ML20217J211
| ML20217J211 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/31/1997 |
| From: | Sipek J ILLINOIS POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| U-602987, NUDOCS 9804300189 | |
| Download: ML20217J211 (161) | |
Text
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U-602987 1A.120 April 24, 1998 i l l l Docket No. 50-461 10CFR50, AppI Document Control Desk Nuclear Regulatory Co nmission Washington, D.C. 20555
Subject:
Clinton Power Station Annual Radiological Environmental Operating Report
Dear Madam or Sir:
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lilinois Power is submitting the 1997 Annual Radiological Environmental Operating Report for Clinton Power Station. This submittal is provided in accardance with the requirements of Section 5.6.2 of the Clinton Power Station Technical l Specifications. l Sincerely yours,
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Joseph . Sip - Director - Licensing i GBS/mlh
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Attachment cc: NRC Clinton Licensing Project Manager Ok NRC Resident Office, V-690 (",O Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety 9804300189 971231 PDR ADOCK 05000461 PDR R
g n u nces POWER uimom. - g Clinton Power Station 1997 Annual Radiological I Environmental Operating Report I Pride and Excellence in Nuclear Generation I ;- j , y :a.:
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l I I 1997 g ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING g REPORT , I FOR THE i CLINTON POWER STATION I I I i Prepared by Radiological Programs Group 5 Pi t a aietie a e n e m istrv n ev ert m e t h i ] -
i TABLE OF CONTENTS 1 ITEM PAGE LIST OF TABLES iii LIST OF FIGURES iv I. EXECUTIVE
SUMMARY
1 II. INTRODUCTION l A. B. Characteristics of Radiation 1 Sources of Radiation Exposure 3 l C. Description of the Clinton Power Station 10 D. Nuclear Reactor Operations E. 11 Containment of Radioactivity 15 F. G. Sources of Radioactive Effluents 16 Radioactive Waste Processing 17 III. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM '
- (REMP)
A. Program Description 1 B. Direct Radiation Monitoring 23 C. Atmospheric Monitoring D. 27 Aquatic Monitoring 33 Fish 33 Shoreline Sediments 34 Bottom Sediments 35 Aquatic Vegetation (Periphyton) 35 E. Terrestrial Monitoring l
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F. Water Monitoring
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, Drinking Water 42 Surface Water 43 Well Water 44 G. Quality Assurance Program 46 H. Changes to the REMP During 1997 46 IV. ANNUAL LAND USE CENSUS A. Annual Lac 3 Use Census 1 V. LIST OF REFERENCES i l
I TABLE OF CONTENTS (Cont'd) ITEM PAGE VI. APPENDICES A. Exceptions to the REMP During 1997 A-1 ' B. 1. Summary of Sample Collection and Analysis i Methods B-1
- 2. Sampling and Analysis Frequency Summary B-7
- 3. Radiological Environmental Monitoring Program Annual Summary B-9 C. Glossary C-1 D. 1997 Radiological Environmental Monitoring Program Quality Control Check Results D-1 E. CPS Radiological Environmental Monitoring Results during 1997 E-1 I
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l LIST OF TABLES l TABLE SUBJECT PAGE l 1 Common Sources of Radiation II-7 2 Clinton Power Station Sample Codes III-15 3 REMP Sample Locations III-17 4 Average Quarterly TLD Results III-27 5 Average Gross Beta Concentrations in Air Particulates III-29 6 Average Monthly Gross Beta Concentrations in Air Particulates III-30 7 Average Gross Beta Concentrations in Drinking, Surface and Well Water III-45 8 1997 Annual Land Use Census IV-1 l l l l l I l l l l l iii i
I LIST OF FIGURES FIGURE SUBJECT PAGE 1 l 1 Dose Contributions to the U. S. Population from Principal Sources of Radiation Exposure II-7 l 2 Clinton Power Station Basic Plant Schematic II-13 3 Potential Exposure Pathways of Man Due to l Releases of Radioactive Material to the i Environment III-3 I 4 REMP Sample Locations within 1 l'ile III-7 l 5 REMP Sample L6 cations from 1 - 2 Miles III-9 6 REMP Sample Locations frota 2 - 5 Miles III-11 7 REMP Sample Locations Greater than 5 Miles III-13 l 8 Direct Radiation Comparison III-25 9 Air Particulate Gross Beta Activity l Comparison III-31 10 Strontium-90 Activity in Milk III-39, I I I I I I I iV I I
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This report describes the Annual Radiological Environmental Monitoring Program (REMP) conducted near the Clinton Power Station (CPS) during the 1997 calendar year. The REMP was performed as required by the CPS Operating License issued ; by the United States Nuclear Regulatory Commission. The objective of the REMP is to assess any radiological impact upon the surrounding environment due to the operation of the Clinton Power Station. During 1997, over 1,700 environmental samples were collected. These samples represented direct radiation; atmospheric, terrestrial, and aquatic environments; and Clinton Lake surface water and public drinking water supplies. About 2200 analyses were performed on these environrrantal samples. Results of the analyses showed natural radioactivity and radioactivity attributed to other historical nuclear events. The radioactivity levels detected were similar to the preoperational levels. The CPS Preoperational REMP Report documented natural background radionuclides and man-made radioactivity in the environment surrounding CPS prior to plant operations. Radiological environmental measurements taken during 1997 demonstrated that operational and engineered controls on the radioactive effluents released from the plant functioned as designed. Any radioactivity that was detected in the environment at indicator locations was appropriately compared with both the measurements at control locations (sample locations not affected by station operations) and preoperational results. There were no radioactive liquid discharges during 1997. Releases of gaseous radioactive materials were accurately measured in plant effluents. There were no gaseous releases that came close to approaching the limits specified in the CPS Offsite Dose Calculation Manual (ODCM). The highest calculated offsite dose received by a member of the public due to the release of gaseous materials from Clinton Power Station was 0.007 mrem. All compansons among operational data and preoperational data showed that the operation of Clinton Power Station had no measurable effect upon the environment in 1997. l l-1 i I
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L I I II. INTRODUCTION The Radiological Environmental Monitoring Program (REMP) at Clinton Power Station (CPS) is ( designed to monitor the environment surrounding the plant for any radioactive material that may be released by CPS as a result ofplant operations. The ( primary concern is what impact, if any, the radioactive materials released from CPS have on the generalpublic. This report is prepared in a way that is useful to a specialized scientific community. However, this introduction, the explanations in later sections, and minimal use of technical terms are all designed to make this report understandable and useful to those with no background in environmental monitoring. A. CT! 1RACTERISTICS OF RADIATION [ Atoms whose nuclei contain an excess of energy are ( called radioactive atoms. They release this excess
, energy by expelling electromagnetic or particulate radiation from their atomic centers to become stable f (non-radioactive). This process is called " radioactive decay". X-rays and gamma rays are examples of electromagnetic radiation and are similar in many ways to visible light, microwaves and radio-waves.
Particulate radiation may be either electrically charged such as alpha and beta particles, or has no charge, like neutrons. The term " half-life" refers to the time required for half of a given amount of a radionuclide to decay. Some radionuclides have a half-life as short as a fraction of a second, while others have a half-life as long as a million years. Radionuclides may u ay directly into stable elements or may undergo a series of decays which ultimately end up reaching a stable element. Radionuclides are found in nature (e.g., radioactive uranium, thorium, carbon and potassium), and may also be / H-1
Il1 I produced-artificially in accelerators and nuclear reactors (e.g., radioactive iodine, cesium and cobalt). NATURALLY OCCURRING MAN-MADE RADIONUCLIDES RAD 70NUCLIDES Uranium Iodine Thorium Cesium Carbon Cobalt Potassium Strontium Lead Barium The activity of a radioactive source is the average number of nuclear disintegrations (decay) of the source per unit of time. The unit of activity is called the curie. A one curie radioactive source undergoes 2.2 trillion diqintegrations per minute, but ip the realm of nuclear power plant effluents and environmental radioactivity, this is a large unit. Therefore, two fractional units, the microcurie and the picocurie, are more commonly used. 1 curie (Ci) = 2,220,000,000,000 disintegrations / minute I 1 millicurie (mci) = 2,220,000,000 disintegrationsiminute g 1 microcurie ( Cl) = 2,220,000 disintegrations / minute 3 1 nanocurie (nCi) = 2,220 disintegrations / minute 1 picoeurie (pCl) = 2.22 disintegrations / minute The microcurie (uCi) is one millionth of a curie (C1) and represents 2.2 million decays per minute. The picocurie (pCi) is one millionth of a microcurie and represents 2.2 decays per minute. Another way of comparing the pCi and the Ci is by analogy with distances. A picocurie would be the width of a pencil j mark while a curie would be 100 trips around the earth. Radioactivity is related to the half-life and the atomic mass of a radionuclide. For example, Uranium-235 (U-235) with a half-life of 704 million yearc requires about 462,400 grams to obtain an activity of one curie. But iodine-131 (I-131) with a half-life of 8.04 days only requires about 0.000008 grams to produce an activity of one curie. 1 Any mechanism that can supply the energy necessary to ionize an atom, break a chemical bond, or alter the chemistry of a living cell are capable of producing biological damage. Electromagnetic and particulate radiation can produce cellular damage in any of these I 11 - 2 1 l I
ways. In assessing the biological effects of radiation, the type, energy, and amount of radiation must be considered. External total body radiation involves exposure of all organs. Most background exposures are of this form. l When radioactive elements enter the body through 3 in.ialation or ingestion, their distribution may not be uniform. I TARGET TISSUE NUCLIDE Bone Strontium-90 Kidney Uranium-235 Thyroid Iodine-131 1 Muscle and Liver Tissue Cesium-137 Gastrointestinal Tract Cobalt-60 For example, radiciodine selectively concentrates in the thyroid gland, whereas radiocesium collects in muscle and liver tissue, and radiostrontium collects in mineralized bone. The total dose to organs by a given radionuclide is also influenced by the quantity and the duration of time that the radionuclide remains in the body. Owing to radioactive decay and human retabolism factors, some radionuclides stay in the body for very short times while others remain for years. The amount of radiation dose that an individual receives is expressed in rem. Since human exposure to radiation l usually involves very small exposures, the millirem I (mrem) is the unit most commonly used. One millirem is one thousandth of a rem. I 1 millirem = 0.001 Rem B. SOURCES OF RADIATION EXPOSURE Many sources of radiation exposure exist. The most common and least controllable source is natural background radiation from cosmic rays and the earth {- which mankind has always lived with and always will. Every second of our lives, over seven thousand atoms [ undergo radioactive decay in the body of the average [ adult. 11 - 3
I Radioactive elements have always been a part of our planet and everything that has come from the earth, including our own bodies is, therefore, naturally B radioactive. N Natural Radionuclides In The Earth's Crust I M wu e : - 4 L ,F-4, Radium-226 (Ra-226) U:w itn __3 :U-JL2 Radon-222 (Rn-222) Inc rit , .?' iTP- 'M Lead-204 (Pb-204) Examples of radioactive materials found in the Earth's crust today consists of radionuclides such as potassium-40, uranium-238, thorium-232, radium-226 and radon-222. l These radionuclides are introduced into the water, soil 5 and air by such natural processes as volcanic activity, weathering, erosion and radioactive decay. Some of the naturally occurring radionuclides, such as raden, are a significant source of radiation exposure to the general public. Radioactive radon is a chemically inert gas produced naturally in the ground as a part of the uranium and thorium decay series. Radon continues to undergo radioactive decay, producing new naturally 3 radioactive materials called " radon daughters". These 5 new materials, which are solid particles, not gases, can stick to surfaces such as dust particles in the air. Concentrations of radon in air are variable and are affected by concentrations of uranium and thorium in soil, as well as, altitude, soil porosity, temperature, pressure, soil moisture, rainfall, snow cover, atmospheric conditions, and season. Radon can move through cracks and openings into basements of buildings 3 and become trapped in a small air volume indoors. Thus, indoor radon concentrations are usually higher than 5 those found outdoors. Building materials such as cinder blocks and concrete are radon sources. Radon can also be dissolved in well water and contribute to airborne radon in houses when released through showers or washing. Dust containing radon daughter particles can be inhaled and deposited on the surface of an individual's lung, 3 I Radon daughters emit high energy alpha radiation dose to g the lung lining. Table 1 shows the average annual effective dose due tc radon. About three hundred cormic rays originating from outer space pass through each person every second. n.4 I l i I
Cosmic-Ray-Activated Radionuclides Beryllium-7 (Be-7) Tritium (H-3) Beryllium-10 (Be-10) Sodium-22 (Na-22) Carbon-14 (C-14) Phosphorus-32 (P-32) The interaction of cosmic rays with atoms in the earth's atmosphere produces radionuclides such as Beryllium-7, Beryllium-10, Carbon-14, tritium, and Sodium-22. Portions of these radionuclides become deposited on land or in water while the remainder stay suspended in the atmosphere. Consequently, there are natural radioactive materials in the soil, water, air and building materials that contribute to radiation doses to the human body. Natural drinking water contains trace amounts of uranium and radium; milk contains measurable amounts of potassium-40. Sources of natural radiation and their average contribut~ing radiation doses are summarized in Table 1. Figure 1 graphically shows the percentage contribution from principal sources of radiation exposure to the general population of the United States. Radiation exposure levels from natural radiation fluctuate with time and also can vary widely from location to location. The average individual in the United States receives erproximately three hundred mrem per year from natural sources. In some areas of the cou' cry, the dose from natural radiation is significant.. y higher. Residents of Colorado, five thousand feet above sea level, receive additional dose due to the increase in cosmic and terrestrial radiation levels. In fact, for every one thousand feet in elevation above sea level, an individual will receive an additional one mrem per year from cosmic radiation. In several areas of the world, high concentrations of mineral deposits result in natural background radiation levels of several thousand mrem per year. In addition to natural background radiation, the average individual is exposed to radiation from a number of man- _ made sources. The largest of these sources come from medical diagnosis: X-rays, CAT-scans, fluoroscopic examinations and radio-pharmaceuticals. Approximately 160 million people in the United States are exposed to medical or dental X-rays in any given year. The annual dose to an individual from such irradiation averages 53 mrem. 11 - 5
I I I I I E I I I I I I I I I I I ,, . e I I
TABLE 1 COMMON SOURCES OF RADIATION A. Average Annual Effective Dose Equivalent to the U.S. Population
- 1. Natural Sources mrem
- a. Radon 200
- b. Cosmic, Terrestrial, Intemal 100
- 2. Man-Made Sources mrem
- a. Medical X-ray Diagnosis 39 Nuclear Medicine 14
- b. Consumer Products 10
- c. Occupational 1
- d. Miscellaneous Environmental <1
- e. Nuclear Fuel Cycle <1 Approximate Total 360 NCRP87a PERCENTAGE OF CONTRIBUTION
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) .X BER M W NATURAL
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Environmental Sources
- Nuclear Fuel Cosmic, Terrestrial internal (27%)
FIGURE 1: DOSE CONTRIBUTIONS TO THE U.S. POPULATION FROM PRINCIPAL SOURCES OF RADIATION EXPOSURE 11 - 7
I I I E I E I I I I I I I I I I I I I
Smaller doses from man-made sources come from consumer products (e.g., television, smoke detectors, fertilizers), fallout from prior nuclear weapons tests, and production of nuclear power and iJ associated fuel cycle.
" Fallout" commonly refers to the radioactive debris that settles to the surface of the earth following the detonation of nuclear weapons. Fallout is dispersed throughout the environment but can be washed down to the Earth's surface by rain or snow.
Radionuclides Found in Fallout Iodine-131 (I-131) Strontium-90 (Sr-90) Strontium-89 (Sr-89) Cesium-137 (Cs-137) There are approximately two hundred radionuclides produced in the nuclear weapon detonation process; a number of these are detected in fallout. The radionuclides found in fallout that produce most of the fallout radiation exposures to man are iodine-131, strontium-89, strontium-90, and cesium-137. Il - 9
I C. DESCRIPTION OF THE CLINTON POWER STATION h The Clinton Power Station is located in Harp Township, DeWitt County, Illinois. It is .pproximately six miles east of Clinton, Illinois. The station, its V-shaped cooling lake, and the g surrounding Illinois Power Company-owned land encloses W 14,182 acres. This includes the 4,895-acre, man-made cooling lake and about 90 acres of privately owned g property. The plant is sited on approximately 150 acres on the northern arm of the lake. The cooling water g' discharge flume, which discharges to the eastern arm of , the lake, occupies an additional 130 acres. Although the nuclear reactor, supporting equipment, and associated electrical generation and distribution equipment lie in Harp Township, portions of the 14,182 E acres lie in Wilson, Rutledge, DeWitt, Creek, Nixon and 5 Santa Anna Townships. The cooling lake was formed by constructing an earthen dam near the confluence of Salt Creek and the North Fork of Salt Creek. The resulting lake has an average depth of 15.6 feet, and includes an ultimate heat sink of about 590 acre-feet. The ultimate heat sink provides sufficient water volume and cooling capacity for approximately thirty days of operation without makeup water. Through arrangements with the Illinois Department of Conservation, Clinton Lake and much of the area immediately adj acent to the lake are used for public recreation activities, including swimming, boating, water-skiing, hunting and fishing. Recreational E facilities exist at Clinton Lake and accommodate up to B 11,460 people per day during peak usage periods. The outflow from Clinton Lake falls into Salt Creek and g flows in a westerly direction for about 56 miles before g joining the Sangamon River. The Sangamon River drains into the Illinois River which enters the Mississippi River near Grafton, Illinois. The nearest use of downstream water for drinking purposes is 242 river miles downstream of Clinton Lake at Alton, Illinois, as verified from the Illinois Environmental Protection 3 Agency Public Water Service. Although some farms in the E Salt Creek drainage area downstream of Clinton Lake use irrigation, the irrigation water is drawn from wells, not from the waters of Salt Creek. Approximately 810,000 individuals live within 50 miles of the Clinton Power Station. Over half are located in the major metropolitan centers of Bloomington-Normal (located about 23 miles north northwest), Champaign- } Urbana (located about 31 miles east), Decatur (located 11 - 1 0 I
about 22 miles south southwest) and Springfield (located aoout 48 miles west southwest). The nearest city is Clinton, the county seat of DeWitt County. The estimated population of Clinton is about 8,000 people. Outside of the urban areas, most of the land within 50 miles of the l Clinton Power Station is used for farming. The j principal crops grown are corn and soybeans. D. NUCLEAR REACTOR OPERATIONS The fuel of a nuclear reactor is made of the element uranium in the form of uranium oxide. The fuel produces ! power by the process called " fission". In fission, the l uranium atom absorbs a neutron and splits to produce fission products, heat, radiation atA free neutrons. l The free neutrons travel in the reactor core and further absorption of neutrons by uranium permits the fission i process to continue. As the fission process continues, , more fission products, radiation, heat and neutrons are ' produced and a sustained reaction occurs. The heat produced is extracted from the fuel to produce steam that drives a turbine generator to produce electricity. The fission products are predominantly radioactive. They are unstable elements that emit radiation as they change from unstable to stable elements. Neutrons that are not absorbed by the uranium fuel may be absorbed by stable atoms in the materials that make up the ( components and structures of the reactor. In such cases, stable atoms often become radioactive. This process is called " activation" and the radioactive atoms which result are called " activation products". Fission Products Activation Products l Cesium-134 (Cs-134) Cobalt-60 (Co-60) Cesium-137 (Cs-137) Manganese-54 (Mn-54) Ruthenium-106 (Ru-106) Iron-55 ( Fe- 5 5 ) Barium-140 (Ba-140) Iron-59 (Fe-59) Cerium-144 (Ce-144) Zinc-65 ( 2n- 6 5 ) Strontium-89 (Sr-90) Tritium (H-3) The reactor at the Clinton Power Station is a boiling water reactor (BWR). Figure 2 provides a basic plant schematic for the Clinton Power Station and shows the separation of the cooling water from plant systems. In this type of reactor the fuel is formed into small l ceramic pellets that are loaded into sealed fuel rods. l ll - 11
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The fuel rods are arranged in arrays called bundles that are supported within a massive steel reactor vessel. The spaces between the fuel rods are filled with water. The heat released during the fission of fuel atoms is transferred to the water surrounding the fuel rods. A type of pump that contains no moving parts (a j et pump) , and recirculation pumps are used to force the water to circulate through the fuel bundles to assure even cooling of the fuel rods. As the water absorbs heat from the fuel rods some of it is changed to steam. The steam is used to drive a turbine which is coupled to a generator, thereby completing the conversion of the energy released during fission to electricity. After the steam passes through the turbine it is condensed back to water and returned to the reactor vessel to repeat the process. As the water circulates through the reactor pressure vessel, corrosion allows trace quantities of the component and structure surfaces to get into the water. The corroded material also contains radioactive substances known as activated corrosion products. Radioactive fission and activation products are normally confined to the primary system although small leaks from the primary system may occur. E. CONTAINMENT OF RADIOACTIVITY During operating conditions, essentially all radioactivity is contained within the first of several barriers that collectively prevent escape of radioactivity to the environment. The fuel cladding (metal tubes) provides the first barrier. The ceramic fuel pellets are sealed within zircaloy metal tubes. There is a small gap between the fuel and the cladding where the noble gases and volatile nuclides collect. The reactor pressure vessel and the steel piping of the primary coolant system provide the second barrier. The reactor pressure vessel is a seventy-foot high vessel with steel walls ranging from four to seven inches thick which encase the reactor core. The reactor pressure vessel and the steel piping provide containment for all radionuclides in the primary coolant. The Containment Building provides the third barrier. The Containment Building has steel-lined, four-foot-thick reinforced concrete walls which completely enclose the reactor pressure vessel and vital auxiliary equipment. This structure provides a third line of H-15
' I defense against the uncontrolled release of radioactive materials to the environment. The massive concrete l walls also serve to absorb much of the radiation emitted a during reactor operation or from radioactive materials I created during reactor operations. F. SOURCES OF RADIOACTIVE EFFLUENTS In an operating nuclear power plant, most of the fission 3 products are retained within the fuel and fuel cladding. 3 However, the fuel manufacturing process leaves traces of uranium on the exterior of the fuel tubes. Fission products from the eventual fission of these traces may be released to the primary coolant. Other small amounts of radioactive fission products are able to diffuse or migrate through the fuel cladding and into the primary E coolant. Trace quantities of the corrosion products 5 from component and structural surfaces that have been activated, also get into the primary coolant. Many soluble fission and activation products such as radioactive iodines, strontiums, cobalts and cesiums are removed by demineralizers in the water purification systems. The noble gas fission products, activated atmospheric gases introduced with reactor feedwater, and some of the volatile fission products such as iodine and g bromine, are carried from the reactor pressure vessel to 3 the condenser with the steam. The steam jet air ejectors or the condenser vacuum pump remove the gases from the condenser and transfer them to the off-gas treatment system. In the off-gas treatment system, the gases are held up by adsorption on specially treated charcoal beds to allow radioactive gases to decay before they are released through the main ventilation exhaust stack. Small releases of radioactive liquids from valves, piping, or equipment associated with the primary coolant system may occur in the Containment, Auxiliary, Turbine, RadWaste and Fuel Buildings. The noble gases become part of the gaseous wastes while the remaining radioactive liquids are collected in sumps and processed E for reuse. Processed primary coolant water that does 5 not meet chemical specifications for reuse may also become waste water. These represent the principal a sources of liquid effluents. g E ll - 16 I
G. RADIOACTIVE WASTE PROCESSING In a normal operating nuclear power plant, radioactive liquid and gaseous wastes are collected, stored and processed through treatment systems to remove or reduce most of the radioactivity (excluding tritium) prior to reuse within the plant or discharge to the environment. i These processing systems are required by the Clinton Power Station Offsite Dose Calculation Manual to be installed and operable to help ensure all releases of radioactive liquid and gaseous effluents are As -Low As ~ ~ Reasonably Achievable (ALARA). The liquid waste tr3atment systems consist of filters, demineralizers and evaporators. Liquid wastes are routed through the waste evaporators to be degassed and volume I distilled thereby reducing concentrating their radioactivity. their The distillates further treated through demineralizers and filters and and are transferred to the waste evaporator condensate storage I tanks. Liquid wastes are processed through appropriate portions of the liquid waste treatment the system to provide assurance that the releases of I radioactive materials in liquid effluents will be kept ALARA. 3 Liquid wastes are discharged into the plant cooling l water stream which varies from approximately 5,000 gallons per minute, when the plant is in shutdown, to 567,000 gallons per minute, when the plant is at full power. The liquid effluents are thoroughly mixed with and diluted by the plant cooling water as it travels the 3.4 miles of the discharge canal before it enters Clinton Lake east of DeWitt County Road 14. The Clinton Power Station Offsite Dose Calculation g Manual requires that liquid effluents not contain a l higher concentration of any radioisotope than that which is set for continuous exposure to the general public. This condition is satisfied at the point the liquid effluent is first introduced into the cooling water I flow. The additional dilution that occurs in the cooling water canal reduces the concentrations of radioisotopes to between 1/73 (for minimum flow) and I 1/1890 (for maximum flow) of their original value before the water enters Clinton Lake. The concentrated radioactive solids captured in the j liquid waste treatment system are processed and stored l on-site or shipped off-site for disposal at licensed low-level waste disposal facilities. l The gaseous effluents from the main condenser are held up in the off-gas charcoal beds for at least 46 hours. ll - 17
I This provides time for the decay of most of the g radionuclides present since most have a half-life of g less than 8 hours. If gaseous effluents in the ventilation exhaust system for the Containment Building and for the Secondary Containment structure exceed conservatively set levels, they are processed through charcoal beds and high efficiency particulate air filters in the Standby Gas Treatment System before being discharged to the environment. This combination of filters and charcoal beds is rated to be 95% efficient for removing iodines and greater than 99% efficient for removing particulate material larger than one micron (one millionth of an inch) in diameter. I I I I I I I I I I I
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IH. RADIOLOGICAL ENV1RONMENTAL MONITORING PROGRAM A. PROGRAM DESCRIPTION The Clinton Power Station is required to maintain a radiological environmental monitoring program in accordance with the Code of Federal Regulations (CFR) Title 10, Section 20.1501 and Criterion 64 of CFR Title 10, Part 50, Appendix A. The program was developed using the following guidance published by the United States Nuclear Regulatory Commission (USNRC) :
=> Regulatory Guide 4.1, " Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants"
=> USNRC Radiological Assessment Branch Technical Position on Radiological Environmental Monitoring (1979)
The Radiological Environmental Monitoring Program is an extensive program of sampling, measuring and analyzing that was instituted to monitor the radiological impact of reactor operation on the environment. Objectives of the program include: 0 identification, measurement and evaluation of existing radionuclides in the environs of the Clinton Power St3 tion and fluctuations in radioactivity levels which may occur 0 evaluation of the measurements to determine the impact of Clinton Power Station operations on the local radiation environment 0 collection of data needed to refine environmental radiation transport models used in offsite dose calculations 0 verification that radioactive material containment systems are functioning to minimize environmental releases to levels that are ALARA 0 demonstration of compliance with regulations and the Clinton Power Station Offsite Dose Calculation Manual. Implicit in these objectives are the requirements to trend and assess radiation exposure rates and radioactivity concentrations in the environment that may contribute to radiation exposure to the public. The program consists of two phases, preoperational (preop) and operational. lil-1
l ' The preoperational portion of the program was initiated in May, 1980 and was completed on February 27, 1987 to establish the baseline for the local Assessment of the operational impact of the radiation 3 wavironment. 3 Clinton Power Station on the radiation environment is l based on data collected since the beginning of reactor g operation. The operational phase implements confirmatory measurements to verify that the in-station controls for g the release of radioactive material are functioning as designed. l Illinois Power Company maintains a contract with Teledyne l Isotopes Midwest Laboratory (TIML) dab Teledyne Brown E
- Engineering Environmental Services Midwest Laboratory g (TBEESML), for analysis of all radiological environmental samples. TIML is located in Northbrook, Illinois.
Samples are collected by Illinois Power Company personnel and shipped to TIML for analysis. After analysis, environmental samples are saved at TIML for a specified period of time in case additional analysis is required. E Analytical results are reported monthly to company W radiation protection personnel. Current regulatory guidance recommends evaluating direct pathways, or the highest trophic level in a dietary pathway, that contribute to an individual's dose. Figure 3 shows the bacic pathways of gaseous and liquid radioactive effluents to an individual. The "important pathways" selected are based primarily on how radionuclides move through the environment and eventually 3 l expose individuals, environment. as well as man's use of the The scope of the program includes the 3 monitoring of five environmental compartments: 1 direct radiation l atmospheric aquatic E terrestrial environments W ground and surface water. Each pathway is monitored at " indicator" and " control" locations. Indicator locations are generally within the 10-mile radius of the station and at locations which are - expected to manifest station effects, if any exists. Control locations are located at least ten miles from the plant, far enough to be unaffected by plant operations. These control samples provide a basis by which to evaluate g fluctuations in radioactivity at indicator locations in g relation to natural phenomena and fallout. An increase in dose rate or radioactive material concentration at an indicator location may be due to plant operations. 111- 2 I I
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l Sampling locations were established by considering site meteorology, population distribution, site hydrology, and land use characteristics of the local area. These locations were selected primarily on the basis of where the highest predicted environmental concentrations would occur. Locations of sampling stations are shown on maps in i Figures 4 through 7. Table 2 provides a list of the sample codes for each sample medium. Table 3 provides information on sample location, media sampled at each location, and a brief description of each location where samples are taken. The location is listed according to distance (in miles) and the compass sector relative to the Station Heating, Ventilation and Air Conditioning (HVAC) stack. i l l l l 1 l Ill-5
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l TABLE 2 CLINTON POWER STATION SAMPLE CODES CODE SAMPLE MEDIUM AP Airborne Particulate AI Airborne Iodine TLD Direct Radiation M Milk DW Drinking Water SW Surface Water WW Well Water VE Green Leafy Vegetables F Fish SL Slime or Aquatic Vegetation BS Bottom Sediments SS Shoreline Sediments SO Soil ME Meat G Grasa lil-15
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REMP SAMPLE LOCATIONS
- r Station Sample Code Medium Location Description CL-1 AP,Al,TLD SO G 1.8 miles W Near the gate to Camp Quest, S of Birkbeck CL-2 AP Al,TLD.SO,G 0.7 miles NNE Located on site's main access road.
Collocated with CL-70 and CL-71. g CL-3 AP Al,TLD,SO 0.7 miles NE Located on site's secondary access road. Collocated with CL-69. CL-4 AP,Al,TLD,SO 0.8 miles SW Located on farm SE of Illinois Power Recreation Area. Collocated with CL-67. CL-5 TLD 0.7 miles NNE Located on site's main access road CL-6 AP,Al,TLD.SO 0.8 miles WSW Located near the Illinois Power Recreation Area softball field. Collocated with CL-66. CL-7 AP,Al,TLD.SO 2.3 miles SE Located in the Mascoutin State Recreation Area CL 78 SS,SL 2.1 miles SE SE of site on Clinton Lake CL-7C BS.SL,SS 1.3 miles SE SE of site on Clinton Lake CL-7D WW 2.3 miles ESE Located in Illinois Power Department of 1 Conservation office at the Mascoutin State Recreation Area CL-8 AP,Al,TLD.SO,G 2.2 miles E Located at DeWitt Cemetery CL-9 SW,SL 2.7 miles ESE Located on NE side of DeWitt County Route 14 bridge CL-10c SW(1),BS.SS,SL 5.0 miles ENE Located on SE side of Illinois Route 48 bridge CL-11c AP Al.TLD,SO,G I 16 miles S Located SW of Argenta at the lilinois Power Substation CL-12 WW 1.6 miles E Located at the DeWitt pumphouse l CL-13 SW 3.6 miles SW Located near the Salt Creek bridge on Illinois Route 10 CL-13A BS 5.0 miles SW Located on Salt Creek at the Route 1300E bridge CL-14 DW Plant Service Located in the Plant Service Building Building lil-17
I TABLE 3 (Cont'd) Station Sample Medium Location Description W Code CL-15 AP,Al,TLD 0.9 miles N Located north of CPS on Route 900N CL-16 SO 0.6 miles ESE Located ESE of CPS just north of discharge fiume CL-17 BS 3.5 miles SW Located on the take side of Clinton Lake dam CL-19 F.BS,SS,SL 3.4 miles E Located E of site at the end of the discharge flume CL-20 TLD 9.1 miles ENE Located at the Campground Cemetery W of Farmer City CL-21 TLD 0.9 miles NNE Located at the intersection of Illinois Route 54 and the site's secondary access road E CL-22 TLD 0.6 miles NE Located on the site's seconddry access road CL-23 TLD 0.5 miles ENE Located on the site's secondary access road CL-24 TLD 0.5 miles E Located on the site's secondary access road h. CL-25 TLD 0.4 miles ESE Located on the Owner Controlled Area fence CL-26 TLD 0.3 miles SE Located on the Owner Controlled Area fence CL-27 TLD 0.6 miles SSE Located on the Owner Controlled Area fence near the Meteorological Tower CL-28 TLD 0.5 miles S Located on the Owner Controlled Area fence CL-29 TLD 0.6 miles SSW Located on the Owner Controlled Area fence CL-30 TLD 0.7 miles SW Located on the Owner Controlled Area fence at the entrance to Illinois Power Recreation Area CL-31 TLD 0.8 miles WSW Located on the Owner Controlled Area fence near the lilinois Power Recreation Area softball field CL-32 TLD 0.7 miles WSW Located on the Owner Controlled Area fence near Clinton Lake CL-33c TLD 11.7 miles SW Located in Maroa at family residence lll-18 I
TABLE 3 (Cont'd) Station Sample Code Medium Location Qescnotion CL-34 TLD 0.8 miles WNW Located near CPS Visitors Center CL-35 TLD 0.7 miles NW Located near CPS Visitors Center near Illinois Route 54 bridge CL-36 TLD 0.6 miles N Located on lilinois Route 54 near intersection with site's main access road CL-37 TLD 3.4 miles N Located N of site CL-38 TLD 3.6 miles NNE Located near microwave tower N of site CL-39 TLD 3.8 miles NE Located 2 miles N of DeWitt CL-40 TLD 3.5 miles NE Located 0.6 miles N of DeWitt CL-41 TLD 2.4 miles E Located at S DeWitt city limit CL-42 TLD 2.8 miles ESE Located S of DeWitt County Route 14 bridge CL-43 TLD 2.8 miles SE Located on Clinton Marina access road CL-44 TLD 2.3 miles SSE Located near Clinton Marine Boat Sales CL-45 TLD 2.8 miles S Located at Lane Day Use Area CL-46 TLD 2.8 miles SSW Located at Peninsula Day Use Area CL-47 TLD 3.3 miles SW Located near Clinton Lake Dam Access Road CL-48 TLD 2.3 miles WSW Located at residence on West Side Access Road CL-49 TLD 3.5 miles W Located W of site along Illinois Route 54 CL-50 TLD 3.2 miles WNW Located WNW of site CL-51 TLD 4.4 miles NW Located NW of site CL-52 TLD 4.3 miles NNW Located NNW of site CL-53 TLD 4.3 miles E Located E of site CL-54 TLD 4.6 miles ESE Located 2 miles N of Weldon CL-55 TLD 4.1 miles SE Located 1.5 miles W of Weldon CL-56 TLD 4.1 miles SSE Located SSE of site 111- 1 9
TABLE 3 (Cont'd) Station Sample
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Code Medium Location Rescription CL-57 TLD 4.6 miles S Located b of site CL-58 TLD 4.3 miles SSW Located in rural Lane CL-59 TLD 3.3 miles SSW Located near Lane city limit CL-60 TLD 4.5 miles SW Located SW of Clinton Lake Dam near Salt Creek TLD 4.5 miles WSW Located WSW of site = CL-61 CL-62 TLD 1.9 miles NW Located NW of site CL-63 TLD 1.3 miles NNW Located at North Fork Boat Access CL-64 TLD 2.1 miles WNW Located 0.5 miles N of Birkbeck CL-65 TLD 2.6 miles ENE Located at residence in DeWitt CL-66 TLD 0.8 miles WSW Located near the !!!inois Power Recreation Area softball field. Collocated with CL-6. CL-67 TLD 0.8 miles SW Located on farm SE of Illinois Power Recreation Area. Collocated with CL-4. CL-68 TLD 4.6 miles N Located N of site. Collocated with CL-112. CL-69 TLD 0.7 miles NE Located on site's secondary access road. Collocated with CL-3. CL-70 TLD 0.7 miles NNE Located on site's secondary access road. Collocated with CL-2 and CL-71. CL-71 TLD 0.7 miles NNE Located on site's secondary access road. Collocated with CL-2 and CL-70. CL-72 TLD 4.5 miles NNE Located NNE of site. Collocated with CL-77. CL-73 TLD 5.1 miles ENE Located near the MidAmerica Commodities plant on lilinois Route 48. Collocated with CL-113. CL-74 TLD 1.9 miles W Located at Camp Quest CL-75 TLD 0.9 miles N Located N of site CL-76 TLD 4.6 miles N Located N of site CL-77 TLD 4.5 miles NNE Located NNE of site. Collocated with CL-72. I 111- 2 0 I
TABLE 4 (Cont'd) Station Sample i Code Medium Location Descnotion CL-78 TLD 4.8 miles NE Located NE of site ! CL-79 TLD 4.5 miles ENE Located ENE of site l CL-80 TLD 4.1 miles W Located W of site CL-81 TLD 4.5 miles WNW Located WNW of site CL-82 TLD 0.9 miles W Located at Illinois Power Recreation Area l l CL-83 TLD 0.5 miles NNW Located near lilinois Route 54 E of the bndge CL-84 TLD 0.6 miles E Located on Old Clinton Road between DeWitt and site. Collocated with CL-94 and CL-86. CL-85 TLD 0.6 miles ESE Located ESE of site CL-86 TLD 0.6 miles E Located on Old Clinton Road between DeWitt and site. Collocated with CL-84 and CL-94. CL-87 TLD 0.6 miles SE Located neardischarge fiume road l CL-88 SS 2.4 miles SE Located SE of site l CL-89 BS,SS 3.6 miles NNE Locatec NNE of site CL-90 SW 0.4 miles SE Located at start of discharge fiume CL-91 SW 6.1 miles ENE Located at Parnell Boat Access CL-94 AP,Al.SO 0.6 miles E Located on Old Clinton Road between DeWitt and site, Collocated with CL-84 and CL-86. CL-95c TLD 10.5 miles W Located at a family residence west of Clinton CL-96c TLD 10.9 miles WSW Located at a family residence SW of Clinton CL-97c TLD 10.3 miles SSW Located on Ma ,unty Road 1400E SE of Maroa CL-106 ME 2.0 miles NNE Located NNE of site CL-99 SW 3.5 miles NNE Located at the North Fork Canoe Access Area CL-105c F SS,BS,SL 50 miles S Located at Lake Shelbyville I l 111- 2 1 l
I l [ l TABLE 4 (Cont'd) Station Sample Code Medium Location Description CL-109 TLD 0.7 miles WSW Located on the Owner Controlled Area fence near Shooting Range CL-110 TLD 0.8 miles SW Located on the Owner Controlled Area fence ! CL-111 TLD 0.6 miles NE Located near site's secondary access road CL-112 TLD 4.6 miles N Located N of site. Collocated with CL-68. , CL-113 TLD 5.1 miles ENE Located near the MidAmerica Commodities p! ant i on Illinois Route 48. Collocated with CL-73. ' t ! CL-114c VE 12.5 miles SSE Located 7 of Cisco CL-115 VE 0.7 miles NF. Located on site's secondary access road CL-116c M,G 14 miles WSW Located in rural Kenney g g CL-117 VE 0.9 miles N Located N of site CL-118 VE 0.7 miles NNE Located on Illinois Route 54 near intersection W with main access road
- Sample location is listed by station code, location and number. Station Code is Clinton (CL)- Number l g
(site's number designator). Location is listed by distance in miles and directional sector from the Station HVAC stack. c Control location; all other locations are indicators. (1) Control location for surface water only. l I i I I lll-22 I I
B. Direct Radiation Monitoring 4 Radionuclides present in the air, and those deposited in or on the ground cause human exposure.by immersion in the atmosphere or by deposition on the ground. TLDs (thermoluminescent dosimeters) are used to measure the ambient gamma radiation field at many locations around the Clinton Power Station. TLDs are crystalline devices that store energy when they are exposed to radiation. They can be processed months after exposure with minimal loss of information. This makes them well suited for quarterly environmental radiation measurements. During processing, the stored energy is released as light and measured by a TLD reader. The light intensity is proportional to the radiation dose the TLD received. The TLDs used in monitoring around the Clinton Power Station are easily capable of measuring environmental levels of radiation, approximately 20 mrem per quarter. Monitoring stations are placed near the site boundary and . approximately five miles from the reactor, in locations representing the sixteen compass sectors. Other locations are chosen to measure the radiation field at places of special interest such as nearby residences, meeting places and population centers. Control sites are located further than ten miles from the site, in areas that should not be affected by plant operations. l TLD measurements register the gamma ray exposure in milliroentgen (mR). For reporting purposes mR is 1 numerically equivalent to mrem. Consequently the terms l are used interchangeably. ' A total of 342 TLD measurements were made in 1997. The average quarterly dose at indicator locations was 16.8 4 mrem. These quarterly measurements ranged from 11.8 to 21.1 mrem. At control locations the average quarterly dose was 17.1 mrem. These quarterly control measurements ranged from 14.0 to 19.5 mrem. Figure 8 compares the 1997 quarterly TLD results with preoperational TLD quarterly averages. Average doses (i2 standard deviations), broken down by calendar quarter, are shown in Table 4 for both indicator and control locations. lll-23
I I I I i l' E l' I I I I I I I l 1 l I a
r 4 o l a ac tor t t a i n D d o p I n C o 7 7 N e 9 9 r 9 9 P O 1 1 S m 5 D I R A P M O 3 C N O I T A I r D e A t r a R u T Q C E 2 R I D _ 8 _ E _ R U G I F 1 0 8 6 4 2 0 3 2 2 2 2 2
TABLE 4 AVERAGE QUARTERLY TLD RESULTS I 1997 1996 PREOP ' OUARTER INDICATOR INDICATOR ALL SITES 1st 15.0 2.6 18.8 3.6 16.4 i 2.9 2nd 16.2 1 2.9 17.2 1 3.3 18.8 i 3.2 3rd 17.6 i 2.9 15.7 i 3.0 19.1 i 4.7 4th 18.4 i 1.3 18.5 i 3.6 17.8 i 2.2 1997 1996 PREOP OUARTER CONTROL CONTROL ALL SITES 1st 15.3 i 2.2 19.0 i 3.1 I 2nd 16.8 i 2.9 17.7 i 2.3 16.4 18.8 1 i 2.9 3.2 3rd 17.8 1 3.2 15.9 i 3.2 19.1 i 4.7 4th 18.4 2.6 19.9 i 2.5 17.8 i 2.2 Site CL-45, located 2.8 miles S of the station, registered the highest annualized dose: 76.4 mrem for the year. From these observations, no increase gamma radiation levels resulted in environmental from operation of I Clinton Power Station. the C. Atmospheric Monitoring The inhalation and ingestion of radionuclides in the air is a direct exposure pathway to man. A network of ten active air samplers around the Clinton I monitors this pathway. There are nine Power Station indicator air sampling stations strategically located in areas which are most likely to indicate effects due to the release of radioactive effluents from the Clinton Power Station. The control location is located approximately 16 miles south of the of the plant in an area which is likely to be independent effects of station operations. Historical meteorological data indicates this control location is normally upwind from the plant. No contribution to the general level of airborne particulate of station radioactivity could be identified as a result operations. The radioactivity that was detected is normally found in the environment and is consistent with expected concentrations of natural radioactivity and fallout from prior atmospheric nuclear weapons testing. Mechanical air samplers are used to draw a continuous volume of air through a filter and charcoal cartridge to 111- 2 7
I collect particulates and radiciodines present in the atmosphere. The samplers are equipped with a pressure-sensing flow regulator to maintain a constant sampling flow rate of about one cubic foot per minute. The total E volume is calculated based on the amount of time the air 5 sampler ran and its flow rate. The air sampling equipment is maintained and calibrated by the Clinton Power Station a personnel using reference standards traceable to the g National Institute of Standards and Technology. Air samples are collected weekly and analyzed for gross beta and I-131 activities. Quarterly, all air particulate filters collected during that period are combined and counted for gamma isotopic activity. Since the intent of 3 particulate sampling is to measure airborne radioactivity 'E released from the plant, the counting of short-lived daughters produced by the decay of natural radon and thoron may mask plant contributions. Therefore, the filters are not analyzed for at least five days after their collection to allow for the decay of the short-lived daughters, thereby reducing their contribution to gross E beta activity. 5 Results of the gross beta airborne particulate analyses g provided comparisons between indicator and control g l locations for the year, as well as comparisons between locations in relation to spatial and temporal differences. l The calculated annual average was 0.022 pCi/m3 for all indicator locations and 0.022 pCi/m3 for the control location. These results are consistent with the j preoperational averages for both indicator and control i locations which were 0.027 pCi/m 3, l The location with the highest calculated annual average was the control station CL-11 which is located 16 miles south of the Clinton Power Station. This location had an average concentration of 0.023 pCi/m3 Individual location averages for the year are presented in Table 5. Minor fluctuations in the gross beta concentrations were noted throughout the year. The general trend for average g weekly gross beta concentrations in the indicator g locations correlated to the trend for control locations throughout the monitoring period. This correlation is evidenced by the similarity of the trends in the average l l monthly gross beta concentrations displayed in Figure 9.
- No significant difference was indicated between individual locations. Monthly averages for indicator and control locations for the year are presented in Table 6.
All gross beta concentrations for the year were within g normal background levels and no increases were noted as a E result of the operation of the Clinton Power Station. lll-28 I I-
l Naturally occurring Be-7 was the only gamma-emitting radionuclide detected in analyses of particulate filters. I TABLE 5 AVERAGE GROSS BETA CONCENTRATIONS IN AIR PARTICULATES I 1996 1997 Average i 20 Average 20 Station Description (pci/m 3) (pci/m 3) CL-1 Camp Quest (Birkbeck) 0.020 i 0.013 0.022 i 0.015 CL-2 CPS Main Access Road 0.020 1 0.012 0.022 1 0.017 CL-3 CPS Secondary Access 0.021 1 0.012 0.023 1 0.014 Road CL-4 0.8 miles SW 0.021 i 0.012 0.02.2 1 0.015 Cir 6 IP Recreation Area 0.020 1 0.012 0.022 1 0.016 CL-7 Mascoutin State 0.019 i 0.012 0.021 1 0.017 Recreation Area CL-8 DeWitt Cemetery 0.020 i 0.012 0.021 1 0.014 CL-11a IP Substation 0.021 1 0.013 0.022 1 0.016 (Argenta) CL-15 0.9 miles N 0.019 1 0.013 0.020 1 0.016 CL-94 Old Clinton Road 0.020 1 0.014 0.022 i 0.016 i (0.6 miles E) (a) Control Station i 1 1 l l lll-29
I TABLE 6 AVERAGE MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES* 1997 1996 1997 1996 Indicator Indicator Control Control Month (Avwrage i 20) (Average i 20) (Average i 25) (Average i 20) January 0.026 10.002 0.023 10.002 0.026 10.010 0.026 10.014 February 0.022 10.002 0.020 10.002 0.021 iO.008 0.023 10.020 March 0.018 10.002 0.018 10.002 0.018 10.005 0.019 10.007 April 0.018 i0.002 0.015 10.003 0.018 iO.008 0.014 10.003 May 0.015 10.002 0.015 10.002 0.014 10.010 0.017 10.004 l June 0.016 10.003 0.015 10.002 0.0,17 10.011 0.017 10.014 ' July 0.021 10.002 0.016 10.003 0.022 10.016 0.019 10.006 August 0.023 i0.003 0.022 i0.003 0.024 10.015 0.025 iO.003 l September 0.025 10.002 0.025 .10.002 0.027 10.011 0.027 10.019 October 0.024 10.003 0.024 10.002 0.023 iO.011 0.023 i0.009 November 0.027 10.002 0.020 10.001 0.029 i0.029 0.020 10.014 December 0.025 10.003 0.026 10.003 0.026 10.020 0.026 10.008
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D. Acuatic Monitorina The Clinton Power Station utilizes a man-made lake as the source of cooling water and returns the used cooling water to the same lake while most nuclear power stations use once-through flow from a river, the ocean or a body of water much larger than Clinton Lake. When radioactive liquid effluents are discharged from the Clinton Power Station into the cooling water outfall, radioisotopes with long half-lives could build up as the same water is reused j on successive trips through the plant. This water travels l from the plant, into the eastern arm of the lake, then into the northern arm of the lake and back into the plant. Although the only user of Clinton Lake as a source of drinking water is the Clinton Power Station, the lake is a major recreational facility, used for fishing, swimming, water skiing, boating and hunting. r l Clinton Lake constitutes the primary environmental l exposure pathway for radioactive materials in liquid effluents. Aquatic monitoring provides for the collection of fish, shoreline and bottom sediments, and periphyton , samples to detect the presence of any radioisotopes l related to operation of the Clinton Power Station. These l samples are analyzed for naturally occurring and man-made l radioactive materials. Both indicator and control locations were sampled. Indicator samples were taken from various locations on Clinton Lake and the control samples l were taken at Lake Shelbyville which is approximately 50 miles south of Clinton Power Station. Aquatic monitoring samples are collected by personnel from the Field Biology Laboratory of the Environmental Resources Department of Illinois Power Company. l l Fish l l Samples of fish are collected from Clinton Lake and Lake Shelbyville. In both lakes the samples include largemouth bass, crappie, carp and bluegill. These species are the fish most commonly harvested from the lakes by sport fishermen. Fish ingest sediments during bottom feeding, or prey on other organisms which ingest sediments or otherwise retain radionuclides. Radiological analyses of these fish samples provide information on the potential ingestion of radionuclides by humans via the aquatic pathway. These samples are collected semiannually and analyzed by gamma spectroscopy. t The results of gamma isotopic analysis on the fish samples showed the presence of naturally occurring K-40 in all samples ranging from 2.28 to 3.18 pCi/g (wet) .
'Preoperational K-40 concentrations ranged from 1.71 to 4.61 pCi/g (wet). All other analytical results were less lil-33
than the lower limit of detection (LLD) for each radionuclide. Shoreline Sediments Samples of shoreline sediments are collected at six locations from Clinton Lake and at one location from Lake 3 Shelbyville. Radiological analyses of shoreline sediments g provide information on the potential shoreline exposure to humans and for determining long-term trends and accumulation of long-lived radionuclides in the environment. Samples are collected semiannually and - analyzed for gross beta, groes alpha, Sr-90 and gamma isotopic activities. Shoreline sediment samples are dried prior to analysis and the results are reported in pCi/g dry weight. Naturally g occurring radioisotopes, such as K-40, Be-7, Ra-226 and g Pb-210, were present in samples taken at both indicator and control locations. There was one fission product, Cs-137 detected at one indicator location. The activity- h W detected was not substantially different from that measured during the preoperational program. The presence of these fission products is attributed to previous nuclear weapons testing and atmospheric fallout from the accident at chernobyl. Preop Range 1997 Range 1996 Range I (oCi/ofdrv) (oCi/ofdrv) (DCi/ofdrv) Cs-137 0.016 - 0.045 0.014 - 0.032 0.017*
- Only one positive result was identifed.
Gross alpha activity was detected at one indicator I location which ranged from 4.41 to 8.43 pCi/g (dry) . This activity was attributed to naturally occurring l radioisotopes and decay products present in soil. This a value compare closely with the activity detected in the preoperational program which ranged from 3.8 to 8.0 pCi/g (dry). Gross beta activity in samples of shoreline sediments collected from all locations ranged from 6.53 to 16.65 l W pCi/g(dry). The majority of this activity was attributed to naturally occurring K-40. These values are comparable with the gross beta activity detected in the E preoperational program which ranged from 7.0 to 17.2 pCi/g 3 (dry). I lll-34 I I
Bottom Sediments Samples of bottom sediments are collected from ~Clinton Lake at six locations and Lake Shelbyville at one location. Radiological analyses of bottom sediments primarily provide information about the amount of radionuclides avai.lable to predators who feed on the organisms found in bottom sediments. Samples are collected semiannually and analyzed for gross beta, gross alpha, Sr-90 and gamma isotopic activities. Bottom sediment samples are dried prior to analysis and the results are reported in pCi/g dry weight. Naturally occurring radioisotopes, such as K-40 and Pb-212, were present in all control and indicator sample locations. Cs-137 and Sr-90 was detected in samples from both indicator and control locations. Both radioisotopes are fission products. Preop Range 1997 Range 1996 Range (DCi/c drv) (DCi/a drv) (DCi/c drv) Sr-90 0.011 - 0.056 0.017 - 0.075 0.011 - 0.027 Cs-137 0.008 - 1.39 0.013 - 0.398 0.016 - 0.323 The presence of these fission products is attributed to previous nuclear weapons testing and atmospheric fallout from the accident at Chernobyl. Gross alpha activity in samples of bottom sediments collected from both lakes ranged from 4.36 to 22.47 pCi/g (dry). This activity was attributed to naturally occurring radium isotopes and decay products present in soil. The preoperational gross alpha activity ranged from 4.4 to 14.7 pCi/g (dry). Gross beta activity in samples of bottom sediments collected from both lakes ranged from 7.09 to 32.69 pCi/g (dry) . The majority of this activity was attributed to naturally occurring K-40. The preoperational gross beta activity ranged from 8.3 to 27.7 pCi/g(dry). Acuatic Vecetation ( Perichyt on). Samples of periphyton are collected from five locations in Clinton Lake and one location in Lake Shelbyville. Periphyton (attached algae) are collected from the submerged surface of the permanently anchored buoys or natural substrate. Periphyton absorb trace elements and 111- 3 5
I h radionuclides directly from water, often concentrating them to levels much higher than the dilute concentrations that occur in the aquatic environment. This is because most algae are coated with a carbohydrate jelly and have a E large surface-to-volun:= ratio. Cell division usually 5 occurs once every one or two days and, as a result, half of the cell wall is a new surface for sorption. 3 Periphyton represent one of the earliest links in the food g chain and provide information about the amounts of radionuclides available to predators further up the food chain. Samples of periphyton are collected every two months between April and October (during the colder months growth g is limited) at the indicator locations and semiannually at W the control location and analyzed by gamma spectroscopy. Periphyton analyses are performed because of their sensitivity to the presence of radionuclides in the aquatic environment due to bio-magnification. Using periphyton as biomonitors for radionuclides in 5 aquatic systems can be a highly sensitive and qualitatively ef fective means of environmental monitoring 3 around nuclear power plants that release radioactive 3 effluents to aquatic systems. It enables the Radiological Environmental Monitoring Program to determine the relative presence of radioactivity before it becomes a problem. The results of the gamma isotopic analyses on periphyton samples detected concentrations of naturally occurring radioisotopes and one fission product, Cs-137. Concentrations for Cs-137 ranged from 0.026 to 0.091 pCi/g (wet) . Preoperational results for Cs-137 showed a concentrations ranging from 0.042 to 0.15 pCi/g(wet). The g presence of Cs-137 is attributed to previous nuclear weapons testing and atmospheric fallout from the accident at Chernobyl. Preop Range 1997 Range 1996 Range (oCi/o drv) (oCi/a drv) (oCi/a drv) Be-7 0.38 - 1.07 0.22 - 2.46 0.49 - 1.93 K-40 0.74 - 6.82 0.68 - 4.08 1.39 - 5.51 Cs-137 0.042 to 0.15 0.026 - 0.091 0.024 - 0.086 I I 111- 3 6 I 5.
E. Terrestrial Monitorina In addition to the diact radiation, radionuclides present in the atmosphere expose individuals when deposited on surfaces (e.g., plants and soil) and are subsequently ingested directly by man or indirectly by consumption of animal products (e.g., meat and milk) . To monitor this food pathway, samples of green leafy vegetables, grass, milk and meat are analyzed. Surface soil samples are collected and analyzed annually at the sewage sludge application site to ensure radionuclides attributed to the operation of Clinton Power Station are not being land applied with the processed sewage sludge. Every three years, samples are taken at four other locations to monitor the potential buildup of atmospherically deposited radionuclides. Surface vegetation samples are collected from a number of locations for the purpose of monitoring the potential buildup of atmospherically deposited radionuclides. Because the radionuclides of interest, with respect to the Clinton Power Station operations, are also present in the environment as a result of several decades of worldwide fallout or because they are naturally occurring, the presence of these radionuclides is expected in all of the samples collected. In addition to naturally occurring radioisotopes, Sr-90 and Cs-137 were found in several samples. However, the concentrations of radionuclides in samples collected near the Clinton Power Station were comparable to the concentrations in samples collected at locations remote from the station. The presence of this fission product is attributable to previous nuclear weapons testing and fallout from the accident at Chernobyl. The operation of Clinton Power Station had no measurable contribution to the radioactive concentration of the terrestrial environment. Milk There is no known commercial production of milk for human consumption within a five-mile radius of the Clinton Power Station. Milk samples are collected from a dairy located about 14 miles west southwest of the station (twice a month during May through October and once a month during November through April) . These samples are analyzed for I-131, Sr-90 and gamma isotopic activities. Results of the analyses showed positive concentrations of K-40 and Sr-90 ranging from 1130 to 1600 pCi/l for K-40 and 0.6 to 2.8 pCi/l for Sr-90. Preoperational activity of K-40 in milk ranged from 706 to 1375 pCi/1. Strontium-111- 3 7
I 90 analysis in milk was added to the REMP during the operational phase of the program, therefore there were no preoperational data for this isotope. I-131 was not detected in any of the milk samples collected. Figure 10 presents the Sr-90 results graphically. Preop Range 1997 Range 1996 Range (DCi/a drv) (DCi/a drv) (DCi/c drv) Sr-90 No Data 0.6 - 2.8 0.8 - 3.8 K-40 706 - 1375 1130 - 1600 1310 - 2220 Grass In addition to milk samples, grass samples are collected at three indicator locations and at one control location. These samples are collected twice a month during May 3 through October and once a month during November through 5 April (when available). Grass samples are analyzed for gamma isotopic activity including I-131. The results of the analyses showed only naturally occurring Be-7 and K-40 in these samples. Iodine-131 was not detected in any of the grass samples collected. Preop Range 1997 Range 1996 Range (DCi/a wet) (DCi/a wet) (DCi/c wet) Be-7 0.022 - 14.0 0.50 - 5.48 0.19 - 7.37 K-40 0.22 - 14.5 3.76 - 11.65 2.76 - 8.27 Veoetables The Clinton Power Station obtains broadleaf vegetable sampl'es from three indicator locations and at one control location. The indicator locations are located in the sectors with the highest potential for surface deposition and the control location is in a sector and at a distance which is considered to be unaffected by plant operations. Samples are collected once a month during the growing season (June through September) and analyzed for gross beta and gamma isotopic activities including I-131. I I I t 111- 3 8 I I
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The results of the gamma isotopic analysis showed only naturally occurring K-40 and Be-7. Preop Range 1997 Range 1996 Range
.(DCi/o wet) (DCi/o wet) (DCi/o wet)
Be-7 0.082 - 0.69 0.20 - 0.51 0.074 - 0.34 K-40 1.45 - 7.00 1.95 - 8.17 1.80 - 7.083 Gross Beta 0.87 - 8.80 1.18 - 12.28 1.81 - 6.61 Iodine-131 was not detected in any vegetable samples collected. Meat As an additional check on the presence of radioactive materials in terrestrial exposure pathways, annual samples of beef liver, beef thyroid and edible beef portions are collected from an animal raised near the Clinton Power Station. These samples are analyzed for gamma isotopic activity including I-131. The results of the gamma isotopic analysis showed only naturally occurring K-40 in all three samples at 2.44 and
- 3. 24 pCi/g (wet) . Preoperational activity ranged from 1.95 to 2.78 pCi/g(wet). I-131 was not detected in the meat samples collected.
Soil Soil samples adjacent to air sample stations are collected triennially from three indicator locations and one control location. The samples are collected to monitor the potential buildup of atmospherically deposited radionuclides. One soil sample was collected from an area where Clinton Power Station land applies processed sewage sludge from the Clinton Power Station Sewage Treatment Plant. Soil samples are sifted to remove any stones or debris, then dried and analyzed. All soil samples are analyzed for gross beta, gross alpha and gamma isotopic activities. The results of the gross beta activities ranged from 17.92 to 27.47 pCi/g(dry). Gross alpha activities ranged from
- 11. 87 to 13.86 pCi/g (dry) .
111- 4 1
I f isotopic activity indicated several naturally Gamma occurring isotopes, such as K-40 and Pb-212, and one ! Cs-137 concentrations ranged fission product, Cs-137. from 0.160 to 0.493 pCi/g(dry). Preop Range 1997 Range 1996 Range (oCi/a wet) (oCi/c wet) (oCi/a wet)* Gross Beta 17.7 - 24.7 17.92 - 27.47 19.90 Gross Alpha 6.2 - 10.4 11.87 - 13.86 7.95 Cs-137 0.14 - 0.40 0.160 - 0.493 0.032 Only one sample taken in 1996 I F. Water Monitorina Water monitoring provides for the collection of drinking water, surface water and ground water (well water) samples to detect the presence of any radioisotopes related to the operation of the Clinton Power Station. The only identified user of water from Clinton Lake for g domestic purposes is the Clinton Power Station; ell others g potentially exposed to any radioisotopes reseased into surface or ground water would not be affected for several years. Samples taken were analyzed for naturally occurring beta and man-made radioactive isotopes. Average gross concentrations in surface, drinking and well water are E presented in Table 7 at the end of this section. 5 Drinkina Water A composite water sampler located in the Service Building collects a small, fixed volume sample at hourly intervals. The sampler discharges each sample into a common sample collection bottle. Therefore, the monthly sample analyzed by the contracted laboratory service is a composite of the g individual samples collected throughout the month. The g monthly composite sample is analyzed for gross A alpha, portion of gross beta and gamma isotopic activities. monthly each monthly sample is mixed with the other samples collected during each calendar quarter. The quarterly composite sample is analyzed for tritium. Gross beta activity ranged from 1.6 to 4.4 pCi/1. These E levels are attributed to very fine particles of sediment W containing K-40 which are not removed during the chlorinating and filtration process. Gross alpha activity ranged from 0.6 to 1.1 pCi/1. Preoperational result were all below the lower limits of I lll-42 I
detection except for one result which was 0.4 pCi/1. These levels can be attributed to naturally occurring radioisotopes, such as U-238 and Ra-226, suspended as fine sediment particles in water. The results of all analyses for tritium and gamma-emitting radioisotopes were all less than the lower limit of detection. These results show no measurable effects on drinking water resulting from operation of the Clinton Power Station. l Surface Water Composite water samplers are installed in three locations to sample surface water from Clinton Lake. These samplers collect a small volume of water at regular intervals and discharge it to a large sample collection bottle. These bottles are collected monthly. Two of the composite samplers are located upstream from Clinton Power Station and are unaffected by plant liquid releases downstream. The other composite sampler is positioned to sample the water released from the plant at the start of the plant discharge flume. Grab samples were collected from two indicator locations and one control location on Clinton Lake. Surface water samples are analyzed for gross beta, gamma isotopic and tritium activities. Additional analyses for gross alpha activity are performed on the upstream water samples. Additional analyses for gross alpha activity and I-131 activity are performed on water samples taken from the discharge flume. Tritium analyses are performed quarterly from composites of monthly samples from all composite sample locations. Results of all gross beta analyses ranged from 1.4 to 6.0 pCi/l at the indicator locations and 2.0 to 2.2 pCi/l at the control location. Preoperational gross beta activity ranged from 1.1 to 7.6 pCi/1. These results are attributed to naturally occurring K-40 suspended as fine sediment particles in water. Other types of samples have confirmed the presence of K-40 in Clinton Lake shoreline and bottom sediments. Tritium analyses performed on samples were all less than LLD. The preoperational tritium concentrations ranged from 220 to 330 pCi/1. As noted in reference (EI87), previous nuclear weapons testing increased the pre-1960 levels of tritium (6-24 pCi/1) by a factor of approximately fif ty (300-1200) . 111- 4 3 1
I Gamma-emitting radioisotopes were all below the lower , limits of detection, and there was no iodine-131 detected in any surface water samples collected. Gross alpha activity was detected in several of the surface water samples analyzed. These results ranged from 0.7 to 9.1 pCi/1. Preoperational gross alpha activity 3 ranged from 1.3 to 1.9 pCi/1. These results were g attributed to naturally occurring radioisotopes, such as U-238 and Ra-226, suspended as fine sediment particles in water. These results show no measurable change in radioactive material concentration in surface water due to operation of the Clinton Power Station. Well Water Every two weeks samples are collected from the well serving the Village of DeWitt (both treated and untreated l W l samples are obtained) and from a well serving the Illinois l Department of Conservation at the Mascoutin State l Recreational Area. Each sample ir analyzed for I-131. 3 All samples drawn from the same well during a particular g month are combined and analyzed for gross alpha, gross l beta and gamma isotopic activities. In addition, a portion of each monthly composite is added to the quarterly composite sample and is analyzed for tritium. Results of the gross beta analyses ranged from 1.3 to 5.3 E pCi/1. Preoperational gross beta activity ranged from 1.1 5 to 5.1 pCi/1. The gross beta activity was attributed to naturally occurring K-40 suspended as fine sediment particles in water Results of the gross alpha analyses ranged from 1.2 to 3.5 pCi/1. Preoperational gross alpha activity ranged from l 5 0.9 to 1.8 pCi/1. Gross alpha activity can be attributed to naturally occurring radioisotopes, such as, U-238 and Ra-226, suspended as fine sediment partirleu in water. Gamma-emitting radioisotopes were all below the lower limits of detection. Tritium and I-131 were not detected in any well water samples collected. These results show no measurable change in radioactive material concentration in well water resulting from operation of the Clinton Power Station. I I 111- 4 4 I
TABLE 7 AVERAGE GROSS BETA CONCENTRATIONS IN DRINKING, SURFACE AND WELL WATER 1996 1997 Average i20 Average i20 Station Descrio_ tion (D_ C1/1) (D_ Ci /1) Drinkina Water l CL-14 CPS (Service Building) 2.2 1 0.3 2.5 i 1.5 Surface Water i CL-9 DeWitt Road Bridge 2.7 i 1.1 2.4 i 0.6 i CL-10(c) IL 48 Bridge 2.9 i 2.3 2.1 i 0.3 CL-13 Salt Creek (below dam) 2.9 1 1.2 2.4 i 0.5 CL-90 CPS Discharge Flume 2.4 i 1.1 2.9 t 2.1 CL-91 Parnell Boat Access 2.5 i 1.4 2.9 i 2.3 CL-99 North Fork Canoe Access 2.9 i 2.3 3.3 i 3.2 i Well Water l CL-7D Mascoutin State I Recreation Area 1.4 i 0.5 2.9 i 3.8 CL-12(T) DeWitt Pump Station 3.0 1 2.2 3.3 i 1.8 l CL-12 (U) DeWitt Pump Station 3.1 i 1.8 3.4 1 1.6 (U) Untreated (T) Treated (c) Control location; all others are indicators l Ill-45
I: G. Ouality Assurance Proaram J. establish confidence that data developed and reported are accurate and precise, all REMP activities are E incorporated into the Illinois Power Company Quality W Assurance (QA) program of audits and surveillances. The Quality Assurance program requires: Participation in intercomparison programs, such as the EPA cross-check program. Audits of the analysis laboratory functions and facilities.
- Periodic review of the Clinton Power Station procedures specifying sampling techniques.
- Duplicate analysis of every tenth sample assayed (not including TLDs). This requirement is to check laboratory precision.
- The routine counting of quality control samples.
Appro.ximately ten percent of the total number of counts performed are to be quality control counts. The analytical results provided by the laboratory were routinely reviewed by the Radiological Programs Group of l the Plant Radiation and Chemistry Department to ensure the required minimum sensitivities have been achieved and the proper analyses have been performed. l Teledyne participates in the several cross-check programs including the EPA cross-check program. Participation in cross-check programs provides assurance that the m l laboratory is capable of meeting widely-accepted criteria g l for radioactivity analysis. l Results of the 1997 Teledyne cross-check programs are I shown in Appendix D. H. Chances to the REMP Durina 1997 I l Occasionally changes to the Radiological Environmental Monitoring Program are necessary to improve the monitoring of the environmental exposure pathways. These changes may I result from items identified during the performance of the Annual Land Use Census, revised or new regulatory l requirements, Quality Assurance audits or supplemental W periodic and long-term sampling and analyses. During 1997, there were no changes to the REMP program as required by the Off-Site Dose Calculation Manual. Other changes that took place are as follows: 111- 4 6 I li l
- 1. Goat milk location CL-98 was deleted from the program because the tenant no longer milked the animals and had no plans on milking them in the near future.
- 2. Grass sampling at location CL-11 was deleted because there were two control locations where grass samples were being taken. The decision to keep CL-116 as the control location was primarily based on this site currently being used as a control location for milk.
- 3. Surface water grab sample at locations CL-9 and CL-10 were discontinued. Because surface water composite samples are being taken at two upstream locations and one downstream location it was decided that this degree of redundancy for surface water sampling was unnecessary.
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IV. 1997 ANNUAL LAND USE CENSUS A land use census is performed to ensure that changes in the use of areas at and beyond the site boundary are identified and that any necessary modifications to the REMP are made. The land use census is performed to identify within a distance of 5 miles (8 km), the locations in each of the 16 meteorological sectors of the nearest milk animals, the nearest residence *and the nearest garden of greater than 500 square feet (50 m) producing broadleaf vegetation. Also, the census shall identify within a distance of 3 miles (5 km), the location in each of the 16 meteorological sectors of all milk animals and all gardens of greater than 500 square feet producing broadleaf vegetation. TABLE 8 ANNUAL LAND USE CENSUS RESULTS Nearest Nearest Nearest Sector Residence (km) Garden (km) Milk Animal (km) N 1.50 7.22** 1.50 NNE 1.59 5.75 2.05 NE 2.07 5.53 3.46 ENE 2.86 2.86 7.74 E 1,67 3.95
- ESE 5.14 5.30
- SE 4.44 *
- SSE 2.90 4.48 3.83 S 4.78 6.60 6.60 SSW 4.90 5.14 5.47 SW 1.17 5.61 5.74 WSW 2.52 3.62 5.53 W 2.63 3.22 3.31 WNW 2.63 2.63
- NW 2.65 4.49 3.55 NNW 2.78 4.17 2.05 None identified within 8 kilometers of CPS in this meteorological sector.
** A garden was found closer at 4.59 km, however the garden area was < 50 m'.
The Annual Land Use Census was conducted during the growing season satisfying the CPS Offsite Dose Calculation Manual requirements. Approximately 190 residences were surveyed by either direct contact, mailed in questionnaire, telephone, or direct observation. Data for this census was obtained using the following means: o Performed door-to-door solicitation of residences / land owners identified in the previous year's Annual Land Use Census and the most current IV-1
I DeWitt County plat book. If a resident was unavailable for questioning, a questionnaire was placed on their door to have them fill out and mail back. o Performed telephone solicitation of persons who were W' unavailable during the door-to-door survey and didn' t mail back their questionnaire. o By direct observation of land when the aforementioned methods were unsuccessful. If an individual was unable to be contacted, data from the previous year was used. Contacted several state and local agencies. The Annual Land Use Census results were examined to ensure that the REMP will provide representative measurements of radiation and radioactive materials in those exposure a pathways and for those radionuclides that lead to the g highest potential radiation exposures to the general public resulting from Clinton Power Station operations. l Using the Annual Land Use Census results and utilizing effluent data supplied by the CPS Chemistry Group, an l evaluation is performed to ensure that the current ODCM 3 l sample location requirements are met. On the basis of this evaluation no changes to the REMP were made. 3 I I I I I I I I I IV - 2 I-3
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V. LIST OF REFERENCES ANSI 75 American National Standards Institute, Inc.,
" Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry,"
ANSI N545-1975. ASTM 75 American Society for Testing and Materials,
" Standard Recommended Practice for Dealing with Outlying Observations," ASTM E178-75.
CFR Code of Federal Regulations, Title 10, Part 20 (Nuclear Regulatory Commission). CL97 CPS 1997 Radioactive Effluent Release Report. EI87 " Environmental Radioactivity," M. Eisenbud, 1987. EPA 72 " Natural Radon Exposure in the United States," Donald T. Oakley, U.S. Environmental Protection Agency. ORP/SID 72-1, June 1972. FRC60 Federal Radiation Council Report No. 1,
" Background Material for the Development of Radiation Prctection Standards," May 13, 1960.
ICRP77 International Commission on Radiological Protection, Publication 2, " Report of Committee II on Permissible Dose for Internal Radiation," (1959) with 1962 Supplement issued in ICRP Publication 6; Publication 9, " Recommendations on Radiation Exposure," (1965); ICRP Publication 7 (1965), amplifying specific recommendations of Pablication 26 (1977). ICRP84 International Commission on Radiation Protection, Publication Exposure to No. 39 (1984), " Principles of Limiting the Public to Natural Sources of Radiation." KA84 " Radioactivity in the Environment: Sources, Distribution and Surveillan:e," Ronald L. Kathren, 1984. NCRP59 National Council on Radiation Protection and Measurements, Report No. 22, " Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, issued June 1959, superseding Handbook 52). l L V-1 ~
I NCRP71 National Council on Radiation Protection and Measurements, Report No. 39, " Basic Radiation Protection Criteria," January 1971. NCRP75 National Council on Radiation Protection and Measurements, Report No. 44, " Krypton-85 in the Atmosphere - Accumulation, Biological Significance, and Control Technology," July 1975. National Council on Radiation Protection and NCRP87a Measurements, Report No. 91, " Recommendations on Limits for Exposure to Ionizing Radiation," June 1987. National Council on Radiation Protection and NCRP87b Measurements, Report No. 93, " Ionizing Radiation Exposure of the Population of the United States," September 1987. Research Council, 1990, Committee on NR90 National Biological Effects of Ionizing Radiation (BEIR on V), E W Board on Radiation Effects Research Life Sciences, "The Effects of Exposure to Low Levels of Ionizing Radiation". States Nuclear Regulatory Commission, NRC74 United Regulatory Guide 5.36, " Recommended Practice for Dealing with Outlying Observations," June 1974. United States Nuclear Regulatory Commission, NRC75 Regulatory Guide 4.1, " Programs for Monitoring g Radioactivity in the Environs of Nuclear Power g Plants," Revision 1, April 1975. NRC77a United States Nuclear Regulatory Commission, Regulatory Guide 4.13, " Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications," Revision E 1, July 1977. W United States Nuclear Regulatory Commission, g NRC77b Regulatory Guide 1.109, " Calculationofof Annual Reactor B Dose to Man from Routine Releases Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October 1977. NRC79a United States Nuclear Regulatory Commission Branch g Technical Position, "An Acceptable Radiological 3 Environmental Monitoring Program," Revision 1, November 1979. V-2 I I
2 NRC79b United States Nuclear Regulatory Commisefion , Regulatory Guide 4.15, " Quality Assuran'ce for Radiological Monitoring Programs (Norm Operations)
- Effluent Streams and the Environment," Revision 1, February 1979.
NUREG86 Technical Specification, Clinton Power Station, Unit No. 1, Docket No. 50-461, Office of Nuclear Reactor Regulation, 1986. PERI 88 "The Use of Diatoms (Periphyton) in Monitoring Light Water Reactor Radioact-i"e Liquid Effluence in the Susquehanna River," 5 Patrick and John M. Palms, 1988. TEPM Analytical Procedures Ma. Teledyne Brown Engineering Environmental . Services Midwest j Laboratory (Northbrook, Illinois). { 1 USAR Illinois Power, Clinton Power Station, Updated Safety Analysis Report. 1 I 1 I v.3
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APPENDICES l
APPENDIX A Exceptions to the REMP During 1997 i p
)
4 I l l l A-1
I Exceptions to the REMP During 1997 Data from the radiological analysis of environmental samples are routinely reviewed and evaluated by the Clinton Power Station (CPS) Radiological Programs Group. This data is a checked for LLD compliance, anomalous values, quality g control sample agreement, and any positive results which are inconsistent with expected results or which exceed any Offsite Dose Calculation Manual (ODCM) reporting levels. E Reporting levels for radioactivity concentrations in E environmental samples required by the CPS-ODCM are listed in Table A-1. If an inconsistent result occurs, an investigation is initiated which may consist of some of the following actions:
- Examine the collection data siteets for any indication of collection or delivery errors, E tampering, vandalism and equipment calibration or 3 malfunctions due to electrical power failure, weather conditions, etc.
- Perform statistical tests
- Examine previous data for trends
- Review other results from same sample media and different sample media
- Review control station data
- Review quality control or duplicate sample data
- Review CPS effluent reports
- Recount and/or reanalyze the sample
- Collect additional samples as necessary During 1997, no investigations were performed as a result of reaching any ODCM reporting levels. All sample analysis y required by the ODCM achieved the LLDs specified by ODCM Table 5.1-3. Sampling and analysis exceptions are listed in Table A-2 of this appendix.
I I I A-2 I I
TABLE A-1 CPS REMP REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Water Airborne Particulate Fish Milk Food Products Analysis (pcut) or Gases (pcum') (pcukg, wet) (pcut) (pcukg. wer) H-3 20,000 - - - - Mn-54 1,000 - 30,000 - - Fe-59 400 - 10,000 - - Co-58 1,000 - 30,000 - - Co-60 300 -- 10,000 - - Zn-65 300 - 20,000 - - Zr-Nb-95 400* - - - - l-131 2 0.9 - 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 - - 300 - a For drinking water samples. This is the 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCui may be used. b If no drinking water pathway exists, a value of 20 pCVI may be used. c Total for parent and daughter. d This hst does not mean these nuchdes are the only ones considered. Other nuchdes are loentrrwx! and reported when applicable. A-3
I TABLE A-2 l SAMPLING AND ANALYSIS EXCEPTIONS FOR 1997 I ODCM REQUIRED LOCATIONS
- 1. Jan 29 Air sampler elapsed timers at CL-2 and CL-3 off by 9.5 m and 9.3 hours respectively due to a power outage during g the sample period. The exact reason for the power outage was unknown. The elapsed timers were used for sample volume calculations.
- 2. Feb 19 Air sample elapsed timer at CL-8 was found not working after 122.4 hours of operation. Another timer was installed. Actual time used for sample volume calculation.
- 3. May 21 Air sampler at CL-11 unable to obtain the minimum air sample volume for the sample period due to a decrease in the air sampler flow rate. The exact cause for this a was unknown. The regulator was readjusted and checked g the next day and no problem was noted for the following sampling period. The analysis of the data indicated the sample to be unreliable and inconsistent with the E other air sample results for the sampling period. W Air sample elapsed timer at CL-8 was found not working g because the timer gears did not engage during reset. g Timer was reset properly for the following sample period. Ac'ual t time used for sample volume calculation.
- 4. Jun 25 Unable to obtain three different types of broadleaf E vegetation at CL-115. Only lettuce was available for 5 collection due to immature plant growth.
Unable to obtain three different types of broadleaf vegetation at CL-118. Only two types were available for collection due to immature plant growth.
- 5. July 30 Air sample pump at CL-11 found not working. Discarded the sample and replaced the air sample pump.
A-4 I
- 6. October 15
. Air sample pump at CL-3 found deenergized with 121.7 hours of operation. Loss of power was due to a wiring I short in the breaker box. As left values used for I sample volume calculation. Analysis result was consistent with the other stations' air sample results and considered valid. Wiring in breaker box was repaired on 10/17 at 13:00 hours.
- 7. October 22 Air sample taken at CL-3 did not meet the minimum required sample volume due the 10/15 incident. The sample was still analyzed and the result was considered valid and consistent with the other stations' air sample results.
- 8. November 19 Air sample pump at CL-2 found with a low flow-rate.
The exact cause was unknown. The analysis of the data indicated the sample to be unreliable and inconsistent with the other air sample results for the sampling period. ADDITIONAL LOCATIONS (NON-REQUIRED)
- 1. Jan 8 Air sampler elapsed timers at CL-4 and CL-6 off by 1.7 hours due to a power outage during the sai..ple period.
The exact reason for the power outage was unknown. The elapsed timers were used for sample volume calculations.
- 2. Jan 29 Air sampler elapsed timers at CL-4 and CL-6 off by 9.6 and 9.0 hours respectively due to a power outage during the sample period. The exact reason for the power outage was unknown. The elapsed timers were used for sample volume calculations.
- 3. Feb 5 Air sampler elapsed timers at CL-4 and CL-6 off by 1.5
{ and 1.2 hours respectively due to a power outage during the sample period. The exact reason for the power outage was unknown. The elapsed timers were used for sample volume calculations. ( l s A-5 r
I
- 4. Jun 4 Air sampler timer at CL-7 found inoperable due to improper reset. Actual time used for samp?e volume E calculation. Timer was properly reset and used for the 5 next sample period.
- 5. Jun 24 CL-111 TLD, holder and stand not found. TLD location was restored two days later. It appear that the location was destroyed after being run over by heavy machinery.
- 6. September 24 Air sampler elapsed timers at CL-4 and CL-6 off by 7.1 g and 5.0 hours respectively due to a power outage during the sample period. The exact reason for the power g
outage was unknown. The elapsed timers were used for sample volume calculations.
- 7. December 30 CL-113 TLD was collected but was lost sometime during the shipping process to receipt by the vendor laboratory. A search for the missing TLD was performed by both parties involved which was unsuccessful. The exact cause for the delivery error is unknown.
I I I I I A-6 I a
i I L i APPENDIX B l REMP Sample Collection and Analysis Methods l l l l i i l I ! B-1 l i
l I I I I I I. Il I Il I I I I I I I I B-2 I I a
TABLE B-1
SUMMARY
OF SAMPLE COLLECTION AND ANALYSIS METHODS
, Approximate Te'edyne Sample Sampling Sample Size Procedure Procedure Analysis Medium Method Collected Number Abstract Gross Beta AP Continuous air 280m3 TIML-AP-02 Sample counted in a low sampling level gas flow p:eportional through filter counter media WW Grab 7.6( TIMi.-W(DS)-01 Sample evaporated on a stainless steel planchette for loa-level gas flow proportional counting SW Grab 3.8( TIML-W(DS)-01 Sample evaporated on a stainless steel planchette for low-level gas flow proportional counting SW Composite 3.8( TIML-W(DS)-01 Sample evaporated on a stainless steel planchette for low-level gas flow proportional counting VE Grab 2.5kg TIML-AB-01 Sample ashed for low- \
level gas flow proporticaal counting BS Grab 1.5-2.0kg TIML-AB-01 Sample pulverized and dried for low-level gas flow proportional counting SS Grab 1.5-2.0kg TIML-AB-01 Sample pulverized and dried for low-level gas flow proportional counting DW Composite 3.8( TIML-W:DS)-01 Sample evaporated on a stainless steel planchette for low-level gas flow proportional counting f SO Grab 1.0kg TIML-AB-01 Sample pulverized and dried for low-level gas flow proportional counting ( B-3 f \ .-
TABLE B-1 (Cont'd) Approximate Teledyne Sample Sampling Sample Size Procedure Procedure Number Abstract - Analysis Medium Method Collected Gamma AP Composite 3640m3 TIML-GS-01 Germanium gamma isotopic g Spectroscopy analysis 3 G Grab 1.Okg TIML-GS-01 Germanium gamma isotopic analysis WN Grab 7.6( TIML-GS-01 Germanium gamma isotopic analysis SW Composite 3.8f TIML-GS-01 Germanium gamma isotopic analysis VE Grab 2.5kg TIML-GS-01 Germanium gamma isotopic analysis BS Grab 1.5 - 2.Okg TIML-GS-01 Germanium gamma isotopic analysis SS Grab 1.5 - 2.0kg TIML-GS-01 Germanium gamma isotopic analysis SL Grab 0.3 - 6.0kg TIML-GS-01 Germanium gamma isotopic analysis Grab 2.5kg TIML-GS-01 Germanium gamma isotopic F analysis l
=
ME Grab 3.0kg TIML-GS-01 Germanium gamma isotopic analysis DW Composite 3.8f TIML-GS-01 Germanium gamma isotopic analysis SW Grab 3.8/ TIML-GS-01 Germanium gamma isotopic analysis SO Gtab 1.0kg TIML-GS-01 Germanium gamma isotopic analysis M Grab 3.8f TIML-GS-01 Germanium gamma isotopic analysis Direct TLD Continuous NA TIML-TLD-01 Integration of thermally Radiation Exposure stimulated visible photons B-4
I l TABLE B-1 (Cont'd) I Analysis Sample Medium Sampling Method Approximate Sample Size Collected Teledyne Procedure Number Proceduru Abstract Gross Alpha SW Composite 3.8( TIML-W(DS)-01 Sample evaporated on n (cont %) stainless steel planchette for low-level gas flow proportional counting WW Grab 7.6f TIML-W(DS)-01 Sample evaporated on a i I stainless steel planchette for low-level gas flow proportional counting
)
BS Grab 1.5 - 2.0kg TIML-AB-01 Sample pulverized and dried for low-level gas flow proportional counting ! DW Composite 3.8( TIML-W(DS)-01 Sample evaporated on stainless steel planchette for low-level gas flow proportional counting 1 SO Grab 1.Okg TIML-AB-01 Sample pulverized and dried for low-level gas flow proportional counting I SS Grab 1.5 - 2.0kg TIML-AB-01 Sample pt.tverized and dried for low-level gas flow proportional counting Sr-90 BS Grab 1.5 - 2.0kg TIML-SR-06 Hydrochloric acid leach and low-level gas flow proportional counting SS Grab 1.5 - 2.Okg TIML-SR-06 Hydrochloric acid leach and low-level gas flow proportional counting M Grab 3.8f TIML-SR-07 Sample chemically separated and dried for low-level gas flow proportional counting Tritium SW Composite 3.8f TIML-T-02 Distillation followed by counting in a liquid scintillation counter l DW Composite 3.8( TIML-T-02 Distillation followed by j counting in a liquid l scintillation counter l B-5 I
I TABLE B-1 (Cont'd) Approximate Teledyne Sample Sampling Sample Size Procedure Procedure Analysis Medium Method Collected Number Abstract Tritium SW Grab 11.4( TIML-T-02 Distillation followed by counting in a liquid l 5 (cont'd) scintillation counter WW Grab 22.8f TIML-T-02 Distillation followed by counting in a liquid scintillation counter SW Grab 3.8f TIML-T-02 Distillation followed by counting in a liquid scintillation counter 1-131 ME Grab 1.4kg TIML-GS41 Germanium gamma isotopic analysis Al Continuous air 280m3 TIML-t-131-02 Germanium gamma isotopic sampling analysis through filter media SW Grab 3.8f TIML-l-131-03 lon exchange and proportional beta counting WW Grab 7.6f TIML-l-131-03 lon exchange and proportional beta counting G Grab 1.0kg TIML-GS-01 Germanium gamma isotopic analysis M Grab 3.8f TIML-l-131-01 lon exchange and proportional beta counting I' B-6 __ - - _____ a
TABLE B-2 SAMPLfNG AND ANALYSIS FREQUENCY
SUMMARY
Number of Number of Number of Sample Sampling Collection Samples Type of Analysis Samples I Type Locations Frequency Collected Analysis Frequency Analyzed
- Air Particulate 10 Weekly 518 Gross Beta Weekly 518 I Gamma isotopic Quarterly Composite 40 Air lodine 10 Weekly 518 lodine-131 Weekly $18 Direct Radiation 86 Quarterly 342 Gamma Exposure Quarterly 342 (TLD) (continuous)
Surface Water 3 Monthly 16 Gamma isotopic Monthly 16 (Grab) Tritium Quarterty Composite 8 Gross Beta Monthly 16 i Surface Water 1 Monthly 12 Gamma isotopic Monthly 12 (Effluent Composite) Gross Beta Monthly 12 Gross Alpha Monthly 12 Tritium Quarterly Composite 4 lodine-131 Monthly 12 Surface Water 2 Monthly 24 Gamma isotopic Monthly 24 (Upstream Composite) Gross Beta Monthly 24 Gross Alpha Monthly 24 Tritium Quarterly Composite 8 Well Water 2' Semimonthly 76 lodine-131 Semimonthly 76 Gross Alpha Monthly Composite 36 I Gross Beta Monthly Composite 36 Gamma isotopic Monthly Comoosite 36 Tritium Quarterly Composite 12 Drinking Water 1 Monthly 12 Gross Alpha Monthly 12 Gross Beta Monthly 12 Gamma Isotopic Monthly 12 3 Tntium Quarterly Composite 4 \ Bottom Sediments 7 Semiannually 14 Gross Alpha Semiannually 14 Gross Beta Semiannually 14 Gamma Isotopic Semiannually 14 Sr90 Semiannually 14 Shoreline 7 Semiannually 14 Gross Alpha Semiannually 14 Sediment Gross Beta Semiannually 14 Gamma Isotopic Semiannually 14 Sr-90 Semiannually 14 r B-7
I I TABLE B-2 (Cont'd) Number of Number of Number of Sample Sampling Collection Samples Type of Analysis Samples Analysis Frequency Analyzed * " Type Locations Frequency Collected Aquatic 6 Semiannually / Bimonthly 22 Gamma it.; topic Semiannual!y/ Bimonthly 22 Vegetation Grass 4 Monthly / Semimonthly' 56 Gamma Isotopic Monthly / Semimonthly 56 (including 1-131) Vegetables 4 Monthly (dunng growing 45 Gross Beta Monthly 45 season) Gamma Isotopic Monthly 45 (including 1-131) Fish 2 Semiannually 16 Gamma Isotopic Semiannually 16 Milk 2 Monthly / Semimonthly 19 Gamma Isotopic Monthty/ Semimonthly 19 lodine-131 Monthly / Semimonthly 19 St-90 Monthly / Semimonthly 19 Meat 1 Annually (when available) 3 Gamma Isotopic Annualy 3 (including 1-131) Soll 5 Triennially /Annualty' 5 Gross Alpha Triennually/ Annually 5 l l Gross Beta 5 Gamma Isotopic 5 Number of samples analyzed does not include duplicate analysis, recounts or reanalysis. a Samples collected at CL-12 are taken prior to water treatment and after water treatment. b Samples are collected semiannually at CL-105 and bimonthly at all other locations from April through October. c Samples are collected monthly from November through April (when requested) and semimonthly May through October. d Samples are collected annually at CL-16, triennial at all other locations. I l I l I I B-8
TABLE B-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Name of Facihty: Chnton Power Station Docket No. 50-461 Location of Facihty: DeWWt. lilinois Reporting Period January 1 - December 31.1997 (county, state) Medium or Type of Lower Limit All Indicator Location with Control Number of Pathway Sampled Analysis of locations: liighest Annual Mean locations: Nonroutine (Unit of Total Number Detection Mean (0 Name Reported Mean(f) Mean (f) Measurement) Performed (LLD) (Range) Distance and Direction (Range) (Range) Measurements Direct Radiation TLD - 16.8 (322/322) CL-45 19.1 (4/4)* 17.1 (20/20) 0 (mR/qtr) 342 (11.8 21.1) 2.8 miles S (17.2 20.7) (14.0 19.5) Air Particulates Gross Beta - 0.022 (467/467)b CL-3 0.023 (52/52) 0.022(51/51) 0 (pCi/m3) 518 (W7 -0.064) 0.7 miles NE (0.009 0.049) (0.009 - 0.054) Gamma Spec 40 Be-7 - 0.078(36/36) CL-2 0.082 (4/4) 0.081 (4/4) 0 (0.052-0.10) 0.7 miles NNE (0.062 0.10) (0.068 - 0.093) Cs-134 0.0016 LLD - LLD LLD 0 Cs-137 0.0069 LLD - LLD LLD 0 Air lodiae 1 131 0.07 LLD - LLD LLD 0 (pCi/m3) 518 Surface Water Gross Beta - 2.3 (14/14) CL-9 2.4 (12/12) 2.1 (2/2) 0 Grab (pCL4) 16 (2.0 2.8) 2.7 mile's ESE (2.2 2.6) (2.0 2.2) Tritium 186 LLD - LLD LLD 0 8 Gamma Spec 16 Mn-54 5.5 LLD - LLD LLD 0 Fe-59 10.0 LLD - LLD LLD 0 Co-58 8.6 LLD - LLD LLD 0 Note: Column explanations at the end of Table B-3. B-9
TABLE B-3 (Cont'd) Medium or Type of lower Limit All Indicator Location with Control Number of Pdiway Sampled Analysis of locations: liighest Annual Mean locations: Nonroutine (Unit of Total Number Detection Name Mean(f) Mean (f) Reported Mean (f) Measurements
- Measurement) Performed (LLD) (Range) Distance and Direction (Range) (Range)
Sirf:ce Water Co-60 6.8 LLD - 11D LLD 0 Grtb (con't) Zn-65 7.4 LLD - LLD LLD 0 Nb-95 10.2 LLD - LLD LLD 0 Zr-95 17.7 LLD - LLD LLD 0 Cs-134 5.6 LLD - LLD LLD 0 Cs-137 6.7 LLD - LLD LLD 0 Ba-140 51.0 LLD - LLD LLD 0 La-140 11.9 LLD - LLD LLD 0 Sirf:.ce Water Gross Beta 2.8 3.0 (32/36) CL-99 3.3 (9/12) NA 0 C:mposite (pCi/l) 36 (1.4 60) 3.5 miles NNE (1.6 - 6.0) Gross Alpha 2.6 2.4 (12/36) CL-91 3.6 (6/12) NA 0 36 (0.7 9.1) 6.i miles ENE (0.9 - 9.1) Tritium 186 LLD - LLD NA 0 W 12 1 131 0.4 LLD - LLD NA 0 12 Gamma Spec l 36 1 i Mn 54 5.9 LLD - LLD NA 0 Fe-59 14.3 LLD - LLD NA 0 W Co-58 6.7 LLD - LLD NA 0 l Co-60 5.3 LLD - LLD NA 0 Zn-65 10.6 LLD - LLD NA 0 Nb-95 9.2 LLD - LLD NA 0 Zr-95 14.1 LLD - LLD NA 0 ! Cs-134 6.7 LLD - LLD NA 0 1 Cs-137 6.3 LLD - LLD NA 0 Ba-140 48.9 LLD - LLD NA 0 La-140 12.1 LLD - LLD NA 0 DriJLing water Gross Beta - 2.5(12/12) CL14 2.5 (12/12) NA 0 (pCL/l) 12 (l.6 - 4 4) O miles (1 6 - 4.4) Gross Alpha 1.8 0.9 (3/12) CL-14 0.9 (3/12) NA 0 12 (0.6 1.1) O miles (0 6 - 1.1) Tritium 180 LLD - LLD NA 0 I Gamma Spec 12 B-10 I
l TABLE B-3 (Cont'd) Medium or Type of lower Limit AllIndicakr Location with Control Number of Pathway Sampled Analysis of im:stions: liighest Annual Mean Locations: Nontoutine (Unit of Total Number Detection Mcan (f) Name Reported Mean(f) Mean (f) Measurement) Performed (LLD) (Range) Distance and Direction (Range) (Range) Measurements Drinking Water Mn-54 5.0 LLD - Lt.D NA 0 (con't) fc-59 12.1 LLD - LLD NA 0 Co-58 60 LLD - LLD NA 0 Co-60 5.8 LLD - LLD NA 0 Zn-65 9.2 LLD - LLD NA 0 Nb-95 86 LLD - LLD NA 0 Zr-95 15.5 LLD - LLD NA 0 Cs-134 6.1 11D - LLD NA 0 Cs-137 7.0 LLD - LLD NA 0 Da140 $1.2 LLD - LLD ha 0 La-140 8.8 LLD - LLD NA 0 Well Water Gross tieta 3.8 3.3 (16/36) CL-12Uc 3.4(5/12) NA 0 (PCi!!) 36 (l3-53) 1.6 n.iles E (2.8 - 4.7) Gross Alpha 3.7 2.2(6/36) CL-12U 3.5(1/12) NA 0 36 (1.2 - 3.5) 16 miles E I 131 0.5 LLD - LLD NA 0 76 Tritium 184 LLD - LLD NA 0 12 Gamma Spec 36 Mn 54 5.2 14.D - LLD NA 0 Fe 59 13.1 LLD - LLD NA 0 Co-58 4.6 LIE - LLD NA 0 Co-60 4.4 LLD - LLD NA 0 Zn-65 9.7 LLD - LLD NA 0 Nb-95 6.9 LLD - LLD NA 0 Zr-95 14.2 LLD - LLD NA 0 Cs-134 63 LLD - LLD NA 0 Cs-137 7.0 LLD - LLD NA 0 Ba-140 57.4 LLD - LLD NA 0 La 140 14.2 LLD - LLD NA 0 Milk (pCl/l) 1-131 0.5 LLD - LLD LL D 0 19 Sr-90 NA NA CLIl6 0 13 (19'19) 13 (19/19) 19 14 miles WSW (0 6 - 2.8) (0 6 - 2.8) Gamma Spec 19 K-40 - NA CL Il6 1363 (19/19) 0 1363 (19/19) 14 miles WSW (1130 - 1600) (1130-1600) B-11 l
TABLE B-3 (Cont'd) Medium or Type of Lower Limit AllIndicator location with Control Number of Pathwsy Sampled Analysis of Locations: liighest Annual Mean locations: Nonroutine Detection Mean(f) Mean (O Reported (Unit of Total Number Mean (0 Name (LLD) (Range) Distance and Direction (Range) (Range) Measurements Measurement) Performed LLD LLD LLD 0 WE Milk (con't) Cs-134 7.6 - Cs-137 8.3 LLD - LLD LLD 0 Ba-140 33.1 LLD - LLD LLD 0 La-140 7.4 LLD - LLD LLD 0 Fish (pCi /g wet) Gamma Spec 16 K-40 - 2.82 (8/8) CL-105 2.84 (8/8) 2.84 (8/8) 0 (2.37- 3.26) 50 miles S (2.28 -3.18) (2.28-3.18) W l l Mn-54 0.023 LLD - LLD LLD 0 Fe-59 0.069 LLD - I.LD LLD 0 Co-58 0.035 LLD - LLD LLD 0 Co-60 0.022 LLD - LLD LLD 0 Zn-65 0.035 LLD - LLD LLD 0 Cs-134 0.025 LLD - LLD LLD 0 Cs-137 0.018 LLD - LLD LLD 0 Bottom Gross Beta - 18.51 (16/36) CL-105 32.58(2/2) 32.58 (2/2) 0 i Sediments 14 (7.09 - 30.44) 50 miles S (32.46 -32.69) (32.46 32.69) (pCi/g dry) Gross Alpha 3.88 9.94 (1/36) CL-10 19.58 (2/2) 13.19 (2/2) 0 14 (4.36 -22.47) 5.0 miles ENE (16.68 22.47) (10.75 -15.62) St-90 0.075 0.038 (9/12) CL-10 0.075 (t/12) 0.036(1/2) 0 14 (0.017 - 0.075) 5.0 miles ENE Gamma Spec 14 Cs-134 0 068 LLD - LLD LLD 0 = Cs-137 0 025 0.161 (10/12) CL-105 0.374 (2/2) 0.374 (2/2) 0 (0.013 0.398) 50 miles S (0.350 0.398) (0.350 0.398) Shireline Gross Beta - 9.42(12/12) CL-89 13.59 (2/2) 10.39(2/2) 0 Sediments 14 (6.53 - 16,65) 3.6 miles NNE (10.52 - 16.65) (10.13 - 10.64) (pCi/g dry) Gross Alpha 5.13 6.42 (2/12) CL-89 6.42 (2/12) LLD 0 14 (4.41 - 8.43) 3.6 miles NNE (4 41 -8.43) Sr-90 0.028 LLD - LLD LLD 0 14 Gamma Spec 14 Cs 134 0 038 LLD LLD LLD 0 B-12 I
TABLE B-3 (Cont'd) Medium or Type of lower Limit AllIndicator location with Control Number of Pathway Sampled Analysis of locations: liighest Annual Mean locations: Nonroutine (Unit or Total Number Detection Mean (0 Name Reported Mean(f) Mean (0 Measurement) Performed (LLD) (Range) Distance and Direction (Range) (Range) Measurements Shoreliac Cs 137 0.029 0.023 (2/12) CL-89 0 023 (2/2) Li D 0 Sediments (con't) (0 014 - 0.032) 3.6 Miles NNE (0.014 - 0 032) l Aquatic Gamma Spec Vegetation 22 (pCl/g wet) Mn-54 0.046 LLD LLD LLD 0 l'e-59 0.108 LLD LLD LLD 0 Co-58 0.045 LL.D 1.LD LLD 0 W Co-60 0.039 LLD - LLD LLD 0 Zn-65 0.110 LLD LLD LLD 0 g Cs-134 0.043 LLD - LLD LLD 0 g Cs-137 0.045 0.051 (7/20) CL-9 0 064 (3/4) 0.057 (2/2) 0 (0.026 - 0.091) 2.7 Miles ESE (0.026 - 0 091) (0.040- 0.073) Vegetables Gross Deta 4.74 (33/33) - CL-il8 5.82 (11/11) 5.03 (12/12) 0 (pCi/g wer) 45 (2.06 - 8.03) 0.7 miles NNE (2.42 -8 03) (1.18 - 12.28) Gamma Spec 5 45 1 131 0.041 LLD - LLD LLD 0 Cs-134 0.029 LLD LLD LLD 0 Cs-137 0 028 LLD LLD LLD 0 i Grass (pCl/g uet) Gamma Spec
$6 I 131 0.045 LLD LLD LLD 0 Cs-134 0.031 LLD LLD M
LLD 0 Cs-137 0.033 LLD LLD LLD 0 Ba-140 0.137 LLD LLD LLD 0 La-140 0.046 LLD LLD LLD 0 Meat (pCi/g wer) Gamma Spec I, 3 I 131 0 039 LLD - LLD LLD 0 Cs 134 0.006 LLD LLD LLD 0 Cs-137 0.006 LLD LLD LLD 0 Soil (pCi/g dry) Gross Beta CL2 23.12 (4/4) 27.47(1/l) 20.92 (1/l) 0 o 5 (17.92-27.47) 0.7 miles NNE Gross Alpha 12.92 (4/4) CL-2 13.86 1313 (t/l) 0 (11.87 13.86) 0.7 miles NNE F B-13
TABLE B-3 (Cont'd)_ Medium or Type of Lower Limit AllIndicator location with Control Number of of Imcations: liighest Annual Mean locations: Nontoutine Pathway Sampled Analysis Detection Mean (0 Reported (Unit of Total Number Mcan (0 Name Mean(0 Distance and Direction (Range) (Range) Heasurements Measurement) Performed (Lt.D) (Range) Gamma Spec 5 Cs-137 0.232 (4/4) CL-i l 0.49)(1/I) 0.493 (t/I) 0 (0.160-0.353) 16 miles S Cs-134 0.068 LLD - LLD LLD 0 a Highest quarterly mean b Values excluded due to insufficient samp.s volume collected c (T) Treated well water sample or (U) Untreated well water sample 3 I 4 i i a i I i Ii 1 B-14 I
TABLE B-3 (Cont'd) Medium or Type of lower Limit AllIndicator location with Conual Number of I Pathway Sampled Analysis of locations: Highest Annual Mean Imations: Nonroutine (Unit of Total Number Detection Mean (f) Name Mean(f) Mean (f) Reported _ Measurement) Performed (LLD) (Range) Distance and Direction (Range) (Range) Measurements l Column I l Column 2 l Column 3 l Column 4 l Column 5 l Column 6 l Column 7 l TABLE EXPLANATIONS: Column 1: The Unit of Measurement describes all the numerical values for LLD, Mean and Range reported for a particular sample medium. Forexample: the Gross Beta LLD in AIR PARTICULATES is 0.010 pCi/m 3 . Abbreviations used are: pCi/m3 . picocurie per cubic meter of sarnpied air, mR/ quarter = exposure measured for calendar quarter period; pCill = picocurie per liter of sample; pCi/g = picoeurie per gram of sample. Column 2: The Types of Analyses are described as follows: Gamma Spec = measurement of each radioisotope in a sample using I Gamma Spectroscopy; Gross Betas and Gross Alphas = measurement of the radioactivity in a sample by measurement of emitted betas rend alphas - no determination of individual radioisotopes is possible; Tritium = measurement of tritium (H-3) is sample by liquid scintillation counting method; TLD = direct measurement of gamme exposure using thermoluminescent dosimeters. Total number of analyses does not include duplicate analyses, recounts or reanalyses. Onty ODCM required LLDs and detectable activity (excluding some naturally occurring actsvity I.e., Bi-212) results are l reported in this table. All sample results can be found in Appendix E of this report. Column 3: The ODCM required LLD is given is given when applicable. LLD reported iu the highest of those reported for each of analysis during the year; if all analyses reported po.sitive values, no LLD is repotted. It should be noted that, in most cases, the CPS REMP uses lower detection limits than required. Column 4: Samples taken at indicator Locations during an operational radiological environmental monitoring program (REMP) { reliably measure the quantities of any radioisotopes cycling through the pathways 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.
'T' is the fraction of all the samples taken at all indicator locations for the 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 indictor locations for that medium.
Column 5: The Mean, f-fraction and Range along with the name of the location, distance from the CPS gaseous 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 stack. The location with the highest annual mean is compared to both indicator and control locations of the medium samples. Column 6: Control locations are sited in areas with low relative deposition and/or dispersion factors. Sample results are used as reference for the controllocation. Column 7: NRC Regulations (Branch Technical Position, Rev.1, November 1979) include a table of radioisotope concentrations that, if exceeded by confirmed sample measurements, indicate that a Nonroutine Reported Measurement exists. Such measurements require further investigation to validate the source. B-15
( APPENDIX C Glossary C-1
I GLOSSARY activation - the process in which stable atoms become radioactive atoms by absorbing neutrons. ALARA - acronym for "As Low As Reasonably Achievable" which l applies to many facets of nuclear power (i.e., radiation g exposure for personnel kept low, minimizes number / activity of effluent discharges). alpha particle - a charged particle emitted from the nucleus of an atom having a mass and charge equal in mag;utude to a helium nucleus which has two protons and two j neutrons. W atom - the smallest component of an element having all the a properties of that element. Comprised of protons, neutrons and electrons such that the number of protons determines the g element. background radiation - source of radiation that mankind has = no control over, such as cosmic (from the sun) and terrestrial (naturally occurring radioactive elements). j beta particle - a charged particle equivalent to an l electron if negative or a positron if positive, originating l near the. nucleus of an atom during radioactive decay or fission. I control location - a sample collection location considered to be far enough away from Clinton Power Station W j so as not to be affected by station operations. cosmic radiation - penetrating ionizing radiation originating from the sun and from outer space, varies from altitude and latitude. - curie (Ci) - the unit of radioactivity equal to 2.2 l trillion disintegrations per minute. dead water - water that contains no tritium. l dose - a quantity (total or accumulated) of ionizing I radiation received. dose equivalent - a quantity used in radiation protection which expresses all radiations on a common scale for calculating the effective absorbed dose (the unit of dose equivalent is the rem). ecology - a branch of biology dealing with the relations between organisms and their environment. l C-2 l
\
electromagnetic radiation - a traveling wave motion resulting from changing electric or magnetic fields. Familiar sources of electromagnetic radiation range from x-rays (and gamma rays) of short wavelength, through the ultraviolet, visible and infrared regions, to radar and radiowaves of relatively long wavelength. All electromagnetic radiation travels in a vacuum at the speed of light. element - one of 103 known chemical substances that cannot be broken down further without changing its chemical properties. environment - the aggregate of surrounding things, conditions, or influences. exposure - a measure of the ionization produced in air by x-ray or gamma radiation. Acute exposure is generally accepted to be large exposure received over a short period of time. Chronic exposure is exposure received over a long period of time. fission - process by which an atomic nucleus splits into ' two smaller nuclei and releases neutrons and energy. fission products - the nuclei formed as part of the fissioning of an atomic nucleus. gamma rays - high energy, short wavelength electromagnetic radiation emitted from the nucleus, half-life - the time required for half of a given amount of a radionuclide to decay. indicator location - a sample collection strategically placed to monitor dose rate or radioactive material that may be the result of Clinton Power Station operations. ionization - the process by which a neutral atom or molecule acquires a positive or negative charge. irradiation exposure to radiation. Lower Limit of Detection (LLD) - the smallest amount of sample activity that will give a net count for which there is a confidence at a predetermined level that the activity is present. microcurie - one millionth of a curie and represents 2.2 million decays per minute. neutron - one of the three basic parts of an atom which has no charge and is normally found in the nucleus (center) of an atom. C-3
I nucleus - the center of an atom containing protons and i1 neutrons; determines the atomic weight and contributes to the net positive charge of an atom. nuclei (plural) nuclides - atoms which all have the same atomic number and mass number. periphyton - water plant life (i.e., algae). radiation - the process by which energy is emitted from a $ nucleus as particles (alpha, beta, neutron) or waves 9 (gamma). radionuclide - a radioactive species of an atom characterized by the constitution of its nucleus. The nuclear constitution is specified by the number of protons, number of neutrons, and energy content. , rem - the unit of dose of any ionizing radiation that produces the same biological effects as a unit of absorbed dose of ordinary x-rays. Acronym for Roentgen Equivalent Man. roentgen - a measure of ionization produced in air by x-ray or gamma radiation. statistics - the science that deals with the collection, classification, analysis and interpretation of numerical data by use of mathematical theories of probabilities. l target tissue - any tissue or organ of the body in which radiation is absorbed. terrestrial radiation - source of radiation pertaining to the ground (Earth's crust). wind rose - a graphic representation indicating from which h direction and speed the wind blew. 9 x-rays - high energy, short wavelength electromagnetic radiation, emitted frcm the electron shells of an atom. 1 I I E C-4
APPENDIX D 1997 Radiological Environmental Monitoring Program Quality Control Check Results A. E D-1
I interfaboratory Comparison Proaram Results Teledyne Brown Engineering Environmental Services Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (cross-check) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. 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 concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency repc.ts the known values to the participant laboratories and specifies control limits. Results consistently higher or :ower than the known values or outside the control limits indicate a need to check the instruments or procedures used. Out-of-limit results are explained directly below the result. e The results in Table D-1 were obtained through participation in the environmental sample cross-check program for water during the past twelve months. This program is conducted by the US Environmental Protection Agency Office of Research and Development National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada. e The results in Table D-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various Intemational intercomparisons of Environmental Dosimeters under the sponsorships listed in Table D-2. Also Teledyne testing results are listed, o Table D-3 lists results of the analyses o.. in-house " spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. e Table D-4 lists results of the analyses on in-house " blank" samples for the past twelve months. The results in Table D-5 were obtained through participation in the Environmental Measurement Laboratory (EML) Quality Assessment Program. The following page lists acceptance criteria for " spiked" samples. I I I I D-2 I I
ACCEPTANCE CRITERIA FOR
- SPIKED
- SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation Analysis Level for sinale determinations Gamma Emitters 5 to 100 pCWteror kg 5.0 pCWter
$100 pCWteror kg 5% of known value Strontium-89b 5 to 50 pCilliter or kg 5.0 pCilliter
>50 pCWter or kg 10% of known value Strontium-906 2 to 30 pCi/ liter or kg 5.0 pCWter
>30 pCWter or kg 10% of known value Potassium-40 >0.1 g/literor kg 5% of known value Gross alpha s20 pCi/ liter 5.0 pChier
>20 pCilliter 25% of known value Gross beta s100 pCilliter 5.0 pCilliter
>100pCilliter 5% of known value Tritium 54,000 pCillite/ is = (pCilliter) =
169.85 x (known)*u
>4,000 pCilliter 10% of known value Radium-226,-228 <0.1 pCilliter 15% of known value Plutonium 0.1 pCilliter, gram, or sample 10% of known value lodine-131, 555 pCilliter 6.0 pCi/ liter lodine-1296 >55 pCilliter 10% of known value Uranium-238, s35 pCi/ liter 6.0 pCilliter Nickel-636 >35 pCilliter 15% of known value Technetium-996 Iron-55b 50 to 100 pCi/ liter 10 pCilliter
>100 pCi/ liter 10% of known value Others6- -
20% of known value
- From EPA publication,
- Environmental Radioactivity Laboratory intercomparison Studies Program, Fiscal Year,1981-1982, EPA-600/4-81-004.
- Tejedynelimit.
D-3
1 I TABLE D-1 U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results'. j b Concentration in pCi/L Lab Sample Date Teledyne Results EPA Resulta Control g) Code Type Collected Jan,1997 Analysis 12 Siama c is.N=1 Limits g STW-782 WATER St-89 9.71 0.6 12.015.0 3.3 -20.7 STW-782 WATER Jan,1997 St-90 24.0 i 1.0 25.0 i 5.0 163 33.7 g STW-783 WATER Jan,1997 Gr. Alpha 10.0 i i.4 5225.0 0.0 13.9 g STW-783 WATER Jan,1997 Gr. Beta 15.822.0 14.71 5.0 6.0 - 23 4 STW-784 WATER Feb,1997 l-131 86.01 2.0 86.019.0 70.4 -101.6 STW-784 WATER Feb,1997 l-131 79312.0 86.019.0 70.4 -101.6 STWW-786 WATER Feb,1997 Ra-226 6.7102 5.910.9 43-7.5 STWW-786 WATER Feb,1997 Ra-228 8.411.1 8222.1 4.6 11.8 STWW-786 WATER Feb,1997 Uranium 26.5113 27.013.0 21.8 32.3 STW-787 WATER fAar,1997 H-3 7,594.0 1 279.7 7,900.0 i 790.0 6,529.4 9,270.6 STW-794 WATER Apr,1997 Gr. Alpha 44 3 i 1.6 48.0 112.0 27.2 68.8 STW-794 WATER Apr,1997 Ra-226 10.7 t 0.9 13.0 2.0 9.5-16.5 STW-794 WATER Apr,1997 Ra-228 4.7 0.4 3.110.8 1.7 - 4.5 A8 raw data and calculations were reviewed for errors. The analysis was repeated with the technician observed by the lab supervisor; the l R result of the reanalysis 3.ii0.5 pCi/L The suspected cause of the higher result was the lower than expected recovery of barium tracer. No further action is planned at this time. STW-794 WATER Apr,1997 ' Uranium 26.8103 24.0 i 3.0 18.8 29.2 STW-735 WATER Apr,1997 Co-60 21.7t 0.6 21.01 5.0 123 29.7 STW-795 WATER Apr,1997 Cs-134 273i1.2 31.0t 5.0 22.3 -39.7 STW-795 WATER Apr,1997 Cs-137 21.7ti.5 22.01 5.0 133 30.7 STW-795 WATER Apr.1997 Gr. Beta 98 2i 2.1 102.11153 75.6 128.6 g STW 795 WATER Apr,1997 Sr49 213112 24.0 i 5.0 153 -32.7 y STW-795 WATER Apr,1997 St-90 12.71 0.6 13.015.0 43 21.7 STW 796 WATER Jun,1997 Ba-133 24.7t i.2 25.015.0 163 33.7 STW-796 WATER Jun,1997 Co-60 18.7i 0.6 18.0 5.0 9.3 26.7 STW-796 WATER Jun,1997 Cs-134 19.7i 0.6 22.015.0 133 -30.7 STW-796 WATER Jun 1997 Cs-137 52.0 2.0 49.015.0 403 57.7 E g STW-796 WATER Jun,1997 Zn-65 101 01 2.0 100.0 1 10.0 82.7-1173 STW-797 WATER Jun,1997 Ra-226 2.71 0.1 3.0 i 0.5 2.13.9 STW-797 WATER Jun,1997 Ra-228 2.3103 3.11 0.8 1.7 - 4.5
- STW-797 WATER Jun,1997 Uranium 38.1i 1.0 40314.0 33.4 47.2 STW-799 WATER Jul1997 Sr49 37.71 3.2 44.015.0 353 52.7 STW-799 WATER Jul,1997 Sr-90 16.02 1.0 16.01 5.0 7.3 24.7 l
STW402 WATER Jul,1997 l-131 10.71 1.2 10.016.0 0.0 - 20.4 STW400 WATER Juf,1997 Gr. Alpha 3.11 0.3 3.1 A 5.0 0.0 -11.8 y STW400 WATER Jul,1997 Gr. Beta 13.9102 15.1t 5.0 6.4 23.8 D-4 I I
TAHLE D-1 U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results'. b Concentration in pCi/L Lab Sample Date Teledyne Results EPA Resulta Control Code Type CoHected Analysis 12 Siamac is.N=1 Limits STW401 WATER Aug,1997 H-3 11,348.7i 241.4 11,010.0 i 1,101.0 9,099.8-12,920 2 STW-803 WATER Sep,1997 Ra-226 20.01 0.8 20.013.0 14.8 252 STW403 WATER Sep,1997 Ra-228 7.010.1 8.0 *2.0 4.5 - 11.5 STW403 WATER Sep,1997 Uranium 5.01 0.1 5.1 i 3.0 0.0 10.3 STW411 WATER Nov.1997 Ba-133 97.3 t 5.0 99.0110.0 81.7-116.3 STW411 WATER Nov,1997 Co40 28.311.7 27.015.0 18.3 35.7 STW411 WATER Nov,1997 Cs-134 9.7i 1.0 10.015.0 1.3-18.7 STW411 WATER Nov,1997 Cs-137 78.0i 3.5 74.01 5.0 65.3 - 82.7 STW411 WATER Nov 1997 Zn45 76.7i 2.1 75.0 i 8.0 61.1 - 88.9
- Results obtained by Teledyne Brown Engineering Enwonmental Servoes Midwest Laboratory as a participant in the enwonmental sample cross-check program operated by the intercomparison and Calibration Sechon, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, US Environmental Protechon Agerry (EPA), Las Vegas, Nevada.
- All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples,which are in pCi/ Filter.
- Unless otherwise indicated, the TBEESML results are given as the mean i 2 standard deviations for three determinations.
8 US EPA results are presented as the known values and expected laboratory precision (1s,1 determination) and controllimits as defined by the EPA. D-5 1
I Table D-2 Crosscheck program results;1hermoluminescent Dosimeters (TLDs). mR Lab Teledyne Results Known Average i2 Sigma Code TLD Tvoe Date Measurement i2 Sioma Value i 2 Sioma (A!! Participants) 11th intemationalIntercomparison 115-11 Apr,1997
- The Eleventh intemational Intercomparison of Environmental Dosimeters was conducted in 1997 and was organized by the Department of 3 Energy's Environmental Measurements Laboratory in collaboration with Brookhaven National Laboratory and the National Institute o' Standards and Technology E
l Results for the Eleventh Intemational Intercomparison were originally reported in error, The results are being re-evaluated and will be l reported in a later update. Teledyne Testino 97-1 LIF-100 Chips Mar,1997 Lab,1 13.41 1.4 15.0 97 1 UF-100 Chips Mar 1997 Lab,2 29.81 0.6 30.1 97-1 UF-100 Chips Mar 1997 Lab,3 63.4 i 0.9 60 2 97-1 CASO4:Dy Mar,1997 Reader 1, #1 15.5 i 0.1 15.0 NO Cards 97-1 CaS0c Dy Mar.1997 Reader 1, #2 34.0s 0.1 30.1 ND Cards l 97-1 CaSO4:Dy Mar,1997 Reader 1, #3 68.31 2.1 60 2 ND Cards 97-2 CaSO4:Dy Mar 1997 Reader 2, #1 16.810.3 15.0 ND Cards 97-2 CaS0c Dy Mar,1997 Reader 2, #2 36.2102 30.1 ND 3 Cards 97-2 CaS0c Dy Mar,1997 Reader 2, #3 69.610.2 60.2 ND Cards ND = No Data; Teledyne Testing was only performed by Telodyne. I Chips and Cards were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in March,1997. Ij i I g4 D-6 I. 1 Il
l Table D-3 In-House " spike" samples Concentration in oCi/La Lab Sample Date Teledyne Results Known Controlc Code Type Collected Analysis 2s.n=16 Activity Lirnits SPW444 WATER Jan,1997 Th-230 3.120 i 0.104 3.070 1.842 4298 SPW444 WATER Jan,1997 Th-232 3355 i 0.108 3.070 1.842-4 298 SPW-548 WATER Feb,1997 Gr. Beta 43.881 1 1.305 41.860 31.860 - 51.860 I SPMI-534 SPMI-534 SPMb535 MILK MILK MILK Feb,1997 Feb,1997 Feb,1997 Cs 134 Cs 137 Sr49 48.649 i 4.940 54.700 t 8.450 49.849 i 7.940 56.400 52300 40.030 46.400 66.400 42300 62.300 30.030 50.030 SPMi-535 MILK Feb,1997 Sr-90 48.856 i 1.740 50300 40.240 60.360 SPW-536 WATER Feb,1997 H-3 27229.744 i 452.056 28234.000 27587.200 33880.800 SPW-547 WATER Feb,1997 Co40 65.219 i 8.790 62.950 52.950 72.950 SPW-547 WATER Feb,1997 Cs-134 52.996 8.000 56.430 46.430 -66.430 i SPW-547 SPW400 SPW400 WATER WATER WATER Feb,1997 Feb.1997 Feb,1997 Cs 137 l-131 l-131 (g) 60.419 i 12.900 72.182 1 1.009 68.816 i 14.800 52320 66300 66.300 42320 62.320 53.040 79.560 39.780 - 76 300 i SPCH-701 SPAP-704 CHARCOAL CANISTER AIR FILTER Feb,1997 Feb,1997 Feb,1997 l-131 (g) Gr. Beta 1.171i 0.023 6302 1 0.041 1.080 5.740 0.648 1.512 0.000 15.740 i SPW438 WATER Ra-226 19.T7010.189 17.300 12.110 22.490 SPW-838 WATER Feb,1997 Ra-228 36.7841 2.571 31300 21.910 40.690 SPW440 WATER Feb,1997 Sr-90 35.822 1 2.020 33.520 26.816 40.224 SPW441 WATER Feb,1997 l-129 15.525 1 0.854 14.942 2.942 26.942 i SPW443 SPAP-2730 SPML1670 WATER AIR FILTER MILK Feb,1997 Mar,1997 Apr,1997 Fe-55 Cs-137 Cs-134 1.418
- 0.530 2.151 0.025 50282 i 8.920 1.535 1.900 53.600 0.000 21.535 1.140 2.660 43.600 63.600 i SPMI-1670 SPW-2073 SPW-2073 SPW-2073 MILK WATER WATER WATER Apr,1997 Apr,1997 Apr,1997 Apr.1997 Cs-137 Co40 Cs-134 Cs-137 56.090 i 14.900 54.077 i 4280 47.636 t 4.150 60.688 i 5.760 52.100 51300 53200 42.100 62.100 41300 61300 43200 63200 52.100 42.100 62.100 SPW 2075 WATER Apr 1997 Gr. Alpha 34.554 i 2.677 41300 20.650 -61.950 i, SPW-2075 WATER Apr,1997 Gr. Beta 38.729
- 1.658 41.700 31.700 - 51.700 SPW-2546 WATER Apr,1997 H-3 25445.478 t 428.384 26257.000 21005.600 31508.400 I
SPF-3434 FISH May,1997 Cs-134 0.199 i 0.020 0.222 0.133 - 0.311 SPF-3434 FISH May,11/97 Cs-137 0234 1 0.037 0227 0.136-0 318 SPW 3750 WATER Jun,1997 l-131 76.174 2 0.776 71.800 57.440 66.160 g SPW-3750 WATER Jun,1997 l- 131 (g) 66 587i 8.750 71.800 43.080 81.800 g SPMI-3752 MILK Jun.1997 l-131 79.851 i 0.833 71.800 57.440 - 86.160 SPMi-3752 MILK Jun,1997 l-131 (g) 78.8871 7.750 71.800 43.080 81.800 SPCH-3754 CHARCOAL Jun.1997 l-131 (g) 81.869 2 0317 76.600 45.960 86.600 CANISTER 1 SPMi-4216 MILK Jul.1997 Cs-134 38265 t 5.450 39.500 29.500 49.500 SPMi4216 MILK Jul,1997 Cs-137 46.472 i 10.600 41.500 31.500 51.500 SPMl4216 MILK Jul.1997 l-131 752471 0.831 83230 66.584 - 99.876 SPMl4216 MILK Jul,1997 1-131 (g) 84.8721 7.010 83230 49.938 93230 SPMl4216 MILK Jul,1997 Sr-90 33.610 t 1.430 33210 26.568 39.852 SPW4420 WATER Jul.1997 Co40 26270 i 4360 24.900 14.900 - 34.900 SPW4420 WATER Jul.1997 Cs-134 36.591 1 5.040 39.540 29.540 49.540 SPW4420 WATER Jul,1997 Cs 137 45.552 1 7.770 41.480 31.480 - 51.480 SPW4420 WATER Jul,1997 l-131 (g) 85 221 i 9.660 83.230 49.938 93230 SPW4420 WATER Jul 1997 Sr-90 36285 1 1.629 33.210 26.568 39.852 D-7
I Table D-3 In-House " spike" samples Concentration in DCi/L8 Lab Sarnple Date Teledyne Results Known Controlc Code Tvoe Collected Analysis 2s.n=18 Activity limits SPMI-4916 MILK Jul,1997 1131(g) SPW-5470 WATER Jul1997 Fe-55 84.870 i 7.010 4.548 1 0.640 83.230 5.477 49.938 - 93.230 0.000 25A77 l M SPW-5472 WATER Jul,1997 H3 41026.000 1 329.000 41578.000 33262.400 49893.600 SPW4474 WATER Jul,1997 Gr. Alpha 49.266 1 2.081 41.305 20.653 61.958 g SPW-5474 WATER Jul,1997 Gr. Beta 44 A5011.334 41.406 31.406 $1.406 g SPF-5476 FISH Jul,1997 Cs-134 0.641 1 0.030 0.700 0.420 -0.980 SPF-5476 FISH Jul 1997 Cs 137 0.632 1 0.042 0.527 0.316 0.738 SPW-7500 WATER Oct,1997 Co40 30.424 7.530 33 642 23.642 43.642 SPW-7500 WATER Oct,1997 Cs-134 37.410 i 6.690 36.086 26.086 -46.086 SPW-7500 WATER Oct,1997 Cs-137 52.845 i 11.300 41.221 31.221 51.221 The Cs 137 spike is suspect. No errors were found in the spectroscopy program and the Cs-134 and Co40 test results on the same sample were very good. Sample results prepared with a new standard are acceptable. SPW-7500 WATER Oct.1997 l131 78.1261 1201 78.302 62.642 93.962 SPMi-7505 MILK Oct.1997 Cs-134 15.166 i 3.250 18.043 8.043 28.043 SPMI-7505 MILK Oct 1997 Cs-137 91.1101 8.370 82.440 72.440 92.440 SPM!-7505 MILK Oct.1997 l-131 73.529 i 1 253 78.302 62.642 93.962 SPMI-7505 MILK Oct,1997 l-131 (g) 74.613 i 8.810 78.302 46.981-88.302 SPMI-7506 MILK Oct 1997 St-89 312811 4.601 39.490 29.490 49.490 W SPCH-7727 CHARCOAL Oct 1997 i-131 (g) 0.450 1 0.050 0.440 0264 0.616 CANISTER SPAP-7730 AIR FILTER Oct,1997 Gr. Beta 3.080 1 0.030 3.040 1.824 4256 (ss) SPF-8485 FISH Nov,1997 Cs 134 0.306 1 0.025 0.318 0.191 0.445 SPF-8485 FISH Nov,1997 Cs-137 0.7381 0.049 0.649 0.389 0.909 SPW-9315 WATER Nov,1997 Gr. Alpha 51.420t 6.385 41280 20.640 61.920 SPW-9315 WATER Nov,1997 Gr. Beta 48.938 1 3.735 43.164 33.164 53.164 SPW-9706 WATER Dec,1997 Gr. Alpha 40.480 i 4.598 41.260 SPW-9353 WATER Dec,1997 Co40 20.640 61.920 l 44.900 i 8 290 42.080 32.080 52.080 5' SPW 9853 WATER Dec,1997 Cs-134 40.0101 7.010 37.850 27.850 47.850
- All results are in pCi/L, except for elemental potassium (K) in milk, which are in m%.; air filter sarnples, which are in pCi/ Filter; and food products, ,
which are in mg/kg. j SAll samples are the results of single determinations, cControl limits are based on criteria found on page D-3 of this section. = NOTE: l'or fish, Jello is used for the spike matrix. For vegetation, Sawdust is used for the spike rnatrix. t D-8
Table D.4 In-house " blank" samples Concentration DCi/L8 Teledyne Results Acceptance Lab Sample Sample (4.66 Sioma) Criteria Code Tvoe Date Analysis' LLD Actie (4.66 Siom._a) SPW445 WATER Jan 1997 Th-228 <0.9 -0.263 1 0.560 < 1.000 SPW445 WATER Jan 1997 Th-230 <0.2 0.191 1 0.236 <1.000 SPW445 WATER Jan 1997 Th-232 <0.2 -0.018 i 0.145 <1.000 SPMi-533 MILK Feb i997 Cs-134 <2.7 0.531 1 0.647 < 10.000 SPMI-533 MILK Feb 1997 Cs-137 <5.5 0.526 i 3.380 < 10.000 SPW-2 WATER Feb i997 Ra-226 <0.1 0.000 i 0 034 < 1.000 SPMi-533 MILK Feb 1997 l-131 <0.5 0.031 i 0.316 <0.500 SPMI-533 MILK Feb 1997 Sr49 <0.7 0.994 i 0.952 <5.000 SPMI-533 MILK Feb 1997 Sr-90 N/A 1.695 1 0.439 <1.000 Low level of St-90 concentration in milk (1-5 pCi/L)is not unusual SPW-537 WATER Feb i997 Co-60 <3.1 0.065 i 0.179 < 10.000 SPW-537 WATER Feb 1997 Cs-134 <3.5 0.905 i 1.100 < 10.000 SPW-537 WATER Feb i997 Cs-137 <1.7 -1.430 i i.800 < 10.000 SPW-537 WATER Feb 1997 Gr. Alpha <0.4 -0.109 i 0.218 <1.000 SPW-537 WATER Feu 1997 Gr. Beta <0.9 -0.155 1 0.596 < 3200 SPW-537 WATER Feb i997 l-131 <0.4 0.275 1 0.235 <0.500 SPW-537 WATER Feb i997 Sr49 <0.8 0.167 t 0.557 <5.000 SPW 537 WATER Feb 1997 Sr-90 <0.5 0.099 i 0.239 < 1.000 SPW442 WATER Feb i997 Fe-55 <0.7 0.403 1 0.374 < 1000.000 SPW442 WATER Feb i997 l-129 <0.9 0.129 i 0.442 <1.500 SPW442 WATER Feb i997 Ra-226 <0.04 0.013 i 0.026 < 1.000 SPAP-2731 AIR FILTER Mar 1997 Co40 <2.5 0.000 i 0.000 < 10.000 SPAP-2731 AIR FILTER Mar 1997 Cs-134 <2.6 0.000 i 0.000 < 10.000 SPAP-2731 AIR FILTER Mar 1997 Cs-137 <2.9 0.000 2 0.001 < 10,000 SPMI-1669 MILK Apr1997 Cs-134 <5.5 0.069 t 0.118 < 10.000 SPMI-1669 MILK Apr 1997 Cs-137 <3.8 0.717 2.480 < 10.000 SPW-2074 WATER Apr 1997 Co40 <3.6 0.857 1 8.380 < 10.000 SPW-2074 WATER Apr 1997 Cs-134 <4.7 1.610 ti0.200 < 10.000 SPW-2074 WATER Apr 1997 Cs-137 <5.0 1.800 i 3.200 < 10.000 SPW-2074 WATER Apr 1997 Gr. Alpha <0.5 0.119 i 0.307 < 1.000 SPW-2074 WATER Apr 1997 Gr. Beta < 1.3 0 464 t 0.720 < 3.200 SPW-2547 WATER Apr 1997 H-3 < 150 12.822 i 75.126 < 200.000 SPW-5 WATER May 1997 Ra-226 <0.03 4.053 0.025 <1.000 SPF-3435 FISH May 1997 Cs-134 <0.015 -0.014 2 0 002 < 10.000 SPF-3435 FISH May 1997 Cs 137 c0.016 0.001 t 0.011 < 10.000 SPW4 WATER Jun 1997 Ra-226 <0.04 0.044 i 0.027 < 1.000 SPW-3751 WATER Jun 1997 l-131 <0.3 -0.127 1 0.145 <0.500 SPMI-3753 MILK Jun 1997 l-131 <0.3 0.089 0.167 < 0.500 SPCH-3755 CHARCOAL Jun 1997 i- 131 (g) <0.017 0.010 1 0.009 < 9.600 CANISTER SPMI-4217 MILK Jul1997 Co40 (4.8 0.392 i 1.230 < 10.000 SPMI-4217 MILK Jul1997 Cs-134 <3.0 -0.874 i 1.700 < 10.000 SPMI-4217 MILK Jul1997 Cs-137 <5.9 1.600 i 3.430 < 10.000 SPM14217 MILK Jul1997 l-131 <0.3 0.049 1 0.171 < 0.500 SPW-4421 WATER Jul1997 Co40 < 1.9 -4.660 1 4.750 < 10.000 D-9
.I Table D-4 In-house " blank" samples Concentration DCita Teledyne Results Acceptance Lab Code Sarnple Tvoe Sample Date Analysis LLD (4.66 Siama)
Activity
- Criteria (4.66 Siamal l
g SPW4421 WATER Jul1997 Cs-134 <4.7 -1.450 1 3.090 < 10.000 SPW4421 SPMl4217 WATER MILK Jul1997 Jul1997 Cs-137 Sr49
<6.7
<1.5 0.739 i 4.550 0.165 i 1.901
< 10.000
<5.000 5
g SPMl4217 MILK Jul1997 Sr-90 N/A 1.677 i 0.418 < 1.000 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual SPW4421 WATER Jul1997 Sr49 <1.7 0.917 1 1.547 < 5.000 g SPW4421 WATER Jul1997 St-90 <0.6 0.341 1 0.332 < 1.000 SPW-5471 WATER Jul1997 Fe-55 <733 48.157 t 448.317 < 1000.000 SPW-5473 WATER Jul1997 H-3 <161 22.700 1 58.200 ( 200.000 l W SPW4475 WATER Jul1997 Gr. Alpha <0.6 0.170 1 0.425 <1.000 SPW 5475 WATER Jul1997 Gr. Beta <0.5 0.17J t 0.473 < 3200 g SPF-5477 FISH Jul1997 Co40 <0.011 -0.001 1 0.002 < 10.000 N SPF-5477 FISH Jul1997 Cs-134 <0.015 0.005 1 0.008 < 10.000 SPF-5477 FISH Jul1997 Cs-137 <0.018 0.006 t 0.010 < 10.000 g SPW-7501 WATER Oct 1997 l-131 <0.4 0.010 i 0.009 < 0.500 g SPW-7504 WATER Oct 1997 Sr49 <1.1 0.650 1 0.800 <5.000 SPW-7504 WATER Oct 1997 Sr>JO <0.4 0.150 1 0.210 < 1.000 SPMI-7507 MILK Oct 1997 Co40 <6.2 1.190 i 1.620 < 10.000 SPMI-7507 MILK Oct 1997 Cs 134 <4.9 1.710 i 1.950 < 10.000 SPMI-7507 MILK Oct 1997 Cs-137 <6.5 0.232 i 3.740 < 10.000 SPMI-7507 MILK Oct 1997 l-131 <0.3 0.022 i 0.157 < 0.500 SPMi-7507 MILK Oct 1997 Sr-89 < 1.0 0.862 1 1.107 <5.000 l SPMI-7507 MILK Oct 1997 Sr-90 N/A 1.031 1 0.319 < 1.000 Low level of Sr-90 concentrabon in milk (15 pCi/L)is not unusual. l RA-W-11 WATER Dec 1997 Ra-228 <0.7 0.134
- 0.318 <1.000 l SPW-9852 WATER Dec 1997 Co40 <2.4 1.600 1 9.460 < 10.000 g SPW-9852 WATER Dec 1997 Cs 134 <5.7 -0.450 1 2.340 < 10.000 3 SPW-9852 WATER Dec 1997 Cs-137 <6.0 2.190 i 3 550 < 10.000 l s Liquid sample results are reported in pCi/ Liter, air f,lter sample results are in pCi/ filter, charcoal sample results are in pCi/ charcoal, and solid l sample results are in pCi/ kilogram.
6 The activity reported is the net activity result. l I I I D-10 I I
Table D-5 Environrnental Measurements Laboratory Quality Assessrnent Prograrn (EML), comparison of EML and Tetedyne's Midwest Laboratory results for various sample media 8 Concentrahon in Ba/L' Lab Sample Date Control Code Tvoe Collected Analysis Teledyne Resultsc EML Resur Limits * ,,_ STW-788 WATER Mar,1997 Am-241 0.840 1 0.220 0.837 1 0.028 0.640 1 730 STW-788 WATER Mar,1997 Co-60 96.000 i 3.500 90.850 i 1.15' O.920 1.180 STW-788 WATER Mar,1997 Cs-137 77.000 i 3.500 69.780 i 1 230 0.900 1280 STW-788 WATER Mar,1997 Fe-55 175.500 1 25.400 235.000 i 20.000 0.310 1.540 STW-788 WATER Mar,1997 Gr. Alpha 1,042.600i 36.800 1,130.000 1 10.000 0.500 1290 STW-788 WATER Mar,1997 Gr. Beta 591.400 1 23.300 744.000 i 10.000 0.600 1.640 STW-788 WATER Mar,1997 H-3 272.000 129.700 250.300 1 4.200 0.650 1.910 STW-788 WATER Mar,1997 MrwS4 23.700 1 3.400 20.850 1 0.310 0.870 -1.220 STW-788 WATER Mar,1997 Pu-238 1.400 0200 1291 2 0.063 0.740-1.270 STW-788 WATER Mar,1997 Pu-239 0.900 1 0.100 0.850 i 0.050 0.780-1.420 STW-788 WATER Mar,1997 Sr-90 25.500 i 1.700 23 200 i 1.350 0.72v-1.660 STW-788 WATER Mar,1997 U 1.500 1 0200 1.105 2 0.050 0.350 1.420 STSO-790 SOIL Mar,1997 Am-241 6.740 1 3.730 5.680 1 0.500 0.520 - 2.650 STSO-790 SOIL Mar,1997 Co40 2.010 i 1.170 1.060 0.120 0.500 -1.500 The sample size was too small for an accurate measurement The activity i error overlap the known value. STSO 790 SOIL Mar,1997 Cs 137 918.640 i 8.400 825.500i 14.100 0.800-1.340 STSO-790 SOIL Mar,1997 K-40 359.140 1 32.100 334250 7.140 0.730 1.670 STSO-790 SOfL Mar,1997 Pu-238 0.300 1 0.200 0.530 0.110 0.400- 1.900 STSO-790 SOIL Mar,1997 Pu-239 132.420 1 5.170 134.930 i 17.100 0.660 1.930 STSO-790 SOIL Mar,1997 Sr-90 38.8301 5.770 40.310 2 0.420 0.460 - 2.840 STSO-790 SOIL Mar,1997 U 79260 i 3.800 81.270 i 4.830 0.270-1.360 STVE-791 VEGETATION Mar,1997 Am-241 1.673 i 0.688 1.183 t 0.113 0.680 - 2.780 STVE 791 VEGETATION Mar,1997 Crn-244 0.688 1 0.468 0.900 i 0.050 0.490-1.690 STVE-791 VEGETATION Mar,1997 Co40 16.914 i 3.580 12.5001 0.320 0.620-1.420 STVE-791 VEGETATION Mar,1997 Cs-137 216.6671 9.383 189250 1 7.270 0.810 1.450 STVE-791 VEGETATION Mar 1997 Pu-239 1.771i 0.817 1.942 1 0.222 0.650 - 1.950 STVE-791 VEGETATION Mar,1997 Sr-90 361.1301 19.715 361.000 i43.300 0.480 -1.290 STAP-792 AIR FILTER Mar,1997 Co.57 9.528 i 0230 10.810 11.000 0.620- 1.220 STAP-792 AIR FILTER Mar,1997 Co40 5.325 i 0266 5.010 t 0.300 0.740 1.240 STAP-792 AIR FILTER Mar,1997 Cs-134 10 7671 0.337 10.880 1.000 0.720 1.210 STAP-792 AIR FILTER Mar,1997 Cs-137 9.116 1 0.404 8.700 i 0.800 0.720 1.320 STAP 792 AIR FILTER Mar,1997 Gr. Alpha 1.1991 0.045 0.960 1 0.050 0.830 1.550 STAP-792 AIR FILTER Mar 1997 Gr. Beta 0.608i0.024 0.450 i 0.030 0.730 1.840 STAP-792 AIR FILTER Mar,1997 Mn-54 8.494 0.429 7.620 1 0.600 0.750 1270 STAP-792 AIR FILTER Mar,1997 Pu-238 0.022 i 0.016 0.100 1 0.006 0.620 1.460 The cause of the deviation for the transuranic analysis (Pu-238,239, U) is unknown. A dilution error is suspected. The analysis is being repeated. Analysis result was unavailable for this report i STAP-792 AIR FILTER Mar,1997 Pu-239 0.031i 0.010 0.119 1 0.006 0.500 -1.500 STAP-792 AIR FILTER Mar,1997 Sb 125 14.1181 1.099 12.330 i 1.000 0.600-1.390 D-11
1 Table D-5 Environmental Measurements Laboratory Quality Assessment Program (EML), companson of EML and Teledyne's Midwest Laboratory results for various sample media a. Concentration in BOIL 6 Control Lab Sample Date Analysis Teledyne Resultsc EML Resultd Limits
- Code Tvoe Collected STAP-792 AIR FILTER Mar.1997 Sr-90 129110275 1.450 1 0.149 0.660 2.650 g Mar,1997 U 0.150 0.020 0211 1 0.008 0.808 3.360 5 STAP-792 AIR FILTER WATER Sep,1997 Co40 23.6301 1.450 23.300 1 1200 0.920 1.180 STW405 WATER Sep,1997 Cs-134 63.500 1 2.600 66.0002 2.600 0.500 1.500 STW405 34.880i 2.430 34.3001 1.700 0.900 -1 280 v STW405 WATER Sep,1997 Cs-137 STW405 WATER Sep,1997 Fe-55 101.730 1 33.530 115.000 1 10.000 0.310 -1.540 g STW405 WATER Sep,1997 Gr. Alpha 597.0001 12.000 557.000 i 60.000 0.500 1.290 5 Sep,1997 Gr. Beta 985.0001 13.000 712.000i 70.000 0.603 1.640 STW405 WATER STW405 WATER Sep,1997 H-3 227.600 i 1.800 115.000 t 6.000 0.650 1.910 E g
The sample was acidic, causing a breakdown of resin in the tritium column. The sample was neutralized to pH 7 and reanalyzed. Results of reanalysis: 116.213.6 Bqll. WATER Sep,1997 Mn-54 38.4801 3.230 37.8001 1.900 0.870 1220 STW405 WATER Sep,1997 St-90 3.460 i 0.690 2.940 2 0.180 0.720 -1.660 S1W405 VEGEiATION Sep,1997 Co40 32.330 1 5.560 32.400 + 1.600 0.620-1.420 STVE406 VEGETATION Sep.1997 Cs 137 627.3301 16.670 624.000 1 31.000 0.810 1.450 STVE400 VEGETATION Sep,1997 K 40 1,091.670i 95.180 1,130.000 1 70.000 0.790 1.500 STVE406 VEGETATION Sep,1997 Sra 1,335.0001 32.000 1,434.0001 75.000 0.480 1290 STVE406 S0ll Sep,1997 Cs-137 1,239.440 i 22.460 810.0001 40.000 0.800 1.340 STSO407 ~ The sample size was not standard. The sample was reanalyzed using a different 9eometry. Results of reanalysis: Cs-137 - 813.119.0 Bqlkg; K-40 275.9i 34.6 Bq/kg. STSO407 S0ll Sep,1997 K.40 478.000
- 29.000 315.000 1 70.020 0.730-1.670 5 S0tt Sep,1997 Pu 239 10.800 1 0.400 10.1602 0.370 0.660 1.930 STSO407 Soll Sep,1997 St-90 31.480 1 5.560 34.7501 1.000 0.460 2.840 STSO407 72.900 1 0.850 0.270 1.360 W STSO-807 S0lt Sep,1997 U 57.000 i 1.100 STAP408 AIR FILTER Sep,1997 Gr. Alpha 1.820 1 0 080 1.490 1 0.090 0.830 1.550 STAP408 AIR FILTER Sep,1997 Gr. Beta 325010080 3.000 0.140 0.730 1.840 STAP408 AIR FILTER Sep,1997 Pu-238 0.230 1 0.100 0.210 1 0.007 0.620 1.460 STAP-808 AIR FILTER 4,1997 0 0.130 1 0.100 0.110 0.004 0.800 3.360 g AIR FILTER Sep,1997 Ce-144 16250 i 1.670 19.120 i 0.700 0.500 1.500 W STAP-809 STAP409 AIR FILTER Sep,1997 Co57 10.570 i 0 270 12.640 1 0.430 0.620 1220 STAP-809 AIR FILTER Sep,1997 Co40 9.820 1 0.270 10.730 t 10.900 0.740 1240 STAP-809 AIR FILTER Sep,1997 Cs-134 24.700 1 0.490 28.170 1 0.730 0.720 1210 STAP409 AIR FILTER Sep,1997 Cs-137 72401 0.370 7.310 1 0250 0.720 1.310 g STAP409 AIR FILTER Sep,1997 Mn-54 6.800 1 0.430 6.720 1 0.270 0.750- 1 270 g AIR FILTER Sep,1997 Sb-125 17.98011 270 16.1201 0.790 0 600 1.390 STAP409 STAP409 %IR FILTER Seo.1997 Sr-90 2 830 i 0 370 2.760 i 0 100 0 660 - 2 6.M
- The Environmental Measurements Laboratory provides the following nuclear species: Air Filters, Soit, Tissue, Vegetation and Water.
Teledyne does not participate in the Tissue program.
- Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/ Filter, Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg.
D-12 I
Tatde D-5 Environrnental Measurements Laboratory Quality Assessment Program (EML), compenson of EML and Telodyne's Midwest Laboratory results for various sample media 8 Concentration in Boll 6 Lab Sample Date Control Code Tvoe Codected Analysis Teledyne Resultsc EML Result 8 Limits *
- Teledyne res.J are reported as he mean of three detemunstens tstandard deviation.
8 The EML result listed is the mean of repicate delemanations for each nudideithe standard ermr of the mean.
- The control limits are reported by EML as the ratio of Rcported ValueI EML Value and are established from percentiles of historic data distnbubons (1982-1992). The evaluation of this historic data and the development of the contml limits is presented in DOE report EML-564.
W D-13 f
APPENDIX E CPS Radiological Environmental Monitoring Resulta During 1997 E-l
I I I I I I I I I I I I I I I I I I E-2 l I
TABLE E-l GROSS BETA AND IODINE-131 ACTIVITY IN AIR PARTICULATES FOR 1997a (pCi/m3 ) DATE COI.I.FCTED C1.-1 Cl-2 C1.-3 Cl A Cl .-6 0I/08/97 0.026
- 0.003 0.024
- 0.003 0.026
- 0.004 0.023
- 0.003 0.02I
- 0.003 01/I5/97 0.037
- 0.004 0.035
- 0.004 0.034
- 0.004 0.034 10.004 0.034
- 0.004 01/22/97 0.020
- 0.003 0.023
- 0.003 0.023
- 0.003 0.022
- 0.003 0.022
- 0.003 0I/29/97 0.025
- 0.003 0.023
- 0.003 0.024
- 0.003 0.022
- 0.003 0.022
- 0.003 02/05/97 0.023
- 0.003 0.025
- 0.003 0.026
- 0.003 0.021
- 0.003 0.023
- 0.003 02/12/97 0.025
- 0.004 0.023
- 0.004 0.024
- 0.004 0.02I
- 0.004 0.019
- 0.003 ,
02/19/97 0.025
- 0.004 0.02I
- 0.004 0.026
- 0.004 0.026 *0.004 0.023
- 0.004 1 02/26/97 0.020
- 0.003 0.016
- 0.003 0.018
- 0.003 0.017
- 0.003 0.018
- 0.003 )
03/05/97 0.018
- 0.003 0.015
- 0.003 0.019
- 0.003 0.018
- 0.003 0.019
- 0.003 03/12/97 0.020
- 0.003 0.020
- 0.003 0.022
- 0.003 0.022
- 0.003 0.020
- 0.003 03/19/97 0.016
- 0.004 0.02I *0.004 0.022
- 0.004 0.018 *0.004 0.018
- 0.004 03/26/97 0.015
- 0.003 0.015 *0.003 0.017
- 0.003 0.016
- 0.003 0.016
- 0.003 04/02/97 0.016
- 0.003 0.014 + 0.003 0.017
- 0.003 0.016
- 0.003 0.016
- 0.003 04/09/97 0.013
- 0.003 0 015
- 0.003 0.015
- 0.003 0.011
- 0.003 0.016
- 0.003 04/16/97 0.019
- 0.004 0.019 i 0.004 0.022
- 0.004 0.021
- O 004 0.02I
- 0.004 04/23/97 0.020
- 0.004 0.020
- 0.004 0.025
- 0.004 0.022
- 0.004 0.023
- 0.004 04/30/97 0.015
- 0.003 0.015
- 0.003 0.019
- 0.004 0.018 i 0.003 0.013
- 0.003 05/07/97 0.020
- 0.003 0.018
- 0.003 0.017
- 0.003 0.015
- 0.003 0.020
- 0.003 05/14/97 0.013
- 0.003 0.013
- 0.003 0.014
- 0.003 0.013
- 0.003 0.011
- 0.003 05/21/97 0.024
- 0.004 0.020
- 0.004 0.021
- 0.003 0.020
- 0.003 0.020
- 0.003 05/28/97 0.009
- 0.003 0.011
- 0.003 0.012
- 0.003 0.011
- 0.003 0.012
- 0.003 06/04/97 0.01I
- 0.003 0.012
- 0.003 0.013
- 0.003 0.013 *0.003 0.011
- 0.003 06/11/97 0.010
- 0.003 0.009
- 0.003 0.014
- 0.003 0.013
- 0.003 0.011
- 0.003 06/18/97 0.015
- 0.003 0.016
- 0.003 0.014
- 0.003 0.016
- 0.003 0.015
- 0.003 06/25/97 0.02I
- 0.003 0.026
- 0.004 0.022
- 0.004 0.023
- 0.004 0.023
- 0.004 07/02/97 0.020
- 0.004 0.017
- 0 003 0.018
- 0.003 0.018
- 0.003 0.018
- 0.003 07/09/97 0.014
- 0.003 0.015
- 0.003 0.016
- 0.003 0.015
- 0.003 0.015
- 0.003 07/16/97 0.015
- 0.003 0.019
- 0.003 0.020
- 0.003 0.017
- 0.003 0.018
- 0.003 07/23/97 0.025
- 0.004 0.026
- 0.004 0.028
- 0.004 0.031
- 0.004 0.026
- 0.004 07/30/97 0.028
- 0.004 0.026
- 0.004 0.025
- 0.004 0.022
- 0.004 0.028
- 0.004 08/06/97 0.030
- 0.004 0.026
- 0.004 0.031
- 0.004 0.033
- 0.004 0.026
- 0.004 l 08/l3/97 0.020
- 0.004 0.019
- 0.004 0.020
- 0.004 0.023
- 0.004 0.020
- 0.004 08/20/97 0.013
- 0.003 0.014 i 0.003 0.014
- 0.003 0.014
- 0.003 0.0II
- 0.003 l 08/27/97 0.027
- 0.004 0.022 + 0.004 0.027
- 0.004 0.026
- 0.004 0.028
- 0.004 l 09/03/97 0.030
- 0.004 0.030
- 0.004 0.030
- 0.004 0.033
- 0.004 0.030
- 0.004 l 09/10/97 0.026
- 0.004 0.029 + 0.004 0.028
- 0.004 0.026
- 0.004 0.026
- 0.004 09/I7/97 0.033
- 0.004 0.034 + 0.004 0.033
- 0.004 0.033
- 0.004 0.029
- 0.004 l 09/24/97 0.022
- 0.004 0.021
- 0.004 0.019
- 0.004 0.017
- 0.004 0.019
- 0.004 10/0I/97 0.019
- 0.003 0.023
- 0.004 0.027
- 0.004 0.025
- 0.004 0.024
- 0.004 10/08/97 0.031
- 0.004 0.039
- 0.004 0.034
- 0.004 0.035
- 0.004 0.034
- 0.004 10/15/97 0.023
- 0.004 0.022
- 0.004 0.027
- 0.005 0.020
- 0.003 0.024
- 0.004 10/22/97 0.018
- 0.003 0.022
- 0.004 0.020
- 0.005 0.019
- 0.003 0.021
- 0.003 10/29/97 0.019
- 0.003 0.020 + 0.003 0.024
- 0.004 0.022
- 0.004 0.02I
- 0.004 11/05/97 0.02I
- 0.003 0.019
- 0.003 0.019
- 0.003 0.019
- 0.003 0.020
- 0.003 11Il2/97 0.018
- 0.003 0.019
- 0.003 0.019
- 0.003 0.02I
- 0.003 0.021
- 0.003 11Il9/97 0.020
- 0.004 0.008 + 0.004 0.022
- 0.004 0.020
- 0.003 0.023
- 0.003 II/26/97 0.052 s 0.005 0.059 + 0.005 0.049
- 0.005 0.052
- 0.005 0.054
- 0.005 12/03/97 0.025
- 0.004 0.019
- 0.003 0.023
- 0.004 0.023
- 0.004 0.024
- 0.004 12/10/97 0.008
- 0.003 0.012
- 0.003 0.009
- 0.003 0.011
- 0.003 0.011
- 0.003 12/17/97 0.032
- 0.004 0.036
- 0.004 0.032
- 0.004 0.035
- 0.004 0.037
- 0.004 12/23/97 0.029
- 0.004 0.033
- 0 004 0.033
- 0.004 0.031 *.0.004 0.035
- 0.004 12/31/97 0.024
- 0.003 0.024 i0.003 0.020
- 0.003 0.023
- 0.003 0.025
- 0.003 I
l E-3 i J I I
I 1 I TABLE E-l (Cont'd) DATECollFCTED Cl 7 Cl-8 CI A l* CIA 5 Cl 94 01/08/97 0.023
- 0.003 0.021
- 0.003 0.025
- 0.003 0.02I
- 0.003 0.026
- 0.003 01/I5/97 0.035
- 0.004 0.035
- 0.004 0.033
- 0.004 0.04I
- 0,004 0.036
- 0.004 01/22/97 0.023
- 0.004 0.023
- 0.004 C.02I*0.003 0.020
- 0.003 0.024
- 0.004 0I/29/97 0.023
- 0.003 0.023
- 0.003 0.026
- 0.003 0.019
- 0.003 0.025
- 0.003 02/05/97 0.022
- 0.003 0.022
- 0.003 0.024
- 0.003 0.022
- 0.003 0.022
- 0.003 02/12/97 0.025
- 0.004 0.02I i 0.004 0.022
- 0.004 0.019
- 0.003 0.024
- 0.004 02/19/97 0.026
- 0.004 0.024
- 0.004 0.023
- 0.004 0.025
- 0.004 0.03I
- 0.004 l 02/26/97 0.019
- 0.003 0.017
- 0.003 0.015
- 0.003 0.015
- 0.003 0.011
- 0.003 03/05/97 0.018
- 0.003 0.019 i 0.003 0.017
- 0.003 0.017
- 0.003 0.017
- 0.003 03/12/97 0.02I
- 0.003 0.02I
- 0.003 0.022
- 0.003 0.019
- 0.003 0.023
- 0.003 03/19/97 0.017
- 0.004 0.015
- 0.003 0.019
- 0.004 0.017
- 0.003 0.021
- 0.004 03/26/97 0.012
- 0.003 0.014
- 0.003 0.017
- 0 003 0.015
- 0.003 0.015
- 0.003 04/02/97 0.016
- 0.003 0.015 e. 0.003 0.015
- 0.003 0.014
- 0.003 0.016
- 0.003 04/09/97 0.014
- 0.003 0 012
- 0.003 0.013
- 0.003 0.014
- 0.003 0.015
- 0.003 04/16/97 0.023
- 0.004 0.022
- 0.004 0.022
- 0.004 0.020
- 0.004 0.025
- 0.004 04/23/97 0.023
- 0.004 0.023
- 0.004 0.02I
- 0.004 0.020
- 0.004 0.02I
- 0.004 04/30/97 0.015
- 0.003 0.016
- 0.003 0.016
- 0.003 0.017
- 0.003 0.015
- 0.003 05/07/97 0.017
- 0.003 0.020
- 0.003 0.019
- 0.003 0.018
- 0.003 0.019
- 0.003 05/14/97 0.013
- 0.003 0.011
- 0.003 0.009
- 0.003 0.010
- 0.003 0.013
- 0.003 05/21/97 0.019
- 0.003 0.020
- 0.003 0.012
- 0.004 0.016
- 0.003 0.022
- 0.004 05/28/97 0.013
- 0.003 0.011
- 0.003 0.014
- 0.003 0.009
- 0.003 0.009
- 0.003 06/04/97 0.012
- 0.003 0.011
- 0.003 0.013
- 0.003 0.008
- 0.003 0.015
- 0.003 06/1I/97 0.013
- 0.003 0.014
- 0.003 0.012
- 0.003 0.007
- 0.003 0.012
- 0.003 06/18/97 0.011
- 0.003 0.014
- 0.003 0.015 *0.003 0.010
- 0.003 0.016
- 0.003 06/25/97 0 024
- 0.004 0.02I
- 0.004 0.025
- 0.064 0.02I
- 0.004 0.023
- 0.004 07/02/97 0.020
- 0.004 0.018
- 0.004 0.021
- 0.004 0.018
- 0.003 0.022
- 0.004 07/09/97 0.014
- 0.003 0.014
- 0.003 0.015
- 0.003 0.015
- 0.003 0.014
- 0.003 i 07/16/97 0.018
- 0.003 0.016
- 0.003 0.019
- 0.003 0.018
- 0.003 0.020
- 0.003 1
07/23/97 0.025
- 0.004 0.026
- 0.004 0.033
- 0.004 0.025
- 0.004 0.026
- 0.004 07/30/97 0.026
- 0.004 0.019
- 0.004 0.020
- 0.004 0.024
- 0.004 0.024
- 0.004 08/06/97 0.025
- 0.004 0.028
- 0.004 0.029
- 0.004 0.022
- 0.004 0.030
- 0.004
( 08/I3/97 0.018
- 0.004 0.018
- 0.004 0.019
- 0.004 0.018
- 0.004 0.026
- 0.004 l 08/20/97 0.013
- 0.003 0.015
- 0.003 0.014
- 0.003 0.013
- 0.003 0.013
- 0.003 l 08/27/97 0.029
- 0.004 0.024
- 0.004 0.028
- 0.004 0.02I
- 0.004 0.024
- 0.004
! 09/03/97 0.029
- 0.004 0.026
- 0.004 0.032
- 0.004 0.026
- 0.004 0.028
- 0.004 09/10/97 0.029
- 0.004 0.028
- 0.004 0.029
- 0.004 0.028
- 0.004 0.030 1 0.004 09/17/97 0.032
- 0.004 0.031
- 0.004 0.033
- 0.004 0.028
- 0.004 0.028
- 0.004 09/24/97 0.015
- 0.003 0.02I
- 0.004 0.020
- 0.004 0.015
- 0.003 0.020
- 0.004 10/01/97 0.023
- 0.004 0.024
- 0.004 0.025
- 0.004 0.022
- 0.003 0.025
- 0.004 10/08/97 0.029
- 0.004
. 0.032
- 0.004 0.030
- 0.004 0.031
- 0.004 0.034
- 0.004 10/15/97 0.022
- 0.004 0.025
- 0.004 0.024
- 0.004 0.019
- 0.003 0.023
- 0.004 10/22/97 0.017
- 0.003 0.02I
- 0.004 0.017
- 0.003 0.014
- 0.003 0.019
- 0.003 10/29/97 0.023
- 0.004 0.024
- 0.004 0.022
- 0.003 0.020
- 0.003 0.023
- 0.004 11/05/97 0.019
- 0.003 0.02I
- 0.003 0.020
- 0.003 0.017
- 0.003 0.020
- 0.003 11/12/97 0.019
- 0.003 0.022
- 0.003 0.020
- 0.003 0.019
- 0.003 0.022
- 0.003 11/19/97 0.017
- 0.004 0.018
- 0.003 0.023
- 0.004 0.017
- 0.003 0.014
- 0.003 11/26/97 0. % 4
- 0.005 0.051
- 0.005 0.054
- 0.005 0.052
- 0.005 0.055
- 0.005 12/03/97 0.019
- 0.003 0.027
- 0.004 0.030
- 0.004 0 025
- 0.004 0.023
- 0.004 12/10/97 0.009
- 0.003 0.013
- 0.003 0.012
- 0.003 0.012
- 0.003 0.01I
- 0.003 12/17/97 0.033
- 0.004 0.032
- 0.004 0.032
- 0.004 0.034
- 0.004 0.032
- 0.004 12/23/97 0.028
- 0.004 0.031
- 0.004 0.034
- 0.004 0.033
- 0.004 0.033
- 0.004 12/3I/97 0.02I
- 0.003 0.025
- 0.003 0.027
- 0.003 0.025
- 0.003 0.022
- 0.003 a all1-131 activity was <0.7 pCi/m' b control location, all other locations are indicators E-4 I
TABLE E-2 GAMMA ISOTOPIC ACTIVITY IN AIR PARTICULATES FOR 1997 (pCi/m') i SITE ISOTOPE 1" QTR 2" QTR 3"" QTR 4" QTR CL-I Be-7 0.07i
- 0.008 0.092
- 0.010 0.093 i 0.0'0 0.060
- 0.013 K-40 < 0.016 < 0.013 < 0.023 < 0.025 g Co-60 < 0.0005 < 0.0004 < 0.0010 <0.0011 g Zr-95 < 0.0014 < 0.0007 < 0.0005 < 0.0005 Nb-95 < 0.0008 < 0.0006 < 0.0008 < 0.0008 Ru-103 < 0.0004 < 0.0005 < 0.0007 < 0.0004 i Ru-106 Cs-134
< 0.0024
< 0.0004
< 0.0031
< 0.0004
< 0.0026
< 0.0014
< 0.0092
< 0.0003 Cs-137 < 0.0006 < 0.0005 < 0.0003 < 0.0003 Ce-141 < 0.0007 < 0.0006 < 0.0011 < 0.0016 Ce-144 < 0.0028 < 0.0014 <0.0038 < 0.0037 I CL-2 Be-7 0.067 i 0.010 0.10
- 0.007 0.10 0.013 0.062 0.016 K-40 < 0.017 < 0.017 < 0.024 < 0.024 l Co-60 <0.0007 < 0.0006 < 0.0010 < 0.0012 5 Zr-95 < 0.0018 < 0.0015 < 0.0009 < 0.0010 Nb-95 < 0.0010 < 0.0006 < 0.0005 < 0.0006 g Ru-103 < 0.0009 < 0.0003 < 0.0006 < 0.0006 g Ru-106 < 0.0064 < 0.0057 < 0.0037 < 0.0023 Cs-134 < 0.0003 < 0.0004 < 0.0003 < 0.0005 Cs-137 < 0.0007 < 0.0005 < 0.0004 < 0.0007 Cc-141 < 0.0015 < 0.0008 < 0.0013 < 0.0013 Cc-144 < 0.0029 < 0.0024 < 0.0059 < 0.0025 CL-3 Be-7 0.072
- 0.013 0.095
- 0.008 0.092 0.011 0.058* 0.011 K-40 < 0.025 < 0.015 < 0.024 < 0.027 Co-60 < 0.0004 < 0.0006 < 0.0009 < 0.0012 Zr-95 < 0.0008 < 0.0012 < 0.0007 < 0.0006 Nb-95 < 0.0011 < 0.0006 < 0.0009 < 0.0005 lr Ru-103 Ru-106
< 0.0008
< 0.0054
< 0.0003
<0.0042
< 0.0008
< 0.0051
< 0.0008
< 0.0072 Cs-134 < 0.0003 < 0.0005 < 0.0007 < 0.0009 Cs-137 < 0.0005 < 0.0004 < 0.0006 < 0.0008 Cc-141 < 0.0017 < 0.0008 < 0.0012 < 0.0019 Cc-144 < 0.0033 < 0.0030 < 0.0028 < 0.0042 l
l l E-5 L
I I TABLE E-2 (Cont'd) SITE ISOTOPE 1" QTR 2* QTR 3"" QTR 4" QTR CL-4 Be-7 0.065
- 0.012 0.091i 0.006 0.091* 0.011 0.056* 0.01I K-40 < 0.025 < 0.009 < 0.024 <0.024 Co-60 <0.0003 <0.0003 < 0.0011 < 0.0011 Zr-95 < 0.0013 < 0.0008 < 0.0011 < 0.0004 Nb-95 < 0.0009 < 0.0005 < 0.0005 < 0.0011 Ru-103 < 0.0007 < 0.0004 < 0.0005 Ru-106 < 0.0027 < 0.0033 < 0.0037
< 0.0012
< 0.0089 l
W Cs-134 < 0.0004 < 0.0004 < 0.0005 < 0.0003 Cs-137 < 0.0006 < 0.0004
<0.0006
< 0.0007 < 0.0004 g l Ce-141 < 0.0009 < 0.0008 < 0.0008 g Ce-144 < 0.0042 < 0.0020 < 0.0050 < 0.0046 CL-6 Be-7 0.052 0.017 0.10t 0.014 0.080
- 0.011 0.062
- 0.012 K-40 < 0.025 < 0.022 < 0.023 < 0.025 l Co-60 < 0.0011 < 0.0009 < 0.0010 <0.0010 Zr-95 < 0.0005 < 0.000"'
l Nb-95 < 0.0012 < 0.0009
< 0.0004
<0.0005
< 0.0012
<0.0006 l
5 Ru-103 < 0.0008 < 0.0008 < 0.0009 < 0.0009 Ru-106 < 0.0070 < 0.0058 < 0.0033 < 0.0044 g Cs-134 Cs-137
< 0.0003
< 0.0008
< 0.0007
< 0.0069
< 0.0003 < 0.0016 g
< 0.0006 < 0.0007 Ce-141 < 0.0017 < 0.0011 < 0.0013 < 0.0015 Cc-144 < 0.0034 < 0.0039 < 0.0057 < 0.0058 CL-7 Be-7 0.068* 0.015 0.10* 0.019 0.091* 0.012 0.053
- 0.011 K-40 Co-60
< 0.025 < 0.038 < 0.024 < 0.025 g j
Zr-95
< 0.0004 < 0.0006 < 0.0010 < 0.0012 g l < 0.0005 < 0.0014 < 0.0012 < 0.0012 Nb-95 < 0.0008 < 0.0021 < 0.0008 < 0.0011 Ru-l03 <0.0008 < 0.0011 < 0.0007 < 0.0007 Ru-106 < 0.0029 < 0.0102 < 0.0038 < 0.0090 v Cs-134 < 0.0007 < 0.0006 < 0.0005 < 0.0016 Cs-137 < 0.0005 < 0.0011 < 0.0006 l Ce-141 < 0.0013 < 0.0021 < 0.0015
< 0.0010
< 0.0017 l
W Ce-144 < 0.0023 < 0.0071 < 0.0041 < 0.0043 CL-8 Be-7 0.068
- 0.011 0.1Ot 0.015 0.080
- 0.012 0.052 0.012 K-40 < 0.024 < 0.029 < 0.024 < 0.024 Co-60 < 0.0005 < 0.0006 < 0.0011 < 0.0011 Zr-95 < 0.0008 < 0.0013 < 0.0005 < 0.0008 Nb-95 < 0.0009 < 0.0001 < 0.0004 < 0.0009 l
Ru-103 < 0.0008 < 0.0005 < 0.0004 < 0.0008 Ru-106 <0.0054 < 0.0062 < 0.0024 < 0.0064 Cs-134 < 0.0005 <0.0006 < 0.0006 < 0.0007 Cs-137 < 0.0005 < 0.0005 < 0.0004 < 0.0003 Cc-141 < 0.0014 < 0.0008 < 0.0015 < 0.0014 Cc-144 < 0.0043 < 0.0017 < 0.0040 < 0.0041 E-6 I
TABLE E-2 (Cont'd) SITE ISOTOPE 1" QTR 2* QTR 3" QTR 4* QTR CL-1 I Be-7 0.071
- 0.008 0.093
- 0.014 0.091 0.009 0.0681 0.013 K-40 < 0.015 < 0.024 < 0.023 < 0.024 Co-60 < 0.0003 < 0.0009 < 0.0007 <0.0012 Zr-95 < 0.0006 < 0.0015 < 0.0016 < 0.0005 Nb-95 < 0.0005 < 0.0006 < 0.0004 < 0.0005 Ru-103 < 0.0006 < 0.0005 < 0.0005 < 0.0004 Ru-106 <0.0038 < 0.0059 < 0.0030 < 0.0033 Cs-134 < 0.0005 < 0.0005 < 0.0004 < 0.0015 Cs-l37 < 0.0004 < 0.0038 < 0.0006 < 0.0005 Ce-141 < 0.0008 < 0.0013 < 0.0012 < 0.0013 Ce-144 < 0.0015 < 0.0032 < 0.0016 < 0.0035 CL-15 Be-7 0.072
- 0.013 0.088
- 0.011 ~ 0.091
- 0.012 0.057
- 0.010 K-40 < 0.024 < 0.025 < 0.023 < 0.024 Co-60 < 0.0008 < 0.0002 < 0.0008 < 0.0011 Nb-95 < 0.0016 < 0.0016 < 0.0005 < 0.0013 Zr-95 < 0.0012 < 0.0009 <0.0006 < 0.0006 i Ru-103 Ru-106 Cs-134
< 0.0008
< 0.0047
< 0.0009
< 0.0005
< 0.0072
< 0.0006
< 0.0005
< 0.0074
< 0.0007
<0.0005
< 0.006I
< 0.0015 Cs-137 < 0.0003 < 0.0007 < 0.0008 < 0.0005 Cc-141 < 0.0012 < 0.0008 < 0.0007 < 0.0019 Cc-144 < 0.0034 < 0.0024 < 0.0042 < 0.0052 CL 94 Be-7 0.072
- 0.007 0.10
- 0.017 0.087
- 0.014 0.059
- 0.011 K-40 < 0.017 < 0.035 < 0.024 < 0.024 l
E Co-60 Nb-95
< 0.0004
< 0.0008
< 0.0009
< 0.0016
< 0.0009
< 0.0013
< 0 0010
< 0.0006 Zr-95 < 0.0003 < 0.0012 < 0.0005 < 0.0011 g Ru l03 < 0.0006 < 0.0012 < 0.0008 < 0.0008 g Ru-106 < 0.0037 < 0.0081 < 0.0023 < 0.0046 Cs-134 < 0.0003 < 0.0009 < 0.0014 < 0.0008 Cs-137 < 0.0006 < 0.0005 < 0.0004 < 0.0004 l
8 Ce-141 Ce-144
< 0.0008
< 0.0022
< 0.0012
< 0.0041
< 0.0016
< 0.0025
< 0.0007
< 0.0033 l
l E-7
I TABLE E-3 4 1997 CPS REMP OUARTERLY TLD RESULTS g (mR/ quarter Net Exposure) g Location I" QTR 2* QTR 3" QTR 4" QTR CL-1 14.1
- 0.2 16.9
- 0.2 17.1
- 0.2 18.5
- 0.2 CL-2 14.8 0.2 17.0
- 0.2 18.1 i 0.2 19.0
- 0.2 CL-3 14.5 i 0.3 16.5
- 0.2 17.8
- 0.2 17.7
- 0.2 CL-4 15.3
- 0.2 15.0
- 0.3 17.4
- 0.2 17.4 0.2 g CL-5 15.4
- 0.2 18.3 t 0.2 18.6
- 0.4 18.9 i 0.2 g CL-6 12.1
- 0.2 13.9 0.2 14.9
- 0.2 15.6
- 0.3 CL-7 13.9
- 0.3 15.2
- 0.3 16.2
- 0.2 17.0
- 0.2 CL-8 13.7
- 0.2 15.9
- 0.2 16.5
- 0.2 17.6 0.2 CL-11 14.0
- 0.2 16.7
- 0.2 15.7
- 0.2 16.6
- 0.2 CL-15 12.4
- 0.2 15.0
- 0.4 14.7 1 0.3 15.5
- 0.2 CL-20 16.1 0.2 19.3
- 0.2 18.1
- 0.2 19.2
- 0.2 l CL-21 16.4
- 0.2 17.9
- 0.2 18.2
- 0.2 19.3
- 0.3 W CL-22 15.5
- 0.2 16.2
- 0.2 17.2
- 0.2 18.1
- 0.2 CL-23 12.2 i 0.2 12.9 i 0.2 12.8
- 0.2 14.7 t 0.2 CL-24 14.0
- 0.3 17.7
- 0.2 17.2
- 0.2 17.3
- 0.2 CL-25 11.8
- 0.3 14.3
- 0.2 13.8
- 0.2 14.6
- 0.2 CL-26 13.0
- 0.2 13.9 i 0.2 15.3
- 0.2 15.8
- 0.2 CL-27 13.8
- 0.2 15.2 0.2 17.1
- 0.2 18.4
- 0.2 CL-28 15.1*0.2 17.1
- 0.2 17.9
- 0.3 19.5
- 0.3 CL-29 15.9 i 0.2 17.0
- 0.2 18.0
- 0.4 19.6 0.3 CL-30 16.3 02 17.0
- 0.2 18.2
- 0.3 19.5 0.3 g CL-31 12.5
- 0.2 13.8 0.2 15.1* 0.2 17.0
- 0.2 3 CL-32 13.7
- 0.5 15.4
- 0.2 16.2
- 0.2 17.4
- 0.4 CL-33 16.7
- 0.2 17.6 0.2 18.9
- 0.2 19.5
- 0.4 CL-34 16.8
- 0.2 17.5
- 0.2 18.7 0.4 19.5
- 0.2 l CL-35 14.0
- 0.4 14.4
- 0.2 16.5 0.2 17.7
- 0.2 CL-36 15.4 0.2 15.0 0.3 17.5
- 0.2 18.6
- 0.2 CL-37 16.4
- 0.2 15.2
- 0.4 17.8
- 0.2 18.8
- 0.2 CL-38 15.5
- 0.2 16.3
- 0.2 18.1 0.2 19.6
- 0.2 l
5 CL-39 14.6 i 0.5 14.1 0.2 16.6
- 0.2 17.6
- 0.2 CL-40 14.1
- 0.3 15.4
- 0.3 16.8
- 0.2 17.7
- 0.2 CL-41 15.5 0.2 17.3
- 0.2 18.1
- 0.2 18.8
- 0.8 CL-42 15.5
- 0.2 15.1
- 0.4 17.5
- 0.2 18.7 A 0.2 CL-43 16.8
- 0.2 15.0 0.4 19.7
- 0.2 20.0
- 0.2 CL-44 16.8 0.2 16.6
- 0.2 19.5
- 0.2 21.1
- 0.2 CL-45 17.2
- 0.2 18.5
- 0.2 20.0
- 0.2 20.7
- 0.2 CL-46 15.9
- 0.2 15.9 A 0.2 19.2
- 0.2 19.5 0.2 CL-47 16.7
- 0.2 17.0
- 0.2 18.2
- 0.2 20.4 0.2 CL-48 14.0
- 0.3 16.5
- 0.2 17.6
- 0.2 18.4
- 0.2 E
g CL-49 16.4
- 0.2 17.6
- 0.2 19.2
- 0.2 19.5*0.3 CL-50 16.6 0.2 17.1
- 0.2 18.3
- 0.2 18.8
- 0.2 CL-51 15.5
- 0.2 17.5
- 0.2 17.8
- 0.2 19.4
- 0.3 CL-52 15.4
- 0.2 16.3
- 0.2 18.0
- 0.2 18.5
- 0.2 Cl-53 15.5
- 0.2 14.3 i 0.2 17.5 0.2 18.4
- 0.2 E-8 I
1 1 l i TABLE E-3 (Cont'd) j Location 1" QTR 2*"QTR 3""QTR 4' QTR l CL-54 15.1
- 0.2 16.8 i 0.2 17.1 0.2 18.210.2 l CL-55 15.5
- 0.2 18.4
- 0.2 17.5
- 0.2 18.4 i 0.2 l CL-56 15.2
- 0.2 18.5
- 0.2 18.2
- 0.3 19.5
- 0.3
! CL-57 16.0
- 0.2 17.5
- 0.2 18.7
- 0.2 18.5 1 0.2 CL-58 16.5
- 0.3 16.9*0.2 19.1
- 0.2 19.2
- 0.3 CL-59 16.4
- 0.2 17.6
- 0.2 19.8
- 0.2 19.5
- 0.2 CL-60 16.2
- 0.3 17.5
- 0.2 19.5
- 0.2 19.4 i 0.2 CL-61 16.2 i 0.2 17.5
- 0.2 18.1
- 0.2 19.5 i 0.2 i CL-62 15.9
- 0.2 17.5
- 0.2 18.3
- 0.2 19.3
- 0.3 i CL-63 17.6
- 0.2 18.7
- 0.2 18.8
- 0.2 19.7
- 0.2 l CL-64 16.1 0.2 17.6 0.2 18.1
- 0 3 19.5
- 0.3 I CL-65 16.7
- 0.2 17.5 0.2 19.6 0.2 19.7
- 0.2 CL-66 12.5
- 0.2 13.4
- 0.2 14.7
- 0.2 13.7
- 0.3 CL-67 14.9i0.5 15.0
- 0.3 16.5 0.2 17.7
- 0.2 CL-68 13.8
- 0.2 13.5
- 0.2 16.4
- 0.2 17.2 i 0.2 CL-69 13.9
- 0.3 14.9
- 0.3 15.7 0.2 16.9 i 0.2 CL-70 14.0
- 0.4 14.8
- 0.2 16.5
- 0.2 17.3
- 0.2 CL-71 13.8
- 0.2 14.0*0.2 15.5
- 0.2 16.6
- 0.2 CL-72 15.5
- 0.2 15.1
- 0.3 16.5
- 0.2 17.7
- 0.2 CL-73 15.9
- 0.2 17.7*0.9 18.2
- 0.4 I8.6
- 0.2 CL-74 15.4
- 0.2 15.8
- 0.2 18.1
- 0.3 18.5
- 0.2 CL 75 15.5
- 0.2 16.6
- 0.2 18.9
- 0.2 19.4
- 0.4 CL-76 15.9
- 0.2 16.9 i 0.2 19.5
- 0.2 19.5
- 0.3 CL-77 15.2
- 0.2 15.0
- 0.3 17.1
- 0.2 18.9 0.2 CL~8 14.2
- 0.2 17.5
- 0.2 18.2
- 0.2 19.5
- 0.3 CL-79 15.9
- 0.2 17.5
- 0.2 19.9
- 0.2 19.4
- 0.3 CL-80 15.2
- 0.2 16.6 i 0.2 19.5 0.2 18.4
- 0.2 CL-81 14.3
- 0.4 17.4
- 0.2 18.1 0.3 19.5
- 0.4 CL-82 14.3
- 0.4 13.9
- 0.2 18.3 0.2 18.1
- 0.2 CL-83 16.7
- 0.2 17.3
- 0.2 19.8
- 0.2 19.6
- 0.2 CL-84 14.3
- 0.2 14.3 i 0.2 16.5
- 0.2 16.8
- 0.2 CL-85 15.8
- 0.2 16.4 0.2 19.5 0.2 17.8
- 0.2 CL-86 14.2
- 0.4 16.3 0.2 17.9
- 0.3 16.9
- 0.2 CL-87 14.2
- 0.2 15.2
- 0.2 17.8
- 0.2 18.8
- 0.2 CL-95 15.9
- 0.2 18.3
- 0.2 19.5
- 0.2 19.4
- 0.3 CL-96 14.4
- 0.4 14.4
- 0.3 16.5
- 0.2 17.4
- 0.2 CL-97 15.5 i 0.2 16.9*0.2 18.4
- 0.3 19.1
- 0.2 CL-109 13.7
- 0.2 15.1
- 0.4 15.8
- 0.2 16.9
- 0.2 CL-110 15.2
- 0.2 17.4 0.2 17.7
- 0.4 I8.8
- 0.2 CL-111 15.6
- 0.2 ND' 16.8
- 0.2 16.9 i 0.2 CL 112 14.5
- 0.3 15.8
- 0.2 16.7
- 0.2 17.8
- 0.2 CL-113 13.5
- 0.2 15.8
- 0.5 16.0
- 0.2 ND'
'ND = No Data; TLD lost in the field E-9
I TABLE E-4 SURFACE WATER BETA AND GAMMA ISOTOPIC ACTIVITY (pCi/l) - CL-9 6 Date Collected 01-29-97' 02-26-97' 03-26-97 04-30-97 Gross Beta - - 2.2
- 0.7 2.6
- 0.6 Be-7 - - < l5.4 < 28.0 K-40 - -
< 35.2 < 38.7 Mn-54 - -
< 2.0 <2.5 Fe-59 - -
<4.1 <2.2 l Co-58 - - <2.0 < 2.7 =
Co-60 - - <2.3 < 2.8 Zn-65 Zr-95
< 7.4
< 5.2
<3.6
< 5.6 5
g Nb-95 - - < 2.0 <2.0 Cs-134 - -
< l.8 < l.5 g Cs-137 Ba-140
<2.3
< 6.1
< l.7
< 14.4 g
La 140 - -
<2.6 <3.3 Ce-144 - - < 30.8 < 39.8 TABLE E-5 SURFACE WATER BETA AND GAMMA ISOTOPIC ACTIVITY (pCill) - CL-10 (control) 6 Date Collected 01-29-97' 02-26-97* 03-26-97 04-30-97 Gross Beta - -
2.0
- 0.9 2.20.7 Be-7 - -
< 20.9 < 27.5 K-40 - -
< 30.1 < 34.6 Mn 54 Fe-59
< l.9
<3.4
<2.0
<4.3 5
Ur Co-58 - -
<l.5 <l.6 Co-60 - -
< 2.0 <2.0 E Zn-65 - -
<2.2 < 3.4 5 Zr-95 - -
< 4.4 <5.2 Nb-95 - -
< 2.3 <3.3 g Cs-134 - -
<2.6 <2.4 g Cs-137 - - <2.1 <2.6 Ba-140 - - <6.8 < 16.3 La-140 - -
<3.0 < 2.6 Ce-144 - -
< 27.7 < 32.8
- ND = Sample not collected
- Location deleted as a surface water sample E-10 E
l TABLE E-6 SURFACE WATER BETA AND GAMMA ISOTOPIC ACTIVITY (pCi/l) - Cl 13 paie Collected 01-29-97 02-26-97 03-26-97 04-30-97 05-28-97 06-25 97 Gross Beta 2.I i 0.3 2.2
- 3.6 2.6 0.6 2.4* 0.6 2.0i 0.8 2.3* 0.6 Be-7 < 23.6 < 20.8 < 14.8 < 26.8 < 22.9 < 62.7 K-40 < 36.0 < 27.1 < 26.4 < 39.9 < 30.8 < 101.0 Mn-54 <2.1 < l.4 < 0.9 < 2.8 < l.4 < 4.3 l
p Fe-59 Co-58
< 5.7
< 2.7
<3.3
<l.2
< 3.2
< l.7
< 5.5
< 2.6
< 5.4
< 2.2
< 6.6
<6.4 Co-60 <2.2 <l.5 < l.6 <3.0 < 2.2 < 6.1 g Zn-65 < 2.4 <5.3 < 3.1 <5.0 <3.8 < 5.1 y Zr-95 <3.5 < 4.4 < l.8 < 5.9 < 3.2 <l5.0 Nb-95 <2.9 < 2.3 < l.8 <l.6 <3.0 < 7.6 Cs-134 < 2.4 < l.6 < l.8 < 2.6 < 2.2 < 2.9 Cs-137 < l.7 <l.8 < l.9 < 2.7 < 2.4 < 6.7 Ba-140 < 7.8 < 18.6 < 6.9 < 16.5 < 14.6 <51.0 La 140 <4.0 < 2.6 < l.1 < 5.4 < 4.1 <11.9 Ce-144 < 16.1 < 29.6 < 16.8 < 25.8 < 31.1 < 62.9 1 Date Collected 07-30-97 08-27-97 09-24-97 10-29-97 11-26-97 12-31-97 Gross Beta 2.0
- 0.6 2.2
- 0.7 2.7* 0.6 2.8* 0.6 2.5* 0.4 2.4* 0.6 Be-7 < 63.1 < 56.4 < 46.1 < 17.3 < 30.8 < 30.4 K-40 < 108.0 < 116.0 < 87.8 < 53.5 < 42.7 < 78.9 Mn-54 <3.6 <5.5 < 3.2 < l.5 < l.6 < 3.3 Fe-59 < 8.5 < 10.0 < 5.4 < 6.8 < 6.1 < l.8 Co-58 <5.5 < 8.6 . < l.8 < 2.5 <2.2 < 2.0 Co-60 < 6.8 < 4.0 < 2.5 <2.3 <2.5 <2.9 Zn-65 < 5.0 <5.7 < 7.2 <3.2 <2.2 <3.5 Zr-95 < 17.7 < 8.0 < 9.7 <3.1 <3.8 < 7.9 i Nb-95 < 7.2 < 10.2 < 2.7 <3.7 < l.9 <3.0 I
Cs-134 < 5.2 <5.6 < 3.9 < 2.6 <3.4 < 2.0 Cs-137 <5.9 < 6.4 <3.6 <3.0 <3.3 < 3.2 Ba-140 < 47.7 < 22.7 < 34.0 < 20.0 < 11.2 < 14.8 La-140 < 11.6 < 9.4 < 6.8 < 2.4 <2.1 < 3.7 Cc-144 < 46.1 < 66.7 < 27.6 < 21.7 < 30.7 < 37.5 E-11 l
I TABLE E-7 SURFACE WATER GROSS BETA. GROSS ALPilA. I-131 AND GAMMA ISOTOPlc ACTIVITY (pCi/l)- CL-90 Date Collected 01-29 97 02-26-97 03-26-97 04-30-97 05-28-97 06-25-97 Gross Alpha <0.6 0.9 i 0.4 <0.7 1.l* 0.6 < l.3 0.7+ 0.5 Gross Beta 2.3* 0.5 2.9
- 0.4 2.8
- 0.5 2.5* 0.5 2.6i 0.8 2.5 i 0.5 lodine-131 < 0.4 <0.4 < 0.4 < 0.4 < 0.4 < 0.4 Be-7 <18.6 < 25.9 < 17.7 < 18.3 < 13.7 <l 9.6 K-40 < 34.2 < 38.6 < 29.1 < 38.0 < 3 7.2 < 104.0 Mn-54 <2.2 < 2.8 <2.2 < 2.5 < 2.6 < 3.8 Fe-59 <5.2 <4.5 <2.2 <3.4 <5.0 < 4.8 Co-58 <2.2 <2.6 <l.I < 2.5 <2.7 <3.5 Co-60 <l.3 <2.8 <2.2 <2.2 <2.9 <2.6 l
5 Zn-65 <2.7 < 4.8 <l.6 <3.8 < 2.3 <3.0 Zr-95 < 4.4 < 4.0 <3.5 < 6.1 < 5.6 < 9.9 g Nb-95 Cs-134
< 2.9
<2.5
< 2.7
<3.I
< 2.5
< l.9
< 2.4
< 2.2
< 2.8
< 2.4
< 4. I
< 2.6 g
Cs-137 < 2.1 < 2.3 <2.1 < 2.7 <3.I < 4.4 Ba-140 La-140
< 7.8
<2.3
<6.5
<3.4
<6.2
<2.6
< 9.0
< l.3
< 13.7
<3.3
< 19.7
< l.8 h
m Cc-144 < 40.0 < 18.0 < 29.3 < 19.0 < 25.9 < 24.9 Date Collected 07-30-97 08 27-97 09-24-97 10-29-97 11-26-97 12-31-97 Gross Alpha < l.3 < l.6 <2.0 2.8 1.1 0.7 0.4 <0.6 Gross Beta 3.0 0.8 2.1
- 0.8 2.7
- 1. I 6.0 0.9 2.7
- 0.5 2.2
- 0.4 lodine-131 <0.3 < 0.4 < 0.4 < 0.3 < 0.4 <0.3 Be-7 < 34.9 < 21.5 < 32.9 < 59.0 < 35.4 < 29.9 K-40 < 105.0 < 111.0 < 69.8 < 93.2 < 68.8 < 92.6 Mn-54 <2.7 <2.5 < 2.1 <3.1 <3.3 <3.1 Fe-59 <4.2 < 4.8 < 7.1 < 10.0 < 6.2 < 4.6 l
Wr Co-58 <3.4 <3.3 <3.6 <3.5 <3.3 <l.9 Co-60 <3.2
< 5.5
<l.1
<2.5
<2.8 < l.9 < 2.0 <l.7 g Zn-65 <2.9 < 9.6 <3.1 < 4.7 5 Zr-95 <5.7 < 5.6 <4.0 < 10.9 < 10.3 < 8.2 l Nb-95 < 2.I < 2.8 x 1.9 < 2.9
<3.9
< 3.6 <3.7 g Cs-134
<3.6
< 2.2 <3.2 < 2.5 < 4.3 < 4.8 g Cs-137 < 2.9 <3.6 <5.5 < 4.5 <3.9 Ba-140 < 10.3 < 17.6 < 19.5 < 20.6 < 20.5 < 13.3 la-140 < 5.3 < l.9 < 4.4 <2.7 <2.7 < l.8 I
Ce-144 < 24.2 < 39.6 < 35.4 < 31.7 < 31.9 < 28.5 l m,2 I I
TABLE E-8 SURFACE WATER GROSS BETA. GROSS ALPHA.1-131 AND G AMMA ISOTOPIC ACTIVITY (oCi/1)- CL-91 Date Collected 01-29-97 02-26-97 03-26-97 04-30-97 05-28-97 06-25-97 Gross A1pha < 0.9 < l.7 < l.1 0.9
- 0.6 2.3
- 1.5 < 2.6 Gross Beta 3.2
- 0.7 2.8
- 1.I 1.4
- 0.6 1.8
- 0.6 4.0
- 1.2 < 2.8 Be-7 < 24.4 < l 7.2 < l 8.4 < 29.7 < 30.8 < 26.3 K-40 < 32.3 < 28.6 < 39.2 < 36.6 < 39.6 < 75.6 l3 Mn-54 Fe-59
< 2.7
< 6.2
<l.2
<3.5
< 2.5
< 5.9
< 2.6
< 5.9
< 2.9
< 7.0
<3.2
<3.5 Co-58 < 2.3 < l.5 < l.2 < 2.5 <2.9 <3.7 Co-60 <2.5 < l.8 < 2.5 < 2.4 < 2.2 < 2.7 Zn-65 <4.2 < 2.3 <4.1 < 2.4 < 3.6 < 6.3 Zr-95 <2.8 < l.9 < 5.2 < 5.1 <5.0 < 4.9 Nb-95 <3.0 <2.3 <3.0 <3.5 <3.2 <4.6 r
l Cs-134 Cs-137
<2.6
< 2.3
< l.4
<l.7
< 2.4
<2.9
< 3.0
<3.3
< 2.4
<3.3
<4.3
<6.3 Ba-140 < 17.3 < 11.4 < 12.5 < 16.9 < 11.4 < 21.5 i La-140 Ce-144
<3.3
< 20.3
<3.5
< 25.6
<3.9
< 17.5
<2.8
< 12.8
<5.8
< 23.8
< 5.0
< 33.0 Date Collected 07-30-97 08-27-97 09-24-97 10-29-97 11-26-97 12-31-97 Gross Alpha < l.2 < l.6 2.1
- 0.8 6.2
- 2.0 9.1
- 1.1 0.9
- 0.6 Gross Beta 3.3
- 0.9 2.6
- 1.0 3.1
- 0.7 5.4
- 1.2 3.0
- 0.7 1.7
- 0.7 Be-7 < 43.9 < 35.9 < 36.5 < 31.9 < 58.3 < 29.6 K-40 < 109.0 < 78.5 < 73.3 < 64.2 < 99.0 < 88.5 l5 Mn-54 Fe-59
<4.6
< l4.3
< 5.0
< 8.1
< 2.2
<3.6
< 3.2
<3.9
<4.1
< 10.3
<2.4
< 8.6 Co-58 < 4.2 < 2.8 < 5.0 < 2.4 <5.1 <2.2 g Co-60 <3.8 <3.0 < 4.7 < 3.4 <4.0 < l.7 y Zn-65 < 9.0 < 5.5 < 5.9 <3.7 <5.1 < 4.2 Zr-95 < 7.4 < 10.5 < 8.5 < 6.7 < 14.1 < 5.0 Nb-95 < 9.2 <3.2 <3.6 < 5.6 < 3.6 <5.3
) Cs-134 Cs-137
< 4.8
<2.7
<3.5
<4.5
<3.0
< 5.9
< 2.2
<4.0
<6.7
< 2.5
< 5.0
<3.7 Ba-140 < 47.9 < 41.1 < 23.6 < 31.0 < 48.9 < 15.5 La-140 < 12.1 < 6.9 < 8.2 < 6.3 <6.5 <3.3 Cc-144 < 24.3 < 33.5 < 35.9 < 36.2 < 64.9 < 39.1 E-13 l
I l TABl.E E-9 SURFACE WATER GROSS BETA. TRITIUM. l AND GAMM A ISOTOPIC ACTIVITY (pCi/l) - Cl,-99 Date Collected 01-29-97 02-26-97 03-26-97 04-30-97 05-28-97 06-25-97 Gross Alpha < l.5 < l.5 < l.4 <l.3 < 2.5 1.0
- 0.7
- Gross Beta 2.3 i 0.9 2.2
- 0.9 1.6 0.9 1.8
- 0.9 <2.5 2.4 0.9 l Be-7 < 21.6 < 21.9 < 26.0 < 21.0 < 13.6 < 26.0 K-40 < 34.5 < 34.5 < 41.1 < 43.7 < 42.3 < 67.1 Mn-54 < 2.1 <2.0 <2.7 < 2.7 < 2.1 < 2.2 l Fe-59 < 4.0 < 5.3 < 4.8 < 7.5 <3.3 <6.1
! Co-58 < 2.1 < l.3 <2.4 < l.4 <2.7 < 2.4 Co-60 < l.3 < l.0 <2.4 < 2.4 < 2.2 < 2.5 Zn-65 Zr-95
< 2.9
< 6.6
< 4.0
< 5.7
< 6.2
< 4.9
<3.3
< 4.8
<5.3
< 6.6
<7.7
<6.5 5
W Nb-95 < 2.8 <l.6 <3.0 <3.7 <3.8 <3.6 ( Cs-134 < l.1 <2.7 <l.5 < 3.0 <3.2 <4.3 g Cs-137 Ba-140
< l.4
< 10.1
< 2.3
< 13.0
< 3.4
<13.8
< 2.3
< 21.7
<2.8
< 23.6
<3.1 g
< 25.0 La-140 < 2.1 <3.3 < 2.3 < 3.0 < 5.7 < 5.0 l Ce-144 < 22.5 < 32.6 <13.4 < 27.3 < 39.0 < 36.7 l Date Collected 07-30-97 08-27-97 09-24-97 10-29-97 11-26-97 12-31-97 I
Gross Alpha < 2.6 < 2.6 < l.4 < l.2 < l.9 E l <l.4 5 l Gross Beta < 2.6 3.6
- 1.5 4.9
- 1.0 5.0
- 1.1 6.0
- 1.0 <2.6 l
Be-7 < 27.2 < 38.8 < 56.1 < 16.1 < 30.4 < 39.3 K-40 < 89.7 < 36.8 < 116.0 <57.5 < 77.3 < 64.7 Mn-54 <3.2 <2.3 < 4.2 <3.I <3.6 <5.9 Fe-59 <3.6 <6.3 < 10.1 <3.7 < 3.6 < 7.2 Co-58 <3.3 <3.0 < 6.7 <3.8 <l.4 < 4.4 Co-60 <3.8 <2.9 <2.0 < l.8 <5.3 <3.2 Zn-65 < 4.9 < 2.9 < 10.6 < 10.5 < 7.7 <4.1 l Zr-95 <4.7 < 7.2 < 9.0 < 6.4 <3.0 < 4.0 - Nb-95 < 5.1 <4.2 < 9.2 <2.2 <2.0 <3.9 Cs-134 <3.8 <2.8 < 6.7 <3.3 <5.0 < l.8 Cs-137 <3.5 <3.3 < 6.2 < 2.1 < 6.1 < 3.8 Ba-140 < 30.0 < 40.9 < 42.6 <l6.6 < 28.3 < 16.4 La-140 < 5.8 <4.6 < 8.6 < 2.7 < 4.7 < 6.6 Cc-144 < 33.5 < 33.9 < 53.7 < 17.5 < 44.4 < 39.7 I Il E-14 I
1 TAl3LE E-ID SURFACE WATER OUARTERLY TRIT (UM COMPOSITE (pCill) 1997 CL-9 CL-10' CL-13 CL-90 CL-91 CL-99 Ist Quarter <l53 <l53 <l53 <l53 <l53 <l53 2nd Quaner <!86 <l86 <l84 <!84 <184 <!84 (, 3rd Quaner --- --
<l59 <l66 <l59 <166 4th Quaner -- ---
<l59 <l80 <180 <l59 L
- controllocation TABLE E-Il WELL- WATER OUARTERLY TRITIUM COMPOSITE (pCi/l)
I 1997 CL-7D CL-12 (Untreated) CI,-12 (Treated) ist Quaner <l50 <l50 <l50 I 2nd Quaner <l84 <184 <184 k 3rd Quarter <l59 <!66 <l66 4th Quarter <!80 <160 <l60 TAI 3LE E-12 DRINKING WATER OUARTERLY TRITIUM COMPOSITE (pCi/l) I 1997 lst Quarter <l53 2nd Quaner <l65 3rd Quarter <l59 4th Quaner <l80 E-15
I TABLE E-13 WELL WATER SEMIMONTHLY IODINE ACTIVITY (pCill) Date CL-7D CL-12 Untreated Cl 12 Treated I/8/97 < 0.4 < 0.4 < 0.4 1/22/97 < 0.3 <0.3 < 0.4 2/5/97 < 0.3 <0.3 <0.3 2/19/97 < 0.4 < 0.4 < 0.4 3/5/97 < 0.4 < 0.4 < 0.4 3/19/97 < 0.4 < 0.3 < 0.4 I 4/2/97 < 0.4 < 0.3 <0.3 4/16/97 < 0.4 < 0.4 < 0.3 4/30/97 < 0.5 < 0.5 < 0.5 5/14/97 < 0.5 < 0.4 < 0.4 ( 5/28/97 < 0.3 < 0.3 < 0.3 6/11/97 < 0.4 < 0.4 < 0.4 l 6/25/97 < 0.3 < 0.3 <0.3 7/9/97 < 0.3 7/23/97
< 0.3 < 0.3 g
< 0.3 < 0.3 < 0.3
- 8/6/97 <0.2 -
< 0.2 < 0.2 8/20/97 < 0.3 < 0.3 <0.3 9/3/97 < 0.3 < 0.3 < 0.3 9/17/97 < 0.3 < 0.3 < 0.3 10/1/97 <0.3 < 0.3 < 0.3 10/15/97 < 0.3 <0.3 < 0.3 10/29/97 < 0.3 < 0.3 <0.3 11/12/97 < 0.3 < 0.3 11/26/97
< 0.3 g
< 0.3 < 0.4 < 0.4 W 12/10/97 < 0.3 < 0.4 < 0.4 12/23/97 < 0.4 < 0.4 < 0.4 I
I E-16 I
TABLE E-14 WELL WATER MONTilLY COMPOSITE ACTIVITY CL-7D (nCi/h Collection Period January February March April May June Gross Alpha < l.1 1.6
- 0.9 < l.2 < l.1 < l.8 <3.7 Gross Beta < l.3 2.4
- 0.9 < l.3 1.3
- 0.8 <2.2 <3.8 Be-7 < 26.7 < 33.2 < 22.8 < 20.8 < 13 5 <53.0 K-40 < 33.9 < 39.6 < 32.6 < 25.3 < 25.8 < 120.0 Mn-54 < 2.5 < 2.7 < 2.2 < 0.8 < l.1 <2.3 Fe-59 < 6.0 < 7.0 < 4.7 < 3.1 <3.0 < 6.4 Co-58 < l.5 < 2.6 < l.7 < l.6 < 0.8 < l.4 Co-60 < 2.8 < 2.8 < 2.4 < l.9 <l.3 < l.7 Zn-65 <3.5 < 4.9 <3.2 < 3.1 <3.7 < 5.7 Zr-95 < 2.8 < 6.4 < 5.0 <2.0 <2.3 <l3.4 Nb-95 <3.2 <5.0 < l.4 < 2.0 < l.2 < 6.4 Cs-134 <3.2 <2.6 < l.9 < 2.1 < l.1 <4.5 Cs-137 <2.2 < 2.9 < l.8 < l.7 < l.5 < 5.3 Ba-140 < 13.7 < 40.6 < 9.6 < l 3.2 < 6.6 < 40.1 La-140 < 2.5 < 6.4 < 3.6 < l.6 < l.7 < 4.9 Ce-144 < 20.8 < 15.3 < 27.5 < 28.5 < 23.8 < 37.2 Collection Period u J_uly Aucust September October November December Gross AIpha <2.0 1.4
- 0.9 2.I
- 0.9 3.4 + 1.0 < 0.9 1.2 0.8 Gross Beta < l.8 < l.4 < l.3 5.0 A 1.0 <l.3 < l.2 Be-7 < 23.9 < 30.7 < 31.6 < 16.7 < 28.8 < 68.7 K-40 < 69.4 < 87.1 < 60.7 < 27.6 < 32.4 < 81.3 Mn-54 < 3.0 <3.9 <2.3 < l.5 < l.3 <3.8 Fe-59 < 7.8 <8.0 < 8.0 <1.9 < 6.3 < 13.1 Co-58 < 3.9 < 2.7 <2.0 <2.1 <2.I < 4.6 Co-60 <2.7 < 3.0 < l.7 < 2.1 < 2.4 < 4.4 Zn-65 <3.9 <3.5 < 3.3 < 6.7 < 3.8 <4.3 Zr-95 < 8.1 < 10.4 < 6.6 < 4.4 < 7.6 < 10.5 Nb-95 < 4.7 < 6.8 < 5.2 < l.8 < 2.3 < 4.3 Cs-134 <3.4 < 6.3 <3.5 < l.8 <2.2 < 4.4 Cs-137 < l.9 <5.0 <3.3 < l .5 <2.0 < 7.0 Ba-140 < 27.6 <57.4 < 42.5 < 14.0 < 26.0 < 51.6 La-140 <5.1 < 13.5 < 4.9 <5.3 < 8.0 < 8.4 Cc-144 < 25. I < 46.2 < 65.8 < 13.1 < 17.9 < 42.9 E-17
I TABLE E-15 WELL WATER MONTHLY COMPOSITE ACTIVITY CL-12 UNTREATED (pCi/D Collection Period January Febniary March April May June Gross Alpha <2.3 <2.0 <2.6 <2.3 < 2.9 < 2.6 Gross Beta <2.4 3.3 A 1.4 <2.6 <2.6 <2.5 <2.4 Be-7 <13.6 < 33.4 < 25.6 < 26.9 < 22.9 < 26.3 K-40 < 26.5 < 36.0 < 39.9 <59.6 < 33.9 < 104.0 g' Mn-54 < l.7 <2.6 < l.4 <2.4 <2.3 <3.2 3 Fe-59 < 2.9 <6.8 <6.6 < 6.2 <5.2 <3.4 Co-58 , <l.5 <3.2 < l.9 <2.3 < l.4 <3.6 g Co-60 <l.7 < 2.9 <2.7 <2.9 <2.0 <l.5 g Zn-65 < l.4 <5.5 <3.7 <4.0 < 4.7 < 8.7 Zr-95 <3.6 <5.0 < 5.4 < 6.4 < 3.2 < 8.9 g Nb-95 < l.4
< l.7
<4.1
< 2.4
<3.3
<l.8
<3.9
< l.9
<l.4
<2.3
<4.1
< 2.0 g
Cs-134 Cs-137 <l.8 <3.2 <3.0 <2.1 < 2.4 < 4.1 Ba-140 <l1.9 < 44.7 <l6.0 < 31.6 <14.7 < 30.7 La-140 < 2.7 < 8.8 <9.3 <5.8 < 6.2 <3.4
- Ce-144 < 27.2 < 20.6 <18.0 < 26.8 < 31.5 < 23.1 I
Collection Period 1,uly Aueust September October November Decem.,bg Gross Alpha 3.5
- 2.2 <2.5 <3.0 <2.1 <2.0 <l.8 Gross Beta 4.7
- 1.7 3.3
- 1.7 2.8
- 1.8 <2.5 <2.4 2.8 1.6 Be-7 < 40.9 < 41.8 < 42.1 < 30.1 < 34.6 < 23.3 K-40 < 85.3 < 96.6 < 43.3 <$0.0 < 57.1 < 94.9 Mn-54 <2.7 <2.7 <l.5 <l.3 < 2.6 <2.2 Fe-59 <5.1 <9.8 <4.0 < 6.8 <3.6 <4.1 Co-58 <3.4 <3.7 <2.5 <3.3 <2.2 <4.2 Co-60 < 2.5 <2.4 <3.3 < 2.4 <2.4 <l.9 Zn-65 <4.8 <3.5 < 5.5 <5.8 < 5.2 < 9.7 Zr-95 < 8.2 < 7.9 < 8.8 < 7.3 < 9.3 <5.9 Nb-95 <3.7 <4.7 <3.9 <2.2 <5.7 <2.3 Cs-134 <2.8 <3.6 <3.5 < l.7 < l.3 <3.2 l
m Cs-137 <2.0 <l.8 <3.1 <3.0 < 2.3 <3.9 Ba-140 <54.7 < 54.1 < 54.1 < 21.1 < 24.9 < 14.3
< 12.0 gi La-140 < 7.5 <6.0 <6.1 < 8.2 < 2.8 g Ce-144 < 31.9 < 29.9 < 57.3 < 4 5.0 < 23.3 < 26.5 I
E-18 8
TABLE E-16 WELL WATER MONTHLY COMPOSITE ACTIVITY CL-12 TREATED (nCi/l) Collection Period January February March April May June Gross AIpha <3.3 <l.7 <2.4 <3.0 < 2.9 <3.2 , Gross Seta 2.8
- 1.8 5.3
- 1.5 3.1
- l.8 3.1 1.9 2 A
- 1.7 < 2.6 Be-7 < 22.0 < 29.0 < 17.2 < 29.9 < 22.7 < 35.1 K-40 < 23.2 < 37.3 < 36.0 < 31.3 < 42.1 < 75.1 Mn-54 < l.3 < l.9 <2.5 <2.2 < 3.3 < 3.1 Fe-59 < 4.8 <4.9 < 6.6 <2.8 < 7.0 < 8.2 Co-58 <l.7 <3.0 <3.5 < l.5 < l.8 <3.1 Co-60 < 2.0 <2.1 <2.6 < l.I <3.3 <3.3 Zn-65 < 2.6 <4.6 <4.1 <4.0 < 6.1 < 6.6 Zr-95 <3.7 < 7.4 <6.4 < 3.1 < 6.0 < 9.0 l Nb-95 <l.9 <4.1 <3.4 <3.6 <2.7 < 4.5 Cs-134 < 2.4 <2.1 <3.3 < l.8 <3.8 <4.3 Cs-137 <2.5 <2.5 <3.3 < 2.7 <3.5 < 4.1 Ba-140 < 14.3 < 27.9 <l1.7 < 15.1 < 13.7 < 29.9 La-140 < 2.2 <5.0 <9.8 <6.5 <5.9 <3.7 Ce-144 < 27.9 < 37.0 < 43.5 < 13.0 < 28.2 < 28.9 Collection Period Lu]y Auzust Seritember October November December Gross Alpha <3.5 <3.1 <l.9 <2.1 <2.4 < 2.2 Gross Beta 4.2
- 1.8 3.2 i 1.8 <2.4 <2.5 2.9 1.7 <2.2 Be-7 < 30.2 <51.0 < 4 8.7 < 31.0 < 51.4 < 62.1 K 40 <51.1 < 39.5 < 86.9 < 48.8 < 59.1 < 97.0 Mn-54 <l.3 <2.2 <l.6 < l.3 < 3.9 < 5.2 Fe-59 <3.7 < 8.6 <4.0 <3.7 <5.7 < 9.5 Co-58 <2.5 <3.3 <2.9 <2.8 < 3.7 <3.0 Co-60 <2.4 < 2.7 <2.6 <2.6 <3.2 <3.3 Zn-65 <29 <4.8 <5.4 < 4.1 < 6.4 < 7.4 Zr-95 < 7.1 < 9.6 < 10.6 <4.0 < 8.9 < 14.2 Nb-95 < 2.9 <3.4 <6.6 <3.5 <6.9 < 5.1 Cs-134 <1.4 <3.8 <3.0 <2.9 <2.7 < 5.3 Cs-137 <2.6 < l.7 < 2.6 <2.5 <4.0 <4.6 Ba-140 < 22.4 < 37.0 < 38.6 < 16.4 < 21.5 < 34.1 La-140 <11.5 < 8.6 < 14.2 < 7.9 < 9.9 < 5.2 Ce-144 < 244 < 32.1 < 21.6 < 14.2 < 23.7 < 31.4 E-19
I TABLE E-17 DRINKING WATER ACTIVITY - CL-14 (oCi/l) Date Collected 01-29-97 02-26-97 03-26-97 04-30-97 05-28-97 06-25-97 Gross Alpha <0.6 < 0.4 1.1 0.5 < 0.7 < l.0 <l.8 Gross Beta 2.4
- 0.4 2.9
- 0.3 2.9 i 0.4 2.2
- 0.4 1.6 0.6 2.1 0.6 Be-7 < 17.9 < 21.9 < 20.6 < 17.4 < 17.6 < 30.5 K-40 < 26.6 < 35.4 < 37.9 < 34.8 < 42.3 < 63.8 Mn-54 < 2.0 <2.5 <2.2 <l.I <l.6 <2.6 Fe-59 < 3.8 < 3.2 <2.4 <5.0 < 6.8 < 6.1 l
e Co-58 < l.8 <3.2 < 2.6 < l.0 <3.2 <l.8 Co-60 Zn-65
< l.8
< 2.9
< l.9
<3.7
<3.2
<3.7
< l.4
<3.8
<2.7 <l.2 g Zr-95
<2.5 <3.2 g
< 4.0 <6.3 <2.8 < 4.6 < 7.1 < 7.0 Nb-95 < 2.1 < 2.9 <3.5 <2.6 <3.4 <l.9 Cs-134 <l.0 < 2.2 <3.1 < l.5 <l.8 <2.7 Cs-137 <2.2 < l.7 < 2.8 < 2.3 <l.9 <3.3 ""
Ba-140 < 11.9 < 23.5 < 15.5 < 14.5 < 19.0 <11.3 La-140 < l.7 <3.5 < l.5 < 4.8 < 6.8 <2.2 Ce-144 < 30.1 < 25.1 < 22.0 < 29.0 < 13.8 < 31.0 Date Collected 07 30-97 08-27-97 09-24-97 10-29-97 11-26-97 12-3l-97 Gross Alpha < l.0 < l.3 < 0.6 1.0
- 0.5 0.6
- 0.4 < 0.4 Gross Beta 2.4 0.5 2.3 0.6 2.0
- 0.4 4.4
- 0.5 2.6 0.4 1.8
- 0.3 Be-7 K-40
< 25.8
< 107.0
< 43.6
< 71.0
< 29.1
< 49.6
< 21.3
< 28.4
< 46.2
< 107.0
< 27.0
< 110.0 I
Mn-54 < 4.9 < l.4 < l.3 < l.6 < 4.0 <5.0 Fe-59 < 12.1 <5.2 <5.5 <2.2 < 4.7 < 7.2 l
=
Co-58 < 6.0 <2.0 <2.6 < l.9 < 3.5 <4.5 Co-60 <5.8
<6.3
<3.4 <2.5 < l.5 < l.9 <5.5 g Zn-65 < 9.2 < 4.9 < 6.3 < 7.5 <5.3 m Zr-95 < 9.0 < l5.5 <3.2 <2.1 < 10.0 < 6.9 Nb-95 < 8.6 <3.9 <3.5 <2.0 < l.5 < 6.9 Cs 134 <3.1 <2.6 <2.4 < 2.0 E
< 4.6 <6.1 g Cs-137 < 7.0 <4.3 < 2.8 <l.1 < 3.0 <5.4 Ba-140 < 22.1 < 51.2 < 23.0 < 14.3 < 22.3 < 25.9 La-140 <5.0 < 7.9 < 7.0 < 4.8 < 8.8 <4.2 -
Cc-144 < 47.0 < 44.6 < 20.4 < 30.8 < 35.3 < 34.1 I' l I E-20 I
TABLE E-18 MILK ACTIVITY-CL-116(control)(pCi/l) Date Collected 01-29-97 02-26-97 03-26-97 04-30-97 05-!4-97 I-131 < 0.4 < 0.4 < 0.4 < 0.4 < 0.4 Sr-90 1.3 1 0.4 1.I
- 0.4 1.2 i 0.3 1.1 0.2 1.9 i 0.4 Be-7 < 25.5 < 30.0 < 26.4 < 21.1 < l 5.5 K-40 1400* 80 1440 80 1370
- 80 1490
- 80 1440* 50 Mn-54 <2.3 <3.8 < l.3 <3.5 < l.9 Fe-59 < 6.1 <6.5 < 4.8 <3.8 <3.3 Co-58 < 3.1 < l.9 < 2.5 <2.8 < l.4 Co-60 < 4.1 <2.5 < 4.3 <3.4 < 2.4 Zn-65 < 7.7 <5.4 < 6.6 < 4.7 <3.8 Zr-95 <6.5 < 6.1 < 4.9 < 6.6 < 4.7 i Nb-95 Cs-134 Cs-137
<2.6
< l.9
<2.7
<3.2
< l.8
<3.7
<3.0
< 2.8
<3.2
<3.3
<3.3
<3.5
< 2.3
< 2.4
< 2.1
< 11.3 < 10.2 < 13.2 <11.8 <5.8 I Ba-140 La-140 <2.5
< 22.3
<2.8
< 24.2
< l.4
< 19.4
<2.6 s 13.5
< l.8
< 17.1 Ce-144 i Date Collected 05-28-97 06-11-97 06-25-97 07-09-97 07-23-97 I 131 <0.3 < 0.4 < 0.4 < 0.4 < 0.5 I Sr-90 0.6
- 0.3 1.3 i 0.3 2.0
- 0.5 1.1
- 0.4 2.8
- 0.5 Be-7 < 21.3 < 30.1 <53.8 < 47.9 < 29.8 i K-40 Mn-54 1440
- 80
< 3.2
< 6.5 1210 110
< 2.6
< 4.4 1320
- 170
<5.6 1310
- 160 1360
- 110
< 7.0 < 3.8 Fe-59 < 17.4 < 7.3 < 4.5 i Co-58 Co-60 Zn-65
< 2.4
<4.1
< 3.8
< l.8
<3.0
< 6.2
< 6.4
< 11.2
< 12.0
<30
< 6.7
< 14.3
< 2.9
< 5.1
< 8.8 ly Zr-95 Nb-95
<4.9
<3.0
< 4.4
<2.2
< 12.3
< 7.9
< 16.1
<5.7
< 7.7
< 3.0 Cs-134 < 3.5 < 4.7 < 7.1 < 7.6 < 4.1 g Cs-137 < 2.7 <4.4 < 6.9 < 8.1 < 3.4 3 Ba-140 < 6.6 < 13.9 < 24.5 < 13.1 <11.7 La-140 < 2.4 < l.4 < 4.6 < 7.4 < l.8 Cc-144 < 21.8 < 20.8 < 59.1 < 58.7 < 22.0 i
1 1 E-21
I l TABLE E-18 (Cont'd.) I Date Collected 08-06-97 08-20-97 09-03-97 09-17-97 10-01-97 I-131 < 0.3 < 0.4 < 0.4 < 0.3 < 0.4 Sr-90 0.9
- 0.4 1.1 0.4 1.2
- 0.5 0.8
- 0.4 1.5
- 0.4 Be-7 < 49.4 < 55.2 < 40.6 < 43.3 < 29.7 K-40 1270 160 1260
- 170 1250
- 120 1130
- 140 1410
- 110 gl Mn-54 <3.1 < 5.1 <4.5 <5.8 <3.5 g' Fe-59 < 12.8 < 8.8 <4.7 < 12.4 <7.4 Co-58 <3.2
<3.8
< 7.5 <4.8 <3.0 < 2.9 g Co-60 < 8.8 <5.9 < 9.1 <3.6 3 Zn-65 < 8.1 < 6.3 < 9.3 < 12.4 < 7.1 Zr 95 < 7.5 < 8.2 < 7.9 < 12.3 < 7.7 Nb-95 <5.6 < 7.3 <3.7 <5.2 <3.6 Cs-134 <3.3 < 5.5 <4.3 <6.1 <3.4 Cs-137 < 6.3 < 8.3 < 5.4 < 6.3 <5.0 Ba-140 < 28.6 < 33.1 < 18.0 < 20.5 <13.5 La-140 < 4.9 < 2.9 <2.9 < 2.4 <2.3 Cc-144 < 35.7 < 62.3 < 25.7 <522 < 37.2 Date Collected 10-15 07 10-29-97 11-26-97 12-31-97 I
1 131 < 0.4 1.3
- 0.4
<0.3 < 0.4 < 0.3 g Sr-90 1.2
- 0.4 1.9
- 0.4 0.6
- 0.4 g Be-7 < 19.7 < 29.6 < 34.9 < l6.0 K-40 1320* 90 1320* 120 1600* 160 1360
- 90 Mn-54 < l.9 < 3.2 < 4.8 < l.3 Fe-59 <5.4 <3.9 < ! 0.5 < 7.1 Co-58 <2.4 < 3.6 <2.9 <3.2 Co-60 <3.3 < 4.8 < 9.1 <3.4 Zn-65 < 10. I < 9.8 < 18.0 < 6.2 Zr-95 < 7.6 < 5.7 < 16.2 < 6.3 bb95 < 2.3 < 2.0 < 6.8 < 2.4 Cs-134 <2.8 <5.6 < 7.5 < 3.5 Cs-137 < 5.1 < 4.9 <3.1 < 3.9 Ba-140 < 10.3 < 17.6 < 28.4 < 16.6 l
5 La-140 <3.0 < 2.1 < 4.4 <l.2 Ce-144 < 21.5 < 39.9 < 44.7 <57.1 I I E-22 I
TABLE E-19 GRASS ACTIVITY - CL-1 (nCi/n wen Date Collected 01-29-97 02-26-97 03-26-97 05-01-97* 05-14-97 Be-7 1.073
- 0.10 1.28
- 0.10 i K-40 Mn-54 Fe-59 6.56
- 0.24
< 0.007
< 0.018 5.02*0.I8
< 0.009
<0.010 Co-58 < 0.005 < 0.006 Co-60 < 0.009 < 0.013 Zn-65 <0.018 < 0.023 Zr-95 < 0.011 < 0.019 Nb-95 < 0.008 < 0.008 I-131 < 0.012 <0.010 Cs-134 < 0.008 < 0.006 Cs-137 < 0.008 <0.011 Ba-140 < 0.025 < 0.021 La-140 < 0.006 < 0.006 Cc-144 < 0.048 <0.039 Date Collected 05-28-97 06-11-97 06-25-97 07-09-97 07-23-97 Be-7 0.82* 0.085 0.95
- 0.26 0.73
- 0.25 1.85 0.30 1.75
- 0.22 K-40 5.81
- 0.22 5.60
- 0.58 7.93
- 0.79 5.38
- 0.70 5.67
- 0.45 i
g Mn-54 < 0.006 < 0.020 < 0.028 < 0.027 < 0.013 Fe-59 < 0.011 < 0.046 <0.050 < 0.035 < 0.032 Co-58 < 0.004 < 0.024 < 0.026 < 0.026 < 0.007 Co-60 < 0.013 < 0.019 < 0.038 < 0.031 < 0.016
' Zn-65 < 0.016 < 0.050 < 0.062 < 0.074 <0.024 Zr-95 < 0.017 < 0.043 < 0.064 < 0.038 <0.021 Nb-95 < 0.009 < 0.015 < 0.021 < 0.021 < 0.017 1-131 < 0.009 < 0.029 <0.036 <0.036 <0.026 Cs-134 < 0.008 < 0.022 < 0.021 < 0.020 < 0.016 i Cs-137 Ba-140
<0.009
< 0.033
< 0.003
< 0.019
< 0.105
< 0.026
<0.103
< 0.027
<0.211
< 0.014
< 0.059 La-140 < 0.0 t I < 0.013 < 0.012 < 0.014 Cc-144 < 0.047 < 0.097 <0.100 < 0.158 < 0.100
- Sample was collected for the month of April l
l 1 E-23
I-TABLE E-19 (Cont'd) Date Collected 08-06-97 08-20-97 09-03-97 09-17-97 10-01-97 Be-7 0.97 0.21 1.89
- 0.23 1.11 0.21 2.52
- 0.29 1.72
- 0.19 K-40 7.20
- 0.48 4.37
- 0.41 6.45
- 0.63 3.79
- 0.46 6.32 i 0.42 g Mn-54 < 0.009 < 0.016 < 0.009 < 0.020 < 0.014 5 Fe-59 < 0.033 < 0.032 < 0.037 < 0.043 < 0.026 Co-58 < 0.017 < 0.008 < 0.013 < 0.014 < 0.008 g Co-60 < 0.025 < 0.022 < 0.026 < 0.012 < 0.026 5 Zn-65 < 0.031 < 0.017 < 0.021 < 0.029 < 0.017 Zr-95 < 0.018 <0.026 < 0.020 < 0.023 < 0.016 g Nb-95 < 0.007 < 0.009 < 0.019 < 0.019 < 0.016 g I-131 < 0.024 < 0.026 < 0.027 < 0.024 < 0.015 Cs-134 < 0.009 < 0.016 < 0.019 <0.017 < 0.013 Cs-137 <0.010 <0.012 < 0.010 < 0.018 <0.015 Ba-140 < 0.060 < 0.079 < 0.071 < 0.071 < 0.053 La-140 < 0.019 < 0.012 < 0.009 < 0.009 < 0.006 Ce-144 < 0.077 < 0.068 <0.125 < 0.127 < 0.109 Date Collected 10-15-97 10-29-97
- 1.
- 0.23 1.96
- 0.30 Be-7 K-40 4.46
- 0.42 5.33
- 0.60 Mn-54 < 0.017 < 0.021 Fe-59 < 0.021 < 0.023 Co-58 < 0.014 < 0.017 g Co-60 < 0.009 < 0.030 W Zn-65 < 0.028 < 0.026 Zr-95 Nb-95
< 0.026 < 0.039 g
< 0.009 < 0.023 g 1-131 < 0.026 < 0.029 Cs-134 < 0.011 < 0.024 Cs-137 < 0.019 < 0.022 Ba-140 < 0.092 < 0.104 La-140 < 0.008 < 0.018 Ce-144 < 0.147 < 0.127 I
I E E-24 I
TABLE E-20 GR ASS ACTIVITY - CL-2 (nCi/e wet) Date Collected 01-29-97 02-26-97 03-26-97 05-01-97* 05-14-97 Be-7 1.75 0.095 5.35
- 0.I8 I K-40 Mn-54 Fe-59 6.72 0.20
< 0.006
< 0.013 5.16 0.25
< 0.011
< 0.021 g Co-58 < 0.004 < 0.011 g Co-60 < 0.006 < 0.013 I Zn-65 <0.008 < 0.033 ,
Zr-95 < 0.015 < 0.027 I Nb-95 1-131
< 0.004
< 0.010
< 0.012
< 0.012 Cs-134 < 0.007 < 0.013 Cs-137 < 0.007 < 0.010 Ba-140 < 0.028 < 0.044 La-140 < 0.005 < 0.007 Cc-144 < 0.033 < 0.051 Date Collected 05-28-97 06-11-97 06-25-97 07-09-97 07-23-97 Be-7 1.52 0.093 1.28
- 0.23 0.78 0. I 8 1.61
- 0.26 1.34
- 0.28 K-40 4.73
- 0.I7 4.57
- 0.50 4.98
- 0.36 5.94 0.55 5.61 0.57 I Mn-54 Fe-59
< 0.006
< 0.012
< 0.019
< 0.050
< 0.012
< 0.023
< 0.009
< 0.021
< 0.024
<0.0$0 Co-58 < 0.005 < 0.012 < 0.014 < 0.010 < 0.026 I Co-60 Zn-65
< 0.008
< 0.021
< 0.022
< 0.027
< 0.007
< 0.018
< 0.020
< 0.029
< 0.029
< 0.045 Zr-95 < 0.012 < 0.051 < 0.014 < 0.051 <0.029 Nb-95 < 0.004 < 0.014 < 0.013 < 0.009 < 0.025 l-131 < 0.008 < 0.020 < 0.019 < 0.018 < 0.040
, Cs-134 <0.008 < 0.009 < 0.014 <0.022 < 0.022 I Cs-137 Ba-140
< 0.007
< 0.025
< 0.022
< 0.080
< 0.009
< 0.057
< 0.023
<0.102
< 0.023
< 0.052 La-140 < 0.005 < 0.009 < 0.010 < 0.009 < 0.011 Ce-144 < 0.045 < 0.076 < 0.105 < 0.129 < 0.168
- Sample was collected for the month of April E-25
I \ TABLE E-20 (Cont'd) I l Date Collected 08-06-97 08-20-97 09-03-97 09-17-97 10-01-97 Be-7 1.35
- 0.I9 3.70 i 0.29 1.26
- 0.32 1.076
- 0.20 2.92
- 0.42 K-40 5.80
- 0.42 3.76
- 0.35 5.09
- 0.60 5.34*0.46 6.73
- 0.78 Mn-54 < 0.021 < 0.013 < 0.017 < 0.012 < 0.03 i Fe-59 < 0.022 < 0.029 < 0.040 < 0.030 < 0.062 Co-58 < 0.015 < 0.013 < 0.022 < 0.015 < 0.033 l
l Co-60 < 0.015 < 0.017 < 0.021 <0.020 < 0.021 5 l Zn-65 < 0.043 < 0.053 <0.035
< 0.065 <0.036 l
Zr-95 < 0.037 < 0.033 <0.025 <0.034 < 0.024 g Nb-95 < 0.017 < 0.019 < 0.022 < 0.015 < 0.016 5 1-131 < 0.018 < 0.031 <0.020 < 0.023 < 0.043 Cs-134 < 0.008 <0.014 < 0.022 < 0.017 < 0.026 Cs-137 < 0.014 < 0.014 < 0.018 < 0.017 < 0.033 Ba-140 < 0.035 < 0.038 <0.111 < 0.081 < 0.137 La-140 < 0.010 < 0.016 < 0.011 < 0.015 <0.046 Ce-144 < 0.112 < 0.067 <0.162 <0.150 <0.110 Date Collected 10-15-97 10-29-97 Be-7 3.22 i 0.32 5.48 0.35 K-40 6.84
- 0.54 5.77
- 0.47 Mn-54 < 0.010 < 0.009 I Fe-59 < 0.019 <0.032 Co-58 < 0.016 < 0.020
- Co-60 < 0.018 < 0.026 Zn-65 < 0.024 < 0.10I Zr-95 < 0.017 < 0.025 Nb-95 < 0.020 < 0.032 j 1-131 < 0.026 < 0.024
- Cs-134 < 0.010 <0.019 Cs-137 < 0.018 < 0.019 Ba-140 < 0.043 < 0.076 l
=
l La-140 < 0.010 <0.016 I Ce-144 < 0.175 < 0.112 5 8 I E-26 I
TABLE E-21 GRASS ACTIVITY - CL-8 (oCi/c wet) Date Collected 01-29-97 02-26-E 03-26-97 05-01-97* 05-14-97 Be-7 0.60 = 0.083 0.64
- 0.087 K-40 6.99 = 0.27 6.38
- 0.26 Mn-54 < 0.006 < 0.012 Fe-59 < 0.024 < 0.022 Co-58 < 0.007 < 0.011 Co-60 < 0.007 < 0.013 Zn-65 < 0.034 <0.019 Zr-95 <0.010 < 0.022 I Nb-95 1 131
< 0.011
<0.013
<0.010
< 0.013 Cs-134 < 0.010 < 0.010 Cs-137 < 0.006 < 0.006 Ba-140 < 0.036 < 0.042 La-140 < 0.007 < 0.008 Ce-144 < 0.062 < 0.067 Date Collected 05-28-97 06-11-97 06-25-97 07-09-97 07-23-97 Be-7 0.99
- 0.13 1.57
- 0.27 2.29
- 0.27 1.47 0.24 1.13 i 0.20 K-40 5.49
- 0.26 6.31
- 0.65 7.95
- 0.61 8.65 0.60 6.63
- 0.48 i Mn-54 Fe-59
< 0.011
< 0.012
< 0.022
< 0.052
< 0.018
< 0.052
< 0.017
< 0.033
< 0.013
< 0.030 Co-58 < 0.011 < 0.020 < 0.014 < 0.016 < 0.015 Co-60 < 0.014 < 0.032 < 0.025 < 0.020 < 0.022 Zn-65 < 0.021 < 0.055 < 0.034 < 0.030 <0.025 Zr-95 < 0.024 < 0.029 < 0.030 < 0.020 < 0.021 lN Nb-95 < 0.009 < 0.019 < 0.012 < 0.010 < 0.016 1-131 < 0.007 < 0.023 < 0.030 < 0.023 < 0.031 Cs-134 < 0.011 < 0.028 < 0.023 < 0.012 < 0.012 l Cs-137 < 0.012 < 0.019 < 0.017 < 0.018 < 0.016 B Ba-140 < 0.020 < 0.057 < 0.078 < 0.070 < 0.061 La-140 < 0.006 < 0.012 < 0.007 < 0.007 < 0.015 Ce-144 < 0.060 < 0.169 < 0.097 < 0.129 < 0.083
- Sample was collected for the month of April E-27
l Il TABLE E-21 (Cont'd) Date Collected 08-06-97 08 20-97 09-03-97 09-17-97 10-01-97 Be-7 0.83 i 0.27 0.77
- 0.24 0.50 i 0.24 1.61
- 0.I6 1.49
- 0.23 K-40 6.97
- 0.76 5.89
- 0.62 6.86
- 0.69 4.77
- 0.34 9.92 i 0.66 Mn-54 < 0.016 < 0.020 < 0.014 < 0.013 < 0.016 Fe-59 < 0.048 < 0.039 < 0.037 < 0.028 < 0.040 Co-58 Co-60
< 0.013
< 0.028
< 0.010 < 0.022 < 0.009 < 0.017 g
< 0.013 < 0.033 < 0.016 < 0.015 im Zn-65 < 0.043 < 0.028 < 0.026 < 0.022 < 0.031 Zr-95 Nb-95
< 0.052 < 0.044 < 0.057 < 0.015 < 0.040 g
< 0.032 <0.014 < 0.026 < 0.013 < 0.023 5 I-131 <0.036 < 0.029 < 0.032 < 0.010 < 0.031 Cs-134 < 0.021 < 0.011 < 0.027 < 0.013 < 0.012 g Cs-137 < 0.016 < 0.020 < 0.020 <0.016 < 0.024 g Ba-140 < 0.092 < 0.046 <0.112 < 0.049 < 0.079 La-140 < 0.012 < 0.010 < 0.033 < 0.006 < 0.013 Ce-144 <0.143 <0.117 < 0.118 < 0.117 <0.166 Date Collected 10-15-97 10-29-97 Be-7 1.75
- 0.37 1.80 0.25 K-40 Mn-54 9.27
- 0.83
< 0.023 9.19
- 0.59
< 0.012 g
g Fe-59 < 0.055 < 0.028 Co-58 Co-60
< 0.014
< 0.022
< 0.012
< 0.020 g
g Zn-65 < 0.047 < 0.030 Zr-95 <0.044 < 0.020 Nb-95 < 0.022 < 0.014 i I-131 < 0.045 < 0.020 Cs-134 < 0.030 < 0.018 Cs-137 < 0.016 < 0.018 Ba-140 < 0.072 < 0.070 La-140 < 0.015 < 0.007 l Cc-144 < 0.149 < 0.121 I I I E-28 I I
l TABLE E-22 GRASS ACTIVITY - CL-116 (nCi/e wet) Date Collected 01-29-97 02-26-97 03-26-97 05-01-97* 05-14-97 Be-7 1.71 0.13 2.14 i 0.084 K-40 5.96
- 0.29 6.30
- 0.16 Mn-54 < 0.012 < 0.005 Fe-59 < 0.013 < 0.012 Co-58 < 0.006 < 0.006 Co-60 < 0.012 < 0.007 Zn-65 < 0.027 < 0.020 Zr-95 <0.021 < 0.018 Nb-95 <0.005 < 0.005 1-131 < 0.014 <0.004 Cs-134 < 0.013 < 0.008 i Cs-137 Ba-140
<0.011
< 0.042
< 0.006
< 0.02i La-140 <0.013 < 0.003 Ce-144 < 0.063 <0.085 Date Collected 05-28-97 06-11-97 06-25-97 07-09-07 07-23-97 Be-7 1.021
- 0,10 1.72
- 0.27 1.79 0.30 1.14
- 0.25 2.92
- 0.28 g K-40 5.87
- 0.24 4.97
- 0.46 11.65
- 0.78 5.78
- 0.65 7.49
- 0.50 l Mn-54 Fe-59
< 0.005
< 0.018
< 0.010
< 0.036
< 0.021
< 0.064
< 0.010
< 0.019
< 0.019
< 0.053 Co-58 < 0.005 < 0.009 < 0.027 < 0.022 < 0.020 Co-60 < 0.011 < 0.017 < 0.026 <0.031 < 0.019 Zn-65 < 0.022 < 0.033 < 0.036 < 0.052 < 0.046 Zr-95 < 0.018 < 0.040 <0.039 <0.045 < 0.029 lr Nb-95 < 0.009
< 0.007
< 0.018
< 0.016
< 0.030
< 0.038
< 0.024
< 0.020
< 0.015
< 0.03 I 1-131 Cs-134 <0.008 < 0.023 < 0.029 < 0.020 < 0.020 Cs-137 < 0.007 < 0.009 < 0.022 < 0.019 < 0.020 l
i Ba-140 < 0.024 < 0.072 < 0.058 < 0.067 < 0.080 La-140 < 0.007 < 0.011 < 0.009 < 0.011 < 0.011 Ce-144 < 0.058 < 0.118 < 0.115 < 0.149 < 0.124
- Sample was collected for the month of April E-29
l TABLE E-22 (Cont'd) I Date Collected 08-06-97 08-20-97 09-03-97 09-17-97 10-01-97 Be-7 1.78
- 0.24 2.060
- 0.23 0.77
- 0.I9 0.91
- 0.27 0.68 i l 0.26 K-40 6.96
- 0.56 4.41
- 0.45 6.87
- 0.47 4.84
- 0.62 7.19
- 0.79 Mn-54 Fe-59
< 0.018
< 0.022
< 0.014
< 0.034
< 0.016 < 0.031 < 0.031 g
< 0.016 < 0.042 < 0.038 3 Co-58 < 0.018 < 0.013 < 0.013 < 0.019 < 0.023 Co-60 Zn-65
< 0.026
< 0.044
< 0.015
< 0.024
< 0.017
< 0.022
< 0.016 < 0.039 g
< 0.066 < 0.054 g Zr-95 < 0.045 < 0.020 < 0.029 < 0.052 < 0.049 Nb-95 < 0.009 < 0.017 < 0.011 < 0.020 < 0.033 1-131 < 0.019 <0.019 < 0.030 < 0.033 < 0.021 Cs 134 < 0.020 < 0.019 < 0.014 < 0.022 < 0.031
! Cs-137 < 0.021 < 0.015 < 0.017 < 0.024 < 0.018 Ba-140 < 0.100 < 0.043 < 0.071 < 0.058 < 0.088 La-140 < 0.010 < 0.017 < 0.005 < 0.012 < 0.011 l Ce-144 < 0.082 < 0.159 < 0.120 < 0.176 < 0.206 I Date Collected 10-15-97 10-29-97 Be-7 1.I5
- 0.31 1.96
- 0.30 l K-40 6.00
- 0.66 4.41
- 0.52 Mn-54 < 0.011 < 0.012 Fe-59 < 0.049 <0.022 l Co-58 < 0.020 < 0.022 l Co-60 < 0.011 < 0.014 Zn-65 < 0.050 < 0.045 Zr-95 <0.038 <0.035 l
=
Nb-95 < 0.027 < 0.015 1-131 < 0.032 < 0.019 Cs-134 < 0.025 < 0.019 E W Cs-137 < 0.027 < 0.023 Ba-140 La-140
< 0.086
< 0.015
<0.072
< 0.009 g
g Ce-144 < 0.077 < 0.134 I I I s>e I I
TABLE E-23 GREEN LEAFY VEGETABLE ACTIVITY - CL-114 (control)(pCi/a wet) Date Collected 6/25/97 6/25/97 6/25/97 7/30/97 7/30/97 7/30/97 Sample Type Lettuce Tumips Collards Cabbage Lettuce Collards Gross Beta 6.80
- 0.29 12.28 0.39 5.44
- 0.20 5.62 0.19 6.29
- 0.20 4.20
- 0.15 Be-7 < 0.19 < 0.23 < 0.18 < 0.14 0.37
- 0.16 <0.10 K-40 3.64
- 0.46 6.20
- 0.60 6.20
- 0.55 3.89 0.39 6.51
- 0.53 5.21 0.30 Mn-54 < 0.011 < 0.011 < 0.016 < 0.015 < 0.012 < 0.007 Fe-59 < 0.029 < 0.054 < 0.042 < 0.015 < 0.041 < 0.024 Co-58 < 0.012 < 0.021 < 0.009 < 0.010 < 0.021 < 0.007 Co-60 < 0.025 < 0.027 < 0.023 <0.015 < 0.014 < 0.009 Zn-65 < 0.020 < 0.054 < 0.038 < 0.032 < 0.049 < 0.022 Zr-95 < 0.039 < 0.056 < 0.024 < 0.022 < 0.036 < 0.025 Nb-95 < 0.020 < 0.024 < 0.010 < 0.015 < 0.010 < 0.008 l-131 < 0.026 < 0.041 < 0.027 <0.027 < 0.029 < 0.017 Cs-134 < 0.014 < 0.024 < 0.016 < 0.007 < 0.017 <0.008 Cs-137 < 0.021 < 0.022 < 0.020 < 0.015 < 0.021 . < 0.008 Ba-140 < 0.038 < 0.077 < 0.090 <0.055 < 0. 091 < 0.030 La-140 < 0.011 < 0.011 < 0.009 < 0.008 < 0.007 < 0.005 Ce-144 <0.090 <0.100 < 0.078 < 0.061 < 0.138 < 0.065 i
Date Collected 8/27/97 8/27/97 8/27/97 9/24/97 9/24/97 9/24/97 Sample Type Swiss Chard Cabbage Collards Swiss Chard Kale Collards Gross Beta 4.21
- 0.15 2.34
- 0.07 3.19
- 0.10 4.26
- 0.16 4.50
- 0.14 1.18
- 0.04 Be-7 0.22
- 0.11 <0.10 < 0.10 < 0.18 0.47
- 0.26 < 0.21 K-40 2.86
- 0.28 2.38 0.32 3.04
- 0.30 3.40
- 0.40 2.99
- 0.47 3.56 6.49 Mn-54 <0.008 <0.016 < 0.011 < 0.012 < 0.019 < 0.006 Fe-59 < 0.017 < 0.035 < 0.020 < 0.028 < 0.040 < 0.030 Co-58 < 0.008 < 0.011 < 0.010 < 0.012 < 0.015 < 0.010 Co-60 < 0.006 < 0.014 < 0.012 < 0.018 < 0.010 < 0.022 Zn-65 < 0.012 < 0.022 < 0.026 < 0.032 < 0.025 < 0.030 Zr-95 <0.021 <0.027 < 0.016 < 0.027 < 0.017 < 0.039 Nb-95 < 0.009 < 0.017 < 0.007 < 0.014 < 0.024 < 0.012 1-131 < 0.015 < 0.021 < 0.014 < 0.024 < 0.036 < 0.026 Cs-134 < 0.011 < 0.014 < 0.010 < 0.018 < 0.022 < 0.016 Cs-137 < 0.010 < 0.011 < 0.009 < 0.015 < 0.022 < 0.017 Ba-140 < 0.051 < 0.037 < 0.052 < 0.063 < 0.072 < 0.049 La-140 < 0.004 < 0.016 < 0.008 < 0.009 < 0.011 < 0.010 Ce-144 < 0.089 < 0.111 < 0.078 < 0.106 < 0.148 < 0.084 E-3I
I TABLE E-24 GREEN LEAFY VEGETABLE ACTIVITY - CL-115 (nCi/e. we0 Date Collected 6/25/97 6/25/97 6/25/97 7/30/97 7/30/97 7/30/97 Sample Type Lettuce NU NU Lettuce Cabbage Swiss Chard Gross Beta 5.47
- 0.18 4.04 0.14 3.46 0.14 7.73
- 0.25 Be-7 < 0.30 0.40
- 0.20 < 0.23 < 0.26 K-40 5.90 0.69 4.55
- 0.54 3.55 0.54 7.69
- 0.77 Mn-54 < 0.026 < 0.009 < 0.014 < 0.022 Fe-59 < 0.048 < 0.051 < 0.031 <0.026 Co.58 <0.015 < 0.011 < 0.014 < 0.018 Co-60 < 0.033 < 0.026 < 0.014 < 0.024 Zn-65 < 0.034 < 0.044 < 0.048 < 0.034 Zr-95 < 0.032 < 0.023 < 0.037 < 0.033 143-95 < 0.014 < 0.026 < 0.018 < 0.022 l 13l < 0.029 < 0.032 < 0.022 <0.019 Cs-134 < 0.024 < 0.023 < 0.014 < 0.029 l
=
Cs-137 < 0.028 < 0.017 < 0.013 < 0.021 Ba-140 < 0.093 < 0.08 i < 0.092 < 0.046 La-140 < 0.026 < 0.020 < 0.013 < 0.013 l 5 Ce-144 < 0.202 < 0.081 < 0.080 < 0.136 Date Collected Sample Type 8/27/97 Swiss Chard 8/27/97 8/27/97 9/24/97 9/24/97 9/24/97 I Cabbage Collards Swiss Chard Cabbage Kale Gross Beta 5.76 0.18 2.06 0.07 3.50 0.09 6.89 0.22 2.57
- 0.09 5.75
- 0.20 Be-7 0.51
- 0.21 < 0.052 < 0.26 0.40 0.17 < 0.16 0.46
- 0.20 K-40 5.73
- 0.57 2.24
- 0.I8 3.64
- 0.41 7.60
- 0.45 1.95
- 0.30 5.10* 0.44 l
W Mn 54 < 0.023 < 0.004 < 0.022 < 0.007 < 0.012 < 0.014 Fe-59 < 0.054 Co-58 < 0.014
< 0.005
< 0.008
< 0.036
< 0.008
< 0.032
< 0.009
< 0.021 < 0.048 g Co-60 < 0.027 < 0.008 < 0.018
< 0.010 < 0.007 W
< 0.020 < 0.013 < 0.026 Zn-65 < 0.043 < 0.011 < 0.048 < 0.026 < 0.016 Zr 95 < 0.040 < 0.018
< 0.027 g l Nb-95 < 0.023 < 0.006
< 0.034
< 0.014
<0.026 < 0.026 < 0.044 g
< 0.016 < 0.008 < 0.011 1-131 < 0.038 < 0.009 < 0.028 < 0.023 < 0.023 < 0.018 Cs-134 < 0.021 < 0.005 < 0.019 < 0.013 < 0.008 < 0.021 l Cs-137 < 0.012 < 0.005 < 0.026 < 0.014 < 0.016 < 0.019 I Ba-140 < 0.107 < 0.035 < 0.120 < 0.075 < 0.058 < 0.070 l La-140 < 0.011 < 0.003 <0.015 < 0.005 < 0.007 < 0.010 Ce-144 < 0.121 < 0.039 s 0.094 < 0.112 < 0.094 < 0.130 l
NU = sample unavailable due immature plant growth I E-32 I
l L I TABLE E-25 GREEN LEAFY VEGETABLE ACTIVITY - CL-117 (nCi/n wet) Date Collected 6/25/97 6/25/97 6/25/97 7/30/97 7/30/97 7/30/97 Sample Type Lettuce ' Tumip Collards Cabbage Swiss Chard Collards Gross Beta 3.8i
- 0.15 5.33
- 0.20 3.57
- 0.14 2.67
- 0.08 6.34 A 0.23 3.80* 0.15 Be-7 < 0.17 <0.20 < 0.23 < 0.13 < 0.15 < 0.13 K-40 3.60
- 0.50 4.4i
- 0.56 3.92
- 0.52 2.69
- 0.33 5.44
- 0.45 3.64i 0.36 I <0.017 Mn-54 <0.015 < 0.020 < 0.012 < 0.009 < 0.007 l Fe-59 < 0.047 <0.042 < 0.046 < 0.023 < 0.021 < 0.021 Co-58 <0.021 <0.016 < 0.019 < 0.007 < 0.012 <0.015 Co-60 <0.021 < 0.017 < 0.014 <0.016 < 0.021 - <0.013 ;
l Zn-65 <0.019 <0.021 < 0.021 < 0.036 <0.036 <0.014 l l Zr-95 <0.041 < 0.023 <0.036 < 0.014 <0.027 <0.025-l Nb-95 <0.019 <0.017 <0.027 < 0.016 <0.018 <0.018 l-131 < 0.026 < 0.021 <0.025 <0.016 <0.016 < 0.020 l Cs-134 < 0.017 <0.011 <0.024 < 0.014 <0.019 <0.010 ! Cs-137 < 0.015 <0.012 <0.013 < 0.008 < 0.015 < 0.012 Ba-140 < 0.068 < 0.097 < 0.059 < 0.054 < 0.067 < 0.041 ! La-140 < 0.010 < 0.011 < 0.012 < 0.006 < 0.011 <0.006 Ce-144 < 0.146 < 0.141 < 0.128 < 0.109 < 0.050 < 0.089 ; Date Collected 8/27//97 8/27/97 8/27/97 9/24/97 9/24/97 9/24/97 p Sample Type Swiss Chard Cebbage Collards Swiss Chard Cabbage Kale Gross Beta 3.59 i 0.12 2.25A 0.07 2.94i 0.10 3.09* 0.10 2.16
- 0.07 5.71
- 0.18 Be-7 0.44* 0.18 < 0.083 <017 < 0.15 < 0.11 < 0.14 l K-40 4.07 i 0.41 2.23* 0.23 3.04 +- 0.39 3.22
- 0.35 2.13
- 0.27 3.57
- 0.38 l Mn-54 < 0.007 < 0.006 < 0.016 < 0.014 < 0.012 < 0.014 Fe-59 < 0.026 < 0.015 < 0.021 < 0.015 <0.018 < 0.027 Co-58 < 0.007 < 0.007 < 0.018 < 0.015 < 0.011 < 0.018
, Co-60 < 0.016 < 0.011 < 0.021 < 0.016 < 0.010 < 0.015 Zn 65 < 0.017 < 0.012 < 0.040 < 0.021 < 0.024 < 0.029 I Zr-95 < 0.023 <0.012 < 0.032 < 0.026 < 0.017 < 0.03i Nb-95 < 0.013 < 0.007 < 0.015 < 0.014 < 0.010 < 0.018 I-131 < 0.035 < 0.013 < 0.027 < 0.021 < 0.018 < 0.023 Cs-134 < 0.018 < 0.010 < 0.015 < 0.009 < 0.006 < 0.016 l Cs-137 <0.016 < 0.006 < 0.013 <0.012 <0.011 <0.015
' Ba-140 <0.088 < 0.024 < 0.036 <0.060 <0.048 <0.080 La-140 <0.017 < 0.004 <0.009 <0.007 <0.006 <0.006 Cc-144 < 0.098 < 0.065 < 0.061 < 0.087 < 0.041 < 0.079 E-33
- e. .:
TABLE E-26 GREEN LEAFY VEGETABLE ACTIVITY - CL-118 (nCi/c wet) Date Collected 6/25/97 6/25/97 6/25/97 7/30/97 7/30/97 7/30/97 Sample Type Lettuce Swiss Jhard NU Lettuce Swiss Chard Collards Gross Beta 4.05
- 0.I3 7.61
- 0.23 8.03
- 0.27 7.I4
- 0.I5 7.I3
- 0.26 Be-7 < 0.26 < 0.22 < 0.22 0.20
- 0.079 < 0.I5 K-40 4.47
- 0.56 7.69 0.65 5.59
- 0.65 8.I7 0.29 4.59
- 0.43 Mn-54 < 0.024 < 0.014 < 0.023 < 0.009 < 0.015 g Fe-59 < 0.036 < 0.033 < 0.030 < 0.012 < 0.028 Co-58 < 0.027 < 0.019 < 0.012 < 0.010 < 0.011 5
Co-60 < 0.011 < 0.024 < 0.025 < 0.016 < 0.024 Zn-65 < 0.053 < 0.045 < 0.041 < 0.023 < 0.032 Zr-95 < 0.059 < 0.053 <0.055 < 0.022 < 0.034 Nb-95 < 0.022 < 0.020 < 0.011 < 0.006 < 0.007 I-131 < 0.035 <0.025 < 0.038 < 0.009 < 0.027 Cs-134 < 0.028 < 0.023 < 0.019 < 0.011 < 0.015 l Wr Cs-137 < 0.026 < 0.022 < 0.019 < 0.010 < 0.015 Ba-140 < 0.124
< 0.012
< 0.058 < 0.106 <0.027 < 0.065 g La-140 < 0.018 < 0.012 < 0.006 < 0.012 B Ce-144 < 0.099 < 0.170 < 0.138 < 0.060 < 0.092 Date Collected Sample Type 8/27/97 Swiss Chard 8/27/97 Cabbage 8/27/97 9/24/97 9/24/97 9/24/97 I
Collards Swiss Chard Cabbage Kale l Gross Beta 6.62
- 0.20 2.87
- 0.09 6.52
- 0.22 5.09
- 0.16 2.42
- 0.07 6.55
- 0.20 Be-7 K-40
< 0.18 4.99 0.49
< 0.094 2.46
- 0.23 0.32
- 0.13 0.34 0.13 < 0.10 0.32
- 0.14 g 4.67
- 0.38 6.93
- 0.41 2.13
- 0.23 5.2720.41 3 Mn-54 < 0.017 < 0.008 < 0.009 < 0.011 < 0.007 < 0.015 Fe-59 Co-58
< 0.044
< 0.014
< 0.015
< 0.006
< 0.027
< 0.012
< 0.027 < 0.020 < 0.014 g
< 0.013 < 0.006 < 0.010 g Co-60 < 0.010 < 0.010 < 0.007 < 0.018 < 0.013 < 0.017 Zn-65 < 0.039 < 0.008 < 0.033 < 0.025 < 0.015 < 0.028 g Zr-95 Nb-95
< 0.023
< 0.022
< 0.009
< 0.005
<0.026
<0.017
< 0.026
< 0.014
< 0.024
< 0.006
< 0.027
< 0.007 g
I-131 < 0.019 < 0.015 < 0.025 < 0.016 < 0.017 < 0.016 Cs-134 < 0.017 < 0.008 < 0.014 < 0.011 < 0.010 < 0.013 Cs-137 < 0.022 < 0.011 < 0.006 < 0.012 < 0.005 < 0.016 Ba-140 < 0.072 < 0.037 < 0.067 < 0.051 < 0.028 < 0.052 La 140 < 0.010 < 0.004 <0.006 < 0.005 < 0.007 < 0.006 Ce-144 < 0.064 < 0.058 < 0.104 < 0.094 < 0.054 < 0.066 NU = sample unavailable due to immature plant growth I E-34 5 1
TABLE E-27 MEAT ACTIVITY - CL-106 (pCi/n wet) Date Collected I/6/97 1/6/97 1/6/97 Type Ground Beef BeefLiver BeefThyroid Be-7 < 0.053 < 0.0$0 < 0.045 K-40 2.44
- 0.I4 2.44
- 0.15 3.24
- 0.I6 Mn-54 < 0.003 < 0.003 < 0.006 Fe-59 < 0.015 < 0.017 < 0.017 Co-58 < 0.005 < 0.006 <0.007 Co-60 < 0.006 < 0.004 < 0.007 Zn-65 < 0.009 < 0.010 < 0.014 Zr-95 < 0.013 < 0.009 < 0.013 Nb-95 < 0.006 < 0.009 < 0.009 Ru 103 < 0.005 < 0.005 < 0.004 Ru 106 < 0.024 < 0.058 < 0.061 1-131 < 0.030 < 0.039 < 0.022 Cs 134 < 0.005 < 0.006 < 0.004 Cs-137 < 0.006 < 0.006 < 0.006 Ba-140 < 0.064 < 0.071 < 0.042 La-140 < 0.011 <0.011 2 0.011 Ce-141 < 0.006 < 0.009 < 0.011 Cc-144 < 0.028 < 0.021 < 0.038 I ~
I i . , ,
TABLE E-28 I FISH ACTIVITY - CL-19 (nCi/c wet) Date Collected 4/21/97 4/21/97 4/21/97 4/21/97 Type Blue Gill Crappie Carp Bass Be-7 < 0.035 < 0.092 < 0.034 < 0.08 i K-40 2.37
- 0.13 2.86
- 0.19 2.78
- 0.15 3.003 0.I 7 g Mn-54 < 0.005 < 0.010 < 0.004 < 0.007 g Fe-59 < 0.007 < 0.013 < 0.014 <0.019 Co-58 < 0.007 < 0.008 < 0.006 < 0.004 Co-60 < 0.008 < 0.010 < 0.007 < 0.010 Zn-65 < 0.013 < 0.032 < 0.011 < 0.013 =
Zr-95 < 0.009 < 0.014 < 0.007 < 0.015 Nb-95 < 0.009 < 0.008 < 0.007 < 0.010 g Ru-l03 < 0.006 < 0.006 < 0.004 < 0.008 3 Ru-106 < 0.051 < 0.039 < 0.025 < 0.030 Cs-134 < 0.006 < 0.010 < 0.006 < 0.008 E Cs-137 Ba-140
< 0.006
< 0.055
< 0.009
< 0.093
< 0.003
< 0.048
< 0.008
< 0.075 g
La-140 < 0.012 < 0.012 <0.018 < 0.019 Ce-141 < 0.007 < 0.014 < 0.012 < 0.017 l 5 Cc-144 < 0.034 < 0.048 < 0.031 < 0.039 Date Collected 10/14/97 10/14/97 10/14/97 10/14/97 Type Blue Gill Crappie Carp Bass Be-7 < 0.19 < 0.21 < 0.14 <0.13 K-40 2.45 0.52 3.040
- 0.52 2.79 s 0.33 3.26
- 0.42 l Mn-54 < 0.016 < 0.011 < 0.012 < 0.018 =
Fe-59 < 0.022 <0.035 < 0.025 < 0.069 Co-58 < 0.014 < 0.035 < 0.011 < 0.026 l Co-60 < 0.011 < 0.015 < 0.010 < 0.022 5 Zn-65 < 0.030 < 0.035 < 0.024 < 0.024 Zr-95 < 0.028 <0.058 <0.048 <0.041 g Nb-95 Ru-103
< 0.045
< 0.017
< 0.047
< 0.038
< 0.026
< 0.019
< 0.051
< 0.031 g
Ru-106 < 0.130 < 0.180 < 0.112 < 0.145 Cs-134 < 0.018 < 0.025 < 0.009 < 0.021 l E Cs-137 < 0.017 < 0.008 < 0.010 < 0.018 Ba-140 < 0.363 < 0.653 < 0.228 < 0.752 La-140 < 0.057 < 0.085 < 0.060 < 0.122 E Ce-141 < 0.064 < 0.077 < 0.040 < 0.072 g Ce-144 < 0.072 < 0.071 < 0.077 < 0.057 I I E-36 I
1 TABLE E-29 FISil ACTIVITY - CL-105 (control)(pCi/c wet) Date Collected 4/22/97 4/22/97 4/22/97 4/22/97 Type Crappie B!ue Gill Bass Carp Be-7 < 0.062 < 0.043 < 0.060 < 0.03 i K-40 2.98
- 0.16 2.28
- 0.11 3.030
- 0.11 2.87
- 0.17 Mn-54 < 0.005 < 0.003 < 0.005 < 0.007 Fe-59 < 0.020 < 0 006 < 0.007 < 0.020 Co-58 < 0.007 < 0.003 < 0.005 < 0.007 Co-60 < 0.007 < 0.005 < 0.008 < 0.009 Zn-65 < 0.012 < 0.010 < 0.012 < 0.014 Zr-95 < 0.010 < 0.007 < 0.010 < 0.018 I Nb-95 Ru-103
< 0.009
< 0.007
< 0.006
< 0.005
< 0.008
< 0.004
< 0.011
< 0.009 Ru-106 < 0.050 < 0.045 < 0.023 <0.045 I Cs-134 Cs-137
< 0.007
< 0.008
< 0.004
< 0.005
< 0.005
< 0.006
< 0.008
< 0.007 Ba-140 <0.057 < 0.049 < 0.031 <0.073 i La-140 Ce-141 Cc-144
< 0.015
<0.009
< 0.029
<0.010
< 0.007
< 0.025
< 0.007
< 0.010
< 0.023
<0.008
<0.016
< 0.066 Date Collected 10/14/97 10/14/97 10/14/97 10/14/97 Type Crappie Blue Gill Bass Carp i Be-7 K-40 Mn-54
< 0.13
- 3. I 8 0.41
< 0.018
< 0.21 2.59
- 0.42
< 0.023
<0.14 2.93
- 0.35
< 0.009
< 0.16 2.84
- 0.42
< 0.012 Fe-59 <0.029 < 0.067 < 0.045 < 0.023 i Co-58 Co-60
< 0.0I I
< 0.018
< 0.013
< 0.017
< 0.016
< 0.009
< 0.008
< 0.018 Zn-65 <0.018 <0.024 <0.020 <0.022 I Zr-95 Nb-95
<0.049
< 0.024
<0.055
< 0.046
< 0.038
< 0.028
<0.029
< 0.014 Ru-103 < 0.013 < 0.038 < 0.025 < 0.015 Ru-106 <0.110 i Cs-l34 Cs-137
< 0.008
< 0.017
< 0.191
< 0.009
< 0.017
< 0.131
< 0.008
< 0.009
< 0.069
< 0.014
< 0.016 Ba-140 < 0.298 < 0.566 < 0.527 < 0.036 i La-140 Ce-141
< 0.041
<0.021
< 0.068
< 0.055
< 0.054
< 0.039
< 0.008
< 0.026 Ce-144 < 0.053 <0.118 < 0.091 < 0.064 l
E-37
I TABLE E-30 AOUATIC VEGETATION ACTIVITY -(nCi/tt wet) Location CL-7B 3 Date Collected 4/21/97 6/17/97 8/6/97 10/14/97 g Be-7 2.46
- 0.53 0.66 0.23 < 0.19 0.74 0.32)
K-40 3.35 0.84 0.93
- 0.43 0.68
- 0.26 1.55
- 0.27 Mu-54 < 0.046 < 0.029 < 0.015 < 0.018 l
W Fe-59 < 0.091 < 0.027 < 0.043 < 0.048 Co-58 Co-60
< 0.045 < 0.017 < 0.015 < 0.019 g
< 0.029 < 0.032 <0.017 < 0.020 g Zn-65 < 0.110 < 0.086 < 0.029 < 0.067 Zr-95 < 0.100 < 0.032 < 0.035 < 0.065 g Nb-95 Cs-134
< 0.069
< 0.030
< 0.029
< 0.030
< 0.029
<0.020
< 0.056
< 0.020 g
Cs-137 < 0.043 < 0.029 < 0.020 0.035
- 0.017 Ba-140 < 0.271 < 0.137 < 0.187 < 0.776 l La-140 < 0.114 < 0.023 < 0.042 < 0.108 l
W Ce-144 < 0.105 < 0.166 < 0.103 < 0.094 Location CL-7C Date Collected 4/21/97 6/17/97 8/6/97 10/14/97 Be-7 1.47
- 0.38 0.47 0.I3 0.48
- 0.23 0.31 A 0.I6 K-40 2.64 0.47 2.19
- 0.24 3.00 0.37 1.58
- 0.21 Mn-54 < 0.026 < 0.014 < 0.024 < 0.012 Fe-59 < 0.033 < 0.032 < 0.046 < 0.039 Co-58 < 0.039 < 0.010 < 0.021 < 0.016 E
Co-60 3
< 0.032 < 0.015 < 0.021 < 0.0 1 7 Zn-65 < 0.107 < 0.044 < 0.076 < 0.053 Zr-95 < 0.046 g
Nb-95 < 0.043
< 0.041
< 0.011
< 0.069
< 0.035
< 0.066
< 0.042 g
! Cs-134 < 0.040 < 0.017 < 0.026 < 0.01 7 Cs-137 0.046 0.026 < 0.014 < 0.027 < 0.019 Ba-140 < 0.277 < 0.065 < 0.255 < 0.470 l W La-140 < 0.026 < 0.023 < 0.052 < 0.084 Ce-144 < 0.110 < 0.087 < 0.055 < 0.068 I I I E-38 I
I TABLE E-30 (Cont'd)
' Location CL-9 Date Collected 4/21/97 6/17/97 8/6/97 10/14/97 Be-7 1.33
- 0.39 0.74* 0.25 < 0.22 0.84
- 0.33 K-40 2.71* 0.60 1.28
- 0.45 1.36
- 0.35 3.48
- 0.53 Mn-54 < 0.036 < 0.023 < 0.023 < 0.030 Fe-59 < 0.108 < 0.049 <0.046 < 0.044 Co-58 < 0.045 < 0.021 < 0.025 < 0.032 Co-60 < 0.039 < 0.029 < 0.023 < 0.036 Zn-65 < 0.036 < 0.077 < 0.033 <0.088 Zr 95 < 0.086 <0.061 < 0.040 < 0. I 10 Nb-95 < 0.059 < 0.024 < 0.027 < 0.071 Cs-134 < 0.043 < 0.028 < 0.023 < 0.029 Cs-137 0.074
- 0.040 < 0.033 0.026
- 0.015 0.091
- 0.040 Ba-140 <0.316 < 0.072 < 0.152 < l.080 La-140 <0.111 < 0.014 <0.026 < 0.216 Cc-144 < 0.210 <0.151 <0.104 < 0.118 Location CL-10 Date Collected 4/21/97 6/17/97 8/6/97 10/14/97 Be-7 0.82
- 0.20 0.54
- 0.29 0.40
- 0.22 0.81
- 0.29 K-40 1.76
- 0.35 0.96
- 0.52 2.21
- 0.30 4.08
- 0.40 Mn-54 < 0.025 < 0.030 < 0.019 < 0.024 Fe-59 < 0.033 < 0.057 < 0.035 < 0.09I Co-58 < 0.017 < 0.031 < 0.014 < 0.018 Co-60 < 0.028 < 0.021 < 0.023 < 0.03 I Zn-65 < 0.069 < 0.070 < 0.069 < 0.099 Zr-95 <0.040 < 0.066 < 0.065 < 0.117 Nb-95 < 0.038 < 0.037 < 0.031 < 0.074 Cs-l34 <0.033 < 0.043 < 0.023 < 0.032 Cs-137 < 0.032 < 0.040 < 0.026 0.056
- 0.022 Ba-140 < 0.157 < 0.156 < 0.229 < 0.928 La-140 < 0.049 < 0.024 < 0.047 < 0.156 Ce-144 < 0.137 <0.104 < 0.079 < 0.119 E-39
I TABLE E-30 (Cont'd) Location CL-19 Date Collected 4/21/97 6/17/97 8/6/97 10/14/97 Be-7 1.044
- 0.33 1.010
- 0.33 0.77
- 0.39 < 0.23 K-40 1.70
- 0.59 1.91
- 0.40 2.73
- 0.56 2.69 0.31 Mn-54 < 0.033 < 0.031 < 0.025 < 0.016 Fe-59 < 0.085 < 0.035 < 0.091 < 0.063 Co-58 < 0.031 < 0.026 < 0.041 < 0.021 l
=
Co-60 < 0.037 < 0.031 < 0.035 < 0.015 Zn-65 Zr-95
< 0.107
< 0.084
< 0.107
< 0.058
< 0.089 < 0.059 g
< 0.088 < 0.039 5 Nb-95 < 0.045 < 0.022 < 0.036 < 0.044 Cs-134 < 0.038 < 0.037 < 0.033 < 0.027 g Cs-137 Ba-140
< 0.045
< 0.336
< 0.039
< 0.103
< 0.039
< 0.248 0.031
- 0.018
< 0.297 g
La-140 < 0.098 < 0.052 < 0.090 < 0.139 Cc-144 < 0.186 < 0.217 < 0.150 < 0.066 Location CL-105 Date Collected 4/22/97 10;i4/97 Be-7 0.71
- 0.29 < 0.29 K-40 3.62
- 0.64 2.20 0.32 Mn-54 < 0.033 < 0.018 Fe-59 < 0.056 < 0.053 l
=
Co-58 < 0.03 8 < 0.028 Co-60 < 0.039 < 0.021 Zn-65 < 0.058 < 0.067 E Zr-95 < 0.045 3
< 0.037 Nb-95 < 0.049 < 0.05 i Cs-134 <0.034 < 0.019 Cs-137 0.073
- 0.039 0.040 0.016 Ba-140 < 0.236 <0.807 La-140 < 0.065 < 0.209 Ce-144 < 0.155 < 0.081 I
I l I E-40 l 1 I L
i l l l l TABLE E-31 l SHORELINE SEDIMENT ACTIVITY -(nCi/a dry) Location C1k78 CL-7C Date Collected 4/2187 10/1487 4/21M7 10/14M7 Gross Alpha < 2.03 < 3.57 < 2.17 < 3.55 Gross Beta 6.53 i 1.47 9.99
- 2.52 7.16
- 1.4I 8.67
- 2.30 l St-90 < 0.020 < 0.022 <0.020 < 0.012 Be-7 0.15
- 0.068 < 0.29 0.051* 0.029 < 0.12 l K-40 6.093
- 0.22 9.20
- 0.75 2.30
- 0.093 7.98 i 0.38 l
Mn-54 < 0.010 < 0.017 < 0.004 < 0.008 l Fe-59 ,
< 0.011 < 0.044 < 0.006 <0.024
- Co-58 < 0.008 < 0.036 < 0.003 < 0.015 1 l
Co-60 < 0.008 < 0.032 < 0.003 < 0.012 ) Zn-65 < 0.025 < 0.116 < 0.013 < 0.052 l Zr-95 < 0.024 <0.125 < 0.006 < 0.024 ! Nb-95 < 0.011 < 0.061 < 0.006 < 0.011 Cs-134 < 0.009 < 0.038 < 0.004 <0.026 Cs-137 < 0.007 < 0.029 < 0.003 <0.01I l Ba-140 < 0.031 <0.457 <0.026 <0.114 La-140 < 0.012 < 0.122 < 0.007 < 0.015
- l. Cc-144 < 0.026 < 0.174 < 0.013 < 0.059
! Ac-228 0.029
- 0.006 0.098* 0.038 < 0.007 0.043
- 0.015 Bi-212 0.113
- 0.064 < 0.437 < 0.044 < 0.149 Bi-214 0.072
- 0.016 0.248
- 0.050 < 0.011 0.164
- 0.025 Pb-212 0.095
- 0.011 0.303
- 0.047 0.042
- 0.005 0.146
- 0.023 i Pb-214 0.083
- 0.018 0.320
- 0.076 0.032
- 0.007 0.203
- 0.037 l Ra-226 0.257
- 0.099 0.673
- 0.360 < 0.06 I < 0.29 I TI-208 0.094
- 0.033 0.349
- 0.105 0.037
- 0.012 0.176
- 0.045 i Location CL-10 CL-19 Date Collected 4/21/97 10/14M7 4/2 f /97 10/14M7 )
Gross Alpha < 2.07 < 3.60 <l.84 < 4.44 I Gross Beta 7.56
- 1.37 9.25
- 2.51 9.28
- 1.46 9.47
- 2.47 I Sr-90 < 0.026 <0.011 <0.026 < 0.020 Be-7 < 0.037 <0.12 0.11
- 0.049 < 0.11 K-40 3.24
- 0.II 8.10
- 0.41 8.81
- 0.20 9.60
- 0.29 Mn-54 < 0.005 < 0.009 < 0.008 < 0.010 Fe-59 < 0.012 < 0.014 < 0.016 < 0.024 Co-58 < 0.004 < 0.018 < 0.007 < 0.008 Co-60 < 0.004 < 0.013 <0.006 < 0.008 Zn-65 < 0.015 < 0.0$6 < 0.024 < 0.044 Zr 95 < 0.004 <0.016 < 0.012 <0.013 Nb-95 < 0.003 < 0.011 < 0.010 < 0.023 Cs-134 < 0.004 < 0.029 < 0.008 < 0.012 Cs-137 < 0.003 < 0.011 < 0.007 < 0.009 Ba-140 < 0.036 < 0.200 < 0.035 < 0.193 La-140 < 0.006 < 0.016 <0.013 <0.051 Cc-144 < 0.024 <0.072 < 0.053 <0.051 Ac-228 < 0.007 0.054
- 0.021 0.060
- 0.007 0.051
- 0.0II Bi-212 0.081
- 0.037 < 0.166 0.I6I
- 0.071 0.160
- 0.094 l Bi-214 0.020
- 0.007 0.166
- 0.027 0.144
- 0.016 0.143
- 0.019
! Pb-212 0.065
- 0.006 0.154
- 0.026 0.1 %
- 0.012 0.174
- 0.014 Pb-214 0.046* 0.008 0.2 %
- 0.040 0.152
- 0.016 0.174
- 0.021 Ra-226 < 0.069 < 0.30 0.341
- 0.097 0.253
- 0.115 TI-208 0.054
- 0.013 0.204
- 0.054 0.194
- 0.029 0.164
- 0.040 E-41
TABLE E-31 (Cont'd) Location Cl 88 C1,89 Date Cohected 4/21/97 10/1457 4/2167 10/15/97 Gross Alpha < 2.40 < 5.13 4.41
- 2.86 8.43
- 3.51 Gross lieta 8.44
- 1.52 9.501 3.37 10.52
- 2.41 16.65
- 2.78 l Sr-90 < 0.019 < 0.015 < 0.028 < 0.020 lle-7 < 0.20 < 0.11 0.18
- 0.079 < 0.14 K-40 8.93
- 0.44 7.75
- 0.34 8.75
- 0.25 11.54
- 0.48 Mn-54 < 0.021 < 0.009 <0.0.1 <0.015 Fe-59 < 0.039 < 0.021 < 0.019 < 0.016 Co-58 < 0.021 < 0.015 < 0.008 < 0.006 Co-60 < 0.008 < 0.011 <0.010 < 0.012 Zn-65 < 0.065 < 0.045 < 0.033 < 0.064 Zr-95 < 0.035 < 0.020 < 0.030 < 0.023 Nb-95 < 0.019 < 0.008 < 0.014 < 0.022 Cs 134 < 0.022 <0.024 <0.011 < 0.034 Cs-137 < 0.016 < 0.009 0.014
- 0.008 0.032
- 0.019 3 Ba-140 La 140
< 0.078
<0.025
< 0.1II
< 0.012
< 0.060
<0.026
< 0.198
<0.029 g
l Cc-144 < 0.083 <0.057 <0.086 < 0.088 Ac-228 0.077
- 0.015 0.041
- 0.015 0.066
- 0.007 0.I30 0.022 Bi-212 < 0.256 <0.127 0.282 A 0.122 0.450
- 0.149 Bi-2I4 0.163
- 0.029 0.171
- 0.023 0.191
- 0.021 0.276
- 0.032 Pb-212 0.214
- 0.029 0.129
- 0.022 0.253
- 0.015 0.371
- 0.033 Pb-214 0.186
- 0.039 0.176
- 0.029 0.211
- 0.022 0.328
- 0.043 l Ra-226 < 0.35 < 0.24 0.522
- 0.108 0.738
- 0.2!4 5 TI-208 0.227
- 0.066 0.179
- 0.043 0.272
- 0.038 0.395
- 0.056 Location CL-105 l Date Collected 4/22N7 10/14M7 5 Gross Alpha < 2.47 < 3.56 Gross Beta 10.64
- 1.54 10.13
- 2.39 E
Sr-90 Be-7
< 0.017 0.23
- 0.079
< 0.020 0.17
- 0.084 g
K-40 8.99
- 0.27 10.24
- 0.30 Mn-54 < 0.016 <0.009 Fe-59 <0.022 <0.031 Co-58 < 0.013 < 0.013 Co-60 < 0.009 < 0.011 Zn-65 < 0.031 < 0.046 Zr-95 < 0.015 < 0.012 l
m Nb-95 < 0.011 < 0.022 Cs-134 < 0.011 <0.013 Cs-137 < 0.008 Ba-140 < 0.036
< 0.01I
< 0.168 l
W La-140 < 0.008 <0.037 Cc-144 < 0.032 < 0.053 g Ac-228 Bi-212 0.044
- 0.007
< 0. I 19 0.078
- 0.012 0.259
- 0.132 g
Bi-214 0.100
- 0.018 0.185
- 0.025 Pb-212 Pb-214 0.140
- 0.014 0.148
- 0.022 0.241
- 0.015 0.206
- 0.023 g
Ra-226 g 0.204
- 0.121 0.404
- 0.104 TI-208 0.152
- 0.037 0.204
- 0.036 I
E-42 I
l TABLE E-32 BOTTOM SEDIMENT ACTIVITY -(pCi/c dry) Locrtion Cl 7C C1,10 Cl,13A Date Collected 4/2 tM7 10/I4M7 4/21M7 10/14M7 4/2iM7 10/15M7 Gross Alpha I8.16
- 4.7I I4.54
- 4.56 16.68 i 4.82 22.47 i 7.70 5.16
- 3.55 < 3.88 Gross Beta 27.80
- 3.19 29.54
- 3.38 30.44
- 3.46 24.87
- 4.44 10.64
- 2.53 7.09
- 2.21 Sr-90 < 0.M7 0.02 I i 0.011 < 0.018 0.075
- 0.028 < 0.049 < 0.016 Be-7 s.19 < 0.28 < 0.18 < 0.31 < 0.092 < 0.13 K-40 18.I6
- 0.48 17.92 i 0.72 17.00I i 0.46 17.53
- 0.78 10.066
- 0.27 8.78* 0.41 Mn-54 < 0.022 < 0.020 < 0.023 < 0.014 < 0.017 < 0.011 Fe-59 < 0.027 < 0.061 <0.036 < 0.%7 < 0.013 < 0.017 Co-58 <0.020 < 0.018 <0.024 < 0.041 < 0.014 <0.021 Co-60 < 0.017 < 0.025 < 0.014 < 0.023 < 0.010 < 0.013 Zn-65 < 0.07i < 0.108 < 0.070 < 0.127 <0.034 < 0.055 Zr-95 <0039 < 0.022 < 0.038 < 0.047 < 0.015 < 0.023 Nb-95 < 0.040 < 0.017 < 0.031 < 0.031 < 0.014 < 0.008 Cs-134 < 0.025 < 0.06l <0.024 < 0.067 < 0.012 < 0.025 Cs-137 0.228
- 0.023 0.215
- 0.029 0.279
- 0.019 0.293
- 0.035 < 0.008 < 0.013 Ba-140 < 0.120 < 0.11I < 0.139 < 0.380 < 0.059 < 0.078 La-140 < 0.055 < 0.031 < 0.049 < 0.031 < 0.012 < 0.011 Cc-I44 < 0.106 < 0.078 < 0.101 < 0.087 < 0.065 < 0.084 TI-208 0.409
- 0.020 0.378
- 0.045 0.380
- 0.018 0.4 %
- 0.045 0.077
- 0.008 0.059
- 0.017 Bi-212 1.220
- 0.271 1.255
- 0.245 1.217
- 0.270 1.376
- 0.311 0.257
- 0.122 < 0.169 Bi-214 0.834
- 0.037 0.825 0.059 0.762
- 0.034 0.740
- 0.064 0.I65
- 0.018 0.160
- 0.026 Pb-212 1.275
- 0.036 1.233
- 0.062 1.212
- 0.035 1.346
- 0.074 0.247
- 0.0l 6 0.189
- 0.026 Pb-214 0.937
- 0.046 0.973
- 0.071 0.847
- 0.041 0.934
- 0.081 0.214 d.023 0.I72
- 0.033 Ra-226 2.129
- 0.244 2.250
- 0.4 I I 2.001
- 0.217 1.993
- 0.463 0.426
- 0.167 <0.30 Ac-228 1.185
- 0.077 1.36i
- 0.118 1.161
- 0.089 1.354
- 0.154 0.237
- 0.040 0.234
- 0.049 l
l l E-43 1 L
I l TABLE E-32 (Cont'd) Location CL-17 Cl 19 Cir89 4/21N7 10/15/97 = Date Collected 4/2167 10/14/97 4/21M7 10/14/97 Gross Alpha 6.83
- 2.21 5.50
- 3.09 4.50
- 2.05 4.36
- 2.71 4.82 i 3.32 6.35
- 3.5I Gross Beta 16.12
- 1.66 20.94
- 2.92 15.01
- 1.57 12.12
- 2.50 14.53
- 2.80 12.97
- 2.67 Sr-90 0.017
- 0.009 < 0.020 < 0.014 < 0.021 < 0.016 < 0.018 Be-7 0.20 1 0.088 < 0.18 0.32 i 0.10 < 0.33 < 0.24 < 0.1I l K-40 12.85
- 0.33 14.72
- 0.56 11.92
- 0.28 12.079
- 0.83 12.59
- 0.50 8.65
- 0.36 i Mn-54 < 0.019 <0.019 < 0.014 < 0.022 <0.037 < 0.011 Fe-59 < 0. 035 < 0.022 < 0.032 < 0.121 < 0.043 < 0.028 l Co-58 < 0.007 < 0.018 < 0.010 < 0.048 < 0.022 < 0.005 Co-60 < 0.008 < 0.015 < 0.008 < 0.027 < 0.021 < 0.012 l Zn-65 < 0.046 < 0.088 < 0.042 < 0.122 < 0.081 < 0.057 Zr-95 < 0.012 <0.032 < 0.017 < 0.064 < 0. 031 < 0.024 Nb-95 < 0.020 < 0.039 < 0.016 < 0.033 < 0.028 < 0.024 l Cs-134 < 0.015 < 0.043 < 0.012 < 0.037 < 0.026 < 0.03 I j Cs-137 0.029
- 0.013 0.047
- 0.019 0.033 i 0.009 < 0.025 < 0.024 0.022
- 0.010 Ba-140 < 0.094 <0.270 < 0.093 < 0.499 < 0.229 < 0.123 I. i La-140 < 0.020 < 0.022 < 0.024 < 0.067 < 0.023 < 0.011 Cc-144 < 0.070 < 0.059 < 0.068 < 0.137 < 0.126 < 0.05 4 TI-208 0.150
- 0.011 0.213
- 0.026 0.131
- 0.009 0.081
- 0.029 0.155
- 0.020 0.093
- 0.018 l Bi-212 0.482
- 0.I53 0.668
- 0.257 0.388
- 0.120 < 0.381 0.570
- 0.208 0.422
- 0.181 g Bi-214 0.294
- 0.021 0.423
- 0.040 0.298
- 0.019 0.233
- 0.049 0.372
- 0.039 0.343
- 0.029 W Pb-212 0.476
- 0.022 0.635
- 0.043 0.324 1 0.016 0.299
- 0.045 0.461
- 0.041 0.308
- 0.028 Pb-214 0.344
- 0.027 0.510
- 0.056 0.291
- 0.022 0.231
- 0.048 0.454
- 0.065 0.415
- 0.036 Ra-226 0.765
- 0.155 1.093
- 0.287 0.616
- 0.117 0.587
- 0.309 0.863
- 0.329 0.483
- 0.I89 Ac-228 0.474 i 0.059 0.617
- 0.084 0.380
- 0.039 0.288
- 0.104 0.420
- 0.090 0.376
- 0.05I I
I I E-44 I :
I TABLE E-32 (Cont'd) Location Cl-105 Date Collected 4/22/97 10/I4/97 Gross Alpha 15.62
- 4.78 10.75
- 3.80 Gross Beta 32.69
- 3.58 32.46
- 3.30 St-90 < 0.029 0.036
- 0.012 Be-7 <0.29 < 0.32 K-40 20.46
- 0.64 20.29
- 0.83 Mn-54 < 0.047 < 0.023 Fe-59 < 0.041 < 0.065 Co-58 < 0.020 < 0.042 Co-60 < 0.028 < 0.026 Zn-65 < 0.098 <0.133 Zr-95 < 0.041 <0.030 Nb-95 < 0.044 <0.028 Cs-134 < 0.033 < 0.068 Cs-137 0.398
- 0.040 0.350
- 0.039 Ba-140 < 0.214 <0.290 La-140 < 0.073 < 0.041 Cc 144 < 0.191 <0.183 TI-208 0.404-1 0.029 0.439
- 0.044 Bi-212 1.217
- 0.376 1.435
- 0.2 %
Bi-214 0.858
- 0.057 0.804
- 0.065 Pb-212 1.289
- 0.057 1.494
- 0.075 Pb-214 0. % 3
- 0.072 0.910
- 0.084 Ra-226 2.106
- 0.403 2.067
- 0.460 Ac-228 1.176
- 0.135 1.440 i 0.139 E-45
I TABLE E-33 SOIL ACTIVITY -(pCi/c drv) Location CL-2 CL-3 CL-8 CL-i l CL-16A Date Collected 10/21/97 10/21/97 10/21/97 10/23/97 10/23/97 Gross Alpha 13.86 i 4.29 12.78
- 3.85 11.87 3.83 13.13
- 4.38 13.15
- 4.06 Gross Beta 27.47
- 3.30 17.92
- 2.38 24.56
- 3.05 20.92 i 3.00 22.51
- 2.98 Be-7 <0.27 < 0.46 < 0.50 < 0.56 <0.II K-40 16.58 i 0.66 17.70
- 1.060 18.062
- 1.12 16.14
- 1.24 16.3 I i 0.73 Mn-54 < 0.014 < 0.046 < 0.034 < 0.054 < 0.023 l
=
Fe-59 < 0.057 < 0.096 < 0.106 < 0.140 < 0.043 Co-58 < 0.041 < 0.064 < 0.056 < 0.031 < 0.033 Co-60 < 0.023 < 0.053 < 0.055 < 0.023 < 0.017 l 5 Zn-65 < 0.117 < 0.200 < 0.210 < 0.245 < 0.115 Zr-95 < 0.051 < 0.149 < 0.168 < 0.115 < 0.049 g Nb-95 < 0.035 < 0.079 < 0.099 < 0.115 < 0.016 g Cs-134 < 0.068 <0.054 < 0.055 < 0.068 < 0.063 Cs-137 0.160 0.031 0.239
- 0.060 0.353
- 0.076 0.493 0.066 0.175
- 0.030
< 0.290 <0.706 < 0.487 E
Ba-140 < 0.735 < 0.292 E La-140 < 0.051 < 0. I56 < 0.235 < 0.062 < 0.045
< 0.210 Cc-144 < 0.143 < 0.276 < 0.297 < 0.164 g
TI-208 0.404
- 0.049 0.353
- 0.053 0.394
- 0.059 0.446
- 0.066 0.301
- 0.038 g
! Bi-212 1.458
- 0.400 0.937
- 0.430 1.649 0.698 1.199 0.6I9 1.054
- 0.247 Bi-214 1.002
- 0.065 0.626
- 0.097 0.864 i 0.091 0.987
- 0.137 0.549
- 0.065 g Pb.212 1.100
- 0.065 1.065
- 0.080 1.126
- 0.083 1.202
- 0.105 0.900
- 0.067 g Pb-214 1.223
- 0.083 1.025
- 0.115 0.989
- 0.119 1.070
- 0.I39 0.851
- 0.081 l Ra-226 2.346
- 0.597 2.078
- 0.575 2.053
- 0.620 2.393
- 0.669 1.428
- 0.419 Ac-228 1.277
- 0.I12 1.067
- 0.I87 1.038
- 0.I98 1.I37 i 0.203 0.909
- 0.104 l
l I I l I E-46 i
3 I I' I l 1 i l I! I I i I l Il il . l. I. I I FOR MORE INFORMATION, CALL OR WRITE: Plant Radiatles and Chemelsery Deparament CIlesse Power Station - P.O. Box 678 CIIeese, Illisels &I727 (217) 935-8881 .}}