ML20085E167

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Radiological Survey of the Combustion Engineering Burial Site Hematite,Missouri
ML20085E167
Person / Time
Site: 07000036
Issue date: 07/31/1983
From: Booth L, Bronson F, Groff D, Mcdowell G, Peck S, Somers W
RADIATION MANAGEMENT CORP. (RMC)
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
CON-FIN-B-6901 NUREG-CR-3387, NUDOCS 8308010022
Download: ML20085E167 (70)
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{{#Wiki_filter:NUREGICR-3387 Radiological Survey of the Combustion Engineering Burial Site Hematite, Missouri b Prepared by L. F. Booth, D. W. Groff, S. l. Peck G. S. McDowell, W. M. Somers, F. L. Bronson R:diation Management Corporation Prepared for U.S. Nuclear riegulatory Commission l s ,b., ) / u. >oont go u :m s one

4 NOTICE This report was prepared as an account of work sponsored by an agency of the United States Government, Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability of re-sponsibility for any third party's use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:

1. The NRC Public Document Room,1717 H Street, N.W.

Washington, DC 20555

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Referenced documents available for inspection and copying for a fee from the N3C Public Docu-ment Room include NRC correspondence and ir.ternal NRC memoranda; NRC Office of Inspection 1 and Enforcement bulletins, circulars, information notices, inspection and investigation notices; Licensee Event Reports; vendor reports and correspondence; Commission papers; and applicant and - licensee documents and correspondence. The following documents in the NUREG series a e available for purchase from the NRC/GPO Sales - Program: formal NRC staff and contractor reports, NRC sponsored conference proceedings, and N RC booklets and brochures. Also available are Regulatory Guides, NRC regulations in the Code of ' Federal Regulations, and Nuclear Regulatory Commission Issaances. Documents available from the National Technical information Service include NUREG series-reports and technical reports prepared by other federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. f Documents available from public and special technical libraries include' all open literature items, such as books, journal and periodical articles, and transactions. Federal Register notices, federal and state legislation, and congressional reports can usually be obtained from these libraries. l Documents such as theses, dissertations, foreign reports and translations, ar.d non-NRC conference. l l proceedings are available for purchase from the organization sponsoring the publication cited. ~ I Single copies of NRC ' draft. reports are available free upon written request to.the Division of Tech- . nical Information,and Document Control, U.S. Nuclear Regulatory Commission, Washington, DC 20555. ^ ' Copies of industry codes and standards used in a substantive manner in the NRC regulatory process ,.j' are maintained at the NRC Library, 7920 Norfolk' Avenue, Bethesda, Maryland,'and are available there for reference use by the public'.; Codes and standards are usually copyrighted and may be y f purchased from the originating organization or.-if they are American National Standards, from the American National Standards institute 1430 Broadway, New York, NY 10018. i 1 7

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NUREGICR-3387 Radio ogica Survey o" the Combustion Engineering Burial Site Hematite, Missouri Minuscript Completed: June 1983 Date Published: July 1983 Prepared by L. F. Booth, D. W. Groff, S.1. Peck, G. S. McDowell, W. M. Somers, F. L. Bronson Radiation Management Corporation 3356 Commercial Avenue Northbrook, IL 60062 Pr: pared for Division of Fuel Cycle and Material Safety Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Wrihington, D.C. 20555 NRC FIN B6901 l

ABSTRACT This report presents the results of a radiological sur-vey of the burial site adjacent to the Combustion Engineer-Ing (C-E) plant in Hematite, Missouri, performed by Radia-tion Management Corporation (RMC) in the spring and summer of 1982. Measurements were made to determine external radt-ation levels, surface and subsurface radionuclide concentra-tions and radioactivity in air and water. Results show uranium concentrations in burial pits as high as 38 and 21 pCl/g for U-238 and U-235 respectively. Results also show uranium concentrations in surface soils as high as 4.7 and 1.1 pCl/g for U-238 and U-235 respectively. Based on an es-tImated U-234/U-238 activity ratio of about 10 to 1,-the highest U-234 activity In the burial pits is estimated to be approximately 400 pCl/g, and in surface soils approximately 47 pCl/g. Radium and thorium concentrations did not exceed background levels. Radioactivity in water which exceeded EPA drinking water standards was found in two onsite moni-toring wells, til

,d 4 TABLE DE CONTENTS 1 1. INTRODUCTION............................ 1 J 11. SITE CHARACTERISTICS.................... 3 1 j lI1. RADIOLOGICAL SURVEY METHODS............. 6 i IV. RADIOLOGICAL SURVEY RESULTS............ 10 V. CONCLUSl0NS............................ 18 APPENDlY. l............................. 45 a l l l I I I i P' V. -. -,-+, -.,,--4 --.-,,,,c. e,---y , _. ~

LIST DE FIGURES 1. Location of Combustion Engineering Facility,

Hematite, Missouri, 21 2.

Burial site at Combustion Engineering

Facility, Hema-tite, Missouri.

22 3. External exposure rates in uR/hr, Combustion Engineer-Ing Facility Burial Site. 23 4. Locations of surface soll samples. Samples 13 and 14 are sediments from the creek on the east border of the burial site. Samples 15, 16, and 17 are sediments from Joachim Creek. 24 5. Location of bore holes used for subsurface logging and water sampling. 25 6. In situ gamma spectrum at the 2-foot depth in borehole 4, using the IG detector and a 10 minute count time. 26 7. In situ gamma spectrum at the 4-foot depth in borehole 6, using the IG detector and a 10 minute count time. 27 8. Location of water samples. Sample numbers listed in Table 6 are shown in parentheses. 28 l-1 Portable survey instrument kit. 56 l-2 High sensitivity tissue equivalent lonization chamber system. 57 l-3 lon chamber exposure rate vs Nal(TI) count

rate, Combustion Engineering Facility burial site.

58 l-4 Interior of mobile lab showing gamma counting system and other equipment. 59 l-5 in situ auger hole logging system with intrinsic ger-manium detector and narrow dewar assembly data acquisi-tion equipment and storage / fill dewar. 60 l-6 Automatic alpha-beta gas flow proportional counter. 61 l-7 Calibration rig assembly. 62 i vi

.s LIST DE TABLES 1. Gamma radiation levels and beta-gamma count rates at grid locations. 29 2. Surface soll sample radionuclide concentrations (pCI/g+/-% error), by gamma analysis. 31 3. Soil core sample radionuclide concentrations (pCi/g), by gamma analysis. 32 4 Borehole Nel counts and IG analyses (pCI/g). 34 5. In situ borehole measurements vs core sample analyses. 39 6. Water sample analyses. 40 7. Gamma spectroscopic analysis of selected water samples. 41 8. Particulate high volume air samples, long lived activi-ty. 42 9. Summary of offsite background radiological measure-ments. 43

10. Target criteria and measurement LLD's for Combustion Engineering Facility burial site.

44 i i vil

I i l. INTRODUCTION i Radiation Management Corporation, under contract to the U. S. Nuclear Regulatory Commission (NRC), performed a ra-diological evaluation of the burial site adjacent to the Combustion Engineering plant in Hematite, Missouri. An ini-tial site visit occurred in March 1982, and the detailed ra- } diological evaluation was performed in the spring and summer of 1982. The purpose of this survey was to clearly define the radiological conditions at the burial site and to determine if radioactive material is moving from the burial pits into the surrounding environment. The methods used to evaluate this site included the following: 1) Measurement of external exposure rates at one meter above the ground surface and beta-gamma count rates at one cm. above the ground surface; 2) Measurement of radionuclide concentrations in surface soII and vegetation; 3) Measurement of radionucilde concentrations in

subsurface deposits; 4) Measurement of gross alpha and beta activity in surface and subsurface water samples; 5) Measurement of airborne radioactivity. l Measurements were performed onsite using an RMC designed mobile laboratory facility. Analyses which could not be performed onsite were sent to the RMC analytical la-boratory in Philadelphia, Pennsylvania. l l l l 2

l 11. SITE CHARACTERISTICS The project site (Fig. 1) is located adjacent to the Combustion Engineering plant in Hematite, Jefferson County, Missouri. The site is approximately 35 miles south of St. Louis in a rural area isolated from large residential and/or commercial developments. The plant proper is a re-stricted area, and completely fenced in. The burial site is located immediately to the east of the fence line and ex-tends to a wooded area at the site boundary (Fig. 2). The active site is bounded by Route 21A on the

north, railroad tracks to the south, and wooded areas on both sides.

There is no method of controlling access to any areas other than the plant. During its lifetime, the plant has had four different operators. The Initial operations began in 1956, under Mal-linckrodt Chemical. In 1961, United Nuclear took control; in 1970, United Nuclear and Gulf ran the facility in a joint venture; and in

1974, Combustion Engineering assumed responsibility.

Burials were made in the late 50's and early 60's under the direction of both Mallinckrodt and United Nuclear, in accordance with all applicable NRC (AEC) regulations. Plant operations involve processing and treating vari-3

ous uranium compounds. All manner of uranium materials, 1 ranging from depleted to highly enriched uranium, have been used at this site. While any of these may have been buried, it is more likely that depleted uranium was disposed of rather than enriched, due to the commercial value of the en-riched material. Records indicate that an estimated 27 kil-ograms of U-235 (60 MCI) have been disposed of. Because all materials were assayed for U-235 only (by scanning with a scintilletor set to count the 186 kev gamma peak), no es-timate of total U-238 and U-234 content has been made. Additionally, some work on thorium fuel was performed, so there exists the possibility that small quantitles of thori-um have been buried. No other radioisotopes have been used or disposed of at this site. The nature of the buried material is described as being primarily contaminated combustibles and small pieces of equipment. Apparently, the bulk of bur led material consist-ed of paper, plastic and wood items. Some metal items, such as pipes and buckets, have been buried, although no major metallic

objects, except possibly a

pickup truck, were disposed of. These materials were buried in 40 pits, each approxi-mately 20 feet by 40 feet by 12 feet deep. The Individual pits were not marked or otherwise Identified, although some 4

can be located by ground settling. Each is covered by 2 to 5 feet of fill dirt. The pits were not lined or prepared in any

way, nor were they capped with special materials.

The soll is silty clay to a depth of approximately 30 feet, then gravel for about 10 feet to rock. Ground water ranges from depths of a few feet to 20 feet, depending on the season. Ground water flow is generally from the north to the south, possibly into Joachim Creek, which is about one-half mile from the site. The burial ground is an open grassy area with some apparent water runoff. 5 ~

Ill. RADIOLOGICAL SURVEY METHODS A) Measurement of External Radiation Levels The burial site was gridded and surveyed for both gamma radiation levels at one meter above the ground surface and beta gamma count rates at the ground surface. Initially, precise exposure rate measurements at selected grid points were made with a high sensitivity Tis-sue Equivalent lonization Chamber System, described in Ap-pendix 1. Nal(TI) scintillation detector measurements were also made at these points, and a conversion factor for the Nal(TI) count rate versus uR/hr was established. Once this factor was confirmed, the scintillation detector was used j for all grid point measurements. At each grid point, an end window G-M tube was used for surface measurements. Open and closed window readings were made at I cm and the ratio of the two used to indicate the presence or absence of surface contamination. I B) Measurement of Surface Radioactivity Based on external measurements, surface soll samples were collected from locations where surface deposits were ) i, 6 .-_____-______O

l Indicated, as well as locations where drainage characterls-tics Indicated the possibility that radioactive materlass may have been transported from their original burial loca-tions. The samples were dried and sealed in 500 ml aluminum cans for counting on the intrinsic germanium (lG) gamma ray spectroscopy system described in Appendix 1. Sediment samples from Joachim Creek and the small creek east of the site were also collected and analyzed using the same method. Onsite vegetation samples consisted of grasses which were located in areas where drainage and wind characterls-tics Indicated the possibility that radioactive materials may have been transported from the original locations and deposited onto or taken up by vegetation. C) Measurement of Subsurface Radioactivity A series of holes through and bordering the burial site were drilled and lined with four-inch PVC casing. Each hole was logged at one-foot intervals using a one-inch by one-Inch Nal(TI) scintillation detector and scaler system. Theso preliminary measurements were used to indicate the lo-cations a n'd approximate magnitude of subsurface contamina-tion. Selected holes were then logged using a specially 7 i .b

designed IG detector coupled to a multi-channel analyzer system (see Appendix I). Soll layers with gamma count rates exceeding background rates, as measured with the Nal(TI) de-tector, were logged at one-foot increments using the IG de-tector. Layers which did not exceed background were logged at two-foot increments. D) Measurement of Radioactivity in Water l Whenever possible, water samples were taken from bore-holes. Four permanent water monitoring wells were drilled to provide access to ground water flow through the burial site. These wells were located at points which intercept the ground water flow through the pit areas. Periodic sam-pies were taken from these wells to measure any possible change in ground water radionuclide content. Samples were also taken from the two creeks near the burial area. Water samples were filtered to remove suspended parti-

culates, then 100 mi aliquots were evaporated in planchetts and counted for gross alpha and beta activity.

All samples which showed gross activities greater then EPA drinking water standards were sealed in Marinelli beakers and counted using the gamma spectroscopic analysis system. E) Measurement of Airborne Radioactivity 8

l High volume air particulate samples were taken to meas-ure long lived activities. These samples were counted for gross a!phe and beta activity using a low background gas flow proportional counter with methods described in Appendix 1. F) Measurement of Radioactivity in Vegetation Samples of vegetation were collected,

dried, crushed and counted for gamma activity.

These samples consisted only of grass, weeds and other

common, non-edible vegeta-tion.

Environmental sampling and measurements were performed to document the background radiological characteristics of offsite areas surrounding the CE plant. A summary of these measurements and analysis results is shown in Table 9.. ) 9

IV. RADIOLOGJEAL SURVEY RESULTS A) External Radiation Levels Results of the external radiation surveys are listed in Table 1 and shown in Fig. 3. As can be seen, the only de-tectable levels above normal background were found in the northwest corner of the burial site, adjacent to the facill-ty security fence. It was readily determined that these elevated levels (>20 uR/hr) were due to sources

onsite, rather than buried material, because containers of-UF6 are routinely stored near the designated fence line in the secu-rity area.

The survey results show that levels increase as one approaches these containers, confirming that the source is primarily the UF6 containers, rather than material in the burial site. The beta-gam...o count rates verify the absence of measurable surface contamination. The negative findings are not unexpected since it is known that only small quantitles of U-235, U-234 and U-238 have been disposed of. The absence of detectable exposure ] levels Indicates that little or no thorium wastes are present near the ground surface. B) Surface Soll Analyses 10 l

A total of 11 surface soll samples were gathered from the burial site. In addition, five stream sediment samples were taken, two from the small creek bordering the burial site on the east, and three from Joachim Creek. All samples were dried, sealed and counted on the gamma spectroscopy system. Samples were analyzed for gamma spectra from U-238, U-235, K-40 and radium daughters. The locations of the surface soll samples are shown in Fig. 4 and the analytical results in Table 2. Radionuclide concentrations in all creek sediment samples were Indistin-guishable from normal background concentrations, and were often ilthin the lower limits of detection of the counting system used. Several samples from the burial site surface showed measurable uranium activities, ranging from 1.7 to 4.9 pCI/g for U-238 and 0.6 to 1.1 pCI/g for U-235. U-234 activities were estimated to range from 2 to 47 pCl/g. In each case but one, a positive U-238 finding corresponded to a positive U-235 value (and an estimated posit've U-234 value). For all samples, the radium daughter and K-40 activities were relatively constant. Although the uranium activities are slightly above background in some cases, they do not exceed NRC target criteria for contaminants in soll. (NRC target criteria for concentration limits and measurement lower lim-11

Its of detection are summarized in Table 10.) The source of this apparent low level surface contami-nation is not clear. While it is possible that the contami-nation is a result of burial activities, it is also possible that it resulted from past effluent (i.e. stack) releases. In either case, these surface activities seem to be a result of facIIIty operations rather than unusually high naturally occurring radionuclides because' no corresponding uranium daughter activities can be found. C. Subsurface Soll Analysis Subsurface contamination was assessed by extensive log-ging of holes drilled through and around the burial site, using both a one-inch by one-inch Nal(TI) detector and an Intrinsic germanium (IG) detector. A total of 14 holes were drilled on the site, 10 of which were lined with 4 inch PVC casing for logging. The other 4 were lined with.2 inch slotted casing, for use as water sampling wells. Fig. 5 shows the location of all holes drilled at the site. For three of these (holes 5, 7 and 11), cores were taken during drilling activities. Each core was dried and counted in.a j manner identical to the surface soll procedure. In addi-

tion, four core samples were sent to the RMC Analytical La-boratories for duplicate gamma spectral. analysis and uranium 12

\\ determinations using alpha spectroscopy. Each borehole was logged with the Nal(TI) detector to identify areas of increased gross activity, then with the IG detector at selected locations, to quantify and qualify these increases. Each IG measurement was designed to deter-mine the concentrations of U-238, U-235, Th-232 by its daughter Pb-212, and Ra-226 by its daughter Pb-214. The results of the onsite core sample analyses are presented in Table 3. In general, concentrations are con-sistent with normal background levels, and are well within all target criteria.

However, several samples from bore hole 7 showed slightly elevated U-235 and U-238 activities, without a corresponding increase in radium daughters, Indi-cating the presence of facility waste material.

Table 4 contains the bore hole logging results. Elevated gross count rates, as detected by the Nal(TI) de-tector, are present in boreholes 1 and 6, while increased U-235 and/or U-238 concentrations, as measured by the IG de-tector, are found in boreholes 6, 7 and 13 (boreholes 1 and 14 were not logged with the IG). k The isotopes shown in Table 4 were identified by measuring the following photopeaks: 93 kev for U-238, 186 13 q

\\ kev for U-235 (corrected for estimated Ra-226 contribution), 239 kev for Pb-212 and 352 kev for Pb-214. Plots of spec-tral data for borehole 4, 2 foot depth, and borehole 6, 4 foot depth, are shown in Figs. 6 and 7 respectively, and'de-monstrate the ease with which these photopeaks can be iden-tified, even at relatively low concentrations. The highest concentrations were measured in borehole 6, where levels as high as 21 pCl/g U-235 and 38 pCI/g U-238 were recorded. U-234 concentrations were estimated to be as high as 400 pCI/g. Concentrations in boreholes 7 and 13 did not exceed 1 pCi/g U-235 and 14 pCl/g U-238. All lev-els, except the 38 pCI/g U-238 concentration, are within the NRC target criteria shown in Table 10. There were no elevated concentrations in the perimeter boreholes in the general direction of ground water flow (boreholes 8 and 11), nor were there elevated levels in other boreholes onsite which are believed to have been drilled directly through burial pits. A set of core samples was sent to the RMC Analytical l Laboratories for analysis and compared with onsite measure-ments. Results are presented in Table 5 and show general agreement except for the U-238 values. For this nuclide, the in situ measurements gave consistently higher values than core sample analysis. The cause of this apparent sys-14

I tematic error has not been determined, and U-238 results for borehole measurements have not been reported, except in the case where gross Nal(TI) counts are above background or where positive U-235 results are reported. All U-234 deter-minations were done at the RMC Analytical Laboratories using alpha spectroscopy since this nuclide could not be detected using field measurement techniques. Ratios of U-234/U-238 and U-235/U-238 by weight were found to have similar enrich-ment (or depletion) factors. These factors were used to es-timate U-234 concentrations in surface and subsurface soils. Uranium isotopic determinations by alpha spectroscopy are shown in Table 5. Based on all the data, the average en-richment is estimated to be about 4%. Using this enrichment

factor, an activity ratio for U-234 to U-238 of 10 is as-sumed.

D) Analyses of Radioactivity in Water A total of 22 water samples were collected (Fig. 8), 11 from the water monitoring wells Installed for this project (boreholes 2, 3, 9 and 12), 3 from other boreholes onsite, 2 from standing water and 6 from creek water. A 100 ml aliquot from each sample was filtered, evapo-rated on a planchett and counted 100 minutes for gross alpha and beta activities. Results are listed in Table 6. Only 15

one

sample, taken from borehole 1, showed gross alpha ac-tivity exceeding the EPA Interim primary drinking water limit for drinking water (15 pCl/l gross alpha).

This sam-pie was further analyzed for Isotopic content, and found to contain elevated (i.e. above background level) U-238 and Th-232 concentrations as shown in Table 7. Gross beta activity exceeding 50 pCi/l was found in five different samples, three of which came from borehole 9, which was located approximately 200 feet east of Combus-tion Engineering's settling ponds. The other two also came from onsite sampling locations. Further analysis of these samples indicates that the high gross beta levels are due in part to K-40. These samples also show elevated U-238, U-235 and Th-232 concentrations. E) Airborne Radioactivity Measurements A set of high volume air samples was collected in the vicinity of the burial site. The results are listed in Table 8, and show no unusual or elevated levels. These results are

expected, because it is known that the buried material is not ;lkely to be a source of airborne emissions, l

due to the absence of daughter activity which could produce gaseous emanations (radon). 16

i F) Radioactivity in Vegetation Several vegetation samples, from onsite and offsite locations, were analyzed on the gamma spectroscopy system. No unusual activity was found in any sample. a a ' e4 W 17

V. CONCLUSIONS The results of this survey confirm that small quanti-ties of uranium have been buried in the pits adjacent to the Combustion Engineering plant in

Hematite, Missouri.

Analysis of borehole activity and soil samples taken from the burial pits showed slightly elevated levels of U-235 and/or U-238 in some measurements, and only naturally occur-ring background activity in all others. The highest level measured during this survey was 38 pCI/g of U-238, which was the only measurement that exceeded the target criteria of 30 pCl/g U-238 or U-235. It can be assumed that elevated U-234 concentrations are also present, prehaps as high as 400 pCI/g. These measurements tend to confirm that generally only low level contaminated materials and equipment were disposed of in these pits. 1 These survey results also indicate the difficulty in trying to determine specific locations of buried contamina-tion. This material cannot be located through past records because specific burial records were apparently not main-tained, nor were individual burial pits marked or otherwise identified, in addition, the absence of uranium daughters I i (radium and daughters) makes it essentially impossible to locate low level contaminated buried material with surface measurement techniques. 18 i

The overall conclusions are that relatively small quan-titles of uranium have been buried and that the buried ma-terial is essentially stable at this time. The burial pits have little or no effect on the population or the surround-Ing environment. L ? i 19

REFERENCES [1.] U. S. Nuclear Regulatory Commission Letter Contract: NRC-02-80-034, 13 Aug 1980. 20

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c g , ig.f: L U238 - 38 pCi/g U235 - 21 pCi/g Pb212-1.9 pCi/g Pb214-0.2 pC1/g 10 = 2 2 b s i i s 3 i n s i [0s i s i g s i s i l00risigasislissilissegsiistaisslisiaissusg4 aislaissginsulaisigsiisivisiginni;innigin Cher.ael 50 10 2 300 400 500 600 700 800 900 1000 Energy (kev) 50 100 200 300 400 500 Fig. 7. In situ gamma spectrum at the 4 foot depth in borehole 6, using the IG detector and a 10 minute count.

Highway 21-A J + Admin. Bldg. q 8H I l Vo (14) l N - - 00 l To - l So 1 Ro Qo {-] Fenced Po Security Oo Area No Mo - ~ BH 6. BH 3. C' ~Ko l (1) (16,20) I I Jo BH,7. 10 - 2,17,21) 4 _._ Ho d BH. 2. Go (7,15,19) Fo ,. Ep - BH 12. (1 I.' .'.'.' ' i s'." l l ; (13,18,22) ' ' 170 Co (6,9,11 ) Bo \\ Ao i i l oA oB cc OD oE OF oG oH of oJ oK OL oM oN 00 oP oQ oR oS oT l 50 meters Fig. 8. Location of water samples. Sampic numbers listed in Table 6 are shown in parentheses. i 28

i Table 1 Gamma radiation levels and beta-gamma count rates at grid locations Nel Exposure Beta-Gamma Count Beta-Gamma Count Grid Count Rate Rate Rate, closed window Rate, open window Location (c/ min) (uR/hr) (c/ min) (c/ min) GOOK 1700 9 40 70 G00L 1700 9 50 50 G00M 1800 10 50 40 G00N 1600 9 50 40 G000 1700 9 30 40 GOOP 1900 10 50 40 G00Q 1700 9 30 50 HOOK 1700 9 30 40 HOOL 1700 9 40 50 H00M 1700 9 40 20 HOON 1700 9 30 40 H000 1800 10 30 30 HOOP 1700 9 60 40 H00Q 1500 8 30 40 100K 1700 9 50 50 100L 1700 9 40 60 100M 1800 10 30 50 100N 1700 9 70 50 1000 1600 9 50 40 100P 1800 10 40 50 100Q 1600 9 40 40 J00K 1500 8 50 50 J00L 1800 10 40 50 J00M 1700 9 70 60 J00N 1800 10 60 60 J000 1700 9 70 60 J00P 1800 10 60 40 J00Q 1600 9 60 40 K00K 1700 9 40 40 K0OL 1600 9 30 60 K00M 1700 9 50 60 K00N 1900 10 70 60 K000 1800 10 40 50 K00P 1800 10 50 50 K00Q 1900 10 50 70 LOOK 1700 9 70 50 ,) LOOL 1900 10 40 60 LOOM 1800 10 60 60 LOON 1900 10 50 50 LOOO 1800 10 60 50 LOOP 1900 10 40 60 MOOK 1700 9 50 70-M00L 2000 11 60 80 h00M 2100 12 30 60 MOON 2000 11 50 60 29

Table 1, cont. Nel Exposure Beta-Gamma Count Beta-Gamma Count Grid Count Rate Rate Rate, closed window Rate, open window Location (c/ min) (uR/hr) (c/ min) (c/ min) M000 2000 11 40 60 M00P 1800 10 40 80 N00K 1800 10 80 100 N00L 2300 13 70 90 N00M 2100 12 60 110 N0ON 2100 12 40 60 N000 1800 10 70 60 N00P 1500 8 50 70 000K 2100 12 90 70 000L 2400 14 70 80 000M 2300 13 60 70 000N 2500 14 70 110 0000 1800 10 70 70 P0OK 2000 11 40 60 P0OL 3200 17 80 100 POOM 2700 14 90 100 POON 2800 15 80 100 P000 2200 12 70 70 QOOK 4100 22 50 60 QOOL 5000 26 60 90 Q00M 3800 20 60 100 QOON 3000 15 50 80 0000 2600 13 80 50 ROOK 4500 23 100 140 ROOL 11000 56 140 130 ROOM 5000 26 110 80 I ROON 3500 18 60 50 i R000 2600 13 40 70 S00K 50000 256 360 320 S00L 13000 67 110 90 1 S00M 6000 31 100 140 S00N 3800 20 90 110 l S000 2800 14 80 80 l TOOK 45000 231 530 490 TOOL 12000 62 120 150 TOOM 5000 26 100 110 TOON 3700 19 80 90 i T000 2700 14 90 100 000K 17000 87 80 100 1 U0OL 8000 41 90 90 UOOM 4000 21 80 60 1 000N 3500 18 70 60 U000 2500 13 90 110 UOOK 5000 26 130 110 UOOL 3500 18 70 80 000M 3500 18 60 80 000N 3000 15 80 100 0000 2300 12 90 70 30

( Table 2 Surface soil sample radionuclide concentrations (pCI/g +/- T counting error) by gamma analysis Sample Sample Location Mass U-238 U-235 Ac-228 Pb-212 Pb-214 BI-214 K-40 (g) 1 B50L 210 1.4E0+/-110 7.5E-2+/-200 7.7E-1+/-67 3.4E-1+/-49 8.2E-1+/-44 2.2E-1+/-110 6.3E0+/-42 i 2 B50L 299 1.2E0+/-110 2.7E-2+/-380 7.5E-1+/-63 5.9E-1+/-30 9.7E-1+/-35 5.9E-1+/-46 8.5E0+/-34 3 L55P 315 3.1E-1+/-330 8.6E-2+/-130 4.9E-1+/-90 6.0E-1+/-29 8.9E-1+/-36 5.9E-1+/-44 1.2El+/-28 4 000M 224 3.1E0+/-60 6.8E-1+/-89 6.4E-1+/-80 6.6E-1+/-30 8.1E-1+/-44 4.5E-1+/-74 1.2El+/-27 5 0000 267 1.7E0+/-85 5.6E-1+/-71 3.0E-1+/-110 6.3E-1+/-26 8.EE-1+/-39 4.4E-1+/-53 6.5E0+/-35 03 6 K310 224 4.9E0+/-39 1.1E0+/-71 5.7 E-1 +/-81 3.7E-1+/-47 8.5E-1+/-41 4.4E-1+/-59 9.0E0+/-32 7 T000 176 3.0E0+/-72 9.4E-1+/-110 7.9E-1+/-75 7.8E-1+/-29 1.1E0+/-44 3.1E-1+/-99 6.5E0+/-45 8 L50Q 266 3.8E-1+/-330 1.0E-1 +/-110 5.7E-1+/-73 4.9E-1+/-33 9.4E-1+/-35 6.2E-1+/-42 5.5E0+/-42 9 L50Q 228 7.1E-1+/-210 8.5E-2+/-150 5.2E-1+/-90 4.8E-1+/-37 1.2E0+/-32 6.0E-1+/-47 1.0El+/-30 10 H55R 319 7.8E-1+/-170 6.72-2+/-170 3.5E-1+/-120 6.7E-1+/-27 1.2E0+/-29 4.4E-1+/-57 1.1El+/-28 11 TOOM 148 3.3E0+/-78 6.7E-1+/-97 6.2E-1+/-100 4.7E-1+/-51 5.7E-1+/-79 9.3E-1+/-45 9.9E0+/-38 12 Offsite Bkg 174 3.6E-1+/-460 1.5E-1+/-130 1.1E-I+/-330 2.4E-1+/-70 8.5E-1+/-48 4.9E-1+/-65 8.7E0+/-37 13 Small creek 303 3.2E-1+/-370 7.7E-3+/-1200 8.0E-1+/-61 ?.3E-1+/-37 5.6E-1+/-51 4.7E-1+/-55 4.1E0+/-58 upstream 14 'Small creek 320 4.0E-1+/-280 4.3E-3+/-2000 6.1E-1+/-71 1.9E-1+/-66 4.7E-1+/-57 2.9E-1+/-73 1.4E0+/-130 downstream 15 Joachim Creek 256 2.4E-1+/-480 3.9E-2+/-250 2.3E-1+/-150 9.9E-2+/-130 2.9E-1+/-90 7.6E-2+/-250 2.6E0+/-72 upstream 16 Joachim Creek 234 3.0E-2+/-3800 3.1E-2+/-320 1.2E-1+/-280 2.4E-1+/-66 4.2E-1+/-66 1.9E-1+/-110 5.3E0+/-41 downstream 17 Joachim Creek 272 4.2E-1+/-290 6.2E-3+/-1400 1.5E-1+/-220 2.7E-1+/-49 5.9E-1 +/-84 2.3E-1 +/-84 1.6E0+/-90 midstream u

Table 3 Soll core sample radionuclide concentrations (pCI/g +/- % counting error), by gamma analysis Borehole #5 Depth Mass U-238 U-235 Ac-228 Pb-212 Pb-214 Bi-214 K-40 (ft) (g) 0 217 7.7E-1+/-2005 1.2E-1+/-120% 1.9E-1+/-220% 5.6E-1+/-36% 1.0E0+/-39% 7.0E-1+/-42% 9.9E0+/-31% 1 277 9.9E-1+/-130% 4.1E-2+/-220% 6.1E-1+/-75% 5.0E-1+/-32% 9.7E-1+/-33% 6.3E-1+/-46% 1.1El+/-26% 2 326 1.1E0+/-110% 4.6E-2+/-210% 8.4E-1+/-56% 7.0E-1+/-25% 7.1E-1+/-42% 6.3E-1+/-40% 1.1El+/-28% 3 229 4.1E-1+/-360% 2.4 E-2+/-430% 8.2E-1+/-62% 4.8E-1+/-38% 1.1E0+/-35% 6.7E-1+/-45% 8.6E0+/-34% 4 232 6.3E-1+/-2005 -2.2E-2+/-500% 4.2E-1+/-110% 5.0E-1+/-37% 1.4E0+/-29% 7.4E-1+/-41% 8.5E0+/-34% 5 248 5.6E-1+/-260% -2.6E-3+/-38005 5.7E-1+/-79% 6.4 E-1 +/-28% 1.1E6+/-33% 8.5E-1+/-34% 1.2EI+/-26% 6 284 9.7E-1 +/-150% 5.2E-2+/-220% 1.5E0+/-42% 8.0E-1+/-27% 9.8E-1+/-37% 8.0E-1+/-39% 1.3El+/-27% 7 247 9.2E-1+/-160% 1.2E-2+/-6805 1.1E0+/-46% 5.8E-1+/-31% 9.5E-1+/-37% 5.3E-1+/-47% 1.1El+/-27% M 8 262 4.8E-1+/-260% 3.9E-2+/-260% 5.9E-1+/-74% 6.2E-1+/-28% 1.1E0+/-32% 8.3E-1+/-34% 8.5E0+/-31% 9 256 8.8E-1+/-150% 3.1E-2+/-320% 6.0E-1+/-74% 5.9El+/-30% 1.3E0+/-29% 8.4E-1+/-35% 1.0El+/-28% 10 218 1.8E0+/-98% 3.5E-2+/-280% 6.5E-1+/-79% 8.6E-1+/-26% 9.2E-1+/-43% 8.1E-1+/-40% 1.2El+/-29% 11 232 1.3E0+/-130% 6.0E-2+/-180% 7.2E-1+/-72% 8.8E-1+/-24% 1.1E0+/-35% 5.9E-1+/-47% 8.5E0+/-33% 12 251 3.3E-1+/-430% 1.2E-1+/-100% 7.0E-1+/-65% 4.4E-1+/-36% 9.9E-1+/-35% 5.5E-1+/-50% 1.0El+/-28% i 13 209' 1.6E0+/-110% 6.0E-2+/-210% 9.6E-1+/-37% 5.3E-1+/-24% 2.1E0+/-24% 1.2E0+/-31% 1.1El+/-29% Borehole #7 l Depth' Mass U-238 U-235 Ac-228 Pb-212 Pb-214 B1-214 K-40 (ft) (g) 0 216 1.1E0+/-160% 2.6E-1+/-745 1.4E-1+/-290% 5.3E-1+/-36% -5.3E-1+/-33% 6.3E-1+/-49% 9.7E0+/-33% 1 252 1.3E0+/-1105 9.4E-1+/-130% 6.6E-1+/-71% 8.3E-1+/-23% 1.2E0+/-30% 5.2E-1+/-50% 6.9E0+/-36% 2 199 2.4E0+/-78% 8.4E-2+/-170% 8.9E-1+/-67% 9.1E-1+/-25% 1.2E0+/-37% 5.9E-1+/-53% 9.2E0+/-35% 3 236 2.1E0+/-77% 2.6E-1+/-74% 6.6E-1+/-77% 4.4E-1+/-41% 9.2E-1+/-38% 7.8E-1+/-38% 1.2El+/-27% 4-222 1.4E0+/-120% 3.1E-1+/-76% 3.4E-1+/-140% 5.8E-1+/-33% 1.0E0+/-37% 5.3E-1+/-50% 1.1ET+/-30% 8 219 3.0E0+/-61% 1.4E0+/-64% 7.0E-1+/-76% 8.1Etl+/-43% 8.7E-1+/-43% 6.7E-1+/-45% 1.3El+/-26% 9 249 1.1EO+/-120% 4.0E-1+/-66% 9.0E-1+/-56% 6.0E--1 +/-29% 9.2E-1+/-37% 6.2E-1+/-43% 9.3E0+/-30% 10-' 225' 1.5E0+/-120% 7.5E-1+/-67% 6.3E-1 +/-795 5.9E--1 +/-31 % 9.9E-1+/-38% 5.5E-1+/-50% 1.2El+/-28% 11 211 1.4E0+/-120% 9.8E-2+/-130% 5.6E-1+/-91% 6.4E 1+/-32% 1.2E0+/-44% 7.1E-1+/-44% 9.5E0+/-32% __m

~ Table 3, cont. l Borehole #11 Depth Mass U-238 U-235 Ac-228 Pb-212 Pb-214 BI-214 K-40 (ft) (g) 0 175 4.6E-1+/-360% 6.8E-2+/-220% 6.5E-1+/-33% 6.9E-1+/-33% 1.3E0+/-39% 5.3E-1+/-63% 1.1E1+/-35% 1 254 9.6E-1+/-140% 1.4E-2+/-700% 6.9E-1+/-27% 6.5E-1+/-27% 7.5E-1+/-41% 6.6E-1+/-41% 9.0E0+/-31% 2 240 1.0E0+/-140% 1.7 E-1 +/-120% 5.0E-1+/-91% 4.2E-1+/-41% 5.3E-1+/-62% 3.3E-1+/-75% 6.1E0+/-42% 3 245 1.1E0+/-140% 1.1E-2+/-800% 4.9E-1+/-91% 6.6E-1+/-28% 1.1 E0+/-34% 8.3E-1+/-37% 1.3El+/-25% 4 235 1.2E0+/-130% 9.2E-2+/-120% 2.5E-1+/-150% 2.0E-1+/-83% 8.4 E-1 +/-42% 2.5E-1+/-100% 5.1E0+/-50% 5 212 2.3E-1+/-580% 1.9E-1+/-110% 3.2E-1+/-120% 3.8E-1+/-49% 5.8E-1+/-60% 3.8E-1+/-75% 6.3E0+/-44% 6 232 1.2E0+/-140% 1.4E-2+/-750% 6.0E-1+/-76% 6.2E-1+/-28% 8.3E-1+/-44% 4.5E-1+/-58% 1.0El+/-31% 7 246 8.9E-1+/-160% 1.1E-2+/-770% 7.2E-1+/-68% 6.2E-1+/-29% 7.9E-1+/-42% 5.5E-1+/-49% 1.3El+/-25% 8 263 3.0E0+/-47% 1.0E-2+/-630% 9.4E-1+/-52% 8.6E-1+/-22% 8.2E-1+/-41% 5.8E-1+/-44% 9.7E0+/-30% 9 249 3.2E-2+/-4000% 2.0E-2+/-440% 2.5E-1 +/-150% 2.4E-1+/-66% 2.0E-1+/-120% 2.9E-1+/-77% 3.5E0+/-57% 10 279 7.6E-1+/-170% 6.4 E-2+/-130% 1.5E-1+/-220% 3.0E-1+/-44% 4.8E-1+/-58% 5.4E-1+/-47% 5.3E0+/-44% EY 11 272 1.6E0+/-84% 1.2E-2+/-570% 1.1E0+/-47% 4.9E-1+/-32% 1.3E0+/-27% 4.1E-1+/-57% 7.4EG+/-33% 12 283 7.3E-2+/-1900% 6.8E-2+/-160% 1.6E0+/-39% 7.2E-1+/-29% 8.4E-1+/-42% 7.2E-1+/-42% 1.3El+/-27% 13 278 1.7E0+/-78% 1.1 E-2+/-760% 1.0E0+/-48% 5.3E-1+/-30% 9.3E-1+/-35% 6.0E-1+/-41% 1.2El+/-25% 14 296 8.2E-1+/-170% 2.4E-2+/-410% 1.0E0+/-52% 6.6E-1+/-30% 1.0E0+/-34% 6.9E-1+/-42% 1.2E1+/-28% l l

Table 4 Borehole Nal counts and IG analysis (pCI/g +/- counting error) Borehole #1 Gross Nal Depth Counts / Min U-235 U-238 Pb-212 Pb-214 0 3.47E3+/-2% 2 3.24E3+/-2% 4 3.24E3+/-2% 6 4.92E3+/-2% 7 1.15E4+/-2% 8 3.61E3+/-2% 10 3.03E3+/-2% 12 3.25E3+/-2% 14 3.34E3+/-2% w

  1. ^

16 3.08E3+/-2% 18 3.29E3+/-2% Borehole #4 Gross Nal Depth Counts / Min U-235 U-238 Pb-212 Pb-214 3.5E-1+/-17% 5.3E-1+/-21% 0 2.5E3+/-2% 1.0E-1+/-45% 5.6E-1 +/ -12% 4.8E-1+/-17% 2 3.IE3+/-2% 1.8E-2+/-29% 6.1E-1+/-11% 6.0E-1+/-12% 4 3.3E3+/-2% 4.5E-3+/-440% 6.1E-1+/-11% 6.9E-1+/-10% 6 3.5E3+/-2% 9.8E-3+/-497% 3.1E-1+/-18% 8.6E-1+/-8% 8 3.3E3+/-2% 1.1E-1+/-42% 6.1E-1+/-12% 1.1E0+/-7% 10 3.3E3+/-2% 1.0E-1+/-43% 6.5E-1+/-10% 8.6E-1+/-11% 12 3.2E3+/-2% 5.9E-2+/-373% 7.7E-1+/-85 7.4E-1+/-16% 14 3.1E3+/-2% 3.0E-2+/-600% 6.8E-1+/-10% 1.1E0+/-8% 16 3.2E3+/-2% 7.8E-2+/-112% 8.1E-1+/-8% 7.4E-1+/-10% 18 3.1E3+/-2% 5.8E-2+/-81% n

Table 4, cont. Borehole #5 Gross Nai Depth Counts / Min U-235 U-238 Pb-212 Pb-214 6.8E-1+/-9% 6.7E-1+/-10% 0 3.83E+/-2% 1.5E-I+/-25% 7.2E-1+/-9% 6.5E-1+/-11% 2 3.0E3+/-2% 9.3E-2+/-49% 5.8E-1+/-13% 7.8E-1+/-10% 4 3.3E3+/-2% 1.2E-1+/-43% 7.3E-1+/-9% 8.9E-1+/-8% 6 3.3E3+/-2% 7.3E-2+/-177% 5.2E-1+/-15% 6.3E-1+/-12% 8 3.4E3+/-2% 5.5E-2+/-83% 8.1E-1+/-9% 1.2E0+/-7% 10 3.4 E3+/-2% 2.9 E-2+/-161 % 4.7E-1+/-14% 9.8E-1+/-8% 12 3.5E3+/-2% 7.4E-3+/-63% 5.5E-1+/-12% 9.0E-1+/-8% 14 3.2E3+/-2% 3.6E-3+/-1250% 5.5E-1+/-12% 1.0E0 +/-6% 16 3.1E3+/-2% 7.5E-2+/-59% l U$ Borehole #6 Gross Nal Depth Counts / Min U-235 U-238 Pb-212 Pb-214 0 3.1E3+/-2% 1.4E0+/-4% 1.0El+/-12% 6.7E-1+/-12% 3.9E-1+/-10% 1 3.3E3+/-2% 5.6E-1+/-9% 1.0El+/-12% 5.6E-1+/-10% 8.1E-1+/-10% 2 3.6E3+/-2% 9.1E-1+/-6% 1.3El+/-10% 6.1E-1+/-10% 5.3E-1+/-11% 3 3.8E3+/-2% 1.1El+/-55 8.3E0+/-18% 4.9E-1+/-16% 2.1E-1+/-17% 4 1.6E4+/-1% 2.1El+/-1% 3.8El+/-9% 1.9E0+/-8% 1.4E-1+/-32% 5 1.9E4+/-15 5.4E0+/-2% 1.6El+/-14% 5.7E-1+/-13% 4.7E-1+/-20% 6 6.8E3+/-1% 3.8E0+/-2% 1.9El+/-8% 6.4E-1+/-11% 4.5E-1+/-13% 7 6.0E3+/-1% 4.1E0+/-2% 2.2El+/-7% 7.2E-1+/-11% 7.6E-1+/-12% 8 5.1E3+/-1% 2.4E0+/-3% 1.5El+/-10% 6.2E-1+/-12% 6.6E-1+/-10% 9' 4.0E3+/-1% 9.7E-1+/-5% 1.3El+/-9% 6.3E-1+/-11% 5.2E-1+/-125 10 3.8E3+/-25 1.5E0+/-4% 1.4El+/-9% 6.7E-1 +/-12% 6.8E-1 +/-9% 12 3.3E3+/-2% 7.5E-1+/-7% 8.7E0+/-13% 5.7E-1+/-10% 6.2E-1+/-11% 14 3.4 E3+/-2% 7.2E-1+/-7% 1.1El+/-12% 7.7E-1+/-10% 7.2E-1+/-105 16 3.2E3+/-2% 7.7 E-1 +/-8% 8.3E0+/-15% 8.5E-1 +/-9% 5.7 E-1 +/-12% t 18 3.2E3+/-2% 8.7E-1 +/-6% 1.IEl+/-11% 7.7 E-1 +/-10% 7.6E-1+/-10%

Table 4, cont. Borehole #7 Gross Nal Depth Counts / Min U-235 U-238 Pb-212 Pb-214 0 2.4 E3 +/-2% 2.3E-1+/-15% 6.7E0+/-13% 3.3E-1+/-13% 3.0E-1+/-15% 1 2.9E3+/-2% 5.9E-2+/-43% 8.4E0+/-11%

4. 2E-1 +/-9%

7.1 E-1 +/-12% 2 2.7 E3+/-2% 5.6E-2+/-51% 4.8E0+/-18% 9.8E-2+/-24% 3.5E-1+/-17% 3 2.5E3+/-2% 6.7E-2+/-42% 4.9E0+/-17% 1.1E-1+/-29% 3.7E-1+/-23% 4 2.3 E3 +/-2% 1.0E-1+/-27% 6.3E0+/-13% 1.6E-1+/-16% 4.6E-1+/-12% 5 1.6E3+/-3% 2.3E-1+/-12% 2.3E0+/-30% 1.4E-2+/-85% 1.8E-1+/-27% 6 1.3E3+/-3% 4.9E-1+/-7% 1.6E0+/-41% 8.9E-2+/-37% 1.4E-1+/-30% 8 2.4E3+/-2% 9.3E-1+/-5% 7.3E0+/-12% 3.1E-1+/-12% 5.4E-1+/-10% 10 3.1E3+/-2% 3.lE-1+/-12% 5.7E0+/-15% 8.3E-2+/-32% 3.9E-1+/-11% 12 3.0E3+/-2% 1.0E-1+/-29% 6.0E0+/-16% 2.8E-1 +/-12% 4.9E-1+/-10% 14 3.0E3+/-2% 1.7E-1+/-21% 7.6E0+/-12% 2.5E-1+/-11% 5.3E-1+/-10% u, 16 3.0E3+/-2% 3.2E-1+/-14% 8.9E0+/-11% 4.8E-1+/-10% 8.1E-1+/-9% 18 3.4E3+/-2% Borehole #8 Gross Nal U-2 Pb-212 Pb-214 ______4_8 Depth Counts / Min U-235 4.3E-1+/-13% 5.6E-1+/-12% 0 2.6E3+/-2% 6.0E-2+/-77% 4.0E-1+/-14% 6.1E-1+/-13% 2 3.1E3+/-2% 2.0E-1+/-20% 2.5E-1+/-29% 5.9E-1+/-12% 4 3.1E3+/-25 1.6E-2+/-302% 4.2E-1+/-15% 5.8E-1+/-14% 6 3.3E3+/-2% 8.5E-2+/-41% 4.7E-1+/-12% 7.5E-1+/-10% 8 3.2E3+/-2% 9.7E-2+/-35% 2.4E-1+/-26% 7.4E-1+/-105 10 3.1 E3+/-2% 2.7E-2+/-176% 4.5E-1+/-14% 5.6E-1+/-12% 12 3.1 E3 +/-2% 1.2E-1+/-31% 1.1E-1+/-68% 6.8E-1+/-11% 14 3.1 E3+/-2% 7.2E-2+/-47% 3.5E-1+/-18%

8. 0E-1 +/-9%

16 3.1E3+/-2% 4.8E-2+/-125% 7.3 E-1 +/-9% 7.7 E-1 +/-9% ~18 3.1E3+/-2% 2.7 E-2+/-200%

g Table 4, cont. Borehole #10 Gross Nal Depth Counts / Min U-235 U-238 Pb-212 Pb-214 3.3E-1+/-22% 7.8E-1+/-8% 0 2.3E3+/-2% 1.7E-1+/-18% 6.9 E-1 +/-9% 9.4E-1+/-7% 2 3.1E3+/-2% 2.6E-2+/-140% 4.4E-1+/-14% 5.8E-1+/-13% 4 3.2E3+/-2% 3.9E-2+/-115% 5.4E-1+/-14% 9.8E-1+/-6% 6 3.4E3+/-2% 5.8E-2+/-955% 6.8E-1+/-10% 9.3E-1+/-7% 8 3.4 E3 +/-2% 1.2E-1+/-34% 4.9E-1+/-15%

8. 8 E-1 +/-9%

10 3.3E3+/-2% 6.8E-2+/-900% 6.0E-1+/-11%

8. 0 E-1 +/-9%

12 3.4E3+/-2% 4.0E-2+/-538% 5.6E-1+/-14% 9.6E-1+/-7% 14 3.2E3+/-2% 1.4E-2+/-26% 3.7E-1+/-20% 8.3E-1+/-9% 16 3.2E3+/-2% 4.9E-2+/-101% 4.3E-1+/-15% 9.7E-1+/-7% 18 3.1E3+/-2% 1.9E-1+/-25% ti Borehole #11 Gross Nai Depth Counts / Min U-235 U-238 Pb-212 Pb-214 3.8E-1+/-16% 5.6E-1+/-13% 0 2.3 E3+/-2% 1.0E-1+/-45% 7.6E-1+/-9% 6.2E-1+/-12% 2 2.9E3+/-2% 1.2E-1+/-40% 2.6E-1+/-24% 7.0E-1+/-10% 4 3.1E3+/-2% 5.3E-2+/-423% 5.9E-1+/-12% 9.4E-1+/-8% 6 3.4E3+/-2% 4.9E-3+/-970% 5.0E-1+/-11% 6.5E-1 +/-12% 8 3.3E3+/-2% 1.2E-3+/-3700% 5.8E-1+/-12% 7.3E-1+/-10% 10 3.3E3+/-2% 4.5E-2+/-190% 3.9E-1+/-16% 7.6E-1+/-10% 12 3.2E3+/-2% 8.6E-3+/-530% 3.9E-1+/-16% 4.7E-1+/-16% 14 3.0E3+/-2% 9.3E-2+/-50% 4.6E-1+/-14% 6.9E-1+/-10% 16 3.0E3+/-2% 1.1E-1+/-31% 3.2E-1+/-17% 9.2E-2+/-8% 18 3.0E3+/-2% 2.4E-2+/-173%

s E Table 4, cont. Borehole #13 Gross Nai Depth Counts / Min U-235 U-238 Pb-212 Pb-214 0 2.2E3+/-2% 2.1E-1+/-19% 6.0E0+/-16% 3.5E-1+/-17% 3.9E-1+/-15% 2 3.1E34/-2% 9.9E-2+/-44% 2.9E0+/-38% 4.0E-1+/-16% 5.2E-1+/-13% 4 3.0E3+/-2% 3.9E-3+/-120% 4.3E0+/-26% 3.3E-1+/-21% 6.3E-1+/-10% 6 2.8E3+/-2% S.0E-1+/-7% 4.9E0+/-22% 3.4E-1+/-15% 4.8E-1+/-10% 8 3.1E3+/-2% 2.1E-1+/-23% 1.1El+/-10% 4.9E-1+/-12% 4.8E-1+/-14% 10 3.2E3+/-2% 7.7E-2+/-65% 1.1El+/-10% 3.7E-1+/-18% 7.9E-1+/-8% 12 3.2E3+/-2% 1.8E-1+/-30% 1.3El+/-99% 6.3E-1+/-11% 6.0E-1+/-10% l 14 3.3E3+/-2% 2.4E-1+/-20% 1.4El+/-8% 6.8E-1+/-10% 7.7E-1+/-8% 16 3.1E3+/-2% 1.5E-1+/-34% 6.9E0+/-16% 5.0E-1+/-13% 7.3E-1+/-10% gg 18 3.2E3 +/-2% 2.7E-1+/-18% 3.6E0+/-32% 5.8E-1+/-12% 6.7E-1+/-11% m.

l Table 5 In situ bore hole measurements vs core sample analyses (pCl/g +/- % counting error) Core Core in situ Sample Gamma Sample Gamma Core Borehole 7 Gamma Spectroscopy Spectroscopy Sample Alpha 2 foot Spectroscopy On Site RMC Labs Spectroscopy U-234 1.1El+/-15% U-235 5.6E-2+/-51% 8.4E-2+/.70% 3.3E-1+/-98% U-238 4.8E0+/-18% 2.4E0+/-78% 2.3E0+/-29% Pb-212 9.8E-2+/-24% 9.1E-1+/-25% Pb-214 3.5E-1+/-17% 1.2E0+/-37% 9.2E-1+/-13% BI-214 5.9E-1+/-53% 6.5E-1+/-17% K-40 9.2E30+/-32% 2.0El+/-10% Borehole 7 8 foot U-234 3.5El+/-10% U-235 1.0E0+/-5% 1.4E0+/-64% 2.2E0+/-27% 1.2El+/-23% U-238 6.2E0+/-13% 3.0E0+/-61% <1.0E1 3.2El+/-16% Pb-212 3.0E-1+/-19% 8.0E-1+/-43% <1.2E0 Pb-214 5.0E-1+/-12% 9.0E-1+/-43% 8.0E-1+/-16% BI-214 7.CE-1+/-45% 7.0E-1+/-17% K-40 1.3El+/-26% 2.0El+/-10% Borehole 7 10 Foot U-234 1.5El+/-10% U-235 3.0E-1+/-12% 8.02-It/-12$ 1.5E0+/-27% 5.0E-1+/-39% U-238 5.7E0+/-14% 1.5E0+/-120% <1.1El 1.1E0+/-25% A Pb-212 8.0E-1+/-10% 6.0E-1+/-31% <1.3E0 Pb-214 4.0E-1+/-15% 1.0E0+/-38% 9.0E-1+/-13% DI-214 6.0E-1+/-50% 7.0E-1+/-14% K-40 1.2El+/-28% 1.9El+/-10% Borehole 7 11 Foot U-234 3.0E0+/-15% U-235 1.0E-1+/-130% <5.0E-1 <9.0E-1 U-238 1.4E0+/-120% <1.1El 5.0E-1+/-40% Pb-212 6.0E-1+/-30% <1.9E0 Pb-214 1.2E0+/-44% 9.0E-1+/-18% BI-214 7.0E-1+/-44% 1.2E0+/-25% K-40 9.5E0+/-325 1.8El+/-10% 39

Table 6 Water sample analyses (pCl/l +/- counting error) Sample Gross Alpha Gross Beta No. Sample Location (pCl/ l ) (pCI/ l) 1 Borehole #6-3/26/82 1.3El+/-27% 4.2El+/-16% 2 100H 2.2E0+/-86% 1.5El+/-39% 3 Standing #20 near trucks 9.0E0+/-31% 8.8El+/-9% 4 Small creek near H55R 1.2E0+/-140% 5.6E0+/-90% 5 Stream SE of plant 1.2E0+/-140% 1.6E0+/-338% 6 Joachim Creek upstream 5.0E-1+/-260% 4.2El+/-16% 7 Borehole #2-4/2/82 1.7E0+/-110% 2.0El+/-30% 8 Borehole #7-3/26/82 8.8E0+/-32% 1.4El+/-31% ^ 9 Joachim Creek downstream 1.0E0+/-160% 3.1El+/-20% 10 Small creek upstream 8.3E-1+/-200% 7.9E0+/-590% 11 Joachim Creek midstream 1.7E-1+/-56% 9.1E0+/-268% 12 Borehole #9 4/2/82 2.3E0+/-80% 3.2E2+/-4% 13 Borehole #12 4-2-82 1.1El+/-28% 6.1E0+/-90% ~ 0% 14 Borehole #1 3/24/82 1.8E2+/-6% 1.3E2+/-7% 15 Borehole #2 4/16/82 8.3E-1+/-200% 1.7El+/-27% 16 Borehole #3 4/16/82 1.2E0+/-140% 8.9E0+/-56% 17 Borehole #9 4/16/82 1.7E0+/-110% 4.7E2+/-3% 18 Borehole #12 4/16/82 2.7E0+/-73% 2.3E0+/-230% 19 Borehole #2 4/22/82 2.0E0+/-91% 8.8E0+/-56% 20 Borehole #3 4/22/82 1.5E0+/-120% 2.1El+/-29% 21 Borehole #9 4/23/82 2.0E0+/-91% 5.0E2+/-35 22 Borehole #12 4/22/82 1.0E0+/-160% 2.5El+/-24% o 5 40

Table 7 Gamma spectroscopy analysis of selected water samples isotopic Results (pCI/l +/- counting error) Sample U-238 U-235 Th-232 Ra-226 K-40 No. Sample Location (pCI/l) (pCl/l) (pCl/l) (pCI/l) (pCI/l) 14 Borehole #1 3/24/82 5.3E1+/-53% 6.8E0+/-66% 1.9El+/-46% -6.7E0+/-77% 8.0El +/-43% O

Table 8 Particulate high volume air samples, long lived activity (uCl/ml +/- % counting error) Date Location Gross Alpha Activity Gross Beta Activity (uC1/ml) (uCl/ml) 4/7/82 NW fence line 1.8E-14+/-49% 6.0E-14+/-33% 4/14/82 15 m N of NW fence 2.3E-14+/-36% 6.4E-14+/-25% post 4/14/82 3 m downwind of 1.1E-14+/-58% 3.9E-14+/-38% borehole #1 4/15/82 South of plant 5.6E-15+/-149% 2.8E-14+/-99% 4/15/82 South of parking 2.7E-14+/-49% 3.7E-14+/-75% lot 42

1 I Table 9 Summary of offsite background radiological measurements Type of Measurement Value External exposure rate one meter above ground 12 uR/hr Beta gamma count rates at surface 35/32 Long lived airborne Gross alpha 5.8E-15 uCl/mi +/- 150% particulate activity Gross beta 2.8E-14 uCI/mi +/- 99% Soll radionuclide U-238 3.6E-1 ( pCI/g)+/-460% concentrations U-235 1.5E-1 ( pCI/g)+/-130% Ac-238 1.1 E-1 ( pCI/g)+/-330% Pb-212 2.4E-1(pCI/g)+/-70% Pb-214 8.5E-1(pCl/g)+/-48% BI-214 4.9E-1(pCI/g)+/-65% K-40 8.7E0(pCl/g)+/-37% Water Activities Gross alpha Gross beta Small creck upsiream 3.3E-1+/-200 7.9E0+/-590% Small creek downstream 1.2E0+/-140% 5.6E0+/-90% Joachim Creek upstream 5.0E-1+/-260% 4.2El+/-15% Joachim Creek downstream 1.0E0+/-100% 3.1El+/-20% Joachim Creek midstream 1.7E-1+/-56% 9.1E0+/-268% 43

Table 10 Target criteria and measurement LLD's for Combustion Engineering Facility burial site. Soll Contaminants Nuclide Target Criteria LLD Ra-226 5pCl/g 1pCl/g Total U 15pCl/g 3pCI/g U-238 30pCI/g 6pCl/g U-235 30pCI/g 6pCl/g Th-232

  • 5pCi/g 1 pCl/g Th-230 15pCI/g 3pCl/g Water and Airborne Contaminants Nuclide Target Criteria LLD All MPC Unrestricted 20% MPC Ra-226 (water) 3E-8 uCl/mi 6E-9 uCl/mi External Radiation Nucilde Target Criteria LLD All 20 uR/hr 4 uR/hr
  • Th-232 in equilibrium with daughters l

l 44

i APPENDIX 1 Radiological Survey instruments and Methods 45 kg

A. Portable Survey instrument The portable survey instruments used at the C-E facIII-ty burial site included two complete sets of Wm. B. Johnson & Associates equipment, which consist of battery operated rate

meters, scalers and alpha, beta and gamma probes, and an Eberline PRS-1 ratemeter scaler and detectors.

These systems (see Fig. 1-1) are totally portable and can be used in the field for both measurements and sample counting. The alpha probes use a ZnS(Ag) scintillation detector; the beta detector is a thin window (1.4mg/cm2 m!ca) GM tube, and the gamma detectors are Nal(TI) crystals. The alpha and beta probes were calibrated with "NBS traceable" sources at the RMC calibration facility in Philadelphia and the gamma scintillator was cross-calibrated with a primary ionization chamber system, described below. B. lonization Chamber System External gamma dose rates were accurately measured with the RMC constructed Tissue Equivalent lonization Chamber System (Fig. 1-2). This system consisted of a 16 liter tissue equivalent, gas filled lonization chamber (Shonka chamber), a Keithley vibrating capacitor electrometer, a printer and battery pack. It is capable of measuring dose 46

rates at background levels to a precision of a few percent. Since this system is bulky and somewhat fragile, it is not as suited for extensive field measurements as a smaller, lightweight Nal(TI) portable survey Instrument. Therefore, the Nal(TI) detector was used for the majority of the field gamma measurements. Since this detector's response is ener-gy dependent, it cannot be used as a " micro R meter" unless It is initially calibrated for such use. The calibration performed by RMC consisted of accurate-ly measuring the exposure rate at several locations at the C-E facility burial site using the Tissue Equivalent loniza-tion

Chamber, then recording Nal(TI) measurements at the same location.

In this manner a set of Nal(TI) count-rate versus exposure rates were obtained and a uR/hr calibration factor established, as shown in Fig. 1-3. Due to the energy dependence of the Nel detector, this conversion factor will apply only to the radionuclides and geometries for which the calibrations were made. in the case of the C-E facility burial site, it is known that only naturally occurring nuclides and U-238 and U-235 are likely to be present. Therefore, the conversion factor established at this site, will apply only to naturally occurring ra-dionuclides distributed in soll. 47

C. Mobile Lab Gamma Analysis System The mobile lab gamma analysis system (Fig. I-4) con-sists of a PGT 15% ef ficient (relative to a 3" x 3" Nal(TI) crystal) Intrinsic germanium (lG) detector, shield and Ten-necomp TP-50 laboratory computer data acquisition module. The analysis system was calibrated for all counting geome-tries with an NBS supplied Eu-152 source. Each count was analyzed by a computer program for de-termination of gamma energies and peak areas. All results were printed out immediately following analysis on-site, and data was stored on floppy discs for future analysis, as needed. Typical LLDs for U-235 and 'l-238 in soll are 1 and 2 pCl/g, respectively. D. Auger Hole Logging System Detailed logging of selected auger holes was performed with the system shown in Fig. 1-5. This system consists of a custom designed EG&G Ortec Intrinsic germanium detector (10% off) with a narrow dewar, coupled to a Tracor-Northern 1750 MCA used for data acquisition and initial field evalua-tions. Data were stored on a tape cassette recorder, then 48

, ~ - transferred to the lab computer system for flhaj analysis. The entire system, including an NIM module power supply with a bias power supply and amplifier, was powered in the field by a portable 5 BOO watt gasoline-driypr ge'nerator. x s The logging system was calibrated as< described in t- ~, tachment 1. Field counting times were normally 10 minutes s at each location. Typical LLDs for this system for a 10 minute count are 0.1 pCI/g for U-235 1 pC1/g for U-238, 0.2 s pCl/g for Pb-212 and 0.1 for pCI/g Pb-214. E. Alpha-Beta Counting System. All t par, tic 4 ate air samples and evaporated water sam-pies were couited for gross alpha or beta detivity on the Gamma Products low background gas flow proportional counter, shown in Fig. 1-6. The system is automattu and Osn be pro-grammed for a variety of counting parameters. s s ~ b ...g e f 's*. 6 \\% 49 i ^" J s <

l

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l I s b I .r s l L s \\ s h \\ d g e 4* m a w p. k, ATTACHMENT 1 TO APPENDIX l x h V N s + 4 4 rg s k,* .e a s g t A 4 M e e 4 a 4 4 w { s e 50 s a

INTRINSIC GERMANIUM WELL LOG DETECTOR CAllBRATION The Intrinsic germanium detector was connected to the pulse height analysis system consisting of the following components: Ortec Model 459 High Voltage Power Supply Canberra 2011 Spectroscopy Amplifier Tracor Northern 1750 MCA Teletype Model 43 Printer Gain and voltage supply settings were adjusted to ob-tain an energy spectrum of 0 to 2000 kev, which corresponds to approximately one kev per channel. Calibration of the well logging system was performed using tho calibration rig shown in Fig. l-7. This rig is constructed as a series of four concentric rings surrounding a six inch PVC casing. Each ring contains thin plastic tubes 1-1/4" diameter by 36" long. A set of " source rods" and " background rods" were prepared and loaded into these tubes in a variety of configurations for the various call-bration and test counts. The geometry of the rig is such that the distance from the center of the casing (or detector) to the center of the 51

l l Innermost ring is 3.75 inches, to the center of the second ring is 5.0 inches, to the center of the third ring is 6.25 inches, and to the center of the fourth ring is 7.50 inches. All volds between tubes were filled with low background sand. It was determined that the ratio of source volume in ecch ring to the total ring area was about 0.6. Hence, when source rods were fully loaded into a given ring, the activi-ty counted represented approximately 60% of the total area (volume) the detector viewed, and counts were adjusted ac-cordingly. ' Each source tube is a twelve Inch high by one Inch di-ameter tube filled with a material containing Eu-152. The source material was prepared by mixing the standard Eu-152 source solutlen with plaster of parts, at a constant ratio designed to give a uniform specific activity of 440 pCI/ gram. Backgrounc rods were fliled with " clean" plaster of parls. Plaster of paris was chosen because of its ease of

handling, ability to uniformly distribute the source throughout the material, and its density, which approximates that of common soll.

(Density of soII, 1.7-?.3 g/ cubic cm; density of plaster, 1.5 g/ cubic cm; density of

sand, 1.4 g/ cubic cm)

Four different configurations of source and blank tubes were used for the calibration. Source tubes were placed 52

h i three high in one of the four concentric rings of the rig for ecch count while the balance of the rig was filled with blanks. These configurations correspond to the source ma-terial being a radial distance of 3.75, 5.00, 6.25 and 7.50 inches frem the detector. Each configuration was counted for 900 seconds, and the area under each of the eight major Eu-152 photopeaks deter-mined for each count. As a calibration check for the low energy U-238 pho-

tons, a

second set of calibra Ion rods containing Cd-109 d (E =88 kev), was prepared and counted in a similar manner. Calculation of counts per gamma per gram was determined by the following method (for the Eu-152 rods): NCNTS/ GAMMA / GRAM = [NCNTS]/[(440pCI/g)(3.7E-2d/s/pCI)(900s)(ABUNDANCEgamma/d)] For each gamma energy, the not counts / gamma / gram vs distance from the center of the detector was liste2, These response curves were then plotted for each energy, for dis-tances and activ!tles which extend to zero net counts. This represents an "!nfinite" distance from the detector. Using these

curves, the total counts from the detector to an.in-finite distance was calculated by integrating the area under

~ 53

the curve using Simpson's rule for approximating integrals. Of prime importance is the integral from 2 inches to infini-ty, since this is the area the detector will view when placed inside a four-inch PVC casing. Finally, the integrated net count / gamma / gram, from two inches to infinity, was plotted vs energy, for each of the Eu-152 photons. With this efficiency curve, a specific ac-tivity in soll (pCI/ gram) can be determined from a bore hole count, assuming the radionuclide can be identified and its gamma abundance determined. The calculation is: SPECIFIC ACTIVITYpCI/gm(In soll) = [NETCOUNTS]/[(ABUNDANCEgamma/ dis)(2.22 dis / min /pCI) (MINUTES COUNTED)(EFFICIENCYcounts/ gamma /gm)] This determination will be valid so long as the ra-dioactive material is uniformly distributed to an " infinite" distance in soII, and the detector is in a four-inch PVC (or similar material) casing. Although soll should be at the surface of the casing, the data indicate that small volds will not produce sigalficant errors in activity estimations. Results of this calibration Indicate that an " infinite" thickness in soll for a bore hole logging device is about 10 Inches from the center of the detector.

Thus, for a.

four-inch

hole, gamma logging will only "see" activity out 54

to about seven or eight inches from the hole. For low enera gles (e.g. 100 kev), 50 to 60% of the total activity seen is in the interval of two to four inches. For energies above 500 key, this value is 40 to 50%. While this volume may not seen large. It represents several thousand (2000 to 4000) grams of soII, which is much larger than typical core sam-pies, and is therefore more representative of the actual soll activity. This calibration Indicates that the sensitivity of the IG well logging system is such that the Ra-226 daughter 81-214, as measured by the 47% abundant 609 kev peak, can be easily detected at one pCI/ gram in soII, in a five minute count, with a 95% confidence level and precision of 0.4 pCl/g. 55-

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I Figure I-7 CAllBRATION RIG ASSEMBLY "A" - 6" 1.D. PVC Pipe "B" - 1.25" diameter x 36" long butyrate source holder tubes "C" - 1" diameter x 12" long source tubes. 3 per holder tube "0" - IG Detector C B . _. I I . I- ~[ i; l B l l 1 - / s '9 O E t4 -j D l-- ' ' g-s l s, / A l Top View I l Cross Section 62

U.S. NUCLEAR REGULATORY COMMISSION BIBLIOGRAPHIC DATA SHEET NUR M R-M87 'RSIIo$ EEIluste"i o"I'""" "*"'*'elthe Combustion Eng neering Burial Site

2. tteare ei,*>

Hematite, Missouri 3 RECIPIENT'S ACCESSION NO. L. $"$oth G. S. McDowell S. I. Peck ^ ""f'1983 y D. W. Groff W. M. Somers F. L. Bronson June 9 PERFORMING OHGANi2ATION N AME AND M AILING ADDRESS (include 2,0 Codel DATE REPORT ISSUED Radiation Management Corporation uoyrs l YEAR 3356 Commercial Avenue July 1983 Northbrook, IL 60062 s etcave wan*s 8 (Leave Nankt

12. SPONSORING ORGANIZ ATION N AME AND M A! LING ADDRESS //nclude 2,p Codel
1. PR JECT / TASK / WORK UNIT NO Division of Fuel Cycle and Material Safety Office of Nuclear Material Safety and Safeguards

N N - B-6901 U.S. Nuclear Regulatory Commission Washington, DC 20555

13. T Y PE OF R E PO R T PE RIOD COV E RE D (Incius,ve cares)

Final Report

15. SUPPLEMENTARY NOTES 14 (Leave osm*/
16. ABSTH ACT (200 wr>rds or sess)

This report presents the results of a radiological survey of the burial site adjacent Management Corporation (RMC)g (C-E) plant in Hematite, Missouri, performed by Radiation to the Combustion Engineerin in the spring and summer of 1982. Measurements were made to determine external radiation levels, surface and subsurface radionuclide concentra-tions and radioactivity in air and water. Results show uranium concentrations in burial pits as high as 38 and 21 pCi/g for U-238 and U-235 respectively. Results also show uranium concentrations in surface soils as high as 4.7 and 1.1 pC1/g for U-238 and U-235 respectively. Based on an estimated U-234/U-238 activity ratio of about 10 to 1, the highest U-234 activity in the burial pits is estimated to be approximately 400 pC1/g, and in surface soils approximately 47 pCi/g. Radium and thorium concentrations did not exceed background levels. Radioactivity in water which exceeded EPA drinking water standards was found in two onsite monitoring wells.

17. KEY WOROS AND DOCUMENT AN ALYSis 17a DESCRIPTORS 17tt IDENTIFIERS OPEN ENDE D TERVS 18 AV AILABILITY STATEMENT 19 SE CURITY CLASS (Th,s reporfl 21 NO. OF PAGES Unclassi fied Unlimited 20 SECUPitTY CLASS (Thrs papel 22, P RICE Unclae,,,,.

S NRC F 03M 335 41141i m

UNITED STATC's* rouxrn ctcssent NUCLEAR REGULATORY COMMtI'lON

  1. 0S
  • f us WASHINGTON, D.C. 20555 WASM D C PE RW:T sue M OFFICIAL SUSINESS PENALTY FCR PRIVATE USE,1300 tja53:0lan//

1 IC' 5 g o, NHL I ' E l ' ' $T d b - P U t' f,i t( ~ put g, zos,s x -,a oppiItovIUN j}}

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