United States
Environmental Protection
Agency
Office of Radiation and
Indoor Air
Washington, DC 20460
EPA-402-R-02-002
February 2002
&EPA
Annual Water Sampling and
Analysis, Calendar Year 2001
RULISON Test Site Area
RIO BLANCO Test Site Area
FAULTLESS Test Site Area
SHOAL Test Site Area
GASBUGGY Test Site Area
GNOME Test Site Area
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Annual Water Sampling and
Analysis, Calendar Year 2001
RULISON Test Site Area
RIO BLANCO Test Site Area
FAULTLESS Test Site Area
SHOAL Test Site Area
GASBUGGY Test Site Area
GNOME Test Site Area
by
N
a
~
(J
Max G. Davis
Terry L. Mauck
Prepared for the U.S. Department af Energy
under Interagency Agreement
DE-AI08-96NVl1969
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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 (EP A) through Interagency Agreement (IAG) DE-AI08-96 NY
11969 from the United States Department of Energy (DOE). This document has been subjected
to the Agency's peer and administrative review, and it has been approved for publication as an
EP A 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&IE), operates the radiological surveillance program
surrounding the Nevada Test Site (NTS) and, in addition, 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 2001; Projects Rulison and Rio Blanco in
Colorado; Projects Shoal and Faultless in Nevada; and Projects Gasbuggy and Gnome in New
Mexico. Monitoring results for Alaska and Mississippi are reported separately.
Radiological results for 2001 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 National Primary
Drinking Water Standard for tritium of 20,000 pCiIL, 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, 4.2 x 107 pCiIL, was from one of these wells, Well DD-l
(Project Gnome).
111
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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. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 1
2.0 Sample Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 1
2.1 Sampling at Project RULISON, Colorado. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 2
2.1.1 Water Analysis Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 4
2.1.2 Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 5
2.2 Sampling at Project RIO BLANCO, Colorado. . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 5
2.2.1 Water Analysis Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 5
2.2.2 Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 5
2.3 Sampling at Project FAULTLESS, Nevada. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 8
2.3.1 Water Analysis Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 8
2.3.2 Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 8
2.4 Sampling at Project SHOAL, Nevada. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 10
2.4.1 Water Analysis Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 12
2.4.2 Conclusions... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 12
2.5 Sampling at Project GASBUGGY, New Mexico """"""""""""'" 13
2.5.1 Water Analysis Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 13
2.5.2 Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 13
2.6 Sampling at Project GNOME, New Mexico. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 15
2.6.1 Water Analysis Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 16
2.6.2 Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . " 16
References. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . " 19
Glossary of Terms. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 20
Appendix. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . " 21
v
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FIGURES
Page
1. RULISON Site sampling locations for May 2001 ..,............................... 3
2. RIO BLANCO Site sampling locations for May 2001 ............................,.. 6
3. FAULTLESS Site sampling locations for March 2001 ........................,..... 9
4. SHOAL Site sampling locations for February 2001 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 11
5. GASBUGGY Site sampling locations for June 2001 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 14
6. GNOME Site sampling locations for June 2001 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 17
TABLES
Page
1. Analysis Results for Water Samples Collected at RULISON Site - May 2001 ............ 4
2. Analysis Results for Water Samples Collected at RIO BLANCO Site - May 2001 ........ 7
3. Analysis Results for Water Samples Collected at FAULTLESS Site - March 2001 ""'" 10
4. Analysis Results for Water Samples Collected at SHOAL Site - February 2001 ......... 12
5. Analysis Results for Water Samples Collected at GASBUGGY Site - June 2001 """" 15
6. Analysis Results for Water Samples Collected at GNOME Site - June 2001 """""" 18
VI
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ABC
DOE
DRI
RSL
EPA
DCG
g
3H+
3H
HpGe
lAG
keV
kg
KT
LTHMP
L
m
mm
MDC
MeV
mL
MT
ORIA
pCi/L
PHS
R&IE
SGZ
USGS
IT
ACRONYMS AND ABBREVIATIONS
U.S. Atomic Energy Commission
U.S. Department of Energy
Desert Research Institute
Radiation Sciences Laboratory
U.S. Environmental Protection Agency
Derived Concentration Guide (20,000 pCiIL for Tritium in Drinking Water)
gram
Enriched Tritium
Tritium
high.purity germanium gamma detector
Interagency Agreement
kilo electron volts (one thousand electron volts)
kilogram, 1000 grams
kiloton (one thousand tons TNT equivalent)
Long-Term Hydrological Monitoring Program
liter
meter
minute
minimum detectable concentration
one million electron volts
milliliter (one thousandth of a liter)
megaton (one million tons TNT equivalent)
Office of Radiation and Indoor Air
picocuries per liter = 10-12 curies per liter = 1/1,000,000,000,000 curies per liter
U.S. Public Health Service
Radiation and Indoor Environments National Laboratory, Las Vegas, NV
surface ground zero
U.S. Geological Survey
International Technology Corp.
VB
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ACKNOWLEDGMENTS
The authors would like to thank Rich Flotard, Rose Houston, Pat Honsa, Betty Strickland, and the
staff of the hydrological monitoring team, EP A, for their dedication to quality and tireless work in
the execution of the sampling and laboratory analysis effort.
V11l
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1.0 INTRODUCTION
Under an Interagency Agreement with the Department of Energy (DOE), the Radiation & Indoor
Environments Laboratory (R&IE), Office of Radiation and Indoor Air (ORIA), EP A, 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 2001, around the following test site areas:
.
.
.
.
.
.
2.0 Sample Analysis
Project RULISON Test Site, Garfield County, Colorado
Project RIO BLANCO Test Site, Rio Blanco County, Colorado
Project FAULTLESS Test Site, Nye County, Nevada
Project SHOAL Test Site, Churchill County, Nevada
Project GASBUGGY Test Site, Rio Arriba County, New Mexico
Project GNOME Test Site, Eddy County, New Mexico
Radiochemical procedures used to analyze the samples collected for this report are described in
Johns, et al. (1979) and are summarized below (see Appendix for typical minimum detectable
concentration (MDC) values for gamma spectroscopy). These include standard methods to
identify natural and man-made gamma-emitting radionuclides, tritium, plutonium, strontium, and
uranium in water samples. Two types of tritium analyses were performed; conventional and
electrolytic enrichment. The enrichment method lowers the MDC from approximately 300 pCiIL
to 5 pCi/L. An upper limit of activity of 700 - 800 pCiIL has been established for the tritium
enrichment method because sample cross contamination becomes a problem at higher levels.
In late 1995, it was decided that a maximum of 25 percent of all samples collected would be
analyzed by the low-level enrichment method. This decision was based on the time required for
analysis, budgetary constraints, and an assessment of past results. Under the current sampling and
analysis protocol for the site, all samples are initially screened for tritium activity by the
conventional method, and selected samples 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
uramum.
1
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Summary of Analytical Procedures
Type of Analytical Counting Analytical Size of Approximate
Analysis Equipment Period (Min) Procedures Sample Detection Limit"
HpGe HpGe detector -150 Radionuclide concen- 3.5 L Varies with radionuclides
Gammab calibrated at 0.5 keY! tration quantified from and detector used, if
channel (0.04 to 2 MeV gamma spectral data counted to a MDC of
range) individual detector. by online computer approx. 5 pCiIL for 137CS.
Efficiencies ranging from program.
15 to 35%.
3H Automatic liquid 300 Sample prepared by 30 - 40 mL 300 to 700 pCiIL
scintillation counter distillation.
3H+ Automatic liquid 300 Sample concentrated 250 mL c 5 pCiIL
Enrichment scintillation counter by electrolysis following
distillation.
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).
b Gamma spectrometry using a high purity intrinsic germanium (HpGe) detector:
C Sample distilled, then concentrated to -5 mL by electrolysis.
2.1 Sampling at Project RULISON, Colorado
History
Co-sponsored by the U.S. Atomic Energy Commission (ABC) and Austral 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.
Sampling was conducted on May 16, 2001, from all sampling locations at Grand Valley and
Rulison, Colorado. Routine sampling locations are shown in Figure 1. Sampling included the
Grand Valley municipal drinking water supply springs, water supply wells for five local ranches,
and five sites in the vicinity of surface ground zero (SGZ), including one test well, a surface-
discharge spring and two wells (RU-1 and RU-2) located at SGZ.
2
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,
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Douglas K. Sauter Potter Ranch
Ranch
Grand Valley
City Springs
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Rulison..J /
....- --*,
---~~ I
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~ - - - - - ~ Tim Jacobs Ranch
I , .Patrick Mc Carty
,I \
,..II! I .\ Battlement Creek
. -;, CER8
DamelGardner li t W II ...... S .
Ranch es e. pnng
RU-1.O,
RU-2.
. RU-3
,
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o Surface Ground Zero
I Water Sampling Locations
- - - Unpaved Road
LOCATION MAP
Scale in Miles
o 5
---~
Scale in Kilometers
GARFIELD
COUNTY
o
8
Figure 1. RULISON Site sampling locations for May 2001.
3
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2.1.1 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
2001 was from 24:t 3.8 pCi/L at Well RU-2 to 51 :t 4.2 pCi/L at Tim Jacobs Ranch (see Table 1).
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 component 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).
A
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It ~
Wt
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C II t d
RULISON S.
M
2001
nalYSlS esu S or a er ampJes 0 ec e at Ite - ay
TABLE 1
Sample Collection Emiched Tritium TritiumCa) Gamma SpectrometryCb)
Location Date pCi/L :t 2 SD (MDC) pCi/L :t 2 SD (MDC) pCi/L (MDC)
Battlement Creek 5/16/01 -53 :t 126 (210) ND (4.7)
City Springs 5/16/01 28 :t 128 (210) ND (4.6)
David Gardner 5/16/01 -57 :t 126 (210) ND (4.9)
CER Test Well 5/16/01 -27 :t 127 (210) ND (4.5)
Patrick McCarty 5/16/01 76:t 129 (210) ND (4.6)
Potter Ranch 5/16/01 -1.4 :t 127 (210) ND (4.4)
Douglas Sauter 5/16/01 -49 :t 126 (210) ND (1.5)
Tim Jacobs 5/16/01 51 :t 4.2 (5.5) ND (1.6)
Spring 300 yds N. 5/16/01 24:t 3.8 (5.6) ND (4.8)
ofGZ
Well RU-l 5/16/01 58 :t 129 (210) ND (4.9)
Well RU-2 5/16/01 24:t 3.7 (5.4) ND (4.5)
Well RU-3 5/16/01 -10 + 127 (210) ND (4.9)
(a) Indicate results are less than MDC (emiched or conventional method).
(b) Value in parenthesis represents 137CS MDC (pCi/L).
ND Non-detected.
4
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2.1.2 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. None were detected above the MDC (see Table 1, page 4).
2.2 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 unti11976 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.
Sampling was conducted on May 17-18, 2001, and locations are shown in Figure 2. 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.
2.2.1 Water Analysis Results
Gamma-ray spectral analysis results indicated that no man-made gamma-ray emitting
radionuclides were present in any offsite samples. None of the 15 samples collected were above
the MDC for enriched tritium or conventional method. This year Well RB- W -01 was not
sampled, as it is a back up well for RB-D-03 (see Table 2, page 7).
2.2.2 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 2001. All samples were
analyzed for presence of gamma-ray emitting radionuclides. None were detected above the MDC.
5
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o
~
o
Fawn Cr.500'
Upstream
Fawn Cr. 6800'
Upstream
Fawn Cr.500' Downstream
RB-D-01 }
RB-D-03 4
RB-S-03
RB-W-01
. Fawn Cr. NO.3
Scale in Miles
...
5
.
8
Scale in Kilometers
RIO BLANCO COUNTY
-------------------------------
GARFIELD COUNTY
o Surface Ground Zero
. Water Sampling Locations
~
N
LOCATION MAP
COLORADO
RIO BLANCO
COUNTY
Figure 2. RIO BLANCO Site sampling locations for May 2001.
6
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Analysis Results for Water Samples Collected at RIO BLANCO Site - May 2001
TABLE 2
Sample Collection Emiched Tritium Tritium{a) Gamma Spectrometry(b)
Location Date pCi/L :!: 2 SD (MDC) pCi/L :!: 2 SD (MDC) pCiIL (MDC)
B-1 Equity Camp 5/18/01 -12.6:!: 121 (210) ND (4.9)
Brennan Windmill 5/17/01 -83 :!: 125 (210) ND (4.9)
CER #1 Black 5/18/01 -23 :!: 127 (210) ND (4.9)
Sulphur
CER #4 Black 5/18/01 -70:!: 126 (210) ND (5.0)
Sulphur
Fawn Creek #1 5/17/01 -109:!: 125 (210) ND (4.9)
Fawn Creek #3 5/17/01 -182:!: 123 (210) ND (4.9)
Fawn Creek 500' 5/17/01 -18:!: 127 (210) ND (5.0)
Upstream
Fawn Creek 6800' 5/17/01 -53:!: 126 (210) ND (4.4)
Upstream
Fawn Creek 500' 5/17/01 -18:!: 127 (210) ND (4.7)
Downstream
Fawn Creek 8400' 5/17/01 58 :!: 129 (210) ND (4.7)
Downstream
Johnson Artesian 5/17/01 -113:!: 125 (210) ND (4.9)
Well
Well RB-D-Ol 5/17/01 -.79 :!: 3.4 (a) (5.6) ND (4.3)
Well RB-D-03 5/17/01 1.6:!: 3.7 (a) (6.0) ND (5.0)
Well RB-S-03 ' 5/17/01 .43 :!: 3.7 (a) (6.0) ND (5.0)
Well RB-W-Ol 5/17/01 Not Sampled
(a) Indicate results are less than MDC (emiched or conventional method).
(b) Value in parenthesis represents J37Cs MDC (pCi/L).
ND Non-detected.
7
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2.3 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 detennine 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).
Sampling was conducted on March 11-14,2001. Sampling locations are shown in Figure 3. They
include one spring and six wells of varying depths. All sampling locations were collected with
the exception of HTH-2, it was decided it would not be sampled this year per DOE
(Pete Sanders). A location that had been previously deleted has been added to the sampling
locations by request of the rancher Blue Jay Springs.
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). All samples yielded negligible gamma activity.
Enriched tritium concentrations were less than the MDC and less than 0.02 percent of the DCG.
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.
2.3.1 Water Analysis Results
All gamma-ray spectral analysis results indicated that no man-made gamma-ray emitting
radionuclides were present above minimum detectable levels in any on site and bffsite samples.
All tritium results were below the MDC (see Table 3, page 10).
2.3.2 Conclusions
Tritium concentrations of water samples collected onsite and offsite are consistent with those of
past studies at the FAULTLESS Site. No gamma-ray emitting radionuclides were detected above
the MDC.
8
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1
/
« HTH 2
'. HTH 1
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;; /
/ ;; /
/ ; /
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Hot Creek If 1 '\
Ranch Spring I r .
1 Six-Mile Well
Blue Jay ~ 1
ILS~i~gs I II
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SiteC
Complex
. Twin Springs Ranch
Blue Jay
Maintenance
Station
o Surface Ground Zero
. Water Sampling Locations
I 0
I
o
5
~
NYE
COUNTY
Scale in Miles
5
10
Scale in Kilometers
LOCATION MAP
Figure 3. FAULTLESS Site sampling locations for March 2001.
9
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Analysis Results for Water Samples Collected at FAULTLESS Site - March 2001.
TABLE 3
Sample Collection Enriched Tritium{a) Tritium{a) Gamma Spectrometry{b)
Location Date pCiIL :t 2 SD (MDC) pCiIL :t 2 SD (MDC) pCiIL (MDC)
Hot Creek Ranch 3/12/01 34 :t 132 (216) ND (4.8)
Spring
Blue Jay Springs 3/14/01 4.0 :t 3.3 (5.2) ND (1.9)
Blue Jay Maint 3/12/01 34 :t 132 (216) ND (4.9)
Station
Well HTH-l 3/13/01 1.2 :t 3.0 (5.0) ND (5.0)
Well HTH-2 3/13/01 Not sampled (DOE)
Site C Complex 3/13/01 43 :t 132 (216) ND (4.5)
Six Mile 3/14/01 -57 :t 130 (216) ND (1.6)
Twin Springs 3/11/01 -4.3 :t 130 (216) ND (5.0)
Ranch
(a) Indicate results are less than MDC (enriched or conventional method).
(b) Value in parenthesis represents 137CS MDC (pCiIL).
ND Non-detected.
2.4 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 13IXe and 133Xe, and less than 1.0 curie of 1311.
Samples were collected on February 9 23,2001. The sampling locations are shown in Figure 4.
Only eight of the nine routine locations were sampled. Since 1997, eight new wells have been
added to the LTHMP at this site which are positioned near GZ. Two of the eight new wells
drilled at Shoal in 1999 were designed for conducting a tracer test. Previous modeling of the site
found that the effective porosity of the aquifer was a very important, but highly uncertain,
parameter. The purpose of the tracer test is to determine the effective porosity of the fractured
granite aquifer. The test was conducted in two phases. The initial, smaller, injection consisted of
iodide, carbon-13, and deuterium, and occurred on November 3, 1999. Its primary purpose was to
provide information for the major injection. The major injection occurred on November 10, 1999,
and consisted of lithium bromide, and poly-fluorinated benzoic acid. On November 28, 1999,
cesium was injected, and in June 2001, polystyrene microspheres were injected. The
breakthrough has been slow, leading to an extension of the test beyond its planned four-month
time period to the end of the federal fiscal year (September 2001). Both the injection well, HC-6,
10
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Fallon
95
. Flowing Well
Well H-3 .
-----
,
,
,
, CHURCHILL COUNTY
-----------------------------___1
. HS-1
,
,
,
(;., ,
o-} ,
°0 ,
<1v ,
0-
MINERAL COUNTY
To Scheelite Mine
~
N
LOCATION MAP
o Surface Ground Zero
. Water Sampling Locations
o 5
~
10
~
15
Scale in Miles
o
5
10
Scale in Kilometers
Figure 4. SHOAL Site sampling locations for February 2001.
11
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and pumping well, HC-7, are likely to contain remnants from the tests for some time to come.
The routine sampling locations include one spring, one windmill, and eleven wells of varying
depths. At least one location, Well HS-l, should intercept radioactivity migrating from the test
cavity, if it occurs (Chapman and Hokett 1991).
2.4.1 Water Analysis Results
Gamma-ray spectral analysis results indicated that no man-made gamma-ray emitting
radionuclides were present in any samples above the MDC. Tritium concentrations at all the
locations except for one were below the MDC. The only sampling location that had a tritium
concentration above the MDC was Well HC-7 of 7.6:!: 3.2 pCiIL. (see Table 4, below).
2.4.2 Conclusions
No radioactive materials attributable to the SHOAL nuclear test were detected in samples
collected in the onsite and offsite areas during 2001.
A I . R
I ~
w
S
I
Cll
d
SHOAL S'
Fb
2001
nalYSIS esu ts or ater ampJes 0 ecte at lte. e ruary
TABLE 4
Sample Collection Emiched Tritium Tritium(a) Gamma Spectrometry(b)
Location Date pCi/L :!: 2 SD (MDC) pCi/L :!: 2 SD (MDC) pCi/L (MDC)
Hunts Station 2/13/01 16:!: 135 (222) ND (1.5)
Flowing Well 2/13/01 -.29 :!: 134 (222) ND (1.6)
Well H-2 2/13/01 43 :!: 136 (222) ND (1.8)
Well H-3 2/15/01 No Sample
Well HS-l 2/15/01 29.5:!: 135 (222) ND (1.6)
Well HC-l 2/15/01 -81 :!: 3.0 (5.0) ND (3.1)
Well HC-2 2/13/01 15 :!: 135 (222) ND (1.7)
Well HC-3 2/13/01 34 :!: 135 (222) ND (1.8)
Well HC-4 2/21/01 220:!: 139 (222) ND (1.7)
Well HC-5 2/09/01 20 :!: 134 (222) ND (1.8)
Well HC-6 2/14/01 43 :!: 136 (222) ND (1.6)
Well HC -7 2/23/01 7.6 :!: 3.2 (5.0) ND (1.8)
Well HC-8 2/15/01 -.30 + 134 (222) ND (2.0)
(a) Indicate results are less than MDC (emiched or conventional method).
(b) Value in parenthesis represents 137Cs MDC (pCi/L).
ND Non-detected.
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. ABC and El Paso
Natural Gas Co., conducted near Gobemador, 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 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).
Annual sampling at Project GASBUGGY was completed during June 13-15,2001. All of the
routine sampling locations were collected except for the Arnold Ranch Spring which was dry (see
Figure 5).
2.5.1 Water Analysis Results
The Cave Springs sampling site yielded enriched tritium activities of 8.1 :!: 4.0 pCiIL which is less
than -0.04 percent of the DCG and similar to the range seen in previous years. Tritium samples
from the other locations with the exception of EPNG 10-36 were all below the average MDC.
Well EPNG 10-36 has yielded tritium activities between 100 and 560 pCiIL in each year since
1984, except in 1987. The sample collected in June 2001, yielded a tritium activity of 78.2:!: 4.8
pCiIL. 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 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.
All gamma-ray spectral analysis results indicated that no man-made gamma-ray emitting
radionuclides were present in any onsite and offsite samples above minimum detectable levels.
2.5.2 Conclusions
Tritium concentrations of water samples collected onsite and offsite are consistent with those of
past studies at the GAS BUGGY Site.
13
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. Pond N. of
. Well 30.3.32.343N
Well 30.3.32.343N
Bixler Ranch.
Cedar Springs.
Cave Springs.
~
N
. Well 28.3.33.233S
Arnold Ranch Spring
Arnold Ranch Well
.10
LOCATION MAP
o
8
o Surface Ground Zero
. Water Sampling Locations
Scale in Miles
o 5
..-~
Scale in Kilometers
Figure 5. GASBUGGY Site sampling locations for June 2001.
14
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A
1 . R
1 ~
w
S
1
c
nalYSlS esu ts or ater amp es ollected at GAS BUGGY Site - June 2001
TABLE 5
Sample Collection Enriched Tritium Tritium(a) Gamma Spectrometry(b)
Location Date pCiIL :t 2 SD (MDC) pCifL :t 2 SD (MDC) pCifL (MDC)
Arnold Ranch 6/15/01 Not Sampled
Spring Well Dry
Bubbling Springs 6/13/01 Not sampled
Well Dry
Cave Springs 6/14/01 8.1 :t 4.0 (6.4) ND (4.5)
Cedar Springs 6/15/01 47.3:t 131 (213) ND (4.9)
La J ara Creek 6/13/01 7.4 :t 130 (213) ND (4.5)
Lower Burro 6/14/01 -19.2 :t 129 (213) ND (4.5)
Canyon
-
Pond N. of Well 6/14/01 29.6:t 130 (213) ND (4.7)
30.3.32.343
Well EPNG-1O-36 6/13/01 78.2 :t 4.8 (5.8) ND ( 4.1)
Jicarilla Well 1 6/14/01 25.2 :t 130 (213) ND (4.3)
Well 28.3.33.233 6/14/01 78.4 :t 131 (213) ND (4.9)
(South)
Well 30.3.32.343 6/14/01 -50.3 :t 128 (213) ND (4.9)
(North)
Windmill #2 6/14/01 -1O.3:t 129 (213) ND (4.8)
Arnold Ranch Well 6/15/01 0.15:t3.3 (5.5) ND (4.9)
(a) Indicate results are less than MDC (enriched or conventional method).
(b) Value in parenthesis represents I37Cs MDC (pCifL).
ND Non-detected.
2.6 Sampling at Project GNOME, New Mexico
Project GNOME, conducted on December 10, 1961, near Carlsbad, New Mexico, was a
multipurpose test emplaced at a depth of 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.
15
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Radioactive gases were accidentally vented following the test. In 1963, USGS conducted a tracer
study involving injection of 20 Ci tritium, 10 Ci I37Cs, 10 Ci 90Sr, 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.
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.
Annual sampling at Project GNOME was completed on June 19-21,2001. 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.
2.6.1 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 DD-l, LRL-7,
USGS-4, and USGS-8 ranged from 1.5 x 103 (LRL-7) to 4.2 x 107 (DD-l) pCiIL. 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.
In dd" . . 137C d 90s
a Ihon to tntmm, s an r concentrations were observed in samples from of Wells DD-
1, LRL-7, and USGS-8, while 90Sr activity was detected in Well USGS-4 as in previous years (see
Table 7). No tritium was detected in the remaining sampling locations, including Well USGS-I,
which the DR! 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.
2.6.2 Conclusion
No radioactive materials attributable to the GNOME Test were detected in samples collected in
the offsite areas during June of 2001.
16
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Carls bad
Carls bad
City.
Well?
.
Loving City
Well 2
~
N
PHS Well 6 .
PHS Well 9 .
.
PHS Well 10
. PHS Well 8
Scale in Miles
.0 5 10
~
EDDY
COUNTY
o
5 10 15
Scale in Kilometers
NEW.
MEXICO
o Surface Ground Zero
. Water Sampling Locations
Figure 6. GNOME Site sampling locations for June 2001.
17
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Tritium Results for Water Samples Collected at GNOME Site. June 2001
TABLE 6
Sample Collection Enriched Tritium Tritium Gamma Spectrometry(b)
Location Date pCi/L :t 2 SD (MDC) pCi/L :t 2 SD (MDC) pCi/L (MDC)
Well 7 City 6/19/01 6.4 :t 3.5 (5.6) ND (4.9)
Well 2 City 6/19/01 26.9:t 135(a) (222) ND (4.5)
PHS 6 6/19/01 41:t 135(a) (222) ND (5.0)
PHS 8 6/19/01 -99.4 :t 133(a) (222) ND (4.6)
PHS 9 6/19/01 -74.9:t 133(a) (222) ND (4.7)
PHS 10 6/19/01 -74.9:t 133(a) (222) ND (4.5)
USGS Well 1 6/19/01 55 :t 136(a) (222) ND (4.6)
USGS Well 4 6/20/01 6.3 x 104:t 558 (222) ND (1.6)
Well USGS 8 6/20/01 5.2 x 104:t 512 (222) Cs-137
68.8 :t 10.6 (1.6)
J. Mobley Ranch 6/19/01 7.0:t4.2 (6.6) ND (5.0)
Well DD-l 6/21/01 4.2 x107 :t 646 (222) Cs-137
6.4x105 :t 9.7x104
LRL-7 6/20/01 1.5x103 :t 158 (222) Cs-137
34.3 + 5.8 (1.8)
(a) Indicate results are less than MDC (enriched or conventional method).
(b) Value in parenthesis represents 137Cs MDC (pCi/L).
ND Non-detected.
18
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REFERENCES
Chapman & Hockett, 1991. Evaluation of Groundwater Monitoring at Offsite Nuclear Test
Areas, Las Vegas, NV, Desert Research Institute, University of Nevada System, Report
DOE/NV/10845-07.
Code of Federal Regulations, Vol. 41, title 40, Part 141, July 9,1976, National Interim Primary
Drinking Water Regulations.
A Guide for Environmental Radiological Surveillance at U.S. Dept. of Energy Installations, July
1981, Office of Operational Safety Report. Las Vegas, NV: U.S. Department of Energy;
DOEIEP-0023.
Johns, F., et aI. 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 6001R-941209.
19
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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 (J.LCi) is 0.000001 Ci.
Isotope
Atoms of the same element with different numbers of neutrons in the nuclei. Thus 12C, l3C, and
14C 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 l3C are stable, 14C 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
pCiIL.
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.
20
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Appendix
Typical MDA Values for Gamma Spectroscopy
(100 minute count time)
Geometry*
Matrix
Volume
Isotope
Marinelli
Water
3.5 liter
MDA
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
Model 430G
Density 1.0 g/ml
Units pCiIL
Isotope MDA
Ru-106 4.76E+01
Sn-l13 8.3 2E+00
Sb-125 1.65E+01
1-131 8.28E+00
Ba-133 9. 16E+00
Cs-134 6. 12E+00
Cs-137 6.43E+00
Ce-144 7.59E+01
Eu-152 2. 86E+0 1
Ra-226 1. 58E+01
U-235 1.01E+02
Am-241 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 determing 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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