ML20198Q144
| ML20198Q144 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/31/1985 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| U-600563, NUDOCS 8606090070 | |
| Download: ML20198Q144 (166) | |
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I I RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT PREOPERATIONAL STAGE 1985 I FOR CLINTON POWER STATION ILLINOIS POWER COMPANY I
I PREPARED BY: 8. h. )Fa[1/
T. v. Walsh REVIEWED BY: ~
/k J. Fyoelich l usn APPROVED:
M D.W'? Hill
[-23 ~d r Date I
I RADIATION PROTECTION DEPARTMENT CLINTON POWER STATION ILLINOIS POWER COMPANY I
I gs!6MM"Pyhi I -
I TABLE OF CONTENTS Page TABLE OF CONTENTS i LIST OF TABLES iii LIST OF FIGURES vii
SUMMARY
l INTRODUCTION 3 DOSE TO THE PUBLIC 12 PROGRAM 13 General Description 13 Design 14 Airborne Particulate Sampling 17 Airborne Iodine Sampling 20 Direct Radiation 20 l Surface Water Sampling 23 Well Water Sampling 33 l
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Intake Water 34 ;
Effluent Water 37 Bottom and Shoreline Sediment Sampling 49 Periphyton Sampling 46 Iodine Ingestion Pathway Sampling 46 I Broadleaf Vegetable Sampling 48 Fish Sampling 48 Soil Sampling 50 ;
QUALITY ASSURANCE PROGRAM 53 I
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TABLE OF CONTENTS (continued)
I Psge REFERENCES 58 APPENDIX A: Environmental Radiological 60 I Monitoring Program Annual Summary l APPENDIX B: Radiological Environmental Monitoring Program Sampling Locations for 1985 76 APPENDIX C: 1985 Deviation in the Sampling 86 Schedule APPENDIX D: Land Use Census 89 APPENDIX E: Radiological Environmental Monitoring 92 Program Changes in 1985 APPENDIX F: 1985 Radiological Environmental 94 Monitoring Program Sample Collection and Analysis Methods APPENDIX G: Data Reporting Conventions 96 APPENDIX H: Data Tables and Figures 99 I
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LIST OF TABLES Table Title Page 1 Estimated Exposure to Man from 8 Environmental Radioactivity United States Locations 2 Estimated Exposure to Man from 10 Environmental Radioactivity in l 3 the Clinton Area.
Synopsis of the Preoperational 15 Radiological Environmental Monitoring
?rogram for Clinton Power Station 1985 4 1985 Summary of gross beta results for 19 I air sampling stations 5 1985 Summary of thermoluminescence 24 l 6 dosimeter data 1985 Summary of gross beta results for 30 surface water samples 7 1985 Summary of gross alpha results for 31 drinking water 8 1985 Summary of gross beta results for 32 drinking water 9 1985 Summary of gross alpha results for 35 well water samples 10 1985 Summary of gross beta results for 36 well water samples 11 1985 Summary of gross beta results for 38 intake water samples 12 1985 Summary of tritium results for 39 intake water samples I 13 1985 Summary of gross alpha and gross beta results for effluent water 41 14 Summary of October 1985 gross alpha and 44 I gross beta results for bottom sediment samples I l 1
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LIST OF TABLES (continued) l Page i I 15 Summary of October 1985 Gross Alpha and Gross Beta results for shoreline sediment samples 45 16 1985 Summary of gross beta results for 49 green leafy vegetables 17 1985 Summary of gross alpha and beta 52 results for soil samples I 18 Crosscheck comparison of results for milk, water, air filters, and food samples between analysis laboratory 55 and Environmental Protection I Agency (EPA) for 1985 I
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I LIST OF FIGURES Figure Title Page B-1 1985 Environmental Sample Locations 81 (within 2 miles of Clinton Power Station)
B-2 1985 Environmental Sample Locations 82 (within 6 miles of Clinton Power Station)
B-3 1985 Environmental Sample Locations 83 (within 50 miles of Clinton Power Station)
I B-4 1985 Environmental Sample Locations (for Fish, Periphyton, Lake Shoreline and Lake Bottom Sediments) 84 B-5 1985 Environmental Sample Location 85 CL-105 (Fish, Periphyton, Lake Shoreline and Lake Bottom Sediment Controls)
H-1 1985 Weekly Airborne Particulate 113 Gross Beta Activity, Location CL-1 H-2 1985 Weekly Airborne Particulate 114 Gross Beta Activity, Location CL-2 H-3 1985 Weekly Airborne Particulate 115 Gross 3 eta Activity, Location CL-3.
H-4 1985 Weekly Airborne Particulate 116 Gross Beta Activity, Location CL-4 H-5 1985 Weekly Airborne Particulate 117 Gross Beta Activity, Location CL-6.
H-6 1985 Weekly Airborne Particulate 118 Gross Beta Activity, Location CL-7.
H-7 1985 Weekly Airborne Particulate 119 Gross Beta Activity, Location CL-8.
I H-8 1985 Weekly Airborne Particulate Gross Beta Activity, Location CL-11.
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SUMMARY
I This report provides a description of the sampling conducted as part of the Clinton Power Station radiological environmental monitoring program. In 1985, the preoperational monitoring program was directed by the Radiation Protection Department. Teledyne Isotopes Midwest Laboratory performed most of the sample collections and all of the analyses. The monitoring program complies with United States Nuclear Regulatory Commission (USNRC)
I requirements for a nuclear power plant under construction, and conforms to the guidelines of USNRC Regulatory Guide 4.1 " Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants" and USNRC Radiological Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program", Revision 1 (November, 1979). The purpose of the preoperational program is to measure base levels of radioactivity in the environment surrounding the plant and evaluate the procedures, equipment and techniques of the program.
The report also discusses the results of the sample analyses data.
From January 1, 1985 through December 31, 1985, 623 samples were taken from the water, air, and land around the station and analyzed in the laboratory. A total of 249 gamma isotopic, 34 gross alpha, 494 gross beta, 30 tritium, 86 iodine-131, and 4 strontium-90 analyses were performed on the 623 samples. Thermoluminescent dosimeters (TLDs) were located at 82 stations around the plant.
Although nuclear fuel arrived on site in 1985, no operational fission processes occurred at the station. Consequently, no releases of radioactivity resulting from fission processes were made to the environment. All radioactivity measured during 1985 is naturally occurring or originated from sources other than Clinton Power Station such as atmospheric nuclear weapons tests.
All sample analyses show concentrations of radioactivity or levels of radiation within background environmental ranges for the region I as reported by other utilities and federal and state agencies, Naturally-occurring potassium-40 was detected in most terrestrial samples. Beryllium-7, produced naturally by cosmic radiation was j
j detected in air particulate, bottom sediment, aquatic organisms, ,
terrestrial vegetation, and soil samples. l l
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SUMMARY
(continued)
In addition to naturally-occurring radionuclides, three fission products were detected in small concentrations in some environmental samples. Cesium-137 was detected in lake shoreline and bottom sediments, aquatic organisms, and soil. Strontium-90 was detected in lake bottom sediment samples while tritium was found in a surface water sample. The cesium-137, strontium-90, and tritium found in the environment around the site resulted from the deposition of fallout produced by atmospheric nuclear weapons testing. Although no atmospheric nuclear weapons tests have occurred since late 1980, the long half-life of cesium-137 (30.0 years), strontium-90 (28.1 years), and tritium (12.4) years coupled with sensitive analytical instrumentation, allows the measurements of very small concentrations of these radionuclides.
The final section of the report is the appendix. The appendix includes the results of all sample analyses performed in 1985, maps and tables of sampling locations, deviations, changes and additions to the program, and data reporting conventions.
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INTRODUCTION I The Radiological Environmental Monitoring Program (REMP) at the Clinton Power Station is designed to monitor and evaluate E the radiological impact of the facility on the environment.
E This report is required to be useful to a specialized scientific community. however, this introduction, the explanations in later sections, and the avoidance of I unnecessary technical terms are all designed to make this report understandable and useful to those with no background in environmental monitoring.
Radioactive Materiel All materials are made up of atoms. The atoms of a small I number of materials contain an excess of energy. This excess energy is continuously released in all directions, or The radiated energy may be in I radiated from the material.
the form of fast moving particles from the atomic. center, or energy waves similar to, but more energetic than light waves.
This material is said to be radioactive and the energy released is called radiation. The radioactivity of a material produces the radiation, and it is the radiation that interacts with other materials.
After expulsion of this excess energy, the atoms may have new chemical or physical properties, and will become either a type of radioactive material, or become a stable material I with no more release of energy. In general, materials divided up by their atomic properties are called isotopes.
Those isotopes that are radioactive are radioisotopes. The I whole process of release of energy and subsequent transformation is called radioactive decay. The rate of this process is described by the time it takes for one-half of the I material to decay. Each radioisotope has its own half-life which may be as short as a fraction of a second, or as long as millions of years. Compared to a long-lived radioisotope with the same amount of material, a radioisotope with a short I half-life will give off more radiation per second but will lose its radioactivity sooner. A long-lived radioisotope will remain radioactive for a longer time, but will give off less radiation per second.
The unit used to measure the activity of a radioactive I material is the curie (Ci). A curie is the quantity of a radioactive nuclide which undergoes 37.0 billion disintegrations (transmutations) per second. Instrumentation l used in radiological analyses of environmental samples can I I detect activities as low as a trillionth of a curie.
Consequently, the unit, picoeurie (pC1) or a trillionth of a l
curie is generally used in reporting the radioactivity of an l environmental sample.
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I The unit used to assess the biological effects of I radioactivity on the human body is the rem. The rem is a measure of the energy absorbed by the body, adjusted for different types of radiation to measure equivalent biological I effects. Generally, a millirem (one thousandth of a rem) is the standard reporting convention.
Effects of Radiation on Humans Many forms of energy are constantly being absorbed by the human body. These include heat, visible light, radiowaves, I and ultraviolet radiation from the sun. Our discussion concerns ionizing radiation from radioisotopes or cosmic (extraterrestrial) sources. Ionizing radiation supplies enough energy to an atom to break a negatively charged I electron away from the rest of the atom which then becomes positively charged. This production of an ion pair in the material absorbing the radiation can break chemical bonds or I structure of living cells possibly resulting in biological damage.
I The effects on the body produced by ionizing environmental radiation depends on how the energy is supplied to the tissue with different radiation types depositing energy in different I ways. When dealing with environmental radioactivity, there
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are three principle types of radiation: alpha particles, beta articles, and gamma rays. An alpha particle consists of four p' heavy" atonic particles i two protons and two neutrons. Beta I particles are relatively " light" atomic electrons. Gamma rays are high energy electromagnetic waves similar to but more energetic than light waves. All three types of I radiation are capable of producing biological damage in varying degrees. To illustrate how particles with the same energy can cause different damage to the human person, consider:
A four ounce chunk of lead and a four ounce tennis ball are traveling at 30 I miles per hour. Both " particles" have the same amount of energy. When they strike a human body, the area over which I the energy is delivered to the tissue determines how much damage is done.
tennis ball will spread the energy over The I a wide area, and may bounce off without giving up all the energy. The lead will expend its energy quickly into the body and destroy the tissue it contacts.
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I Effects of Radiation on Humans (continued)
In a rough approximation, the diffuse damage of the tennis ball can be related to gamma and beta interactions with I tissue components. The alpha particle, like the lead chunk, deposits its energy in a short space causing more damage from the same amount of energy.
The areas of tissue immediately surrounding the alpha producing radioactive material will absorb the highest amount of energy and have the greatest chance of damage. Therefore, the energy given off by alpha particles in the body is given higher relative chance of causing biological damage.
Organs and tissues in the human body are affected differently I by radiation. The variety of res'3onse to radiation is based on the radiation, on the type of biological tissue and the function of the organ involved. The rapidly dividing cells I of the red blood marrow have a greater chance of damage from radiation than the relatively resistant muscle tissue.
I To provide a single measure of the effects of radiation on the body, the doses to each organ of the body are given a relative measure of effect to the effect on the whole body.
I This is called weighting the doses to the organs into an equivalent whole body dose. This relative chance of causing harmful effects is used in calculating the unit of radiation dose, the mrem.
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Radiation from the Earth's Crust Some of the materials found naturally in the earth's crust
- today were present when the earth was formed, including l radioactive uranium, and thorium. The uranium and thorium series undergo transformations resulting in long chains of successive radioisotope. The end products of the uranium and s I thorium series transformations are the stable isotopes of lead, 1
g Terrestrial (occurring on the earth) radioactive materials E are found everywhere in the environment. Their concentration at any one location and time is a result of many natural geologic processes, such as weather, erosion, and volcanic action. These natural forces have brought the radioisotopes from their place of origin in the earth s crust into the i soil, air, and water of man's environment. One of the kI necessary building blocks of man's body and the body's natural chemical processes is potassium. All natural potassium contains potassium -40, a long lived radioactive 1
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The choice of construction techniques can bring materials ~
- higher in natural radioisotopes, such as granite and ;C l
concrete, directly into the work and living habitat of man.
i Even construction projects requiring much excavation and grading, release natural radon into the environment that l would have otherwise decayed beneath the ground, and never
' s exposed man, Radon gas attaches to airborne particulates -
" allowing it to collect and concentrate in areas of man's environment, even inside his own home.
Radon gas has a half-life of 3.8 days. It decays through a complex chain of radioactive particles most of which have a -
g short half-lives of less than one hour. These daughter -
particles produce most of the dose to humans from radon
, inside buildings. Data from a small number of homes surveyed i allows estimates to be made in references 19 and 20 that the average dose to the lungs of people in the U.S. is about 3000 e millirem per year, and that millions of people get more than t
I ten times this dose. Lung doses can be compared to whole body doses used elsewhere in this report by comparing the relative risk of causing cancer. It takes about twelve times as much dose to the lun L
l wholebody,or3000milfstocausecancerasdosetothe irem to the lungs causes a risk comparable to 240 millirem to the whole body (Reference 19).
Comic Radiation
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Energetic radiation from outside the earth, including our I sun, constantly bombards the earth. This cosmic radiation not only ex3oses man directly, it also interacts with atoms of the earta's atmosphere to produce such radioisotopes as
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y3'-7 carbon-14, beryllium-7, sodium-22, and tritium. Sf '
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Fallout
__ Highly concentrated fissionable uranium or plutonium is forced together and the rapid fissioning gives off tremendous anounts of energy and heat. The fission fragments, the unused fissionable material, and the materials activated by neutrons in the explosion are rapidly released into the 3 atmosphere.
Fallout refers to this radioactive debris that settles to the I earth after a nuclear weapons explosion. There are approximately 200 radioisotopes produced in the fission process of the nuclear explosion. Fallout is spread throughout the world by the winds in the atmosphere. Rain or snow washes the material down to the earth's surface. The radioisotopes from fallout that result in most of radiation exposure to man are iodine-131, strontium-90, and cesium-137.
Iodine-131 has relatively short half-life of 8.1 daysi however, large amounts of iodine-131 are produced by nuclear detonation. The longer half-lives of strontium-90 (28.1 years) and cesium-137 (30.0 years) cause their isotopes to remain in the environment for longer geriods of time. They have chemical properties which make them likely to cause human exposure. Small amounts of plutonium or uranium lef t over from the explosion also are spread in the fallout.
Average yearly doses to people in the U.S. from fallout are about 4 millirem (Reference 4).
Typical Environmental Radiation Doses The dose a person receives depends on how much natural radioactive material is around him, how much cosmic radiation I is reaching him through the atmosphere, how much radioactive material is in the air he breathes, the amount of medical x-rays he receives, how much radiation is present in his body, and how much radioactive material is in his water and food. Radiation from natural sources in the environment is the major source of exposure to man. In the United States, the variations in altitude and radioisotope content of the I soil, produce a range of natural exposure from approximately 80 to 200 mrem / year (Reference 17) excluding the contribution from indoor radon. Table 1 gives several examples. Most regions of the world have yearly exposures around 100 mrem from natural background excluding indoor radon exposure (Reference 5). Several small areas of the world with concentrated amounts of natural radioisotopes in the soil, experience yearly dose rates 10 to 100 times this. The yearly dose in the region of the Clinton Power Station is about 89 mrem from this portion or the natural radiation background (Reference 18).
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I TABLE 1 Estimated Exposure to Man from Environmental Radioactivity United States Locations (mrem / year)
Location Earth's Crust Cosmic Total I Tampa, Florida Salt Lake City, Utah Reno, Nev.
23 46 67 41 65 46 64 111 113 Denver, Colo. 90 75 165 From Natural Sources Inside the Body (excluding radon daughter products)
Potassium-40 19 Rubidium-87 0.3 Carbon-14 0.7 20 References 4 and 17 l
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Typical Environmental Radiation Doses (continued)
Recently the estimate _of yearly radiation dose from natural
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sources of radiation in areas of " normal" background in the world has been raised by the National Council on Radiation Protection (NCRP) (Reference 19). The higher estimate is caused mainly by the addition of the dose resulting from exposure of the lung from the decay products of radon, principally in indoor air, to that dose from the more uniform exposure of the whole body by the other components of natural background radiation. Table 2 gives estimates of environmental exposures to man in the Clinton area. External doses are estimates for this area of Illinois. Other estimated doses are typical in the Un-ited States.
Medical X-rays are widely used for diagnoses in medical and dental practice. Radioisotopes produced in fission reactors or produced in high energy particle accelerators are also used in medical diagnosis and treatment. Common biomedical isotopes include iodine-123, technetium-99, and xenon-133.
These radioisotopes have short half-lives and their remnants are rapidly eliminated from the body into the environment.
The estimated whole body dose equivalent from medical diagnostic x-rays and radioisotopes is about 100 millirem each year as an average to each person in the United States (Reference 5). - Doses used fcr medical treatment as in cancer radiotherapy are usually millions of millirem for one person over a period of a few months, but these doses are to a small part of the body.
Other Sources of Radiation Television gives off radiation estimated as an average of about 1 millirem yearly in the United States (Reference 4).
l Air transport in high altitude commercial passenger jets increases the exposure to cosmic radiation such that air travel adds a dose of about 3 millirem to the individual traveler per transcontinental plane trip (Reference 4).
Man-made Radioactive Material in the Environment Man contributes to the radioactivity in the environment.
Radioisotopes have been produced by man, for medical, scientific, industrial and military uses. These l radiois'otopes released into the environment spread and migrate by natural transport mechanisms into the air, water and soil. In' addition, some of man's activities bring natural radioisotopes closer to man, or concentrate amounts of natural radioisotopes into man's habitat.
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1 TABLE 2 Estimated Exposure to Man from Environmental Radioactivity in the Clinton Area (mrem / year)
From External Natural Sources l
Earth's Crust 46 Cosmic 43 From Sources Inside the Body l I
Internal Emitters 20 (mostly Potassium-40)
Inhaled Radon Contribution 240 Total from natural background including radon 349 1
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1 Medical Diagnoses 100 1 Fallout 4 l Television 1 less than 1 I Nuclear Power Total 455 i
References 4, 5, 17 and 19 I I I
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I Nuclear Power Generation Nuclear power plants use the controlled fission process to produce heat to generate electricity. In addition to producing fission radioisotopes, the neutrons released in the nuclear reactor activate some of the support and piping materials around the fuel. These activation products include isotopes of iron, manganese, and cobalt. Tritium is another radioisotope generated in a nuclear reactor.
Nuclear plants are designed and operated to control the generated fission and activation products. The uranium fuel I is encapsulated in metal cladding. The fission process takes place in a sealed reactor vessel. The vessel and its major components are enclosed in a sealed containment structure.
I All three barriers are designed to contain nearly all these radioisotopes. Normal operations release small amounts of these radioisotopes to the environment. Radioisotopes are I monitored in the discharge air stream from plant ventilation and in the water streatus from the facility. These water and air streams are referred to as the plant effluents. These I effluent streams add minute quantities of radioisotopes to the natural and man-made sources of radiation making up man's environmental radiation background. In 1985, Clinton Power Station did not release any reactor produced effluents to the I environment.
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I DOSE TO PUBLIC
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Doses to members of the public could in principle be determined by having selected persons wear TLDs and by measuring the amounts of radioisotopes inside their bodies.
However, approximations can be made with accuracy sufficient for the needs of radiological environmental monitoring programs without such interference with the public.
TLDs are posted in the environment to approximate external dose. The data does not directly represent any person since no one can stand at one of these spots for an extended period. The data is used to show the range of external outdoor exposures the public receives.
For internal radiation dose the variation is much less than the external dose because most of the internal dose is derived from natural potassium 40 in the diet. Variations in amounts of this radioisotope in diet cause annual doses to vary a few millirem, and variations in fallout radioisotopes cause even smaller changes in annual doses. The whole body counting program in the station measures the internal radioactivity of persons who work at the Station and who live in the region. Most of these workers are expected to have no internal radioactivity contributed by the Station and therefore provide useful data on internal radioactivity of those who live in the region.
Approximations to doses in the region around the Clinton Power Station can be made using this data and the numerous measurements made throughout the United States as referenced 1 in various sections of this report. The data from the preoperational environmental survey has been evaluated and I
l shows nothing unusual in sources of radiation and radioactivity affecting the public. Following is a summary l of estimated 1985 doses to the public within ten miles of Clinton Power Station:
215 millirem to the whole body from such sources as (
natural background, fallout, medical and naturally occurring radioisotopes inside the body i 240 millirem to the whole body from radon daughter products if homes in the Clinton area are .
representative of the average of the United States 6000 person-rem whole body collective dose from background and medical (excluding inhaled indoor radon daughter products) to the 30000 people who live within ten miles of the Station Radiation and radioactivity from Clinton Power Station have caused no detectable changes in these doses to the public through,1985.
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PROGRAM General Description The Clinton Power Station Radiological Environmental Monitoring Program is designed to sample steps in the I environmental pathways of radioactivity to man.
locations of the monitoring programs are described in Appendix B and are shown on Figures B-1 through B-5.
Sampling Water is sampled from the Clinton Lake and wells lo'cated in the vicinity of the site. Sediment samples are taken from the shoreline and bottom of the lake. Terrestrial vegetation, milk, periphyton and fish samples are taken in the area to monitor food chain pathways. Air is continuously sampled around the site through the use of filters and I charcoal canisters. All of these samples are analyzed in a laboratory by highly sensitive radiation detectors.
Radioactive material present in the samples from the environment is detected, identified and documented.
The preoperational phase provides baseline data to characterize the natural radiation levels and radioactivity concentrations present in the environment prior to the operation of the Clinton Power Station. This data also provides an indication of the degree of natural variations to I be expected in the background radioactivity levels. During plant operations this information is used as the baseline to determine, whether, and to what magnitude, any station-related effects may have occurred over the monitoring periods.
The objectives of the preoperational program are:
- 1. To identify, measure, and evaluate radionuclides and I radiation levels existing in the environment, and their fluctuations, prior to the operation of Clinton Power Station.
- 2. To fulfill the obligation of United States Nuclear Regulatory Commission (USNRC) Regulatory Guide 4.1
" Programs for Monitoringand Radioactivity in the Environs I of Nuclear Power Plants the USNRC Radiological Assessment Branch Technical Position (1979) on radiological environmental monitoring.
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Design Environmental pathway analysis during the preoperational monitoring program requires that samples be taken from the water, air, and land environments. Sample locations were selected for the evaluation of potential radiation dose to individuals around Clinton Power Station. Sample types were based on established pathways for the transfer of radionuclides through the environment to the population.
Sampling locations were determined after consideration of meteorology, population centers and land use.
Sample types can be divided into the exposure pathways they monitor. Continuous sampling of particulates and radiciodine using filters and charcoal canisters attached to vacuum pumps monitors the airborne pathway. Thermoluminescent dosimeters monitors the direct gamma radiation to the population. Waterborne radioisotopes are monitored in surface water, well water, and drinking water. In addition, natural accumulators of waterborne radioisotopes are sampled.
Lake bottom sediments, shoreline sediments, and some aquatic organisms (periphyton) can concentrate and retain certain waterborne radioisotopes. Finally, foods which are eaten by humans are sampled. Foods such as leafy vegetables or fish may concentrate isotopes from the air and water pathways.
Milch animals may concentrate radiciodine by grazing on grass contaminated by radioiodine. The milk pathway can also be characterized by samples of grass which serve as forage, if milk is not available.
In addition to sample locations which would be most likely to indicate effects from the station, control samples are taken at locations which should be independent of station operations. Fluctuations in background radiation levels will be evaluated by comparison with fluctuations of control samples as well as with fluctuations measured prior to plant operation.
A brief summary of the Program is shown in Table 3.
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E E E M M M E E Table 3 SYNOPSIS OF Tile PREOPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR CLINTON POWER STATION 1985 Number of Number of PATHWAY Sampling Collection Samples Type of Analysis Sample Type Locations Frequency Scheduled / Collected Analysis Frequency l AIRBORNE Weekly Gross Beta Weekly Air Particulates 8 (Continuous) 416/405 Gamma Isotopic Quarterly Composite Air Iodine 8 Weekly 240/234 Iodine-131 Weekly (Continuous)
DIRECT RADIATION TLD 82 Quarterly 319/304 Gamma Exposure Quarterly i
g (Continuous) t.n WATERBORNE Surface Water 3 Monthly 36/36 Gamma Isotopic Monthly Tritium Quarterly Composite Gross Beta Monthly Well Water 2 Monthly 24/23 Gamma Isotopic Monthly Gross Beta Monthly Tritium Quarterly Composite Intake Water 1 Monthly 7/7 Gamma Isotopic Monthly Gross Beta Monthly Tritium Quarterly Com;, unite Effluent Water 1 Monthly 7/7 Gamma Isotopic Monthly Gross Alpha Monthly Iodine-131 Monthly Gross Beta Monthly Tritium Quarterly Composite Bottom Sediments 6 Semiannually 12/12 Gamma Isotopic Semiannually Semiannually 12/12 Gamma Isotopic Semiannually
'; Shoreline Sediments 7 Aquatic Vegetation 4 Semiannually 8/8 Gamma Isotopic Semiannually i
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Table 3 ,
SYNOPSIS OF Tile PREOPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR CLINTON POWER STATION 1985 Number of Number of PATHWAY Sampling Collection Samples Type of Analysis Sample Type Locations Frequency Scheduled / Collected Analysis Frequency AIRBORNE Weekly Gross Beta Weekly Air Particulates 8 (Continuous) 416/405 Gamma Isotopic Quarterly Composite Air Iodine 8 Weekly 240/234 Iodine-131 Weekly (Continuous)
DIRECT RADIATION TLD 82 Quarterly 319/304 Gamma Exposure Quarterly g (Continuous) t.n WATERBORNE Surface Water 3 Monthly 36/36 Gamma Isotopic Monthly Tritium Quarterly Composite Gross Beta Monthly Well Water 2 Monthly 24/23 Gamma Isotopic Monthly Gross Beta Monthly Tritium Quarterly Composite Intake Water 1 Monthly 7/7 Gamma Isotopic Monthly Gross Beta Monthly Tritium Quarterly Composite Effluent Water 1 Monthly 7/7 Gamma Isotopic Monthly Gross Alpha Monthly Iodine-131 Monthly Gross Beta Monthly Tritium Quarterly Composite
, Bottom Sediments 6 Semiannually 12/12 Gamma Isotopic Semiannually Shoreline Sediments 7 Semiannually 12/12 Gamma Isotopic Semiannually Aquatic Vegetation 4 Semiannually- 8/8 Gamma Isotopic Semiannually 1'
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I Table 3 (continued)
Number of Number of PATHWAY Sampling Collection Samples Type of Analysis Sample Type Locations Frequency Scheduled / Collected Analysis Frequency INGESTION Iodine Ingestion 4 Monthly 24/16 Gamma Isotopic Monthly (grass in lieu (with Iodine-131) of milk) Semimonthly 48/48 Gamma Isotopic Semimonthly (with Iodine-131)
[ Vegetables 3 Monthly 54/20 Gamma Isotopic Monthly (during (I-131 required (during growing growing with green, season) season) leafy vegetables)
Fish 2 Semiannually 16/16 Gamma Isotopic Semiannually H
Milk 1 Semimonthly 7/7 Gamma Isotopic Semimonthly ,,
(May-October) (with Iodine-131)
Monthly 2/2 Gamma Isotopic Monthly (November-April) (With Iodine-131)
Soil 8 Triennially 8/8 Gamma Isotopic Triennially Gross Alpha Triennially
, Gross Beta Triennially 4
. Deviations from the sampling schedule.are listed in Appendix C.
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Airborne Particulate Sampling In 1985, airborne particulate samples were collected weekly at eight monitoring stations around the site. (See Appendix B and Figures B-1, B-2, and B-3 for station descriptions and locations). Seven monitoring locations are designated as indicator stations while an eighth station serves as a control station. An indicator station is a sample location which is most likely to indicate effects from Clinton Power Station while a control station is a location which should be independent
, of Clinton Power Station operations.
The sampling of airborne particulates is performed as a method of evaluating the concentration and deposition of radionuclides in an area. Inhalation and ingestion are the pathways affected by particulates. At each station, a filter paper is used to collect particulates weekly. A new filter is inserted at the time of collection. The used filter is analyzed weekly for gross beta concentrations. Since the intent of particulate sampling is to measure airborne radioactivity released from the plant, the counting of the short half-life daughters produced by the decay of natural radon and thoron may mask plant contributions. The filter is not analyzed for at least 5 days after collection to allow for the short half-lived daughter products of natural radon ard thoron to decay, eliminating their contribution to the gross beta activity. Because the amount of radon and thoron escaping from the earth's soil varies over time in response to meteorological conditions, weekly changes in gross beta activity measured on the particulate filters would occur. Without allowing for the decay of the radon and thoron daughters, the weekly changes in gross beta activity measured on the filters could be attributed to either natural or plant effects. At the end of a l calendar quarter, all the filters collected weekly 1 throughout the quarterly time period are grouped together and analyzed by gamma spectroscopy to identify gamma-emitting radioisotopes.
The total beta radiation measured on the filter paper is divided by the volume of air drawn through the filter during the sampling period giving a result of activity per unit volume. Gross beta concentrations are reported as trillionths of curies or picocuries of radioactivity per cubic meter (m3 ) of air sampled. Gross beta analysis results represent the total beta energy found in the filter. However, the analysis does not identify specifically the isotopes which contributed to the total beta energy.
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Airborne Particulate Sampling (continued)
In 1985, 405 filters were collected and analyzed for gross beta activity. The data recorded shows gross beta activities ranged from 0.010 pCi/m 3 to 0.078 pCi/m 3.
Weekly results of the gross beta results are found in Appendix H, Tables H-1 through H-8. Graphs of the weekly results are also found in Appendix H, Figures H-1 through H-8.
Noticeable increases in gross beta activity occurred for the samples collected during the weeks of February 13 and December 11 for all the samples. Higher concentrations of particulates found in the atmosphere during those weeks caused higher gross beta activities in the filters.
The high concentrations of particulates in the atmosphere resulted from meteorological conditions known as inversions. An inversion occurs on clear, calm nights when the lower boundary layer of the atmosphere cools faster than the upper boundary layer. Consequently, the temperature of the lower boundary layer is cooler than the temperature of the upper boundary layer. This temperature scheme is known as an inversion since temperature usually decreases slightly with altitude in the atmosphere's boundary layer. Since inversion conditions stratify the boundary layer due to density differences caused by air temperature differences, mixing of air in the boundary layer is suppressed.
Consequently, particulates present in the atmosphere become trapped in the stratified layer closest to the earth's surface. Examination of the site's meteorological data reveals inversion conditions occurred on February 8, 9, 10 and 11 and December 8, 9, and 10.
Since particulates in the midwest region of the U.S.
result from the combustion of coal and wood, which contain naturally occurring Ra-226, higher gross beta activities are found when Ra-226 is present in the ,
atmosphere and collects on the filter as a particulate. l The decay of Ra-226 to its daughter products produce radionuclides which emit both alpha and beta radiation.
In 1985, 32 quarterly gamma analyses were performed on !
the composited filters. Data shows only naturally occurring beryllium-7 was present during the course of the year. Beryllium-7 results from cosmic energy emitted from both space and the sun, interacting with oxygen, carbon and nitrogen gases present in the earth's atmosphere. Concentrations of beryllium-7 vary as a function of latitude, altitude, time and meteorological conditions. In 1985, beryllium-7 concentrations reported for the air sampling stations ranged from less than .026 pCi/m3 to .102 pCi/m 3. Gamma results are listed in Appendix H, Table H-9. ,
1 i I i
18
Table 4 1985 Summary of gross beta results for air sampling stations Station Annual Highest Lowest Average Weekly Weekly Activity Activity Activity (pCi/m3) (pCi/m 3) (pCi/m 3)
CL-1 0.027 0.078 0.016 CL-2 0.025 0.074 0.014 CL-3 0.027 0.079 0.014 CL-4 0.026 0.078 0.015 CL-6 0.026 0.073 0.010 CL-7 0.027 0.075 0.014 CL-8 0.025 0.077 0.015 CL-11 0.025 0.072 0.015
't A
I i
19
~
Airborne Iodine Sampling l l
Sampling for airborne iodine is conducted at the eight i locations described in Airborne Particulate Sampling.
(See Appendix B and Figures B-2, B-3, and B-3 for station descriptions and locations). At each location, air is drawn continuously through a particulate filter and a charcoal filter cartridge. Elemental iodine present in l the air is adsorbed onto the charcoal cartridges. The :
cartridges are analyzed weekly for iodine-131 using gamma l spectroscopy.
Iodine-131 is occasionally detected in the environment i
resulting from nuclear power plant releases, medical and pharmaceutical uses, and nuclear weapons tests fallout.
The airborne pathway of iodine makes radioactive iodine available to be directly inhaled. The human metabolism
- concentrates most iodine to the thyroid gland, increasing the exposure to that particular organ. Weekly collection and analyses of the charcoal cartridges located at the air monitoring stations around the plant provides information on the local concentrations of-iodine-131 present in the atmosphere.
4 Although weekly analysis of the charcoal cartridges is i only required for six months prior to the operational monitoring program, iodine analysis began on June 12, 1985 to determine preoperational concentrations in the site vicinity. Two hundred and thirty-nine samples were l
analyzed in 1985 and all results reported iodine-131 concentrations to be less than the lower limit of detection of 0.07 pCi/m 3. Since the plant did not produce any iodine-131 nor were there any atmospheric 4 nuclear weapons tests in 1985, these results were to be expected.
Direct Radiation
! In 1985, thermoluminescent dosimeters (TLDs) were used at 82 locations around Clinton Power Station in radial distances ranging from approximately 0.6 miles to 16 miles. (See Appendix B and Figures B-1, B-2 and B-3 for station descriptions and locations). The TLD monitoring network consists of one TLD placed in each 22.5 degree meteorological sector surrounding the plant at the site boundary, and at a distance of approximately 4.5 miles for a total of 32 stations. An additional 8 stations are l located at seven residences and one control location.
The remaining 42 stations are located in special interest areas that include other Clinton Power Station sampling locations, population centers, residences, recreation i areas, and regulatory agency TLD stations. Collection of TLDs occurs at the end of each calendar quarter and the data are reported as exposures received over a 91 day period. If the collection interval is not 91 days, the exposure is interpolated or extrapolated linearly-to a 91 day period.
20
Direct Radiation (continued)
TLDs are used to measure radiation exposures at specific locations. The TLDs used by the Clinton Power Station monitoring program measure gamma radiation from both terrestrial and cosmic sources. Terrestrial radiation results primarily from naturally occurring radioactive uranium, thorium, and potassium-40 present in the earth's crust. Cosmic sources of radiation result from the interaction of cosmic rays with atmospheric gases.
Since TLD exposures are affected by environmental factors such as soil moisture, rock and soil composition, snow-cover, sunlight, and temperature, data comparisons between TLD locations are difficult. Even if TLD data collected during a particular quarter of one year is compared to the same quarter of another year (for the same location), environmental factors specific to the time of the field cycles must be considered.
NUREG/CR-4068, " Summary of Historical Experience with Releases of Radioactive Materials from Commercial Nuclear Power Plants in the Unites States" (March, 1985) indicates that seasonal variations in terrestrial external dose can be as much as 5 mrem during any three month period.
The amount of radiation emitted from the radionuclides in the soil depends on the moisture content of the soil and the presence and amount of snow cover. Increased amounts of soil moisture create a shielding effect and reduce the amount of radiation emitted from soils.
Similarly, snow cover provides shield.ing and lowers the amount of radiation emitted from the soil. Weapons test debris (fallout) produced from atmospheric nuclear weapons testing also contributes to radiation exposure in the environment but to a much lesser extent than the natural terrestrial and cosmic sources.
\
l l
l I
l l
21
i Direct Radiation (continued)
A TLD is a small passive detector which integrates exposure of ionizing radiation through the.use of a crystalline phosphor material. The TLD works on the principle that alteration of the phosphors' electron energy levels occur under exposure to radiation. This-alteration is in proportion to the radiation exposure received. Upon thermal heating of the TLD phosphors, the altered electron states are returned to their normal energy level. During this process, light emission occurs and is measured by a very sensitive readout instrument.
The total quantity of light emitted is directly proportional to the amount of radiation which caused the altered energy levels. Through the.use of conversion factors, the light emitted is converted to a known quantity of radiation exposure, millirem (mrem). Since each TLD has four phosphors, the radiation exposure reported is the average value of the four readings. The exposure received by the TLD during transit and storage along with any residual exposure in the phosphor is accounted for during the analysis process by the use of transit TLDs.
The type of phosphor used in the monitoring program's environmental TLDs was changed in 1985. The planned change occurred at the beginning of the first. quarter when calcium sulfate phosphors replaced lithium. fluoride phosphors. The change of phosphors was made because calcium sulfate is more sensitive to lower radiation exposures and experiences less fading over time than lithium fluoride phosphors. Although calcium sulfate phosphors over-respond to low energy radiation between 10 kiloelectron volts (kev) and 200 kev, the dosimeter is designed to compensate for the over-response by using metal shields to flatten out-responses at low energies between 40 kev and 200 kev. Since only six percent of the environmental exposures are due to photons with energies less than 100 kev, the response of the badge is-less critical at low energies. The calcium sulfate phosphor used in the environmental monitoring program meets American National Standards Institute (ANSI) -
N545-1975, " Performance, Testing, and Procedural Specification for Thermoluminescent Dosimetry (Environmental Applications)" specifications, i
1 22
Direct Radiation (continued)
The quarterly data found in Table 5 are average exposures of the four separate phosphor readings for each TLD. The standard deviations (plus or minus two sigma) of the average value indicates the exposure variability between the four phosphors. That is the larger the standard deviation, the greater the variability between the exposure readouts. For most field conditions, the variability in recorded exposures among the four phosphors is plus or minus ten percent provided the phosphors are subjected to consistent annealing, calibration, readout, storage, and exposure periods. The 1985 data show standard deviations less than ten percent of the mean for all the TLDs with the exception of stations CL-28 and CL-52 in the first quarter. The standard deviations reported for CL-28 and CL-52 during that quarter were 11.1 percent and 10.6 percent, respectively. However, both of these standard deviations are less than half of the variation noted in natural background exposures over a calendar quarter.
The data reported beneath the total column of Table 5 is the summation of the four quarterly exposures. The range of exposures (for four quarters) was from 67.0 millirem to 89.2 millirem. The data values were consistent with the expected exposures of between 63 and 105 millirem noted in the National Council on Radiation Protection and Measurements Report Number 45, Natural Background Radiation in the United States (November 1975) for the Clinton area. Since Clinton Power Station is not operating, the exposures measured by the TLDs are due solely to natural environmental radiation.
Surface Water Sampling A total of 36 monthly grab samples were obtained from three locations on Clinton Lake in 1985. (See Appendix B and Figure B-2 for station descriptions and location).
Surface water is sampled as a method of evaluating potential pathways of radionuclides via the aquatic food chain and direct exposure. Radionuclides present in surface water can become attached to very fine particles suspended in the water. These particles are consumed by aquatic organisms which provide entry of the radionuclides into the food chain. Direct exposure to radionuclides in surface water can occur during recreational activities such as swimming and boating.
Also, radionuclides attached to fine sediment particles in the water may eventually be deposited on a shoreline resulting in another direct exposure pathway.
23
Table 5 1985 Summary of thermoluminescence dosimeter data First Second Third Fourth Quarter Quarter Quarter Quarter Total Location (millirem) (millirem) (millirem) (millirem) (millirem)
CL-1 22.0!1.2 17.4!0.7 25.2!0.9 18.2 0.5 82.8 CL-2 23.9!1.2 19.6 1.0 26.420.7 19.420.8 89.3 CL-3 18.7!0.8 20.2!1.4 23.8 0.5 18.510.5 81.2 CL-4 19.8!1.0 16.8:0.8 21.6!0.4 16.6!0.5 74.8 CL-5 22.8!0.8 17.6 1.0 23.7 0.7 18.220.4 82.3 CL-6 20.011.0 17.9 1.0 23.9:1.0 18.3 1.1 80.1 CL-7 19.1 1.1 17.1 0.9 21.3!1.4 17.410.8 74.9 CL-8 18.921.3 19.3!1.2 19.6!0.4 18.2 0.4 76.0 CL-11 16.2!1.3 18.5 0.6 19.6 0.5 17.7!0.5 72.0 CL-20 a 17.5 0.9 19.2 0.8 16.9 0.4 53.6c CL-21 18.0!1.5 19.3 1.2 22.1 1.0 18.7!1.4 78.1 CL-22 16.8t0.9 17.9 0.7 19.6!0.5 17.5 0.7 71.8 CL-23 15.8 0.9 16.620.9 18.920.8 15.7 0.4 67.0 CL-24 17.0 1.7 19.1 1.2 19.411.1 17.510.5 73.0 CL-25 13.2 0.8 b 16.610.4 13.6 0.9 43.4c CL-26 16.4 0.9 ~ b 19.420.9 15.0 0.5 50.8e CL-27 17.8!0.9 16.910.8 19.3 0.6 17.3 0.7 71.3 CL-28 18.0!2.0 19.2 1.0 23.720.4 18.1 0.4 79.0 CL-29 20.7 0.8 19.011.0 24.2 0.4 19.5 0.4 83.4 CL-30 19.9 0.8 18.2!0.7 20.1 0.5 17.7 1.4 75.9 CL-31 14.1 1.4 b 16.520.9 15.3 0.5 45.9c CL-32 15.9 0.9 17.5!0.6 21.2 2.3 17.0 0.7 71.6 CL-33 17.8 1.5 18.010.8 20.6!3.1 17.7 0.7 74.1 CL-34 17.4tl.1 21.0!1.2 23.9 1.0 19.8!0.4 82.1 CL-35 18.1!1.3 18.1 0.8 20.310.7 18.2 0.6 74.7 CL-36 19.3 1.4 18.6 0.8 24.3!1.4 18.510.6 80.7 CL-37 19.3!1.0 17.510.7 24.1 0.3 17.4 0.4 79.3 CL-38 21.1!0.8 17.610.8 22.010.8 18.510.4 79.2 C
CL-39 18.021.8 18.1 0.7 b 17.5 0.5 53.6 CL-40 20.2!0.7 18.721.2 22.7!0.5 18.321.3 79.9 1 s
CL-41 20.6 1.0 19.9 0.7 24.lt0.4 18.220.8 82.8 CL-42 29.0 1.2 18.8 1.2 25.4 0.9 18.2!0.8 82.8 CL-43 21.9!1.3 20.010.7 21.1 0.5 19.6t0.4 82.6 ,
1 CL-44 17.0!1.7 18.7 0.2 21.810.6 18.511.0 76.0 CL-45 20.8!0.9 20.4 1.7 25.010.3 18.3!0.6 84.5 l CL-46 21.011.4 17.1!0.7 22.7 1.3 16.7 0.8 77.5 24 n_
Table 5 (continued)
First Second Third Fourth Quarter Quarter Quarter Quarter Total Locetion (millirem) (millirem) (millirem) (millirem) (millirem)
CL-47 22.9!1.5 18.6 0.8 25.2!1.0 19.2!1.2 85.9 CL-48 23.6!0.9 20.0!0.7 24.8 0.6 19.210.5 87.6 CL-49 20.811.1 19.8!1.3 21.5 0.2 17.310.6 79.4 CL-50 19.4 1.9 17.7 0.9 22.0!0.6 18.5 0.6 77.6 CL-51 20.8!1.1 18.1 1.0 21.9 1.8 18.010.6 78.8 CL-52 18.7 2.0 18.0!0.7 19.6 0.8 17.7!0.7 74.0 CL-53 16.221.5 19.8 1.4 19.1 0.6 18.612.5 73.7 CL-54 18.2!0.9 19.420.6 20.2!0.3 17.4 0.6 75.2 CL-55 18.4!1.2 18.710.8 23.7 1.0 17.2!0.8 78.0 CL-56 22.2!0.7 20.8 1.0 22.9 1.8 17.7 0.5 83.6 CL-57 30.3!0.8 18.2 1.0 21.2 1.4 17.7 0.6 77.4 CL-58 21.4!1.0 18.720.8 23.3:1.8 17.6 0.8 81.0 c
CL-59 21.4 0.9 b' 21.3!0.3 18.2 1.1 60.9 CL-60 18.9 1.2 18.6!0.8 24.0 0.6 17.6 0.8 79.1 CL-61 20.4!0.8 19.4 1.0 23.7 0.5 18.010.7 81.5 CL-62 20.0 1.2 19.9!1.2 b 17.510.5 57.4" CL-63 18.7 1.3 20.1 1.4 22.210.7 18.5!1.0 79.5 CL-64 17.7 1.0 18.910.8 24.3 1.4 16.9 1.2 77.8 CL-65 21.5 1.0 18.3!0.7 24.0 0.7 17.8 0.9 81.6 CL-66 21.2 1.4 17.1!0.9 19.4 0.2 17.121.0 74.7 CL-67 21.0 0.8 19.0 0.6 22.6 1.1 18.020.8 80.6 CL-68 18.0 0.7 17.011.2 21.6!0.9 15.4!0.8 72.0 CL-69 23.5!0.8 19.8 1.0 23.0!0.2 19.0 0.9 85.3 CL-70 21.320.7 20.0!1.2 27.2 2.3 18.0tl.0 86.5 CL-71 25.3 0.9 19.511.5 23.420.3 17.6!0.7 85.8 CL-72 22.010.7 b b b 22.0c CL-73 34.310.8 20.5 0.8 24.9 1.1 17.3 0.9 86.0 CL-74 23.2!0.8 19.5 1.3 26.8!0.8 17.7 0.9 87.2 CL-75 22.9 0.9 19.4 1.2 24.7 0.4 17.110.6 84.1 CL-76 22.2 0.7 19.3!0.7 23.0!0.6 18.2!0.8 82.7 !
CL-77 20.3!0.8 18.6!1.0 b b 38.9c CL-78 20.0 0.8 18.3 1.3 23.0 0.7 17.2!0.5 78.5 i CL-79 19.8 1.0 17.210.8 18.7 0.4 16.4!0.5 72.1 CL-80 14.5 1.2 18.6 1.0 19.0!1.4 17.210.5 69.8 CL-81 18.9!1.0 19.3!1.2 17.711.4 17.810.5 73.7 c CL-82 14.8 1.1 17.9!1.5 b 15.510.8 49.2 I
i 25 i
_ _ 1
Table 5 (continued)
First Second Third Fourth Quarter Quarter Quarter Quarter Total Location (millirem) (millirem) (millirem) (millirem) (millirem)
CL-83 21.610.9 19.3 1.1 24.110.6 18.7!0.8 83.7 CL-84 12.710.8 b b b 12.7c CL-85 20.7!0.9 19.6 0.7 b 17.411.0 57.7c CL-86 20.520.9 18.810.9 b 17.510.6 56.8c CL-87 19.5!1.3 22.1:1.1 23.6 0.4 19.311.0 84.5 CL-109 a 18.310.8 22.410.3 17.4 0.6 58.lc CL-110 a b 24.7!1.0 18.110.6 42.8c CL-111 a 18.4!0.6 19.0!0.3 18.3 0.6 55.7c CL-112 a 17.8 1.0 21.810.8 15.810.5 55.4c CL-113 a 19.9 0.9 23.4 1.2 18.210.6 61.5c 8
location added in second quarter b
TLD stolen during quarter; no data available c four quarters of data not available -
(Note: For a station with less than four quarters of data, an estimate of the total exposure received during the year can be made by averaging the reported quarterly exposures. This average is used as an exposure for a quarter where data is not available. Exposure for stations with missing quarterly values range from 50.8 to 88.0 mrem when quarterly averages are used).
l l
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26
Surface Water Sampling (continued)
Gamma isotopic analyses were performed on the water samples obtained from the Clinton Lake throughout 1985.
At the end of each calendar quarter, a small volume of water was taken from each of the monthly samples and combined to form one quarterly composite sample. The composite sample was analyzed for tritium. Beginning in July 1985, gross beta analyses were. performed on the monthly samples as part of.the planned expansion of the monitoring program. The expansion of the program to perform gross beta analyses on water samples allows for the collection of additional data to assess
! concentrations of natural radioactivity present in the environment.
In 1985, all gamma results were less than the lower limit of detection (LLD). Specific searches were made for radioisotopes produced from neutron radiation in reactors, including manganese, iron, cobalt and zinc, and for fission products niobium, zirconium, cesium, barium and lanthanium. Gamma results are listed in Appendix H,
- Table H-10 through H-12.
4 Gross beta activities for surface water samples ranged from less than 1.5 pCi/l to 6.1.pCi/1. The results lif analyses are listed in Table 6. The beta activities were ~-
associated with fine sediment particles in the samples which contain naturally occurring potassium-40. Analyses of shoreline and bottom sediments from Clinton Lake confirm the presence of potassium-40.
I Tritium analyses performed on the quarterly composites of l the monthly samples show all concentrations as less than i
the lower limit of detection which ranged between 200 and <
300 pCi/1. These results are consistent with present
! background concentration of tritium in water which ranges i between 150 pCi/1 and 300 pCi/1. The 150 pCi/l to 300 pCi/l concentration is an estimate for the State of j
Illinois based on data collected by other utilities in Illinois and the Illinois Department of Nuclear Safety.
1 4
3 I-1 27 l
Surface Water Sampling (continued)
Clinton Lake is the source of drinking water for ,
employees at Clinton Power Station. The water is chemically treated onsite before being distributed throughout the station for drinking purposes. No other member of the general public use Clinton Lake as a source of drinking water. The closest reported use of drinking water downstream of Clinton Lake occurs approximate 242 miles away at Alton, Illinois on the Mississippi River.
4 Sampling and analyses of Clinton Power Station's drinking water as part of preoperational monitoring began in April 1985 at CL-14. (See Appendix B and Figure B-2 for sample-descriptions and location). CL-14 is located in the Service Building of the station and is representative of the drinking water distributed throughout the plant. The water is sampled as a means of monitoring the drinking water ingestion pathway. A monthly grab sample was collected from CL-14 from April through December. A water composite sampler installed at CL-14 during the '
- first week of April provided an additional sample during that month. However, an operational problem with the composite sampler beginning in May, prevented collection of additional samples. Consequently, a grab sample was taken each month. Although the preoperational monitoring program provides baseline data to characterize the natural radiation level and radioactivity concentrations present in the environment, the program also serves to field test equipment under a variety of environmental conditions. Problems which are uncovered in the preoperational program are resolved prior to the operational program. Analyses performed on the samples included gross alpha, gross beta, gamma isotopic and iodine-131.
)
I t
k l
>= . , _ , . -- -,. ..
Surface Water Sampling (continued)
Gross alpha activities were reported as less than the lower limit of detection for all samples with one exception. Gross alpha results are listed in Table 8.
The April 1985 sample reported an activity of 0.4 0.3 pCi/1. Statistically, the two sigma counting uncertainty of 0.3 indicates the measurement could fall between 0.1 and 0.7 pCi/1 at a ninety-five (95) percent confidence interval or a significance level of .05. The range of concentrations is consistent with the lower limit of detection values reported for the other CL-14 gross alpha results. The activity in the April 1985 sample is associated with fine particles present in the sediment which emit alpha radiation. The sediment particles contain naturally occurring alpha emitters such as uranium-238 and radium-226.
Gross beta activities ranged from 1.4 to 2.7 pCi/1.
Results are listed in Table 8. The gross beta activity found in the samples originates from very fine sediment particles which contain naturally occurring potassium-40.
Gamma results for the Cl-14 samples were all reported as less than the lower limit of detection. Specific searches were made for radioisotopes produced from neutron radiation in reactors, including manganese, iron, cobalt, and zinc, and for fissions products niobium, zirconium, cesium, barium, and lanthanium. Gamma results are listed in Appendix H, Table H-13.
Iodine-131 analyses were also performed on the water samples collected from CL-14. No iodine-131 was detected in any of the samples. All results were reported as less than the lower limit of detection which was 0.5 pCi/1.
Results of the iodine-131 analyses are listed in Appendix H, Table H-14.
Tritium analyses were performed on the quarterly composite of the monthly samples begintilng with the second quarter of 1985. The analyses were part of the planned expansion of the monitoring program. All tritium concentrations were reported as less than the lower limit of detection which ranged between 200 and 300 pCi/1.
29
Table 6 1985 Summary of gross beta results for surface water samples Collection Date CL-9 CL-10 CL-13 (pCi/1) (pCi/1) (pCi/1) 07-17-85 2.4 0.7 3.0 0.8 2.4*0.8 08-14-85 2.5 0.7 2.6 0.7 2.2 0.6 09-04-85 1.9t0.9 3.3i1.0 5.8 1.1 10-09-85 2.9 0.7 3.2*1.0 < 1. 5 b
11-27-85 6.lil.2 2.1tl.1 2.6 0.6 12-24-85 3.0 0.8 3.4 0.8 2.6*0.7 a
explanations of the data reporting conventions are given in Appendix G 30
=. -
- ma m.
Table 7 1985 Summary of gross alpha results for drinking water.8 Month Gross Alpha (pCi/1)
April 0.4 0.3 May < 0. 8 June < 0. 7 July < 0. 2 August < 0.6 September < 0. 3 October < 0. 8 November < 0. 8 December < 0. 8 8
explanations of the data reporting conventions are given in Appendix G
)
l 31
l l
Table 8 1985 Summary of gross beta results for drinking water l l
Month CL-14 (pCi/1)
April 2.7t0.6 May 2.2i0.4 June 2.5 0.4 July 1.5i0.4 August 2.1*0.5 September 1.4i0.3 1
October 1.6i0.4 November 1.6 0.4 December 2.2 0.3 a
- explanations of the data reporting conventions are given in Appendix G l
l
-1 32 M .. ~
Well Water Sampling Twenty-one monthly grab samples of well water from stations CL-7 and CL-12 were collected in 1985. (See Appendix B and Figure B-2 for sample descriptions and locations). Station CL-7 and CL-12 provide drinking water to the Mascoutin Recreation Area and the community of DeWitt, respectively. The water is sampled as a means of monitoring the ingestion pathway via water consumption. Although both the Mascoutin Recreation Area and DeWitt are several miles from the Clinton Power Station, the wells which supply the water are located within two miles of the site. Analyses performed on the samples included gross alpha, gross beta, gamma and tritium.
Gross alpha analyses were performed on samples collected from CL-7 on the second month of each calendar quarter.
Beginning in July, gross alpha analyses were performed monthly on CL-12 samples as part of the planned expansion of the monitoring program. At Cl-7, gross alpha activity ranged from less than 1.1 pCi/l to 0.9 Ci/l at CL-12, results ranged from less than 1.5 to 1.8 pCi/1. These activities are extremely low and close to the lower limit of detection. Naturally occurring uranium-238 and ralium-226 in the fine sediment particles present in the sample contribute to the alpha activity. Gross alpha results are listed in Table 9.
In 1985, positive gross beta results from CL-7 showed activities ranging from 1.1 to 2.3 pCi/1. All other results were less than the lower limit of detection.
Positive gross beta results from CL-12 ranged from 1.4 to 1.9 pCi/1. All other results were less than the lower limit of detection. The presence of naturally-occurring potassium-40 (a beta emitter) in the. fine sediment particles contributes to the beta activity. Gross beta results are listed on Table 10. Since Clinton Power ;
Station was not operating in 1985, both the alpha and '
beta activities found in the well water samples are the result of radioactivity already present in the environment.
All gamma results for the samples were less than the lower limit of detection. Specific searches were made for radioisotopes produced from neutron radiation in i reactors, including manganese, iron, cobalt, and zinc, j and for fission products niobium, zirconium, cesium, '
barium, and lanthanium. Gamma results are listed in Appendix H, Tables H-15 and H-16, 33
i
- i
! Well Water Sampling (continued) .
- Tritium. analysis performed on the quarterly. composites of
- the monthly samples showed all concentrations as less j than the lower limit of detection which ranged between 4 200 and 300 pCi/1.
In 1985, gamma results were reported as less than the lower limit _of detection for all samples collected from
- CL-7 and CL-12.
[ The 1985 quarterly. tritium analyses performed on the quarterly composites of the monthly samples shows all J concentrations as less than the lower limit of detection.
1 Intake Water i
In June 1985, a water composite sample was installed at 4 CL-92 in the Clinton Power Station intake screenhouse, j (See Appendix B and Figure B-2 for sample description and location). The sampler obtains a specific volume of l water every hour. At the end of a month, the composite i sample is analyzed for gross beta, gamma isotopic, and i
tritium concentrations. During 1985, this location l served as the upstream sample location providing j information on the background concentrations of radioactivity found in surface water prior to entering the plant.
4 Gross beta activities at CL-92 ranged from 1.6 to 2.8 pCi/1. These results are consistent with surface water l' data from Clinton Lake which showed ranges from 1.9 to i 6.1 pCi/1. The beta activity at CL-92 is attributed to the presence of fine sediments in the sample which Gross beta
- contain naturally occurring potassium-40.
i results are listed in Table ll. 3 Gamma analyses showed.all results as less than the lower limit of detection.- Specific searches were made for j radioisotopes produced from neutron radiation in s reactors, including manganese, iron, cobalt,- and zinc, and i for fission products niobium, zirconium, cesium, barium '
j and lanthanium. Again, these results are consistent'with
- 1985 surface water sample data which also showed all.
I gamma activities as less than the lower limit of ;
l detection. Gamma results are listed in Appendix H, Table i H-17.
J i
34 i
- .. -.~ . - - . _ .
a Table 9 1985 Summary of gross alpha results for well water samples Collection Date CL-7 CL-12 (pCi/1) (pCi/1) b 07-17-85 < 1.7 d
08-14-85 0.9 0.8 b < 1. 6 09-04-85 b
10-09-85 1.8 1.0 11-27-85 < 1.1 1.8 0.7 b d 12-24-85 explanations of the data reporting conventions are given in Appendix G b gross alpha analysis performed on samples from the second month of each calendar quarter as planned expansion of the monitoring program c sample unavailable to collector when municipality changed locks to sampling location without notifying Clinton Power Station d collector missed sample 35
Table 10 1985 Summary of gross t a results for well wbtcr7 samples" Collection Date CL-7 -CL-12 (pCi/1) (pCi/1) 01-02-85 < 2. 4 < 4. 8 h b 02-27-85 03-20-85 < 2. 4 < 4. 8 04-06-85 < :1. 8 < 3. 5 05-15-85 < 2. 0 < 4. 0 06-12-85 < 1. 3 < 4.2 07-17-85 2.3il.2 < 1. 7 c
08-14-85 _
1.1 0.9 09-04-85 1.4 1.2 < 1. 7 10-09-85 2.0il.3 < 1. 7 11-27-85 1.9i0.9 1.4 1.0 d
12-24-85 1.4t0.9 a
explanations of the data reporting conventions are given in' Appendix G l b
sample not received, carton damaged in shipment and contents discarded by UPS c
sample unavailable to collector when municipality changed locks to sampling lodation without notifying Clinton-Fower Station l d
collector missed sample , e i
/
4 36
( - --
[
- .p- _ _ _ _ _ -
Intake Water (continued)
Tritium analyses showed all results as less than the lower limit of detection with one exception. A concentration of 220 100 pCi/l was recorded for the July 1985 sample. This concentration is consistent with background tritium concentrations found in the surface water around the Clinton Power Station area. Data collected in 1982 by the Illinois Department of Nuclear Safety reported positive tritium concentrations in two surface water samples from the Clinton Lake. The concentrations of the samples were 303i27 pCi/1 and 429 260 pCi/1. 1985 results from the Illinois Department of Nuclear Safety were not available. The presence of tritium in the Lake is primarily from atmospheric nuclear weapons testing and to a lesser extent, cosmogenic processes. Tritium results are listed in Table 12.
Effluent Water In June 1985, a water composite sampler was installed at location CL-90. The sampler was located at the Clinton Power Station discharge flume. (See Appendix B and ;
Figure B-2 for sample description and location). The i composite sampler collects a specific volume of water from the discharge flow of the plant at specific time intervals. The collection interval depends upon the amount of water discharged from Clinton Power Station. A short interval is used for high flow rates while a longer interval is used for lower flow rates. The composite !
sampler is programmed monthly based on the expected '
discharge for ,the plant. Analyses performed on the '
effluent water included gross alpha, gross beta, gamma isotopic, iodine-131 and tritium.
Gross alpha results from CL-90 show one positive activity of 1.3 pCi/l in September 1985. All other results were less than the lower limit of detection. The concentration of 1.3 pCi/l is very close to the analysis laboratory's lower limit of detection. The activity is attributed to sediment particles present in the sample containing naturally-occurring uranium-238 and radium-226, both alpha emitters. Gross alpha results are listed in Table 13.
37
a a
Table 11 1985 Summary of gross beta results for intake water samples Month CL-92 (Intake)
(pCi/1)
June 2.8 0.9 July 2.0tl,0 August 1.6 0.9 September 2.4i0.7 f October 2.0*0.9 November 2.6 1.0 December 2.Si0.7 a
explanations of the data reporting conventions are given in Appendix G I
j j
i 38
Table 12 1985 Summary of tritium results for-intake water samples Month CL-92 (Intake)
(pCi/1)
- June < 200 July 220 100 -
August < 200 September < 200 October < 200 November < 200 December < 200 a explanations of the data reporting conventions are given in Appendix G i
I l
I T
I 39
- _ - - _ _ _ - - - _ _ - - _ _ 6 -- -_ . - _ - - _ _ . - - _ _ _ _ _ _ _ _ . . - - _ __ _ _ _ _ _ _ _ ____ _
Effluent Water (continued)
Gross beta activities recorded for effluent water CL-90 ranged from 1.6 to 6.1 pCi/1. These activities were similar to the surface water results which ranged from 1.9 to 6.1 pCi/1. Gross beta results are listed in Table 13.
Gamma analyses performed on the effluent water samples show all results as less than the lower limit of -
detection. Gamma results are listed in Appendix H, Table H-18. Specific searches were made for radioisotopes produced from neutron radiation in reactors, including manganese, iron, cobalt, and zinc, and for fission products niobium, zirconium, cesium, barium, and lanthanium. Again, these results are consistent with 1985 surface water data which also showed all gamma activity as less than the lower limit of detection.
Tritium analyses were performed on the effluent water samples beginning in June 1985 as part of the planned expansion of the monitoring program. Quarterly composite samples of the monthly collections were analyzed with all results reported as less than the lower limit of detection of 200 pCi/1.
Bottom and Shoreline Sediment Sampling Samples of bottom and shoreline sediments obtained from the Clinton Lake provide information on the radionuclide content of the sediments. Radionuclides present in water can become adsorbed onto suspended sediments in water and deposited on either the lake shoreline or the lake bottom.
l In 1985, a total of ten bottom sediment samples were collected at five locations (CL-7c, CL-10, CL-13, CL-19 and CL-89) fron the Clinton Lake in June and October.
Two additional samples obtained from Lake Shelbyville, approximately fifty (50) miles south of Clinton Power Station, served as control samples. (See Appendix B and l Figure B-4 and B-5 for sample descriptions and '
locations). Gamma isotopic, gross alpha and beta analyses performed on the samples from both Clinton Lake and Lake Shelbyville indicate the presence of both naturally-occurring and man-made radionuclides. Results are reported in units of pCi/g (dry) since the samples are dried for analyses.
I 40
Table 13 1985 Summary o effluentwater{grossalphaandgrossbetaresultsfor Month Gross Alpha Gross Beta (pCi/1) (pCi/1)
June < 1.4 5.1 1.0 July < 1. 5 2.7*1.1 August < 1. 2 4.0il.0 September 1.3i0.6 6.li0.9 October < 1. 3 4.2il.1 November < 0. 6 3.6i0.7 December < 0. 7 1.6 0.6 8
explanations of the data reporting conventions are given in Appendix G 4
41
Bottom and Shoreline Sediment-Sampling (continue'd)
Naturally-occurring potassium-40 detected in Clinton Lake and Lake Shelbyville samples, ranged in-concentrations from 8.67 to 20.62 pCi/g at CL-13 and CL-105, respectively. Also, the cosmogenically produced radionuclide, beryllium-7 was detected.in one Clinton Lake sample (CL-7c) at a concentration of 0.67 pCi/g.
The presence of beryllium-7 is not considered unusual in sediments of Clinton Lake as this radionuclide was found in 1985 air particulate, grass, milk, soil, and vegetation _ samples for the-Clinton Power Station.
Two fission products, cesium-137 and strontium-90 were detected in most of the sediment samples. The concentrations of Cs-137 ranged from 0.03 to 0.62 pCi/g.
Strontium-90 was detected in the bottom sediment samples at concentrations ranging from 0.011 pCi/g to 0.056 pCi/g. Strontium-90 concentrations are calculated to range between 0.16 and 0.21 pCi/g for-this area.. The presence of cesium-137 and strontium-90 in the environment is attributed to fallout. Gamma and strontium-90 results are listed in Appendix.H, Table H-19.
Gross alpha analyses were performed on these bottom-sediment samples collected in October 1985 as part of the planned expansion of the monitoring program. Results in Table 14 show activities ranging from less than 4.6 pci/g to 14.7 pCi/g. The alpha activity is attributed to naturally-occurring radionuclides from the uranium-238 and thorium-232 series. Soil samples collected in 1985 show similar gross alpha activities ranging from 6.2 to 10.4 pCi/g.
Gross beta analyses were also performed on the bottom sediment samples collected in October.1985 as part of the planned expansion of the monitoring l program. Results in Table 14 show activities ranging from 13.4 to 27.2 pCi/g.
The beta activity is attributed t6 naturally-occurring potassium-40 found in all the samples.- The fission products cesium-137 and strontium-90~also contribute.to the beta activity. However, the majority of the gross beta activity is attributed to naturally-occurring potassium-40 since concentrations ranged between-8.67 and 20.62 pCi/g. Soil' samples collected in 1985 show' similar gross beta activities ranging from 17.7 pCi/g to-24.7 pCi/g.
I 42
f f
Bottom and Shoreline Sediment Sampling (continued) i Twelve sediment samples were collected from six locations j along the shoreline of the Clinton Lake in June and October, 1985. Two additional samples were obtained from Lake Shelbyville to serve as control samples. (See Appendix B and Figures B-4 and B-5 for sample 1
descriptions and locations). Gamma isotopic analyses were performed on all the samples. Additionally, gross alpha and gross beta analyses were performed on the October 1985 samples as part of the planned expansion of 4 the monitoring program.
Gamma analyses showed only naturally-occurring potassium-40 present in all the samples and the fission product, cesium-137 in one sample. The potassium-40
! concentrations ranged from 6.33 to 9.39 pCi/g. The cesium-137 concentration was 0.04 pCi/g. The presence of-cesium-137 in the sample was attributed to fallout from atmospheric nuclear weapons testing. Gamma results are listed in Appendix H, Table H-20.
Gross alpha analyses performed on the shoreline sediment 4
samples collected in October 1985 show all results as ,
less than the lower limit of detection which ranged between 3.0 and 4.7 pCi/g. Results of the gross alpha j analyses are found in Table _15.
Gross beta analyses performed on the shoreline sediment
- samples collected in October 1985 show concentrations ranging from 8.8 to 11.1 pCi/g. The gross beta activity detected is primarily from. naturally- occurring potassium-40. Also, the fission product cesium-137 was detected at a low concentration of 0.04 pCi/g which would ,
contribute some beta activity. Results of the gross beta analyses are found on Table 15.
The higher gross alpha and beta activities reported from i the bottom sediments as compared to shoreline sediments i reflects the greater adsorption capability of the bottom sediment. Since bottom sediment is composed of clay and silts versus the shoreline's composition of sand, radionuclides are more easily adsorbed onto bottom sediments. Consequently, radionuclides become more
' concentrated on the lake bottom sediments resulting in
' higher activities.
1 h
i t
i 43
Toble 14 Summary of October 1985 Grogs Alpha and Gross Beta results for bottom sediment samples Location Gross Alpha Gross Beta (pCi/g-dry) (pCi/g-dry)
CL-7C 14.7*5.4 24.5*3.6 CL-10 7.9i4.2 25.9 3.7 CL-13 < 4.7 13.4 2.2 CL-19 13.2*5.4 24.2*3.8 CL-89 12.7 5.3 21.5i3.6 CL-105 10.9*3.6 27.2 2.8 8
explanations of the data reporting conventions are given in Appendix G 1
l 44
l Table'15 Summary of-October 1985 Gross glpha and Gross Beta results for shoreline sediment samples Location Gross Alpha Gross Beta (pCi/g-dry) (pCi/g-dry)
CL-7b < 4. 5 9.5*2.7 CL-7d < 3.1 8.8*2.2 CL-10 < 4. 7 9.3*2.9 CL-19 < 3. 5 9.5 2.6 CL-88 < 4. 4 11.1*2.8 CL-89 < 3.1 10.2t2.2 CL-105 < 3. 0 10.2 2.2 a explanations of the data reporting conventions are given in Appendix G I
i
, 1 45
l i
Periphyton Sampling In 1985, periphyton was sampled at three locations in Clinton Lake and one location in Lake Shelbyville. (See Appendix B and Figures B-4 and B-5 for sample descriptions and locations). A total of eight samples were collected in June and October. Periphyton is made up of organisms which are attached to permanently anchored buoys. The buoys mark the sampling locations in the lake. Since periphyton concentrates radionuclides through biological processes, sampling of this media provides a methodolcgy for evaluating the concentration
) of radionuclides in the aquatic environment.
Gamma analyses were performed on all the samples. Results k are reported in units of pCi/g and are found in Appendix H, Table H-21. The results showed naturally-occurring potassium-40 present in all the samples in concentrations ranging from 2.52 to 5.23 pCi/g. Beryllium-7, also naturally-occurring was detected in one sample at a concentration of 1.66 pCi/g. Cesium-137, a fission product was detected in two samples. The concentrations i were 0.07 and 0.11 pCi/g. The presence of cesium-137 is attributed to fallout from atmospheric nuclear weapons testing.
Iodine Ingestion Pathway Sampling Milk is an important medium to check for radiciodine entering the food chain. Radioiodine deposited on the surface of plants can be ingested directly by grazing animals and passed into milk and other dairy products.
Since iodine-131 has an eight day half-life, milk consumption may occur before iodine decays, allowing the radionuclide to enter the human food chain.
The production of milk for human consumption in the immediate vicinity of Clinton Power Station is virtually non-existent. However, a control location (CL-ll6),
approximately 14 miles west-southwest of the plant and in the least prevalent wind direction, provides cow milk samples on a semi-monthly (May through October) and monthly (during the rest of the year from November through April) basis. Although no milk indicator stations are available for sampling, the control location provides information on fallout and a reference data base. (See Appendix B and Figure B-3 for sample description and location).
46
~ - -- .- _ . . - - -
Iodine Ingestion Pathway Sampling (continued)
As part of the planned expansion of the monitoring program, sampling of CL-ll6 began in July 1985. From July to December 1985, nine samples were collected.
Iodine-131 and gamma isotopic analyses were performed on the samples. All iodine-131 results were reported as less than the lower limit of detection. Gamma analyses show naturally-occurring potassium-40 present in all the samples. Concentrations of potassium-40 ranged from 1150 to 1375 pCi/1. Potassium-40 is found naturally in soil, plants, and fertilizers. Results of gamma analyses are i shown in Appendix H, Table H-22.
Grass samples collected as part of the monitoring program serve as another method for identifying iodine-131 entry into man's food chain. Three locations (CL-15, CL-16, and CL-17) are sampled as indicator stations while a fourth location (CL-11) is sampled as a control. The grass samples are collected semi-monthly from May through October and monthly from November through April. (See Appendix B and Figures B-1, B-2 and B-3 for sample j descriptions and locations).
In 1985, sixty-four grass samples were collected and analyzed for iodine-131 and gamma-emitting isotcpes. All iodine-131 analyses showed results as less than the lower limit of detection. Gamma analyses show naturally-occurring beryllium-7 and potassium-40 present in the samples. Beryllium-7 concentrations ranged from 0.22 to 14.00 pCi/g. Potassium-40 concentrations ranged from 1.36 to 14.50 pCi/g.
The particulate beryllium-7, produced by cosmic ray interaction with atmospheric gases, settles onto grass by gravitational settling, and wet or dry deposition.
Potassium-40 is present in grass via root uptake from the soil or surface deposition of fertilizer and soil particles. Gamma analyses results are listed in Appendix H, Tables H-23 through H-26.
47
~-_-___~___._._____._-___ _ _ . _ _ _ _ _ . _ _ _ _ _ . . - . _ _ _ _ _ _ _ _
._. ._-_._____m__ - _ _ _ _ ___
f Broadleaf Vegetable Sampling Three vegetable gardens were sampled in 1985. (See Appendix B and Figure B-1 and B-2 for sample descriptions and locations). The choice of two indicator locations were based upon the results of a meteorological model which predicts the areas most likely to be affected by deposition of radionuclides released from Clinton Tower Station gaseous effluents. The third garden located approximately 12.5 miles from the site in one of the least prevalent wind directions serves as a control station. Sampling of the gardens occurs monthly during the growing season. The vegetables sampled included cabbage, lettuce, and swiss chard. These vegetables have broad leaves which act as receptors for the deposition of particulates. Gamma isotopic, gross beta and iodine-131 analyses were performed on the samples.
In 1985, twenty samples were collected from the three sampling locations as part of the planned expansion of the monitoring program. Gamma isotopic results show only naturally-occurring potassium-40 present in the samples ranging in concentrations form 1.45 to 5.51 pCi/g.
These concentrations were within the range of the 1985 grass sample gamma isotopic results. All 1985 gamma results were reported in pCi/g and are found in Appendix H, Table H-27.
Gross beta results ranged from 0.87 to 6.69 pCi/g. The gross beta activity is attributed to the uptake of potassium-40 from soil and the deposition of potassium-40 on the outer surface of the vegetables. Gross beta results were reported in pCi/g and are found on Table 16.
All iodine-131 analyses were reported as less than the lower limit of detection. The iodine-131 results are included in Appendix H, Table H-27 with the gamma results.
Fish Sampling Fish samples were collected from Clinton Lake in June and October of 1985. Additionally, as part of the planned expansion of the monitoring program, fish were collected from Lake Shelbyville. (See Appendix B and Figures B-4 and B-5 for sample descriptions and locations). The fish were analyzed by gamma spectroscopy.
48 e_ _ r________-_______ : m - - = - _ = _ -
Table 16 1985 Summary of gross beta results for. green leafy vegetables Collection Cabbage (pci/g) Swiss Chard (pci/g) Lettuce (pci/g) i Date CL-18 CL-114 CL-115 CL-18 CL-114 CL-115 CL-18 CL-114 CL-115 l
l l 07-29-85 2.20 0.05 2.4210.54 1.7510.50 5.08!0.17 6.6910.15 a 1.51 0.03 a a 08-28-85/ 1.96!0.07 1,77 0.006 1.02 0.04 3.46!0.12 b 4.5810.16 a a a 0.87 0.04 08-29-85 2.6420.09 3.68!0.13 09-26-85 1.83!0.06 1.7610.06 1.47 0.06 2.91 0.11 4.16!0.15 a a 1.5210.08 Not available due to poor growth of vegetable.
(Twoseparatesamplesanalyzedbylaboratory.
Fish Sampling (continued)
Since fish are part of man's food chain, radiological analysis of fish provide information on the potential intake of radionuclides by man via the fish consumption pathway. Fish ingest sediments which contain radionuclides by bottom feeding or by predation on other organisms which ingest sediment. Biological uptake and retention of radionuclides varies among different fish based upon feeding habits and habitat.
Indicator fish samples were taken in the vicinity of the plant discharge flume. Control fish samples were collected from Lake Shelbyville, approximately 50 miles south of Clinton Power Station. These species of fish collected at each location included largemouth bass, white crappie, carp, and bluegill. These species comprise the four most commonly caught fish in the Clinton Lake.
Gamma isotopic analyses performed on the sample show only naturally-occurring potassium-40 present in both indicator and control species. Results found in Appendix H, Table H-28 and H-29. Concentrations of potassium-40 ranged from 2.10 to 3.11 pCi/g for the Clinton Lake samples. At Lake Shelbyville, concentrations ranged from 1.91 to 3.19 pCi/g.
Soil Sampling Surface soil samples were collected at each of the eight air monitoring stations in 1985. (See Appendix B and Figures B-1, B-2, and B-3 for sample descriptions and locations). Soil samples provide information regarding deposition of radionuclide fallout in an area. Gross alpha, gross beta, and gamma isotopic analyses were performed on the samples.
Gross alpha results were reported as pCi/g and are listed on Table 17. Al 6.2 to 10.4 pCi/pha
- g. activity in the samples ranged fromThe alpha acti range of concentrations reported for the Clinton Lake bottom sediment samples. The alpha activity in the samples is from naturally-occurring radionuclides of the uranium-238 and thorium-232 series.
50
- - _ _ _ _ _ - _ . =2 _- __ : : _ _ ___
. .- _ __ __._ _ _ . _ _ _ _ _ . _ _ _ _ ~
i l Soil Sampling (continued) i ,
J Gross beta results were reported as pCi/g and are listed
- on Table 17. Beta activity- in the samples ranged from i 17.7 to 22.3 pCi/g. These results were within the range
, of the bottom sediment samples results collected from Clinton Lake. The beta activity in all the samples is attributed to naturally-occurring potassium-40. Also, ,
the fission product cesium-137 detected.in some of the samples contributes to the total beta activity.
Gamma analyses results were reported as pCi/g and are listed in Appendix H, Table H-30. Naturally- occurring-potassium-40 was detected in all the samples.
Concentrations ranged from 12.0 to 15.9 pCi/g.
( The i i cosmogenically produced radionuclide, beryllium-7 was i found in one sample at a concentration of f
0.44
- 0.07 pCi/gm. Cesium-137 was detected in seven of ;
- the eight samples at concentrations ranging from 0.14 to - !
j 0.40 pCi/g. The cesium-137 concentrations are within the i range of concentrations reported for the bottom sediment t samples. The presence of cesium-137.in the environment
, is attributed to fallout from past atmospheric weapons tests.
i l !
i i
I I
i l 1 l 1 l i
(
l 3
)
i i 51 '
1 Tcble 17 1985 Summary of gross alpha and beta results for soil samples l Location Gross Alpha Gross Beta (pCi/g-dry) (pCi/g-dry)
CL-1 7.3*2.9 19.6*2.4 CL-2 9.0*3.2 22.3*2.5 CL-3 7.3*2.9 21.2*2.5 CL-4 8.8i3.1 24.7*2.6 CL-6 8.0i3.0 17.7*2.3 ,
CL-7 10.4*3.4 22.2*2.5 CL-8 6.2i2.8 20.0i2.4 CL-11 8.8 3.2 21.1*2.4 52
QUALITY ASSURANCE PROGRAM The Clinton Power Station Quality Assurance program for the preoperational monitoring program consists of: (1) requiring the analysis laboratory, to participate in the Environmental Protection Agency Cross-Check Programs (2) requiring the laboratory to perform duplicate analyses on every tenth samples and (3) a yearly audit of the laboratory facilities. Clinton Power Station's preoperational monitoring program is audited by the Nuclear Regulatory Commission and the station's Quality-Assurance department.
The laboratory used by Clinton Power Station for radiological analyses of environmental samples has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs have been operated by agencies which supply environmental-type t samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laborator ies . The purpose of such a program is to provide an independent check on the laboratory s analytical procedures and to alert it to any possible problems.
Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies the range the reported results should fall within. Results consistently higher or lower than the known values and results outside the specified ranges indicate a need to check the instruments or procedures used.
The results in Table 18 were obtained through participation in the environmental sample crosscheck program for milk, water, air filters, and food samples for January through October 1985. This program has been conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.
53
- - - ,- , es- y e -.w , -
,ay+-. -e- -. r, e --- -. . 2- --:- =
The criteria used to determine the agreement between the analysis laboratory and the EPA result involved -
examination of both the result and the standard deviation. If the ranges of the analysis laboratory and the EPA results overlapped when compared to each other, the results were considered consistent. The range of the analysis laboratory is the mean of three sample value determinations plus or minus two standard deviations of the three values. The range of the EPA is the value from one determination plus or minus three standard deviations for the single determination.
In 1985, all of the reported Environmental Protection Agency crosscheck results for the sample types used in the Clinton Power Station monitoring program were within acceptable ranges with two exceptions. The first exception involved a February 1985 water sample. The chromium-51 concentration was analyzed as less than the lower limit of detection by the analysis laboratory while the EPA result was reported as 48.0 pCi/1. Subsequent chromium-51 analyses performed on water samples in June and October shows concentrations which were within the acceptable range.
The second exception occurred in March 1985. An initial radium-228 analysis. performed on a water sample by the laboratory differed from the Environmental Protection Agency's results. A reanalysis of the sample showed agreement between results.
l l
54
Te.ble-18 Crosscheck comparison of results for milk, water, air filters, and food samples between analysis laboratory and Environmental Protection Agency (EPA) for 1985.
Concentration in pCi/l a Lab Sample Date AnalysisbLab EPAResu{t Code Type Collected Analysis 20 3c,n=1 STW-392 Water Jan. 1985 Sr-89 < 3. 0 3.0 8.7 Sr-90 27.3 5.2 30.0 2.6 STW-393 Water Jan. 1985 Gross Alpha 3.3*1.2 5 8.7 Gross Beta 17.3*3.0 15 8.7 STS-395 Food Jan. 1985 Sr-89 25.3*6.4 34.0i5.0 Sr-90 27.0i8.8 26.0il.5 I-131 38.0*2.0 35.0 6.0 Cs-137 32.7 2.4 29.0 5.0 K-40 1410*212 1382i120 STW-397 Water Feb. 1985 Cr-51 < 29 48i8.7 Co-60 21.3*3.0 20i8.7 Zn-65 53.7i5.0 55.8.7 Ru-106 < 23 25 8.7 Cs-134 32.3*1.2 35*8.7 Cs-137 25.3*3.0 25 8.7 STW-398 Water Feb. 1985 H-3 3869 319 3796i634 STM-400 Milk March 1985 I-131 7.3 2.4 9.0i0.9 STW-402 Water March 1985 Ra-226 4.6i0.6 5.0tl.3 Ra-228 0.8 9.0t2.3 Reanalysis Ra-228 9.0i0.4 STW-404 Water March 1985 Gross Alpha 4.7*2.3 6i8.7 Gross Beta 11.3*1.2 15i8.7 STAF-405 Air March 1985 Gross Alpha 9.3tl.0 10.0i8.7 Filter Gross Beta 42.0*1.1 36.0*8.7 Sr-90 13.3*1.0 15.0 2.6 Cs-137 6.3*1.0 6.0i8.7 STW-407 Water April 1985 I-131 8.0i0.0 7.5i1.3 STW-408 Water April 1985 H-3 3339*150 3559*630 i
55
Table 18 -(cont'd)
Concentration in pCi/1 8 Lab Sample Date AnalysisbLab EPAResuft Coda Type . Collected Analysis i20 - 3a,n=1 STW-409 Water April 1985 (Blind) Gross Alpha 29.7 1.8 32.0i5.0 Sample A Ra-226 4.4 0.2 4.1*0.6 Ra-228 d ~6.2*0.9 Uranium e 7.0i6.0 Sample B Gross Beta 74.3t11.8 72.0 5.0 Sr-89 12.3*7.6 10.0*5.0 Sr-90 14.7*2.4 15.0tl.5 Co-60 14.7*2.4 15.0*5.0 Cs-134 12.0i2.0 15.0*5.0 Cs-137 14.0i2.0 12.0*5.0 STW-413 Water May 1985 Sr-89 36.0il2.4 39.0i5.0 Sr-90 14.3*4.2 15.0*1.5 STW-414 Water May 1985 Gross Alpha 8.3*4.1 12.0*5.0 Gross Beta 8.7 1.2 11.0*5.0 STW-416 Water June 1985 Cr-51 44.7*6.0 44.0*5.0 Co-60 14.3*1.2 14.0 5.0 Zn-65 50.3*7.0 47.0i5.0 Ru-106 55.3t5.8 62.0*5.0 Cs-134 32.7 1.2 35.0i5.0 Cs-137 22.7i2.4 20.0i5.0 STW-418 Water June 1985 H-3 2446i132 2416t351 STM-421 Milk June 1985 Sr-89 10.3*4.6 11.0*8.7 Sr-90 9.0*2.0 11.0*2.6 I-131 11.7*1.2 11.0t10.4 Cs-137 12.7*1.2 11.0 8.7 K-40 1512*62 1525*132 STW-423 Water July 1985 Gross Alpha 5.0i0.0 11.0i8.7 Gross Beta 5.0 2.0 8.0i8.7 STW-425 Water August 1985 I-131 25.7*3.0 33.0*10.4 STW-426 Water August 1985 H-3 4363i83 4480*776 STAF-427 Air August 1985 Gross Alpha 11.3i0.6 13.0*8.7 Filter Gross Beta 46.0tl.0 44.0*8.7 Sr-90 17.7 0.6 18.0*2.6 Cs-137 10.3i0.6 8.0*8.7 56 e- . _
Table 18 (cont'd) -
Concentration in pCi/la Lab Sample Date Analysis bLab EPAResuft Code Type Collected Analysis i2 3 ,n=1 STW-419 Water Sept. 1985 Sr-89 15.7*0.6 20.0*8.7 Sr-90 7.0i0.0 7.0i2.6 STW-430 Water Sept. 1985 Ra-226 8.2i0.3 8.9t2.3 Ra-228 4.li0.3 4.6 1.2 STW-431 Water Sept. 1985 Gross Alpha 4.7 0.6 8.0i8.7 Gross Beta 4.7tl.2 8.0 8.7
)
i STW-433 Water Oct. 1985 Cr-51 <13 21.0i8.7 i Co-60 19.3i0.6 . 20.0*8.7 l Zn-65 19.7 0.6 19.0t8.7 Ru-106 <19 20.0i8.7 i Cs-134 17.0 1.0 20.0i8.7 Cs-137 19.3tl.2 20.0*8.7 f
l STW-435 Water Oct. 1985 H-3 1957 50 1974 598 l
a All results are in pCi/1, except for elemental potassium (K) data, which are in mg/1, air filter samples which are in pCi/ filter, and food, whie '. are in pCi/kg.
b Unless otherwise indicated, the analysis laboratory's results are given as the mean of three sample value determinations 2 standard deviations c for three values.
OSEPA results are presented as the known values t control limits of 1 d 3 standard deviations for one determination.
Analysis l'aboratory lost sample.
- Analysis laboratory does not test for uranium, i October'1985 is the latest available result, i l
57
REFERENCES (1) Code of Federal Regulations, Title 10, Part 50.36 (a).
(2) Code of Federal Regulations, Title 10, Part 50, Appendix I,Section IV, paragraph B, subsections (2) and (3).
(3) United States Nuclear Regulatory Commission Radiological Assessment Branch Technical Position, Revision 1, November 1979, entitled: An Acceptable Radiological Environmental Monitoring Program.
(4) Committee on the Biological Effects of Ionizing Radiations, Division of Medical Sciences, National Research Council, "The Effects on Populations of Exposure to Low Levels of Ionizing Radiation: 1980" National Academy Press, Washington, D.C., 1980 (5) United Nations Scientific Committee on the Effects of Atomic Radiation, Ionizing Radiation: Sources and Biological Effects, United Nations, New York, 1982. -
(6) Teledyne/Hazelton Analytical Procedures Manual, Nuclear Sciences Department, Revision 2, May 1981.
(7) Teledyne Isotopes Quality Assurance Manual with addenda, QAP No. 1, June 22, 1984.
(8) Teledyne Isotopes Midwest Laboratory, Analytical Procedures Manual, Revision 4, June 1984.
(9) Teledyne Isotopes Midwest Laboratory, Quality Control Procedures Manual, Revision 2, May 1981.
(10) National Council on Radiation Protection and Measurements,
" Environmental Radiation Measurement, NCRP Report No. 50",
Washington D.C., December 27, 1976.
(11) NRC NUREG-0854, FINAL ENVIRCNMENTAL STATEMENT Related to the Operation of Clint'on Power Station, May 1982.
(12) U.S. Atomic Energy Commission Report, " Sources of Tritium and Its Behavior Upon Release to the Environment", by D. G. Jacobs, TID-24635, 1968.
(13) National Council on Radiation Protection and Measurements Report Number 45, Natural Background Radiation in the United States, issued November 15, 1975.
58
(14) CRC Handbook of Environmental Radiation, 1982 by CRC Press, Inc. , Table 5, enti tled: Estimates of Natural Radionuclides in the Lithosphere and Soils.
(15) Environmental Radiation '85, Proceedings of the Eighteenth Midyear Topical Symposium of the Health Physics Society. Paper presented: The Use of Attached Alcae in Monitorine the Radioactive Liquid Effluents, by Ruth Patrick, Academy of Natural Sciences and John Palms of Emory University.
(16) United States Nuclear Regulatory Commission, Regulatory Guide 1.109, " Calculations of Annual Doses to man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October 1977.
(17) U.S. Environmental Protection Agency. " Natural Radiation Exposure in the United States." Donald T. Oakley. ORP/SID 72-1, June 1972.
(18) United States Nuclear Regulatory Commission, Regulatory Guide 4.1, " Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.
(19) National Council on Radiation Protection and Measurements Report Number 77, Exposure from Uranium Series with Emphasis on Radon and its Daughters. March 15, 1984.
(20) National Council on Radiation Protection and Measurements Report Number 78. Evaluation of Occupational and Environmental Exposure to Radon and Radon Daughters in the United States, 1984.
(21) Merril Eisenbud. Environmental Radioactivity, Second Edition, Academic Press, New York and London, 1973.
59
. . . . . - . _ . . _ -- . _- . _ - . . .- _ _ - . - - - . - - - . _ _ . - - ~ = _ - _ - - - . - - -
f 1
i
, APPENDIX A 1
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
Name of Facility Clinton Power Station Docket No. 50-461 Location of Facility Dewitt, Illinois Reporting Period January 1 - December 31, 1985 l
(County, State)
Medium or Type of Lower Limit All Indicator Location with Control Number of l Pathway Sampled Analysis of Locations: Highest Annual Mean Locations: Nonroutine
- (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f Distance f f Measurements Range Direction Range Range Column 1 Column 2 Column 3 Column 4 Column 5 Column 6 Column 7
' TABLE EXPLANATIONS:
E$ Column 1: The unit of Measurement describes all the numerical values for LLD, Mean and Range reported for a particular sample medium. Example: the Gross Beta LLD in AIR PARTICULATES is 0.010 pCi/m8 . .
Abbreviations used are: pCi/m3 = picocurie per cubic meter of sampled air; arem/ quarter = dose measured for calendar quarter period (3 months); pCi/1 = picoeurie per liter of sample; pCi/g =
I l
picocurie per gram of sample.
I Column 2: The Type of Analyses are described as follows: Gamma Spec. = measurement of each radioisotope in a sample using Gamma Spectroscopy; Cross Beta = measurement of the radioactivity in a sample by measurement of emitted betas - no determination of individual radioisotopes is possible; Tritium j
= measurement of tritium (H-3) in sample by liquid scintillation counting method; TLD = direct measurement of gamma dose using thermoluminescent dosimeters. t
. Column 3: LLD reported is the highest of those reported for each type of analysis during the year; if all A
analyses reported positive values, no LLD is reported.
Column 4: Samples taken at Indicator Locations during a operational radiological environmental monitoring program (REMP) reliably measure the quantities of any radioisotopes cycling through the pathways I to man from the nuclear station. The reported values are the mean or average for the year of all samples of that type which had values greater than the LLD. "f" is the fraction of all the samples taken at all indicator location for that medium which reported values greater than the LLD. Example: 7 results greater than LLD out of 15 samples taken would be reported 7/15. The Range is the values of the lowest to highest sample results greater than LLD reported at all the indicator locations for that medium.
1
Fr
~
Column 5: Tha Mean, f fraction and Range along with the N me of the location, Dietence from tha CPS grs9eum effluent stack in miles, and the letter (s) name of the compass sector in the Direction of the sample location from the CPS gaseous effluent stock. The Location with the Highest Annual Mean is compared to both Indicator and Control location of the medium samples.
Column 6: - Control Locations are sited in areas where radioisotopes from CPS are not expected. Sample
- results are used as reference for the control location.
I Column 7: NRC Regulations (Branch Technical Position, Rev 1, November 1979) includes a table of lj radioisotope concentrations that if exceeded by confirmed sample measurements indicates a Nonroutine Reported Measurement, and requires further action.
P l
I d
Ch i,
da 1'
i -
[I lf -
I i
i l
'l APPENDIX A (continued) lI Medium or Type of Lower Limit All Indicator Location with Control Number of l Pathway Sampled Analyses of Locations: liighest Annual Mean Locations: Nonroutine i
(Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f Distance f f Measurements i
Range Direction Range Range l
!* Air Particulates Gross Beta a .026 CL-1 .027 .025
- pCi/m 3 405 351/351 1.8m 50/50 52/52 l ,
.010 .079 W .016 .078 .015 .072 i b Gamma Spec 32 I Be-7 .032 .082 CL-3 .0797 .076 ii 22/28 0.65m 4/4 3/4
! m .055 .102 NE .067 .096 .030 .109 w
Nb-95 .011 < LLD -
< LLD < LLD Zr-95 .0090 < LLD --
< LLD < LLD Ru-103 .0079 < LLD --
! Ru-106 .024 < LLD --
< LLD < LLD l Cs-134 .0028 < LLD --
< LLD < LLD Cs-137 .0024 < LLD --
, i l Ce-141 .0092 < LLD --
! Ce-144 .0087 < LLD -- < ,iLLD < LLD Direct Radiation TLD c 19.5 CL-2 22.3 18.0 305 301/301 0.7m 4/4 4/4 12.7-27.2 NUE 19.4-26.4 16.2-19.6 l
I a = no LLDs reported i b = Mn-54, Fe-59 Co-58, Co-60, Zn-65, Ba-140 and La-140 reported only if identified during analysis.
- e - not applicable.
4
.~
L l
i
- APPI'NDIX A (continusd)
}
}
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: Highest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f Distance f f Measurements Range Direction Range Range j Surface Water Gamma Spec j' pCi/1 34 i
Be-7 27 < LLD -- < LLD < LLD l < LLD < LLD l Mn-54 15 < LLD -
Fe-59 33 < LLD -- < LLD < LLD l
< LLD < LLD < LLD D Co-60 15 --
Zn-65 30 < LLD -- < LLD < LLD m Nb-95 15 < LLD - < LLD < LLD
" 15 < LLD -- < LLD < LLD Zr-95 Cs-134 15 < LLD - < LLD < LLD Cs-137 15 < LLD -- < LLD < LLD
Ba-140 60 < LLD -- < LLD < LLD La-140 15 < LLD -- < LLD < LLD j Ce-144 30 < LLD -- < LLD < LLD it < LLD il Tritium 300 < LLD -- -
12 Cross Beta 1.5 3.0 CL-9 3.13 2.97 i 18 12/12 2.7m 6/6 6/6 1.5-6.1 ESE 1.9-6.1 2.1-3.4
- I j = after July 1, 1985, Ba-La-140 was reported as two separate peaks, Ba-140 and La-140 l
h U
APPENDIX A (continutd)
Medium or Type of ' Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: Highest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) ,f Distance f f Measurements ,
Range Direction Range Range __
Surface Water Gross Alpha 0.6 1.3 CL-90 1.3 intake & effluent 7 1/7 0.4m 1/7 pCi/1 1.3 ENE 1.3 Gross Beta 3.4 CL-90 3.4 2.3 14 _ 7/7 0.4m 7/7 7/7 ,
1.6-6.1 ENE 1.6-6.1 1.6-2.8
2
! *- ENE d
,!- f Tritium 200 200 CL-92 220 220 li 7 1/7 Screen house 1/7 1/7 220 EN_E ,( -220 220 Gamma Spec -
14 .
Be-7 43 < LLD -- '
/
Mn-54 5 < LLD-
< LLD, -- < LLD < LLD Co-58 5 < LLD -- < LLD < LLD i Co-60 5 < LLD -- < LLD < LLD
{j Zn-65 12 < LLD --
ir '
Nb-95 10 < LLD --
< LLD' < LLD Zr-95 10 < LLD --
,e Cs-134 5 < LLD --
Os-137 5 < LLD ~
Ba-140 60 < LLD -- < LLD < LLD La-140 15 < LLD --
< LLD >-
T
, - -- . ~ - _ _ - _
APPENDIX A (continued)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: Highest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f_ Distance f f, Measurements Range Direction Range Range Soil Cross Alpha 8.1 CL-7 10.4 8.8 pCi/g dry 8 7/7 2.3m 1/1 1/1 6.2-10.4 SE 10.4 8.8 Gross Beta 21.1 CL-4 24.7 21.1 8 7/7 0.8m 1/1 1/1 17.7-24.7 WSW 24.7 21.1 Gamma Spec os 8 -
w Be-7 0.24 0.44 CL-7 0.44 < LLD 1/7 2.3m 1/1 0.44 SE 0.44-0.44 4
K-40 13.7 CL-2 15.9 13.5 7/7 0.7m 1/1 1/1 11.5-15.9 NNE 15.9 13.5 Mn-54 0.028 < LLD -
'! Fe-59 0.079 < LLD - < LLD < LLD Co-58 0.028 < LLD - < LLD < LLD Co-60 0.026 < LLD -
< LLD < LLD Zn-65 0.082 < LLD - < LLD < LLD Nb-95 0.035 < LLD -
~
Zr-95 0.053 < LLD -
< LLD < LLD Cs-134 0.039 < LLD -
.j Cs-137 0.026 0.23 CL-4 0.39 0.40 6/7 0.8 1/1 1/1 0.14-0.39 WSW 0.39 0.40 Ba-140 0.16 < LLD- - -
< LLD La-140 0.053 < LLD - - < LLD Ce-144 0.18 < LLD - -
< LLD
APPENDIX A (continued)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: Highest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f Distance f f Measuremente Range Direction Range Range Well Water Gross Alpha 1.7 1.5 CL-12 1.8 pCi/1 7 3/7 1.6m 2/7 0.9-1.8 E 1.8-1.8 Gross Beta 4.8 1.7 CL-7 1.7 21 8/21 2.3m 6/21 1.1-2.3 SE 1.1-2.3 Gamma Spec 21 cn m.
I Be-7 27 < LLD --
< LLD Mn-54 15 < LLD - . < LLD Fe-59 30 < LLD --
< LLD Cs-134 15 < LLD -- < LLD Cs-137 15 < LLD --
< LLD a
BaLa-140 15 < LLD --
< LLD La-140 15 < LLD -- < LLD Ce-144 30 < LLD -- < LLD Tritium 200 < LLD --
< LLD 8
= after July 1, 1985, Ba-La-140 was reported as two separate peaks, Ba-140 and La-140 m._ _ _ _ _ _ . _ . __._______.-_________._m. _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 4 -.
. - - - - -_ .. ~-_ -
4 APPENDIX A (continued)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: liighest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f Distance f f Measurements Range Direction Range Range l
Grass Gamma Spec pCi/g wet 64 Be-7 0.091 3.08 CL-17 3.95 3.62 28/30 2.2m 10/10 10/10 0.22-13.60 E 0.52-13.60 0.72-14.00 K-40 6.27 CL-15 6.64 7.05
! 48/48 Site Boundary 16/16 16/16
- cn 1.36-11.8 E 3.66-10.50 2.21-14.50 i w Mn-54 0.038 < LLD -
< LLD < LLD Fe-59 0.075 < LLD -
< LLD < LLD Co-58 0.040 < LLD -
< LLD < LLD Co-60 0.041 < LLD -
< LLD < LLD Zn-65 0.10 < LLD -
< LLD < LLD Nb-95 0.039 < LLD -
< LLD < LLD Zr-95 0.071 < LLD -
< LLD < LLD I-131 0.060 < LLD -
< LLD < LLD Cs-134 0.039 < LLD -
< LLD < LLD Cs-137 0.042 < LLD - < LLD < LLD a < LLD BaLa-140 0.059 < LLD -
< LLD < LLD La-140 0.063 < LLD -
< LLD < LLD Cc-144 0.22 < LLD -
j ^
= after July 1, 1985, Bata-140 was reported as two separate peaks-Ba-140 and La-140 8
e
1 APPENDIX A (continued)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: liighest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f Distance f f Measurements 1 Range Direction Range Range Drinking Water Gross Alpha 0.8 0.4 CL-14 0.4 --
pCi/l 9 1/9 Service Bldg. 1/9 0.4 WNW 0.4 Gross Beta 2.0 CL-14 2.0 --
9 9/9 Service Bldg. 9/9 1.5-2.7 WNW 1.5-2.7 g I-131 0.5 < LLD --
< LLD --
10 Gamma Spec 9
< LLD < LLD Fe-59 30 < LLD -- < LLD < LLD Co-58 15 < LLD --
< LLD < LLD Co-60 15 < LLD -- < LLD < LLD Zn-65 30 < LLD -- < LLD < LLD Nb-95 15 < LLD -- < LLD < LLD
- Zr-95 15 < LLD -- < LLD < LLD Cs-134 15 < LLD -- < LLD < LLD ll Cs-137 15 < LLD -- < LLD < LLD "BaLa-140 15 < LLD -- < LLD < LLD Ba-140 60 < LLD --
< LLD < LLD p La-140 15 < LLD -- < LLD < LLD l Ce-144 30 < LLD -- < LLD < LLD Tritium 200 < LLD --
< LLD -
l 3 i
= after July 1, 1985, Ba-La-140 was reported as two separate peaks, Ba-140 and La-140
APPENDIX A (continutd)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: Highest Annual Mean Locations: Nonroutine i (Unit of Total Number Detection Mean Name Mean Mean Reported j - - Measurement) Performed (LLD) f_ Distance f f_ Measurements j Range Direction Range Range Periphyton Gamma Spec pCi/g vet 8 Be-7 1.31 <LLD -- <LLD 1.66 1/4 1,66 K-40 3.95 CL-19 5.03 4.81 j 4/4 3.4m 2/2 4/4 s .
2.52-6.26 Discharge flume 3.80-6.26 3.80-6.26 1 O Mn-54 0.098 <LLD --
< LLD <LLD Fe-59 0.24 <LLD --
< LLD <LLD Co-58 0.10 < LLD --
<LLD <LLD Co-60 0.11 <LLD --
<LLD <LLD Zn-65 0.18 <LLD --
< LLD <LLD Nb-95 0.11 <LLD --
<LLD <LLD Zr-95 0.19 <LLD -- <LLD <LLD Cs-134 0.10 <LLD - <LLD <LLD Cs-137 0.082 0.07 CL-7c 0.07 0.11 1/4 1.6m 1/2 1/4 0.07-0.07 SE 0.07-0.07 0.11-0.11 ka-140 0.65 <LLD --
<LLD <LLD La-140 0.29 <LLD --
<LLD <LLD Ce-144 0.24 <LLD --
<LLD <LLD
i APPENDIX A (continued)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: Highest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f Distance f f Measurements Range Direction Range Range I
Vegetation Gross Beta 2.28 CL-18 2.83 3.56 .
I pCL/g wet 20 14/14 Site Boundary 8/8 6/6
- 0.87-5.08 NE 1.51-5.08 1.76-6.69 t
Comma Spec 20
-- Be-7 0.072 < LLD -
< LLD 0.14 sa 1/6 i C) 0.14 K-40 2.81 CL-18 3.47 3.38 14/14 Site Boundary 8/8 6/6 1.45-5.51 NE 1.75-5.51 1.67-4.83 i
Mn-54 0.010 .< LLD -
. Fe-59 0.028 < LLD -
< LLD < LLD Co-58 0.010 < LLD -
< LLD < LLD Zn-65 0.030 < LLD - < LLD < LLD Nb-95 0.010 < LLD -
- Zr-95 0.017 < LLD -
< LLD < LLD I-131 0.012 < LLD -
< LLD < LLD Cs-134 0.008 < LLD -
< LLD < LLD Cs-137 0.010 < LLD -
< LLD- < LLD
[
Ba-140 0.035 < LLD - < LLD < LLD j
La-140 0.010 < LLD - < LLD < LLD Ce-144 -0.069 < LLD - < LLD < LLD
{
t i
C l
l APPENDIX A (continusd)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: liighest Annual Mean Locations: Nonroutine (Unit of Total Number Detectien Mean Name Mean Mean Reported Measurement) Performed (LLD) f_ Distance f f Measurements Range Direction Range Range Milk I-131 0.5 None < LLD < LLD pCi/l 9 Gamma Spec 9
Be-7 27 None < LLD < LLD K-40 None CL-116 1261 1261 y 14.0m WSW 9/9 1150-1375 9/9 1150-1375 Mn-54 5 < LLD < LLD Fe-59 12 < LLD < LLD Co-58 5 < LLD < LLD Co-60 5 < LLD < LLD
. Zr-65 7 < LLD < LLD Nb-95 10 < LLD < LLD Zn-95 10 < LLD < LLD Cs-134 5 < LLD < LLD Cs-137 5 < LLD < LLD Ba-140 60 < LLD < LLD ~
La-140 15 < LLD < LLD Cc-144 30 < LLD < LLD
APPENDIX A (continued)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: liighest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f Distance f f_ Measurements Range Direction Range Range f Fish Gamma Spec" l
pCi/g wet 16 Common Carp Be-7 0.15 < LLD --
^
Bluegill White Crappie K-40 2.54 CL-19 2.54 2.47 Large Mouth Bass 8/8 3.1m 8/8 8/8 2.10-3,10 E 2.10-3.10 1.9l-3.19 i
l N Co-58 .017 < LLD --
< LLD < LLD Nb-95 .019 < LLD --
< LLD < LLD Zr-95 .031 < LLD -- < LLD < LLD Ru-103 .024 < LLD -- < LLD < LLD Ru-106 .079 < LLD -- < LLD < LLD Cs-134 .011 < LLD --
< LLD < LLD Cs-137 .010 < LLD -- < LLD < LLD Ce-141 .037 < LLD --
< LLD < LLD Ce-144 .050 < LLD -- < LLD < LLD a Mn-54, Fe-59, Zn-65, Ba-140 and La-140 reported only if identified during analysis.
"*90
\
1
.. . - . - - _ . . -_ . . _ _ = . _ . _. _ - -
APPENDIX A (continued)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled, Analyses of Locations: Highest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f Distance f f Measurements Range Direction Range Range Shoreline Gross Alpha 4.7 < LLD -- --
< LLD Sediment 7 pCi/g dry Gross Beta 9.7 CL-88 11.1 9.9 7 4/4 2.4m 1/1 3/3 8.8-11.1 SE 11.1-11.1 9.3-10.2 Gamma Spec 14 w
K-40 7.41 CL-88 7.78 7.96 8/8 2.4m 2/2 6/6 6.26-9.30 SE 6.26-9.30 6.93-9.39 Mn-54 0.014 < LLD -- < LLD < LLD Fe-59 0.15 < LLD --
< LLD < LLD Co-58 0.029 < LLD --
< LLD < LLD Co-60 0.012 < LLD --
< LLD < Ltp Zn-65 0.044 < LLD -- < LLD < LLD Nb-95 0.096 < LLD --
< LLD < LLD Zr-95 0.060 < LLD --
< LLD < LLD Cs-134 0.016 < LLD --
0.04 1/6 0.04-0.04 Ba-140 15.10 < LLD -- --
< LLD
APPENDIX A (continuad)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: Highest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Mean Name Mean Mean Reported Measurement) Performed (LLD) f_ Distance f f Measurements Range Direction Range Range Bottom Sediments Gross Alpha 4.7 13.9 CL-7c 14.7 10.5 pCi/g dry 6 2/3 1.3m 1/1 3/3 13.2-14.7 SE 14.7 7.9-12.7 Gross Beta 20.7 CL-7c 24.5 24.9 6 3/3 1.3m 1/1 3/3 13.4-24.5 SE 24.5 21.5-27.2 Strontium .038 CL-19 .043 0.03 t, 2/2 3.4m 1/1 2/2
.011 .043 E .043 .011 .056 u
Gamma Spec
~2 Be-7 0.88 < LLD -- --
.067 1/6
.067 K-40 14.24 CL-19 16.20 15.75 6/6 3.4m 2/2 6/6 8.67-17.20 E 15.20-17.20 9.42-20.62 Mn-34 0.028 < LLD -- < LLD < LLD Fe-59 0.39 < LLD -- < LLD < LLD Co-58 0.69 < LLD --
< LLD < LLD Co-60 0.028 < LLD ~
< LLD < LLD 7n-65 0.066 < LLD -- < LLD < LLD Nb-95 0.098 < LLD --
< LLD < LLD Zr-95 0.150 < LLD -- < LLD < LLD Cs-134 0.029 < LLD -- < LLD < LLD Cs-137 0.024 0.266 CL 0.325 0.41 5/8 3.4m 212 6/6
.03 .49 E 0.16-0.49 .05 .62
r e
i APPENDIX A (continutd)
Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analyses of Locations: Highest Annual Mean Locations: Nonroutine (Unit of Total Number Detection Menn Name Mean Mean Reported.
Measurement) Performed (LLD) f Distance f f_ Measurements Range Direction Range Range Bottom Sediments (continued) Ba-140 119.30 < LLD -- --
< LLD
} La-140 33.5 < LLD -- --
< LLD M .
LA .
\
l f
1 e
I 1
L____.____ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
1 APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS FOR 1985 l l
a Station Map 1 Code Number Distance Sample Medium CL-1 1 1.8 miles W of HVACb stack AP,TLD,AI,SO CL-2 2 0.7 mile NNE of HVAC stack AP,TLD,AI,SO CL-3 3 0.65 mile NE of HVAC stack AP,TLD,AI,SO CL-4 4 0.7 mile SW of HVAC stack AP,TLD,AI,SO CL-5 5 0.7 mile N of HVAC stack TLD CL-6 6 0.8 mile WSW of HVAC stack AP,TLD,AI,SO CL-7A 7A 2.2 miles SE of HVAC stack AP,AI, TLD CL-7B 7B 2.1 miles SE of HVAC stack SS CL-7C 7C 1.6 miles SE of HVAC stack BS,SS,SL CL-7D 7D 2.3 miles SE of HVAC stack WW CL-8 8 2.2 miles E of HVAC stack AP,TLD,AI,SO CL-9 9 2.7 miles ESE of HVAC stack SW CL-10(C) 10 5.0 miles ENE of HVAC stack SW,BS,SS,AQ CL-11(C) 11 16 miles S of HVAC stack AP,M,TLD,VE,AI, SO,G CL-12 12 1.6 miles E of HVAC stack WW CL-13 13 3.6 miles SW of HVAC stack SW CL-14 14 Plant Service Building DW CL-15 15 Within 100 yards of CL-1 G CL-16 16 Within 100 yar'ds of CL-2 G CL-17 17 Within 100 yards of CL-8 ,
G CL-18 18 2.5 miles E of HVAC stack VE CL-19 19 3.4 miles E of HVAC stack ,
F CL-20 20 12.2 miles ENE of HVAC stack TLD CL-21 21 0.9 mile NNE of HVAC stack TLD CL-22 22 0.6 mile NE of HVAC stack TLD - .
CL-23 23 0.5 mile ENE of HVAC stack TLD CL-24 24 0.5 mile E of HVAC stack TLD CL-25 25 0.4 mile ESE of HVAC stack TLD 76
APPENDIX B (Cont'd)
Station Map Code Number Distance Sample Medium CL-26 26 0.3 mile SE of HVAC stack TLD CL-27 27 0.6 mile SSE of HVAC stack TLD CL-28 28 0.5 mile S of HVAC stack TLD CL-29 29 0.6 mile SSW of HVAC stack TLD CL 30 30 0.7 mile SW of HVAC stack TLD CL-31 31 0.8 mile WSW of HVAC stack TLD CL-32 32 0.7 mile WSW of HVAC stack TLD CL-33(C) 33 11 miles SSW of HVAC stack TLD CL-34 34 0.8 mile WNW of HVAC stack TLD CL-35 35 0.7 mile NW of HVAC stack TLD CL-36 36 0.6 mile N of HVAC stack TLD CL-37 37 3.4 miles N of HVAC stack TLD CL-38 38 3.6 miles NNE of HVAC stack TLD CL-39 39 3.8 miles NE of HVAC stack TLD CL-40 40 3.5 miles NE of HVAC stack TLD CL-41 41 2.4 miles E of HVAC stack TLD CL-42 42 2.8 miles ESE of HVAC stack TLD CL-43 43 2.8 miles SE of HVAC stack TLD CL-44 44 2.3 miles SSE'of HVAC stack TLD CL-45 45 2.8 miles S of HVAC stack TLD CL-46 46 2.8 miles SSW of HVAC stack TLD CL-47 47 3.3 miles SW of HVAC stack. TLD CL-48 48 2.3 miles WSW of HVAC stack TLD CL-49 49 3.5 miles W of HVAC stack TLD CL-50 50 3.2 miles WNW of HVAC stack TLD CL-51 51 4.4 miles NW of HVAC stack TLD -
CL-52 52 4.3 miles NNW of HVAC stack TLD CL-53 53 4.3 miles E of HVAC stack TLD CL-54 54 4.6 milec ESE of HVAC stack TLD CL-55 55 4.1 miles SE of.HVAC stack TLD CL-56 ,
56 4.2 miles SSE of HVAC stack TLD CL-57 57 4.5 miles S of HVAC stack TLD f
77
APPENDIX B (Cont'd)
Station Map Code Number Distance Sample Medium CL-58 58 4.3 miles SSW of HVAC stack TLD CL-59 59 3.3 miles SSW of HVAC stack TLD CL-60 60 4.5 miles SW of HVAC stack TLD CL-61 61 4.5 miles WSW of HVAC stack TLD CL-62 62 1.9 miles NW of HVAC stack TLD CL-63 63 1.3 miles NNW of HVAC stack TLD CL-64 64 2.1 miles WNW of HVAC stack TLD CL-65 65 2.5 miles ENE of HVAC stack TLD CL-66 66 0.8 mile WSW of HVAC stack TLD (colocated with CL-6)
CL-67 67 0.7 mile SW of HVAC stack TLD (colocated with CL-4)
CL-68 68 4.6 miles N of HVAC stack TLD (colocated with CL-112)
CL-69 69 0.7 mile NE of HVAC stack TLD (colocated with CL-3)
CL-70,71 70,71 0.7 mile NNE of HVAC stack TLD (colocated with CL-2)
CL-72 72 4.5 miles NNE of HVAC stack TLD (colocated with CL-72)
CL-73 73 5.1 miles ENE of HVAC stack TLD (colocated with CL-113) ,
CL-74 74 1.9 miles W of HVAC stack TLD CL-75 75 1.0 miles N of HVAC stack TLD CL-76 76 4.6 miles N of HVAC stack TLD CL-77 77 4.5 miles NNE of HVAC stack TLD CL-78 78 4.8 miles NE of HVAC stack TLD CL-79 79 4.5 miles ENE of HVAC stack TLD CL-80 80 4.1 miles W of HVAC stack TLD CL-81 81 4.5 miles WNW of HVAC stack TLD CL-82 82 1.4 miles W of HVAC stack TLD CL-83 83 0.5 miles NNW of HVAC stack TLD i
78
APPENDIX B (Cont'd)
Station Map Code Number Distance Sample Medium CL-65 85 0.2 miles W of HVAC stack TLD CL-86 86 0.2 miles WNW of HVAC stack TLD CL-87 87 0.2 miles NW of HVAC stack TLD CL-88 88 2.4 miles SE of HVAC stack SS CL-89(C) 89 3.6 miles NNE of HVAC stack SW,BS, SS,F, SL CL-90 90 0.4 miles ESE of HVAC stack SW CL-92 92 0.1 miles NW of HVAC stack SW CL-105(C) 105 50.0 miles S of HVAC stack F,SS,BS, AQ CL-109 109 0.7 miles WSW of HVAC stack TLD CL-110 110 0.8 miles SW of HVAC stack TLD CL-111 111 0.6 miles NE/ENE of HVAC stack TLD CL-ll2 112 4.6 miles N of HVAC stack TLD CL-113 113 5.1 miles ENE of HVAC stack TLD CL-ll4(C) 114 12.5 miles SSE of HVAC stack VE CL-115 115 0.9 miles NE of HVAC stack VE CL-ll6(C) 116 14.0 miles WSW of HVAC stack M a Control locations are indicated by "(C)" in this column.
All other locations are indicators, b HVAC: Heating Ventilation and Air Conditioning b
i 79
APPENDIX B (Cont'd)
Sample Codes Code Description i
CL Clinton AP Airborne Particulates
, AI Airborne Iodine i
TLD Thermoluminescent Dosimeter M Milk DW Drinking Water SW Surface Water WW Well Water VE Green Leafy Vegetables and Tuberous Vegetables
! G Grass F Fish AQ Periphyton BS Bottom Sediments SS Shoreline Sediments
! . SO Soil i
i 80
FIGURE B-1 1985 ENVIRONMENTAL SAMPLE LOCATIONS-(within 2 miles of Clinton Power Station)
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(K , ._
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81
FIGURE B-2 1985 ENVIRONMENTAL SAMPLE LOCATIONS (within 6 miles of Clinton Power Station) 1 N
. wv" h NNW l
- ii. . i
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l Notes:
- 7b, 7c, and 7d are shown on Figure B-4 I
t 82
FIGURE B-3 1985 ENVIRONMENTAL SAMPLE LOCATIONS (within 50 miles of Clinton Power Station)
N
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.,, u , _ ,.
____._ m ,
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83
l FIGURE B-4 1985 ENVIRONMENTAL SAMPLE LOCATIONS (for Fish, Periphyton, Lake Shoreline and Lake Bottom Sediments) l 89'bF 7
l .- -
W ile [
7d r 9
(-)
7 S ,
H 88 e . S gand 13 ctzuron LAxe 84
FIGURE B-5 1985 ENVIRONMENTAL SAMPLE LOCATION CL-105 (Fish, Periphyton, Lake Shoreline and Lake Bottom Sediments Controls) 74 CLINTON 9 55 Clinton Lake' 72 C ' DECATUR$
9 SPRIN3 FIELD Lake Shelbyville 57 105 (55}
- Key:
ILLINOIS N
0 10 20 SCALE OF M]LE5 j o
I
~85 ._ . . .- . . _ . _ _ _
f APPENDIX C 1985 DEVIATIONS IN THE SAMPLING SCHEDULE One of the purposes of the preoperational monitoring program is to evaluate the procedures and equipment used to collect environmental samples. Occassionally, equipment malfunctions or program deficiencies result in missed sample collections. Listed below are
- all deviations in the sampling schedule encountered in 1985.
January 9, 1985 No power was provided to the air i
sample pump at station CL-8 due to i blown fuse in fusebox.
January 16, 1985 No power was provided to the air sample pump at station CL-8 due to blown fuse in fusebox.
January 23, 1985 No power was provided to the air
- sample pump at station CL-8 due to
! blown fuse at adjacent fusebox.
t ~
i January 23, 1985 Filter paper from station CL-7 blew j away during collection.
i . January 30, 1985 No power was provided to the air sample pump at station CL-8 due to i blown fuse at adjacent fusebox.
February 1985 No grass samples were taken at stations CL-11, CL-15, CL-16 and CL-17
- due to snow cover on ground preventing j deposition.
l February 6, 1985 No power was provided to the air sample pump at station CL-8 due to blown fuse at adjacent fusebox.
f
- February 13, 1985 No power w4s provided to the air i sample pump at station CL-8 due to blown fuse at adjace.nt fusebox.
l February 27, 1985 Water samples containers from stations CL-7, 9, 12 and 13 were damaged during
- shipment and discarded by U.P.S.
February 27, 1985 Low sample volume at Station CL-1 due
, to power losa associated with utility
- pole transformer.
i March, 1985 No grass samples were taken at l
stations CL-ll, CL-15, CL-16 and CL-17 i
due to snow cover preventing -
deposition.
4 86
APPENDIX C (continued)'
March 6, 1985 No power was provided to the air sample pump at station CL-1 due to utility pole transformer problem.
March 13, 1985 No power was provided to the air sample pump at station CL-1 due to utility pole transformer problem.
April 17, 1985 Power was provided to station CL-7 for 45.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. No sample was analyzed due to low volume. Power problem resulting from blown fuse at adjacent fusebox.
April 24, 1985 No power was provided to the air sample pump at station CL-7 due to blown fuse at adjacent fusebox.
April - June, 1985 1985 Second Quarter TLDs were stolen from locations CL-25, 26, 31, 59, 72,
~84 and 110.
April - December, 1985 Monthly grab sample obtained from CL-14-since. water composite sampler ~~
was inoperable.
May 1, 1985 No power was provided to the air sample pump at station CL-7 due to blown fuse at adjacent fusebox.
July 17, 1985 Sample pump at station CL-8 operated for 102.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> instead of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.
July 24, 1985 Sample pump at station CL-8 operated for 124.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> instead of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.
July 24, 1985 Low sample volume due to pump malfunctions at station _CL-3. Pump operated for 122.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> instead of 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br />.
July 31, 1985 No power was provided to the air ,
sample pump at station CL-3 due to '
junction box problem. l July - September, 1985 1985 Third Quarter TLDs were stolen ,
from locations CL-39, 62, 72, 77, 82, 84, 85, and 86.
l l
l 87 )
APPENDIX C (continued)
August 7, 1985 Low sample volume due to pump malfunction at station CL-3. Pump operated for 87.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> instead of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.
August 7, 1985 Sample pump at station CL-7 operated for 89.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> instead of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.
August 14, 1985 Lock change to door of Dewitt Water Treatment Plant by municipality without notification of CPS Radiation Protection prevented collection of CL-12 sample.
September 4, 1985 Time meter at station CL-3 inoperable.
September 11, 1985 Time meter at station CL-3 inoperable.
December, 1985 Collector missed sample at CL-12.
December 28,. 1985 1985 Fourth Quarter TLDs were stolen from locations CL-72, 77, and 84, s
o
@ O ep 9
8
'4" 88
APPENDIX D LAND USE CENSUS In October, 1985, the annual land use census was conducted to identify in each of the 16 meteorological sectors, the nearest milk animal and the nearest garden of greater than 500 ft 2 producing broad leaf vegetation. The census is performed for a five mile radial distance from Clinton Power Station.The census was conducted by visual observation and consultation with the Illinois Department of Agriculture.
Results from the census found no milking cows or goats within a five mile radius of the site. Several herds of beef cattle were observed within the area; however, none of the cattle were milked for human consumption.
Vegetable gardens greater than 500 ft 2 within the five mile radius were also identified. Although the identification of vegetable gardens is not required, the survey provides information which is useful in evaluating the selection of broad leaf vegetation sampling sites. Again, changes from the 1984 census are noted on Table D-1.
In December, 1985, a survey was conducted to determine the nearest residence in each of the sixteen meteorological sectors. The survey used aerial overflights, topographical maps, and a drive-around to locate residences. Table D-1 shows the results of the survey.
I 4
l l
l 89 l
+ -- .c - ,- m--- -
--- --r .-
i Table D-1 -l l
APPENDIX D (continued) !
1985 LAND USE CENSUS
SUMMARY
Within 5 Miles of CPS Matsorological Nearest Nearest Garden Nearest Milk Animal 2
Sector Residence ( 500 ft ) Distance (Azimuth *) miles miles miles Type (1)
N(348.75'-11.25') 1.0 1.0 > 5.0 NA NNE(11.25'-33.75') 1.0(1) 1.1(6)' > 5. 0 NA NE(33.75*-56.25') 1.3 > 5.0(6) > 5.0 NA ,
ENE(56.25'-78.75') 1.8(1) > 5.0(6) > 5. 0 NA E(70.75'-101.25') 1.0 > 5.0(6) > 5.0 NA ESE(101.25'-123.75') 2. 6 (1) , (2) > 5.0(6) > 5.0 NA SE(123.75'-146.25*) 3.0(1) > 5.0(6) > 5.0 NA SSE(146.25*-168.75') 1. 8 (1) , (3) > 5.0(6) > 5.0 NA S(168.75'-191.25') 2.8 3.2(6) > 5.0 NA SSW(191.25'-213.75*) 3.1 (1) , (4) 3.2(6) > 5. 0 NA SW(213.75'-236.25*) 0.76 3.6(6) > 5.0 .N WSW(236.25*-258.75') 1.5 4.8(6) > 5. 0 NA W(258.75*-281.25') 1. 4 (1) , (5) 2.5 > 5.0 NA '
WNW(281.25*-303.75') 0.8 > 5.0(6) > 5. 0 NA NW(303.75'-326.25') 0.7 2.2(6) > 5.0 NA NNW(326.25'-348.75') 1.4 2.2(6) > 5.0 NA -
NOTES:
>- Greater than (1) Change from 1984 due to different reference point used for CPS release point. The 1985 reference point is the~more accurate since it uses the physical location of the HVAC stack.
(2) Identity is the Clinton Lake State Recreation Area building located in the Mascoutin State Recreation Area. Occupancy of the building is only part-time throughout all the year.
90 1
J-n - A L- ~ ' A #--
APPENDIX D (continued)
NOTES: (continued)
(3) New residence-located at Clinton Lake Marina' (4) New residence (5) Part time residence during summer (6) New garden location 5
1 1
3 s,
i 91 r
~ ..
4
) *
'~' '
APPENDIX E RADIOLOGICAL ENVIR,0NMENTAL MONITORING PROGRAN CHANGES IN 1985 - '
c January, 1985 Installed'TLD at stations CL-53 thr~ough.'CL-87 and CL-109 through CL-ll3.,
April, 1985 Deleted station CL-ll(c) sinNe no vegetables would be available in the upcoming growing season due to poor health'of' grower. Three additional vegetable sampling locations were-added in as part of planned REMP expansions.
April, 1985 ~ Instituted composite sampling of drinking water from station CL-14.
April, 1985 Installed TLD at station CL-20.
~
June, 1985 Instituted sampling of shoreline sediment at CL-88.
June, 1985 - Instituted sampling of shoreline and bottom sediment at,CL-89.
June, 1985 Instituted sampling of: discharge water composite at station'.CL-90.
June, 1985 Institut'ed sampling of intake water composite at station CL-92.
l June, 1985 Instituted sampling 'of fish, shoreline and bottom sediment and periphyton at station CL-105.
July, 1985 Instituted-sampling of vegetation at station CL-ll4.
July, 1985 Instituted sampling of vegetation at station CL-115. -
July, 1985 3- Instituted-sampling of milk at station CL-ll6.
A %
e l 92 i .
.. . -. . . - . . . . = . . .- -. ..
APPENDIX E (Cont'd)
_ l
' December, 1985 Instituted soil sampling at air sampling station CL-1, 2, 3, 4, 6, 7,
- .8 and 11.
i I
e l
.I I
i
)
4 I
i I
5 L
i I
I i
1 4
4 s
i j
I e :
)
. l
! l 1
93
. . _ _ . _ _ _ _ .._ ______.....___.__.._....=._.a_--_.__.__-.__,__,_.,.-...,_._.._._.._.._,
1 APPENDIX F 1985 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION AND ANALYSIS METHODS i
Approximate Teledyne Sample Sample Size Procedure Procedure Analysis Medium Sampling Method Collected Number Abstract Gross AP Continuous air sampling I filter Midwest Sample was counted on Beta through a filter paper (280m3 ) 2.1.1 a low-level gas flow proportional counter WW Grab sample monthly 1.5-2.0 kg Midwest Sample was evaporated 2.2.2 on a stainless steel planchette for low background gas flow proportional counting e
- ' Gamma AP Quarterly composite of 13 weeks Midwest Germanium gamma Spectro- each station (3640 m3 ) 3.1 isotopic analysis scopy 1
M Grab sample % lb in fall Midwest Germanium gamma
- (cut grass) 8 lb.in spring 1.1 isotopic analysis WW Grab sample monthly 1 gallon Midwest Germanium gamma i
3.1 isotopic analysis SW Grab sample monthly 1 gallon Midwest Germanium gamma 3.1 isotopic analysis j VE Grab sample annually 2.5 kg Midwest Germanium gamma i (at harvest time) per sample 3.1 isotopic analysis
] BS Grab sample semiannually 1.5-2.0 kg Midwest Germanium gamma 3.4 isotopic analysis i
1
APPENDIX F (Cont'd)
Approximate Teledyne Sample Sample Size Procedure Procedure Analysis Medium Sampling Method Collected Number Abstract SS Grab sample semi-annually 1.5-2.0 kg Midwest Germanium gamma 3.4 isotopic analysis SL Grab sample semi-annually 0.5 kg Midwest Germanium gamma
. 3.4 isotopic analysis F Grab sample semi-annually 2.5 kg Midwest Germanium gamma 3.5 isotopic analysis Tritium WW Grab sample monthly I gallon Midwest Water was purified by 3.8 distillation portion is transferred to e vial containing scintillation fluid.
Contents of vial are mixed and counted in a liquid scintillation counter I-131 M Grab sample Midwest Cut grass was dried, (cut grass) 1.1 then compacted into a four liter marinelli beaker. Sample is analyzed by a germanium gamma isotopic system TLD ID Dosimeters exchanged quarterly TLD Midwest Thermoluminescent 3.7 dosimetry
APPENDIX G DATA REPORTING CONVENTIONS 1.0 All activities are decay corrected to collection time, i
2.0 Single Measurements l
Each single measurement'is reported as follows:
x*s l where x = value of the measurement; s=2o counting uncertainty (corresponding to the 95%
confidence level).
In cases where the activity is found to be below the lower limit of detection (LLD) it is reported as less than the numerical value of the LLD as follows:
< LLD where LLD = is the numerical value of the lower limit of detection based on 4.66cuncertainty for s background sample. In Appendix A only, the letters "LLD" are substituted for the nunerical values which are listed in Column 3 of the Appendix A table.
3.0 Duplicate Analvses 3.1 Individual results:
xy
- sy x2 s2 Reported result: xis where x = (1/2) (xy + x2) s = (1/2) s 2+sf 3.2 Individual results: < LLD
< LLDf Reported result: < LLD where LLD = lower of LLDy and LLD2 a 3.3 Individual results: x1 i sy
< LLD 2 Reported result: x y i sy if x LLD 2
<LLD 2 therwise 96
APPENDIX G (continued) 4.0 Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations.
The average x and standard deviations of a set of n numbers-x1, s2' - *
- *n are defined as follows:
x=fIx n s= (*n- )2 n-1 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1 If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is ,
rounded off to 11.44.
- 4.5.2 If the figure following those to be retained is greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.446 is rounded off to 11.45.
4.5.3 If the figure following those to be retained is 5, and if there are not figures other than zeros'beyond the five, the figure 5 is dropped, and the last-place figure retained is increased by one if it is an odd number or it is kept unchanged if an even number. As an example, 11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42.
97 2 ,-, - - - - - , - vrw-w -- v-w r
APPENDIX G (continued)
The LLD is defined, for purposes of this report, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%
probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
4.66 sb L "
E V
2.22 Y
exp (- A A t )
Where:
LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit massor volume, is the standard deviation of the background sbuntingrateorofthecountingrateofablank c
sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picoeurie, Y is the fractional radiochemical yield, when applicable, A is the radioactiye decay constant for the partienlar radionuclide (sec ), and A t for environmental samples is the elapsed' time between sample collection, or end of the sample collection period, and time of counting (sec).
Typical values of E, V, Y, andA t should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
98
i l
l l
I l
l l
1 APPENDIX H Data Tables and Figures 99
LIST OF TABLES Page H-1 1985 Weekly Analysis of Airborne Particulates 102 for Gross Beta activity at CL-1 H-2 1985 Weekly Analysis of Airborne Particulates 103 for Gross Beta activity at CL-2 H-3 1985 Weekly Analysis of Airborne Particulates 104 for Gross Beta activity at CL-3.
H-4 1985 Weekly Analysis of Airborne Particulates 105 for Gross Beta activity at CL-4.
H-5 1985 Weekly Analysis of Airborne Particulates 106 for Gross Beta activity at CL-6.
H-6 1985 Weekly Analysis of Airborne Particulates 107 for Gross Beta activity at CL-7.
H-7 1985 Weekly Analysis of Airborne Particulates 108 for Gross Beta activity at CL-8.
H-8 1985 Weekly Analysis of Airborne Particulates 109 for Gross Beta activity at CL-ll.
H-9 1985 Quarterly Composites of Airborne 110 Particulates Analyzed for Gamma-Emitting Isotopes.
H-10 1985 Monthly Analysis of Surface Water for 121 Gamma-Emitting Isotopes at CL-9.
H-11 1985 Monthly Analysis of Surface Water 123 for Gamma-Emitting Isotopes at CL-10.
H-12 1985 Monthly Analysis of Surface Water 126 for Gamma-Emitting Isotopes at CL-13.
H-13 1985 Analysis of Drinking Water (CL-14) 128 for Gamma-Emitting Isotopes H-14 1985 Monthly Analysis of Drinking Water 130 (CL-14) for iodine-131 H-15 Monthly Analysis of Well Water for 131 Gross Beta and Gamma-Emitting Isotopes at CL-7 H-16 Monthly Analysis of Well Water for 133 Gross Beta and Gamma-Emitting Isotopes at CL-12
)
100
- + - . - .
l LIST OF TABLES Page H-17 1985 Analysis of Monthly Composite 135 of Intake Water (CL-92) for Gamma-Emitting Isotopes 2
H-18 1985 Analysis of monthly composite of 136 Effluent Water (CL-90) Gamma-Emitting Isotopes l H-19 Semiannual Analysis of Bottom Sediment 137 for Gamma-Emitting Isotopes and Stronrium-90 H-20 1985 Semi-Annual Analysis of Shoreline 139 Sediment for Gamma-Emitting Isotopes.
H-21 1985 Semiannual Analysis of Periphyton 141 for Gamma-Emitting Isotopes.
H-22 1985 Monthly (November-April) and Semimonthly 142 (May-October) Analysis of Milk at CL-ll6 for Gamma-Emitting Isotopes.
H-23 1985 Monthly (November-April)/ Semimonthly 144 (May-October) Analysis of Grass (in lieu of milk) for Gamma-Emitting Isotopes at CL-ll.
H-24 1985 Monthly (November-April)/ Semimonthly 146 (May-October) Analysis of Grass (in. lieu of milk) for Gamma-Emitting Isotopes at CL-15.
H-25 1985 Monthly (November-April)/ Semimonthly 148
- (May-October) Analysis of Grass (in lieu of
- milk) for Gamma-Emitting Isotopes at CL-16.
H-26 1985 Monthly (November-April)/ Semimonthly 150 (May-October) Analysis of Grass (in lieu of milk) for Gamma-Emitting Isotopes at CL-17.
H-27 1985 Monthly (during growing season) Analysis 152 of Green Leafy Vegetables for Iodine-131 and Gamma-Emitting Isotopes i
H-28 1985 Semiannual Gamma Isotopic Analysis of 156 fish from the Clinton Lake H-29 1985 Semiannual Gamma Isotopic Analysis of 157 fish from Lake Shelbyville H-30 1985 Analysis of Soil Samples for Gamma- 158 i Emitting Isotopes 4
101
_ _ _ . _ _ _ _ _ _ _ . _ . , , _ _ _ ___ . _ - _ _ _ . . . _ _ _ - . _ . , ~ ~ _ _
l Table H-1 1985 Weekly Analysis of Airborne Particulates for Gross Beta activity at CL-1 Date Volume Gross Beta Date Volume Gross Beta
. Collected (m ) (pCi/m ) Collected (m ) (pCi/m )
l 1-09-85 270 0.029 0.004 7-10-85 285 0.032i0.004 i 1-16-85 285 0.028*0.004 7-17-85 296 0.032*0.004 1-23-85 282 0.021i0.004 7-24-85 275 0.031*0.004 >
. 1-30-85 298 0.021*0.003 7-31-85 296 0.030i0.004 l 2-06-85 299 0.039 0.004 8-07-85 275 0.024*0.004 i 2-13-85 286 0.052*0.005 8-14-85 299 0.031 0.004 I
2-20-85 271 0.025*0.004 8-21-85 277 0.017*0.004 2-27-85 a 0.033 0.016 8-28-85 277 0.029t0.004 l
3-06-85 b -- 9-04-85 299 0.028i0.004
- 3-13-85 b -- 9-11-85 272 0.022i0.004 3-20-85 297 0.019i0.003 9-18-85 298 0.019 0.003 i 3-27-85 286 0.019i0.004 9-25-85 273 0.024*0.004
- 4-03-85 288 0.019*0.003 10-02-85 285 0.026*0.004 l 1st Qtr mean i s.d. 0.028 0.010 3rd Qtr mean i s.d. 0.027i0.005 4-10-85 289 0.022*0.004 10-09-85 294 0.028*0.004
, 4-17-85 283 0.029i0.004 10-16-85 282 0.024*0.004 1 4-24-85 272 0.028i0.004 10-23-85 27C 0.027*0.004 i 5-01-85 299 0.018i0.004 10-30-85 299 0.022*0.004 i 5-08-85 271 0.018i0.004 11-06-85 286 0.020i0.004 1
5-15-85 286 0.021 0.004 11-12-85 226 0.018*0.004
, 5-22-85 286 0.021*0.004 11-20-85 325 0.024*0.003 i 5-29-85 286 0.023i0.004 11-27-85 304 0.039 0.004- ,
i 6-05-85 285 0.017i0.003 12204-85 272 0.035*0.004 l 6-12-85 300 0.016i0.003 12-11-85 286 0.078i0.006 i j 6-19-85 278 0.021i0.004 12-18-85 310 0.050 0.005
- 6-26-85 277 0.024i0.004 12-24-85 257 0.035i0.004 l 7-03-85 285 0.023*0.003 1-01-86 322 0.020t0.003 i
- 2nd Qtr mean
- s.d. 0.022 0.004 4th Qtr mean i s.d. 0.032*0.016 j a low volume due to loss of electricity.
no data due to loss of electricity.
i 1
1 l
A
- 102
Table H-2 1985 Weekly Analysis of Airborne Particulates for Gross Beta activity at CL-2.
Date Volume Gross Beta Date Volume Gross Beta Collected (m ) (pCi/m ) Collected (m ) (pCi/m )
1-09-85 282 0.027 0.004 7-10-85 285 0.031 0.004 1-16-85 291 0.025*0.004 7-17-85 296 0.017 0.004 1-23-85 308 0.024 0.003 7-24-85 291 0.031i0.004 1-30-85 304 0.021 0.003 7-31-85 296 0.028 0.004 2-06-85 292 0.037 0.004 8-07-85 274 0.022 0.004 2-13-85 297 0.050 0.005 8-14-85 307 0.026*0.003 2-20-85 277 0.033 0.004 8-21-85 266 0.018i0.004 2-27-85 281 0.017 0.003 8-28-85 278 0.025 0.004 3-06-85 267 0.015 0.003 9-04-85 299 0.028i0.004 3-13-85 280 0.022 0.004 9-11-85 272 0.018 0.004 3-20-85 286 0.018t0.003 9-18-85 299 0.021*0.003 i 3-27-85 291 0.015i0.003 9-25-85 267 0.024 0.004 4-03-85 300 0.014 0.003 10-02-85 291 0.021 0.003 1st Qtr mean s.d. 0.024 0.010 3rd Qtr mean i s.d. 0.024*0.005 l 4-10-85 309 0.022*0.003 10-09-85 298 0.024 0.004 i 4-17-85 289 0.024 0.004 10-16-85 283 0.021*0.004 4-24-85 283 0.027 0.004 10-23-85 275 0.025t0.004 5-01-85 304 0.016 0.003 10-30-85 293 0.019i0.003 5-08-85 270 0.018i0.004 11-06-85 288 0.018t0.004 5-15-85 281 0.024*0.004 11-12-05 227 0.019 0.004
- 5-22-85 286 0.017 0.003 11-20-85 308 0.020 0.003 5-29-85 286 0.019t0.004 11-27-85 295 0.036i0.004 6-05-85 279 0.017i0.003 12-04-85 256 0.031 0.004 6-12-85 294 0.019 0.003 12-11-85 273 0.074 0.006 6-19-85 256 0.025 0.004 12-18-85 276 0.053*0.005 6-26-85 259 0.024 0.004 12-24-85 244 0.030i0.004 7-03-85 285 0.020 0.003 1-01-86 303 0.022 0.004 2nd Qtr mean s.d. 0.021 0.004 4th Qtr mean s.d. 0.030 0.016 l
103
Teble H-3 1985 Weekly Analysis of Airborne Particulates for Gross Beta activity at CL-3.
Date Volume Gross Beta Date Volume Gross Beta 1 Collected (m ) (pCi/m ) Collected (m ) (pCi/m )
1-09-85 270 0.031 0.004 7-10-85 285 0.030 0.004 1-16-85 285 0.027 0.004 7-17-85 296 a 0.033 0.004 1-23-85 280 0.030 0.004 7-24-85 105 0.070*0.010 1-30-85 297 0.024 0.004 7-31-85 b --
2-06-85 293 0.042 0.004 8-07-85 148c 0.024*0.007 2-13-85 286 0.060 0.005 8-14-85 307 0.028i0.004 2-20-85 277 0.028 0.004 8-21-85 266 0.015 0.004 2-27-85 286 0.014i0.003 8-28-85 278 d
0.025i0.004 3-06-85 273 0.021 0.004 9-04-85 299 d 0.031 0.004 3-13-85 285 0.023 0.004 9-11-85 272 0.020i0.004 3-20-85 298 0.019i0.003 9-18-85 292 0.020 0.003 3-27-85 291 0.021i0.004 9-25-85 273 0.026 0.004 4-03-85 282 0.018i0.003 10-02-85 286 0.024*0.004 1st Qtr mean s.d. 0.028*0.012 3rd Qtr mean s.d. 0.029i0.014 4-10-85 273 0.022 0.004 10-09-85 399 0.023i0.003 4-17-85 289 0.022 0.004 10-16-85 227 0.018 0.004 4-24-85 267 0.029i0.004 10-23-85 274 0.022t0.004
. 5-01-85 298 0.020t0.004 10-30-85 299 0.019i0.003 5-08-85 271 0.020 0.004 11-06-85 278 0.016 0.004 5-15-85 281 0.020 0.004 11-12-85 215 0.026i0.005 5-22-85 286 0.018 0.004 11-20-85 333 0.024*0.003 5-29-85 286 0.024 0.004 11-27-85 303 0.040 0.004 l 6-05-85 279 0.020 0.003 12-04-85 264 0.036i0.004 0.018 0.003 12-11-85 0.079i0.006 6-12-85 294 287 6-19-85 256 0.019i0.004 12-18-85 290 0.047i0.005 6-26-85 260 0.022i0.004 12-24-85 252 0.034*0.004 7-03-85 285 0.020t0.003 1-01-86 313 0.015*0.003 2nd Qtr taean
- s .d. 0.021 0.003 4th Qtr mean
- s.d. 0.031i0.018 I,
a low volume due to pump malfunction s pump ran for 122.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
no data due to loss of electricity at station.
jlowvolumeduetopumpmalfunction pump ran for 87.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
estimated volume since time meter was not working.
104
- Teble H-4 1985 Weekly Analysis of Airborne Particulates for Gross Beta activity at.CL-4.
3
+
Date Volume Gross Beta Date Volume Gross Beta Collected (m ) (pCi/m 3) Collected (m3 ) (pci/m 3) 1-09-85 270 0.022i0.004 7-10-85 280 0.030*0.004 1-16-85 286 0.026*0.004 7-17-85 302 0.033*0.004
- 1-23-85 280 0.028 0.004 7-24-85 264 0.033*0.004 1-30-85 298' O.027*0.004 7-31-85 295 0.026 0.004
, 2-06-85 293 0.036 0.004 8-07-85 281 0.025i0.004 2-13-85 286 0.053i0.005 8-14-85 307 0.027*0.003 2-20-85 282 0.032*0.004 8-21-85 272 0.020*0.004-l 2-27-85 280 0.018i0.003 8-28-85 277 0.028*0.004 3-06-85 273 0.020 0.004 9-04-85 304 0.031*0.004 3-13-85 285 0.028 0.004 9-11-85 261 0.020i0.004 3-20-85 304 0.020*0.003 9-18-85 292 0.024*0.004 3-27-85 280 0.019*0.004 9-25-85 284 0.023*0.004 4-03-85 288 0.016i0.003 10-02-85 288 0.024*0.004 1st Qtr mean s.d. 0.027 0.010 3rd Qtr mean
- s.d. 0.026t0.004 4-10-85 278 0.019i0.004 10-09-85 313 0.025 0.003
- 0.023 0.004 4
i 4-17-85 289 0.023i0.004 10-16-85 272
- 4-24-85 267 0.031i0.005 10-23-85 275 0.026*0.004 1 5-01-85 299 0.018i0.004 10-30-85 293 0.019i0.003 5-08-85 276 0.020i0.004 11-06-85 287 0.015*0.003 5-15-85 281 0.024 0.004 11-12-85 232 0.016i0.004 5-22-85 291 0.018i0.003 11-20-85 325 0.015*0.003 5-29-85 Z80 0.021 0.004. 11-27-85 ~301 0.036i0.004 4 6-05-85 285 0.019i0.003 12-04-85 263 0.034*0.004
- 6-12-85 307 0.016i0.003 12-11-85 288 0.078i0.006 1 6-19-85 278 0.021 0.004 12-18-85 289 0.043i0.004 i 6-26-85 266 0.017i0.004 12-24-85 260 0.038*0.004
! 7-03-85 280 0.020t0.003 1-01-86 315 0.020*0.003 2nd Qtr mean i s.d. 0.020*0.003 4th Qtr mean i s.d. 0.031*0.017 4
l l
10 5
Table H-5 1985 Weekly Analysis of Airborne Particulates for Gross Beta activity at CL-6.
Date Volume Gross Beta Date Volume Gross Beta Collected (m ) (pCi/m ) Collected (m ) (pCi/m )
1-09-85 270 0.027 0.004 7-10-85 297 0.022i0.003 1-16-85 286 0:025 0.004 7-17-85 312 0.026 0.004 1-23-85 291 0.027 0.004 7-24-85 276 0.028*0.004 1-30-85 297 0.027 0.004 7-31-85 302 0.026 0.004 2-06-85 293 0.036 0.004 8-07-85 275 0.024*0.004 2-13-85 291 0.055 0.005 8-14-85 313 0.026 0.003 2-20-85 282 0.033 0.004 8-21-85 277 0.018 0.004 2-27-85 292 0.018 0.003 8-28-85 283 0.026*0.004 3-06-85 273 0.020 0.004 9-04-85 303 0.031 0.004 3-13-85 285 0.027i0.004 9-11-85 272 0.021 0.004 3-20-85 297 0.019i0.003 9-18-85 310 0.010t0.003 3-27-85 286 0.018*0.004 9-25-85 278 0.023 0.004
- 4-03-85 288 0.020*0.003 10-02-85 297 0.026 0.004 1st Qtr mean s.d. 0.027 0.010 3rd Qtr mean
- s.d. 0.024*0.005 4-10-85 284 0.021 0.004 10-09-85 331 0.028i0.003 4-17-85 289 0.018 0.004 10-16-85 282 0.022 0.004 4-24-85 281 0.030*0.004 10-23-85 275 0.025*0.004 5-01-85 137 0.028 0.007 10-30-85 303 0.018*0.003 5-08-85 271 0.020i0.004 11-06-85 277 0.015 0.003 5-15-85 292 0.024i0.004 11-12-85 226 0.016 0.004 5-22-85 297 0.016 0.003 11-20-85 332 0.027 0.003 5-29-85 285 0.022i0.004, 11-27-85 302 0.036 0.004 6-05-85 285 0.020i0.003 12-04-85 266 0.037 0.004 6-12-85 313 0.018i0.003 12-11-85 282 0.073*0.006 6-19-85 278 0.017 0.003 12-18-85 294 0.045 0.004 6-26-85 277 0.020 0.004 12-24-85 256 0.038*0.004 7-03-85 297 0.024i0.003 1-01-86 312 0.020 0.003 2nd Qtr mean s.d. 0.021 0.004 4th Qtr mean s.d. 0.031 0.016 106
Table H-6 1985 Weekly Analysis of Airborne Particulatds for Gross Beta activity at CL-7.
Date Volume Gross Beta Date Volume Gross Beta Collected (m3 ) (pci/m 3) Collected (m3 ) (pci/m 3) 1-09-85 271 0.027 0.004 7-10-85 285 0.031i0.004 1-16-85 285 0.028i0.004 7-17-85 293 0.031i0.004 1-23-85 a -- 7-24-85 276 0.032i0.004 1-30-85 309 0.023*0.003 7-31-85 295 0.028i0.004 2-06-85 293 0.041 0.004 8-07-85 151c 0.032 0.007 2-13-85 286 0.056i0.005 8-14-85 319 0.026i0.003 2-20-85 276 0.034i0.004 8-21-85 270 0.018i0.004 2-27-85 295 0.017i0.003 8-28-85 284 0.028*0.004 3-06-85 273 0.018 0.004 9-04-85 298 0.034 0.004 3-13-85 291 0.029 0.004 9-11-85 272 0.021*0.004 3-20-85 303 0.017 0.003 9-18-85 304 0.021i0.003 3-27-85 286 0.022*0.004 9-25-85 273 0.025i0.004 4-03-85 288 0.019 0.003 10-02-85 280 0.026i0.004 1st Qtr mean s.d. 0.028 0.012 3rd Qtr mean s.d. 0.027*0.005 4-10-85 284 0.023 0.004 10-09-85 313 0.027 0.004 4-17-85 b --
10-16-85 286 0.019i0.003 4-24-85 b --
10-23-85 273 0.028 0.004 5-01-85 b --
10-30-85 311 0.025 0.004 5-08-85 271c 0.018 0.004 11-06-85 292 0.018 0.003 5-15-85 286 0.023i0.004 11-12-85 223 0.021i0.004 5-22-85 286 0.020 0.004 11-20-85 326 0.028 0.004 5-29-85 286 0.021i0.004 11-27-85 393 0.036t0.004 l 6-05-85 285 0.016i0.003 12-04-85 254 0.030i0.004 6-12-85 301 0.020i0.003 12-11-85 284 0.075 0.006 6-19-85 278 0.014i0.003 12-18-85 284 0.045 0.004 6-26-85 276 0.020i0.004 12-24-85 251 0.043i0.005
- 7-03-85 285 0.022 0.003 1-01-86 314 0.022 0.004 2nd Qtr mean t s.d. 0.020 0.003 4th Qtr mean
- s.d. 0.032*0.015 a
no data since sample was lost in the field.
no data due to loss of electricity.
c estimated volume since time meter was inoperable.
low volume due to pump malfunction.
107
Table H-7 1985 Weekly Analysis of Airborne Particulates for Gross Beta activity at CL-8.
Date Volume Gross Beta Date Volume Gross Beta 3
Collected (m3 ) (pCi/m 3) Collected (m ) (pci/m 3) 1-09-85 a --
7-10-85 288 0.024 0.004 1-16-85 a -- 7-17-85 177 b 0.027 0.005 1-23-85 a -- 7-24-85 108 b 0.052*0.009 1-30-85 a -- 7-31-85 296 0.026*0.004 2-06-85 a -- 8-07-85 275 0.023 0.004 2-13-85 a -- 8-14-85 307 0.026*0.003 2-20-85 282 0.031*0.004 8-21-85 276 0.015*0.004 2-27-85 271 0.018 0.003 8-28-85 278 0.020 0.004 3-06-85 275 0.021*0.004 9-04-85 292 0.028i0.004 3-13-85 297 0.016*0.004 9-11-85 267 0.021*0.004 3-20-85 309 0.015 0.003 9-18-85 298 0.021*0.003 3-27-85 303 0.020 0.004 9-25-85 273 0.023 0.004 4-03-85 288 0.018t0.003 10-02-85 291 0.023i0.004 1st Qtr mean
- s.d. 0.020i0.005 3rd Qtr mean i s.d. 0.025*0.009 4-10-85 301 0.022i0.004 10-09-85 309 0.025*0.004 4-17-85 289 0.024i0.004 10-16-85 285 0.021*0.004 4-24-85 294 0.030i0.004 10-23-85 274 0.020 0.004 5-01-85 311 0.018 0.004 10-30-85 299 0.019*0.003 5-08-85 276 0.015 0.004 11-06-85 282 0.016i0.003 5-15-85 292 0.026*0.004 11-12-85 228 0.020i0.004 5-22-85 291 0.018 0.004 11-20-85 321 0.024*0.003 5-29-85 302 0.026*0.004 11-27-85 292 0.037 0.004, 6-05-85 285 0.019 0.003 12-04-85 264 0.035i0.004 6-12-85 307 0.019*0.003 12-11-85 288 0.077i0.006 6-19-85 278 0.021*0.004 12-18-85 290 0.043 0.004 6-26-85 276 0.020t0.004 12-24-85 252 0.030 0.004 7-03-85 288 0.019i0.003 1-01-86 318 0.018t0.003 2nd Qtr mean
- s.d. 0.021i0.004 4th Qtr mean i s.d. 0.030i0.016 a no data due to loss of electricity.
low volume due to pump malfunction.
1 108
Table H-8 1985 Weekly Analysis of Airborne Particulates for Gross Beta I activity at CL-ll.
Date Volume Gross Beta Date Volume Gross Beta Collected (m3 ) (pci/m 3) Collected (m3 ) (pci/m 3) 1-09-85 282 0.026*0.004 7-10-85 297 0.027*0.004 1-16-85 314 0.021*0.003 7-17-85 306 0.031*0.004 -
1-23-85 285 0.016 0.003 7-24-85 260 0.027*0.004 1-30-85 309 0.015*0.003 7-31-85 307 0.028i0.004 2-06-85 293 0.039*0.004 8-07-85 270 0.018*0.004 2-13-85 291 0.052 0.005 8-14-85 307 0.024*0.003 2-20-85 282 0.025*0.004 8-21-85 282 0.016i0.004 2-27-85 286 0.016*0.003 8-28-85 284 0.024*0.004 3-06-85 280 0.019*0.004 9-04-85 304 0.028 0.004 3-13-85 291 0.024*0.004 9-11-85 278 0.020i0.004 3-20-85 309 0.018t0.003 9-18-85 310 0.023*0.003 3-27-85 292 0.022i0.004 9-25-85 278 0.023*0.004 4-03-85 300 0.018i0.003 10-02-85 297 0.022 0.003 1st Qtr mean i s.d. 0.024*0.010 3rd Qtr mean
- s.d. 0.024*0.004 4-10-85 290 0.022i0.004 10-09-85 313 0.028*0.004 4-17-85 289 0.021*0.004 10-16-85 300 0.024 0.004 4-24-85 283 0.030i0.004 10-23-85 271 0.023i0.004 5-01-85 310 0.024*0.004 10-30-85 305 0.023i0.004 5-08-85 281 0.019i0.004 11-06-85 301 0.018i0.003 5-15-85 292 0.025i0.004 11-12-85 224 0.015*0.004 5-22-85 298 0.018i0.003 11-20-85 333 0.023*0.003 5-29-85 291 0.025*0.004 11-27-85 305 0.041*0.004 6-05-85 297 0.022i0.003 12-04-85 265 0.034i0.004 6-12-85 306 0.020i0.003 12-11-85 288 0.072t0.006 6-19-85 279 0.018i0.004 12-18-85 288 0.043*0.004 6-26-85 276 0.022 0.004 12-24-85 258 0.034*0.004 7-03-85 297 0.017*0.003 1-01-86 320 0.024+0.004 2nd Qtr mean i s.d. 0.022*0.004 4th Qtr mean
- s.d. 0.031*0.015 109
Tcble H-9 1985 Quarterly Composites of Airborne Particulates Analyzed for Gamma-Emitting Isotopes Activity (pCi/m')
Location Isotope 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
b CLAP-1550 CLAP-1693 CL-1 Lab Code
- CLAP-1298 CLAP-1417 Volume (m ) 8 2907 3697 3430 3739 Be-7 < 0.031 <0.019 0.08010.009 0.060!0.009 Nb-95 < 0.0066 <0.0032 < 0.0017 < 0.0013 Zr-95 < 0.0063 <0.0046 < 0.0030 < 0.0024 Ru-103 < 0.0049 <0.0025 < 0.0019 < 0.0017 Ru-106 < 0.017 < 0. 014 < 0.011 < 0. 015 Cs-134 < 0.0019 <0.0015 < 0.0014 < 0.0014 Cs-137 < 0.0016 < 0.0017 < 0.0015 < 0.0014 Ce-141 < 0.0054 < 0.0024 < 0.0016 < 0.0019 Ce-144 < 0.0065 < 0.0054 < 0.0030 < 0.0053 CL-2 Lab Code CLAP-1299 CLAP-1418 CLAP-1551 CLAP-1694 8 3681 3438 3619 Volume (m ) 3756 Be-7 < 0.032 0.102 0.011 0.090 0.011 0.09010.011 Nb-95 < 0.0059 < 0.0021 <0.0019 < 0.0012 Zr-95 < 0.0061 < 0.0030 <0.0032 < 0.0029 Ru-103 < 0.0057 < 0.0021 <0.0018 < 0.0021 Ru-106 < 0.018 < 0.011 <0.010 < 0.0080 Cs-134 < 0.0020 < 0.0014 <0.0015 < 0.0015 Cs-137 < 0.0018 < 0.0011 <0.0013 < 0.0011 Ce-141 < 0.0053 < 0.0028 <0.0031 < 0.0026 Ce-144 < 0.0066 < 0.0067 <0.0067 < 0.0087 CL-3 Lab Code CLAP-1300 CLAP-1419 CLAP-1552 CLAP-1695 Volume (m8 ) 3703 3625 3168 3734 Be-7 0.06710.021 0.078 0.008 0.078 0.009 0.096 0.011 Nb-95 < 0.0041 < 0.0017 < 0.0019 < 0.0013 Zr-95 < 0.0044 < 0.0022 < 0.0030 < 0.0023 Ru-103 < 0.0030 < 0.0014 < 0.0018 < 0.0020 Ru-106 < 0.012 < 0.0098 < 0.014 < 0.014 Cs-134 < 0.0013 < 0.0011 < 0.0018 < 0.0016 Cs-137 < 0.0011 < 0.0012 < 0.0013 < 0.0014 Ce-141 < 0.0037 < 0.0014 < 0.0016 < 0.0013 -
Ce-144 < 0.0041 < 0.0026 < 0.0037 < 0.0048 110
1 Ttble H-9 (continued)
Activity (pC1/m 3)
Location Isotope 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
CL-4 Lab Code CLAP-1301 CLAP-1420 CLAP-1553 CLAP-1696 8 3705 3677 3460 3713 Volume (m )
Be-7 < 0.029 0.098 0.018 0.08710.015 0.061!0.008 ht-95 ( 0.0057 < 0.0017 < 0.0022 < 0.0021 Zr-95 < 0.0046 < 0.0036 < 0.0033 < 0.0026 Ru-103 < 0.0045 <0.0038 < 0.0020 <0.0020 Ru-106 < 0.0016 < 0.011 < 0.010 < 0.011 Cs-134 < 0.0018 <0.0014 < 0.0011 < 0.0017 Cs-137 < 0.0016 < 0. 0018 < 0.0014 < 0.0019 Ce-141 < 0.0050 <0.0024 < 0.0026 < 0.0020 Ce-144 < 0.0060 < 0.0075 < 0.0058 < 0.0048 CL-6 Lab Code CLAP-1302 CLAP-1421 CLAP-1554 CLAP-1697 8 3586 3533 3738 Volume (m ) 3731 Be-7 0.079!0.025 < 0.018 0.089 0.011 0.06810.008 Nb-95 < 0.0062 < 0.0034 <0.0017 < 0.0013 Zr-95 < 0.0058 < 0.0034 <0.0027 < 0.0019 Ru-103 < 0.0047 < 0.0025 <0.0019 < 0.0012 Ru-106 < 0.017 < 0.017 <0.013 < 0.0088 Cs-134 < 0.0028 < 0.0018 <0.0016 < 0.0011 Cs-137 < 0.0016 < 0.0020 <0.0011 < 0.0012 Ce-141 < 0.0054 < 0.0027 <0.0028 < 0.0020 Ce-144 < 0.0068 < 0.0060 <0.0065 < 0.0060 CL-7 Lab Code CLAP-1303 CLAP-1422 CLAP-1555 CLAP-1698 8 3714 Volume (m ) 3456 2915 3314 Be-7 < 0.026 0.099 0.018 0.08910.013 0.08410.009 Nb-95 <0.0059 < 0.0028 < 0.0023 < 0.0010 Zr-95 < 0.0056 < 0.0039 < 0.003? < 0.0016 Ru-103 <0.0046 < 0.0024 < 0.0019 < 0.0015 Ru-106 < 0.015 < 0.012 < 0.011 < 0.0092 Cs-134 < 0.0019 < 0.0015 < 0.0011 < 0.0010 Cs-137 < 0.0018 < 0.0017 <0.0012 < 0.00098 Ce-141 < 0.0052 < 0.0023 < 0.0024 < 0.00097 l Ce-144 < 0.0063 < 0.0054 < 0.0054 <'0.0034 111
Table H-9 (continued)
Activity (pC1/m 3 )
Location Isotope 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
CL-8 Lab Code" CLAP-1304 CLAP-1423 CLAP-1556 CLAP-1699 Volume (m8 ) 2025 3789 3189 3702 Be-7 0.09810.036 0.078 0.009 0.077!0.008 0.055!0.006 Nb-95 < 0.011 < 0.0014 < 0.0015 < 0.0012 Zr-95 < 0.0090 <0.0032 < 0.0033 < 0.0020 Ru-103 < 0.0079 <0.0014 < 0.0018 < 0.0012 Ru-106 < 0.024 <0.012 < 0.011 < 0.0091 Cs-134 < 0.0026 < 0.0014 < 0.0015 < 0.0010 Cs-137 < 0.0024 <0.0014 < 0.0012 < 0.0011 Ce-141 < 0.0092 < 0.0017 < 0.0015 < 0.0012 Ce-144 < 0.010 <0.0033 < 0.0035 < 0.0034 CL-11 Lab Code CLAP-1305 CLAP-1424 CLAP-1557 CLAP-1700 volume (m ) 8 3814 3790 3481 3771 Be-7 < 0.030 0.102 0.014 0.109 0.014 0.06410.010 Nb-95 < 0.0080 < 0.0022 < 0.0025 < 0.0017 Zr-95 < 0.0057 < 0.0027 < 0.0037 < 0.0028 Ru-103 < 0.0052 < 0.0023 < 0.0025 < 0.0017 Ru-106 < 0.013 < 0.015 < 0.016 < 0.0097 Cs-134 < 0.0017 < 0.0016 < 0.0019 < 0.0011 Cs-137 < 0.0017 < 0.0015 < 0.0013 < 0.0012 Ce-141 < 0.0051 < 0.0033 < 0.0041 < 0.0021 Ce-144 < 0.0056 < 0.0078 < 0.0082 < 0.0065 1ab code used by analyses laboratory for sample identification b
CLAP represents Clinton Power Station air particulate sample. Numerical designation is assigned by laboratory based upon sample receipt sequence I
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L Tcble H-10 1985 Monthly Analysis of Surface Water for Gamma-Emitting Isotopes at l' CL-9.
Sample Description and Concentration (pC1/1)
Dste collected 01-02-85 02-27-85 03-20-85 b c d Lab Code
- CLSW-56 CLSW-1074,5 Mn-54
< 15 -- < 15 Fa-59 < 30 -- < 30 l
i Co-58 < 15 -- < 15 Co-60 < 15 -- < 15 Zn-65 < 30 -- < 30 l Nb-95 < 15 -- < 15 Zr-95 < 15 -- < 15 C2-134 < 15 -- < 15 Ce-137 < 15 -- < 15 Ba-La-140 < 15 -- < 15 Date Collected 04-06-85 05-15-85 06-12-85 1 Lab Code CLSW-1280 CLSW-1754 CLSW-2136 Mn-54 < 15 < 15 < 15 Fa-59 < 30 <30 .< 30 Co-58 < 15 < 15 < 15 l Co-60 < 15 < 15 < 15 l Zn-65 < 30 <30 < 30 Nb-95 < 15 < 15 < 15 Zr-95 < 15 < 15 < 15
, Cs-134 < 15 < 15 < 15 i Cs-137 < 15 < 15 < 15 Bs-La-140 < 15 < 15 < 15 I
t l
l 121
I Tcble H-10 (continued)
Sample Description and Concentration (pCi/1)
Date Collected 07-17-85 08-14-85 09-04-85 Lcb Code CLSW-2659,60 CLSW-3016 CLSW-3270 B2-7 < 16 < 20 < 19
< 5 < 5 kb-54 < 5 Fa-59 < 12 < 12 < 12
< 5 < 5 Co-58 < 5
< 5 < 5 Co-6C < 5
< a < 6 Zn-65 < 6 ht-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10
< 5 < 5 < 5 Ce-134
< 5 < 5 < 5 Cs-137 Ba-140 < 60 < 60 < 60 Ls-140 < 15 < 15 < 15 i C1-144 < 30 < 30 < 30 Date Collected 10-09-85 11-27-85 12-24-85 Lab Code CLSW-3821,2 CLSW-4441 CLSW-4848 Ba-7 < 16 < 23 < 18 Hn-54 < 5 < 5 < 5 Fa-59 < 12 < 12 < 12 Co-58 < 5 <- 5 < 5 Co-60 < 5 < 5 < 5 Zn-65 6 < 6 < 6 Nb-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 Ca-134 < 5 < 5 < 5 Cs-137 < 5 < 5 < 5 j
Bs-140 < 60 < 60 < 60 L:-140 < 15 < 15 < 15 Ca-144 < 30 <> 30 < 30 1ab code used by analyses laboratory for sample identification CLSW represents Clinton surface water sample. Numerical designation is assigned by laboratory based upon receipt sequence.
sample not received, carton damaged in shipment and contents discarded by UPS.
d represents duplicate analyses performed on the sample by the laboratory.
I I
122
Tcble H-11 1985 Monthly Analysis of Surface Water for Gamma-Emitting Isotopes at CL-10.
Sample Description and Concentration (pCi/1) i Date Collected 01-02-85 02-27-85 03-20-85 Lab Code
- CLSW-57 CLSW-694 CLSW-1076 Mn-54 < 15 < 15 < 15 Fc-59 < 30 < 30 < 30 co-58 < 15 < 15 < 15 Co-60 < 15 < 15 < 15 Zn-65 < 30 < 30 < 30 Nb-95 < 15 < 15 < 15 Zr-95 < 15 < 15 < 15 Ca-134 < 15 < 15 < 15 Cs-137 < 15 < 15 < 15 BI-La-140 < 15 < 15 < 15 Date Collected 04-06-85 05-15-85 06-12-85 Lab Code CLSW-1281 CLSW-1755 CLSW-2137 Mn-54 < 15 < 15 < 15 Fs-59 < 30 < 30 < 30 Co-58 < 15 < 15 < 15 Co-60 < 15 < 15 < 15 Zn-65 < 30 < 30 < 30 Nb-95 < 15 < 15 < 15 Zr-95 < 15 < 15 < 15 Cs-134 < 15 < 15 < 15 Ce-137 < 15 < 15 < 15 Bt-La-140 < 15 < 15 < 15 l
4 t
i l
t i
123 '
. ._ . . ~. . . . _ . ,
I I
l Table'H-11 (continued)
Sample Description and Concentration (pC1/1)
Date Collected 07-17-85 08-14-85 09-04-85 Lab Code CLSW-2661 CLSW-3017 CLSW-3271 Be-7 < 24 < 15 < 23
, Mn-54 < 5 < 5 < 5 Fe-59 < 12 < 12 < 12 Co-58 < 5 < 5 < 5 Co-60 < 5 < 5 < 5
- Zn-65 < 6 < 6 < 6 Nb-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 Cs-134 < 5 < 5 < 5 Cs-137 < 5 < 5 < 5 Ba-140 < 60 < 60 < 60 La-140 < 15 < 15 < 15 Ce-144
< 30 < 30 < 30 l
Y I
I
! 124
Table H-11 (continued)
Sample Description and Concentration (pC1/1)
Date Collected 10-09-65 11-27-85 12-24-85 Lab Code CLSW-3823 CLSW-4442 CLSW-4849 Be-7 < 25 < 23 < 23 MM-54 < 5 < 5 < 5 Fe-59 < 12 < 12 < 12 Co-58 < 5 < 5 < 5 Co-60 < 5 < 5 < 5 Zn-65 < 6 < 6 < .6 Nb-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 j Cs-134 < 5 < 5 < 5 !
Cs-137 < 5 < 5 < 5 Ba-140 < 60 < 60 < 60 La-140 < 15 < 15 < 15 Ce-144 < 30 < 30 < 30 i 1ab code used by analyses laboratory for sample identification b
CLSW represents Clinton surface water sample. Numerical designation is assigned by laboratory based upon receipt sequence i
l l
l 4
1 i
125
Tcble H-12 1985 Monthly Analysis of Surface Water for Gamma-Emitting Isotopes at CL-13.
Sample Description and Concentration (pC1/1)
Date Collected 01-02-85 02-27-85 03-20-85 Lab Code
- CLSW-58 CLSW-1077 Mn-54 < 15 -- < 15 Fa-59 < 33 -- < 30 Co-58 < 15 -- < 15 Co-60 < 15 - < 15 Zn-65 < 30 -- < 30 ht-95 < 15 -- < 15 Zr-95 < 15 -- < 15 Cs-134 < 15 -- < 15 Ca-137 < 15 -- < 15 Bt-La-140 < 15 -- < 15 Date Collected 04-06-85 05-15-85 06-12-85 Lab Code CLSW-1282 CLSW-1756,7 CLSW-2138,9 Mn-54 < 15 < 15 < 15 Fa-59 < 30 < 30 < 30 Co-58 < 15 < 15 < 15 Co-60 < 15 < 15 < 15 Zn-65 < 30 < 30 < 30 Nb-95 < 15 < 15 < 15 Zr-95 < 15 < 15 < 15 Cs-134 < 15 < 15 < 15 Ca-137 < 15 < 15 < 15 Be-La-140 < 15 < 15 < 15 126
. - , . - - - - .... - . - . . ~ . -. .-
l i Table H-12 (continued)
Sample Description and Concentration (pC1/1)
Date Collected 07-17-85 08-14-85 09-04-85 Lab Code CLSW-2662 CLSW-3018 CLSW-3272 Be-7 < 16 < 22 < 16 Mn-54 <5 < 5 < 5 Fs-59 < 12 < 12 < 12 Co-58 < 5 < 5 < 5 Co-60 < 5 < 5 < 5 Zn-65 < 6 < 6 < 6 Nb-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 Ca-134 < 5 < 5 < 5 Ca-137 < 5 < 5 < 5 Ba-140 < 60 < 60 < 60 La-140 < 15 < 15 < 15 Cs-144 < 30 < 30 < 30
___ Date Collected 10-09-85 11-27-85 12-24-85 Lab Code CLSW-3824 CLSW-4443,4 CLSW-4850 Be-7 < 25 < 27 < 13 Mn-54 < 5 5 5 Fe-59 < 12 < 12 < 12
< 5 < 5 < 5 Co-58 Co-60 < 5 5 5
< 6 < 6 < 6 Zn-65 Nb-95 < 10 < 10 < 10 l Zr-95 < 10 < 10 < 10 )
Cs-134 < 5 5 5
< 5 < 5 < 5 Cs-137 Ba-140 < 60 < 60 < 60 L2-140 < 15 < 15 < 15 Cc-144 < 30 < 30 < 30 l
8 lab code used by analyses laboratory for sample identification CLSW represents Clinton surface water sample. Numerical designation is assigned by laboratory based upon receipt sequence.
l sample not received, carton damaged in shipment and contents discarded by UPS l
l l
l i
'127
~Tcble H-13 1985 Analysis of Drinking Water (CL-14) for Gamma-Emitting Isotopes Sample Description.and Concentration (pCi/1) j Month Collected April May" June" C CLDW-2448 Lab Code CLDW-1717 CLDW-2104 Mn-54 < 15 < 15 < 15 Fe-59 < 30 < 30 < 30 Co-58 < 15 < 15 < 15 Co-60 < 15 < 15 < 15 Zn-65 < 30 < 30 < 30 Nb-95 < 15 < 15 < 15 Zr-95 < 15 < 15 < 15 Cs-134 < 15 < 15 < 15 Cs-137 < 15 < 15 < 15 Ba-La-140 < 15 < 15 < 15 Month Collected July" August
- September
- Lab Code CLDW-2803 CLDW-3281 CLDW-3742 Be-7 ._.
< .27 < 18 < 24 l Mn-54 < 5 < 5 < 5
. Fe-59 < 12 < 12 < 12
, Co-58 < 5 < 5 < 5 Co-60 < 5 < 5 < 5 Zn-65 < 6 < 6 < 6 .
! Nb-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 i
Cs-134 < 5 < 5 < 5 Cs-137 < 5 <.5 < 5 Ba-140 < 60 < 60 < 60 j La-140 < 15 < 15 < 15 Ce-144 < 30 < 30 < 30 J
4 i
128
_ _ _ _ _ . _ _ . ____. _ _ _ . - . _ . . . - . _ . _ . _ . _ _ _ _ - . _ _ _ _ _ . . . . . _ . . ~. . - _ _ . _
Table H-13 (continued) 1 1
-Sample Description and Concentration (pCi/1) a Month Collected October November" December
- Lab Code CLDW-4027 CLDW-4369 CLDW-4903
- Be-7 < 24 < 22 < 22 Mn-54 < 5 < 5 < 5 Fe-59 < 12 < 12 < 12 Co-58 < 5 < 5 < 5 Co-60 < 5 < 5 < 5 Zn-65 < 6 < 6 < 6 Nt-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 Cs-134 < 5 < 5 < 5 Cs-137 ,
< 5 < 5 < 5 Ba-140 < 60 < 60 < 60 La-140 < 15 < 15 < 15 Ce-144 < 30 < 30 < 30
~~
composite sample lab code used by analysis laboratory for sample identification.
d CLDW represents Clinton Power Station drinking water sample. Numerical designation is assigned by laboratory based upon receipt sequence.
+
129
, . . , - . - . -- ..m v _, , - . - . . . - - _ . - ..y..
s Table H-14 1985 Monthly Analysis of Drinking Water (CL-14) for iodine-131 (pCi/1)"
Collection Date Lab Code I-131 04-02-85 CLDW-1223,4 ** < 0.5 c
1- 04-30-85 CLDW-1586 < 0.5 b < 0.5 05-31-85 CLDW-2104 D < 0.5 06-30-85 CLDW-2448 b
07-31-85 CLDW-2803 < 0.5 b
08-30-85 CLDW-3281 < 0.5 b
09-30-85 CLDW-3742 < 0.5 b
10-23-85 CLDW-4027 < 0.5 b
11-26-85 CLDW-4369 < 0.5 b
12-31-85 CLDW-4903 < 0.5 __
l l explanations of the data reporting commentions are given in Appendix G.
b grab sample e
composite sample d
lab code used by analysis laboratory for sample identification. CLDW represents Clinton Power Station drinking water sample. Numerical designation is assigned by laboratory based upon sample receipt sequence.
represents duplicate analysis performed on the sample by the laboratory.
i l
l l
130
Table H-15 Monthly Analysis of Well Water for Gross Beta and Gamma-Emitting Isotopes at CL-7.
Sample Description and Concentration (pC1/1)
Date Collected 01-02-85 02-27-85 03-20-85 l
Lab Code CLW-45 CLW-1078 l
l Mn-54 < 15 --
< 15 l Fe-59 < 30 --
< 30 Co-58 < 15 --
< 15 Co-60 < 15 --
< 15 Zn-65 < 30 --
< 30 Nb-95 < 15 --
< 15 Zr-95 < 15 --
< 15 Cs-134 < 15 --
< 15 Cs-137 < 15 --
< 15 Ba-La-140 < 15 --
< 15 Date Collected 04-06-85 05-15-85 06-12-85 Lab Code CLW-1283 CLW-1758 CLW-2140 _
Mn-54 < 15 < 15 < 15 Fe-59 < 30 < 30 < 30 Co-58 < 15 < 15 < 15 Co-60 < 15 < 15 < 15 l
Zn-65 < 30 < 30 < 30 Nb-95 < 15 < 15 < 15 l Zr-95 < 15 < 15 < 15 Cs-134 < 15 < 15 < 15 Cs-137 < 15 < 15 < 15 Ba-La-140 < 15 < 15 < 15 131
Tcble H-15 (continued)
Sample Description and Concentration (pC1/1) l D te Collected 07-17-85 08-14-85 09-04-85 l Lib Code CLW-2663 CLW-3019 CLW-3273
)
I B2-7 < 21 < 15 < 23 Nh-54 < 5 < 5 < 15 Fe-59 < 12 < 12 < 12 Co-58 < 5 < 5 < 5 Co-60 < 5 < 5 < 5 Zn-65 < 6 < 6 < 6 Nb-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 Cs-134 < 5 < 5 < 5 Cs-137 < 5 < 5 < 5 Ba-140 < 60 < 60 < 60 La-140 < 15 < 15 < 15 Ce-144 < 30 < 30 < 30 Date Collected 10-09-85 11-27-85 12-24-85 Lab Code CLW-3820 CLW-4445 CLW-4851 Be-7 < 16 < 20 < 22 Mn-54 < 5 < 5 < 5 l Fe-59 < 12 < 12 < 12 Co-58 < 5 < 5 < 5 Co-60 < 5 < 5 < 5 Zn-65 < 6 < 6 < 6 Nb-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 Cs-134 < 5 < 5 < 5 Cs-137 < 5 < 5 < 5 Ba-140 < 60 < 60 < 60 La-140 < 15 < 15 < 15 Ce-144 < 30 < 30 < 30 lab code used by analysis laboratory for sample identification.
b CLWL represents Clinton well water sample. Numerical designation is assigned by laboratory based upon receipt sequence.
132 l
Table H-16 Monthly Analysis of Well Water for Gamma-Emitting Isotopes at CL-12 I
1 Sample Description and Concentration (pC1/1)
Date Collected 01-02-85 02-27-85 03-20-85 b c Lab Code
- CLW-59 CLW-1079 l
Mn-54 < 15 --
< 15 Fe-59 < 30 --
< 30 Co-58 < 15 --
< 15 Co-60 < 15 --
< 15 Zn-65 < 30 --
< 30 Nb-95 < 15 --
< 15 Zr-95 < 15 --
< 15
< 15 Cs-134 Cs-137 < 15 15 15 (
Ba-La-140 < 15 --
< 15 Date Collected 04-06-85 05-15-85 06-12-85 Lab Code CLW-1284,5 CLW-1759 CLW-2141 Mn-54 < 15 < 15 < 15 Fe-59 < 30 < 30 < 30 Co-58 < 15 < 15 < 15 Co-60 < 15 < 15 < 15 Zn-65 < 30 < 30 < 30 Nb-95 < 15 < 15 < 15 Zr-95 < 15 < 15 < 15 Cs-134 < 15 < 15 < 15 Cs-137 < 15 < 15 < 15 Ba-La-140 -
< 15 < 15 < 15 133
Table H-16 (continued)
Sample Description and Concentration (pC1/1)
Date Collected 07-17-85 b 08-14-85 09-28-85 c
Lab Code" CLW-2664 CLW-3741 Be-7 < 25 --
< 27 Fb-54 < 5 -- < 5 Fe-59 < 12 --
< 12 Co-58 < 5 -- < 5 Co-60 < 5 -- < 5 Zn-65 < 6 -- < 6 Nb-95 < 10 -- < 10 Zr-95 < 10 --
< 10 Cs-134 < 5 -- < 5 Cs-137 < 5 --
< 5 Ba-140 < 60 -- < 60 La-140 < 15 --
< 15 Ce-144 < 30 --
< 30 Date Collected 10-31-85 11-26-85 Lab Code CLW-4134 CLW-4367,8 Be-7 < 24 < 20 Mn-54 < 5 < 5 Fe-59 < 12 < 12 Co-58 < 5 < 5 Co-60 < 5 < 5 Zn-65 < 6 < 6 Nb-95 < 10 < 10 Zr-95 < 10 < 10 Cs-134 < 5 < 5 Cs-137 < 5 < 5 Ba-140 < 60 -
< 60 La-140 < 15 < 15 Ce-144 < 30 < 30 a
lab code used by analysis laboratory for sample identification.
b CLW represents Clinton well water sample. Numerical designation is assigned by laboratory based upon receipt sequence.
no sample; sample unavailable to collector when municipality changed locks to sampling location without notifying CPS Radiation Protection.
134 L -
Ttble H-17 1985 Analysis of Monthly' Composite of Intake Water (CL-92) for Gamma-Emitting Isotopes Sample Description and Concentration (pC1/1)
Collection Period June July August September 1
Lab Code
- CLSW-2465 CLSW-2794- CLSW-3283 CLSW-3744 Be-7 < 43 < 25 < 17 < 28 Mn-54 < 5 < 5 < 5 < 5 Fe-59 < 15 < 12 < 12 < 12 Co-58 < 5 < 5 < 5 < 5 Co-60 < 5 < 5 < 5 < 5 Zn-65 < 12 < 6 < 6 < 6 Nb-95 < 10 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 < 10 Cs-134 < 5 < 5 < 5 < 5 Cs-137 < 5 < 5 < 5 < 5 Ba-140 < 60 < 60 < 60 < 60 La-140 < 15 < 15 < 15 < 15 Ce-144 < 31 < 30 < 30 < 30 Collection Period October November December Lab Code CLSW-4029 CLSW-4366 CLSW-4902 Be-7 < 21 < 11 < 20 Mn-54 < 5 < 5 <5 Fe-59 < 12 < 12 <12 Co-58 < 5 < 5 <5 Co-60 < 5 < 5 <5 Zn-65 < 6 < 6 <6 Nb-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 Cs-134 < 5 < 5 <5 j Cs-137 < 5 < 5 <5
! Ba-140 < 60 < 60 < 60 La-140 < 15 < 15 < 15 Ce-144 < ,30 < 30 < 30 l
lab code used by analysis laboratory for sample identification i
l l
135
I Table H-18 1985 Analysis of monthly composite of Effluent Water (CL-90) Ganna Emitting Isotopes Sample Description and Concentration (pCi/1)
Collection Period June July August September Lab Code
- CLSW-2464 CLSW-2802 CLSW-3283 CLSW-3743 Be-7 < 39 < 19 < 17 < 15 kb-54 < 5 < 5 < 5 < 5 f Fe-59 < 12 < 12 < 12 < 12 Co-58 < 5 < 5 < 5 < 5 Co-60 < 5 < 5 < 5 < 5 Zn-65 < 9 < 6 < 6 < 6 Nb-95 < 10 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 < 10 Cs-134 < 5 < 5 < 5 < 5 Cs-137 < 5 < 5 < 5 < 5 Ba-140 < 60 < 60 < 60 < 60 La-140 < 15 < 15 < 15 < 15 Ce-144 < 32 < 30 < 30 < 30 Collection Period October November December Lab Code CLSW-4028 CLSW-4365 CLSW-4901 Be-7 < 18 < 16 < 14 Mn-54 < 5 < 5 < 5 Fe-59 < 12 < 12 < 12 Co-58 < 5 < 5 < 5 Co-60 < 5 < 5 < 5 Zn-65 < 6 < 6 < 6 Nb-95 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 l Cs-134 < 5 < 5 < 5 - #l Cs-137 < 5 < 5 < 5 Ba-140 < 60 < 60 < 60 La-140 < 15 < 15 < 15 Ce-144 < 30 ,
< 30 < 30 1ab code used by analysis laboratory for sample identification 136
Table H-19 Semiannual Analysis of Ect. tom Sediment for Gamma-Emitting Isotopes and Stronium -90 Sample Description and Concentration (pCi/g dry)
(
! Location CL-7c CL-10 CL-13 CL-19 Lab Code
- CLES-434,5 CLBS-436 CLBS-437 CLBS-438 Date Collected 06-10-85 06-10-85 06-10-85 06-10-85 Be-7 < 0.88 < 0. 74 < 0.52 < 0. 62 K-40 15.2410.16 16.56!0.20 14.1110.17 17.2010.77 Mn-54 < 0.028 < 0.025 < 0.019 <0.019 Fe-59 < 0.36 < 0.39 < 0.31 <0.28 Co-58 < 0.068 < 0.066 < 0.050 < 0.051 Co-60 < 0.019 < 0.019 < 0.014 < 0.016 Zn-65 < 0.064 < 0.066 < 0.054 < 0.064 Nb-95 < 0.098 < 0.088 < 0.064 < 0.22 Zr-95 < 0.15 < 0.14 < 0.11 < 0.11 Cs-134 < 0.029 < 0.027 < 0.020 < 0.021 Cs-137 0.3220.01 0.5810.01 0.03!0.01 0.16!0.01 Ba-140 < 119. 30 < 109.60 < 82.00 < 94.30 La-140 < 33.5 < 26.8 < 21. 2 < 32.0 Ce-144 < 0.17 < 0.12 < 0.082 < 0.12 Location CL-89 CL-105 Lab Code CLBS-439 CLBS-441 Date Collected 06-10-85 06-17-85 Be-7 < 0.32 < 0.20 K-40 9.42 0.13 16.70!0.56 Mn-54 < 0.013 < 0.008 l Fe-59 < 0.15 < 0.078 '
Co-58 < 0.028 < 0.018 Co-60 < 0.010 < 0.007 Zn-65 < 0.032 < 0.026
- Nb-95 < 0.039 < 0.056 Zr-95 < 0.060 < 0.038 I Cs-134 < 0.015 < 0. 010 l r Cs-137 0.05 0.01 0.4810.01 !
Ba-140 < 15.16 < 8.40 La-140 < 3.70 < 2.65 Ce-144 < 0.081 < 0.060 137
Ttble H-19 (continued)
Sample Description and Concentration (pCi/g dry)
Location CL-7c CL-10 CL-13 CL-19 Lab Code
- CLBS-500 CLBS-501 CLBS-502.3 CLBS-504 Date Collected 10-07-85 10-07-85 10-07-85 10-07-85 Sr-90 0.033 0.006 0.05620.009 e 0.04320.006 Be-7 < 0.18 < 0.24 < 0.37 < 0.15 K-40 15.00!0.44 15.90 0.45 8.67 0.56 15.2010.41 Mn-54 < 0.016 < 0.017 < 0.028 < 0.014 Fe-59 < 0.078 < 0.080 < 0.11 < 0.065 Co-58 < 0.023 < 0.025 < 0.040 < 0.019 Co-60 < 0.021 < 0.021 < 0.028 < 0. 014 Zn-65 < 0.056 < 0.049 < 0.064 < 0.048 Nb-95 < 0.042 < 0.045 < 0.069 < 0.034 Zr-95 < 0.043 < 0.049 < 0.076 < 0.036 Cs-134 < 0.021 < 0.021 < 0.025 < 0.017 Cs-137 0.33 0.02 0.6210.02 < 0.024 0.49i0.02 Ba-140 < 0.86 < 1.00 < 1.68 < 0.67 La-140 < 0.30 < 0. 27 < 0.41 < 0.23 Ce-144 < 0.076 < 0.11 < 0.19 < 0.066 Location CL-89 CL-105 Lab Code CLBS-505 CLBS-506 Date Collected 10-07-85 10-08-85 i Sr-90 0.011 0.004 c Be-7 0.67 0.13 < 0.26 K-40 15.3020.43 20.62 0.22 Mn-54 < 0.016 < 0.022 Fe-59 < 0.072 < 0.084 Co-58 < 0.022 < 0.026 Co-60 < 0.015 < 0.018 Zn-65 < 0.047 < 0.050 Nb-95 < 0.040 < 0.032 Zr-95 < 0.045 < 0.054 Cs-134 < 0.020 < 0.027 Cs-137 0.21!0.01 0.52 0.01 Be-140 < 0.80 < 0.54 La-140 < 0.22 < 0.11 Ce-144 < 0.095 < 0.14 lab code user by analysis laboratory for sample identification.
b CLBS represents Clinton bottom sediment sample. Numerical designation is c
assigned by laboratory based upon receipt sequence.
planned expansion of monitoring program included Sr-90 analyses to be performed only at Stations CL-7C, CL-10, CL-19 and CL-89.
138
l Table H-20 1985 Semi-Annual Analysis of Shoreline Sediment for Gamma-Emitting Isotopes Sample Description and Concentration (pC1/g dry)
Location CL-7b CL-7d CL-10 'CL-19 Lab Code" b CLSS-428 CLSS-429 CLSS-430 CLSS-431 Date Collected 06-10-85 06-10-85 06-10-85 06-10-85 Be-7 < 0.11 < 0.22 < 0.30 < 0.24 K-40 6.62!0.28 6.33 0.95 7.89!0.29 8.47!0.10 Mn-54 < 0.0044 < 0.0095 < 0.014 < 0.0095 Fe-59 <
< 0.049 0.11 < 0.15 < 0.11 Co-58 < 0.010 0.022 < 0.029 < 0.022 Co-60 < 0.0038 < 0.0074 < 0.012 < - 0.0078 Zn-65 < 0.015 < <
0.024 0.044 < 0.030 Nb-95 < 0.034 0.027 < 0.096 < 0.027 Zr-95 < 0.021 < <
0.042 0.060 < 0.043 Cs-134 < 0.0047 < 0.010 < 0.014 < 0.0094 Cs-137 < 0.0034 < 0.0076 < 0.011 < 0.0078 Ba-140 < 6.13 < 11. 22 < 15.10 < 11.67 La-140 < 1.85 < 2.76 < 3.84 < 2.30 Ce-144 < 0.030 < 0.058 < 0.078 < 0.062 Location CL-88 CL-89 CL-105 Lab Code CLSS-432 CLSS-433 CLSS-440 Date Collected 06-10-85 06-10-85 06-17-85 Be-7 < 0.15 < 0.30 < 0.13 K-60 6.26!0.06 6.93!0.11 7.94 0.06 Mn-54 < 0.0064 < 0.011 < 0.0064 Fe-59 < 0.071 < 0.14 < 0.0072 Co-58 < 0.013 < 0.026 < 0.013 Co-60 < 0.005 < 0. 008 < 0.0056 Zn-65 < 0.016 < 0.029 < 0.018 Nb-95 < 0.018 < 0.034 < 0.016 i Zr-95 < 0.029 < 0.056 < 0.027 Cs-134 < 0.0065 < 0.012 < 0.0067 Cs-137 < 0.005 < 0.020 < 0.0050 Ba-140 < 7.89 < 0. 21 < 5.04 La-140 < 2.02 < 5. 41 < 1.30 Ce-144 < 0.038 < 0.068 < 0.028 139
Tsble H-20 (continued)
Sample Description and Concentration (pCi/g dry)
)
CL-7b CL-7d .# CL-10 CL-19 Location Lab Code CLSS-493 CLSS-494 CLSS-495 CLSS-496 Date Collected 10-07-85 10-07-85 10-07-85 10-07-85 Ba-7 < 1.078 < 0.075 <<0.71 < 0.087 i K-40 7.3020.22 7.58 0.22 7.54!0.21 7.39!0.11
) Mn-54 < 0.008 < 0.008 < 0.007 < 0.009 Fe-59 < 0.031 <0.032 < 0.003 < 0.042 Co-58 < 0.010 < 0.009 < 0.009 < 0.012 Co-60 < 0.007 < 0.007 < 0.009 < 0.009
) < 0.022 < 0.020 < 0.025 I Zn-65 < 0.022 i
Nb-95 < 0.015 < 0.014 < 0.014 < 0.013 Zr-95 < 0.018 < 0.018 < 0.017 < 0.021 Cs-134 < 0.008 < 0.008 < 0.007 < 0.010 Cs-137 < 0.007 < 0.007 < 0.006 < 0.008 Ba-140 < 0.20 < 0.19 < 0.25 <0.19 La-140 < 0.047 < 0.041 < 0.042 < 0.048 Ce-144 < 0.043 < 0.042 < 0.038 < 0.036 Location CL-88 CL-89 CL-105 Lab Code CLSS-497 CLSS-498 CLSS-499 Date Collected 10-07-85 10-07-85 10-08-85 Be-7 < 0.12 < 0.14 < 0.095 K-40 9.3020.11 9.3920.15 8.10!0.23 Mn-54 < 0.010 < 0.014 < 0.009 Fe-59 < 0.042 < 0.062 < 0.036 Co-58 < 0.013 < 0.016 < 0.012 Co-60 < 0.009 < 0.012 < 0.008 Zn-65 < 0.026 < 0.036 < 0.025 hl-95 < 0.015 < 0.020 < 0.018 Zr-95 < 0.025 < 0.034 < 0.023 Cs-134 < 0.012 < 0.016 < 0.008 Cs-137 < 0.070 0.04 0.01 < 0.008 Ba-140 < 0.25 < 0. 3 2 < 0.23 l La-140 < 0.047 < 0.089 < 0.043 Ce-144 < 0.064 < 0.056 < 0.062 l
1ab code used by analysis laboratory for sample identification.
b CLSS represents Clinton shoreline sediment samples. Numerical designation is assigned by laboratory based upon receipt sequence.
140
Table H-21 1985 Semiannual Analysis of Periphyton for Gamma-Emitting Isotopes.
Sample Description and Activity (pCi/g wet)
Location CL-7C CL-10 CL-19 CL-105 Lab Code" CLSL-193 CLSL-194 CLSL-195 CLSL-198,9b ,c Date Collected 06-10-85 06-10-85 06-10-85 06-17-85 Be-7 < 1.31 < 0.65 < 0.74 1.66 0.13 K-40 3.21 0.20 6.82 0.54 6.2610.67 3.2710.14 Mn-54 < 0.033 < 0.082 < 0.098 < 0.030 j Fe-59 < 0.078 < 0.22 < 0.24 < 0.065 Co-58 < 0.036 < 0.094 < 0.10 < 0.031 Co-60 < 0.033 < 0.096 < 0.11 < 0.030 Zn-65 < 0.065 < 0.18 < 0.18 < 0.064 Nb-95 < 0.036 < 0.098 < 0.11 < 0.032 Zr-95 < 0.060 < 0.16 < 0.19 < 0.056 Cs-134 < 0.035 < 0.095 < 0.10 < 0.032 Cs-137 < 0.030 < 0.082 < 0.081 < 0.063 Ba-140 < 0.20 < 0.60 < 0.57 < 0.026 La-140 < 0.090 < 0.28 < 0.29 < 0.074 ,
Ce-144 < 0.084 < 0.21 < 0.24 < 0.080 Location CL-7C CL-10 CL-19 CL-105 Lab Code CLSL-241 CLSL-242,3 CLSL-244 CLSL-245 Date Collected 10-07-85 10-07-85 10-07-85 10-07-85 Be-7 < 0. 36 <0.42 < 0.23 < 0.37 K-40 2.5210.18 3.94 0.13 3.80 0.32 5.2310.30 Mn-54 < 0.030 < 0. 024 <0.020 < 0.045 Fe-59 < 0.088 < 0. 009 <0.062 < 0.15 Co-58 < 0.031 <0.031 < 0.026 < 0.054 Co-60 < 0.026 < 0. 022 <0.020 < 0.043 Zn-65 < 0.057 < 0.060 <0.051 < 0.10 l Nb-95 < 0.037 <0.035 < 0.037 < 0.058 !
Zr-95 < 0.067 <0.060 <0.049 < 0.096 l Cs-134 < 0.031 <0.028 <0.022 < 0.049 i Cs-137 0.07 0.01 0.11 0.01 <0.019 < -0.049 Ba-140 < 0.52 <0.42 <0.42 < 0.65 La-140 < 0.15 < 0.11 < 0.13 < 0.19 Ce-144 < 0.17 < 0. 079 < 0.12 < 0.12 a
lab code used by analysis laboratory for sample identification.
b CLSL represents Clinton periphyten sample. Numerical designation is assigned by laboratory based upon sample receipt sequence. 1 represents duplicate analysis performed on the sample by the laboratory.
I 141
l l
Table H-22 1985 Monthly (November-April) and Semimonthly (May-October) Analysis of Milk at CL-116 for Gam:na-Emitting Isotopes Sample Description and Concentration (pCi/1)
Date Collected 07-15-85 08-05-85 08-19-85 09-03-85 8 b Lab Code CLMI-977 CLMI-1101 CLMI-1225 CLMI-1362
! Be-7 < 27 < 18 < 20 < 23 i
K-40 1375!30 1260170 1360270 1230170 Mn-54 <5 < 5 < 5 < 5 Fe-59 <12 < 12 < 12 < 12 co-58 <5 <5 < 5 < 5 Co-60 <5 < 5 < 5 < 5 Zn-65 <7 < 7 < 7 < 7
( Nb-95 Zr-95
< 10
<10
< 10
< 10
< 10
< 10
< 10
< 10 Cs-134 <5 < 5 < 5 < 5 Cs-137 <5 < 5 < 5 < 5 Ba-140 <60 < 60 < 60 < 60 La-140 < 15 < 15 < 15 < 15 Ce-144 < 30 < 30 < 30 < 30 Date Collected 09-23-85 10-08-85 10-21-85 11-26-85 Lab Code CLMI-1495 CLMI-1617 CLMI-1657 CLMI-1798 Be-7 < 26 < 20 < 25 < 18 K-40 1290 30 1150 60 1240130 1260!40 Mn-54 <5 < 5 <5 < 5 Fe-59 < 12 < 12 < 12 < 12 Co-58 <5 < 5 < 5 < 5 Co-60 <5 < 5 < 5 <
5 Zn-65 < 7 < 7 < 7 < 7 Nb-95 < 10 < 10 < 10 < 10 Zr-95 < 10 < 10 < 10 < 10 Cs-134 < 5 < 5 <
< 5 5 Cs-137 < 5 < 5 < 5 < 5 Ba-140 < 60 < 60 < 60 < 60 La-140 < 15 < 15 < 15 < 15 Ce-144 < 30 < 30 < 30 < 30 142
Table H-22 (continued)
Sample Description and Concentration (pCi/1) h
)
l Date Collected 12-31-85 l
- Lab Code CLMI-1883 Be-7 < 20 K-40 1180120 Mn-54 < 5 Fe-59 < 12 Co-58 < 5 i Co-60 < 5 Zn-65 < 7 Nb-95 < 10 Zr-95 < 10 Cs-134 < 5 Cs-137 < 5 Ba-140 < 60 La-140 < 15 Ce-144 < 30 lab code used by analysis laboratory for sample identification CLMI represents Clinton milk sample. Numerical designation is assigned by laboratory based upon receipt sequence.
143
Table E-23 1985 Monthly (November-April)/ Semimonthly (May-October) Analysis of Grass (in lieu of milk) for Gamma-Dnitting Isotopes at CL-11.
Sample Description and Concentration (pCi/g wet) ,
Date Collected 01-02-85 02-02-85 03'-02-85 04-24-85 Lab Code CLG-512 CLG-527 i K-40 2.2110.31 6.58!0.74 t
I-131 < 0.057 < 0.060 Cs-134 < 0.025 < 0.038 l
Cs-137 < 0.024 < 0.038 Ba-La-140 < 0.026 < 0.050 Date Collected 05-08-85 05-22-85 06-05-85 06-19-85 Lab Code CLG-541 CLG-547 CLG-561 CLG-565 K-40 9.64 0.74 14.5011.26 9.7610.66 9.28 0.88 I-131 < 0.060 < 0.060 < 0.059 < 0.027 Cs-134 < 0.031 < 0.034 < 0.022 < 0.024 Cs-137 < 0.033 < 0.038 < 0.025 < 0.026 Ba-La-140 < 0.046 < 0.059 < 0.040 < 0.028 Date Collected 07-03-85 07-17-85 08-07-85 08-28-85 Lab Code CLG-586 CLG-595 CLG-609 CLG-614 Be-7 2.80 0.35 3.79 0.16 0.9310.07 1.36 0.08 K-40 9.01 1.01 12.00 0.82 6.69!0.34 5.53 0.28 Mn-54 < 0.034 < 0.018 < 0.009 < 0.008 Fe-59 < 0.051 < 0.039 < 0.022 < 0.018 Co-58 < 0.036 < 0.014 < 0.010 < 0.008 Co-60 < 0.040 < 0.017 < 0.010 < 0.008 Zn-65 < 0.10 < 0.043 < 0.023 < 0.020 Nb-95 < 0.037 < 0.014 < 0.010 < 0.008 Zr-95 < 0.057 < 0.024 < 0.018 < 0.015 I-131 < 0.051 < 0.016 < 0.016 < 0.010 Cs-134 < 0.032 < 0.012 < 0.009 < 0.008 Cs-137 < 0.038 < 0. 014 < 0.010 < 0.008 Ba-140 < 0.15 < 0.054 < 0.048 < 0.034 I.a-140 < 0.050 < 0.013 < 0.011 < 0.008 Ce-144 < 0.16 < 0.066 < 0.062 < 0.055 144 l --- --
Table H-23 (continued)
Sample Description and Concentration (pC1/g wet) 1 Date Collected 09-11-85 09-25-85 10-02-85 10-23-85 Lab Code CLG-618 CLG-622 CLG-637 CLG-662 Be-7 0.79 0.08 0.7210.06 0.91!0.07 6.7620.24 K-40 5.04 0.29 5.85 0.29 5.61!0.28 5.05 0.33 Mn-54 < 0.010 < 0.003 < 0.008 < 0.015 Fe-59 < 0.024 < 0.008 < 0.019 < 0.033 Co-58 < 0.011 < 0.904 < 0.009 < 0.016 Co-60 < 0.011 < 0.003 < 0.008 < 0.016 Zn-65 < 0.026 < 0.009 < 0.022 < 0.035 Nb-95 < 0.011 < 0.004 < 0.009 < 0.016 l Zr-95 < 0.020 < 0.006 < 0.016 < 0.029 l I-131 < 0.014 < 0.006 < 0.013 < 0.022 Cs-134 < 0.010 < 0.003 < 0.008 < 0.016 Cs-137 < 0.012 < 0.003 < 0.009 < 0.017 Ba-140 < 0.044 < 0.018 < 0.03/ < 0.066 La-140 < 0.012 < 0.004 < 0.011 < 0.018 Ce-144 < 0.070 < 0.023 < 0.068 < 0.12 Date Collected 11-06-85 12-04-85 Lab Code CLG-666 CLG-676 Be-7 4.16 0.10 14.00 0.33 K-40 3.56 0.12 2.51 0.18 Mn-54 < 0.013 < 0.017 Fe-59 < 0.034 < 0.034 Co-58 < 0.013 < 0. 018 Co-60 < 0.013 < 0.016 Zn-65 < 0.029 < 0.040 Nb-95 < 0.013 < 0.018 Zr-95 < 0.024 < 0.031 I-131 < 0.024 < 0.028 Cs-134 < 0. 015 < 0. 018 Cs-137 < 0.014 < 0. 019 l Ba-140 < 0.067 < 0.075 La-140 < 0.014 < 0.016 Ce-144 < 0.11 < 0.15 sample not available due to snow cover which prevents deposition onto grass lab code used by analysis laboratory for sample identification where CLG represents Clinton grass sample 145
Table H-24 1985 Monthly (November-April)/ Semimonthly (May-October) Analysis of Grass (in lieu of milk) for Gamma-Emitting Isotopes at CL-15.
Sample Description and Concentration (pC1/g wet) l DateColgected 01-02-85 02-02-85 03-02-85 04-24-85 Lab Code CLG-513,4 CLG-528 K-40 3.66:0.23 5.95!0.83 I-131 < 0.058 < 0.049 Cs-134 < 0.023 < 0.034 Cs-137 < 0.023 < 0.042 Ba-La-140 < 0.024 < 0.056 Date Collected 05-08-85 05-22-85 06-05-85 06-19-85 Lab Code CLG-542,3 CLG-548 CLG-562 CLG-566 I
K-40 8.8010.88 7.47 0.33 10.50 0.88 4.91 0.41 I-131 < 0.060 < 0.054 < 0.060 < 0.020 Cs-134 < 0.028 < 0.032 < 0.020 < 0.014 Cs-137 < 0.034 < 0.032 < 0.024 < 0.017 Ba-La-140 < 0.057 < 0.030 < 0.041 < 0.017 Date Collected 07-03-85 07-17-85 08-07-85 08-28-85 Lab Code CLG-587 CLG-596 CLG-610 CLG-615 Be-7 < 0. 27 0.64t0.10 0.22 0.03 0.'73 0.06 K-40 9.05!0.79 9.32!0.46 2.7710.08 5.22 0.38 Mn-54 < 0.031 < 0.011 < 0.006 < 0.009 Fe-59 <0.069 < 0.028 < 0.020 < 0.024 l Co-58 < 0.030 <0.012 y < 0.006 < 0.009 Co-60 < 0.031 < 0.011 < 0.007 < 0.010 Zn-65 < 0.081 < 0.031 < 0.016 < 0.026 Nb-95 < 0.034 < 0.012 < 0.007 < 0.009 Zr-95 < 0. 05 7 < 0.020 < 0.011 < 0.016 I-131 < 0.056 < 0. 016 < 0. 012 < 0.010 Cs-134 < 0.027 < 0.010 < 0.007 <0.008 Cs-137 < 0.032 < 0.011 < 0.006 < 0.009 Ba-140 <0.16 < 0.046 < 0.032 < 0.033 La-140 < 0.041 < 0. 013 < 0.008 < 0.009 Ce-144 < 0.22 <0.080 < 0.049 < 0.044 i~
l46
Table H-24 (continued)
Sample Description and Concentration (pC1/g wet)
Date Collected 09-11-85 09-25-85 10-02-85 10-23-85 Lab Code CLG-619 CLG-623,4 CLG-638 CLG-663 Be-7 0.66!0.06 1.71!0.06 2.06!0.09 2.83 0.12 K-40 5.4810.12 6.6110.18 5.34!0.23 7.46!0.38 Mn-54 < 0.013 < 0.004 < 0.009 < 0.012 Fe-59 < 0.034 < 0.010 < 0. 022 < 0.025 Co-58 < 0.013 < 0.004 < 0.009 < 0.011 Co-60 < 0.013 < 0.004 < 0.009 < 0. 012 i
Zn-65 < 0.032 < 0.011 < 0.024 < 0.030 Nb-95 < 0.012 < 0.004 < 0.009 < 0.012 Zr-95 < 0.024 < 0.007 < 0. 015 < 0.020 I-131 < 0.024 < 0.007 < 0.015 < 0.020 Cs-134 < 0.015 < 0.004 < 0.008 < 0.010 Cs-137 < 0.014 < 0.004 < 0.008 < 0.011 Ba-140 < 0.059 < 0.021 < 0.033 < 0.047 La-140 < 0.012 < 0.005 < 0.009 < 0.012 Ce-144 < 0.102 < 0.031 < 0.043 < 0.088 Date Collected 11-06-85 12-04-85 Lab Code CLG-667,8 CLG-677 Be-7 4.66!0.10 9.00 0.13 K-40 7.67 0.18 6.10 0.14 Mn-54 < 0.012 < 0.014 Fe-59 < 0.031 < 0.036 Co-58 < 0.012 < 0.016 Co-60 < 0.014 < 0.015 Zn-65 < 0.034 < 0.035 Nb-95 < 0.012 < 0.014 Zr-95 < 0.020 < 0. 027 '
I-131 < 0.015 < 0.021 Cs-134 < 0.010 < 0.016 Cs-137 < 0.011 < 0.016 Ba-140 < 0.049 < 0.055 La-140 < 0.014 < 0.013 Ce-144 < 0. 014 < 0.11 sample not available due to snow cover which prevents deposition onto grass lab code used by analysis laboratory for sample identification l l 147
_ _. .~ . .__
~
f, . + . s , k' 7 >
- . a Table B-25 1985 Monthly" (November-Afril)/3esimontitly}(May'-October) Analysis of - ., fk Grass (in lieu of milk) for Gamma-Emitt'ing Isotopes at CL-16. .
( 4 ., y, 1
4 Sample Description and Concentratior.j pCi/g wei) 4 y .s.s A
u ,s 01-02-85 02-02-85 '0.% 02-85 '
~
04-24-85 -
DateColgected "
4 Lab Code CLG-515
~. . , e CLG-52,9 .
G.
a a K-40 2.73 0.29 h '
5.63 0.85 I-131 < 0.042 Q' * ,-- < 0.055 N Cs-134 < 0. 018 ,
o s < 0.039 ,
J. Cs-137 < 0.018 .N -
- < 0.045 Ba-La-140 < 0.019 ,, 1 q < 0.055
> , ,q ', ,
^ ~ ~ ~ '
Date Collected 05-08-85 _ 05-22-85 '66-05-45 06-19-85 -
Lab Code CLG-544 CLC,-549 ~ CLG-563 CLG-567 'y l K-40 9.6810.63- 5l8710.60 9.57 0.57 4.5010.42 I-131
< 0.055- 4 < 0.050 < 0.060 x < 0.013
- Cs-134 .f < 0.026 - {0.025 ,
< 0.020 ' < 0.013 -
Cs-137 < 0.038 -
ec.0.025 . < 0.021 < 0.015 Ba-La-140 < 0.038 ' .s <,0f036 .tf ' < 0.036 ; <.0.016
.. i*
., Date Collectedt '07-03-85 > 07-17-85 /y' 08-07-85 08-28-85 Lab Code CLG-588 CLG-597 - / -CLG-611 CLG-616 s .
Be-7 2.41t0.28 1.5310.10 1.2010.07 0.71 0.05 K-40 7.67!0.69 5.70 0.31,,. r.10 0.12 4.49i0.09 Mn-54 < 0.028 < 0.010 ,p<0.010 e < 0.008 Fe-59 < 0.075 . < 0.024 1 N < 0.026 < O'.'021 Co-58 < 0.030 ~
< 0.011 < 0.010 < 0.006
! Co-60 < 0.032 < 0.011 < 0.011 < 0.008 Zn-65 < 0.077 < 0.026 < 0.025 < 0.019 i Nb-95 - < 0.032 -
< 0.010 .
< 0.011. < 0.009
- Zr-95 < 0.047 < 0.020.< ; < 0.01(i < 0.015 I-131 < 0.050 < 0.013 ~ < 0.021- < 0.011 Cs-134 < 0.026 < 0.010, T0.011 < 0.009 Cs-137 < 0.031 < 0.011 . 4 0.'0'11 ' ' < 0.010 Ba-140 < 0 13 < 0.0449- - </ O'.038 < 0.036
- La-140 ^
< 0.037 < 0.011- 4 0.012 , < 0.009 Ce-14'4 < O'.22 s < 0.070', ^0.082 ,
< 0.070 9
. 8%t t
- -. ~ s l -
/ ,.
h l q , 4 a * ,w s
k
/ .s v V 4
i s
- s e, k .
- 148 t..
__e
/ ,. . ' .. . _ _ _ % ____._. _ . . _ _ , . ,__ . . _
Table H-25 (continued)
Sample Description and Concentration (pC1/g wet)
Date Collected 09-11-85 09-25-85 10-02-85 10-23-35 Lab Code CLG-620 CLG-625 CLG-639 CLG-664 Be-7 < 0.091 0.83 0.07 0.83 0.03 3.04 0.11 K-40 5.88!0.33 6.31:0.32 3.1110.07 5.36!0.28 Mn-54 < 0.011 < 0.009 < 0.007 < 0.008 Fe-59 < 0.024 < 0.022 < 0.017 < 0.019 Co-58 < 0.011 < 0.010 < 0.007 < 0.009 Co-60 < 0.012 < 0.010 < 0.008 < 0.008 Zn-65 < 0.030 < 0.024 < 0.015 < 0.021 Nb-95 < 0.012 < 0.010 < 0.007 < 0.009 Zr-95 < 0.020 < 0.018 < 0.012 < 0.016 I-131 < 0.015 < 0.016 < 0.010 < 0.013 Cs-134 < 0.011 . < 0.009 < 0.008 < 0.008 Cs-137 < 0.011 < 0.010 < 0.007 < 0.008 Ba-140 < 0.045 < 0.047 < 0.031 < 0.039 La-140 < 0.011 < 0.011 < 0.007 < 0.009 Ce-144 < 0.087 < 0.062 < 0.059 < 0.060 Date Collected 11-06-85 12-04-85 Lab Code CLG-669 CLG-678 _
Be-7 3.74!0.14 9.88 0.25 K-40 6.8510.36 5.75 0.29 Mn-54 < 0.011 < 0. 014 Fe-59 < 0.027 < 0.032 Co-58 < 0.011 < 0.013 Co-60 < 0.011 < 0.016 Zn-65 < 0.029 < 0.035 Nb-95 < 0.012 < 0.012 Zr-95 < 0.020 < 0.022 I-131 < 0.020 < 0.014 Cs-134 < 0.010 < 0.013 Cs-137 < 0.011 < 0.013 Ba-140 < 0.053 < 0.044 La-140 < 0.014 < 0.015 Ce-144 < 0.085 < 0.070 sample not available due to snow cover which prevents deposition onto grass lab code used by analysis laboratory for sample identification I
i 149
Table H-26 1985 Monthly (November-April)/ Semimonthly (May-October) Analysis of Grass (in lieu of milk) for Gamma-Emitting Isotopes at CL-17.
Sample Description and Concentration (pC1/g wet)
Date Col ected 01-02-85 02-02-85 03-02-85 04-24-85 Lab Code CLG-516 CLG-530 8
- K-40 1.3610.16 8.3110.79 I-131 < 0.043 < 0.058 Cs-134 < 0.015 < 0.034 Cs-137 < 0.016 < 0.038 Ba-La-140 < 0.011 < 0.054 Date Collected 05-08-85 05-22-85 06-05-85 06-19-85 Lab Code CLG-545 CLG-550 CLG-564 CLG-568,9 K-40 8.3020.76 6.89 0.75 11.80 0.70 7.1110.40
< 0.060 < 0.019 I-131 < 0.048 < 0.059
< 0.020 < 0. 017 Cs-134 < 0.024 < 0.032
< < 0.019 Cs-137 < 0.025 < 0.032 0.023
< 0.038 < 0. 017 Ba-La-140 < 0.046 < 0.046 Date Collected 07-03-85 07-17-85 08-07-85 08-28-85 Lab Code CLG-589 CLG-598 CLG-612,3 CLG-617 Be-7 1.65!0.30 2.04 0.12 3.00 0.09 0.52 0.04 K-40 7.52!0.95 7.5110.55 4.68 0.19 4.35!0.21 Mn-54 < 0.038 < 0.013 < 0.011 <0.006 Fe-59 < 0.10 < 0.034 < 0.025 <0.013 Co-58 < 0.040 < 0.013 < 0.011 <0.006 Co-60 < 0.041 < 0. 015 < 0.011 <0.006 Zn-65 < 0.10 < 0.037 < 0.027 <0.014 Nb-95 < 0.039 < 0.014 < 0.012 < 0.006 Zr-95 < 0.071 < 0.023 < 0.020 <0.010 I-131 < 0.058 < 0.016 < 0.021 < 0.008 Cs-134 < 0.036 < 0.011 < 0.010 <0.005 Cs-137 < 0.C37 < 0.013 < 0.011 < 0.006 Ba-140 < 0.18 < 0.051 < 0.055 <0.025 La-140 < 0.063 < 0.015 < 0. 015 < 0.006 Ce-144 < 0.18 < 0.061 < 0.085 <0.039 l
l l
150 _ _ _ -
-- - n w. -
Table H-26 (continued)
Sample Description and Concentration (pCi/g wet)
Date Cellected 09-11-85 09-25-85 10-02-85 10-23-85 Lab Code CLG-621 CLG-626 CLG-640 CLG-665 Be-7 1.5010.12 2.45 0.12 2.17!0.09 7.73 0.17 K-40 7.28 0.39 6.34 0.34 4.54 0.23 6.78 0.21 Mn-54 < 0.016 < 0.011 < 0.007 < 0.022 Fe-59 < 0.038 < 0.028 < 0.017 < 0.055 Co-58 < 0.016 < 0.012 < 0.008 < 0.020 Co-60 < 0.018 < 0.012 < 0.008 < 0.026 Zn-65 < 0.044 < 0.029 < 0.017 < 0.049 Nb-95 < 0.016 < 0.013 < 0.007 < 0.022 Zr-95 < 0.026 < 0.021 < 0.014 < 0.042 I-131 < 0.016 < 0.022 < 0.011 < 0.035 Cs-134 < 0.015 < 0.011 < 0.007 . < 0.026 Cs-137 < 0.015 < 0.012 < 0.008 < 0.026 Ba-140 < 0.056 < 0.057 < 0.033 < 0.11 La-140 < 0.019 < 0.014 < 0.009 < 0.021 Ce-144 < 0.075 < 0.087 < 0.054 < 0. 20 Date Collected 11-06-85 12-04-85 Lab Code CLG-670 CLG-679 Be-7 4.82 0.18 13.60!0.35 K-40 4.36 0.23 3.3110.22 Mn-54 < 0.016 < 0.024 Fe-59 < 0.037 < 0.042 Co-58 < 0.018 < 0.023 Co-60 < 0.014 < 0.020 Zn-65 < 0.038 < 0.049 Nb-95 < 0.018 < 0.022 Zr-95 < 0.031 < 0.043 I-131 < 0.032 < 0.028 Cs-134 < 0.014 < 0.021 Cs-137 < 0.017 < 0.025 Ba-140 < 0.084 < 0.088 La-140 < 0.016 < 0.017 Ce-144 < 0.15 < 0.22 sample not available due to snow cover which prevents deposition onto grass b
lab code used by analysis laboratory for sample identification i
-151
Table H-27 1985 Monthly (during growing season) Analysis of Green Leafy Vegetables for Iodine-131 and Gamma-Emitting Isotopes Sample Description and Concentration (pCi/g vet)
Location CL-114 CL-114 CL-115 a CLVe-683 CLVe-677 Lab Code CLVe-681 Simple Type Cabbage Swiss Chard Cabbage Date Collected 07-29-85 07-29-85 07-29-85 Be-7 < 0.056 <0.068 < 0.37 K-40 2.79 0.06 4.8310.29 2.06!0.05 Mn-54 < 0.006 < 0.008 < 0.004 Fe-59 < 0.015 <0.021 < 0.011 Co-58 < 0.006 <0.010 < 0.004 Co-60 < 0.006 <0.009 < 0.005 Zn-65 < 0.015 < 0.022 < 0.010 Nb-95 < 0.007 <0.008 < 0.004 Zr-95 < 0.011 < 0. 015 < 0.007 I-131 < 0.009 < 0.009 < 0.006 Cs-134 < 0.007 <0.008 < 0.004 Cs-137 < 0.006 < 0.008 < 0.004 Ba-140 < 0.027 <0.034 < 0.019 La-140 < 0.005 < 0.007 < 0.004 Ce-144 ' < 0.052 <0.056 < 0.030 Location CL-18 CL-18 CL-18 4 Lab Code CLVe-678 CLVe-679 CLVe-680 Sample Type Lettuce Swiss Chard Cabbage Date Collected 07-29-85 07-29-85 07-29-85 Be-7 < 0.065 < 0.066 <0.058 K-40 2.31!0.07 5.51 0.43 3.2010.07 Mn-54 < 0.007 < 0.010 < 0.006 Fe-59 < 0.018 < 0.028 < 0.017 Co-58 < 0.007 < 0.010 < 0.006 Co-60 < 0.008 < 0. 010 < 0.006 Zn-65 < 0.016 < 0.030 < 0.016 Nb-95 < 0.008 < 0.010 < 0.006 i Zr-95 < 0.013 < 0.017 < 0.012 I-131 < 0.012 < 0. 010 < 0.010 Cs-134 < 0.008 < 0.008 < 0.007 !
Cs-137 < 0.008 < 0.010 < 0.007 l Ba-140 < 0.034 < 0.034 < 0.031 l La-140 < 0.007 < 0.010 < 0.007 Ce-144 < 0.059 < 0.046 < 0.055 l
l 152
l Table H-27 (continued)
Sample Description and Concentration (pC1/g wet)
Location CL-18 CL-18 CL-18 >
Lab Code CLVe-739 CLVe-740 CLVe-741 Sample Type Swiss Chard Swiss Chard Cabbage Date Collected 08-29-85 08-29-85 08-29-85 Be-7 < 0.040 < 0.053 < 0.043 K-40 4.89!0.22 4.53 0.22 1.86t0.05 Mn-54 < 0.005 < 0.007 < 0.005 Fe-59 < 0.012 < 0.016 < 0.012 Co-58 < 0.005 < 0.007 < 0.004 Co-60 < 0.005 < 0.007 < 0.005 Zn-65 < 0.013 < 0.017 < 0.011 Nb-95 < 0.005 < 0.006 < 0.005 Zr-95 . < 0.009 < 0.012 < 0.009 I-131 < 0.007 < 0.009 < 0.007 Cs-134 < 0.004 < 0.006 < 0.005 Cs-137 < 0.005 < 0.007 < 0.005 Ba-140 < 0.021 < 0.027 < 0.022 La-140 < 0.005 < 0.007 < 0.005 Ce-144 < 0.038 < 0.051 < 0.042 Location CL-115 CL-115 CL-115 Lab Code CLVe-774 CLVe-745 CLVe-746 Sample Type Lettuce Cabbage Cabbage Date Collected 08-29-85 08-29-85 08-29-85 Be-7 < 0.072 < 0.030 < 0.028 K-40 2.73!0.17 1.68 0.09 1.95!0.14 Mn-54 < 0.008 < 0.003 < 0.004 Fe-59 < 0.017 < 0.007 < 0.010 Co-58 < 0.008 < 0.004 < 0.004 l Co-60 < 0.009 < 0.003 < 0.004 Zn-65 < 0.021 < 0.008 < 0.010 l
Nb-95 < 0.009 < 0.003 < 0.004 Zr-95 < 0. 016 < 0.006 < 0.007 !
I-131 < 0.011 < 0.004 < 0.005 Cs-134 < 0.008 < 0.053 < 0.004 Cs-137 < 0.009 < 0.004 < 0.004 Ba-140 < 0.035 < 0.015 < 0. 015 La-140 < 0.010 < 0.004 < 0.004 Ce-144 < 0.069 < 0.026 < 0.020 153 1
)
Table H-27 (continued)
Sample Description and Concentration (pC1/g wet)
Location CL-18 CL-18 Lab Code CLVe-814 CLVe-816 Sample Type Cabbage Swiss Chard Date Collected 09-26-85 09-26-85 Be-7 < 0.039 ' < 0.044 K-40 1.75!0.11 3.71 0.06 Mn-54 < 0.005 < 0.004 Fe-59 < 0.010 < 0.013 Co-58 < 0.005 < 0.005 Co-60 < 0.005 < 0.005 Zn-65 < 0.012 < 0.012 Nb-95 < 0.005 < 0.005 Zr-95 < 0.008 < 0.008 I-131 < 0.006 < 0.006 Cs-134 < 0.004 < 0.005 Cs-137 < 0.005 < 0.005 Ba-140 < 0.018 < 0.020 La-140 < 0.005 < 0.005 Ce-144 < 0.038 < 0.039 Location CL-115 CL-115 Lab Code CLVe-819 CLVe-820 Sample Type Cabbage Lettuce Date Collected 09-26-85 09-26-85 Be-7 < 0.031 <0.052 K-40 1.45!0.09 1.73 0.12 Mn-54 < 0.004 < 0.006 Fe-59 < 0.011 < 0.013 Co-58 < 0.005 < 0.006 Co-60 < 0.005 < 0.006 Zn-65 < 0.012 < 0.013 Nb-95 < 0.004 < 0.006 Zr-95 < 0.008 < 0.011 I-13) < 0.004 < 0.007 Cs-134 < 0.004 < 0.006 Cs-137 < 0.004 < 0.007 Ba-140 < 0.016 < 0.025 La-140 < 0.005 < 0.006 Ce-144 < 0.023 < 0.045 154
. -~ .. - - . _ . .
'l Table H-27 (continued)
Sample Description and Concentration (pC1/g wet)
.i CL-114 CL-114
! Location CL-114 CLVe-743 CLVe-817 Lib Code CLVe-742 Cabbage Cabbage Swiss Chard Sanple Type 09-26-85 08-28-85 08-28-85 Data Collected 0.14!0.02 < 0.027 B2-7 < 0.054 1.67 0.09 2.4920.06 4.6510.31 K-40 < 0.005 < 0.004 Mn-54 < 0.006 < 0.009
< 0.015 < 0.014 Fe-59 < 0.005 < 0.004 i Co-58 < 0.006 < 0.005
< 0.006 < 0.006
! Co-60 < 0.014 < 0.010 Zn-65 < 0.013 < 0.004
< 0.006 < 0.005 Nb-95 < 0.009 < 0.007 Zr-95 < 0.010 i
< 0.008 < 0.005 < 0.004 I-131 < 0.004 < 0.003
- Cs-134 < 0.006
< 0.006 < 0.005 < 0.004 Cs-137 < 0.015 Ba-140 < 0.027 < 0.018
< 0.006 < 0.005 < 0.004 La-140 < 0.020 Ce-144 < 0.051 < 0.024 Location CL-114 Lab Code CLVe-818 Sample Type Swiss Chard Data Collected 09-26-85 l1
- Be-7 < 0.032 K-40 3.8610.18 Mn-54 < 0.004
} Fe-59 < 0.010 Co-58 < 0.004 l
Co-60 < 0.004 Zn-65 < 0.011 Nb-95 < 0.004 Zr < 0.007 I-131 < 0.005 Cs-134 < 0.004 Cs-137 < 0.004 Ba-140 < 0.016 La-140 < 0.004 Ce-144 < 0.027 i
- 1ab code used by analysis laboratory for sample identification i
4 155
[
I I
- Table H-28 1985 Semiannual Gamma Isotopic Analysis of fish from the Clinton Lake Sample Description and Concentration (pCi/g wet)
CL-19 1 Date Collected 06-10-85 06-10-85 06-10-85 06-10-85 CLF-596 CLF-598 CLF-600 CLF-602 Lab Code #
Common Carp Bluegill White Crappie Largemouth Type Bass
< 0.15 < 0.14 <0.12 < 0.13
! Be-7 K-40 2.10!0.07 2.44!0.09 2.10!0.78 2.6410.08 Co-58 < 0.015 < 0.017 < 0.013 <0.016 Co-60 < -0.008 < 0.010 < 0.008 < 0.009 h%-95 < 0.018 < 0.017 < 0.015 < 0.016 Zr-95 < 0.031 < 0.030- < 0.026 < 0.029 Ru-103 < 0.024 < 0.023 < 0.019 <0.021 Ru-106 < 0.075 < 0.079 < 0.073 < 0.072 Cs-134 < 0.009 < 0.011 < 0.009 < 0.010 Cs-137 < 0.008 < 0.010 < 0.008 < 0.008 Ce-141 < 0.0046 < 0.032 < 0.037 < 0.028 Ce-144. < 0.0054 < 0.034 - < 0.050 < 0.032 4
Date Collected 10-07-85 10-07-85 10-07-85 10-07-85 i Lab Code CLF-696 CLF-697 CLF-698 CLF-699 Type Largemouth White Crappie Common Carp Bluegill Bass Be-7 < 0.06 < 0.04 < 0.06 < 0.06 l 2.40!0.12 K-40 3.11 0.08 2.95 0.09 2.60 0.08 Co-58 < 0.008 < 0.009 < 0.008 < 0.008 Co-60 < 0.009 <0.009 < 0.007 < 0.007 Nb-95 < 0.008 < 0.008 < 0.008 < 0.008 Zr-95 < 0.016 < 0. 014 < 0.014 < 0.014 Ru-103 < 0.006 < 0.007 < 0.008 < 0.007 Ru-106 < 0.061 < 0.064 < 0.070 < 0.063 Cs-134 < 0.009 < 0.008 < 0.009 < 0.007 Cs-137 < 0.008 < 0.008 < 0.008 < 0.007 Ce-141 < 0.007 < 0.007 < 0.011 < 0.011 Ce-144 < 0.028 < 0.027 < 0.044 < 0.039 a
lab code used by analysis laboratory for sample identification 4
I i
156
Table H-29 1985 Semiannual Gamma Isotopic Analysis of fish from Lake Shelbyville Sample Description and Activity (pC1/g wet)
,CL-105 Date Collected 06-17-85 06-17-85 06-17-85 06-17-85 1
a CLF-603 Lab Code CLF-597 CLF-599 CLF-601 Type Common Carp Bluegill White Crappie Largemouth Bass Be-7 < 0.13 < 0.12 < 0.090 < 0.12 K-40 2.16!0.08 1.91 0.08 2.12!0.11 2.7920.07
! Co-58 < 0.014 < 0.013 < 0.011 < 0.014 Co-60. < 0.007 < 0.007 < 0.006 < 0.009
) Nb-95 < 0.015 < 0.014 -
< 0.019 <- 0.016 Zr-95 < 0.027 < 0.025 < 0.020 < 0.028 Ru-103 < 0.020 < 0.019 < 0.015 < 0.020 Ru-106 < 0.077 < 0.079 < 0.052 < 0.067 Cs-134 < 0.010 < 0.009 < 0.006 < 0.009 Cs-137 < 0.008 < 0.007 < 0.006 < 0.008 i Ce-141 < 0.038 < 0.036' < . 0.025 < 0.027 Ce-144 < 0.050 __ _ . < 0.049 < 0.034 < 0.029 Date Collected 10-08-85 10-08-85 10-08-85 10-08-85 Lab Code CLF-700 CLF-701,2 b CLF-703 CLF-704 Type Largemouth Common Carp White Crappie Bluegill Bass Be-7 < 0.0547 < 0.046 < 0.053 < 0.058
- K-40 2.94 0.13 2.5610.14 3.1910.08 2.13 0.11 i Co-58 < 0.007 < 0.006 < 0.008 < 0.007' I Co-60 < 0.007 < 0.006 < 0.010 < 0.007 Nb-95 < 0.007 < 0.007 < 0.008 < 0.008 Zr-95 < 0.012 < 0.011 < 0.014 < 0.014 Ru-103 < 0.006 < 0.006 < 0.007 < 0.007
- Ru-106 < 0.050 < 0.050 < 0.062 < 0.062 3 Cs-134 < 0.006 < 0.007 < 0.008 < 0.007 Cs-137 < 0.006 < 0.006 < 0.008 < 0.007 Ce-141 < 0.009 < 0.009 < 0.007 < 0.011 Ce-144 < 0.032 < 0.035 < 0.028 - < 0.038 i
a lab code used by analysis laboratory for sample identification b
represents duplicate analysis performed on the sample b, tia laboratory 4
157- )
I'
. , - _ . - . _ , - _ _ _ . . _ . . . . _ _ , _ . . . . . _ _ _ ,_. .. - , __,4.__ _ . _ _ _ . , _ _ . . _ . . . . . _ , , _. ,
Table H-30 1985 Analysis of Soil Samples for Gamma- Emitting Isotopes Sample Description and Concentration (pC1/g dry)
Location CL-1 CL-2 CL-3 CL-4 Leb Code" CLS0-417 CLSO-418 CLS0-419 CLS0-420 12-28-85 12-28-85 Date Collected 12-28-85 12-28-85 Bs-7 < 0.18 < 0.12 < 0.12 < 0.15 K-40 12.0!0.5 15.9 0.4 14.7 0.4 13.5 0.2 Mn-54 < 0.023 < 0.015 < 0.015 < 0.017 Fe-59 < 0.057 < 0.040 < 0.037 < 0.046 Co-58 < 0.023 < 0.016 < 0.015 < 0.016 Co-60 < 0.022 < 0.015 < 0.014 < 0.017 Zn-65 < 0.070 < 0.046 < 0.045 < 0.041 i
Nb-95 < 0.030 < 0.019 < 0.017 < 0.020 Zr-95 < 0.044 < 0.030 < 0.028 < 0.034 l Cs-134 < 0.033 < 0.022 < 0.021 < 0.022 Cs-137 0.15!0.02 0.2410.01 0.3410.01 0.39 0.01 Ba-140 < 0.14 < 0.091 < 0.083 < 0.098 La-140 < 0.038 < 0.024 < 0.021 < 0.031 Ce-144 < 0.14 < 0.091 < 0.088 < 0.12 Location CL-6 CL-7 __ CL-8 CL-11 Lab Code CLS0-421 CLS0-422 CLS0-423 CLS0-424 Date Collected 12-28-85 12-28-85 12-28-85 12-28-85 Be-7 < 0.20 0.44 0.07 < 0. 24 < 0.22 K-40 13.0 0.3 15.3!0.2 11.5!0.3 13.510.6 Mn-54 < 0.022 < 0.017 < 0.026 < 0.028 Fe-59 < 0.067 < 0.049 < 0.079 < 0.068 Co-58 < 0.023 < 0.016 < 0.025 < 0.028 Co-60 < 0.024 < 0.017 < 0.024 < 0.026 Zn-65 < 0.060 < 0.042 < 0.061 < 0.082 Nb-95 < 0.027 < 0.021 < 0.029 < 0.035 j Zr-95 < 0.046 < 0.033 < 0.050 < 0.053 Cs-134 < 0.028 < 0.022 < 0.033 < 0.039 Cs-137 < 0.026 0.14!0.01 0.15!0.01 0.4010.03 Ba-140 < 0.15 < 0.11 < 0.16 < 0.16 La-140 < 0.036 < 0.031 < 0.053 < 0.044 Ce-144 < 0.15 < 0.11 < 0.18 < 0.17 I 1ab code used by analysis laboratory for sample identification 158
e U-600563
) '
L30-86(06-04)-L lA.120
/LLINO/S POWER OOMPANY IP CLINToN Pon1R STAiloN. P.o. BOX 678. CLINTON. ILLINolS 61727 June 4, 1986 9
Docket No. 50-461 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Clinton Power Station Radiological Environmental Monitoring Report Preoperational Stage 1985
Dear Dr. Butler:
Attached is the Clinton Power Station Radiological Environmental Monitoring Report Preoperational Stage for 1985. Please contact us if you have any questions on this report.
Sincerel yours, fA ~A 1
c./4.
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