Annual Water Sampling and
Analysis, Calendar Year 2007
FAULTLESS Test Site Area
SHOAL 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-AI01-07LM00095
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-AI01-07LM00095 from the United
States Department of Energy (DOE)-National Energy Technology Laboratory and Office of Legacy
Management. This supersedes Agreement No. DE-AI0896NV11969, from the United States Department of
Energy (DOE). The EPA (IAG) identification number RW-89-92243501-0 is a continuation of EPA-
Reference RW89-937611-01. 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 Environments National Laboratory in
Las Vegas, Nevada (R&LE), 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 Hydrological Monitoring Program (LTKMP). 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 dunng 2007: 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 2007 are consistent with results from previous years. No increase was seen in
either tritium concentrations or gamma-ray emitting radionuclides at any site. Tntium 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 (4OCFR9/1411142), 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-#1, were all sampled this year.
Negative values for tritium
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 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 Ready Safe
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 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 are now using EcoLume liquid
scintillation cocktail.
All samples were also analyzed for the presence of gamma-ray emitting radionuclides. None were
detected above minimum detectable concentration (MDC) see Appendix B, page 21.
iii
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iv
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CONTENTS
Page
Notice .11
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 FAULTLESS, 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 SHOAL, Nevada 6
2.2.1 Sample Collection 6
2.2.2 Water Analysis Results 6
2.2.3 Conclusions 7
2.3 Sampling at Project RULISON, Colorado 9
2.3.1 Sample Collection 9
2.3.2 Water Analysis Results 9
2.3.3 Conclusions 10
2.4 Sampling at Project I .IO BL t1’ CO, Colorado 12
2.4.1 Sample Collection 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 GNOME, 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 FAULTLESS Site map list sanipling locations for February 2007 2
2. Project SHOAL Site map list of sampling locations for March 2007 5
3. Project RULISON Site map list of sampling locations for May 2007 8
4. Project RIO BLANCO Site map list of sampling locations for May 2007 11
5. Project GASBUGGY Site map list of sampliiig locations for June 2007 14
6. Project GNOME Site map list of sampling locations for June 2007 17
TABLES
Page
1. Analysis Results chart for Water Samples Collected at the FAULTLESS Site — February 2007... 4
2. Analysis Results chart for Water Samples Collected at the SHOAL Site - March 2007 7
3. Analysis Results chart for Water Samples Collected at the RULISON Site - May 2007 10
4. Analysis Results chart for Water Samples Collected at the RIO BLANCO Site - May 2007 13
5. Analysis Results chart for Water Samples Collected at the GASBUGGY Site - June 2007 16
6. Analysis Results chart for Water Samples Collected at the GNOME Site-June 2007.................. 19
vi
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ACRONYMS AND ABBREVIATIONS
AEC U.S. Atomic Energy Commission
BqIL Becquerel per liter
CERMER Center for Environmental Restoration Monitoring and Emergency Response
CRQA Center for Radioanalysis and Quality Assurance
DCC Derived Concentration Guide (20,000 pCi/L for Tritium in Drinking Water)
DOE U.S. Department of Energy
DRI Desert Research Institute
EPA U.S. Environmental Protection Agency
g gram
3 H tritium
3 H+ enriched tritium
HpGe high purity germanium gamma detector
lAG Interagency Agreement
ITC International Technology Corporation
Iodine-131
keY kilo electron volts (one thousand electron volts)
kg kilogram, 1000 grams
KT kiloton (one thousand tons TNT equivalent)
L liter
LTJ{MP Long-Term Hydrological Monitoring Program
m meter
MCL maximum contaminant level
MDA minimum detectable activity
MDC minimum detectable concentration
MeV one million electron volts
mm minute
mL milliliter (one thousandth of a liter)
MT megaton (one million tons TNT equivalent)
O1UA Office of Radiation and Indoor Air
pCiJL picocuries per liter = 10 2 curies per liter = 1/1,000,000,000,000 curies per liter
PHS U.S. Public Health Service
REECo Reynolds Electrical & Engineering Company
R&1E Radiation and Indoor Environments National Laboratory, Las Vegas, NV.
90 Sr Strontium-90
SGZ surface ground zero
USGS U.S. Geological Survey
‘ 31 Xe Xenon-131
‘ 33 Xe Xenon-133
vii
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ACKNOWLEDGMENTS
The external peer review was provided by Dr. Vernon Hodge, 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, Wesley Boyd,
Douglas Sharp and Gary Spradlin. Field /Laboratory personnel consists Rose (Kitty) Houston, Beth
Domowicz, Pat Honsa, Dennis Farmer, Dr. Malek Chatila, Ph.D., and also the dual roles of Dr. George A.
Dilbeck, Ph.D., and Dr. Richard D. Flotard, Ph.D., as internal reviewers. Additional thanks goes to Steve
McLemore, 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 Vegas,
NV, conducts a Long-Term Hydrological Monitoring Program (LTHMP) to measure radioactivity
concentrations in water sources near the sites of former underground nuclear explosions. The results of the
LTHMP provide assurance that radioactive materials from the tests have not migrated into drinking water
supplies. This report presents the results for the samples collected in February, March, May, and July of
2007, around the following test site areas:
• Project FAULTLESS Test Site, Nye County, Nevada.
• Project SHOAL Test Site, Churchill County, Nevada.
• Project RULISON Test Site, Garfield County, Colorado.
• Project RIO BLANCO Test Site, Rio Blanco County, Colorado.
• Project GASBUGGY Test Site, Rio Arriba County, New Mexico.
• Project GNOME Test Site, Eddy County, New Mexico.
Summary of Analytical Procedures
Type of
Analysis
Analytical Counting
Equipment Period (Mm)
Analytical
Procedures
Size of
Sample
Approximate
Detection Limit a
HpGe
Gamma b
HpGe detector —150
calibrated at 0.5 keV/
channel (0.04 to 2 MeV
range) individual detector.
Efficiencies ranging from
15 to 35%.
Radionuclide concen-
tration quantified from
gamma spectral data
by online computer
program.
3.5 L
Varies with radionuclides
and detector used, if
counted to a MDC of
approx. 5 pC1JL for ‘ 37 Cs.
3 H
Automatic liquid 300
scintillation counter.
Sample prepared by
distillation.
4 mL
300 pCi/L
Automatic liquid 300
Enrichment scintillation
counter.
Sample concentrated
by electrolysis following
distillation.
5 n iL
7.5 pCi/L
‘The detection limit is defined as the smallest amount of radioactivity that can be reliably detected.
b Gamma spec trometry using a high purity intrinsic germanium (HpGe) detector.
C Sample distilled, and then concentrated to —5 niL by electrolysis.
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2.0 Sample Analysis
Radiochemical laboratory procedures used to analyze the samples collected for this report are summarized in
R&1E’s SOPs (see Appendix A and B). These include standard methods to identify natural and man-made
gamma-emitting radionuclides, tritium, isotopic plutonium, strontium, and isotopic uranium in water
samples. Two types of tritium analyses were performed: conventional and electrolytic enrichment. The
enrichment method lowers the MDC from approximately 300 pCiIL to 5 pCifL. An upper limit of activity of
800 pCiIL has been established for the tritium enrichment method because sample cross contamination in
laboratory 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 tritium 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 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).
2.1,1 Sample Collection
Sampling was conducted on February 20-22, 2007. Sampling locations are shown in Figure 1. It includes two
springs and seven wells of varying depths. All sampling locations were collected. At least two wells (HTH-l
and HTH-2) are positioned to intercept migration from the test cavity, should it occur (Chapman and Hokett,
1991). Three wells called Monitoring Validation Wells, MV#l, MV#2, and MV#3, are positioned to
intercept any migration these were first sampled February 2006. MV#l well was not sampled this year do to
pumping problems. All remaining samples yielded negligible gamma activity. These results were all
consistent with results obtained in the previous year. 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 into any area of drinking water supplies.
2.1.2 Water Analysis Results
All gamma-ray spectral analysis results indicated that no man-made gamma-ray emitting radionuclides were
present above MDC. Tritium concentrations at all the locations were below the MDC, well below 20,000
pCifL safe drinking water standard (see Table 1, page 4).
3
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Analysis Results for Water Samples Collected at the FAULTLESS Site - February 2007
TABLE 1
Sample Location Collection Enriched Tritium Tritium Gamma Spectrometry
Date pCi/L ±2 SD MDC pCiIL ±2 SD MDC pCi/L MDC
Hot Creek Ranch 2/21/07 -40± 1780 (296) ND (4.9)
Blue Jay Springs 2/22/07 -40± 1780 (296) ND (5.0)
Blue Jay
Maintenance Station 2/20/07 20 ± 1800 (296) ND (4.9)
Well HTH-l 2/21/07 -58± 178° (296) ND (4.8)
Well HTH-2 2/22/07 -74 ± 6.40 (10) ND (4.8)
Site CBase Camp 2/22/07 -40± 1780 (296) ND (5.0)
Six Mile Well 2/20/07 2.0± 1790 (271) ND (49)
Twin Springs Ranch 2/20/07 26 ± 1800 (296) ND (4.9)
MV- #1 Well 2/22/07 ND Pump
mop
MV-#2 Well 2/22/07 1.53±5.70 (9.3) ND (4.9)
MV-#3 Well 2/22/07 -58± 178° (296) ND (1.9)
(a) Indicate results are less than MDC (enriched or conventional method).
ND-Non-detected.
MDC- Minimum detectable concentration.
2.1.3 Conclusions
Tritium 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 dunng 2007. All samples were also analyzed for the presence of
gamma-ray emitting radionuclides.
4
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Figure 2. Shoal Site.
5
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2.2 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 dnllback was detected onsite only and consisted of 110 cunes of i 3 iXe and ‘ 33 Xe, and less than 1.0
curie of 1311.
2.2.1 Sample Collection
Samples were collected on March 20-22, 2007. The sampling locations are shown in Figure 2. 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. Spring windmill well was
not sampled this year do to access difficulties. Gamma spectral analysis results indicated a very minor
concentration of’ 31 Cs was detected in Well HC-3 onsite. The reading for was I .8 ± I. 3 with the MDC of
1.3 pCi/L. At least one location, Well HS-l, should intercept radioactivity migrating from the test cavity, if it
should occur (Chapman and Hokett, 1991). Three new monitoring wells have now been completed and are to
be added to the LTHMP program. These wells were sampled for the first time in 2007. The placement and
positioning of these three new additional wells are intended to also intercept radioactivity from the test
cavity.
2.2.2 Water Analysis Results
All gamma-ray spectral analysis results indicated that no man-made gamma-ray emitting radionuclides were
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 SHOAL Site - March 2007
TABLE 2
Sample Location Collection Enriched Tntium Tritium° Gamma Spectrometry
Date
pCiIL ±2 SD MDC pCi/L ±2 SD MDC pCi/L ±2 SD MDC
Hunts Station 3/20/07 178 ± 179° (288) ND (5.0)
Flowing Spring Well 3/20/07 -17 ± 174° (280) ND (4.0)
Spring Windmill Not
Well 3/22/07 sampled
Well H-2 3/20/07 142 ± 178° (288) ND (47)
Well H-3 No sample, well down
pump mop.
Well HS-l 3/22/07 No sample, no access
perimeter gate locked
Well HC-l 3/21/07 -1.5 ± 5.2° (8.7) ND (5.0)
Well HC-2 3/20/07 35 ± 174° (288) ND (5.0)
Well HC-3 3/22/07 -89± 173° (288) ND (1.3)
Well HC-4 3/21/07 -17± 174° (288) ND (3.7)
Well HC-5 3/22/07 -2.7 ± 4.5° (7.5) ND (4.7)
Well HC-6 3/21/07 29 ± 178a (288) ND (4.5)
Well HC-7 3/21/07 -2.4 ± 174° (288) ND (3.5)
Well HC-8 3/21/07 23 ± 175° (288) ND (45)
PSA Monitoring
Well #1 3/21/07 65± 176° (280) ND (1.4)
PSA Monitoring
Well #2 3/21/07 41 ± 176° (288) ND (2.0)
PSA Monitoring
Well #3 3/21/07 -17± 174° (288) ND (2.0)
HC-3 (Filter) 3/22/07 Gamma only (1.6)
(a) Indicate results are less than MDC (enriched or conventional method).
ND-Non-detected.
MDC-Minimum detectable concentration.
2.2.3 Conclusions
No radioactive materials attributable to the SHOAL nuclear test were detected in samples collected in the
offsite areas during 2007. All samples were also analyzed for the presence of gamma-ray emitting
radionuclides.
7
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Figure 3. Rulison Site.
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8
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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 surface
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 16, 2007, 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 2007, was from 18 ± 5.6 pCi/L
at Spring 500 ft. E. of(SGZ) 40 ± 7.6 pCi/L at Jablonski Morrisana Orchard (see Table 3). All enriched
values were less than 0.2 percent of the DCG (20,000 pCi/L). 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
of the 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, Table 3, page 10).
9
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Analysis Results for Water Samples Collected at the RULISON Site - May 2007
TABLE 3
Sample Location Collection Enriched Tritium Tritium’ Ganuna Spectrometry
Date
pCi/L ± 2 SD MDC pCifL ±2 SD MDC pCIIL ±2 SD MDC
Battlement Creek 5/16/07 42 ± 169’ (278) ND (4.3)
City Springs 5/16/07 21 ± 169’ (278) ND (4.3)
Daniel Gardner 5/16/07 51 ± 170° (278) ND (4.9)
CER Test Well 5/16/07 31±8.7 (13) ND (4.9)
Patrick McCarty 5/16/07 140± 171° (278) ND (4.7)
Potter Ranch 5/16/07 -12± 169° (278) ND (4.8)
MorrisanaOrch. 5/16/07 40± 7.6 (1.1) ND (1.5)
Tim Jacobs 5/16/07 8.5 * 169’ (278) ND (1.3)
Spring 30 0yds N. 00± 168’ ‘278
of Ground Zero 5/16/07 ‘ ND (4.9)
GroundZero 5/16/07 18±5.6 (8.8) ND (5.0)
K. Whelan Ranch 5/16/07 29 ± 169’ (278) ND (4.6)
(a) Indicate results are less than MDC (enriched or conventional method).
ND- Non-detected.
MDC- Minimum detectable concentration.
2.3.3 Conclusions
Tritium concentrations in water samples collected onsite and olfsite 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, perhaps, 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
during 2007. All routine samples were analyzed for presence of gamma-ray emitting radionuclides.
10
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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 ft) 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 17-18, 2007, 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-0l 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
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 2007 is from -1.4 ± 5.3 pCi/L at
Well RB-D-0l to 11 ± 5.7 pCi/L at Fawn reek 8400 ft. (Downstream) location which was the only sampling
location that had a tritium concentration above the MDC (See Table 4, page 13). 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.
12
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Analysis Results for Water Samples Collected at the RIO BLANCO Site - May 2007
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 5/18/07 149± 169° (274) ND (4.4)
Brennan Windmill 5/17/07 3.3 ± 6.2° (10) ND (4.6)
CER#l Black
Sulphur 5/18/07 166± 169° (274) ND (4.9)
CER #4 Black
Sulphur 5/18/07 72 ± 168° (274) ND (4.7)
Fawn Creek #1 5/17/07 4.2 ± 166° (274) ND (5.0)
Fawn Creek #3 5/17/07 -34± 166° (274) ND (4.9)
Fawn Creek 500’
Upstream 5/17/07 -55 ± 165° (274) ND (4.4)
Fawn Creek 6800’
Upstream 5/17/07 -80 ± 168° (274) ND (4.9)
Fawn Creek 500’
Downstream 5/17/07 -12 ± 166° (274) ND (4.4)
Fawn Creek 8400’
Downstream 5/18/07 l1 5.7 (9.1) ND (4.5)
Johnson Artesian
Well 5/17/07 157± 169° (274) ND (5.0)
Well RB-D-01 5/17/07 -1.4 ± 5.3° (8.9) ND (5.0)
Well RB-D-03 5/18/07 1.4 ± 5.5° (9.0) ND 5.0)
WellRB-S-03 5/17/07 (9.2) 136± 169° (274) ND (4.5)
Well RB-W-01 5/17/07 (9.2) 9.8 ± 168° (274) ND (4.2)
(a) Indicate results are less than MDC (enriched or conventional method).
ND-Non-detected.
MDC-Minirnum 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 2007. All samples were also analyzed for presence of
gamma-ray emitting radionuclides.
13
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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 fl) to stimulate a low productivity natural gas reservoir.
Production testing was completed in 1976 and restoration activities were completed in July 1978.
The principal 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 June 13-15, 2007. All of the routine
sampling locations were collected with the exceptions of Well 30-3-32-343 (North) and Bubbhng Springs
which didn’t even yield enough for tritium 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
Tritium concentrations of water samples collected onsite and offsite are 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 4pCiIL when it was last sampled. 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 well 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 plans to drill several wells in the near future, placed in strategic locations designed
to intercept migration of radionuclides, if they occur.
The two sampling location that had a tritium concentration above the MDC were Cave Springs, and
Windmill #2. 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 for the two locations above were below the MDC (see Table 5, page 16).
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Analysis Results for Water Samples Collected at the GASBUGGY Site - June 2007
TABLE 5
Sample Collection Enriched Tritium Tritium Gamma Spectromeiry
Location Date
pCIIL ±2 SD MDC pCi/L ± 2SD MDC pCi/L ±2 SD MDC
Arnold Ranch
(Spring) 6/13/07 -l.6±6.l (10) ND (5.0)
Bubbling Springs 6/15/07 No Sample collected
Cave Springs 6/13/07 39 ± 6.1 (10) ND (4.9)
Cedar Springs 6/13/07 103 ± 1732 (282) ND (4 2)
La Jara Creek 6/13/07 85± 1232 (282) ND (4.9)
Lower Burro
Canyon 6/14/07 38± 17l (282) ND (5.0)
Pond N. of Well
30.3.32.343 6/14/07 90± 1732 (282) ND (4.3)
Jicarilla Well 1 6/14/07 -81 ± 1702 (282) ND (4.9)
Well 28.3.33.233
South 6/14/07 51 ± 1722 (282) ND (5.0)
Well 30.3.32.343 Windmill Dry
North 6/14/07 No sample
Windmill#2 6/13/07 818±6.3 (10) Sample (4.8)
collected from
stock tank
Arnold Ranch Well 6/13/07 116 ± 1702 (282) ND (3.6)
(a) indicate results are less than MDC (enriched or conventional method).
ND Non-detected.
MDC Minimum detectable 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 dunng June 2007.
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Figure 6. Gnome Site.
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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 13lj 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. More material was slurried into the cavity and drifts in
1979. A potential exists for discharge of this slurry to the Culebra Dolomite 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 June 19-21, 2007. 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 1-lokett, 1991) indicates that these sampling locations, which are 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 radionuclides.
Three of four wells, Well USGS #4, Well USGS#8, Well DD-l sampling locations in the immediate vicinity
of SGZ have tritium activity greater than the MDC. Well PHS#8, showed an increase of tritium activity
results were 40 ± 6.3 pCiIL with MDC 10.0 pCiIL. The highest tritium concentration found onsite was in
Well DD-#1 reflecting 13.1 x l0 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, Well IJSGS#4, Well USGS#8,
Well LRL-#7 and Well DD-#l were all sampled in 2007.
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Analysis Results for Water Samples Collected at the GNOME Site - June 2007
TABLE 6
Sample Location Collection Enriched Tritium Tritium Gamma
Date Spectrometry
pCi/L ±2 SD MDC pCi/L ±2 SD MDC pCi/L ± MDC
2 SD
Carlsbad City #7 6/19/07 -1.8 ± 5•52 (9.1) ND (4.6)
Loving City #7 6/19/07 38± 172a (282) ND (4.7)
PHS 6 6119/07 30± 172a (282) ND (4.7)
PHS8 6/19/07 40±6.3a (10) ND (46)
PHS9 6/19/07 3.l±5.9a (9.7) ND (4.7)
PHS 10 6/19/07 60 ± l72 (282) ND (4.9)
USGS Well#1 6/19/07 -42±6.5k (10) ND (49)
USGS Well #4 6/20/07 5.5x10 4 ± 590 (282) ND (1.9)
USGS Well #8 6/20/07 3.2xl0 4 ± 460 (282 ND (1.3)
J. Mobley Ranch 6/19/07 65 ± l72 (282) ND (5.0)
Well DD-#l 6/21/07 3.lXlO 7 ± l.6x 10 4 (300) ND (3.5)
Well LRL-#7 6/20/07 142 ± 1 73a (282) ND (1.9)
(a) Indicate results are less than MDC (enriched or conventional method).
ND- Non-detected
MDC- Minimum detectable concentration.
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 offsite areas during June 2007.
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REFERENCES
Chapman & Hockett, 1991. Evaluation of Groundwater Monitoring at Off i:e Nuclear Test Areas, Las Vegas, NV,
Desert Research institute, University of Nevada System, Report DOE/N V/10845-07
Final rule on Dec. 7, 2000. Code of Federal Regulations, Vol. 65, Title 40, Parts 9, 141, and 142, December 7, 2000,
National Primaty Drinking Water Regulations; Radionuclides; Final Rule; (4OCFR9/ 141/142).
A Guide for Environmental Radiological Surveillance at U.S. Dept. of Ener v Installations, July /981, Office of
Operational Safety Report. Las Vegas, NV: U.S. Department of Energy; DOE/EP-0023.
Johns, F., et al. 1979. Radioche,nical and Analytical Procedures for Analysis of Environmental Samples. Las Vegas,
NV: U.S. Environmental Protection Agency; EMSL-LV-0539-17-1979.
Offsite Environmental Monitoring Report Radiation Monitoring Around Nuclear Test Areas, Calendar Year 1992. EPA
600/R-94/209.
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.
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 0.000001 Ci.
Isotope
Atoms of the same element with different numbers of neutrons in the nuclei. Thus ‘ 2 C, ‘ 3 C, and ‘ 4 C are isotopes of the
element carbon, the numbers denoting the approximate atomic weights. Isotopes have very nearly the same chemical
properties, but have different physical properties (for example ‘ 2 C and ‘ 3 C are stable, ‘ 4 C is radioactive).
Enrichment Method
A method of electrolytic concentration that increases the sensitivity of the analysis of tritiurn in water. This method is
used for selected samples if the tritium concentration is less than 800 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 Test Site Area.
Type I Error
The statistical error of accepting the presence of radioactivity when none is present. Sometimes called alpha error.
Type II Error
The statistical error of failing to recognize the presence of radioactivity when it is present. Sometimes called beta error.
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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 pC l/L
Isotope MDC Isotope MDC
Ru-l06 4.76E+O1
Be-7 4.56E+O1 Sn-113 8.32E+0O
K-40 4.92E+0l Sb-125 l.65E+0l
Cr-51 5.88E+01 1-131 8.28E+00
Mn-54 4.55E+0l Ba-133 9.16E+00
Co-57 9.65E+O0 Cs-134 6.12E+00
Co-58 4.71E+O0 Cs-137 6.43E+0O
Fe-59 1.07E+O1 Ce- 144 7.59E+O1
Co-60 5.38E+00 Eu-152 2.86E+01
Zn-65 1.24E+O1 Ra-226 1.58E+O1
Nb-95 5.64E+00 U-235 1.OIE+02
Zr-95 9.06E-4-00 Am-24 1 6.60E-4-01
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 Germanium 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 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 Program.
Standard Operating Procedures for the Center for Radloanalysis & 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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