Annual Water Sampling and
Analysis, Calendar Year 2005
SHOAL Test Site Area
FAULTLESS Test Site Area
RULISON Test Site Area
RIO BLANCO Test Site Area
GASBUGGY Test Site Area
GNOME Test Site Area
by
Max G. Davis
Rose (Kitty) Houston
Prepared for the U.S Department of Energy
under Interagency Agreement
DE-AI08-96NVII969
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 (IAC) 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.
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ABSTRACT
The U. S. Environmental Protection Agency, Radiation and Indoor Environments National Laboratory in Las Vegas,
Nevada (R&IE), operates the radiological surveillance program and monitors former nuclear test areas in Alaska,
Colorado, Mississippi, Nevada, and New Mexico, each year under the Long Term Hydrological Monitoring Program
(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 2005' 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 2005 are consistent with results from previous years. No increase was seen in either tritium
concentrations or gamma-ray emitting radionuclides at any site, with the exception of Well HC-3 at the SHOAL Site. A
small amount of '"Cs was detected in three samples collected from this well, which is well below the safe drinking
water standard of 15pCi/l (See Table 1). 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
(40CFR9/14I/142), with the exception of samples from several deep wells adjacent to the nuclear cavity at the Gnome
site As in previous years, the highest tritium value recorded for any sample, 3.46 x I07 pCi/L, was from, Well DD-1
(Project Gnome).
in
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IV
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CONTENTS
Page
Notice ... . . . . . jj
Abstract j,j
Figures and Tables vi
Acronyms and Abbreviations vii
Acknowledgments viii
1 0 Introduction ]
2.0 Sample Analysis 1
2 I Sampling at Project SHOAL, Nevada 2
21.1 Sample Collection 2
2.1.2 Water Analysis Results .. .. . 4
2 1.3 Conclusions 4
2.2 Sampling at Project FAULTLESS, Nevada 5
2 2 I Sample Collection 5
2.2.2 Water Analysis Results 5
2 2.3 Conclusions 5
2.3 Sampling at Project RULISON, Colorado ... 7
2.3.1 Sample Collection 7
2.3.2 Water Analysis Results . ... 8
2 3 3 Conclusions . . . 10
2 4 Sampling at Project RIO BLANCO, Colorado 10
2.4.1 Sample Collection 10
2.4.2 Water Analysis Results 10
2.4.3 Conclusions 10
2 5 Sampling at Project GASBUGGY, New Mexico 13
2.5.1 Sample Collection 13
2.5 2 Water Analysis Results 13
2.5.3 Conclusions 15
2 6 Sampling at Project GNOME, New Mexico 16
2.6.1 Sample Collection 16
2.6.2 Water Analysis Results 16
2 6.3 Conclusions . ... 18
References 19
Glossary of Terms 20
Appendix A 21
Appendix B 22
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FIGURES
Page
1 Project SHOAL sampling locations for February 2005 3
2. Project FAULTLESS sampling locations for March 2005 6
3. Project RULISON sampling locations for May 2005 9
4. Project RIO BLANCO sampling locations for May 2005 11
5. Project GASBUGGY sampling locations for June 2005 14
6. Project GNOME sampling locations for June 2005 17
TABLES
Page
1 Analysis Results for Water Samples Collected at the SHOAL Site-February 2005 4
2 Analysis Results for Water Samples Collected at the FAULTLESS Site - March 2005 7
3. Analysis Results for Water Samples Collected at the RULISON Site-May 2005 8
4 Analysis Results for Water Samples Collected at the RIO BLANCO Site - May 2005 12
5. Analysis Results for Water Samples Collected at the GASBUGGY Site - June 2005 15
6 Analysis Results for Water Samples Collected at the GNOME Site - June 2005 18
VI
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ACRONYMS AND ABBREVIATIONS
AEC
Bq/L
"7Cs
60Co
CRQA
DCG
DOE
EPA
g
3H+
3H
HpGe
I AC
ITC
131]
keV
kg
KT
L
LTHMP
m
MCL
MDA
MDC
MeV
min
mL
mT
ORIA
pCi/L
PHS
REECo
R&IE
"Sr
SGZ
uses
!3lXe
133Xe
U.S. Atomic Energy Commission
Becquerel per liter
Cesium-137
Cobalt-60
Center for Radioanalysis and Quality Assurance
Derived Concentration Guide (20,000 pCi/L for Tritium in Drinking Water)
U S. Department of Energy
U.S Environmental Protection Agency
gram
enriched tritium
tritium
high purity germanium gamma detector
Interagency Agreement
International Technology Corporation
Iodine-131
kilo electron volts (one thousand electron volts)
kilogram, 1000 grams
kiloton (one thousand tons TNT equivalent)
liter
Long-Term Hydrological Monitoring Program
meter
maximum contaminant level
minimum detectable activity
minimum detectable concentration
one million electron volts
minute
milliliter (one thousandth of a liter)
megaton (one million tons TNT equivalent)
Office of Radiation and Indoor Air
picocuries per liter = IO'12 curies per liter = 1/1,000,000,000,000 curies per liter
U S Public Health Service
Reynolds Electrical & Engineering Company
Radiation and Indoor Environments National Laboratory, Las Vegas, NV
Stronium-90
surface ground zero
U.S. Geological Survey
Xenon-131
Xenon-133
VII
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ACKNOWLEDGMENTS
The external peer review was provided by Vernon Hodge, Ph D , Chemistry, University of Nevada, Las Vegas. In
addition, the authors would like to acknowledge David R. Musick, Director of CRQA, Richard Flotard, Ph.D., and
George Dilbeck, Ph.D , as internal reviewers
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, located in 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 June of 2005, 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 Arriba County, New Mexico
• Project GNOME Test Site, Eddy County, New Mexico
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
radionuchdes, tritium, plutonium, strontium, and uranium in water samples. Two types of tritium analyses were
performed; conventional and electrolytic enrichment The enrichment method lowers the minimum detectable
concentration (MDC) from approximately 300 pCi/L to 5 pCi/L An upper limit of activity of 800 pCi/L has been
established for the tritium enrichment method because sample cross contamination becomes a problem at higher levels.
It has been 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 site, 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.
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Summary of Analytical Procedures
Type of
Analysis
Analytical
Equipment
Counting
Period (Min)
Analytical
Procedures
Size of
Sample
Approximate
Detection Limit"
HpGe
Gammab
3H
HpGe detector -150
calibrated at 0 5 keV/
channel (0 04 to 2 MeV
range) individual detector.
Efficiencies ranging from
15 to 3 5%
Automatic liquid
scintillation counter
3H+ Automatic liquid
Enrichment scintillation counter
300
300
Radionuclide concen-
tration quantified from
gamma spectral data
by online computer
program.
Sample prepared by
distillation.
Sample concentrated
by electrolysis following
distillation
3 5 L Varies with radionuclides
and detector used, if
counted to a M DC of
approx. 5 pCi/L for l37Cs.
30 - 40 mL 300 to 700 pCi/L
250 mLc 5 pCi/L
The detection limit is defined as the smallest amount of radioactivity that can be reliably detected, i e , probability of
Type I and Type II error at 5 percent each (DOE 1981)
Gamma spectrometry using a high purity intrinsic germanium (HpGe) detector.
Sample distilled, then concentrated to ~5 mL by electrolysis.
2.1 Sampling at Project SHOAL, Nevada
History
Project SHOAL, a 12-K.T nuclear test emplaced at 365 m (1200 ft), was conducted on October 26, 1963, in a
sparsely populated area near Frenchman Station, Nevada, 28 miles southeast of Fallen, 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 m granite and no surface crater was created. The effluent released during drillback was
detected onsite only and consisted of 110 curies of l31Xe and l33Xe, and less than 1.0 curie of I3II.
2.1.1 Sample Collection
Samples were collected on February 14-17, 2005. The sampling locations are shown in Figure 1 All of the locations
were sampled with the exception of Well H-3. The pump was inoperable. The routine sampling locations included
one spring, two windmills, and eleven wells of varying depths. At least one location, Well HS-I, should intercept
radioactivity migrating from the test cavity, if it should occur (Chapman and Hokett 1991) Well HC-3 was sampled
in February 2005 A small amount of l37Cs was detected. It was suspected that cross contamination might have
occurred In July 2005, the well was sampled a second time, all sampling equipment to be used was decontaminated
in accordance with the SOP 804. After analysis was completed, detectable amount ofI37C' still existed. Once again
the sampling cable, tools, and all equipment was decontaminated in accordance with the outlined procedure It was
then decided that a third sampling would take place. New sampling equipment, barrels, and collection containers
were cleaned prior to use. Analysis determined once again small amounts of IJ7Cs still existed. These results are
below the safe drinking water standards of 15pCi/L of l37Cs In February 2006, this well will be investigated further
and re-sampled. A full set of chemistry will be performed.
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Fallon
Sand Springs
TWell
CHURCHILL COUNTY
MINERAL COUNTY
LOCATION MAP
o
Surface Ground Zero
Water Sampling Locations
Map is not to scale
\
Figure 1. Project SHOAL sampling locations for February 2005.
3
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2.1.2 Water Analysis Results
Gamma-ray spectral analysis results indicated that l37Cs was detected in Well HC-3. Tritium
concentrations at all locations except for two were below the MDC. The only sampling
locations that had a tritium concentration above the MDC was Well HC-4 of
26 ±1 pCi/L and Well HC-3 of 11 ± 5.6 (see Table 1, below).
2.1.3 Conclusions
No radioactive materials attributable to the SHOAL nuclear test were detected in samples
collected in the offsite area during 2005.
Analysis Results for Water Samples Collected at the SHOAL Site - February 2005
TABLE 1
Sample
Location
Hunts Station
Flowing Spring
Spring Windmill
Well 1-1-2
Well H-3
WcllHS-1
WellHC-1
Well HC-2
Well HC-4
Well HC-5
Well HC-6
Well HC-7
Well HC-8
l-IC-3 Filter
Well HC-3
Well HC-3
Well HC-3
Collection
Date
2/15/05
2/15/05
2/14/05
2/15/05
2/15/05
2/14/05
2/15/05
2/15/05
2/17/05
2/17/05
2/17/05
2/17/05
2/15/05
2/16/05
2/16/05
7/20/05
8/17/05
Enriched Tritium
pCi/L±2SD (MDC)
4.0 ± 6.0(a>
- 55± 6.0
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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 tuffaceous 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 March 14-16, 2005. Sampling locations are shown in Figure 2. They
include two springs and seven wells of varying depths. All sampling locations were collected.
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). 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 drinking water supplies.
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.
2.2.3 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. All samples were analyzed for the presence of
gamma-ray emitting radionuclides.
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Station
SGZ,
.-I
HTH21
HTH1 *
I
ix Mile Well
Hot Creek*'
Ranch Spring
Tybo Well
r \
I Jim Bias ^ •* «. _
Well —
Blue Jay
Springs
I
N
Tonopah
Warm
Springs
I Blue Jay
Maintenance
— ... / e 1 ^ Station
sitecKr^ NN
\
\
\
\
\
\
I Surface Ground Zero
Water Sampling Locations
Not a Sampling Location
Map is not to scale
NYE
COUNTY
LOCATION MAP
Figure 2. Project FAULTLESS sampling locations for March 2005.
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Analysis Results for Water Samples Collected at the FAULTLESS Site - March 2005.
TABLE 2
Sample
Location
Hot Creek Ranch
Blue Jay Springs
Blue Jay Mamt
Station
Well HTH-1
Well HTH-2
Site C Base Camp
Six Mile Well
Tybo Well
Twin Springs
Ranch
Collection
Date
3/16/05
3/16/05
3/15/05
3/15/05
3/23/05
3/15/05
3/16/05
3/16/05
3/14/05
Enriched Tritium*"
pCi/L±2SD (MDC)
3 8 ± 5 4
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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 2005, was from
26 ± 7.1 pCi/L at the spring 500ft east of GZ to 35 ± 5.7 pCi/L at Tim Jacobs Ranch (see Table 3).
All enriched values were less than 0.25 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
componen remaining from clean-up activities at the site. This is supported by Desert Research
Institute 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).
Analysis Results for Water Samples Collected at the RULISON Site - May 2005
TABLE 3
Sample
Location
Battlement Creek
City Springs
Daniel Gardner
CER Test Well
CER Test Well R
Patrick McCarty
Potter Ranch
Morressiana Rch
Tim Jacobs
Kevin Whelan
Spring 300 yds
N. ofGZ
Spring 500 ft
E. ofGZ (Casey
Weldon)
Collection
Date
5/1 1/05
5/11/05
5/1 1/05
5/1 1/05
5/11/05
5/11/05
5/1 1/05
5/1 1/05
5/11/05
5/1 1/05
5/1 1/05
5/1 1/05
Enriched Tritium
pCi/L±2SD(MDC)
35 ± 5.7 (8.4)
26 ±5.8 (9.0)
26±7.l (11)'
Tritium00
pCi/L ± 2 SD (MDC)
-64±17l(a) (284)
47 ± ! 73
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Douglas K. Sauter Potter Rarwh
Grand Vallfty
City Springs
Grand Valay f^-'P- i. --- -
Keven Wielan
Jacobsl
gfettoment Cn^K.
XB Spring 300 yds
SGZ^b^NofSGZ
EOfSGZ
N
8 Water SatnpSng Locations
tOCATKSHMAP
Map is not to scale
COLORADO
OARFIELO
COUNTY
Figure 3. Project RUI.tSON sampling tocations for May 2W)5.
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2.3.3 Conclusions
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, perhaps, a small amount of residual global "fallout tritium" remaining from nuclear testing in the
1950s and 1960s. All routine samples were analyzed for presence of gamma-ray emitting
radionuclides.
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 12-13, 2005, 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. Three of the 15 samples collected were above the MDC for
enriched tritium and none were above the MDC using the conventional method (see Table 4, page
12).
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 2005. All samples were analyzed
for presence of gamma-ray emitting radionuclides.
10
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Meeker
Black 9ut>hur
B-1 Equity
Creek#1
Fawn Crank 8400' DavwiBtMm
RB-D-03
| R&-W-01
I Fawn Creek SOT/ Downstream
| Fawn Crook 500* Upstream
Fawn Creak 6800' Upstrean
"". Fawn Creak Spr. <3
RbBknoa
N
Ma Sampling Locfitians
Sufaoe Ground Zero
Map Is not to scale
LOCATION NAP
RtoHlura
COUMTV
Figure 4. Project RIO BLANCO sampling locations for May 2005.
II
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Analysis Results for Water Samples Collected at the RIO BLANCO Site - May 2005
TABLE 4
Sample
Location
B-l Equity Camp
Brennan Windmill
CER#I Black
Sulphur
CER #4 Black
Sulphur
Fawn Creek # 1
Fawn Creek #3
Fawn Creek 500'
Upstream
Fawn Creek 6800'
Upstream
Fawn Creek 500'
Downstream
Fawn Creek 8400'
Downstream
Johnson Artesian
Well
WellRB-D-01
Well RB-D-03
Well RB-S-03
Well RB-W-OI
Well RB-D-01 R
Well RB-S-03 R
Well RB-D-03 R
WellRB-W-01 R
Collection
Date
5/13/05
5/12/05
5/13/05
5/13/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
5/12/05
Enriched Tritium
pCi/L ± 2 SD (MDC)
21±7.1 (11)
27 ± 6.4 (9 8)
10 ±6.0 (9.5)
-.53 ±5 7(a) (9 5)
Tritium00
pCi/L ± 2 SD (MDC)
-38±185(0) (305)
38±186(1) (305)
-95±184(a) (305)
105±187(a) (305)
52±186(n) (305)
114±187(a) (305)
109 ±187°" (305)
66±186W (305)
43±186W (305)
-109±183(" (305)
-8I±I84W (305)
1I4±187<" (305)
62±l86(a) (305)
-47±184W (305)
100±187(il) (305)
Gamma
Spectrometry00
pCi/L (MDC)
ND (5.0)
ND (4.7)
ND (4.6)
ND (4.4)
ND (4.9)
ND (4.8)
ND (4.4)
ND (4.2)
ND (4.3)
ND (5.0)
ND (4.8)
ND (4.0)
ND (4.7)
ND (4.7)
ND (5.0)
(a) Indicate results are less than MDC (enriched or conventional method).
(b) Value in parenthesis represents '"Cs MDC (pCi/L).
ND Non-detected.
MDC Minimum detectable concentration
R Rinse sample.
12
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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 (4,232 ft) 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 14-16, 2005. All of the
routine sampling locations were collected except for Bubbling Spring which was dry (see
Figure 5) and EPNG-10-36 which was plugged in 2003.
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.
Well EPNG 10-36 has yielded tritium activities between 100 pCi/L in 2000 to 0.05 ± 4 in 2003. In
2003, Well EPNG 10-36 was plugged due to the severe deterioration of the well casing. DOE will
drill several wells in the near future, placed in strategic location designed to intercept migration of
radionuclides, if they should occur. 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).
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 three were below the MDC. The sampling locations that had a tritium
concentration above the MDC were Cedar Springs of 19 ± 5.8 pCi/L, LaJara Creek 25 ±5.8 pCi/L
and Well 23 South 17 ±6.0 pCi/L (see Table 5, page 15).
13
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To Bloomfield &
Farmington
1 Pond N. of
Well 30.3.32.343N
Well 30.3.32.343N
La Jara Creek
1
Bubbling
Springs
Jicarilla Well 1
EPNG Well
Cedar Springs
Cave Spnngs
Arnold Ranch Spring
Arnold Ranch Well
Lower Burro
Canyon
Well 28.3.33.233S
Gobernador
Old
Store
LOCATION MAP
Surface Ground Zero
Water Sampling Locations
Not a Sampling Location
Map is not to scale
RIO
ARRIBA
COUNTY
NEW
MEXICO
Figure 5. Project GASBUGGY sampling locations for June 2005.
14
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2.5.3 Conclusions
Tritium concentrations of water samples collected onsite and offsite are consistent with those of past
studies at the GASBUGGY Site.
Analysis Results for Water Samples Collected at the GASBUGGY Site - June 2005
TABLE 5
Sample
Location
Arnold Ranch
Spring
Bubbling Springs
Cave Springs
Cedar Springs
La Jara Creek
Lower Burro
Canyon
Pond N. of Well
30 3.32.343
Wei IEPNG- 10-36
JicarillaWell I
Well 28 3.33.233
(South)
Well 30.3.32 343
(North)
Windmill #2
Arnold Ranch Well
Collection
Date
6/15/05
6/14/05
6/15/05
6/16/05
6/15/05
6/15/05
6/16/05
6/16/05
6/15/05
6/15/05
6/16/05
6/15/05
6/15/05
Enriched Tritium
pCi/L±2SD (MDC)
9.5±6.7(a) (11)
19 ±5.8 (9.0)
25 ±5.8 (8.9)
5 8 ±5.4(" (9 0)
17±60 (93)
Tritium00
pCi/L ± 2 SD (MDC)
38±173W (284)
-26±l72(a) (284)
32±173(1) (284)
-21±172<" (284)
-85±171(a) (284)
Gamma Spectrometry00
pCi/L (MDC)
ND (4.9)
No sample, spring dry
ND (4.9)
ND (4.9)
ND (4.9)
ND (5.0)
ND (5.0)
No Sample Well
Plugged
ND (4.9)
ND (5.0)
No Sample Windmill
disconnected
ND (4.8)
ND (4.7)
(a) Indicate results are less than MDC (enriched or conventional method).
(b) Value in parenthesis represents '"Cs MDC (pCi/L).
ND Non-detected.
MDC Minimum detectable concentration.
15
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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 370m (1,216 ft) in the Salado salt formation. The explosive
yield was slightly-more-than 3-K.T. 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 137Cs, 10 Ci 90Sr, and 4 Ci I3II 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 21-23, 2005. The routine sampling
sites, depicted in Figure 6, includes ten monitoring wells in the vicinity of surface GZ; 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 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.
Tritium results greater than the MDC were detected in water samples from four of the 12 sampling
locations in the immediate vicinity of GZ. Tritium activities in wells LRL-7, USGS-4, DD-1 and
USGS-8 ranged from 761 ± 183 (LRL-7) to 3.46 x 107± 1.63 x 104(DD-1) pCi/L. Well DD-1
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 (See Table 6).
In addition to tritium, l37Cs and 90Sr concentrations were observed in samples from Wells DD-1,
LRL-7, and USGS-8, while 90Sr activity was detected in Well USGS-4 as in previous years (see
Table 6). No tritium was detected in the remaining sampling locations, including Well USGS-1,
which the DRI analysis (Chapman and Hokett, 1991) indicated is positioned to detect any migration
of radioactivity from the cavity. All other tritium results were below the MDC.
16
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Carlsbad City
Well 7 •
Carlsbad
Loving City
Well 2 •
HS Well 8
PHSWelMO
PHS Well 6
Surface Ground Zero
Water Sampling Locations
Map is not to scale
EDDY
COUNTY
LOCATION MAP
Figure 6. Program GNOME sampling locations for June 2005.
17
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2.6.3 Conclusion
No radioactive materials attributable to the GNOME Test were detected in samples collected in the
offsite areas during June of 2005.
Analysis Results for Water Samples Collected at the GNOME Site - June 2005
TABLE 6
Sample
Location
Well 7 City
Well 2 City
Well PHS 6
Well PHS 8
Well PHS 9
Well PHS 10
Well USGS 1
Well USGS 4
Well USGS 8
J Mobley Ranch
WellDD-1
Well LRL-7
WellDD-1 R
Well USGS 4 R
Well USGS 8 R
Well LRL-7 R
Collection
Date
6/22/05
6/22/05
6/22/05
6/22/05
6/23/05
6/23/05
6/21/05
6/21/05
6/21/05
6/22/05
6/23/05
6/21/05
6/23/05
6/21/05
6/21/05
6/21/05
Enriched Tritium
pCi/L±2SD (MDC)
4.5±5 4(a) (8.8)
7.7±6 0°" (9.7)
10±65 (10)
Tritium
pCi/L±2SD (MDC)
I73±170(a) (274)
I21±169(" (274)
63±168(a) (274)
5.8±167W (274)
3.l2xl04±517 (274)
3.65x1 0"±555 (274)
3.46xl07±1.63xl04 (274)
761±183(a) (274)
86± 169(a) (274)
.00±167W (274)
IIO±169(a) (274)
-17±166(>) (274)
Gamma Spectrometry™
pCi/L (MDC)
ND (4.9)
No sample-well plugged
ND (4.9)
ND (5.0)
ND (4.6)
ND (5.0)
ND (4.4)
ND (1.7)
89±14 (1.9)
ND (4.7)
6. 12x1 0s ±9.24x10" (3980)
26±4.6 (1.9)
(a) Indicate results are less than MDC (enriched or conventional method).
(b) Value in parenthesis represents '"Cs MDC (pCi/L)
ND Non-detected.
MDC Minimum detectable concentration.
R Rinse sample.
18
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REFERENCES
Chapman & Hockett, 1991. Evaluation ofGroundwater Monitoring at Offsite Nuclear Test Areas,
Las Vegas, NV, Desert Research Institute, University of Nevada System, Report DOE/NV/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 Primary Drinking Water Regulations; Radionuclides: Final Rule;
(40CFR9/141/142).
A Guide for Environmental Radiological Surveillance at U.S. Dept. of Energy Installations, July
1981, Office of Operational Safety Report. Las Vegas, NV: U.S. Department of Energy; DOE/EP-
0023.
Johns, F., et al. 1979. Radiochemical 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-947209.
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GLOSSARY OF TERMS
Background Radiation
The radiation in man's environment, including cosmic rays and radiation from naturally-occurring
and man-made radioactive elements, both outside and inside the bodies of humans and animals. The
usually quoted average individual exposure from background radiation is 125 millirem per year in
mid-latitudes at sea level.
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 (u,Ci) is 0.000001 Ci.
Isotope
Atoms of the same element with different numbers of neutrons in the nuclei. Thus I2C, 13C, and MC
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
12C and "C are stable, I4C is radioactive).
Enrichment Method
A method of electrolytic concentration that increases the sensitivity of the analysis of tritium in
water. This method is used for selected samples if the tritium concentration is less than 700 pCi/L.
Minimum Detectable Concentration (MDC)
The smallest amount of radioactivity that can be reliably detected with a probability of Type I and
Type II errors at 5 percent each (DOE 1981).
Offsite
Areas exclusive of the immediate 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*
Matrix
Volume
Marinelli
Water
3.5 liter
Model
Density
Units
430G
l.Og/ml
pCi/L
Isotope
MDC
Isotope
MDC
Be-7
K-40
Cr-51
Mn-54
Co-57
Co-58
Fe-59
Co-60
Zn-65
Nb-95
Zr-95
4.56E+01
4.92E+01
5.88E+01
4.55E+01
9.65E+00
4.71E+00
1.07E+01
5.38E+00
1.24E+01
5.64E+00
9.06E+00
Ru-106
Sn-113
Sb-125
1-131
Ba-133
Cs-134
Cs-137
Ce-144
Eu-152
Ra-226
U-235
Am-241
4.76E+01
8.32E+00
1.65E+01
8.28E+00
9.16E+00
6.12E+00
6.43E+00
7.59E+01
2.86E+01
1.58E+01
1.01E+02
6.60E+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's will vary with different types of shielding, geometries,
counting times and decay time of sample.
21
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Appendix B
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 89Sr and 90Sr 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
Standard Operating Procedures for the Center for
Environmental Restoration, Monitoring & Emergency Response
CER-203 Standard Operating Procedure for the Long-Term Hydrological Monitoring Program
CER-804 Sampling Equipment Decontamination Procedures
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