ML19317E169

Rept of Preoperational Environ Radioactivity Monitoring Program

ML19317E169
Person / Time
Site:	Oconee
Issue date:	06/15/1971
From:	Lashawnna Lewis DUKE POWER CO.
To:
References
NUDOCS 7912160036
Download: ML19317E169 (54)

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Seneca, S. C.

REPORT OF l

PRE-OPERATIONAL ElVIR0NMENTAL RADIOACTIVITY M0NITORING PROGRAM i

O s

i S l

Prepared by:

Lionel Lewis System Health Physicist June 15, 1971 k

P_ 3 1 f,A_ { {

The Pre-operational Environmental Radioactivity Monitoring Program for the Oconee Nuclear Station has been discussed and reviewed with the South Caro-lina State Board of Health, Division of Radiological Health, and the South Carolina Pollution Control Authority. The U. S. Government Fish and Wild-life Service has also been advised of the program through their district of fice in Atlanta, Georgia.

In addition, the program was discussed with the South Carolina Wildlife Resources Department and this department is co-operating with Duke Power Company in regard to the collection of fish and animal samples.

1 4

9 1

i

l I

ACKNOWLEDGEMENTS Recognition and thanks are due to the following persons for their contributions to the environmental monitoring program and to this report:

Mr. W. T. Linton and Mr. W. G. Crosby of the South Carolina Pollution Control Authority and the South Carolina State Board of Health, Division of Radiological Health, respectively, for their assistance in reviewing the program.

Mr. J. C. Fuller, Jr. and his staff of the South Carolina Wildlife Resources Department for their assistance in specifying and facilitating the collection of animal and fish specimens.

Dr. J. E. Halpin of Clemson University and Mr. A. J. Kish of the Weather Bureau for their help in establishing a sampling station on the University campus.

Mr. C. L. Thames, Health Physics Supervisor, and Mr. C. T. Yongue, Health Physics Technician, Oconee Nuclear Station for conducting the program.

Mr. R. W. Gudger, Jr., Wildlife Biologist, Duke Power Company, for collecting the animal specimens.

Mr. D. L. Archer of the South Carolina Wildlife Resources Department for collecting the fish specimens.

Mr. G. E. Wilson of Duke Power Company for his help in compiling the data.

Mrs. Pat Campbell of Duke Power Company for filing and tabulating data and typing the manuscript.

O e

11

TABLE OF CONTENTS ElUUL 4

Preface i

Acknowledgements.

11 i'

Table of Contents iii I.

Introduction 1

A.

Description of the Oconee Nuclear Station 2

i B.

The Pre-Operational Program 6

C.

Details of Specialized Sample Collection and 10 Co nting Methods II.

Summary and Discussion of Results 17 Appendices 1.

Sample.inalysis Procedures 32 2.

Early Pre-Operational Results 48 3.

The Operational Program 49 i'

i-1

}

i i

L 1

4

+

111

OCONEE NUCLEAR STATION PRE-OPERATIONAL ENVIRONMENTAL RADIOACTIVITY MONITORING PROGRAM REPORT I.

Introduction Generally, throughout the country, radioactivity in the environment is due to three causes:

1.

Naturally occurring radioactive materials and radiation (cosmic rays).

2.

Fallout from testing of nuclear weapons and other nuclear devices.

3.

Releases of gaseous and liquid waste effluents from nuclear Zacilities.

The purpose of an environmental radioactivity monitoring program at a nuclear power plant is to measure and identify that portion of the existing environmental radiation and radioactivity levels that result from plant operations and to evaluate the public health or ecological

' significance, if any, of this activity.

An environmental radioactivity monitoring program is usually divided into pre-operational and operational phases on the assumption that pre-operational levels may provide a base line to which operational levels can be compared.

Such comparisons are complicated by additional nuclear testing, by seasonal and annual variations in natural radioactivity and fallout levels, and discharges of radioactive material from other installations; however pre-operational monitoring does document the existing environmental radioactivity levels and their variability during the period of sampling.

This is a report of the pre-operational phase of the Environmental Radio-activity Monitoring Program for the Oconee Nuclear Station.

A laboratory for the analysis and counting of environmental samples was established at the Duke Power Company, Riverbend Steam Station, in late 1968. The sampling program began in January, 1969, when the Oconee Nuclear Station was in the early stages of construction and Lake Keowee was being formed. However, a few sampling stations were not completed until April,1969, af ter which time the full sampling program begen.

It was expected at the time the program was started that about two years of pre-operational monitoring data would be obtained prior to the operation of Unit 1.

This report is essentially for 24 months of sampling from January, 1969, through January, 1971.

1

W A.

DESCRIPTION OF THE OCONEE NUCLEAR STATION The Oconee Nuclear Station is located in Oconee County, South Carolina, approximately 8 milet Northeast of Seneca, South Carolina, on the shore of Lake Keowee. This lake was formed by damming the Keowee and Little Rivers in that location.

Immediately to the south is the U. S. Govern-ment Hartwell Project.

The Keowee Hydro-electric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell. To the north the Jocassee Hydro-electric Plant joins Lake Jocassee and Lake 1 owee.

Jocassee is a pumped storage plant.

The two hydro-electric plants on these lakes, and the Oconee Nuclear Station are a part of the Duke Power Company Keowee-Toxaway Project.

Maps on the following pages show the location of the Keowee-Toxaway Project and the Oconee Nuclear Station.

The Oconee Nuclear Station consists of three pressurized water reactor units with a total generating capacity of 2,658 megawatts. The first unit will be placed in service in 1971, with Units 2 & 3 scheduled for operation in 1972 and 1973.

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TIIE PRE-OPERATIONAL PROGRAM Table 2.1 on the following page describes the pre-operational environmental radioactivity monitoring program for the Oconee Nuclear Station.

It lists the type samples, sampling locations, and the collection frequency.

In general, the samples are counted for gross alpha and gross beta radioactivity using an automatic low background, gas flow proportional counter. Gamma spectral analyses are also performed to identify the radionuclides involved.

A 400 channel gamma scintillation spectrometer (multichannel analyzer) is used for this purpose.

Specific analyses such as for tritium in water, cesium 137 and strontium 90 in milk, water, fish, and animal samples are per-

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formed by outside laboratories. The measurement of gamma dose and dose rate are considered to be appropriate samples to determine the radiation background.

of an area (as well as to measure the effects of gaseous activity released during the operational period.) Thermoluminescent dosimeters and beta gaman survey instruments (geiger counters) are used for these measurements.

Criteria for the selection of the various sampling locations were as follows:

1.

Water For comparison purposes water samples are collected:

(a) Upstream (b) Near proposed liquid effluent release point (c)

Downstream of Site and Exclusion Area Particular emphasis has also been given to water sampling to evaluate the effect of the filling of Lake Keowee.

2.

Airborne Particulates, Comparison of on-site vs off-site locations Rain and Settled Dust near towns and populated areas; consideration given to prevailing wind direction.

3.

Radiation Dose and Comparison of on-site vs of f-site locations Dose Rate near towns and populated area; consideration given to prevailing wind direction.

4.

Bottom Sediment For comparison purposes, silt samples (River and lake bottom are collected:

sediment; filtered solids from municipal (a) Upstream drinking water supplies)

(b) Near proposed liquid effluent release point l

(c) Downstream of Site and Exclusion Area 5.

Terrestrial Vegetation Comparison of on-site vs off-site locations; consideration given to prevailing wind direction j

6.

Aquatic Vegetation, For comparison purposes, samples are collected:

i Algae and Plankton, i

Bottom organisms and (a) Upstream, from Lake Keowee crustaceans (b) Downstream,. from Hartwell Reservoir close to liquid effluent release point 6

7.

Milk From local area dairies within 10 miles of site. and nearby farms in prevailing wind directions.

8.

Fish and Animals Samples are collected in accordance with the (carp, shad, bass, recommendations of, and in cooperation with, rabbit, squirrel, the S. C. Wildlife Resources Commission from:

and other mammals)

(a) Lake Keowee (b) Exclusion Area (c) Hartwell Reservoir 9.

Miscellaneous Investigation of special situations made to provide program flexibility and extended coverage; such as may be required due to nuclear weapons testing or unusual fallout conditions.

Includes study of Lake Keowee tributary streams and modification as lake fills,and investigation of reported deposits of uranium or thorium in area of plant.

ADDITIONAL PRE =0PERATIONAL INFORMATION Water samples from the Keowee and Little Rivers which flowed by the site prior to the formation of Lake Keowee and well water from private residences in the area were collected, analyzed and counted from late 1966 through 1968. This early work was done at the Carolinas-Virginia Nuclear Power Associates Inc., CVTR Facility in Parr, South Carolina in which Duke Power Company personnel participated. Results of these early pre-operational studies are tabulated in Appendix 2.

THE OPERATIONAL PROGRAM The Environmental Radioactivity Ibnitoring Program will continue during the operating pe riod. Appendix 3 (Table 2.lA) describes the minimum operational program for the Oconee Nuclear Station with one, two or three units in operation. Cooperation with the various agencies involved will continue.

DISCUSSION The environmental radioactivity monitoring program for the Oconee Nuclear Station is conducted by the station Health Physics upervisor with some assistance from the c

station Chemist.

The program was planned and is directed and reviewed by the Duke Power Company System Health Physicist.

It is expected that the results of the Pre-operational and the Operational Environ-men' Radioactivity Monitoring Program for the Oconee Nuclear Station will demon-strate the effectiveness of control over radioactive waste disposal operations at the station and of compliance with Federal and State regulations for the disposal of these materials.

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9

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DETAILS OF SPECIALIZED SAMPLE COLLECTION AND COUNTING METHOD 5 1.

SAMPLING 1.

Airborne Particulates Samples are collected on Hollingsworth and Vose filter paper (HV-70) by use of a Gelman Tempest air sampler mounted in an enclosure and held at 4' above ground level. Monthly composite samples are collected with the samplers cycling so as to operate one hour "on" and three hours "off" at a nominal flowrate of 8 cfm.

An elapsed running time indicator and vacuum gauge are used to determine actual volume sampled.

(See photograph p. 12 )

2.

Rain and Settled Dust Monthly composite samples are collected in open polyethylene pails held at 4' above ground level.

(See photograph p._13_)

3.

Radiation Dose and Dose Rate Quarterly integrated gamma dose measurements are made by use of thermo-luminescent dosimeters sealed within polyethylene packets.

Packets are held in covered wooden boxes at 3' above ground level. (See photograph

p. 14 ) Measurements of dose rate are made with a calibrated Survey Meter using a geiger-muller probe.

4.

Fish, Animals, Milk and Water Specimens and samples are submitted to outside laboratories for required specialized analyses. Fish samples are homogenized and analyzed for strontium 90 and cesium 137 Bone and tissue from animals are analyzed for strontium 90 and cesium 137 respectively. Milk is analyzed for str'n-o tium 90 and cesium 137 Water is analyzed for tritium by electrolytic enrichment and/or gas counting.

Strontium 90 and cesium 137 were chosen because they are the principal long lived components of the fallout at the present time and tritium because it is added to the environment from weapons testing and from the nuclear industry.

2.

COUNTING AND ANALYSIS Prepared environmental samples (deposits on planchets) are counted for gross alpha and gross beta radioactivity on a Low Background Counter, an automatic gas flow proportional counter.(See photograph p.15 ).

The alpha and beta plateaus and efficiencies of this counter were determined with a standard electro-deposited radium D+E Source, and a cesium 137 " gross beta" source, deposited f rom a standard solution, where the" gross beta activity" is taken to be 1.275 times the gamma emission rate, to account for conversion electrons produced by barium 137m decay.

(Results of environmental sample 137 beta activity".)

counting are therefore expressed in terms of " apparent cesium 10 1

The solution standard had an overall accuracy in its determination of + 3%.

The deposited sources were counted at the 90% confidence level to an accu-racy of + 1% in determining the relative counting efficiency of the counter.

+

Efficiencies were calculated to zero absorber and self-absorption corrections were made for each sample counted using data taken from published tables and graphs.

(References, " Standard hethods for the Examination of Water and Wastewater", APHA, for uranium alpha; " Radiological Health Handbook", for mixed fission product beta).

All environmental samples were counted at the 90% confidence level: however due to time factors and considerations of automatic counter operation, each sample was counted for 20 minutes regardless of activity level.

Therefore, the counting error of each determination varies depending on counting rate and ranges from approximately 40% at the minimum detectable activity levels (for beta) to about 2% at the highest levels counted. The nominal background of this counter is 0.05 count per minute alpha and 1.0 count per minute beta.

The minimum detectable activity was calculated at the 90% confidence level for twenty minutes counting time at these backgrounds.

Samples counting less than the minimum detectable activity are listed as non-detectable (N.D.) in the data tables and were considered as having a value of 0 in determining averages.

The gamma analysis instrumentation consists of a Multichannel Analyzer (400 channels) and a 3 X 3 inch sodium iodide detector and photomultiplier within a 6000 pound lead shield lined with cadmium and copper.

Readout devices include a X Y Recorder and a High Speed Printer. (See photograph p.16 )

Environmental samples are generally analyzed by placing or pouring them into a 3.5 liter polyethylene Marinelli beaker mounted on the detector. Because of the very low activity levels existing in environmental samples, they are usually counted for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and then the background is subtracted or the results are compared with a distilled water blank analyzed for the same period of time.

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II.

SUMMALY AND DISCUSSION OF RESULTS A.

SUMMARY

The results of the Pre-operational Environmental Radioactivity Monitoring Program for the Oconee Nuclear Station are summarized on the following pages.

Additional samples have been and will be analyzed prior to operation of Unit 1.

They are not reported here because of the cut-off date requirements for the preparation of this report.

However all of the data wil. remain on file for review by regu-latory authorities and other interested parties, and will be utilized for comparison purposes during station operation.

B.

DISCUSSION During the normal operation of the Oconee Nuclear Station, the only contribution of radioactive materials to the environment will be due to the release of radioactive wastes; that is, from radioactive gaseous and liquid wastes that are released in con-trolled, measured amounts in accordance with AEC Regulations (10CFR20), and the requirements of the Technical Specifications that govern the total operation of the station.

(There will also be a very minor contribution to the radiation levels in the immediate area beyond the inner plant fence due to direct radiation from operations conducted within the plant.) The radio-active wastes released from the station will be further diluted and dispursed in the environment and will exist only in trace quantities beyond the Exclusion Area in concentrations that are many orders of magnitude below the permissible concentrations for an Unrestricted Area.

This should result in population doses in areas beyond the station that are so low as to be meaningless.

The measurement of these extremely low levels of radioactivity requires very sensitive instruments, usually low background counters, and these have been provided.

In many cases, the contribution of radioactivity to the environment from the plant cannot even be measured against the natural background radioactivity and fallout from nuclear testing.

However, reconcentration of certain radio-nuclides can occur sud environmental monitoring will be performed during the operating period to insure that possible reconcentrations are of no significance in regard to dose to man and his environment and to demonstrate compliance with regulations.

17

Using information taken from " Radiological Health Data and Reports" published by the U. S. Department of Health, Education and Welfare, (now by EPA), it appears that testing of nuclear weapons and other devices by the United States, Russia and China, took place continu-ously almost on a month-by-month basis during the report period.

From November 1968 through December 1970, more than 89 nuclear detonations were reported..For the most part, these were underground nuclear tests performed principally by the U. S. and Russia, which included 5 nuclear cratering (Plowshare) experiments performed by the United States.

In addition, 3 air or surface bursts of nuclear weapons were performed by China.

These Chinese tests were intermediate yield devices of about 3 MT TNT equivalent and obviously contributed consi-derable activity to the environment.

In some cases, slight venting of activity to the environment was reported from underground testing. The nuclear cratering experiments also contributed to the environmental activity levels.

The Russian tests took place in the Soviet Northern, Central and Southern Ural Regions of their country (Novaya Zemlya, Volgograd, and Semipalatinsk regions).

The Chinese tests took place in their Lop Nor region. The U. S. at the Nevada Test Site, at Grand Valley, Colorado, and at Amchitka, Alaska.

1 e

e 18

C.

OCONEE PROGRAM RESULTS A Pre-operational Environmental Radioactivity Monitoring Program is generally an exercise in the detection and measurement of natural background radioactivity and fallout from weapons testing, and so it was with the Oconee Program.

The period covered by the pre-operational monitoring phase was generally one of relatively low fallout radioactivity levels that are the result of the nuclear weapons test ban and moratorium on above ground testing by the USA and the USSR which went into effect in late 1962.

The characteristic spring increases in fallout levels were observed during the p.e-operational period. This results primarily from the descent of stra-tospheric debris from past tests into the troposphere. However, the pre-operational period was also punctuated by significant temporary increases in levels due to current nuclear testing.

Gamma-emitting radionuclides found most often in fallout were cesium 134 and 137, cerium 141 and 144, ruthenium 103 and 106, and zirconium-niobium 95 Naturally occurring radioactivity included potasium 40 and uranium (radium) daughter products. A major component of atmos-pheric radioactivity, beryllium 7, is another naturally occurring radionuclide.

Activity values found as a result of*the Pre-operational Program are comparable to values reported by the U. S. Public Health Service, (now EPA) in their " Radiological Health Data and Reports" documents and in the semi-annual reports, "Effect of the Savannah River Plant on Environmental Radioactivity". What appears to be differences in results of gross beta radioactivity in air are due to procedures. The Public Health Service Surveillance Network counts more of the shorter lived activity.

Uranium and radium daughter products found in deep well water is characteristic of the Piedmont Region. The activity values listed in the tables do not reflect the rather significant amounts that exist.

When the water is evaporated for counting, most of the activity which is gaseous is removed.

It is interesting to note that although cesium 137 can be detected and measured in milk by very sensitive analysis, the only gamma activity found in the Pre-operational Program after five hours of counting on a multi-channel gamma spectrometer, is naturally occurring radioactive potassium 40.

This radionuclide exists in milk in concentrations of approximately 1,250 pCi/1.

Cesium 137, which is due to fallout, averaged about 23 pC1/1 in South Carolina milk during 1969 and about 19 pCi/l in 1970.

For comparison purposes, it should be noted that daily intakes up to 3600 pCi/l of Cesium 137 would be expected to result in average exposures to population groups not exceeding the permissible dose limit (Radiation ~

Protection Guide) established by the Federal Radiation Council.

19

.. - -. ~ ~...

... - ~. _ _...... _ -... _ _.

SLMfARY OF PRE-OPERATIONAL RADIOACTIVITY MONITORING RESULTS Averages (and Ranges) for Period January 1969 through January 1971 Suspended Solide Dissolved Solids Total Activity Cause Analyste Results pCill PC1/1 pC1/1 alpha beta alpha beta alpha beta 1.

Water Rivers and Lakes.D Site 000.3 average 0.08 0.67 0.09 4.22 0.28 4.90 range ND to 0.64 ND to 1.69 ND to 0.49 2.21 to 7.35 ND to 2.78 ND to 8.35 background;Cs

,137;g 0 4

Obd.4 average 0.05 0.57 0.07 3.46 0.12 4.03 range ND to 0.36 ND to 2.01 ND to 0.79 0.78 to 5.93 ND to 0.87 1.55 to 7.26 background;K40;Ra der prod 000.7 average 0.10 0.78 0.09 4.04 0.20 4.95 range ND to 0.35 ND to 2.39 ND to 0.53 1.73 to 7.21 ND to 0.53 1.76 to 8.55 background; K40 Newry 005.1 82 average 0.32 1.68 0.09 5.11 0.50 7.16 C'

range ND to 0.80 0.07 to 4.21 ND to 0.34 1.83 to 9.30 ND to 1.14 2.81 to 10.83 background 005.3 average 0.08 0.61 0.09 3.66 0.17 4.27 range ND to 0.57 ND to 2.17 ND to 0.37 0.95 to 6.55 ND to 0.78 1.65 to 8.42 background Clemsoa 006.2 average 0.10 0.61 0.06 3.26 0.17 3.97 range ND to 0.50 ND to 1.87 ND to 0.35 1.77 to 5.15 ND to 0.68 2.1* to 6.18 background Special Annual Samples:

9 Lake Keowee 000.3 (1969) 558+30 (1970) 590+39 1.7.+ 0.1 (1970)

Lake Hartwell 006.2 (1969) 486130. (1970) 594139 2.2 1 0.1 (1970) 4 e

Suspended Solids

-Dissolved Solids pCi/1 Total Activity c==== Analysta Results pC1/1 pCi/1 alpha beta alpha beta alpha beta 1.

Water (Cont'd)

Municipal Water Supplies. B. C.

seneca 004.1 Raw Wa t e r average 0.04 0.56 0.08 5.56 range ND to 0.34 ND to 2.47 ND to 0.49 3.32 to 9.79 Finished Water background Cal 3' average range 0.07 5.90 pp to 0.34

• 4.04 to 11.71

>J Clemmon 006.1 Raw Water average 0.11 0.41 0.15 3.80 range ND to 0.49 ND to 1.33 ND to 0.88 1.17 to 7.70 background Finished Water average range 0.08 2.84 ND to 0.56 0.61 to 3.13 background Anderson 012 Raw Water average 0.06 0.24 0.G1

3...S range ND to 0.38 ND to 2.03 ND to 0.10 l'.84 to 6.12 Finished Water average range 0.03 3.03 ND to 0.S*

5 SC to 4.49 background e

me e

Total Activity Gamma Analysis pC1/1 Results Comments alpha beta 1.

Water (Cont'd)

Wells Former Residences, A (and Construction Drinking Water Supply)

Site 000.8 Radium Daugh,st Total Activity

1. 1 Products figures are for

1. 2 gross non-volatile activity only and average 0.13 2.41 therefore are not range ND to 0.54 ND to 4.29 indicative of concentration of gaseous radium daughter products U

2.

Rain and Settled Dust, E Total Activity Canuna Analysis nC1/m2 Results Alpha Beta Site 000 Average 0.02 9.50 Cel44-Prl44, Zr 5-Nb95-9 Range ND to 0.09 0.28 to 24.17 Be7, Cs134 Walhalla 002 Average 0.03 1.'. 29 Bel 40_ gl40, Zr95-Nb95 Range ND to 0.15

r. 09 to 26.20 Cel44-Prl44, Be7, Csl34 Clemson 006 Average 0.04 10.22 Bal40_gl40, Cel44-Prl44 O

Range ND to 0.27 0.32 to 30.20 tr95-Nb95, Be7, Cs134 Pickens 010 Average 0.03 10.67 Bal40_gl40, Ce144-PrI44 Range ND to 0.06 0.67 to 32.24 Zr95-Nb95, Be7, Csl34 O

.m N

i L

3.

Airborne Particulates,F Total Activity Gamma Analysis pCi/m3 Results Alpha Beta Site 000 Average 0.002 0.40 Ba140-La140, ge, Cal 3' 7

Range 0.0006 to 0.004 0.11 to 0.97 Zr95-Nb 5, Rul03 9

Clemson 006 Average 0.001 0.44 Ba140-La140, Zr95-Nb95 Be, Cs134, Rul03, g40 7

Range 0.0004 to 0.003 0.13 to 1.46

i 4.

Terrestrial Vegetation, G.

Total Activity Gamma Analysis pC1/g Results Site 000 Alpha Beta K40 l44-Prl44 Average 0.53 658.3 Zr9b Ce95, Be7, Cs134 Range ND to 2.38 461 to 822 Nb 1

.Newry 005 Average 0.19 770.8 K40, Cel44-Prl44 Zr95-Nb 5, Be7, Csl34 9

Range ND to 1.52 545 to 1007 Clemson 006 Average 1.12 687.6 K40, Cel44-Prl44 1

.y Range ND to 3.06 478 to 886 Zr95-Nb95, Be7, Cs 34

_ = _. _ _ -

5.

Aquatic Vegetation Total Activity Gamma Analysis Plankton, Bottom Organisms,11.

pCi/g Results alpia beta Site 000.3 Aquatic Vegetation 1

40; Cs 34,137 average 0.41 6.34 K

range ND to 2.01 0.70 to 18.81 U-Ra daughter products Plankton 40 average 1.04 100 K

range ND to 2.08 9.5 to 191 006,2 Aquatic Vegetation w

es 1.33 7.66 K40, Cs134,137 average

range, 0.05 to 9.28 0.78 to 38.33 U-Ra drughter products Plankton 40 one (1) sample 0.55 31.67 K

013

' Mussels K40

4

-Ana

- -"+ -

-h-'

1 7

6.

Bottom Sediment, I Total Activity Camma Analysis pCi/g alpha beta Results Site 000.3 average 0.30 1.47 K40, U-Ra daughter products,Cs134,13 range 0.07 to 0.43 0.41 to 2.81 000.7 average 0.39 1.96 K40, U-Ra daughter products,Cs134,13 range 0.20 to 1.00 0.73 to 3.65 Seneca 004.1 average 0.35 1.78 K40, U-Ra daughter products,Cs 34,13 1

range 0.07 to 0.65 0.32 to 2.97 y

Newry 005.1 average 0.24 1.35 K40, U-Ra daughter products range 0.15 te 0.33 0.56 to 2.57 005.3 average 0.94 4.60 K40, U-Ra daughter products,Cs 34,13 1

rango 0.18 to 2.07 1.04 to 10.19 Clemson 006.2 average 0.94 4.00 K40, U-Ra daughter products, Cs134,1 range 0.12 to 4.17 0.90 to 18.5 Anderson 012 average 0.31 1.69 K40, U-Ra daughter products, Cs 34,1 1

range 0.13 to 0.68 0.49 to 3.58

7.

Radiation Dose and Dose Rate, J Calculated Average Measured Dose Rate Location Average Dose /3 Montlu.mR Dose Rate, mR/hr C-M Instrument, mR/hr Site-000 26.7 0.012 0.014 Salem 001 34.7 0.016 0.016 Walhalla 002-40.8 0.018 0.014 Keowee H.S. 003 27.2 0.013 0.013 Seneca

'004 27.6 0.013 0.014 Newry 005 30.2 0.014 0.015 Clemson 006 23.6 (data missing) 0.011 0.014 Central 007 32.9 0.015 0.013 Liberty 008 32.4 0.015 0.014 Six Mile 009 37.8 0.017 0.015 Pickens 010 35.8 0.017 0.016 Jocassee

'011 34.8 0.016 0.014 i

Overall Averages 32.0 0.015 0.014 e

e i

3

8.

Animals. K pCi/g (wet wt)

Camma Analysis 90 Sr, bone Cs137, muscle Result 9 Site 000.5 Rabbit

'3/19/69 4.19 1 0.09 0.15 1 0.01 6/10/70 4.0 1 0.2 1.3 1 0.1 Natural K40 Squirrel S

7/22/69 7.00 1 0.36 7.22 1 0.07 10/22/69 20to i 1.8 62.6 1 4.5 l

Racoon 11/13/69 4.70 1 0.26 0.50 1 0.03 11/11/70:

5.37 1 0.12 0.62 1 0.04 Opossum 6/26/69 12.5 1 0.4 0.22 1 0.01 NOTE: All annual results are shown on this page, not averages

Results, pCi/g (wet wt)

Camma Analysis Rerultn 9.

Fish, L.

SE90 1

Cs 37 Date of Collection h

Description Lake Hartwell 013_

2-25-69 1

Carp (adult) 1.52 1 0.13 0.08 1 0.02 3

Shad (fingerlings) 0.35 1 0.11 0.39 1 0.02 2

Bass (fingerlings) 1.19 1 0.07 0.36 1 0.04 5-26-69 1

Large Mouth Bass (sub-adult) 1.16 1 0.01 0.025 1 0.004 1

Carp (sub-adult) 0.74 1 0.01 0.142 1 0.005 3

Shad (fingerlings) 0.209 1 0.002 0.022 1 0.003 11-26-69 1

Carp (adult) 3.16 1 0.06 0.033 1 0.003 1

Large Mouth Bass (adult) 0.64 1 0.02 0.074 1 0.003 2

Shad (adult) 0.57 1 0.02 0.033 1 0.002 5-25-70 3

Carp (sub-adult) 2.5 1 0.1 0.21 1 0.02 4

Shad (adult) 0.30 1 0.03 0.33 1 0.03 7-28-70 1

Large Mouth Bass (adult) 0.85 1 0.05 0.22 1 0.01 8-27-70 1

Shad (adult) 0.77 i 0.15 0.06 1 0.01 K40, 28.1 1 4.3 pC1/g' (wet wt.

40, 21.8 1 3.9 pCi/g 1

Carp (sub-adult) 0.74 1 0.15 0.05 1 0.01 K

(vet wt.,

9-24-70 2

Large Mouth Bass (sub-adult) 0.41 1 0.03 0.38 1 0.04 K40, 5.04 1 0.91 pCi/g (wet wt.

11-15-70 3

Shad (adult) 0.28 1 0.01 0.08 1 0.01 3

Large Mouth Bass (Semi-adult) 0.68 1 0.02 0.09 1 0.02 2

Carp (adult) 0.77 1 0.03 0.07 1 0.01 2-19-71 1

Carp (adult) 0.74 1 0.13 0.17 i 0.04 1

Shad (Semi-adult) 0.18 + 0.08 0.07 + 0.01 1

Bass (adult) 0.8210.16 0.18 1 0.03 Lake Keowee 8-26-69 1

Large Mouth Bass (sub-adult) 2.40 + 0.05 N.D.

2 Carp (sub-adult) 2.62 1 0.06 0.169 i 0.003 Natural K40 3-24-70 2

Carp (sub-adult) 1.6 1 0.1 0.33 1 0.03 4

Bream (adult) 3.2 1 0.1 2.7 1 0.1 3

Large Mouth Bass (sub-adult) 1.6 1 0.1 0.41 1 0.03 NOTE: All fish results are shown on this page, not averages.

.m____.

f pCf/1 Gawia.\\nalysis 3,90 Csl37 Results 10.

tiilk, M l

Location 002.1 (Dairy Farm)

-i average value 13.7 1 1.5 12.3 1 1.2 Natural K40 only l

range 7.7 1 0.5 to 23.4 1 1.4 4.7 1 0.1 to 20.5 1 2.0 Location 002.2 (Individual cow) l U

average value 23.4 1 2.2 15.7 1 1.4 Natural K40 only d

range 11.0 1 1.2 to 55.8 i 6.2 14.0 1 1.1 to 19.8 1 2.0

(

Control Location (Processing Plant) 12.6 1 0.6 14.6 i 1.0 j

one (1) sample T

4 4

i

APPENDIX NO. 1 SAMPLE ANALYSIS PROCEDURES i

Procedure No. 1 GROSS ALPHA AND GROSS BETA ACTIVITY IN TOTAL RESIDUE (Water)

The radioactivity in water may consist of many different radio-nuclides either naturally occurring or man-made.

The gross measure-ment provides a means of screening the samples to indicate the general concentration of non-volatile emitters and to determine whether addi-tional tests of radionuclides are necessary. This procedure is appli-cable to the determination of gross alpha and beta activities in the total residue on evaporation of clear water, generally from a potable water supply.

(Drinking water.)

Principle of Method A sample of water is evaporated and the residue is transferred to a planchet for counting gross alpha and gross beta or beta-gamma activities.

Apparatus and Equipment 1500 ml Beakers Stainless Steel Planchets Rubber Policeman Hot Plate Drying Lamp (Infra Red)

Low Background Proportional Counter and Associated Components.

Reagente Lucite:

0.5 mg/ml in acetone Nitric Acid: HNO3 (3N)

Procedure i

1.

Measure into a beaker a volume of sample (approx.1000 ml) con-taining, for alpha, not more than 100 mg of residue and, for beta, not more than 200 mg of residue per 20 cm2 of planchet, and eva-porate to m ar dryness.

2.

With distilled water, transfer the concentrate to a tared stainless steel planchet.

3.

Using a rubber policeman, wash beaker walls with a few drops of nitric acid (3N) 4.

Combine washings with water rinsings in the planchet, and carefully evaporate to dryness.

)

)

32

O.-

5.

If the residue flakes, treat it with 5 - 10 drops of lucite solution and allow to evaporate. Dry in an oven at 100*C to constant weight.

6.

Store the sample in a desiccator until it is to be counted.

7.

Count the gross alpha and the gross beta activity in the Low Background Portional Counter.

Calculations:

AXBXD Cross Alpha activity (pCi/ liter) =

CXE where A = Net alpha count rate (cpm-bgd)

B = Efficiency factor for counting alpha in

" weightless" sample, B= 1 B(cpm)=dpm ef ficiency; C = Volume of sample (liters)

D = 0.455, conversion factor from dpm to pCi E = Self-absorption or transmission correction for alpha (from Table A) i '

AXBXD Gross Beta activity (pCi/ liter) =

A = Net beta count rate (cpm-bgd)

B = Efficiency factor for counting beta, in

" weightless" sample, B=

1 B (cpm)=dpm efficiency; C = Volume of sample (liters)

D = 0.45 conversion factor from dpm to pCi E = Self absorption or transmission correction for beta t

(from Table B)

Re ference :

Radioassay Procedures for Environmental Samples i

U. S. Department of Health, Education, and Welfare Public Health Service l

Publication No. 999-RH-27, January,1967 l

33 L

Procedure No. 2

~

GENERAL METHOD FOR GROSS ALPHA AND GROSS BETA ACTIVITY IN SURFACE WATER Surface water may contain radioactivit-J associated specifically with the suspended matter as well as that which is dissolved or col-loidal.

It is usually important to measure the total radioactivity and also to separate the dissolved and suspended solids.

The filtrate (essentially the dissolved solids) activity is that portion of the total radioactivity that is most likely to appear in finished water following conventional water purification.

The filter-able activity (essentially the suspended solids) may be an important measurement of environmental contamination.

Principle of Method for Dissolved Solids Water samples containing suspended matter are filtered through an appropriate filter, and the filtrate is analyz ed as a sample of clear or potable water, i.e., the filtrate is evaporated and the resi-dur is transferred to a planchet for counting gross alpha and gross beta activity in a low background proportional counter.

Principle of Method for Suspended Solids Depending on the filterability of the water, an appropriate fii-tration system is used.

For the purpose of approximately simulating conventional water filtration in purification plants, the sample is filtered through cellulose fiber or membrane filters. The filter containing the solids is transferred to a tared metal planchet and is dried and fixed. The gross alpha and gross beta activities are measured in a low background proportional cou.1ter.

Apparatus and Equipment 1500 ud Beaker Stainless Steel Planchet Rubber Policeman Hot Plate & Infra-Red Heat Lamp Fullipore Filter Paper (1.2 u pore) and Filtering Equipment Low Background Proportional Counter and Associated Components Reagents Nitric Acid HNO3 (3N)

Nitric Acid HNO3 (Concentrated)

Lucite 0.5 mg/ml in acetone I

(

34

-2_

Procedure 1.

Measure 1000 ml of thoroughly mixed sample into a 1500 ml beaker; add 5ml of concentrated HNO.

3 2.

Slowly pour the entire contents through millipore filter in funnel using suction filtration apparatus including vacuum pump.

3.

Wash sides of beaker and filter funnel with a few milliliters of distilled H 0.

Allow only a few minutes time for all moisture to 2

run through filter paper.

4.

Transfer the filter paper to a tared planchet and add a few drops of concentrated HNO3 to dissolve the filter.

5.

Evaporate to dryness under heat lamp.

6.

Store the sample in desiccator until it is to be counted.

7.

Place the filtrate on hot plate and evaporate to near dryness (approximately 5 ml).

With distilled H 0, transfer the concentrate to a tared planchet.

8.

2 9.

Using a rubber policeman, wash the beaker walls with a few drops of HNO3 (3N).

10.

Combine washings with water rinsings in the planchet, and evaporate to dryness.

11.

Complete drying in oven at 103* - 105*C, cool in desiccator, weigh and keep sample dry. If the residue flakes, treat it with 5 to 10 drops of lucite solution and dry in an oven at 100*C to constant weigh t.

(Approximately 10 minutes.)

12.

Store the sample in a desiccator until it is to be counted.

13.

After net weight has been obtained on planchets containing the dissolved solids and the suspended solids, count for gross alpha and gross beta activity in a low background proportional counter.

Calculations Calculate and Report Results as Follows:

Dissolved: pCi/l Alpha, Beta Suspended: pCi/l and pCi/g Alpha, Beta 1

35

_3_

Gross Alpha activity (pCi/ liter) =

AXBXD CXE where A = Net alpha count rate (cpm-bgd)

B = Efficiency factor for counting alpha in

" weightless" sample, B= 1 B(cpm)=dpm efficiency; C = Volume of sample (liters)

D = 0.45 conversion factor from dpm to pCi E = Self-absorption or transmission correction for alpha (from Table A)

Gross Beta activity (pCi/ liter) = AXBXD CXE A = Net beta count rate (cpt?-bgd)

B = Efficiency factor for counting beta, in

" weightless" sample, B=

1 B(cpm)=dpm efficiency; C = Volume of sample (liters) 4 D = 0.45 conversion factor from dpm to pCi E = Self absorption or transmission correction for beta (from Table B) t In addition determine radioactivity in suspended solids in pCi/g, where:

pCi in sample pCi/g net weight of sample in grams

Reference:

Radioassay Procedures for Environmental Samples U. S. Department of Health, Education, and Welfare Public Health Service Publication No. 999-RH-27, January,1967 36

t 1

Procedure #3 Gross Alpha and Gross Beta Radioactivity in Rain and Settled Dust This method is applicable to the analysis of Rain Water and/or Settled Dust that is collected in an open container over a 30 day period.

Principle of Method When thereis 500 ad or more of water present in the container the entire Volume is measured and filtered, 500 al of filtrate is evaporated, transferred to a tared planchet and counted to determine the activity in dissolved solids. When there is less than 500 ml of water present (or a dry pail) sample is then made up to 500 ml by 1

addition of demineralized water. The resulting sample is filtered, evaporated, and transferred to a tared planchet and counted to deter-adne the activity in the dissolved solids, i

The filter paper containing the residue in both cases above is dissolved in concentrated nitric acid in a tared planchet to determine the activity in the suspended solids.

Apparatus and Equipment 1000 ml Beaker Stainless Steel Planchet Rubber Policeman Drying Oven Hot Plate and Infra-Red Heat Lamp Mil!! pore Filter paper (1.2 u pore) and filtering equipment Low ;ackground Proportional Counter and Associated Components Reagents Nitric Acid HNO3 (0.1 N)

Nitric Acid HNO3 (Concentrated) 37

procedure Note: For dissolved solids only, always use 500 mi volume of sample collected and multiply results by factor to correct for fraction of total volume used. When pail is dry, or less than 500 m1, make up to 500 al with demineralized water.

1.

Measure volume of sample. Mix thoroughly. Filter entire volume of water in pail through 1.2 u pore millipore filter paper.

2.

Using rubber policeman and few ml of 0.1 N HNO wash sides and 3

bottom of pail thoroughly, combing this with H O from pail through 2

filter.

3.

Remove filter paper from filtering apparatus, place in tared planchet, covering it with approximately 5 al of concentrated HNO, place under heat lamp for drying. After it is dried, 3

place in drying oven for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> @ 100*C - remove and place in Dessicator until ready for counting.

(Suspended Solids) 4.

Place 500 ml of filtrate in 1000 m1 beaker, evaporate to near dryness (5 - 10 ml) on hot plate.

5.

Transfer to a tared planchet, using rubber policeman and 0.1 N HNO, Wash beaker several times to insure transfer of all acti-3 vity from beaker to planchet and dry under heat lamp. After it is dried, place in drying ovc7 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> @ 100*C - remove and place in Dessicator until ready for counting.

(Dissolved Solids) e I.

l l

38 l

i

1 I

2 Calculations: Express results in nCi/m 1

Dissolved:

epm-b gd, X E f f Fac. = dpm (correct for total vol.

S.A.F.

in pail or factor using 500 mi vol. sample)

S uspended:

cpm-bgd, X Eff Fac. = dpm S. A. F.

Sum:

dpm (Dissolved, corrected.for volume) dpm (Suspended)

Total dpm X 1.402 X 10-2 = nCi/m2 Note:

Area of pail 0.0324 m2 1.404 X 10-2 = 0.45 X 10-3 = Conversion factor from 0.0324 m4 dpm to nCi/m2 Appropriate Efficiency Factors and Self Absorption Factors should be used for alpha and for beta.

Example:

For Beta, (Collected Vol. 2000 ml) Sample 500 ml Vol. Factor 2060 =4 599 Dissolved:

100 counts in 20 min.

5 cpm - 1 cpm bgd X 3.34 Eff Fac. = 16.7 dpm X 4 = 66.8 dpm 0.8 S.A.F.

S uspended:

180 counts in 20 min.

9 cpm _1 cpm bgd X 3.34 Eff Fac. = 44.42 dpm 0.6 S.A.F.

Dissolved dpm 66.8 Suspended dpm 44.42 Total dpm 111.22 X 1.404 X 10-2 = 1.562 nCi/m2 39 l

L

Procedure No. 4 GROSS ALPHA AND GROSS BETA ACTIVITY COLLECTED ON AIR SAMPLE FILTER PAPER PARTICULATE MATTER Principle of Method A 4" diameter filter paper is removed from sampler and one-fourth or a 2" diameter portion is removed for counting of gross alpha and gross beta activity.

Apparatus and Equipment 2" Metal Cutter Stainless Steel Planchet Low Background Proportional Counter and Associated Equipment 9

Procedure 1.

Take the 2" cutter and cut out one-fourth portion of 4" filter paper containing particulate sample.

2.

Place 2" portion into clean planchet and count for gross alpha and for gross beta activity.

NOTE: Allow at least three days decay prior to counting sample af ter its removal from sampler.

Calculations 3

Report results in pCi/m,

Total counts total time of count = cpm t

cpm - Bgd y Efficiency Factor X size correction factor = dpm S. A. F.

NOTE: Size correction factor for portion of filter paper counted is 4.

dpm X 0.45 pCi / dpm pCi/m3

=

mJ of air sampled Appropriate Efficiency Factors and Self Absorption Factors (S. A.F.),

should be used for alpha and for beta. Where self absorption factors are based on net weight of sample collected i.e.

(weight of paper and sample - weight of paper) expressed in mg/cm2 m3 of air sampled = total hours sampler operated X 60 min /hr X average cu. f t./ min (this is obtained from curve supplied by manufacturer from average of vacuum gage readings at beginning and end of sample period) X 2.832 X 10-2 m3/cu.ft.

40

i Procedure No. 5 GROSS ALPHA AND CROSS BETA ACTIVITI IN BOTTOM SEDIMENT AND SILT This method is npplicable to bottom sediment and silt samples col-lected from rivers and lakes.

Principle of Method Sample is dried, weighed, and then leached with concentrated nitric acid, and transferred to a tared planchet for counting of gross alpha and gross beta activity.

Apparatus and Equipment Mortar and Pestle Drying Oven 50 ud Beakers Stainless Steel Planchets Rubber Policeman Graduate Cylinder 10 ml Filter Paper (1.2 u millipore) and Funnel Pipette 2 ud Hot Place & Drying Lam (Infra-Red)

Low Background Proportional Counter and Associated Equipment Reagents Nitric Acid HNO3 (Concentrated)

Nitric Acid HNO3 (0.1N,)

Procedure i

1.

Weigh out approximately 20 to 25 gms of wet sample and allow it to dry in oven for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period at.110*C.

2.

Crush dry sample to a powder and weigh out 10 gms dry weight of

.t sample (record exact weight.)

3.

Leach sample with 10 milliliters of concentrated HNO.

Repeat twice more.

3 i

4.

Combine all the leachings through a filter paper followed by 0.1N i

HNO3 as a wash.

1

=

5.

Evaporate the filtrate to a small volume (approximately 5 to 10 nd.)

6.

Build the concentrated filtrate to 10 m1 with 0.lN HNO 3 in a graduate

{

cylinder.

i t

t 1

41

i i

Procedure No. 5 Page 2.

I i

7.

Using pipette transfer 2 ml of filtrate to tared planchet and place under heat lamp and evaporate to dryness with0ut splattering.

l 8.

Flame planchet to a dull red, cool and weigh.

9.

Store the sample in a dessicator entil it is to be counted.

t

10. Count the gross alpha and gross beta activity in the low background i

j proportional counter.

1 1

Calculation

{

Express results in pCi/g dry weight 1.

Total counts total time of counts = cpm 1

2.

Cpm - bgd X Efficiency Factor X Correction Factor for Volume of S.A.F.

filtrate used = dpm.

where, Correcti.on Factor for Volume of filtrate used is _5.

3.

dpm X 0.45 pci/dpm = pCi/g dry weight in grams where dry weight is obtained from step 2 above.

NOTE: Appropriate Efficiency Factors and Self Absorption Factors (S. A.F.)

should be used for alpha and for beta.

e l

42

Procedure No. 6 GROSS ALPHA AND GROSS BETA ACTIVITY IN AQUATIC VEGETATION, ALGAE AND PLAhTION This method is applicable to most aquatic samples taken from lakes, rivers, etc.

Principle of Method Measured sample is dried and then leached with concentrated nitric acid, transferred to tared planchet for counting of gross alpha and gross beta activity.

Apparatus and Equipment Mortar and Pestle Drying Oven 150 ml Beakers Stainless Steel Planchet Rubber Policeman Graduate Cylinder (10 ml)

Filter Paper and Funnel Pipette (1 ml)

Hot Plate and Drying Lamp (Infra-Rd)

Low Background Proportional Counter and Associated Equipment Reagents Nitric Acid HNO3 (Concentrated)

Nitric Acid HNO3 (0.lN)

Pro cedure 1.

Weigh out 50 grams wet weight of sample material and place in a 150 m1 beaker.

2.

Dry sample in oven for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 110*C.

3.

Crush dry sample and weigh out up to 10 gms dry weight of sample and record weight.. (Use no more than 10 gms.)

4.

Leach sample with 10 milliliters of concentrated HNO. Repeat two more 3

times.

5.

Combine all the leaching through a filter followed by 0.lN HNO3 as a wash.

6.

Evaporate the filtrate to a small -volume (approximately 5 to 10 ml.)

7.

Build the concentrated filtrate to 10 m1 with 0.lN HNO3 in a graduate cylinder.

43

Procedure No. 6 Page 2.

8.

Using pipette, transfer 1 ml of this solution to a tared planchet place under heat lamp and evaporate to dryness without splattering.

9.

Store the sample in a dessicator until it is to be counted.

e 10.

Count the gross alpha and gross beta activity in low background proportional counter.

Calculations Express results in pCi/g dry weight.

J 1.

Total counts total time of counts = cpm 2.

cpm - b gd_ X Efficiency Factor X Correction Factor for Volume of S.A.F.

filtrate used= dpm where, Correction Factor for Volume of filtrate used is 10 3.

dpm X 0.45 pCi/dpm pCi/g

=

dry weight in grams where, dry weight is obtained from step 3 above.

NOTE:

Appropriate Efficiency Factors and Self ibsorption Factors (S. A.F. )

should be used for alpha and for beta, i

e 44

Procedure No. 7 GROSS ALPHA AND GROSS BETA ACTIVITY IN TERRESTRIAL VEGETATION This method is applicable to grass samples and nest terrestrial vegetation samples of small leaf type, for analysis of non-volatile radionuclides.

Principle of Method Measured sample of grass or other veget'ation is flamed, placed in muf-fle furnace until white ash is obtained, transferred to tared planchet for counting of gross alpha and gross beta activity.

Apparatus and Equipment Evaporating Dish Gas Burner Stainless 9 teel Planchet Muffle Furnace Low Background Proportional Counter and Associated Equipment Lucite 0.5 mg/ml in acetone Procedure 1.

Weigh out 10-15 grams of sample and place in evaporating dish.

2.

Us.ing gas burner, flame sample until black ash is obtained.

3.

Place evaporating dish containing sample into muffle furnace at 600*C for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, or until white ash is obtained.

4.

Af ter cool-down, transfer sample into tared planchet, weigh and record weight, add a few drops of lucite solution (if necessary),

dry thoroughly, and place indessicator until ready for counting.

Calculations Report results in pCi/g of white ash.

Total Counts total time of counts = cpm cpm - bgd X Efficiency Factor = dpm S. A. F.

dpm x 0.45 pCi/dpm pCi/g

=

weight in grams where, weight in grams is taken from step 4 above.

NOTE:

Appropriate Efficiency Factors and Self Absorption Factors (S.A.F.),

should be used for alpha and for beta.

45

~

1 Procedure #8 GAMMA SCAN OF ENVIRONMENTAL SAMPLES COLLECTED MULTICHANNEL ANALYZER This method is applicable to all samples collected for environ-e mental purposes, Qualitative Analyses only.

Principle of Method The sample is prepared for gamma scanning by placing it in a standard container and/or (geometry) in relation to the photomultiplier tube.

}

Apparatus and Equipment 1

Marinelli Beaker (3.5 1) r Appropriate Stand or Holder

(

Multichannel Analyzer (400 ch) and Associated Equipment Procedure 1.

For any liquid samples such as H 0, milk, etc., a volume of 2

exactly 3.5 liters will be poured into the Marinelli beaker, i

and placed next to detector for counting, using the proper

(

support stand.

{

2.

For sample such as Vegetation (Terrestrial) the Marinelli

(

beaker can also be used.

3.

For samples such as air sample, planchet containing a prepared sample-Vegetation (Aquatic), and Bottom Sediment (Aquatic):

These can be analyzed using a1 adjustable stand or holder.

4.

For samples such as animals or fish: These may require special preparation.

(Generally these can be counted, either whole or homogenized, in Marinelli beaker) 5.

All-samples to be counted for a ninimum of 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (300 min.)or otherwise as required by activity level.

6.

Report results - Apparent Radionuclides Energy Mev Half Life and Analyzer Data on forms used for this purpose.

46 j

Sheet No.

DUKE POWER COMPANY OCONEE ENVIRONMENTAL RADIATION MONITORING PROGRAM RESULTS Sample Identification and Collection Data Location Type Sample or Description r

Volume / Weight or Other e

Inclusive Dates or Collection Date Collected By Date Submitted for Analysis Where Sent Analyses Required Analyses and Counting Information and Results D ate (s) Received Prepared for Analysis Amount of Si aple Used

{

Counting Information:

• NOTE Unusual Conditions of Counting (if any) ir alpha beta-namma Date & Time Counted Background, cpm Counting Efficiency or Factor Counting Data:

[

Total Counts Time of Count Corrected cpm f

dpm

, i Counting Results:

(State Amounts & Units) 4 Additional Information Counting Performed By:

Gamma Ray Spectrum Analysis Results:

• NOTE Complete Information Required On Stamp For Analyzer Tape (s) and Plotter i

Chart (s) and Staple Them To This Form.

Apparent Radionuclides Activity a

e 1

Gamma Analysis Performed By:

l Counting & Gamma Analysis Results Approved By l

ONS - HP/C-1 47 I

APPENDIX FO. 2 TABLE 2-2 SJWARY OF EARLY PRE-OPERATIO*AL WONITORING RESJLTS 1.

Vater Susp, ended Solfde Dissolved Sollp Tetal Activit?

Tr i t tuai pct /1 pC1/1 pC1/1 FCt/l alpha beta alpha beta alpha b*ta

(, 2,7310- 3. ;9, g}

A, Rivers 1957 reewee River At (ite N.D. - 4.73 1.16 - 24.09 N.D. - 2.17 M.D. - 7.67 N.D. - 5.01 5.59 - 25.57 rnnee 2.07 8.21 0.75 3.20 2.78 11,.41 a g i<

<2.7x10-3 1967 L!t:1e River At **curv. S.C, N.D. - 3.19 N.D. - 6.80 N.D. - 5.36 4.59 - 16.73 0.34 - 6.74 6.11 - 20.!R ranic_, q,7,to-3 2.M__ _ _ _ _ m er,

- 2. v. 'lz.. -.

..e r sy-a e----e rm m _u. _. __ _. _1. 01,-: -mm_- 7. 52 1.85 10.17 1

n e.-

-==

s u s.ee--

er-se-s.v.-s u. _ _ _.

-_-__3rs._~__.

1755

'* w e P. t ve r et

.i: " !!

• M.D. - 3.42 N.D. - 9.36 0.95 - 21.70 8.00 - 38.70 1.45 - 23.78 11.19 - 43.57 ranee t.JI 4.52 5.75 17.75 7.04 2)(. D avbt <2.7x10-3 1?6? Little Plver t hvry. S.C.

N.D. - 2.17 N.D. - 12.0 7 0.28 - 3.2?

6.25 - 30.14 0.28 - 8.68 7.23 - 31.81 rany.e_,

<2.7m10-3 0.82 5.72 2.30 13.30 3.82 19.70 overay 3.

.'re7 m! Deep k'cIls at Residences Degtgnation Year 6-ia:eand in Surrounding Area On-Site 1966 3.30 - 5.92 11.r5 - 28.58 ra,ne (3 locations,from 4.16 17.74 avernee residences then existing)

Surrounding Area 1966 2.17 - 4.96 10.26 - 25.79 ranne (3 locations,from 3.72 16.20 avera:;r resideners still exts:In?)

On-Site 1 1967 N.D. - 11.94 2.69 - 2(.97 rance 4.57

15. 17 a" era;;"

<2.7x10-3 c_,

On-Site 1 1968 N.D._- 33.44

?. 05 - (.2. t.r.

rans e 9

7.82 25.C2 an t.* pc y

On-Site 2 1967 N.D. - 7.60 1.16 - 19.06 rance_

2.70

• 0.60

<2.7x10-3 aversge On-Site 2 I "6 *,

N.D. - 4.91 la.:7 - 34.7R renne 3.00 l

N.N

-veragej i

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