Annual Water Sampling and Analysis at the Salmon Test Site Area Lamar County, Mississippi April 2006 by James R. Harris Jr. Prepared for the U.S. Department of Energy under Interagency Agreement DE-AI08-96NV11969 RADIATION AND INDOOR ENVIRONMENTS NATIONAL LABORATORY OFFICE OF RADIATION AND INDOOR AIR U.S. ENVIRONMENTAL PROTECTION AGENCY P.O. BOX 98517 LAS VEGAS, NV 89193-8517 ------- NOTICE The information in this document has been funded wholly or in part by the United Slates Environmental Protection Agency (U.S. EPA) through an Interagency Agreement [(LAG) DE-AI 08-96NV11969] from the United States Department of Energy (U.S. DOE). It has been subjected to the Agency's peer and administrative reviews, and it has been approved for publication as an EPA document. Mention of trade names or commercial products does not constitute endorsement or recommendation for use. ------- ABSTRACT The Long-Term Hydrological Monitoring Program (LTI-IMP), directed by the EPA, conducts annual water sampling on and around the Salmon Test Site Area. In 1964 and 1966, nuclear explosives were detonated approximately 2,700 feet (823 m) underground at the Salmon Test Site Area located in Lamar County, Mississippi. Drilling and clean-up activities have resulted in tritium contamination in close proxiimty to the surface ground zero. In this report, the 2006 annual water sampling at the Salmon Site is described, and the analytical results of the collected samples are given. The highest tritium concentration onsite was 7.2 x pCi/L in water from well SAl-lI-I (see Appendix B). No radioactivity attributable to the test site was found in any offsite water sample The highest tritium concentration offsite was 9.4 ± 3.5 pCi/L at the James D. Lowe pond. Negative values for tntium aie obtained when the counts registered on the liquid scintillation counter for a regular sample are less than the average counts obtained for the fossil water samples used as background samples. The average background counts are deducted from the sample counts to correct for background radiation affecting the detector in the scintillation counter. It is normal to get some negative values for samples with little or no tritium in them due to statistical counting vanations; hence environmental samples are at background levels. The incidence of negative results is slightly higher this year than in past years due to a change in the scintillation cocktail used for counting. We are no longer able to use the Beckman ReadySafe scintillation cocktail used in previous years because a change in the formulation has substantially raised the background counts from around 3 5 to 12 counts per minute The result is to ncai ly double the detection limit and the 2-sigma error for the samples is unacceptable. All of the replacement scintillation cocktails show a slightly greater variability in counting resulting in more instances where the average background counts exceed the counts for the low activity samples We are now using EcoLume liquid scintillation cocktail All samples were also analyzed for the presence of gamma-ray emitting radionuclides. None were detected above the minimum detectable concentration (MDC) (see Appendix B). iii ------- This page is left blank intentionally. Iv ------- CONTENTS Page Notice . ii Abstract iii Contents v Figures vi Acronyms and Abbreviations vii/viii Acknowledgments ix Introduction 1 History Historical Monitoring Results 2 Sample Collection 9 Sample Analysis 10 Water Analysis Results 10/11 References 12 Glossary of Terms 13/14 Appendices A. Summary of Analytical Procedures 15 B. Gamma/Tritium Results for Water Samples Collected in April 2006 16/17 C. R&IEs LTHMP related SOPs 18 V ------- FIG URES I Figure Number Page I 1 General site location of Project Salmon Test Site Ai-ea 3 2 Topographic map of the Salmon Test Site Area showing the Surface Ground Zero and outline of Test Area at 2,700 feet below land surface 4 3 Test cavity and aquifers 5 4 Tritium concentration vs. sanipling year for HM-S (depth 30 fl) 6 5 Tritium concentration vs. sampling year for HM-L (depth = 200 fi) 6 6 Locatioiis on the Salmon Test Site Area sampled in 2006 7 7 Offsite locations sampled in 2006 .8 vi ------- ACRONYMS AND ABBREVIATiONS AEC U.S. Atomic Energy Commission Bq/L Becquerel per liter 37 Cs Cesium-I 37 60 Co Cobalt-GO CERMER Center for Environmental Restoration Monitoring and Emergency Response CRQA Center for Radioanalysis and Quality Assurance DCG Derived Concentration Guide DOE U.S. Department olEnergy EPA U.S. Environmental Protection Agency Frac Tank storage container gram Tritiurn 3 H+ Enriched Tritium HpGe high purity germanium gamma detector HM-L, HM-L2 Hydrological Monitoring Well - Local Aquifer HM-S Hydrological Monitoring Well - Surficial Aquifer HM-l Hydrological Monitoring Well - Aquifer I HM-2a Hydrological Monitoring Well - Aquifer 2a HM-2b Hydrological Monitoring Well - Aquifer 2b E-TM-3 Hydrological Monitoring Well - Aquifer 3 lAG Interagency Agreement ITC international Technology Corporation Iodine 131 keV kilo electron volts = thdusand electron volts kg kilogram, 1000 grams kt kiloton (TNT equivalent) L liter LTHMP Long Term Hydrological Monitoring Program ni meter MCL maximum contaminant level MDA minimum detectable activity MDC mi i ii mum detectable concentration MeV one million electron volts miii minute mL milliliter = one thousandth of a liter MT megaton (one million tons TNT equivalent) ORI A Office of Radiation and Indoor Air pCi/L picocuries per liter= lOi2 curies per liter= l/I,000,000,000,000 curies per liter PHS U.S. Public Health Service REECo Reynolds Electrical & Engineering Company vii ------- ACRONYMS AND ABBREVIATIONS Continued R&IE Radiation and Indoor Environments National Laboiatoiy, Las Vegas, NV 90 Sr Strontium-90 SA Wells Source Area Wells SGZ surface ground zero USGS U.S. Geological Survey Xenon-131 Xenon-133 vii ------- ACKNOWLEDGMENTS External peer review was provided by Vernon Hodge, Ph.D., Department of Chemistry, University of Nevada, Las Vegas. In addition, the author would like to acknowledge George Dilbeck, Ph.D., and Richard Flotard, Ph.D., as internal reviewers. A special thanks to Mr. Max G. Davis, USEPA (Ret.) for h assistance and continuous support in the outlined structure of this final product. Thanks also to Natalia Brooks, Mark Ovrebo, of the General Dynamics Corp, IT contractors, for their assistance and significant contributions in this reports/production. Finally the basis of this report could not have happened without the efforts of the large and dedicated LTHMP Field Sampling Team pictured below which made all our work possible. Left to right front row seated: Rose (Kitty) Houston, R&IE (EPALV, NV), Nonya Cage, Mississippi Radiological Health Dept (MRHD), Jackson, MS, Catherine Martin, Stoller/Navarro DOE/LV, NV., contractor, Karl Barber, MRHD. 2 row: David Traub, Stoller, Grand Junction, CO. contractor, Dorsey Hamlin, MRDH, Wesley Boyd, R&IE, Erik Hadwin, Weston Corp., Baton Rouge, LA., contractor. row: Jimmy L. Carson, MRHD, Helly Diaz-Marcano, R&IE LV., Douglas Sharp, R&IE. IF- pg ix ------- INTRODUCTiON Under an Interagency Agreement (JAG) with the DOE, the EPAs Radiation and Indoor Environments National Laboratory (R&IE) located in Las Vegas, NV, conducts annual sampling to measure radioactivity in water sources near the sites of underground nuclear explosions. The results provide assurance that radioactive materials from the tests have not migrated into potable drinking water supplies. This report presents the results for samples collected under EPAs LTHMP in April 2006, on and around the Salmon Test Site Area, Lamar County, Mississippi. History Project Dribble, consisting of two nuclear explosions, and Project Miracle Play, consisting of two non-nuclear gas explosions, were conducted in the Salmon Test Site Area, near Baxterville, Lamar County, Mississippi, between 1964 and 1970. The general area is depicted in Figure 1. The Salmon Test Site Area (Figure 2) contains approximately 1,470 acres located in Sections 11, 12, 13, and 14, Township 2 North, Range 16 West. Test Date Name Type Yield (kt) 10-22-64 Salmon Nuclear 5.3 12-03-66 Sterling Nuclear 0.38 02-02-69 Diode Tube Gas 0.32 04-19-70 Humid Water Gas 0.32 These tests were part of the Vela Uniform Program of the U.S. Atomic Energy Commission (a predecessor agency of the DOE). The purpose was to measure and evaluate the phenomena of seismic waves that are induced from the explosions as compared to those that occur naturally from earthquakes.The first explosion, the Salmon Event, created a cavity in the salt dome underlying the test area. The top of the cavity is 1,160 feet (354 m) below the lop of the salt dome which lies 1,500 feet (457 m) below the land surface (Figure 3). The Salmon detonation cavity was subsequently used to contain the next three explosions. Following each detonation, the surrounding area was closely monitored by the U.S. Public Health Service (PHS). Radiological monitoring became the responsibility of the EPA at its inception in 1970, and after the second site cleanup operation in 1971-72, the LTHMP was instituted. In this program, all potable aquifers, several wells, public water supplies, and selected surface waters in the vicinity of the Salmon Test Site are sampled on an annual basis and analyzed to determine the presence of tritium, gamma and other radioactive contaminants. ------- Histoi-ical Monitoring Results The disposal of drilling mud and fluids iiear the surface ground zero (SGZ) is responsible for tritium ( 3 H) contamination of the soil zone and underlying shallow aquifer. These waters lie at depths of 4 to 10 feet (1.2 to 3 rn) and 30 feet (9 m), respectively, and ai-e not potable. Tritiurn contamination is also present in the potable water of the local aquifer which lies at about 200 feet (61 m). The observed 3 H concentration in the local aquifer is significantly below the 20,000 pCiIL guideline specified in the National Primary Drinking Water Regulations; Radionuclides; Final Rule (4OCFR9/141/142), and is thought to be due to drilling activities at the site (Fenske and Humphrey, 1980; Fordham and Fenske, 1985). 2 ------- La u re OakvaieS EtIisviIie S Bassfieid SartinvilIe McComb Runne lstown MISSISSIPPI LOUISIANA Baxterville Vamado Bogalusa Poplarville Wiggins McNeil McHenry Major Highway Test Site, SGZ L L !t MkU LAMAR COUNT( LOCATiON MAP u I. ( eiwra I site location of Project Sal mon Test Site A rca . ------- ffik a M m m n , bad *i i a railis 4 & MON TEST 1E A I I 4 N 0 OOALIR4PI, 0 i: 011 JW 4 ------- j LIMESTONE SANDSTONE *The test cavity contains fission and activation products fro 10,770 cubic yards of radioactive, contaminated soils and contaminated fluids and water from surfac. cleanup. m the detonations plus 1.305000 gaHons of Figure 3. Sn irnon Site Test C avity and Aquifers, CITRON ELLE AOL) IFER HALF MOON CREEK ALLU VIAL AQU IF ER / HOLE P.5.1 LOCAL AQUIFER 2A 28 3A RECRYSTALLIZED MELT PUDDLE 5 ------- 4S ja. 2. mll flIHmu Figure 4. Tritium concentration vs. sampling year for HM-S (depth = 30 ft). N ,so I CaIeridat Year Figure 5. Tritium concentration vs. sampling year for HM-L (depth = 200 ft). 6 ------- M$.7.Il Mi441 M$-4-H &κd$ 1 $ &M u sr Ii LA, mh . Ii ure 6. Onsite sampling locations sampled 2006. 7 ------- uc--- - , ro . ur ii L , dons k Figure 7. Offsite sampling locations sampled 2006 . 8 ------- Sample Collection According to standard operating procedures agreed to by DOE (U.S. DOE 1981), the shallow wells are first sampled, pumped-down, and resampled on the following day. Wells HM-l, HM-2A, HM-2B, HM-3, and HM-L, which lie adjacent to SGZ, were first sampled and then pumped steadily while further samples were taken at 30 minutes intervals until the pH and conductivity of the water stabilized. A final sample was taken from each well 30 minutes after stability was reached. Water samples were taken from sources near the SGZ area (i.e., Half Moon Creek, Half Moon Creek Overflow, and the Pond west of SGZ), before and after the pumping operations to identify any resulting changes in tritium concentration from previous years. Well HM-L2 was first sampled and then pumped for one hour before a second sample was taken and shut down. For wells with operating pumps, the samples were collected at the nearest convenient outlet. If the well has no pump, a truck-mounted or a submersible pump is used. Using this truck mounted unit, it is possible to collect three-liter samples from wells as deep as 1829 meters (6,000 ft.). The pH, conductivity, water temperature, and sampling waler level was measured and recorded as each sample was collected. Waste water contained from wells HM-3, SAI-7-H, and SAl -2-H, SAl-I-H was contained in a Frac Tank and then disposed of offsite by DOE, contractor Stoller Navarro. In November 2000, the U.S DOE awarded a grant to Lamar County, Mississippi. The grant provided an extension of the current drinking water system around the Salmon Test Site. The water system eliminated the need to sample residential wells in the area and around the site. However, the EPA and the State of Mississippi will continue monitoring wells and surface locations onsite and offsite annually. The offsite sampling sites will consist of city wells in Purvis, Baxterville, Columbia, and Lumberton, as well as some local residents, ponds and streams. In 2002, the U.S. DOE plugged 33 wells on the Salmon Site. There are 28 wells, 3 mud pits, 1 pond, and 2 creek locations remaining in the LTHMP that will be sampled annually onsite. If the reader would like more information on the plugged wells, they should contact the U.S. DOE in Las Vegas, Nevada. The locations of all sampling sites are shown on pages 7 and 8. Sampling results are discussed in the sections that follow. 9 ------- Sample Analysis Radiochernical laboratory procedures used to analyze the samples collected for this report are summarized in R&IEs SOPs (see Appendix A and C). These include standard methods to identify natural and man-made gamma-emitting radionuclides, tritiuni, plutonium, strontium, and uranium in water samples. Two types of tritiurn analyses are performed: conventional and electrolytic enrichment. The enrichment method lowers the mini mum detectable concentration (MDC) froni approximately 300 pCi/L to about 5 pCi/L. An upper activity limit of 800 pCi/L as specified in SOP RQA-603 has been established for the tritium enrichment method because sample cross- contamination becomes a problem at higher levels. In late 1995, it was decided that a maximum of 25 percent of all samples collected would be analyzed by the low-level enrichment method. This decision was based on the time required for analysis, budgetary constraints, and an assessment of past results. Under the current sampling and analysis protocols for the site, all samples are initially screened for tritium activity by the conventional method and selected samples enriched. At this time, only sampling locations that are in position to show migration are selected for enrichment. Sufficient sample is collected from new sampling locations to perform all routine analysis and a full-suite of other radiochemical determinations including assays for strontium-90, plutonium, and urani urn. \Vater Analysis Results No radioactive materials from the Salmon Test Site Area were detected in any water sample collected offsite; nor were tritium concentrations above normal background values detected in any offsite sample. Gamma-ray spectral analysis results indicated that no man-made gamma-emitting radionuclides were detected in either onsite or offsite samples. The highest tritium concentration found onsite was 7.2 x10 3 pCi/L. This was detected in a water sample collected from Well SA1-1H which is a shallow well (40) near SGZ. The water from this well is not available to the public, nor is it potable. Long-term decreasing trends in tritium concentrations are evident for onsite locations that have shown detectable tritium activity since monitoring began under the LTI-IMP in 1980 (wells HM-S and HM-L, depicted in Figures 4 and 5). in all, seven onsi tc sampling locations exhibited tritium concentrations above the MDC (Well HM-L, Well HM-S, Well HMH-5R, SAI-IH, SA-l-2H, SAI-3-H, SAI-5-H). Tritium concentrations in the offsite samples ranged from less than the MDC to 9.4 pCi/L ( 0.3 Bq/L). These results are typical of background tritium levels and do not exceed the tritium activity expected in local precipitation. 10 ------- Water Analysis Results Continue Due to the high rainfall in the area, the sampling procedure for selected onsite wells was modified as follows: after collecti n of an initial sample, wells were purged and a second sample is collected the following day after the well has recharged. The second sample is representative of water that has infiltrated through the soil zone, where as the first sample may represent a mixture of direct rainwater influx at the top of the well and infiltrated soil zone water. A total of 21 of the 34 onsite locations were sampled in this manner (pre-and post- sampling): 10 yielded tritium activities greater than the MDC in either the first or second sample. Of these, 10 yielded results higher than normal background (approximately 25 - 40 pCi/L [ 0.9 - 1.5 Bq/L]) as shown in Appendix B. The locations where the highest tritium activities were measured generally correspond to areas of known contamination. In summary, tritium concentrations in the water samples collected this year at the Salmon Site are consistent with those of past studies: Onsite tritium concentrations, were all below the 20,000 pCi/L maximum contaminant level (MCL) defined in EPAs National Primary Drinking Water Regulations; Radionuclides; Final Rule (4OCFR9/141/142); and, the highest tritium concentration found offsite was 9.4 ± 3.5 pCifL which was at the James D. Lowe Pond, (<1/10 of 1% (0.05%) of EPAs MCL. All samples were analyzed for presence of gamma-ray emitting radionuclides and none were detected (see Appendix B on pages 16-17). 11 ------- REFE RENCES Final rule on Dec. 7, 2000. Code of Federal Regulations, Vol. 65, Title 40, Parts 9, 141, and 142, December 7, 2000, National Primary Drinking Water Regulations; Radionuclides; Final Rule. A Guide for Environmental Radiological Surveillance at U.S. Dept. of Energy Installations, July 198 l,Office of Operational Safety Report. Las Vegas, NV: U.S. Department of Energy; DOE/EP-0023. Fenske, P. R.; Humphrey, T. M., Jr. The Tatum Dome Project Lamar County, Mississippi. Las Vegas, NV: U.S. Department of Energy, Nevada Operations Office, NVO-225; 1980. Fordham, J. W; Fenske, P. R. Tatum Dome Field Study Report and Monitoniig Data Analysis, Las Vegas, NV: U.S. Department of Energy, Nevada Operations Office; DOE/NV/10384-03; 1985. 12 ------- GLOSSARY OF TERMS Background Radiation The radiation in mans environment, including cosmic rays and radiation from naturally-occurring and man-made radioactive elements, both outside and inside the bodies of humans and animals. The usually quoted average individual exposure from background radiation is 125 millireni per year iii mid-latitudes at sea level (Shein & Terplak, 1984). Curie (Ci) The basic unit used to describe the rate of radioactive disintegration. The curie is equal to 37 billion disintegrations per second, which is the equivalent of 1 gram of radium. Named for Marie and Pierre Curie who discovered radium in 1898. One microcurie ( tCi) is one millionth of a Ci. Isotope Atoms of the same element with different numbers of neutrons in the nuclei. Thus 2 C, 3 C, and 14 C are isotopes of the element carbon, the numbers denoting the approximate atomic weights. Isotopes have very nearly the same chemical properties, but oflen different physical properties (for example 2 C and U C are stable, i4 C is radioactive). Enrichment Method A method of electrolytic concentration that increases the sensitivity of the analysis of tritium in water. This method is used by R&IE in selected samples if the tritium concentration is less than 800 pCi/L. Minimum Detectable Activity (MDA) Minimum detectable activity. Minimum Detectable Concentration (MDC) The smallest amount of radioactivity that can be reliably detected with a probability of Type I and Type TI errors at 5 percent each (DOE 1981). o ITs ite Areas exclusive of the immediate Salmon Test Site Area. Onsite Refers to the immediate vicinity of the Salmon Test Site Area. Shallow ground water Water found near the soil surface, caused by precipitation infiltration of the soil. This shallow ground water is not an aquifer. 13 ------- GLOSSARY OF TERMS (Continue) Surficial Aquifer The ground water layer located closest to the surface, generally at a depth of approximately 30 feet at SGZ. Triti u in A radioactive isotope of hydrogen that decays by beta emission. Its half-life is about 12.5 years. Pre Sample First sample taken from wells onsite (before pumping). Post Sample Last sample taken from wells onsite (after recharge). Type I Error The statistical error of accepting the presence of radioactivity when none is present. Sometimes called alpha enor. Type II Error The statistical error of failing to recognize the presence of radioactivity when it is present. Sometimes called beta error. 14 ------- Appendix A Summary of Analytical Procedures Counting Sample Appro inia Ic lype of Analysis Analytical Period Analytical Procedures Size l)eectioiu Liiiiit Equipment (Mm) counted 1-lpGe Gamma b HpGe detectoi 150 Radionuclide 3 5L Vanes with calibrated at concemi ation quantified i adionucl ides and 0 5 flom gamma spectial data cletectoi used, keV/channe l by online computel noi mally counted (0.04 to 2 P 1 ogi am to a MDC of MeV iange) appiox 5 pCi/L Individual fbi Cs-137 detectoi efficiencies ranging fiom 15 to 35% 3 H Automatic 300 Sample piepared by 4 mL 300 pCi/L liquid distillation scintillation counter. Automatic 300 Sample is distilled 5 mL 5 pCi/L Enrichment liquid concentiated by scintillation electrolysis followed by counter re-distillation. The detection limit is defined as the smallest amount of iadioactivity that can be ieliably detected, ic, piobability oflype I and Type II eiioi at 5 peicent each (DOE 1981) (b) Gamma spectiometiy using a high put ily intiinsic germanium (l-lpGe) detectot Typical MDA Values for Gamma Spectroscopy (100 minute count time) Marinelli atci 3.5 liter Model l)eusity Units 430G 1.0 g/mL pCi/L Isotope MDA Isotope MDA Ru-106 4.76E+0l Be-7 4.56E+01 Sn-I 13 8.32 13+00 K-40 492E+01 Sb-125 l.65E-i-0l Ci-51 588E+01 1-131 828E+00 Mn-54 4.55E+0l Ba-133 9 1613+00 Co-57 965E+00 Cs-134 6 12E+00 Co-58 471E+00 Cs-l37 64313+00 Fc-59 1.07E+0I Ce-144 7 59E+Ol Co-60 5.38E+00 Eu-l52 286134-01 Zn-65 1 24E+01 Ra-226 I 58E+Ol Nb-95 5.64E+00 U-235 I OIE+02 Zi-95 9 06E+00 Arn-24 1 6.6013+01 15 ------- OtT-Site sa,iipliiig locations Ba.tciville City Well Lowci Little Cieck NI Lower Littic Crcck #2 Lunibcrton City Vcll #2 Puivis City Supply VeIl City Well 46-003-5-6-7 James D Lowc Pond Ilowaid Smith Pond Thompson l3luc Stoic Gieeiwillc Comm Ctr 4-17 Noblcs Pond 4-17 13 R Andeison Pond 4-17 Indicates results arc less than MDC (bI No gamma radionuclides detected above MDC ND - Non-detected, MDC for ganima represents 37 Cs (pCu/L) MDC Minimum Detectable Concentration Gauim ia Spcctu-oiiic l iv Coiiiuiieiits (b) pCu/l_ Ml)C NI) (4 9) -48 ± I39 (231) NI) (30) NI) (4 6) NI) (49) NI) (4 8) NI) (4 8) NI) (4 9) NI) (4 9) Ill ± I43 (231) l3ackgiound NI) (4 9) sample ioi I-lUll w,iIci 4-17 4-17 4-18 4-I l 4-18 4-17 4-18 4-17 4-18 4-17 4-18 4-17 4-17 4-17 4-17 4-17 4-17 4-Il 4-17 4-I l 4-I l 4-li 4-17 -24 ± I40 (231) -72 ± I40 (231) 2130 ± 167 (222) 3 1l(only) 2710 ± 175 (222) 3 1 1(only) 45 ± 35(a) (222) II (only) 21 ± I 35 (222) I-I (only) 400 ± 149 (231) si-i (only) 534 ± 152 (231) si-i (only) 142 ± l36 (219) 222 ± 137 (219) 177 e 136w (219) III ± l35 (219) 187 * l36 (219) 20 ± l34 (219) -21 ± l33 (219) -28 ± l33 (219) 80 ± I35 (219) 28 ± I33 (219) NI) (50) ND (47) NI) (4 8) ND (49) ND (49) NI) (49) ND (43) ND (48) NI) (4 9) ND (46) ND (47) NI) (4 9) ND (50) ND (47) NI) (46) NI) (49) Snun 1 ilc Location Appendix B Gamma/Tritium Results for ater Samples Collected in April 2006 Ti ilium pCiIL ± 2 SD MDC Collection I)ate 2006 4-18 4-Il 4-17 4-18 4-18 4-18 4-Il 4-Il 4-17 Enriched Tritiuni pCiIL ± 2 SD MDC 70 ± 30 (50) 60 ± 30 (50) 94 * 35 (50) 85 ± 39 (62) -87 ± I 38 (231) -58 ± I 39(i) (231) 67 ± l42 (231) -43 ± I39 (231) 119 ± I4l (231) 77 ± I39 (231) NI) (50) NI) (4 6) NI) (50) Appendix B Cainma/Tritium Results lot- Vater Samples Collected in April 2006 Eiiriclicd Trituiiiii Trititi in pCUL ± 2 SD MDC pCiIL ± 2 SD MDC Gaiiim.i COIn iIICIll , Sped i U unetry 1 iCi/L MI)C Sample Collection I)ate Localiou 2006 Oiisute Miunliluuig locntion VcIl E-7 Ila lf Moon Pre Cicck Post llalfMooii Crk Pre Ovci how Half Moon Crk Ovei how Post Well IIMII5R Prc Post Well IIMIII6R Pre lost \VcIl IIM-S Pie Post VclI hIM-L Pre I 30 Miii 2 d 30 Mm 3 rd 30 Mm 4 th 30 M in 5 th 30 Mm Post Wcll IIM-l Pie lu 30Mm 2 30 Miii 3 30 Miii Post -09 ± 40 (60) 75 ± 40 (60) 82 * 40 (50) 212 ± 60 (50) 123 * 50 (50) ND (49) 16 ------- Appendix B Gainma/Tritium Results for Water Samples Collected in April 2006 (Continued) Sample Collection I)alc Location 2006 Oimsite so mupliimg locations (Continued) VcII HM-2A Pre 4-17 la3OMiil 4-17 2 30Mmn 4-17 3rd3OMlil 4-I l Post 4-17 \VeII IIM-2 13 Pie 4 17 la3OMmn 4-17 Post 4-17 WcIIIIM-3 lrc 4-17 lu3OMIn 4-17 2 30Mm 4-Il 3rd3OMin 4-17 Post 4-17 RE Co Pit Diainage-A 4-19 RECCo Pit Drainage-B 4-19 RECCo Pit Diainagc-C 4-19 I IM-L2 Imc 4-18 Post 4-18 Pond West oIGZ Pre 4-Il Post 4-18 SAl-I-Il Pre 4-Il SAI-8-L SAl-I 1-3 SA 1- 12-Il SA2-I-L SA2-2-L SA2-4-L SA3-4-Il SA3-l 1-3 SA4-5-L SA5-4-4 SA5-5-4 Frac Tank Frac Tank Filici Post Pre Post Pie Post Pre Post Pie Post Pie Post Pre Post 6 ± 31° (50) 15 ± 31° (50) 92 ± 33 (50) 76 ± 54° (90) 86 ± 50 (80) 128 * 72 (90) 125 ± 69 (80) 52 ± 48 (80) 62 ± 58 (90) SI * 54° (90) 91 ± 50 (80) 23 ± 4901 (50) 61 * 48° (80) 50 ± 47 (SO) -22 * 4 0° (6 7) 42 ± 47ia 1 (76) -34 ± 40° (68) 57 5 3° (9 0) 37 ± 49° (90) 35 ± 134° (219) 10 th l33 ° (219) 14 ± 133111 (219) Ii ± I34° (219) 31 ± 134 ° (219) -17 133° (219) 35 ± 133 (1 ) (219) 10 ± 133° (219) 62 ± I34 ° (219) -197 + 144° (245) -130 ± 146 ° (245) 7170 ± 227 (222) 3 1-I (only) 925 ± ISO (222) II (only) 744 & 147 (222) II (only) 216 ± I 38° (222) H (only) 251 ± 139 (222) II (only) 70 ± I 34° (222) II (only) 122 + I 37(1) (222) H (only) ii (only) ii (only) ii (only) H (only) ii (only) ii (only) No Sample 56 ± l36 ° (223) 136 ± I 37° (222) II (only) 56 ± 136° (222) ii (only) 84 ± 137° (223) ND (50) ND (50) ND (50) ND (50) ND (48) ND (50) NI) (50) NI) (47) NI) (50) NI) (4 9) ND (47) ND (50) Nt) (4 7) NI) (4 8) NI) (50) NI) (4 9) ND (50) NI) (50) ND (50) ND (49) ND (49) NI) (50) ND (49) (4 9) (4 9) (7 6) Enriched ruu (I I I Iii li itiului pCiIL ± 2 SD MDC pCi!L ± 2 SD MDC Ca nina Coinuimeuuts Sped 1(1111(11 5 1 )Cu/L MI)C 37 ± 52(1) (90) No Sample No Sample No S mpIe SAI-2-ll SAI-3-ll SAI-4-II SAl-S-Il SAI-6-Il SAI-7-H 6450 ± 219 (222) 3 1I(only) 4-IS 4-17 4-IS 4- 17 4-18 4-17 4-I8 4.17 4-18 4-17 4-18 4-17 4-18 4-19 4-19 4-17 4-18 4-19 4-19 4-19 4-17 4-IS 4-20 4-20 4-20 4-20 4-20 4-20 Pie Post Prc Post II (only) II (only) Indicates ucsults arc less Ihan MDC (b) No gamma radionuclides detected above MDC ND - Non-detected, MDC for gamma represents 37 Cs (pCu/L) MDC - Minimum Detectable Conccntuatuon No Sample NI) ND Ganiuiizm SL1SpCi1dC(I ND Only watci liltem 17 ------- Appendix C Standard Operating Procedures for the Center for Environmental Restoration, Monitoring & Emergency Response CER-203 Standard Operating Proced tire for the Long-Term Hydrological Monitoring Program Standard Operating Procedures for the Center for Radioanalysis & Quality Assurance RQA-302 Standard Operating Procedures of Gamma-Ray Detector Systems. RQA-602 Ti-iti urn Enrichment Procedure. RQA-603 Standard Operating Procedure for 89Sr and 9OSr in Water, Air Filters and Milk. RQA-604 Standard Operating Procedure of Convention Tritium in Water. RQA-606 Analysis of Plutonium, Uranium and Thorium in Environmental Samples by Alpha Spectroscopy. 18 ------- |