 7/12/06 1.9± 4.6 (7.5) ND (4.9)
Bubbling Springs 7/14/06 58 ± 1470 (240) ND (4.9)
Cave Springs 7/12/06 . 116 ± 148 (240) ND (4.9)
Cedar Springs 7/12/06 58 ± 1472 (240) ND (4.8)
La Jam Creek 7/12/06 53 ± 1470 (240) ND (4.9)
Lower Burro 0 ± 146 (240) ND (5.0)
Canyon 7/12/06
Pond N. of Well 7/13/06 24 ± 1460 (240) ND (49)
30.3.32.343
Jicarilla Well 1 7/13/06 6.0 ± 4.60 (7.3) ND (5.0)
Well 28.3.33.233 7/12/Ô6
South 10 ± 4.3 (6.7) ND (4.7)
Well 30.3.32.343 7/13/06
North 24 ± 145 (240) ND (1.9)
Windmill #2 7/12/06 24 ± 1462 (240) ND (48)
Arnold Ranch Well 7/12/06 19 ± 146 2 ND (5.0)
(a) Indicate results are less than MDC (enriched or conventional method).
ND Non-detected.
MDC Minimum delectable concentration.
‘2.5.3 Conclusions
Tritium concentrations of water samples collected onsite and offsite are consistent with those of past studies
at the GASBUGGY Site. No radioactive materials attributable to the Gasbuggy test were detected in samples
collected in the offsite areas during July 2006.
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• 8ur s and Zo
• V O&mØ ig Loo ins
PH$ $
P148 W e
U
4
N
oY
Figure 6. Gnome Site.
LOC N P
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2.6 Sampling at Project GNOME, New Mexico
History
Project GNOME, conducted on December 10, 1961, near Carlsbad, New Mexico, was a multipurpose test
emplaced at a depth of 370 m (1,216 ft) in the Salado salt formation. The explosive yield was slightly-more-
than 3-KT. Oil and gas are produced from the geologic units below the working point. The overlying Rustler
formation contains three water-bearing zones: brine located at the boundary of the Rustler and Salado
formations, the Culebra Dolomite which is used for domestic and stock supplies, and the Magenta Dolomite
which is above the zone of saturation (Chapman and Hokett, 1991). The ground water flow is generally to
the west and southwest.
Radioactive gases were accidentally vented following the test. In 1963, USGS conducted a tracer study
involving injection of 20 Ci tritium, 10 Ci ‘ 37 Cs, 10 Ci 90 Sr, and 4 Ci 1311 in the Culebra Dolomite zone using
Wells USGS 4 and 8. During remediation activities in 1968-69, contaminated material was placed in the test
cavity and the shaft up to within 7 ft of the surface. Moi-e material was slurried into the cavity and diifts in
1979. A potential exists for discharge of this slurry to the Culebra DoloI!mte and to Rustler-Salado brine.
Potentially, this may increase as the salt around the cavity compresses, forcing contamination upward and
distorting and cracking the concrete stem and grout.
2.6.1 Sample Collection
Annual sampling at Project GNOME was completed during July 18-19, 2006. The routine sampling sites,
depicted in Figure 6, include ten monitoring wells in the vicinity of surface GZ and the municipal supplies at
Loving and Carlsbad, New Mexico.
2.6.2 Water Analysis Results
No tritium activity was detected in the Carlsbad municipal supply or the Loving Station well. An analysis by
Desert Research Institute (Chapman and Hokett, 1991) indicates that these sampling locations, which aic on
the opposite side of the Pecos River from the Project GNOME site, are not connected hydrologically to the
site and, therefore, cannot become contaminated by Project GNOME radioriuclides.
Tritiurn activity greater than the MDC was detected in a water sample from one of the 10 sampling locations
in the immediate vicinity of GZ. The highest tritium concentration found onsite was 2.4 xIO 4 pCi/L in Well
USGS# 4. Offsite Well PHS#6 results were 17 ± 5.7 pCi/L with MDC 9.0 pCi/L. Well DD-#l, collects water
from the test cavity; Well LRL-#7 collects water from a side drift; and Wells USGS-#4 and USGS-#8 were
used in the radionuclide tracer study conducted by the USGS. None of these wells are sources of potable
water and only, Well USGS#4 was sampled 2006, the remaining three were not at the recommendation of
DOE.
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Analysis Results for Water Samples Collected at the GNOME Site - July 2006
TABLE 6
Sample Location Collection Enriched Tritiurn Tritium Gamma Spectrometry
Date
pCi/L±2SD MDC pCi/L±2SD MDC pCiJL±2SD MDC
Cailsbad City #7 7/18/06 3.3 ± 4.3 (7 0) ND (5 0)
Loving City #7 7/18/06 78 ± 148 (242) ND (4 1)
PHS6 7/18/06 17 ± 5.7 (9.0) ND (46)
PHS 8 7/18/06 39 ± 147 (242) ND (4.6)
PHS 9 7/18/06 53 ± 148 (242) ND (4.9)
PHS 10 7/18/06 -9.7 ± 146 (242) ND (4.9)
USGS Well #1 7/19/06 92 ± 149 (242) ND (4 8)
USGS Well #4 7/19/06 24,300 ± 423 (242) ND (1 9)
USGS Well #8 Not Sampled 06
J. Mobley Ranch 7/19/06 4.3 ± 5.1 ‘ (8.2) ND (50)
Well DD-#1 Not Sampled 06
Well LRL-#7 Not Sampled 06
(a) Indicate results are less than MDC (enriched or conventional method).
ND- Non-detected
MDC- Minimum detectable concentration.
Note: The above sampling locations UGSG#8, Well LRL-#7, Well DD-#l were not collected per tequest of DOE
2.6.3 Conclusion
Tritium concentrations of water samples collected onsite and offsite are consistent with those of past studies
at the Gnome Site. No radioactive materials attributable to the Gnome test were detected in samples collected
in the olfsite areas during July 2006.
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REFERENCES
Chapman & Hockett, 1991. Evaluation of Groundwater Monitoring at 0ff3 vie Nuclear Test Ai eas, Las Vegas, NV,
Desert Reseaich Institute, University of Nevada System, Report DOEINVI 10845-07
Final iule on Dec 7, 2000. Code of Federal Regulations, Vol 65, Title 40, Paris 9, 141, and 142, Decembci 7, 2000,
National Pruua,y Dunking Water Regulaizom, Radionuclides, Final Rule, (40CFR911411142).
A Guide for Enviromnental Radiological Surveillance at US Dept of Energy lu, tallauons, July /98 1, Office of
Operational Safety Report Las Vegas, NV U S Depai tment of Energy, DOE/EP-0023
Johns, F , et al 1979. Radioclzeunical and Analytical Procedu e.s fou Analysis of En viro,une,,ial Sainple.s. Las Vegas,
NV: U.S. Enviionmental Protection Agency; EMSL-LV-0539- 17-1979
Off3u ’e Environmental Monitoring Report Radial loll Monitoring ,4, ouizd Nude 1 ’ , , Test Areas, Calendai Vea’ /992 El’A
600/R-94/209.
GLOSSARY OF TERMS
Background Radiation
The radiation in man’s environment, including cosmic iays and iadiation from naturally-occurring and man-made
radioactive elements, both outside and inside the bodies of humans and animals. The usually quoted aveiage individual
exposuie fiorn backgiound radiation is 125 milliiem per yeai in mid-latitudes at sea level
Curie (Ci)
The basic unit used to describe the rate of radioactive disintegration. The curie is equal to 37 billion disintegiations pei
second, which is the equivalent of I gram of iadium Named foi Marie and Pierre Cuiie who discoveied iadium in
1898. One microcurie ( pCi) isO 000001 Ci
isotope
Atoms of the same element with diffetent numbers of neutions in the nuclei Thus 12 C, ‘ 3 C, and ‘ 4 C aie isotopes of the
element caibon, the iiumbers denoting the appioximate atomic ‘eights Isotopes have very neai ly the same chemical
properties, but have diffeient physical pioperties (fbi example ‘ 2 C and ‘ 3 C are stable, ‘ 4 C is radioactive).
Enrichment Method
A method of electrolytic concentration that incieases the sensitivity of the analysis of ti itium in watei This method is
used for selected samples if the tritium concentiation is less than 800 pCi/L
Minimu in Detectable Concentration (MDC)
The smallest amount of radioactivity that can be ieliably detected with a probability of Type I and Type It etrois at 5
percent each (DOE 1981).
Offsite
Arcas exclusive of the immediate Test Site Area
Type I Error
The statistical erior of accepting the presence of iadioactivity when none is piesent Sometimes called alpha erioi
Type II Error
The statistical erior of failing to recognize the presence of radioactivity when it is piesent Sometimes called beta ciioi
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Appendix A
Typical MDC Values for Gamma Spectroscopy
(100 minute count time)
Geometry* Marinelli Model 430G
Matrix Water Density 1 .0 g/ml
Volume 3.5 liter Units pCi/L
Isotope MDC Isotope MDC
Ru-106 4.76E+Ol
Be-7 4.56E+01 Sn-I 13 8.32E+00
K-40 4.92E+0l Sb-125 1.65E-I-Ol
Cr-51 5.88E+01 1-131 8.28E+00
Mn-54 4.55E+Ol Ba-133 9.16E+00
Co-57 9.65E+00 Cs-134 6.12E+00
Co-58 4.71E+00 Cs- 137 6.43E+00
Fe-59 l.07E+O1 Ce-l44 7.59E+0l
Co-60 5 38E+00 Eu-152 2.86E-1-0l
Zn-65 l.24E+0l Ra-226 1 58E+01
Nb-95 5.64E+00 U-235 L O IE+02
Zr-95 9.06E+00 Am-24 1 6.60E+O 1
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 *Gei.n .ianiuin 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 othei
type of detector. All gamma spectroscopy MDA may vary with different types of shielding,
geometries, counting times and decay time of sample
Appendix B
Standard Operating Procedures for the Center for Environmental Restoration, Monitoring &
Emergency Response
CER-203 Standard Operating Procedure for the Long-Term Hydrological Monitoring l’rogram
Standard Operating Procedures for the Center for Radioanalysis & Quality Assurance
RQA-302 Standard Operating Procedures of Gamma-Ray Detector Systems.
RQA-602 Tritium Enrichment Procedure.
RQA-603 Standard Operating Procedure for 89 Sr and 90 Sr 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.
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