Text

Draft Radiological Survey of C-E Burial Site,Hematite,Mo
	ML20028C654
Person / Time
Site:	07000036
Issue date:	12/16/1982
From:	Booth L, Groff D, Peck S; RADIATION MANAGEMENT CORP. (RMC)
To:	; NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20028C650	List: ML20028C648; ML20028C654;
References
	CON-NRC-02-80-034, CON-NRC-2-80-34 21723, NUDOCS 8301110653
	Download: ML20028C654 (66)
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RADIOLOGICAL SURVEY OF THE COMBUSTION ENGINEERING BURIAL SITE HEMATITE, MISSOURI DRAFT REPORT L.

F.

Booth G.

S.

McDowell D.

W.

Groff W.

M.

Somers S.

I.

Peck F.

L.

Bronson Radiation Management Corporation Prepared For Division of Fuel Cycle and Material Safety U.

S.

Nuclear Regulatory Commission Under Letter Contract: NRC-02-80-034 l

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l 8301110653 821216 PDR ADOCK 07000036 C

PDR D/793

ABSTRACT This report presents the results of a radiological sur-voy 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 radi-ation levels, surface and subsurface radionuclide concentra-tions and radioactivity in air and water.

Results show uranium 235 and 238 concentrations as high as 21 and 38 pCi/g respectively in burial pits and

1. 1 and

4. 7 pCi/g, respectively, in surface soils.

Radium and thorium concen-trations did not exceed background levels.

Radioactivity in water which exceeded EPA drinking water standards was found in two on-site monitoring wells.

However, there is no indi-cation that buried materials are leaving the site in ground water flow.

TABLE DE CONTENTS I.

INTRODUCTION............................ 1 4

II.

SITE CHARACTERISTICS.....................

3 III.

RADIOLOGICAL SURVEY METHODS..............

6 I V.

RADIOLOGICAL SURVEY RESULTS............

10 l

t V.

CONCLUSIONS.............................I7 l

APPENDIX I................................

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LIST QE FIGURES 1.

Location of Combustion Engineering Facility,

Hematite, Missouri 2.

Burial' site at Combustion Engineering

Facility, Hema-tite, Missouri 3.

External exposure rates.in uR/hr, Cumbustion Engineer-ing Facility Burial Site.

4.

Locations of. surface soil 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.

5.

Location of bore holes used for subsurface logging and water sampling.

6.

In situ gamma spectrum at the 2-foot depth in bore hole 4,

using the IG detector and a 10 minute count time.

7.

in-sity gamma spectrum at the 4-foot depth in bore hole 6,

using the IG detector and a 10 minute count time.

8.

Location of water samples.

Sample numbers listed in Table 6 are shown in parentheses.

I-1 Portable survey instrument kit I-2 High sensitivity tissue equivalent ionization chamber system.

I-3 Ion chamber exposure rate vs NaI(TI) count

rate, Cumbustion Engineering Facility burial site.

I-4 Interior of mobile lab showing gamma counting system and other equipment.

I I-5 in situ auger hole logging system with intrinsic ger-l manium detector and narrow dewar assembly data acquisi-l tion equipment and storage / fill dewar.

I-6 Automatic alpha-beta gas flow proportional counter.

j I-7 Calibration rig assembly.

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LIST DE TABLES 1.

Gamma radiation levels-and beta-gamma count rates-at grid locations.

2.

Surface soil sample

-radionuclide concentrations (pCi/g+/-X error), by gamma analysis.

3.

Soil core sample radionuclide concentrations (pCi/g),

by gamma analysis.

4.

Bore hole NaI counts and IQ analyses (pCi/g).

5.

La glig bore ' hole measurements vs core sample analyses.

6.

Water sample analyses.

7.

Gamma spectroscopic analysis of selected water samples.

8.

Particulate high volume air samples, long lived activi-ty.

9.

Summary of off-site tackground radiological measure-ments.

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

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INTRODUCTION Radiation. Management Corporation under contract to the U.

S.

Nuclear Regulatoru Commission (NRC) parformed a radio-logical evaluation of the burial site adjacent to the Combustion Engineering plant in Hematite, Missouri.

An ini-tial site visit occured in March, 1982, and the detailed ra-dialogical 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 i

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 surfaces 2)

Measurement of radionuclide concentrations in surface soil and vegetations 3)

Measurement of radionuclide concentrations in i

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Pcga 2 subsurface deposits; 4)

Measurement of-gross alpha and beta activity

.in surface and subsurface water samples; 5)

Measurement of airborne radioactivitys Measurements were performed on-site using an RMC designed mobile laboratory facility.

Analyses which could not be performed on-site were sent to the RMC analytical la-boratory in Philadelphia, Pennsylvania.

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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 j

and/or commerical developments.

The plant proper is a res-tricted area, and completely fenced in.

The burial site is l

l located immediately to the east of the fence line, and ex-l tends to a wooded area at the site boundary (Fig. 2).

The l

active site is bounded by Route 21A on the

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

There i

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-linkrodt Chemical.

In 1961. United Nuclear took controls in 1970, United Nuclear and Golf van the facility in a Joint ventures and in

1974, Combustion Engineering assumed responsibility.

Burials were made in the late 50's and early 60's under the direction of both Mallinkrodt and Unit-ed Nuclear, in accordance with all applicable NRC (AEC) re-gulations.

Plant operations involve processing and treating vari-

Pcge 4 ous -uranium compounds.

All manner of uranium materials, ranging from depleted to highly enriched uranium, have been 1

used at this site.

While ang 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.

ki-lograms of U-235 (60 mci) have been disposed of.

Because all materials were assayed for U-235 only (by scanning with a

scintillator set to count the 186 kev gamma peak), no es-timate of total U-238 content has been made.

Additionally, some work on thorium fuel was performed, so there exists.the possibility that small quantities of thorium have been bu-I ried.

No other radioisotopes have been used or disposed of i

at this site, i

I The nature of the buried material is described as being primarily contaminated combustables and small pieces of i

equipment.

Apparently, the bulk of buried material consist-ed of paper, plastic and wood items.

Some metal items, such as pipes and buckets, have been buried, although no major metallic ob Jects, except possibly a

pick-up truck, were j

disposed o f.

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These materials were buried in 40 pits, each approxi-mately 20 feet by 40 feet by 12 feet deep.

The individual I

pits were not marked or otherwise identified, although some g

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Each i s covered by 2 to 5 feet of fill dirt.

The pits were not lifted or. prepared in any

way, nor were-they capped with special materials.

The soil 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 1/2 mile from the site.

The burial ground is an open grassy area with I

some apparent water run off.

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Pcge 6 III. 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 Ionization Chamber System, described in Ap-pendix I.

NaI(T1) scintillation detector measurements were also made at these points and a conversion factor for the NaI(TI) count rate versus mR/hr was established.

Once this factor was confirmed, the scintillation detector was used for all grid point measurements.

i At each grid point an end window G-M tube was used for surface measurements.

Open and closed window readings were made at 1 cm and the ratio of the two used to indicate the presence or absence of surface contamination.

B)

Measurement of Surface Radioactivity l

Based on external measurements, surface soil samples were collected from locations where surface deposits were

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The samples were dried and sealed in 500 ml aluminum cans for counting on the intrinsic germanium (IG) gamma ray spectroscopy system described in Appendix I.

Sedimer., samples from Joachim Creek and the small creek east of the site were also collected and analyzed using the same method.

On-site vegetation samples consisted of grasses which wMre located in areas where drainage and wind characteris-tics indicated the possibility that radioactive materials may have been transported from the original locations and l

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 NaI(TI) scintillation detector and scaler system.

These preliminary measurements were used to indicate the lo-cations and approximate magnitude of subsurface contamina-tion.

Selected holes were then logged using a

specially

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designed IG detector coupled to_a multi-channel analyzer system (see Appendix I).

Soil layers with gamma count rates 4

i exceeding background rates, as measured with the NaI(TI) de-tector were logged at one-foot' increments using the IQ de-tector.

Layers.which did not exceed background were logged at two foot increments.

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D)

Measurement of Radioactivity in Water

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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 i

the ground water flow through the pit areas.

Periodic sam-J ples were taken from these wells to measure any possible 1

change in ground water radionuclide contens.

Samples were o

also taken from the two creeks near the burial area.

)

i Water samples were filtered to remove suspended parti-

culates, then 100 ml aliquots were evaporated onto plan-chetts 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.

i E)

Mrasurement of Airborne Radioactivity i

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High volume air particulate samples were taken to meas-ure long lived activities.

These samples were counted for gross alpha and beta activity using a

low background gas flow proportional counter with methods described in Appendix I.

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.

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Pago-10 I V.

RADIDLOGICAL SURVEY RESULTS A)

' External Radiation Levels Results of the external radiation surveys are listed in Table l'

and shown in Fig.

3.

As can be seen, the only'de-tectable levels above normal background were found in the i

northwest corner of the burial site, adjacent to the facili-ty security fence.

It was readily determined that these elevated levels were due'to sources on-site, rather than bu-ried material, because - containers of UF6 are routinely stored near the des'ignated fence line in the security area.

I The survey results show that levels increase as one ap-proaches these containers, confirming that the source is primarily the UF6 containers, rather than material in the burial site.

The beta gamma count rates verify the absence of measureable surface contamination.

The negative findings are not unexpected since it is known that only small quantities of U-235 and U-238 have been disposed of.

The absence of detectable exposure levels l

indicate that little or no thorium wastes are present.

i B)

Surface Soil Analyses i

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A total of 11 surface soil samples were gathered from

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Page 11 the burial site.

In addition, 5 stream sediment samples were taken, 2 from the small creek boarding the burial site on the

east, and 3 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 soil 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 within the lower limits of detection of the counting system ured.

Several samples from the burial site surface showed measureable uranium activities, ranging from 1.7 to 4.9 pCi/g for U-238 and from 0.6 to 1. 1 pCi/g for U-235.

In each case but one, a positive U-238 finding corresponded to a

positive U-23S value.

For all

samples, the radium daughter and K-40 activities were relatively constant.

Although the uranium activities are slightly above back-ground in some cases, they do not exceed NRC target criteria for contaminants in soil.

i The source of this apparent low level surface contami-nation is not clear.

While it is possible that the contami-

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Pcgo 12 nation is a result of burial activities, it is also possible that it resulted from past effluent (i.e.

stack) releases.

L In either case, these surface activities seem to be a result of facility operations, rather than unusually high naturally occuring radionuclides because no corresponding uranium daughter activities can be found.

C.

Subsurface Soil 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 NaI(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. S 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 manner identical to the surface soil procedure.

In addi-tion, three core samples were sent to the RMC Analytical La-boratories for duplicate gamma spectral analysis and uranium determinations using alpha spectroscopy.

Each bore hole was logged with the NaI(TI) detector to l

identify areas of increased gross activity, then with the IG l

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Pcge 13 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 on-site core sample analyses are presented in Table 3.

In general, concentrations are con-sistant with. normal background levels, and are well within all target criteria.

However, several samples from bore I

hole 7 showed slightly elevated U-235 and U-238 activities, I

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 NaI(TI) de-tector, are present in bore holes 1 and 6, while increased U-235 and/or U-238 concentrations, as measured by the IG de-tector, are found in bore holes 6, 7 and 13 (bore holes 1

and 14 were not logged with the IG).

The isotopes shown in Table 4

were identified by measuring the following photopeaks:

93 kev for U-238, 186 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 bore hole 4, 2 foot depth, and bore hole 6, 4

foot depth, are shown in Figs. 6 and 7 respectively, and de-

Page 14 monstrate the ease with which these photopeaks can be iden-tified, even at relatively low concentrations.

The highest concentrations were measured in bore hole 6,

where levels as high as 21 pCi/g U-235 and 38 pCi/g U-238 were recorded.

Concentrations in bore holes 7 and 13 did not exceed 1

pCi/g U-235 and 14 pCi/g U-238.

All levels, except the 38 pCi/g U-238 concentration, are within the NRC target criteria shown in Table 8.

There were no elevated concentrations in the perimeter bore holes in the general direction of ground water flow (bore holes 8 and 11), nor were there elevated levels in other bore holes on-site which are believed to have been drilled directly through burial pits.

A set of core samples was sent to the RMC Analytical Labs for analysis a r. d compared with on-site measurements.

i Results are presented in Table 5 and show general agreement except for the U-238 values.

For this nuclide, the in situ measurements gave consistantly higher values than core sam-ple analysis.

The cause of this apparent systematic error j

has not been determined, and U-238 results for bore hole measurements have not been

reported, except in the case where gross NaI(TI) counts are above background or where po-sitive U-235 results are reported.

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D)

Analyses of Radioactivity in Water 1

A total of 22 water samples were collected (Fig. 8),

11 from the water monitoring wells installed for this project (bore holes 2, 3,

9 and 12),

3 from other bore holes l

on-site, 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 one

sample, taken from bore hole 1,

showed gross alpha ac-tivity exceeding the target criteria (MPC for U-235 in an unrestricted area, 30,000 pCi/1) or the EPA interim primary drinking uater limit for drinking water (15 pCi/l gross alpha).

This sample was further analyzed for isotopic con-tent, 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/1 was found in 6

different

samples, three of which came from bore hole 9, which was located approximately 200 feet east of Combusion Engineering's settling ponds.

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.

1 Page 16-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 likely to be a. source of airborne emissions, due to the absence of daughter activity which could produce gaseous emanations (radon).

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Radioactivity in Vegetation i

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Several vegetation samples, from on-site and off-site locations, were analyzed on the gamma spectroscopy system, t

No unusual activity was found in any sample.

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Pcgo.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 bore hole activity and soil samples taken from the burial pits showed slightly elevated levels of U-235 l

l and/or U-238 in some measurements, and only naturally. occur-j ing background activity in all others.

The highest ' level l'

measured during this survey was 38 pCi/g-.of U-238, which was the only measurement that exceeded the target criteria of 30 pCi/g U-238 or U-235.

These. measurements tend to confirm f

that generally only low level contaminated -materials and equipment were disposed of in these. pits.

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These survey results also indicate the difficulty in trying to determine specific locations of buried contamina-

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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

l (radium and daughters) makes it essentially impossible to.

located low level contaminated buried material with surface measurement techniques.

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l Although some elevated activity was found in bore hole l-

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. cant movement through ground water off-site.

The overall conclusions are that relatively small quan-tities of uranium have been buried and that the buried ma-terial is essentially stable at this time.

The burial pits l

have little or no effect on the population or the surround-J ing environment.

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REFERE;NCES m

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U. ' S.

Nuclear Regulatory Commission Letter Contract:

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.NRC-02-80-034, 13 Aug 1980.

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4 5

1000 -

g.

2 239 kev 5

c.

o Q

t

%'%g 5

l 1

m...c.-

" ** Y***7*S&.@j,g~;@..i.y. :.

100 i

E z g >. T J +..i.:;M-

~

l:

1 U238 -

38 pCi/g U235 -

21 pCi/g l

i Pb212-1.9 pCi/g Pb214-0.2 pCi/g l

10 l

l 1

i a e i g i i s s [0sa:sgia: ilss:igis ilsiiigieiils aigi: ai aisigiisagiiiigiiisgii:igi:iigiiiagiiaigieiigiiiigii Channel 50 lu 200 300 400 50 600 700 800 900 1000 Energy (kev) 50 100 200 300 400 500 Fig.

7.

In situ gamma spectrum at the 4 foot depf.h in borehole 6, using the IG detector and a 10 minute count.

t

/

Highway 21-A 9

r J

m i

Admin.

Bldg.

J BH 1.

I Vo a l

(14) l N

l

- - Uo To -

l So Ro l

Qo

{-]

l Fenced Po j

Security Area 00 No Ho Lo BH,6.

D H, 3.

Ko (1)

(16,20)

I I

Jo Io

- -------"2 I2'I7'2l) 4^

Ho J

Bit z.

o,.

(7,15,19)

Fo a

2. E p."

^

Bl( 12.

o,

1 i,,,,,, '

llll

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0]

a i

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80 y

Ao i

i i

i I

oA oB oC oD oE of oG oH of oJ oK oL OM ON 00 oP oQ oR oS oT l

F 50 meters Fig. 8.

Location of water samples, Sample numbers listed in Table 6 are shown in parentheses.

. 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)

GOOK 1700 9

40 70 G00L 1700 9

50 50 G00M 1800 10 50 40 GOON 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 KOOK 1700 9

40 40 K00L 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 M00M 2100 12 30 60 MOON 2000 11 50 60

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)

M000 2000 11 40 60 M00P 1800 10 40 80 NOOK 1800 10 80 100 NOOL 2300 13 70 90 N00M 2100 12 60 110 N00N 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 i

POOK 2000 11 40 60 POOL 3200 17 80 100 POOM 2700 14 90 100 c

l P0ON 2800 15 80 100 P000 2200 12 70 70 Q00K 4100 22 50 60 QOOL 5000 26 60 90 QOOM 3800 20 60 100 QOON 3000 15 50 80 Q000 2600 13 80 50 ROOK 4500 23 100 140 ROOL 11000 56 140 130 ROOM 5000 26 110 80 ROON 3500 18 60 50 R000 2600 13 40 70 S00K 50000 256 360 320 S00L 13000 67 110 90 S00M 6000 31 100 140 S00N 3800 20 90 110 S000 2800~

14 80 80 TOOK 45000 231 530 490 TOOL 12000 62 120 150 TOOM 5000 26 100 110 TOON 3700 19 80 90 T000 2700 14 90 100 UOOK 17000 87 80 100 U0OL 8000 41 90 90 UOOM 4000 21 80 60 UOON 3500 18 70 60 i

U000 2500 13 90 110 l

U0OK 5000 26 130 110 000L 3500 18 70 80 l

UOOM 3500 18 60 80 U00N 3000 15 80 100 l

0000 2300 12 90 70

Tcblo 2 Surf ace soll sample radionuclide concentrations (pCl/g +/- % error) by gamma analysis Sample Sample Location Mass U-238 U-235 Ac-228 Pb-212 Pb-214 B1-214 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 2

B50L 299 1.2E0t/-110 2.7E-2+/-380 7.5E-1+/-63 5.9E-1+/-30 9.7E-1+/-35 5.9E-1+/-46 8.5E0t/-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 6

K310 224 4.9E0+/-39 1.1E0+/-71 5.7E-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-1+/-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 4.3E-1+/-37 5.6E-1+/-51 4.7E-1+/-55 4.1 E0+/-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 downstrear 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

Tcblo 3 Soll core sample radionuclide concentrations (pCI/g), 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+/-200%

1.2E-1+/-120%

1.9E-1+/-220% 5.6E-1+/-36% 1.0E0+/-39% 7.0E-1+/-42% 9.9E0+/-315 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 1.1 E0+/-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% 2.4E-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+/-200% -2.2E-2+/-500% 4.2E-1+/-110% 5.0E-1+/-37% 1.4EO+/-29% 7.4E-1+/-41% 8.5E0+/-34%

5 248 5.6E-1+/-2605 -2.6E-3+/-3800% 5.7E-1 +/-79%

6.4E-1+/-28% 1.1E6+/-33% 8.5E-1+/-345 1.2El+/-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+/-680%

1.1E0+/-46%

5.8E-1+/-31% 9.5E-1+/-37% 5.3E-1+/-47% 1.1El+/-27%

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+/-315-9 256 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%

t 10 218 1.8E0+/-98%

3.5E-2+/-280% 6.5E-1+/-79%

8.6E-1+/-26% 9.2E-1+/-43% 8.IE-1+/-40% 1.2El+/-29%

11 232 1.3E0t/-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%

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 Depth Mass U-238 U-235 Ac-228 Pb-212 Pb-214 BI-214 K-40 (ft)

(g) 0 216 1.1E0+/-160%

2.6E-1+/-74%

1.4E-1+/-290% 5.3E-1+/-36% -5.3E-1+/-33% 6.3E-1+/-49% 9.7E0+/-335 1

252 1.3E0+/-110%

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+/-355-3 236 2.1E0+/-77%

2.6E-1+/-74%

6.6E-1+/-77%

4.4E-1+/-41% 9.2E-1+/-38% 7.8E-1+/-385 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% 1.1El+/-30%

8 219 3.0E0+/-61%

1.4E0+/-64%

7.0E-1+/-76%

8.1E-1+/-43% 8.7E-1+/-43% 6.7E-1+/-45%

1.3El+/-26%

9 249 1.1E0+/-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%

6.3 E-1 +/-79%

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%

Tcble 3, cont.

Borehole ill 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+/-2205 6.5E-1+/-33%

6.9E-1+/-33% 1.3E0+/-39%

5.3E-1+/-63%

1.1El+/-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%

1.7E-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% 1.1E0+/-34%

8.3E-1+/-37% 1.3E1+/-25%

4 235 1.2E0+/-130%

9.2E-2+/-120% 2.5E-1+/-150% 2.0E-1+/-83% 8.4E-1+/-42% 2.5E-1+/-1005 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 3.0E0t/-47%

1.0E-2+/-630% - 9.4E-1 +/-52%

8.6E-1+/-22% 8.2E-1+/-41% 5.8E-1+/-44% 9.7E0t/-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% 6.4E-2+/-130% 1.5E-1+/-220% 3.0E-1+/-44% 4.8E-1+/-58% 5.4E-1+/-47% 5.3E0+/-44%

11 272 1.6E0+/-84%

1.2E-2+/-570% 1.1E0+/-47%

4.9E-1+/-32% 1.3E0+/-27%

4.1E-1+/-57% 7.4E0+/-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%

1.1E-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+/-425 1.2El+/-28%

l l

l

Tablo 4 Bore hole Nai counts and IG analysis (pCl/g)

Borehole #1 Gross Nel Depth Counts / Min U-235 IF238 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%

16 3.08E3+/-2%

18 3.29E3+/-2%

Borehole #4 Gross Nal Depth Counts / Min U-235 U-238 Pb-212 Pb-214 0

2.5E3+/-200%

1.0E3+/-2%

3.5E-1+/-17%

5.3E-1+/-21%

2 3.1E3+/-2%

1.8E-2+/-29%

5.6E-1+/-12%

4.8E-1+/-17%

4 3.3E3+/-2%

4.5E-3+/-440%

6.1E-1+/-11%

6.0E-1+/-12%

6.1E-1+/-11%

6.9E-1+/-10%

6 3.5E3+/-2%

9.8E-3+/-497%

I 3.1E-1+/-18%

8.6E-1+/-8%

8 3.3E3+/-2%

1.1E-1+/-42%

10 3.3E3+/-25 1.0E-1+/-43%

6.1E-1+/-125 1.1E0+/-7%

12 3.2E3+/-2%

5.9E-2+/-373%

6.5E-1+/-10%

8.6E-1+/-11%

14 3.1E3+/-2%

3.0E-2+/-600%

7.7E-1+/-8%

7.4E-1+/-16%

6.8E-1+/-105 1.1E0+/-8%

16 3.2E3+/-2%

7.8E-2+/-1125 18 3.1E3+/-2%

5.8E-2+/-81%

8.1E-1+/-85 7.4E-1+/-10%

l Tcble 4, cont.

)

Borehole #5 i

Gross Nal Depth Counts / Min U-235 U-238 Pb-212 Pb-214 6.8E-1+/-9%

6.7E-1+/-10%

J 0

3.83E+/-32%

1.5E-1+/-25%

7.2E-1+/-9%

6.5E-1+/-11%

1 2

3.0E3+/-2%

9.3E-2+/-49%

5.8E-1+/-13%

7.8E-1+/-10%

f 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 3.4E3+/-2%

2.9E-2+/-161%

4.7E-1+/-14%

9.8E-1+/-8%

j 12 3.5E3+/-2%

7.4E-3+/-63%

5.5E-1+/-12%

9.0E-1+/-8%

14 3.2E3+/-2%

3.6E-3+/-1250%

4 5.5E-1+/-12%

1.0E0+/-6%

l 16 3.1E3+/-2%

7.5E-2+/-59%

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+/-5%

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+/-325 5

1.9E4+/-1%

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+/-12%

10 3.8E3+/-2%

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 3.4E3+/-2%

7.2E-1+/-7%

1.1El+/-12%

7.7E-1+/-10%

7.2E-1+/-10%

16 3.2E3+/-2%

7.7E-1+/-8%

8.3E0+/-15%

8.5E-1+/-9%

5.7E-1+/-12%

18 3.2E3+/-2%

8.7E-1+/-6%

1.1El+/-11%

7.7E-1+/-10%

7.6E-1+/-10%

Tcblo 4, cont.

Borehole #7 Gross Nai Depth Counts / Min U-235 U-238 Pb-212 Pb-214 0

2.4E3+/-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%

7.1E-1+/-12%

2 2.7E3+/-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 2.3E3+/-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%

3.1E-1+/-12%

5.7E0+/-15%

8.3E-2+/-32%

3.9E-1+/-11%

l 12 3.0E3+/-2%

1.0E-1+/-29%

6.0E0+/-16%

2.8E-1+/-12%

4.9E-1+/-10%

l 14 3.0E3+/-2%

1.7E-1+/-21%

7.6E0+/-12%

2.5E-1+/-11%

5.3E-1+/-10%

i 16 3.0E3+/-2%

3.2E-1+/-14%

8.9E0+/-11%

4.8E-1+/-10%

8.1E-1+/-9%

l l

18 3.4E3+/-2%

l l

Borchole #8 Gross Nal Depth Counts / Min U-235 U-238 Pb-212 Pb-214 l

0 2.6E3+/-2%

6.0E-2+/-77%

4.3E-1+/-13%

5.6E-1+/-12%

4.0E-1+/-14%

6.1E-1+/-13%

j 2

3.1E3+/-2%

2.0E-1+/-20%

2.5E-1+/-29%

5.9E-1+/-12%

{

4 3.1E3+/-2%

1.6E-2+/-302%

4.2E-1+/-15%

5.8E-1+/-14%

l 6

3.3E3+/-2%

8.5E-2+/-41%

4.7E-1+/-12%

7.5E-1+/-10%

{

8 3.2E3+/-2%

9.7E-2+/-35%

10 3.1E3+/-2%

2.7E-2+/-176%

2.4E-1+/-26%

7.4E-1+/-10%

j 4.5E-1+/-14%

5.6E-1+/-12%

1 12 3.1E3+/-2%

1.2E-1+/-31%

1.1E-1+/-68%

6.8E-1+/-11%

14 3.1E3+/-2%

7.2E-2+/-47%

3.5E-1+/-18%

8.0E-1+/-9%

16 3.1E3+/-2%

4.8E-2+/-125%

7.3E-1+/-9%

7.7E-1+/-95 l

18 3.1E3+/-2%

2.7E-2+/-200%

m

Tablo 4, cont, Borehole #10 Gross Nel Depth Counts / Min U-235 l}-238 Pb-212 Pb-214 0

2.3E3+/-2%

1.7E-1+/-it%

3.3E-1+/-225 7.8E-1+/-85 2

3.1E3+/-2%

2.6E-2+/-140%

6.9E-1+/-95 9.4E-1+/-7%

4 3.2E3+/-2%

3.9E-2+/-115%

4.4E-1+/-14%

f.JE-1+/-13%

6 3.4E3+/-25 5.8E-2+/-955%

5.4E-1+/-14%

9.8E-1+/-65 8

3.4E3+/-2%

1.2E-1+/-34%

6.8E-1+/-10%

9.3E-1+/-7%

10 3.3E3+/-2%

6.8E-2+/-9005 4.9E-1+/-15%

8.8E-1+/-9%

12 3.4E3+/-2%

4.0E-2+/-538%

6.0E-1+/-11%

8.0E-1+/-9%

14 3.2E3+/-2%

1.4E-2+/-25%

5.6E-1+/-14%

9.6E-1+/-75 16 3.2E3+/-25 4.9E-2+/-101%

3.7E-1+/-20%

8.3E-1+/-95 18 3.1E3+/-21 1.9E-1+/-25%

4.3E-1+/-15%

9.7E-1+/-75 Borehole #11 Gross Nat Depth Counts / Min U-235 U-238 Pb-212 Pb-214 0

2.3E3+/-25 1.0E-1+/-455 3.8E-1+/-16%

5.6E-1+/-13%

2 2.9E3+/-25 1.2E-1+/-40%

7.6E-1+/-95 6.2E-1+/-125 4

3.1E3+/-2%

5.3E-2+/-423%

2.6E-1+/-24%

7.0E-1+/-10%

6 3.4E3+/-2%

4.9E-3+/-970%

5.9E-1+/-12%

9.4E-1+/-8%

8 3.3E3+/-25 1.2E-3+/-3700%

5.OE-1+/-11%

6.5E-1+/-12%

10 3.3E3+/-2%

4.5E-2+/-190%

5.8E-1+/-12%

7.3E-1+/-105 12 3.2E3+/-2%

8.6E-3+/-530%

3.9E-1+/-165 7.6E-1+/-105 14 3.0E3+/-2%

9.3E-2+/-50%

3.9E-1+/-16%

4.7E-1+/-165 16 3.0E3+/-2%

1.1E-1+/-31%

4.6E-1+/-14%

6.9E-1+/-10%

18 3 OE3+/-21 2.4E-2+/-173%

3.2E-1+/-17%

9.2E-2+/-8%

Tcblo 4, cont.

Borehole #13 l

i Gross Nal 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 3.1E3+/-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%

8.0E-1+/-7%

4.9E0+/-22%

3.4E-1+/-15%

4.8E-1+/-10%

I 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%

14 3.3E3+/-2%

2.4E-1+/-20%

1.4El+/-85 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%

l' 18 3.2E3+/-2%

2.7E-1+/-18%

3.6E0+/-32%

5.8E-1+/-12%

6.7E-1+/-11%

l l

i I

.Tcblo 5 in st+u bore hole measuienents vs core sample analyses Core Core in situ Sample Gamma Sample Gamma Core Borehole 7 Gamma Spectroscopy Spectroscopy Sample Alpha l

8 foot Spectroscopy On Site RMC Labs Spectroscopy (pCl/g)

(pCl/g)

U-235 1.0+/-5%

1.4+/-64%

2.2+/-27%

1.2+/-23%

U-238 6.2+/-13%

3.0+/-61%

<10 3.2+/-16%

Pb-212 0.3+/-19%

0.8+/-43%

<1.2 Pb-214 0.5+/-12%

0.9+/-43%

0.8+/-16%

.BI-214 0.7+/-45%

0.7+/-17%

f K-40 13+/-26%

20+/-10%

Borehole 7 l

10 Foot l

1 U-235 0.3+/-12%

0.8+/-125 1.5+/-27%

0.5+/-39%

l U-238 5.7+/-14%

1.5+/-120%

<11 1.1+/-25%

i Pb-212 0.8+/-10%

0.6+/-31%

<1.3 Pb-214 0.4+/-15%

1.0+/-38%

0.9+/-13%

BI-214 0.6+/-50%

0.7+/-14%

K-40 12+/-28%

19+/-10%

i Borehole 7 11 Foot U-235 0.1+/-130%

<0.5

<0.9 U-238 1.4+/-120%

<11 0.5+/-40%

Pb-212 0.6+/-30%

<1.9 Pb-214 1.2+/-44%

0.9+/-18%

Bi-214 0.7+/-44%

1.2+/-25%

K-40 9.5+/-32%

18+/-10%

Table 6 Water sample analyses l

Sample Gross Alpha Gross Beta No.

Sample Location (pCI/l)

(pCI/l) 1 Bore hole #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 SmalI 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%

l 7

Bore hole #2-4/2/82 1.7E0+/-110% 2.0El+/-30%

8 Bore hole #7-3/26/82 8.8E0+/-32%

1.4El+/-31%

9 Joachim Creek downstream 1.0E0+/-160% 3.1El+/-20%

10 SmalI creek upstream 8.3E-1+/-200% 2.2E2+/-5%

11 Joachim Creek midstream 1.7E-1+/-56% 1.2E2+/-7%

12 Bore hole #9 4/2/82 2.3E0+/-80%

3.2E2+/-4%

13 Bore hole #12 4-2-82 1.1El+/-28%

6.1E0+/-90%

14 Bore hole #1 3/24/82 1.8E2+/-6%

1.3E2+/-7%

15 Bore hole #2 4/16/82 8.3E-1+/-200% 1.7El+/-27%

16 Bore hole #3 4/16/82 1.2E0+/-140% 8.9E0+/-56%

I 17 Bore hole #9 4/16/82 1.7E0+/-110% 4.7E2+/-3%

18 Bore hole #12 4/16/82 2.7E0+/-73%

2.3E0+/-230%

19 Bore hole #2 4/22/82 2.0E0+/-91%

8.8E0+/-56%

20 Bore hole #3 4/22/82 1.5E0+/-120% 2.1El+/-29%

21 Bore hole #9 4/23/82 2.0E0+/-91%

5.0E2+/-3%

22 Bore hole #12 4/22/82 1.0E0+/-160% 2.5El+/-24%

_ ~ _-

Gamma spectroscopy analysis of selected water samples Isotopic Results 1

Sample U-238 U-235 Th-232 Rn-226 K-40

{

No.

Sample Location (pC1/1)

(pCI/l)

(pCl/I)

(pCl/l)

(pCI/I) i2 Bore hole #9 4/2/82 1.0El+/-31%

3.8El+/-15%

1.2El+/-72% -3.7E0+/-150% 5.0El+/-735 14 Bore hole #1 3/24/82 5.3El+/-53%

6.8E0+/-66% 1.9E1+/-46% -6.7E0+/-77%

8.0E1+/-43%

1 I

i 1

f i

i Y

i l

I i

Table 8 Particulate high volume air samples, long lived activity Date Location Gross Alpha Activity Gross Beta Activity (uCl/ml)

(uCI/ml) l

[.

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 l

l 4/14/82 3 m downwind of 1.1E-14+/-58%

3.9E-14+/-38%

l bore hole #1 l

l 4/15/82 South of plant 5.8E-15+/-149%

2.8E-14+/-99%

4/15/82 South of parking 2.7E-14+/-49%

3.7E-14+/-75%

lot l

1 4

l l

l

_ ~ _

~Tablo 9 Summary cf cff-site background radiological me:surements Type of Measurement Value External exposure rate s

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 uCl/ml +/- 99%

Soll radionuclide U-238 3.6E-1(pCI/g)+/-460%

t concentrations U-235 1.5E-1(pCl/g)+/-130%

Ac-238 1.1E-1(pCl/g)+/-330%

Pb-212 2.4E-1(pCl/g)+/-70%

Pb-214 8.5E-1(pCl/g)+/-48%

D1-214 4.9E-1 ( pCl/g)+/-65%

K-40 8.7E0(pCl/g)+/-37%

Water Activities Gross alpha Gross beta SmalI creek upstream 8.3E-1+/-200

-7.9E0+/-590%

SmalI 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%

I

Tcblo 10 Target criteria and measurement LLDs for Combustion Engineering Facility burial site.

Soll Contaminants

(

NuclIde Target Criterla LLD Ra-226 5pCl/g 1pCl/g Total U 15pCl/g 3pCl/g l

U-238 30pCI/g 6pCI/g U-235 30pC1/g 6pCl/g Th-232

5pCI/g 1pC1/g Th-230 15pC1/g 3pCl/g Water and Airborne Contaminants NuctIde Target Criteria LLD All MPC Unrestricted 20% MPC Ra-226 (water) 3E-8 uCl/mi 6E-9 uCI/mi External Radiation Nuclide Target Criteria LLD All 20 uR/hr 4 uR/hr

Th-232 in equilibrium with daughters

APPENDIX 1 i

i

/

i Radiological Survey Instruments and Methods l

l l

i baain-m

Page 2~

A.

Portable: Survey-Instrument The portable survey instruments used at the C-E. facility bu--

~

rial site included two complete sets of Wm.

B.

Johnson & Associ-atos equipment, which consist of battery operated rate

meters,

. scalers.and alpha, beta and gamma probes,'and an Eberline PRS 41 l

l-

'ratemeter scaler and detectors.

-These systems-(see Fig. I-1) are totally portable and can be used in-the field for both measure-ments and sample counting.

The alpha probes use a ZnS(Ag) scintillation detector; the beta detector is a thin window (1.4mg/cm2 mica) GM tube, and the gamma detectors are NaI(TI) crystals.

The alpha and beta probes were calibrated with "NBS traceable" sources at the RMC calibra-tion facility in Philadelphia and the gamma scintillator was cross-calibrated with a primary ionization chamber system, des-cribed below.

B.

Ionization Chamber System External gamma dose rates were accurately measured with the RMC constructed Tissue Equivalent Ionization Chamber System (Fig.

I-2).

This system consisted of a 16 liter tissue equivalent, gas filled ionization chamber (Shonka chamber), a Keithley vibrating l

capacitor electrometer, a printer and battery pack.

It is capa-3 J

ble of measuring dose rates at background levels to a precision r

1 4

k 3,-

3.-

3 i--~

y v,-

,e--

,,-woe"

-w-

+--mwe----ww-

--c-,e g

e-3r----,,--+--we-w,-~~~--+----

ev.

e-g-s-r--

+=rve-

<-m-wmw-~*---*

-r

Pega.3 of a_few percent.

Since this system is bulky and somewhat fragile, it is not as suited for extensive field-measurements as a smaller, light-weight NaI(TI) portable survey instrument.

Therefore, the NaI(TI) detector was used for the majority of the field gamma measurements.

Since this detector 's response is-energy depen-

dent, it cannot besused as a " micro R meter" unless it is ini-tially calibrated for such use.

The calibration performed by RNC consisted of accurately measuring the exposure rate at several locations at the C-E fa-cility burial site using the Tissue Equivalent Ionization

Chamber, then recording Nal(TI) measurements at the same loca-tion.

In this manner a set of NaI(T1) 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 NaI

detector, this conversion factor will apply only to the radionuclides and geome-tries for which the calibrations were made.

In the caso of the C-E facility burial site, it is known that only naturally occur-ring 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 radionuclides distributed in soil.

1

i. -O[

~

~pegg 4 lC.

Mobile Lab-Gamma Analquis System The-mobile lab gamma analysis system.(Fig. I-4)_ cons'nts of i

a.

PQT-15% efficient (relative to-a 3" x 3" NaI(TI) crystal) in-trinsic germanium (IQ) detector. shield and Tennecomp -TP-50 la-boratory computer data acquisition module.

The analysis system was calibrated for all counting geometries with an. NUS supplied Eu-152 source, Each count was' analyzed by a computer progenm for-determina-tion 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 U-230 in soil are 1 and 2 pCi/g, I

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 EO&O Ortec intrinsic germanium detector (10% off) with a narrow dewar, coupled to a Tracor-Northern 1750 MCA used for dnta acquisition and initial field evaluations.

Data were stored on a tape cassette recorder, then transferred to the lab computer sys-tem for final analysis.

The entire system. including an NIM mo-t

Pcgo 5 4

dule power supply with a bias power supply and amplifier, was powered in the field by a portable 5000 watt gasoline-driven gen-f l

erator.

{

The logging system was calibrated as described in Attachment 1.

Field counting times were normally 10 minutes at each loca-I f

tion.

Typical LLDs for this syster,t for a 10 minuta count are O.1 pCi/g for U-235 1 pC1/g for U-238, 0.2 pCi/g for Pb-212 and 0.1 for pCi/g Pb-214.

E, Alpha-Beta Counting System.

)

1 1

All particulate air samples and evaporated water samples

(

l were counted for gross alpha or beta activity on the Gamma Pro-

)

ducts low background gas flow proportional

counter, shown in i

Fig.

I-6.

The system is automatic and can be programmed for a variety of counting parameters.

l l

Page 6 l

l l

l I

L ATTACitMENT 1 TO APPENDIX I

Page 7 r

L INTRINSIC CERMANIUM WELL LOG i

L DETECTOR CALIDRATION 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 17S0 MCA Teletype Model 43 Printer Gain and voltage supply settings were adjusted to obtain an energy spectrum of O to 2000 kev, which corresponds to approxi-mately one kev per channel.

Calibration of the well logging system was performed using the calibration rig shown in Fig.

I-7.

This rig is constructed c, 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 pre-pared and loaded into these tubes in a variety of configurations for the various ;alibration 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 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

Page O the center of the fourth ring is 7.50 inches.

All voids between tubes were filled with low background sand.

It was determined that the ratio of source volume in each ring to the total ring L

area was about

0. 6.

Hence, when source rods were fully loaded into a given ring, the activity counted represented approximately 60%

of the total area (volume) the detector viewed, and counts ad usted accordingly.

were J

Each source tube is a twelve inch high by one inch diameter tube filled with a material containing Eu-152.

The source ma-terial was prepared by mixing the standard Eu-152 source solution with plaster of paris, at a constant ratio designed to give a un-iform specific activity of 440 pCi/ gram.

Background

rods were filled with " clean" plaster of paris.

Plaster of paris was cho-sen because of its ease of handling, ability to uniformly distri-bute the source throughout the material, and its density, which approximates that of common soil.

(Density of

soil, 1.7-2.3 g/ cubic cms density uF

plaster, 1.b g/ cubic cms density of

sand,

1. 4 g/ cubic cm)

'r > u r different configurations of source and blank tubes were used for the calibration.

Source tubes were placed three high in one of the four concentric rings of the rig for each count while the balance of the rig was filled with blanks.

These configura-tions correspond to the source material being a radial distance of 3.75, 5.00, 6.25 and 7. DO inches from the detector.

Pcgo 9 f

Each configuration was counted for 900 seconds, and the area under each of the eight major Eu-1S2 photopeaks determined for each count.

As a calibration check for the low energy U-238

photons, a

second set of calibration rods containing Cd-lO9 (E =88 kev), was f

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):

NCNTG/OAMMA/ GRAM =

l fNCNTS]/C(440pci/g)(3.7E-2d/s/pCi)(900s)(ADUNDANCEgamma/d)]

{

l l

For each gamma energy, the not counts / gamma / gram vs distance I

from the center of the detector was listed.

These response curves were then plotted for each energy, for distances and ac-tivities which extend to zero net counts.

This represents an l

" infinite" distance from the detector.

Using these

curves, the total counts from the detector to an infinite distance was calcu-lated by integrating the area under the curve using Simpson's rule for approximating integrals.

Of prime importance is the in-tegral from 2 inches to infinity, since this is the area the de-tector 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-102

Page 10 photons.

With this efficiency curve, a sp9cific activity in soil (pCi/ gram) can be determined from a bore hole count, assuming the radionuclide can be identified and its gamma abundance deter-mined.

The calculation is:

SPECIFIC ACTIVITYpC1/gm(in soil)

=

CNETCOUNTS]/E(ADUNDANCEgamma/ dis)(2.22 dis / min /pCi)

(MINUTES COUNTED)(EFFICIENCYeounts/ gamma /gm)J This determination will be valid so long as the radioactive material is uniformly distributed to an " infinite" distance in soil, and the detector is in a four-inch PVC (or similar materi-al) casing.

Although soil should be at the surface of the cas-ing, the data indicate that small voids will not produce signifi-cant errors in activity estimations.

Results of this calibration indicate that an

" infinite" thickness in soil 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 to about seven or eight inches from the hole.

For low energies (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 kev, this value is 40 to 50%.

While this volume may not seem large, it represents several thousand (2000 to 4000) grams of soil, which is much larger than typical core samples, and in therefore more representative of the actual soil activity.

Pego 11 This calibration indicates that the sensitivity of the IO

-well logging system is such that the Ra-226 daughter Bi-214, as measured by the 47% abundant 609 kev peak, can be easily detected at one pCi/ gram in soil, in a five minute count, with a 95X con-

^

fidence level and precision of O.4 pC1/g.

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