ML20153C216

Annual Radiological Environ Operating Rept Sequoyah Nuclear Plant 1987

ML20153C216
Person / Time
Site:	Sequoyah
Issue date:	12/31/1987
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8805060185
Download: ML20153C216 (123)

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j ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT I 1987 l

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RADIOLOGICAL CONTROL l

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i ANNUAL RADIOLOGICAL ENVIR0letENTAL OPERATING REPORT l  !

> 1 SEQUOYAll NUCLEAR PLANT ,

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I TENNESSEE VALLEY AUTHORITY j DIVISION OF NUCLEAR SERVICES j

• 1 RADIOLOGICAL CONTROL 4

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I j April 1988 j

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TABLE OF CONTENTS --

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Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . 11  !

i List of. Tables . . . . . . . . .................. iv List of Figures . . . . . . . . . . . . .............. v i

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l Executive Summary . . . . . . . . . . . . . . . . . . . . . . . . . 1 a i i Introduction .. . . .. . . . .................. 2

] Radiation and Radioactivity .................. 2 Naturally Occurring and Background Radioactivity . . . . . . . . .

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Electric Power Production . .................. 11 i

! Site / Plant Description . . . . .................. 16 ,

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Environmental Radiological Monitoring Program . .......... 18 i' r Direct Radiation Monitoring . . .................. 22  !

Measurement Techniques . . . . . . . . . . . . . . . . . . . . . 22 l Results . ... . . . . . . .................. 23  ;

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Atmospheric Monitoring

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Sample Collection end Analysis . . . . . . . . . . . . . . . . . 26 Results . ... . . . . . . .................. 28-(

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j Terrestrial Monitoring . . .. .................. 30 l Sample Collection and Analysis . . . .............. 30  !

Results . . .. . . . . . . .................. 32  !

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I Aquatic Monitoring . . . . . . .................. 35 i Sample Collection and Analysis . . . . . . . . . . . . . . . . . 35 l j Reselts . ... . . . . . . .................. 37 1

i Assessment and Evaluation . . . . . . . . . . . . . ........ 40 j j Results . ... . .. . . ... ................ 41 i

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Conclusions .. . . . . . . .................. 42 References . . .. . . . . . . .................. 46 1

i Appendix A Environmental Radiological Monitoring Program and l Sampling Locations .................. 49 Appendix 5 1987 Program Modifications .............. 61 1

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i Appendix C Exceptions to the Monitoring Program in 1987 . . . . . 63 Appendix D Analytical Procedures . . . . . . . . . . . '. . . . . . 66 Appendix E Nominal Lower Limits of Detection (LLD) . . . . . . . . 69 Appendix F Quality Control Program . . . . . . . . . . . . . . . . 74 Appendix G Land Use Survey . . . . . . . . . . . . . . . . . . . . 84

( Appendix 5 Data Tables . . . . . . . . . . . . . . . . . . . . . . 90 I

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LIST OF TABLES  ;

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i Table 1 Maxieum Permissible Concentrations for Nonoccupational Exposure . . . . . . . . . . . . . . . . 44 l i

Table 2 Maximus Dose Due to Radioactive Effluent {

Releases . . . . . . . . . . . . . . . . . . . . . . . . 45 ,

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Figure 1 Tennessee Valley Region . . . . . . . . . . . . . . . . . 47 Figure 2 Environmental Exposure Pathways of Man Due . . . . . . . 48

! to Releases of Radioactive Materials to the l Atmosphere and Lake .;

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EXECUTIVE

SUMMARY

t This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of the Sequoyah Nuclear Plant in 1987.

The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations.

The vast majority of the exposures calculated from environmental samples were contributed by naturally occurring radioactive materials or from materials commonly found in the environment as a result of atmospheric nuclear weapons fallout. Small amounts of Co-60 were found in sediment samples downstream from the plant. This activity in stream sediment would result in no measurable increase over background in the dose to the general public.

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l INTRODUCTION 1

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This report describes and summarizes a huge volume of data, the results of many thousands of measurements and laboratory analyses. The measurements are made to comply with regulations and to determir.e potential effects on public I health and safety. This report is prepared annually in partial fulfillment of l

l the requirements of the plant operating license. In addition, estimates of l

the maximum potential doses to the surrounding population are made from 1

radioactivity measured both in plant effluents and in environmental samples.

1 Some of the data presented are prescribed by specific requirements while other data are included which may be useful or interesting to individuals who do not work with this material routinely.

Radiation and Radioact.'tity l The only form of "rao .on" which is clearly observable by the human senses is light. Except for light, and the vaguer general sense of warmth due to radiant heat, there was originally no need for words to describe other kinds of radiation, since no other kinds were known. Beginning about 300 years ago, scientists began to exter.d the range of normal senses with various kinds of instruments. These instruments (lenses, thermometers, etc.) revealed that there were other forms of radiation similar to light but only observable with instruments. At the present time there are two major kinds of radiation known: electromagnetic radiation and high-energy particles.

The family of electromagnetic radiation includes light, radio waves, infrared rays, ultraviolet rays, X-rays, and gamma rays. These forms of radiation are

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all identical except for their energy. Radio waves are of the lowest energies 1

and gamma rays the highest, with light rays between them in energy. l Electromagnetic rays exist only as radiation and can be considered to be pure energy. Many X-rays and gamma rays may penetrate into the body and cause changes in cells in the body rather than being stopped by the skin as ultraviolet light. Electromagnetic radiation can generally be stopped by thicker materials such as lead and concrete.

High-energy particle radiation is not limited to "pure energy," but includes particles of matter behaving like electromagnetic radiation because they are moving at very high speeds. Members of this family include alpha particles, beta particles, and neutrons. These particles are individually smaller than atoms since they are components of atoms. An alpha particle consists of two protons and two neutrons, while a beta particle has a mass and charge equal to that of an electron. These particles produce the same types of changes in matter as electromagnetic radiation. Since alpha particles have a relatively large mass, they can be easily stopped by a sheet of paper, the human skin, or a few centimeters of air. Beta particles, being much smaller, can penetrate i several sheets of paper or thin metal sheets, but can be stopped by a few centimeters of paper. Beta particles may or may not be able to penetrate beyond the skin layer and into deeper body tissues, depending on the speed at which the particles are traveling.

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One additional characteristic of radiation is important to an understanding of the environmental effects of nuclear power plant radiation. That is the concept of "ionizing radiation." About 90 years ago, some forms of radiation were discovered which were unique in that they caused "lonization" of air.

l That is, the radiation had sufficient energy to break apart the molecules of gases in the air. This was first discovered with X-rays (electromagnetic l radiation) and soon after with alpha and beta particles. Environmental monitoring at nuclear power plants is concerned only with "ionizing radiation"; sunlight and radio waves are examples of non-ionizing radiation.

The basic building block of all material in the universe is the atom. Atoms are composed of a central nucleus surrounded by electrons in orbit around the nucleus. The nucleus consists of neutrons which have no electrical charge and l protons which are positively charged. The orbiting electrons have a negative electrical charge. In most atoms the protons and electrons are balanced and the atom is said to be stable. However, in a number of atoms the nucleus contains an excess of energy. In an effort to return to a balanced state, the atom releases the excess energy. Atoms of this type are said to be radioactive. Radiation released by these atoms may be in the form of electromagnetic radiation or high speed alpha or beta particles.

Ionizing radiation does not build up in the body. When this radiation enters the body, it interacts with atoms. It then either exits the body and/or is transformed as energy to body tissues. This means that an individual is affected by external radiation only as long ac he/she is exposed to it. As an 4

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l example, when an individual comes indoors, that individual is no longer exposed to the ultraviolet light from the sun. Exposure to the ultraviolet light ended as soon as the individual came inside. This principle can also be illustrated by the fact that light cannot build up inside a room. As soon as the light switch is turned off, the light vanishes and the room is dark.

l l Radioactive materials are made of atoms which emit ionizing radiation. Even l

l though radiation cannot accumulate in the body, it is possible for atoms of radioactive material to be absorbed by the body or to cling to the body surface. When these atoms are in or on the body, they still emit ionizing radiation in all directions, which means that the radiation is being emitted from inside the body or from the body surface, respectively. As such, these radioactive atoms are called contamination, because they are located at a place (in this case, in or on the body) where they are not wanted.

Electromagnetic radiation is known to have some impacts on human health.

Ultraviolet radiation from the sun produces the familiar sunburn after excessive exposure. The principal health effect hypothesized from exposure to low level ionizing radiation may be a very slight increase in the risk of developing cancer. The determination of this risk is difficult to quantify.

Because of thi.s, the scientific community has not been able to determine whether exposure to low levels of radiation (radiation levels of up to several times natural background) actually increases the chance of developing cancer.

However, it is known that high levels of radiation can increase the chance of getting certain types of cancer such as leukemia. Therefore, the advice of

the scientific community is to avoid unnecessary exposure to ionizing radiation, just as it is best to avoid excessive exposure to the sun's ultraviolet rays. (Excessive exposure to the sun is known to increase the chance of developing skin cancer in many individuals.)

The process by which radioactive atoms give off ionizing radiation is known as radioactive decay. Atoes of the same element which have the same number of protons but a different number of neutrons are called isotopes of the element. The time required for half of the atoms of a specific isotope to transform and consequently emit radiation is known as the half-life of the isotope. The longer the half-life, the longer the period of time between emissions of ionizing radiation. This means that radioactive materials which have a short half-life are more radioactive when compared to equal quantities of radioactive materials with a long half-life. The half-life of each specific type of radioactive material is different. Each type has its own half-life which never changes. Some radioactive materials may have half-lives I

of only a fraction of a second while others have half-lives of millions of years. I 1

When a radioactive atom goes through the process of decay, its internal l l

structure changes. Radioactive decay and internal structural changes occur '

almost instantaneously. The atom may be more or less radioactive than it was at the beginning. Sometimes its internal structure changes in such a way that the atom is no longer radioactive. In this case the atom is said to be I

stable. This finally happens to all radioactive atoms, but for some it may take a very long time.

The unit of radioactivity is the "Curie" (C1), which is equal to a radioactive decay rate of 37 billion disintegrations per second. Because levels of radioactivity in the environment usually exist in very small quantities, a unit one trillion times smaller called the "picoeurie" (pC1) is generally l used. A picoeurie is equal to a radioactive decay rate of 0.037 decays (disintegrations) per second (dps), or 2.22 disintegrations per minute (dpm).

Another unit for expressing radioactivity is the Becquerel (Bq). One pCi is equivalent to 0.037 Bq.

The unit of radiation dose equivalent is the rem. The dose equivalent is a quantity used for radiation protection purposes that expresses, on a common scale for all radiation, the irradiation incurred by exposed persons. Because the dose equivalent from environmental radiation is generally very small, it is convenient to use a much smaller unit called "millirem" (meaning one thousandth of a rem) to express dose equivalent. In other words, 1000 millirems equals 1 rem. When radiation exposure occurs over periods of time, it is appropriate to state the period of time in conjunction with the dose equivalent. For environmental exposures, the time period stated is generally 1 year (millirems per year or mrem / year). Measurements of radiation are made in units of Roentgens (R) or milliroentgens (mR). For purposes of comparison in this report, 1 mR is considered equivalent to 1 mrem.

Naturally Occurring and Background Radioactivity All materials in our world contain trace amounts of naturally occurring radioactivity. Approximately 0.01 percent of all potassium is radioactive l

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potassium-40. Potassium-40 (K-40), with a half-life of 1.3 billion years, is one of the major types of radioactive materials found naturally in our environment. An individual weighing 150 pounds contains about 140 grams of potassium (reference 1). This is equivalent to approximately 1 million pCi of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and sof t tissue of the body. Naturally occurring radioactive materials have always been in our environment. Other examples of naturally occurring radioactive l

materials are uraninum-238, uranium-235, thorium-234, radium-226, radon-222, carbon-14, and hydrogen-3 (generally called tritium). These naturally occurring radioactive materials are in the soil, our food, our drinking water, and our bodies.

The radiation from these materials makes up a part of that low-level radiation called "natural background radiation." The remainder of the natural  ;

background radiation comes f rom outer space. We are all exposed to this I natural radiation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. All natural background radiation is composed of the same types of radiation as that which is emitted by artificially produced radioactive materials. Whether radiation comes from a natural or an artificially produced source does not determine the degree of hazard involved. It is the amount and type of radiation which determines the 1

hazard.

The average dose equivalent at sea level resulting from radiation from outer space (part of natural background radiation) is about 27 mrem / year. This essentially doubles with each 6600-foot increase in altitude in the lower

atmosphere. Another part of natural background radiation comes from naturally occurring radioactive materials in the soil and rocks. Because the quantity of naturally occurring radioactive material varies according to geographical location, the part of the natural background radiation coming from this radioactive material also depends upon the geographical location. Most of the remainder of the natural background radiation comes from the radioactive materials within each individual's body. We absorb these materials from the i food we eat which contains naturally occurring radioactive materials from the 1

soil. An example of this is K-40 as described above. Even building materials l

affect the natural background radiation levels in the environment. Living or working in a building which is largely made of earthen material, such as concrete or brick, will generally result in a higher natural background radiation level than would exist if the same structure were made of wood.

This is due to the naturally occurring radioisotopes in the concrete or brick, such as trace amounts of uranium, radium, thorium, etc.

Because the city of Denver, Colorado, is over 5000 feet in altitude and the soil and rocks there contain more radioactive material than the U.S. average, the people of Denver receive around 350 mrem / year total natural background radiation dose equivalent compared to about 295 mrem / year for the national average. People in some locations of the world receive over 1000 mrem / year natural background radiation dose equivalent, primarily because of the greater quantity of radioactive materials in the soil and rocks in those locations.

Scientists have never been able to show that these levels of radiation have caused physical harm to anyone.

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It is possible to get an idea of the relative hazard of different types of radiation sources by evaluating the amount of radiation the U.S. population receives from each general type of radiation source. The information below is primarily adapted from references 2 and 3.

U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES l

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Cosmic 27 Cosmogenic 1 Terrestrial 28 In the body 39 Radon 200 i Total 295 Release of radioactive material in 5 natural gas, mining, milling, etc. i

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Medical (effective dose equivalent) 53 l l

Nuclear weapons fallout less than 1 '

Nuclear energy 0.28 Consumer products 0.03 j i

Total 355 (approximately) l l

l As can be seen from the table, natural background radiation dose equivalent to l

the U.S. population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background radiation.

Significant discussion recently has centered around exposures from radon.

1 Radon is an inert gas given off as a result of the decay of naturally j l

occurring radium-226 in soil. When dispersed in the atmosphere, radon i 1

concentrations are relatively low. However. when the gas is trapped in closed l

spacas, it can build up until concentrations become significant. The National Council of Radiation Protection and Measurements (reference 2) has estimated that the average annual effective dose equivalent from radon in the' United States is approximately 200 mrem / year. This estimated dose is approximately twice the average dose equivalent from all other natural background sources.

Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electrical generating plants. The basic process behind j i

electrical power production in both types of plants is that fuel is used to l heat water to produce steam.

However, nuclear p? ants require many complex systems to control the nuclear fission process and to safeguard against the possibility of reactor malfunction, which could lead to the release of radioactive materials.

Uranium-235 is a naturally occurring radioactive material used as fuel in commercial power reactors in the United States. The nuclear fuel is contained in fuel rods. The rods themselves are configured in bundles which make up the reactor core. The core is covered with water inside the reactor vessel.

During operation, heat is generated by "splitting" the uranium atoms. This process, called fission, splits the uranium atoms into smaller atoms called fission products. Through the process of nuclear fission, the core becomes

very hot and heats the water, thereby producing steam. The steam is channeled through turbines which turn electrien1 generators to produce electricity.

River water is used to cool the steam and condense it to water so that it may be reused.

Radioactive material in solid, liquid, and gaseous form is produced as a consequence of normal reactor operation. Although nuclear plants are designed to contain the radioactive material created by the fission process, small amounts of this material escape from the fuel rods. Also, structures and components of the plant systems become activated through the bombardment of neutrons. Very small amounts of these "activation products" are released from the components into the plant systems. This radioactive material can be transported throughout plant systems and some of it released to the environment.

Some small amounts of solid radioactive material get into the primary coolant water. The primary coolant water is run through a purification system to remove most of these particles; however, not all are removed. Some of the radioactive liquids may leak from pipes or valves in the system. These liquids are collected in floor and equipment drains and sumps. The collected liqaids are then processed through a clean-up system, composed of storage tanks, recycling systems, and demineralizers, to remove contaminants. The purified water is then monitored to determine the amount of radioactive material remaining in the water prior to its release to the environment. To ensure that the amount of radioactivity released to the environment is as low L __.

as reasonably achievable (ALARA), when the radioactivity in liquid is too high this level is reduced by additional processing through the clean-up system.

All radioactivity released from the plant into the Tennessee River is measured prior to release to ensure that all regulatory requirements have been met.

l The gaseous fission products, called noble gases, do not mix with water and )

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are given off in a gaseous form. A very small amount of radioactive material, I called particulates, is given off along with these noble gases. They are processed so that th adioactive material is filtered and/or decayed prior to release through the plant vents. Sampling and monitoring methods are used to determine the amount of radioactive material released. If these methods indicate that radioactivity in gaseous effluents is too high, releases are terminated until the limits outlined in the operating license can be met.

All paths through which radioactivity is released are monitored. Liquid and gaseous effluent monitors record the radiation levels for each release. These monitors also provide alarming mechanisms to allow for termination of any release above limits.

Releases are monitored at the onsite points of release and through an environmental monitoring program which measures the environmental radiation in outlying areas around the plant. In this way, not only is the release of radioactive materials from the plant tightly controlled, but measurements are made in surrounding areas to ensure that the population is not being exposed  !

to significant levels of radiation or radioactive materials.

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The U.S. Nuclear Regulatory Commission (NRC) requires that nuclear power plants be designed, built, and operated in such a way that levels of radioactive material released into unrestricted areas are as low as reasonably achievable. To ensure that this is done, the plant's operating license includes Technical Specifications which govern the release of radioactivity.

These Technical Specifications limit the release of radioactive effluents, as well as doses to the general public from the release of these effluents.

Additional limits are set by the Environmental Protection Agency (EPA) for doses to the public.

The dose to a member of the general public from radioactive materials released to unrestricted areas, as given in the Technical Specification = for each unit, are limited to the following:

Liquid Effluents Total body 3 mrem / year per unit Any organ 10 mram/ year per unit Caseous Effluents Noble gases:

Gamma radiation 10 mrem / year per unit Beta radiation 20 mrem / year per unit Particulates:

Any organ 15 mrem / year per unit The EPA limits for the total dose to the public in the vicinity of a nuclear 1

i power plant, established in the Environmental Dose Standard of 40 CFR 190, are as follows.  !

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Total body 25 mrem / year l

Thyroid 75 mrem / year i Any other organ 25 mrem / year I

These EPA limits are also included in the technical specifications by which the plant operates.

l In addition,10 CFR 20.106 provides maximum permissible concentrations (MPCs) 1 for radioactive materials released to unrestricted areas. MPCs for.the  ;

principal radionuclides associated with nuclear power plant effluents are presented in table 1.

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SITE / PLANT DESCRIPTION The Sequoyah Nuclear Plant (SQN) is located on a site near the geographical center of Hamilton county, Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River Mile (TRM) 484.5. Figure 1 shows the site in relation to other TVA projects. The SQN site, containing approximately 525 acres, is approximately 7.5 miles northeast of the nearest city limit of Chattanooga, Tennessee, 14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVA's Watts Bar Nuclear Plant (WBN) site.

Population is distributed rather unevenly within 10 miles of the SQN site.

Approximately 60 percent of the population is in the general area between 5 and 10 miles from the plant in the sectors ranging from the SSW, clockwise, to the NW sector. This concentration is a reflection of suburban Chattanooga and the town of Soddy-Daisy. This area is characterized by considerable vacant land with scattered high quality residential subdivisions. The northern extent of the residential development is approximately 2 miles from the site.

The population of the Chattanooga urbanized area is over 250,000, while l Soddy-Daisy has approximately 10,000 people.

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With the exception of the community of Soddy-Daisy, the areas west, north, and {

l east of the plant are sparsely settled. Development consists of scattered i

semirural and rural dwellings with associated small-scale farming. At least one dairy farm is located within a 10-mile radius of the plant.

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Chickamauga Reservoir is one of a series of highly controlled multiple-use reservoirs whose primary uses are flood control, navigation, and the generation of electric power. Secondary uses include industrial and public water supply and waste disposal, c'ommercial fishing, and recreation. Public access areas, boat docks, and an occasional small residential subdivision have been developed along the reservoir shoreline in scattered locations.

The SQN consists of two pressurized water reactors: each unit is rated at l 1171 megawatts (electrical). Fuel was loaded in unit 1 on March 1, 1980, and the unit achieved critically on July 5, 1980. Fuel was loaded in unit 2 in July 1981, and the unit achieved initial criticality on November 5, 1981. The ,

plant has been shut down since August 1985. I l

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ENVIRONMENTAL RAl'IOLOGICAL MONITORING PROGRAM The dictionary definition of "monitoring" includes such words and phrases as "check, test, watch, observe, keep track of, regulate, and control." These i

are the purposes of environmental monitoring as applied to the specific environment (surroundings, neighborhcod) of a nuclear plant. The environment includes soil, water, air, plants, and animals. Any of these could be affected by nuclear power plant operations. Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized. The most important occupants of the environment are humans. The monitoring program is designed to check the pathways between the plant and the humans in the insnediate vicinity. The sampling program is designed to most efficiently monitor these pathways.

The unique environmental concern associated with a nuclear power plant is its production of radioactive materials and radiation. This radioactive material provides the energy that is converted to ordinary electricity. The vast majority of this radiation and radioactivity is contained within the reactor l

itself or one of the other plant systems designed to keep the material in the l plant. The retention of the materials in each level of control is achieved by system engineering, design, construction, and operation. Environmental monitoring is a final verification that the systems are performing as planned. The environmental radiological monitoring program is outlined in appendix A.

There are two primary pathways by which radioactivity can move through the environment to humans: air and water (see figure 2). The air pathway can be

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1 separated into two components: the direct (airborne) pathway and the indirect l 1

(ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types of samples collected in this program are i

designed to monitor these pathways.

A number of factors were considered in determining the locations for collecting environmental samples. The locations for the atmospheric monitoring stations were determined from a critical pathway analysis basea on weather patterns, dose projections, population distribution, and land use.

Terrestrial sampling stations were selected after reviewing such things as the locations of dairy animals and gardens in conjuction with the air pathway j analysis. Liquid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and sediment.

l Table A-2 lists the sampling stations and the types of samples collected from )

each. Modifications made to the program in 1987 are described in cppendix B and exceptions to the sampling and analysis schedule are presented in appendix C. To determine the amount of radioactivity in the environment prior to the operation of SQN, a preoperational environmental radiological monitoring program was initiated in 1971 and operated until the plant began operation in 1980. Measurements of the same types of radioactive materials that are measured currently were assessed during the preoperational phase to 4

l establish normal background levels for various radionuclides in the environment. This is very important in that during the 1950s, 60s, and 70s, atmospheric nuclear weapons testing occurred which released radioactive l material to the environment causing fluctuations in the natural background radiation levels. This radioactive material is the same type as that produced in the SQN reactors. Preoperational knowledge of natural radionuclide '

patterns in the environment permits a determination, through comparison and trending analyses, of whether the operation of SQN is impacting the environment and thus the surrounding population. The determination of impact during the operating phase also considers the presence of control stations that have been extablinhed in the environment. Results of environmental  ;

i samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to establish the extent of SQN i influence. )

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All samples are analyzed by the radioanalytical laboratory of TVA's Environmental Radiological Monitoring and Instrumentation Branch located at I the Western Area Radiological Laboratory (WARL) in Muscle Shoals, Alabana, l

All analyses are conducted in accordance with written and approved procedures

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and are based on accepted methods. A summary of the analysis techniques and methodology is presented in appendix D. Data tables summarizing the sample analysis results are presented in appendix H.

4 The sophisticated radiation detection devices used to determine the radionuclide content of samples collected in the environment are generally 1

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quite sensitive to small amounts of radioactivity. In the field of radiation measurement, the sensitivity of the mcasurement process is discussed in terms of the lower limit of detection (LLD). A description of the nominal LLDs for the radioanalytical laboratory is presented in appendix E.

The radioanalytical laboratory employs a comprehensive quality assurance /

quality control program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement i process as soon as possible so they can be corrected. This program includes equipment checks to ensure that the complex radiation detection devices are working properly and the analysis of special samples which are included I alongside routine environmental samples. A complete description of the program is presented in appendix F.

DIRECT RADIATION MONITORING Direct radiation levels are measured at a number of stations around the plant site. These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and any radioactivity that may be present as a result of plant operations. Because of the relative large variations in background radiation as compared to the small levels from the plant, contributions from the plant may be difficult to distinguish.

Radiation levels measured in the area around the SQN site in 1987 were '

consistent with levels from previous years and with levels measured at other locations in the region.

Measurement Techniques Direct radiation measurements are made with detectors called thermoluminescent dosimeters (TLDs). When certain materials are exposed to ionizing radiation, many of the electrons which become displaced are trapped in the crystalline structure of the material. They remain trapped for long periods of time as long as the material is not heated. When heated, the electrons are released, along with a pulse of light. A measurement of the intensity of the 11ght is directly proportional to the radiation to which the material was exposed.

Materials which display these characteristics are used in the manufacture of TLDs.

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TVA uses a manganese activated calcium fluoride (Ca:F:Mn) TLD material encased in a glass bulb. The bulb is placed in an energy compensating shield to correct for energy dependence of the material. TLDs art, placed approximately 1 meter above the ground, with three TLDs at each station.

Twenty-two stations are located around the plant near the site boundary, at least one station in each of the 16 sectors. Dosimeters are also placed at the perimeter and remote air monitoring sites and at 22 additional stations l

out to approximately 10 miles from the site. The TLDs are exchanged every 3 I

months and read with a Victoreen model 2810 TLD reader. The values are corrected for gansna response, self-irradiation, and fading, with individual gansna response calibrations and self-irradiation factors determined for each TLD. rhe system meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 for environmental applications of TLDs.

Results All results are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).

The stations are grouped according to the distance from the plant. The first group consists of all stations within 1 mile of the plant. The second group i lies between 1 and 2 milcs, the third group between 2 and 4 miles, the fourth betweers 4 and 6 miles, and the fifth group is made up of all stations greater than 6 miles from the plant. Past data have shown that the results from all

(

stations greater than 2 miles from the plant are essentially the same.

Therefore, for purposes of this report, all stations 2 miles or less from the plant are identified as "onsite" stations and all others are considered "offsite."

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1 1

Prior to 1976, direct radiation measurements in the environment were made with less sensitive dosimeters. Consequently, environmental radiation levels reported in the preoperational phase of the monitoring program exceed current i measurements of background radiation levels. For this reason, data collected prior to 1976 are not included in this report.

The quarterly gamma radiation levels determined from the TLDs deployed around SQN in 1987 are given in table H-1. The rounded average annual exposures are shown below. For comparison purposes, the average direct radiation measurements made in the preoperational phase of the monitoring program are also shown.

l Annual Average  ;

Direct Radiation Levels l SQN mR/ year Preoperational 1987 Average Onsite Stations 76 79 Offsite Stations 65 63 The data in table H-1 indicate that the average quarterly radiation levels at

}

the SQN onsite stations are approximately 2-3 mR/ quarter higher than levels at 1

the offsite stations. This difference is also noted in the preoperational l

phase and in the stations at WBN and other nonoperating TVA nuclear power l

plant construction sites where the average levels onsite are generally 2-6 mR/ quarter higher than levels offsite. The causes of these differences have not been isolated; however, it is postulated that the differences are probably

attributable to combinations of influences such as natural variations in environmental radiation levels, earth-moving activities onsite, and the mass of concrete employed in the construction of the plant. Other undetermined influences may also play a part.

Figure H-1 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1987. To reduce the variations present in the data sets, a 4-quarter i moving average was constructed for each data set. Figure H-2 presents a trend plot of the direct radiation levels as defined by the moving averages. The data follow the same general trend as the raw data, but the curves are smoothed considerably.

All results reported in 1987 are consistent with direct radiation levels identified at locations which are not influenced by the operation of SQN.

There is no indication that SQN operations increased the background radiation levels normally observed in the areas surrounding the plant.

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ATNOSPHERIC MONITORING l

The atmospheric monitoring network is divided into three groups identified as  ;

local, perimeter, and remote. Four local air monitoring stations are located on or adjacent to the plant site in the general areas of greatest wind frequency. Four perimeter air monitoring stations are located in communities out to about 10 miles from the plant, and four remote air monitors are located out to 20 miles. The monitoring program and the locations of monitoring j stations are identified in the tables and figures of appendix A. The r' emote t 5

~

i stations are used as control or baseline stations.

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Results from the analysis of samples in the atmospheric pathway are presented in tables H-2 and H-3. Radioactivity levels identified in this reporting j

period are consistent with background and materials produced as a result of I

i fallout from previous nuclear weapons tests. There is no indication of an 1

increase in atmospheric radioactivity as a result of SQN.

l Sample Collection and Analysis 4

Air particulates are collected by continuously sampliag air at a flow rate of I

approximately 2 cubic feet per minute (cfm) through a 2-inch Hollingsworth and ,

l

Vose LB5211 glass fiber filter. The sampling system consists of a pump, a magnehelic gauge for measuring the drop in pressure across the system, and a i

dry gas meter. This allows an accurate determination of the volume of air passing through the filter. This system is housed in a building approximately 2 feet by 3 feet by 4 feet. The filter is contained in a sampling head l I I

i

~26- l i

I mounted on the outside of the monitor building. The filter is replaced every 7 days. Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 weeks composites of the f11ters from each location are analyzed by gamma spectroscopy. On a quarterly basis, all of the filters from one location are composited and analyzed for Sr-89,90.

Gaseous radioiodine is collected using a comunercially available cartridge i

containing TEDA-impregnated charcoal. This system is designed to collect iodine in both the elemental form and as organic compounds. The cartridge is located in the same sampling head as the air particulate filter and is downstream of the particulate filter. The cartridge is changed at the same i

I time as the particulate f11ter and samples the same volume of air. Each '

cartridge is analyzed for I-131. If activity above a specified limit is  !

detected, a complete gansna spectroscopy analysis is performed.

I a 1 1

i Rainwater is collected by use of a collection tray attached to the monitor i building. The collection tray is protected from debris by a screen cover. As water drains from the tray, it is collected in one of two 5-gallon containers inside the monitor building. A 1-gallon sample is removed from the container every 4 weeks. Any excess wr.ter is discarded. Rainwater samples are held to 1

be analyzed only if the air particulate samples indicate the presence of elevated activity levels or if fallout is expected. For example, rainwater samples were analyzed during the period of fallout following the accident at Che rnobyl . No rainwater samples from SQN were analyzed in this reporting l period.

During a recent review of calculational methods, an error was identified in the data base program used to calculate the total volume of air sampled in the monthly air filter composites. This error, which resulted from a change in the sampling procedure, affected only about half of the SQN air sampling locations. The result was a calculated volume approximately 40 percent lower than the actual value with a corresponding positive bias for the measured activity. All data reported herein have been calculated with the corrected program.

Data for 1986 and a part of 1985 were also biased positively as a result of this error. The results from all locations involved have been reviewed. The reported activity was all due to naturally occurring radionuclides except for fallout from the accident at the Chernobyl nuclear power station. Fallout from this event was detected for approximately 4 weeks in 1986. It was concluded that a revision to the 1985 and 1986 annual reports was not '

necessar; because a recalculation of the results would not affect the overall conclusions of the reports.

Results The results from the analysis of air particulate samples are summarized in table H-2. Gross beta activity in 1987 was consistent with levels reported in previous years. The average level at both indicator and control stations was 0.022 pci/m*. The annual averages of the gross beta activity in air particulate filters at these stations for the years 1971-1987 are presented in figure H-3.

Increased levels due to fallout from atmospheric nuclear weapons testing are eviden'., especially in 1971, 1977. 1978, and 1981. Evidence of a small increase resulting from the Chernobyl accident can also be seen in 1986. These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites.

Only natural radioactive materials were identified by the monthly gamma spectrial analysis of the air particulate samples. No fission or activation products were found at levels greater than the LLDs. Strontium was not identified in the quarterly composites.  !

i As shown in table H-3, iodine-131 was detected in three charcoal canister samples at levels slightly higher than the nominal LLD. Since the half life of I-131 is only about 8 days and the plant has not operated in over 2 years, this activity could not be from SQN.

1

TERRESTRIAL MONITORING Terrestrial monitoring is accomplished by collecting samples of environmental l media that may transport radioactive material from the atmosphere to humans.

l For example, radicactive material may be deposited on a vegetable garden and

! be ingested along with the vegetables or it may be deposited on pasture grass "

i where dairy cattle are grazing. When the cow ingests the radioactive material, some of it may be in the milk and consumed by humans who drink the f

milk. Therefore, samples of milk, vegetation, soil, and food crops are -

collected and analyzed to determine potential impacts from exposure to this pathway. The results from the analysis of these samples are shown in tables H-4 through H-12.

A land use survey is conducted annually to locate milk producing animals and gardens within a 5-mile radius of the plant. Only one dairy farm is located  ;

in this area; however, four farms with at least one milk producing animal have >

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been identified within 5 miles of the plant. The dairy and the farms are l i

considered indicator stations and routinely provide milk and/or vegetation l

samples. The results of the 1987 land use survey are presented in appendix G. i i

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Sample Collection and Analysis Milk samples are purchased every 2 weeks f rom the dairy f rom two of the f arms I within 5 miles of the plant and from at least one of three control dairies.

) These samples are placed on ice for transport to the radioanalytical i laboratory. A specific analysis for I-131 is performed on each sample and a l 1

! gamma spectroscopy analysis and Sr-89.90 analysis are performed every 4 weeks.

I

4 Samples of vegetation are collected every 4 weeks for I-131 analysis. The samples are collected from the same locations as milk samples and from the air monitorin;; stations. The samples are collected by cutting or breaking enough vegetation to provide between 100 and 200 grams of sample. Care is taken not to include any soll with the vegetation. The semple is placed in a container with 1650 ml of 0.5 N NaOH for transport back to the radioanalytical laboratory. A second sample of between 750 and 1000 grams is also collected from each location. After drying and grinding, this sample is analyzed by gamma spectroscopy. Once each quarter, the sample is ashed after the gamma analysis is completed and analyzed for Sr-89,90.

Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cutter" or an auger type sampler.

After drying and grinding, the sample is analyzed by gamma spectroscopy. When the gamma analysis is complete, the sample is ashed and analyzed for Sr-89,90.

Samples representative of food crops raised in the area near the plant are obtained from individual gardens, corner markets, or cooperatives. Types of foods may vary from year to year as a result of changes in the local vegetable Sardens. In 1987 samples of cabbage, corn, green beans, potatoes, and tomatoes were collected from local vegetable gardens. In addition, samples of j apples were also obtained from the area. The edible portion of each sample is prepared as if it were to be eaten and is analyzed by gama spectroscopy. 1 After drying, grinding, and ashing, the sample is analyzed for gross beta activity.

l 1

P Results The results from the analysis of milk samples are presented in table H-4. No ;

i radioactivity which could be attributed to SQN was identified. All I-131 results were less than the established nominal LLD of 0.2 pCi/ liter.

Cesium-137 was identified in three samples at levels slightly higher than the LLD. Strontium-90 from previous nuclear weapons tests was found in less than i

half of the samples. The average concentration reported from indicator I stations was 7.9 pCi/ liter. An average of 3.6 pCi/ liter was identified'in ,

l l samples from control stations. By far the predominent isotope reported in milk samples was the naturally occurring K-40. An average of approximately 1300 pCi/ liter of I-40 was identified in all milk samples.

As has been noted in this series of reports for previous years, the levels of '

r Sr-90 in milk samples from farms producing milk for private consumption only are up to six times the levels found in milk from commercial dairy farms.

Samples of feed and water supplied to the animals were analyzed in 1979 in an i r

effort to determine the source of the strontium. Analysis of dried hay l I

samples indicated levels of Sr-90 slightly higher than those encountered in l

routine vegetation samples. Analysia of pond water indicated no significant f

strontium activity.

I '

l This phenomenon was observed during the preoperational radiological monitoring near SQN and near the Bellefonte Nuclear Plant at farma where only one or two cows were being milked for private consumption of the milk. It is postulated that the feeding practices of these small farms differ from those of the  !

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larger dairy farmers to the extent that fallout from atmospheric nuclear weapons testing may be more concentrated in these instances. Similarly, Hansen, et al. (reference 4), reported an inverse relationship between the levels of Sr-90 in milk and the quality of fertilisation and land management.

Results from the analysis of vegetation samples (table H-5) were similar to those reported for milk. One sample had an I-131 value slightly higher than the nominal LLD. Average Cs-137 concentrations were 38.5 and 31.9 pCi/kg for indicator and control stations, respectively. Strontium-90 levels averaged 128 pCi/kg from indicator stations and 105 pC1/kg from control stations.

Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7.

The only fission or activation products identified in soil samples were Cs-137 and Sr-90. The maximum concentration of Cs-137 was 1.1 pCi/g. Sr-90 was identified in two samples with a maximum value of 0.5 pCi/g. These values are consistent with levels previously reported from fallout. Sr-89 was identified in one sample. With a half-life of approximately 60 days, this isotope cannot be present in the environment as a result of plant operations or previous nuclear weapons testing. The positive identification of Sr-89 is an artifact of the calculational process and the low concentrations the laboratory is attempting to detect. All other radionuclides reported were naturally occurring isotopes (table H-6).

All radionuclides reported in food samples were naturally occurring. The maximum K-40 value was 3,640 pCi/kg in potatoes. Cross beta concentrations l

1 for all indicator samples were consistent with the control values. Analysis I

of these samples indicated no contribution from plant activities. The results are reported in tables H-7 through H-12. '

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AQUATIC MONITORING Potential exposures from the liquid pathway can occur from drinking water, ingestion of edible fish and clams, or from direct radiation exposure from radioactive materials deposited in the river sediment. The aquatic monitoring program includes the collection of samples of river (reservoir) water, groundwater, drinking water supplies, fish, Asiatic clams, and bottom and shoreline sediment. Samples from the reservoir are collected both upstream and downstream from the plant, j l

Results from the analysis of aquatic samples are presented in tables H-13 through H-22. Radioactivity levels in water, fish, and clams were consistent with background and/or fallout levels previously reported. The presence of Co-60 and Cs-134 was identified in sediment samples; however, the projected exposure to the public from this medium is negligible.

Sample Collecti_on and Analysis Samples of surface water are collected from the Tennessee River using automatic sampling pumps from two downstream stations and one upstream station. A timer turns on the pump at least once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The line is flushed and a sample collected into a composite jug. A 1-gallon sample is removed from the composite jug at 4-week intervals and the remaining water in the jug is discarded. The composite sample is analyzed by ganna spectroscopy l and for gross beta activity. A quarterly composite sample is analyzed for Sr-89,90 and tritium.

l l

1 Semples are also collected by an automatic sampling pump at the first downstream drinking water intake. These samples are collected in the same manner as the surface water samples. These monthly samples are analyzed by gamma spectroscopy and for gross beta activity. At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source. These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity. A quarterly composite sample from each station is analyzed for Sr-89.90 and tritium. The sampic collected by the automatic pumping device is taken directly from the river at the intake structure. Since the sample at this point is raw water, not water processed through the water treatment plant, the control sample should also be unprocessed water. Therefore, the upstream surface water sample is also considered as a control sample for drinking water.

Groundwater is sampled from an onsite well and from a private well in an area unaffected by SQN. The samples are composited by location quarterly and analyzed by gamma spectroscopy and for gross beta activity and tritium content.

Samples of comercial and game fish species are collected semiannually from each of three reservoirs the reservoir on which the plant is located (Chihekamauga Reservoir), the upstream reservoir (Watts Bar Reservoir), and l l

l the downstream reservoir (Nickajack Reservoir). The samples are collected using a combination of netting techniques and electrofishing. Most of the 1

l fish are filleted, but one group is processed whole for analysis. After l drying and grinding, the samples are analyzed by gamma spectroscopy. When the 1

l

l l

l gamma analysis is completed, the sample is ashed and analyzed for gross beta i 1

1 activity.

l Bottom and shoreline sediment is collected semiannually from selected TRM l locations using a dredging apparatus. The samples are dried and ground and analyzed by gamma spectroscopy. After this analysis is complete, the samples are ashed and analyzed for Sr-89,90. l Sarples of Asiat ic clams are collected semiannually from three of the the same locations as the bottom sediment. The clams are usually collected in the i dredging process with the sediment. However, at times the clams are difficult i i

to find and divers must be used. Enough clams are collected to produce approximately 50 grams of wet flesh. The flesh is separated from the shells, and the dried flesh samples are analyzed by gamma spectroscopy.

Results Sr-89 was identified in four water samples and tritium was found in one sample. Gross beta activity was present in most samples. As noted earlier, the positive identification of Sr-89 in environmental samples is an artifact i l

of the calculational process. All other values were consistent with previously reported levels f rom fallout. A trend plot of the gross beta activity in surface water samples from 1971 through 1987 is presented in figure H-4. A summary table of the results is shown in table H-13.

No fission er activation products were identified in drinking water samples.

j Average gross beta activity was 2.7 pCi/ liter at the downstream stations and

J s

2.9 pCi/ liter at the control stations. The results are shown'in table H-14 '

and a trend plot of the gross beta activity in drinking water from 1971 to the present is presented in figure H-5.  !

E P

Concentrations of fission and activation products in ground water were all below the LLDs. Only naturally occurring radionuclides were identified in these samples. The average gross beta concentration in samples from the ,

onsite well was 5.8 pC1/11ter, while the average from the offsite well was 3.2 pCi/ liter. The results are presented in table H-15. i Cesium-137 was identified in seven fish samples. The downstream samples I t

i contained a maximum of 0.13 pCi/g, while the upstream sample had a maximum of l O.24 pCi/g. The only other radioisotope found in fish was the naturally t r 3

occurring K-40. The concentrations of K-40 ranged from 4.0 pC1/g to 16.9 l pCi/g. These results, which are summarized in tables H-16, H-17. H-18, and [

H-19, indicate that the Cs-137 activity is probably a result of fallout or l l other upstream effluents rather than activities at SQN.

I

, i i

Radionuclides of the types produced by nuclear power plant operations were j identified in sediment samples. The materials identified were Cs-137, Co-60, 1

l and Cs-134. In bottom sediment samples the average levels of Cs-137 were 1.24 pC1/g in downstream samples and 1.17 pCi/g upstream. In shoreline sediment, Cs-137 levels were 0.06 and 0.09 pCi/g, respectively, in downstream and upstream samples. These values are consistent with previously identified f allout levels; therefore, they are probably not a result of SQN operations.

r In bottom sediment, Co-60 concentrations in downstream samples averaged 0.30 l t

pCi/g, while concentrations upstream averaged 0.09 pCi/g. The maximum  !

L concentrations were 0.60 and 0.11 pCi/g, respectively. Cesium-134 i concentrations in upstream samples were all below the LLD. Levels in downstream samples averaged 0.04 pC1/g, with a maximum of 0.04 pCi/g. A l i

realistic assessment of the impact to the general public from this activity >

produces a negligible dose equivalent. Results from the analysis of bottom r sediment samples are shown in table H-20. I Co-60 was identified in only one shoreline sediment sample. A concentration t

of 0.02 pCi/g was found in a downstream station. This is less than the Co-60 levels found in upstream bottom sediment samples, indicating no impact from

, i j SQN. Results from the analysis of shoreline sediment samples are shown in table H-21.

l I

Co-60 was also identified in one clam flesh sample. A concentration of 1.0 l i'

pCi/g was found at tRM 483.4. The dose projected from the ingestion of clams with this concentration is 0.2 mrem / year. However, clams are not known to be i

consumed; therefore, no dose will be received by humans through this pathway.  !

The results from the analysis of clam samples are presented in table H-22.

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ASSESSMENT AND EVALUATION Potential doses to the public are estimated from measured effluents using computer models. These models were developed by TVA and are based on guidance provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living in the vicinity of the plant. The doses calculated are a representation of the dose to a "maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates) are maximum expected values which will tend to overestimate the dose to this "maximum" person. In reality, the expected dose to actual individuals is lower.

The area around the plant is analyzed to determine the pathways through which the public may receive an exposure. As indicated in figure 2, the two major ways by which radioactivity is introduced into the environment are through liquid and gaseous effluents.

For liquid effluents, the public can be exposed to radiation from three f sources: drinking water from the Tennessee River, eating fish caught in the Tennessee River, and direct exposure to radioactive material due to activities on the banks of the river (recreational activities). Data used to determine these doses are based on guidance given by tho NRC for maximum ingestion rates, exposure times, and distribution of the material in the river.

Whenever possible, data used in the dose calculation are based on specific conditions for the SQN area.

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For gaseous effluents, the public can be exposed to radiation from several sources: direct radiation from the radioactivity in the air, direct radiation l

from radioactivity deposited on the ground, inhalation of radioactivity in the air, ingestion of vegetation which contains radioactivity deposited from the atmosphere, and ingestion of milk or meat from animals which consumed vegetation containing deposited radioactivity. The concentrations of l

radioactivity in the air and the soil are estimated by computer models which use the actual meteorological conditions to determine the distribution of the effluents in the atmosphere. Again, as many of the parameters as possible are based on actual site specific data.

Results F

j The estimated doses to the maximum exposed individual due to radioactivity released from SQN in 1987 are presented in table 2. These estimates were made using the measured concentrations from the liquid and gaseous effluent monitors. Also shown are the regulatory limits for these doses and a comparison between the calculated dose and the corresponding limit. A more i

l complete description of the effluents released from SQN and the corresponding I

doses projected from these effluents can be found in the SQN ennual radiological impact reports.

j 1

As indicated, the estimated increase in radiation dose equivalent to the general public resulting from the operation of SQN is trivial when compared to the dose from natural background radiation.

l a

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The results from each sample are compared with the concentrations from the  !

corresponding cone;.o1 stations and appropriate preoperational and background data-to determine influences from the plant. During this report period, Co-60 Cs-134, and Cs-137 were seen in aquatic media. Cs-137 in sediment is  !

! i l consistent with fallout levels identified in samples both upstream and l downstream from the plant. Co-60 and Cs-134 were identified in sediment I

r samples downstream from the plant in concentrations which would producw no- f

! measurable increase in the dose to the general public. No increases of l

radioactivity attributable to SQN have been seen in water samples.

f I

l Dose estimates were made from concentrations of radioactivity found in samples  !

of environmental media. Media evaluated include, but are not limited to, sir, _ f milk, food products, drinking water, and fish. Inhalation and ingestion doses  !

j estimated for persons at the indicator locations were essentially identical to f

those determined for persons at control stations. Greater than 95 percent of  !

l j those doses were contributed by the naturally occurring radionuclide K-40 and i

by Sr-90 and Cs-137, which are long-lived radioisotopes found in fallout from nuclear weapons testing.

l i Conclusions l j

i It is concluded from the above analysis of the environmental sampling results t

} and from the trend plots presented in appendix H that the exposure to members l of the general public which may have been attributable to SQN is negligible.

f The radioactivity reported herein is primarily the result of fallout or natural background radiation. Any activity which may be present as a result I

e i i

l j  !

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of plant operations does not represent a significant contribution to the exposure of members of the public.

The maximum calculated whole body dose equivalent from measured liquid effluents as presented in table 2 is 0.14 mrem / year, or 2.3 percent of the ,

limit. The maximum organ dose equivalent.from gaseous effluents is 0.024 I ares / year. This represents approximately 0.08 percent of the Technical Specification limit.

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Table 1 MAXIMUM PERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE MPC In Water In Air DCi/l* DCi/m3 8 Alpha 30 Gross beta 3,000 100 H-3 3,000,000 200,000 Cs-137 20,000 500 Ru-103,-106 10,000 200 '

Ce-144 10,000 200 Zr Nb-95 60,000 1,000 i

Ba-140 - La-140 20,000 1,000 I-131 300 100 Zn-65 100,000 2,000 Mn-54 100,000 1,000 Co-60 30,000 300 Sr-89 3,000 300 Sr-90 300 30 Cr-51 2,000,000 80,000 Cs-134 9,000 400 l

Co-58 90,000 2,000 '

• 1 pCi = 3.7 x 10-a Bq.

Source: 10 CFR, Part 20, Appendix B, Table II.

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l Table 2 Maximum Dose due to Radioactive Effluent Releases Sequoyah Nuclear Plant 1987 mrem / year i

i i Liquid Effluents l

l 1987 NRC Percent of EPA Percent of Type Dose Limit NRC Limit Limit EPA Limit Total Body 0.137 6 2.3 25 0.5 Any Organ 0.158 20 0.8 25 0.6 Gaseous Effluents 1987 NRC Percent of EPA Percent of Type Dose Limit NRC Limit Limit EPA Limit Noble Gas

. (Gamma) 0.000002 20 0.00001 25 0.000008 Noble Gas (Beta) 0.00035 40 0.00088 25 0.0014 Any Organ 0.024 30 0.08 25 0.096

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REFERENCES

1. Merril Eisenbud, Environmental Radioactivity. Academic Press Inc., New York, NY, 1973.

2. National Council on Radiation Protection and Measurements Report No. 93, "Ionizing Radiation Exposure of the Population of the United States," l September 1987.

3. United States Nuclear Regulatory Commission, Regulatory Guide 8.29, i "Instruction Concerning Risks From Occupational Radiation Exposure " July 1981.

4. Hansen, W. G., Campbell, J. E., Fooks, J. H., Mitchell, H. C., and Eller, ,

C. H., Farmina Practices and Concentrations of Emission Products in Milk, U.S. Department of Health, Education, and Welfarel Public Health Service Publication No. 999-R-6, May 1964.

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m. Water 5

=gd l %c '

Fish 1

l Vegetation Uptake From Soil

l APPENDIX A l

l ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM AND SAMPLING LOCATIONS r

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Table A-1 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program *

r. tor, pm, w , w far * - lg Sampiing and

• - le tnratians* Callertien Fr.ausarv Tune and Fra==*arv af Analusis

1. AIR 90RNE

a. Particulates 4 samples from locations (in Continuous sampler operation Analyze for gross beta dif ferent sectors) at or near the with sample collection once radioactivity greater than er site boundary (LM 2, 3, 4 and 5) per 7 days (more frequently equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following if required by dust loading) filter change. Perferin gamma isotopic analysis on each sample if gross beta is greater than 10 times yearly mean of control sample.

Composite at least once per 31 days (by location for gmaa scan).

4 samples from comununities

' appreminately 6-10 miles distance from the plant E (PM 2, 3, 8 and 9) 4 samples from control locations greater than 10 miles from the plant (RM 1, 2, 2, and 4)

6. Radiciodine Samples from same location as Continueos sampler operation I-131 at least once per 7 days air particulates with filter collection once per 7 days

c. Soil Samples f rom same locations as Once per year Gamuna scan, Sr-49, Sr-90, air particulates once each year

d. Rainwater Same locations as air particulate Composite sample at least Analyzed for gamuna neclides once per 31 days only if radioactivity in other media indicates the presence of increased levels of fallout

2. DIRECT RADIATION 2 or more dosimeters (TLDs) Once per 92 days Gama dose at least once per placed at II of the air particulate sampling stations 92 days (L W3, L N4, LM-5, PS 2, PN 3 P5 8, P5 9. RS ), RS2, R A 3, and RM-4 2 or more desimeters (TLDs) placed at each of at least 30 other locations

_d

Table A-1 l SEQUOYAH 94JCLEAR PLANT En.ironetal Radiological Monitoring Program" l Sampiing and r==acure pa h n mad /or < -l e < - 1 ,inratians* Callection freauency Tune and f r-- v af Anal usi s

3. WATER 90ResE

a. Surface TRM 497.0 Collected by automatic Gamma scan of each composite TRM 483.4 seguential-type sampler

• with sample. Composite for Sr-89 TRM 473.2 cosposite samples collected Sr-90, and tritium analysis at over a period of less than or least once per 92 days.

equal to 32 cays

b. Ground I sample adjacent to plant sample collected by automatic Composited for gross beta, gasen.

(well #6) seguential-type sampler" with scan, and tritium analysis at composite sample collected least once per 92 days over a period of less than or egual to 31 days I sample from ground water At ? cast once per 92 days Gross beta. gamma scan, and source upgradient (Farm HW) tritium analysis at least once ,.

v 8 per 92 days Y c. Drinking i sample at the first potable Collected by automatic Gross beta and gamuna scan of surface water supply downstream seguential-type sampler

• each composite sample.

from the plant (TRM 473.0) with composite sample collected Campesite for tritium. Sr-49, over a period of less than or Sr-90, at least once per 92 equal to 31 days days.

1 sample at the nemt 2 downstream Grap sample once per 31 days potable surface water suppliers (greater than 10 miles downstream)

(TRM 470.5 and 465.3) 2 samples at control locations Samples collected i>y sequential-(TRM 497.0 and TRM 503.8) type sampler" with composite sample collected over a period of less than or equal to 31 days l

d. Sediment TRM 4%.5 At least once per 184 days Gamina scan of each sample l TRM 483.4 1

TRM 480.8 TRM 472.8

e. Shoreline sediment TRM 485 At least once per 184 days Gasmia scan of each sample TRM 478 l

TRM 477 l

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Table A-1 SEQUOYAH NUCLEAR ptANT Environmental Radiological Monitoring Program

• Sampllag and r= mature pae w ma/ar '-le e - le t_acatians* Callection Freauenew Yume and fr===maru af h 1wsis 4 INGESTION

a. Milk I sample from milk producing At 1est once per 15 days Gamma isotopic and I-131 animals in each of 1-3 areas analysis of each sample.

indicated by the cow census where Sr-89. Sr-90 ence per doses are calculated to be guarter highest. If samples are not available from a milk animal location. doses to that area will .

be estimated by projecting the doses from concentrations detected in milk from other sectors or by sampiing wegetation where milk is not available.

At least 1 sample from a control d location Y b. Fish I sample each for Nickajath. At lest once per 184 days. Gamma scan c,e edible portion Chickamauga. and h tts sar One sample of each of the Reservoi rs fellowing species:

Channel Catfish Crappie Smallmouth seffalo

c. Invertebrates TRM 4%.5 At least once per 184 days Gammia scan on edible portion (Asiatic Class) TRM 483.4 TRM 480.8

d. Feed Products 1 sample each of principal feed At least once per 365 days at Gamma scan en edible portion products grown at private time of harvest. The types of gardens and/or farms in the foods available for sampling will immediate vicinity of the plant. wary. Following is a list of typical feeds which may be available:

Cabbage and/or lettuce Corn Green Beans Potatoes Tematoes

m _m __ __ _ _ _ _ _ _

Taule A-1 SEQUOYAH SEJCLEAR PLANT Environmental Radiological Monitoring program

• Sampling and

• - in tacatinan* Callectian Freauencv Twee and Fr-- - w af ^~ fusis F_===-re Pa h n w /ar t===le I sample f rom up to three locations At lest once per 31 days Gamma scan at least once per 31

v. Vegitation days. Sr-89. Sr-98 analysis of milk-producing animals shere a at least once per 92 days.

sample of milk is not available i

and at each air particulate station l

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a. The sampling program outlined in this table is that ishich esas in effect at the end of 1987.

b. Sample locations are described in tables A-2 and A-3 and shown in Figures A-1. A-2. A-3.

c. Samples shall be collected by collecting an aliguet at intervais not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Table A-2 SEQUOYAM NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations l

Map Approximate Indicator (I)

Location Distance or Samples  :

Number Station Sector (Miles) . Control (C) Collected" 2 IN-2 N 0.8 I AP.CF.R.S V 4

3 LM-3 SSW 1.2 I AP.CF.R.S.V 4 LN-4 NE 1.5 I AP.CF R.S.V 5 IR-5 NNE 1.8 I AP.CF,R.S,V 7 PM-2 SW 3.8 I AP,CF,R,S,V 8 PM-3 W 5.6 I AP CF.R.S.V 9 PM-8 SSW 8.7 I AP.CF R.S,V 10 PM-9 WSW 2.6 I AP,CF,R.S.V 11 RM-1 SW 16.7 C AP.CF R.S.V 12 RM-2 NNE 17.8 C AP CF,R S V 13 itM-3 ESE 11.3 C AP.CF,R.S V 14 RM-4 WNW 18.9 C AP CF.R.S,V 15 Farm B NE 43.0 C M.V 16 Farm C NE 16.0 C M.V l 17 Farm S NNE 12.0 C M,V i 18 Farm J WNW 1.1 I M,V 19 Farm HW NW 1.2 I M,V,W*

20 Farm EM N 2.6 I V i 21 Farm Br SSW 2.2 I V 22 Farm Le* S 3.5 I MV 23 Farm G' E 1.7 I V 24 Well No. 6 NNE 0.15 I W 31 TRM' 473.0 --

11.5" I PW (C.F. Industries) 32 TRM 470.5 -

14.0' I PW (E.I. DuPont) '

33 TRN 465.3 -

19.2* I PW (Chattanooga)  ;

34 TRM 497.0 -

12.5' c' SW 35 TRM 503.8 --

19.3' C PW t (Dayton) 36 TRM 496.5 -

12.0' C CL.SD 37 TRM 485.0 -

0.5* C SS j 38 T1LM 483.4 -

1.1* I CL.SD.SW i 39 11tM 480.8 -

3.7' I CL.SD l 40 TRM 477.0 -

7.5* I SS l l

11.3 8 41 TRM 473.2 --

I SW 42 TRM 472.8 -

11.7* I SD ,

44 TRM 478.8 -

6.5" I SS i I

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Table A-2 4

SEQUOYAH NUCLEAR PLANT 1

! Environmental Radiological Monitoring Program ,

i Sampling Locations  !

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Map Approximate Indicator (I)

Location Distance or Samples l Number _ Station Sector (Miles) __ Cont rol(C) Collected' 45 TRM 425-471 -- -- 1 F

(Nickajack ,

Reservoir) 46 TRM 471-530 -- -- I F (Chickamauga ,

l Reservoir) '

47 TRM 530-602 -- --

C F i 4

(Watts Bar '

I Reservoir) l 48 Farm H NZ 4.2 I M,V t

J a. Sample Codes AP = Air particulate filter CF = Charcoal filter

. CL = Class i F = Fish '

l M = Milk

$ PW = Public water R = Rainwater ,

S = Soil l SD = Sediment i SS = Shoreline sediment I

SW = Surface water '

I V = Vegetation I

W = Well water

b. A control for well water.

c. Milk producing animal not identified in 1986 land use survey - vegetation sample collected until locations deleted from the sampling program April 28, 1987.

d. Distance from plant discharge (TRM 484.5) e TRM = Tennessee River Mile.

f. Surface water sample also 2 sed as a control for public water.

l l _ - _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ __ _________-____ _ _ _ - _ _ _ - _ _ _ _ _ _ _ - - _ _ - -

Table A-3 SEQUOYAH NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) Locations Approximate Onsite (On)*

Map Distance or Location Number Station Sector (Miles) Offsite (Off)

! 3 SSW-1A SSW 1.2 On 4 NE-1A NE 1.5 On 5 NNE-1 NNE 1.8 On 7 SW-2 SW 3.8 Off l 8 W-3 W 5.6 off ,

I 9 SSW-3 SSW 8.7 Off 1 10 WSW-2A WSW 2.6 Off 11 SW-3 SW 16.7 Off 12 NNE-4 NNE 17.8 Off 13 ESE-3 ESE 11.3 Off 14 WNW-3 WNW 18.9 Off 49 N-1 N 0.6 On 50 N-2 N 2.1 Off 51 N-3 N 5.2 Off  ;

52 N-4 N 10.0 Off  !

53 NNE-2 NNE 4.5 Off 54 NNE-3 NNE 12.1 Off  ;

55 NE-1 NE 2.4 Off I 56 NE-2 NE 4.1 Off l 57 ENE-1 ENE 0.4 On 58 ENE-2 ENE 5.1 Off l 59 E-1 E 1.2 On 60 E-2 E 5.2 Off i 61 ESE-A ESE 0.4 On 62 ESE-1 ESE 1.2 On 63 ESE-2 ESE 4.9 Off 64 SE-A SE 0.4 On 65 SE-B SE 0.4 On 66 SE-1 SE 1.4 On l 67 SE-2 SE 1.9 On l 68 SE-4 SE 5.2 Off l 69 SSE-1 SSE 1.6 On l 70 SSE-2 SSE 4.6 Off 71 S-1 S 1.5 On 72 S-2 S 4.7 Off 73 SSW-1 SSW 0.6 On 74 SSW-2 SSW 4.0 Off 75 SW-1 SW 0.9 On 76 WSW-1 WSW 0.9 On 77 WSW-2 WSW 2.5 Off

Table A-3 SEQUOYAH NUCLEAR PLANT' Thermoluminescent Dosimeter (TLD) Locations Approximate Onsite (On)*

Map Distance or Location Number Station Sector (Miles) Offsite (Off) 78 WSW-3 WSW 5.7 Off 79 WSW-4 WSW 7.8 Off 80 WSW-5 WSW 10.1 Off 81 W-1 W 0.8 On 82 W-2 W 4.3 Off 83 WNW-1 WNW 0.4 On 84 WNW-2 WNW 5.3 Off 85 NW-1 NW 0.4 On 86 NW-2 NW 5.2 Off 87 NNW-1 NNW 0.6 On 88 NNW-2 NNW 1.7 On 89 NNW-3 NNW 5.3 Off l

a. TLDs designated onsite are those located 2 miles or less from the plant.

TLDs designated offsite are those located more than 2 miles from the plant.

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Figure A-1 1

Environmental Radiological Sampling Locations Within 1 Mile of Plant 48 75 7, 11.as NNW NNE 32e.2s 33.7s I

NW / 2 NE 303.7s 7 s e.2 s WNW

\*a ENE 85 \* '

281.2s

( f\ ,,

/ 78.7s

/

'- . s.% N'h i .

~

SEQUOYAH W-n

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= II 6

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v P/ i s sg 2sa.7s 5 4

WSW ESE

[s 23e.25 6

5 [ 123.73 BB SW sg6 gW SE

(# g6s 213.7s

$gg 14 e.2 s SSW SSE 191.2s 1 e a.7 s 3

Scale Mlle 58

Figuro A-2 Environmental Radiological Sampling Locations From 1 to 5 Miles From The Plant 348.75 N 11.25 NNW NNE g

326.25 ( 33.75 NW NE l +p 303.75 '

48 g 56 l

WNW 5 e55 ENE 5, ,

s 8*

281.25 - -

' 4 ge 78.75

$ 0g 3

82 19 jbc39 l W- 18 ' 59 -E 10 J 2 258.75 77 66 101.25

/ y, ee 63 l WSW ESE 236.25 7 /e 39' 1

e22 SW SE

'46 .\

• 70 213.75 7,2 146.25 SSW /

SSE 191.25 S 188.76 SCALE 6 1 2 MILES 59

Figuro A-3 Environmental Radiological Sampling Locations Greater Than 5 Miles From The Plant 348.75 Y .a. 11.25 NNW CROS$VILLE NNE 326.25 33.75 0

l Nw ,,,

PRIN CIT Y McM2NNVILLE I 303.75 *

-/ 15 56.25 f, SWEET *AT R DAYTON #

16

• 3 'fi 281.25 ,

' '*t ' 78.75 14 54 E owAs 8 58 TJ - "***=e= s aa 60 -E SE'WANEE 1 EVELAND j k *6 ef g4EE s.

^/ J

$9 101.25

.y l f CH A TT ANOOG A l wsw f Est

/ '

/

326.25 123.75

,g,

\ sw LAFAYETTE sE t

213.75 j' b [

146.25 ssw ssE 191.25 a 168.75 SCALE

~

O ~ ~ 10 10- 20 25 MILES 60

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i APPENDIX B 1987 PROGRAM MODIFICATIONS l

Table B-1 l

l SEQUOYAH NUCLEAR PLANT l

Environmental Radiological Monitoring Program Modifications 1987 Date Station Modification 4/28/87 Farm Le Milk producing animals not identified in l & 1986 land use survey-vegetation samples Farm G collected until 4/28/87 when locations were removed from the sampling schedule l

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APPENDIX C EXCEPTIONS TO THE MONITORING PROGRAM IN 1987 i

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i Appendix C Exceptions to the Monitoring Program in 1987 1

During this reporting period, a small number of the sampling requirements were not met. These exceptions usually involved the malfunction of automatic sampling equipment or the unavailability of samples. A number

of milk samples which were unavailable were from farms with only 1 or 2 1

milk producing animals. The following table is a summary of the exceptions to the monitoring program in 1987.

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Table C-1 1

i SEQUOYAH NUCLEAR PLANT l Environmental Radiological Monitoring Program Exceptions Date S_tation Remarks.

1/27/87 PM-2 Air particulate and charcoal filters not collected-sampling equipment failure 3/31/87 Farm J Milk sample not available for collection Farm Br Vegetation sample-insufficient volume for analysis 4/21/87 PM-2 Air particulate and charcoal filters not collected-sampling equipment failure 7/7/87 Farm B Milk sample not available for collection Dayton Public water sample missed-equipment malfunction 7/21/87 Farm EM Vegetation sample inadvertently destroyed prior to analysis for I-131 8/1/87 Watts Bar Fish sample (Cre.ppie) lost in transit Reservoir to the laboratory 9/1/87 Farm RW Milk sample not available for collection 9/8/87 RM-4 Air particulate and charcoal filters not collected-sampling equipment malfunction 9/15/87 Farm HW Milk sample not available for collection RM-3 Vegetation sample inadvertently destroyed prior to analysis for I-131 9/29/87 Farm HW Milk sample not available for collection ,

l 10/20/87 RM-2 Air particulate filters lost in transit to the laboratory 12/9/87 RM-4 Air particulate and charcoal filters not collected-sampling equipment malfunction 12/15/87 RM-2 Vegetation sample inadvertently destroyed prior to analysis for I-131

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APPENDIX D I

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l ANALYTICAL PROCEDURES 1

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l APPENDIX D l

Analytical Procedures I

All analyses are performed by the radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals. All analysis procedures are based on accepted methods. A summary of the analysis techniques and methodology follows.

The gross beta measurements are made with an automatic low background counting system. Normal counting times are 50 minutes. Water samples are prepared by evaporating 500 ml of samples to near dryness, transfering to a stainless steel planchet and completing the evaporation process. For solid samples, a specified amount of the sample is packed into a deep stainless steel planchet. Air particulate filters are counted directly in a shallow planchet.

The specific analysis of I-131 in milk, water, or vegetation samples is performed by first isolating and purifying the iodine by radiochemical '

separation and then counting the final precipitate on a beta-gamma coincidence counting system. The normal count time is 100 minutes. With the beta-gamma coincidence counting system, background counts are virtually eliminated and extremely low levels of detection can be obtained.

After a radiochemical separation, samples analyzed for Sr-89,90 are l

i counted on a low background beta counting system. The sample is counted l

a second time after a 7-day ingrowth period. From the two counts the l

Sr-89 and Sr-90 concentrations can be determined.

Water samples are analyzed for tritium content by first distilling a l portion of the sample and then counting by liquid scintillation. A consnerically available scintillation cocktail is used.

?

Gamma analyses are performed in various counting geometries depending on the sample type and volume. All gamma counts are obtained with germanium type detectors interfaced with a computer based mutlichannel analyzer system. Spectral data reduction is performed by the computer program HYPERMET.

The gaseous radioiodine analyses are performed with well-type NaI detectors interfaced with a single channel analyzer. The system is calibrated to measure I-131. If activity above a specified limit is detected, the sample is analyzed by gamma spectroscopy.

All of the necessary efficiency values, weight-efficiency curves, and geometry tables are established and maintained on each detector and counting system. A series of daily and periodic quality control checks are performed to monitor counting instrumentation. System logbooks and control charts are used to document the results of the quality control checks.

APPENDIX E NOMINAL LOWER LIMITS OF DETECTION (LLD) l l

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_ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ __ _ _ __. ____________--l

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Appendix E Nominal Lower Limits of Detection' Sensitive radiation detection devices can give a signal or reading even when no radioactivity is present in a sample being analyzed. This signal may come f rom trace amounts et radioactivity in the components of the device, from cosmic rays, from naturally occurring radon gas, or from l machine noise. Thus, there is always some sort of signal on these sensitive devices. The signal registered when no activity is present in the sample is called the background.

The point at which the signal is determined to represent radioactivity in the sample is called the critical level. This point is based on statistical analysis of the background readings from any particular device. However, any sample measured over and over in the same device will give different readingst some higher than others. The sample should have some well-defined average reading, but any individual reading will vary from that average. In order to determine the activity present in a sample that will produce a reading above the critical level, additional statistical analysis of the background readings is required. The hypothetical activity calculated from this analysis is called the lower limit of detection (LLD). A listing of typical LLD values that a ,

laboratory publishes is a guide to the sensitivity of the analytical measurements performed by the laboratory.

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Every time an activity is calculated from a sample, the machine background must be subtracted from the sample signal. For the very low l

1evels encountered in environmental monitoring, the sample signals are 1

often very close to the background. The measuring equipment is being used at the limit of its capability. For a sample with no measureable

! activity, which often happens, about half the time its signal should fall below the average machine background and half the time it should be above the background. If a signal above the background is present, the calculated activity is compared to the calculated LLD to determine if there is really activity present or if the number is an artifact of the way radioactivity is measured.

A number of factors influence the LLD, including sample size, count time, counting efficiency, chemical processes, radioactive decay factors, and interfering isotopes encountered in the sample. The most likely values for these factors have been evaluated for the various analyses performed '

in the environmental monitoring program. The nominal LLDs calculated from these values are presented in the following table.

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Table E-1 Nominal LLD Values A. Radiochemical Procedures Charcoal Sediment Air Filters Filters Water Milk Fish Flesh Whole Fish Food Crops and Soil (pCi/m') (pCi/m') (pCi/L) (pCi/L) (pCi/q dry) (pCl/q dry) (DCi/kg wet) (pCi/q dry Gross Alpha 0.0007 1.5 Gross Beta 0.002 1.7 9 Tritium 250 Iodine-131 .020 1.0 0.2 Strontium-89 0.0006 3.0 2.5 0.3 0.7 1.0 Strontium-90 0.00025 1.4 2.0 0.04 0.09 0.3 Gum Paper Het Vegetation Clam Flesh Heat (mci /km')_ (pCi/kg Het) (pCi/q Dry) (pC1/kg Het)

Gross Beta 0.01 0.2 15 Iodine-131 4 i Strontium-89 140 Strontium-90 60 1-.c

Table E-1 Nominal LLD Values B. Gamma Analyses (GeLi)

Air Water Vegetation Wet Soil and Clan Flesh Particulates and Milk and Grain Foods. Tomatoes Meat and Ve9etation 5sdiment Fish and Plankton Clamshells Potatoes, etc. Poultry oCi/m3 oCi/L oCi/a_ dry oCi/ka. wet oCi/a_ dry oCi/a_ dry oC1/a_ dry oCi/a_ dew oCi/ka wet oCi/ka_ wet

Ce .005 10 .07 28 .02 .07 .15 .02

'**Ce .01 33 .25 100 .06 .25 10 25

Cr .02 .50 .06 33 50 45 .45 180 .10 .45 .94

I .005 .10 45 90 10 .09 36 .02 .09 .18 .02

Ru .005 5 .05 20 .01 .05 .11 10 20

Ru .02 40 .48 190 .09 .48 .95

.01 5 15

*Cs 005 5 .07

.09 40 95 28 .01 .07 .11

Cs .005 5 .06 24 .01 .06 .10

.01 5 15 "Zr .005 .01 5 15 10 .11 44 .02 .11 .19 .02

Nb 005 5 .06 24 .01 .06 10 25

**Co .005 .11 .01 5 15 5 .05 20 .01 .05 .10 N "Mn .005 5 .01 5 15

.05 20 .01 .05 .10 .01 Y ****Zn 005 10 .11 44 .01 .11 .21 .01 10 5 15 Co 005 5 .07 28 .01 25

• • K .07 .11 .01 5

.04 150 1.00 400 .20 1.00 15

' "8a .01 25 2.00 .20 150 300

.23 92 .05 .23 .47 .05

• • • La .005 8 .11 44 .02 .11 25 50 "Fe 005 .17 .02 8 20 l 5 .10 40 .01 .10

'Be .02 45

.33 .01 5 15

.50 200 .10 .50 .90 .10

Pb 005 20 .10 40 45 100

*Pb .02 .10 .25 .02 20 005 20 .20 80 .02 40

*8i 005

.20 .25 .02 20 40 20 .12 48 .04 .12 .25 .04 20 40 eseense l-l _

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APPENDIX F QUALITY ASSURANCE / QUALITY CONTROL PROGRAM

Appendix F Quality Assurance / Quality Control Program A thorough quality assurance program is employed by the laboratory to ensure that the environmental monitoring data are reliable. This program includes the use of written, approved procedures in performing the work, a nonconformance and corrective action tracking system, systematic internal audits, a complete training and retraining system, audits by various external organizations, and a laboratory quality control program.

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The quality control program employed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as intended. The program includes equipment checks and the analysis of special samples along with routine samples.  !

Radiation detection devices are complex and can be tested in a number of ways. There are two primary tests which are performed on all devices.

In the first type, the device is operated without a sample on the detector to determine the background count rate. The background counts are usually low values and are due to machine noise, cosmic rays, or trace amounts of radioactivity in the materials used to construct the detector. Charts of background counts are kept and monitored to ensure that no unusually high or low values are encountered.

In the second test, the device is operated with a known amount of radioactivity present. The number of counts registered from such a

I radioactive standard should be very reproducible. These reproduciblity

! checks are also monitored to ensure that they are neither higher nor 1

lower than expected. When counts from either test fall outside the expected range, the device is inspected for malfunction or contamination. It is not placed into service until it is operating properly.

In addition to these two general checks, other quality control checks are performed on the variety of detectors used in the laboratory. The exact nature of these checks depends on the type of device and the method it uses to detect radiation or store the information obtained.

1 Quality control samples of a variety of types are used by the laboratorp to answer questions about the performance of the different portions of the analytical process. These quality control samples may be blanks,

, replicate samples, blind samples, or cross-checks.

l Blanks are samples which contain no measureable radioactivity or no

{

activity of the type being measured. Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference from isotopes other than the one being measured.

Replicate samples are generated at random by the same computer program which schedules the collection of the routine samples. For example, if the routine program calls for four milk samples every week, on a random i t-i basis each farm might provide an additional sample several times a year.

These duplicate samples are analyzed along with the other routine samples. They provide information about the variability of radioactive content in the various sample media.

There is another kind of replicate sample. From time to time, if enough sample is available for a particular analysis, the laboratory analyst can split it into two portions. Such a sample can provide information about the variability of the analytical process since two identical portions of material are analyzed side by side.

Analytical knowns are another category of quality control sample. A known amount of radioactivity is added to a sample medium by the quality control staf f or by the analysts themselves. The analysts are told the radioactive content of the sample. Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run.

In this way, the analysts have immediate knowledge of the quality of the measurenent process. A portion of these samples are also blanks.

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Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples.

The analyst does not know they contain radioactivity. Since the bulk of the ordinary workload of the environmental laboratory contains no measureable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the laboratory or they can be used to test the data review process. If an analysis 4

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i routinely generates numerouc zeroes for a particular isotope, the presence of the isotope should come to the attention of the laboratory supervisor in the review process. Blind spikes test this process since

they contain radioactivity at levels high enough to be detected.

l Furthermore, the activity can be put into such samples at the extreme limit of detection to determine whether or not the laboratory can find any unusual radioactivity whatsoever.

At present, 5 percent of the laboratory workload is in the category of internal cross-checks. These samples have a known amount of radioactivity added and are presented to the analysts labeled as -

cross-check samples. This means that the quality control staff knows the radioactive content or "right answer" but the analysts do not. They are ,

aware they are being tested. Such samples test the best performance of i I

i the laboratory by determining if the analysts can find the "right answer." These samples provide information about the accuracy of the measurement process. Further information is available about the variability of the process if multiple analyses are requested on the same sample. Cross-checks can also tell if there is a difference in l performance between two analysts. Like blind spikes or analytical knowns, these samples can also be spiked with low levels of activity to test detection limits.

A series of cross-checks is produced by the EPA in Las Vegas. These interlaboratory comparison samples or "EPA cross-checks" are considered to be the primary indicator of laboratory performance. They provide an

j l independent check of the entire measurement process that cannot be easily provided by the laboratory itself. That is, anlike internally produced l l

cross-checks, EPA cross-checks test the calibration of the laboratory

( detection devices since different radioactive standards produced by individuals outside TVA are used in the cross-checks. The results of the analysis of these samples are reported back to EPA which then issues a t

report of all the results of all participants. These reports are examined very closely by laboratory supervisory and quality control personnel. They indicate how well the laboratory is doing compared to others across the nation. Like internal cross-checks, the EPA cross-checks provide information to the laboratory about the precision and accuracy of the radioanalytical work it does. The results of TVA's participation in the EPA Interlaboratory Comparison Program are presented in table F-1.

i TVA splits certain environmental samples with laboratories operated by the States of Alabama and Tennessee and the EPA Eastern Environmental Radiation Facility in Montgomery, Alabama. When radioactivity has been present in the environment in measureable quantities, such as following atmospheric nuclear weapons testing, following the Chernobyl incident, or as naturally occurring radionuclides, the split samples have provided TVA with yet another level of information about laboratory performance.

These samples demonstrate performance on actual envitonmental sample matrices rather than on the constructed matrices used in cross-check programs.

1 l

I All the quality control data are routinely collected,' examined, and reported to laboratory supervisory personnel. They are checked for trends, problem areas, or other indications that a portion of the analytical process needs help or improvement. The end result is a measurement process that provides accurate data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans.

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Table F-1 RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM A. Air Filter (pCi/ Filter)

Cross Alpha Cross Beta Strontium-90 Cesium-137 EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Date ( 3o) AS. (i3o) A_vg. (i3o) AS. ( 3o) Avg.

4/87 1419 15 4319 45 1712.0 a 819 8 8/87 1019 11 30i9 30 1012.6 10b 1019 12 B. Radiochemical Analysis of Water (pC1/L)

CD Gross Beta Strontium-89 Strontium-90 Tritium Iodine-131 7 EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Date (i3o) Avg.

( 3o) Avg. (i3o) A3 (i3o) Avg.

(t3o) A S.

1/87 1019 11 2519 25 2512.6 21c 2/87 4209 729 3667 3/87 1319 12 4/87d 19;9 16 1012.6 10 4/87 711.2 8 5/87 719 7 4119 39 2012.6 16c 6/87 28951618 2604 7/87 519 7 8/87 48110 47 9/87 1219 10 10/87 44921778 3871 10/87d 1619 21 1012.6 10 11/87 1919 18 12/87 26110 29

Table F-1 RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM (Continued)

C. Camma-Spectral Analysis of Water (pCi/L)

Chromium-51 Cobalt-60 Zine-65 Ruthenium-106 Cesium-134 Cesium-137 EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Date ( 3o) A3 (13o) Avg.

( 3o) A_vg. (13o) Avg. (t3o) A_v1 (t3o) A_vg.

2/87 5019 49 9119 83 10019 86* 5919 51 8719 83 4/87d 819 8 2019 18 1519 14 6/87 4119 46 6419 67 1019 10 7519 68 4019 36 8019 79 10/87 7019 60f 1519 17 4619 47 6119 55 2519 23 5119 51 10/87d 1619 16 1619 15 2419 24

D. Food (pC1/Eg, Wet Weight) oo oa e Iodine-131 Cesium-13/ Potassium-405 EPA Value TVA EPA Value TVA EPA Value TVA Date (13o) A_vg. ( 3o) A3 (t3o) A_vg.

1/87 78t14 84 8419 94h 980i 85 976 7/87 80114 82 5019 49 16801145 1790 E. Milk (pC1/L)

Strontium-89 Strontium-90 Iodine-131 Cesium-137 Potassium-405_

EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Avg. ( 3o) Avg.

Date ( 3o) A3 (t3o) Avg. ( 3o) A_vg. ( 3o) _

2/87 911.6 10 6/87 There appears to have been an error in the preparation of the cross-check. Values are not reported.

10/87 Cross-check cancelled.

Footnotes for Table F-1 Results Obtained in Interlaboratory Comparison Program

a. Lost in analysis.

b. Only two analyses available. '

c. The low Sr-90 results were investigated. A definitive cause for the

! low results could not be identified. The Sr-90 results for other EPA l cross-checks and quality control samples analyzed during this j reporting period were in good agreement with known values.

d. Performance Evaluation Intercomparison Study,

e. The analysis of Ru-106 has always been one of the most difficult.

The low abundance of the gamma line used for identification combined with the level of background counts in the region of interest produce the problems with this analysis.

f. A review of the Cr-51 results for this cross-check indicated that there was very good agreement between all of the detectors used for counting the sample. A majority of the participating labs reported Cr-51 results with a negative bias for the cross-check. This negative bias may have resulted from plating out of this radionuclide on the walls on the counting container.

s. Units are milligram potassium rather than pierocuries.

h. This cross-check displayed a tendency to separate into two phases during the gamma analyses. This lack of sample homogeneity could have caused the error in the Cs-137 value.

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l APPENDIX G 1

LAND USE SURVEY i

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Appendix G LAND USE SURVEY A land use survey is conducted _ annually to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of 5 miles from the plant.

i The land use survey is conducted between April 1 and October 1 using i

appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural l authorities or other reliable sources.

From these data, radiation doses are projected for individuals near the plant. Doses from breathing air (air submersion) are calculated for the nearest resident in each sector, while doses from drinking milk or eating

foods produced near the plant are calculated for the areas with milk producing animals and gardens, respectively. These doses are calculated using ef fluent release information and historical meteorological data.

Doses calculated in 1987 for air submersion were unchanged from those projected for 1986.

Doses calculated for 1987 for ingestion of home-grown foods changed 1

somewhat in some sectors, reflecting shifts in the location of the c85-

aearest garden. The most notable change occurred in the NNW sector where a garden was located 0.7 miles closer to the plant that in 1986.

Fqr milk ingestion, doses projected for 1987 were unchanged from those calculated for 1986. Doses were not calculated for one location (2.2 miles SSW of the plant) because at the time of the 1987 survey, milk animals were not identified. Later it was discovered that milk animals were present at that location; however, the milk was not used for human consumption (vegetation samples are routinely co? tected at this location).

Annual doses projected for 1987 are not appreciably different from those calculated for 1986. Tables G-1, G-2, and G-3 show the comparative 1

\

calculated doses for 1986 and 1987.

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Table G-1 SEQUOYAH NUCLEAR PLANT Projected Annual Air Submersion Dose to the Nearest Resident Within Five Miles of Plant (arem/ year / reactor)

Fall 1987 Survey Fall 1986 Survey Approximate Approximate Sector Distance (Miles) Annual Dose Distance (Miles) Annual Dose N 0.9 0.12 0.9 0.12 NNE 1.7 0.06 1.7 0.06 NE 1.3 0.08 1.3 0.08 ENE 1.4 0.03 1.4 0.03 E 1.1 0.02 1.1 0.02 ESE 1.1 0.02 1.1 0.02 SE 1.0 0.03 1.0 0.03 SSE 1.4 0.03 1.4 0.03 S 1.3 0.06 1.3 0.06 SSW 1.4 0.13 1.4 0.13 SW 1.9 0.04 1.9 0.04 WSW 0.7 0.08 0.7 0.08 W 1.1 0.03 1.1 0.03 WhV 1.1 0.02 1.1 0.02 hN 0.7 0.05 0.7 0.05 Nhv 0.5 0.14 0.5 ,i0.14 4

1

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Table G-2 SEQUOYAH NUCLEAR PLANT Projected Annual Dose to Child's Critical Organ from Ingestion of Home-Grown Foods (arem/ year / reactor)

Fall 1987 Survey Fall 1986 Survey Approximate Annual Dose Approximate Annual Dose Sector Distance (Miles) (Bone) Distance (Miles) (Bo.ne )

N 1.0 2.54 0.9 3.45 NNE 1.9 1.48 1.9 1.48 NE 1.3 2.3 1.3 2.29 ENE * -- * --

E 1.6 0.39 1.6 0.39 i ESE 1.2 0.59 1.2 0.61 I SE 1.9 0.37 1.9 0.37 SSE 1.4 0.92 1.4 0.92 S 1.4 1.60 1.4 1.60 SSW 1.4 3.83 1.4 3.83 SW 2.3 0.92 2.3 0.92 WSW 1.0 1.34 1.0 1.34 W 1.1 0.93 1.1 0.99 WNW 1.1 0.66 1.1 0.66 NW 0.7 1.37 0.7 1.37 NNW 0.5 3.96 1.2 1.04

• Garden not identified in this sector.

s

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D Table G-3 SEQUOYAH NUCLEAR PLANT Projected Annual Dose to Receptor Thyroid from Ingestion of Milk (Nearest Milk Producing Animal Within Five Miles of Plant)

(arem/ year / reactor)

Approximate Distance Annual Dose Location No. Sector (Miles)* Fall 1987 Fall 1986 Farm Br SSW 2.2 -- 0.26 Fara EM' N 2.6 0.05 0.05 Fa rm H ' ' ' NE 4.2 0.03 0.03 ,

Fa rm J ' ' ' WNW 1.1 0.04 0.04 Fa rm HW * *

• NW 1.2 0.06 0.06 I

i

a. Distances measured to nearest property line,

b. Vegetation sampled at this location. )

c. Milk producing animals not identified at this location in 1987. I

d. Milk sampled at this location. I I

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APPENDIX H DATA TABLES 1

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1

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, Table H-1 l

DIRECT RADIATION LEVELS Average External Radiation Levels at Various Distances from Sequoyah Nuclear Plant for Each Quarter - 1987 l mR/ Quarter

• Average External Gamma Radiation Levels

• Distance 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Miles (Feb-Apr 87) (May-Jul 87) (Aua-Oct 87) (Nov 87-Jan 88) 0-1 20.8 1 2.0 16.9 1 4.2 22.4 1 2.3 20.6 1 3.0 1-2 18.2 1 3.0 14.8 1 3.1 19.5 1 3.0 17.6 1 3.1 2-4 16.4 1 3.7 13.1 1 2.0 17.7 1 3.3 17.0 1 2.6 4-6 16.6 1 2.6 13.9 1 2.0 17.9 1 2.2 16.9 1 2.3

>6 17.1 1 2.3 14.4 1 3.6 18.0 1 1.9 16.6 1 2.2 Average, 19.6 1 2.8 16.0 1 3.8 21.1 1 3.0 19.2 1 3.4 '

0-2 miles '

(onsite)

Average 16.7 1 2.7 13.9 1 2.5 17.9 1 2.3 16.8 1 2.2

>2 miles (offsite)

I

a. Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).

b. Averages of the individual measurements in the set il standard deviation of the set.

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l

<_ _ . . . - , _ - _ _ _ - _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - . _ . . i ____ _ , __ _.____.-_m _ _ __ _ _ _ -.. - .- -- - - - - - --

e T ABLE H-2 RADI0 ACTIVITY IN AIR FILTER PCI/P(3) - 0.337 00/P(3) 4A6E of FACILITY }iCL*2Ig3 _ _

_____ DOCKET No._12:12?clZi ___

___I; heil;1g_ REP 0kTINS PEaIOD,113{__

LOCATICN Os FACILITY _t3!;LI;1__ _

TYPE AMD lower LIPIT ALL C0hTROL LUFiE* OF IhDICATCA LCCATICNS _(g[3IIQ3_g;I3.3113111,33$k!L 33}M=_ LOCATIOh5 %C7COUTINE TOTAL NU39E2 0F _

OF Analysis DETECTICN Mgah (F) NaMI Pgau ;F) MEAN (F) PE*O*TED PERF0EFED (LLD) ann;E DISTAACE AND EIRECTICN RANGE CANOE P!Asutf7ENTS

.311 321f.1 _____III L2II_Z_____ -

__111 32I1_2_____ 311_$2Ii_Z______ ___

GEOSS GETA 2.0LE-03 2.12E-C2( 61&/ 416) _DAI57, T%-_ 2.21E-02( 52/ 52) ____2.17E-02( 205/ 235) oli 5.17E 4.st!-02 5.5 FILES W 1.16E 3.79E-02 9.19E 4.30E-02

{

GAGPA (SELI) 15f EI-214 5.0CE-03 5.90E-C3( 1/ 104) CCUNTY PAEE, is 5.9CE-C3C 1/ 13) 9.7CE-03( 1/ 52) l 5.50E-C3 - 5.90E-03 3.75 PILES Sb 5.90E 5.90E-C3 9.7CE 9.70E '

PB-214 5.0CE-03 5.73E-C3C 1/ 104) CCUATV PAEK, TN 5.70E-C3( 1/~ 13) 3.CCE-03( 1/ 523 5.70E 5.7CE-01 3.75 FILES Sb 5.70E 5.70E-03' 8.CCE 6.00E-03

! et-7 2.0CE-02 1.11E-C1( 104/ 104) LP-3 IST TA E A ?.K 1.25E-C1( 13/ 13) 1.0!!-01( 52/ .523 6.11E-C2 - 2.57E-01 1.5 FILES 55h 7.62E 2.67E-01 6.97E 1.99E-C1 TL-233 hcf ESTA5 1.20E-C3C II 104) LM-4 SELLL ISLAN 1.40E-03( 1/ 13) 9.CCE-04( 1/ 52) 4 1.COE-C3 - 1.40E-C3 1.5 PILES NE 1.40E 1.40E-03 9.CCE 9.0GE-C4' l AC-228 ACT ESTA8 1.61E-C3( 6/ 104) LP-5 WARE POIAT 2.03E-C3C 1/ 13) 3.9CE-0!( 3/ 52)

% 3.00E-C4 - 3.5CE-03 1.7 FILES NME 2.00E 2.00E-03 1.3CE 5.30E-03

~

SR 49 6.0CE-04 3 VALUES (LLD 4 VALU!$ (LLD 4 ANALYSIS PERF04 PED Sn 90 3.0CE-04 3 VALUES (LLD 4 VALUES (LLD 4 ANAlf5IS PERF09 PED

__ _--- __________=__ -

k3fEt 1. ACP.IkAL LOWER LIPIT CF DETECTIC1 (LLC) As DESCAIEED IN T ABLE E-1 40TE: 2. P.EAN AND RANGE EASED UPC% DETECTA3LE MEASUAEPENTS ONLY. FRACTION OF DETECTABLE MEASCAE"ENTS AT $*ECIF*E3 LCT1TIONS 15 INDICATEC 11 PARENTHESES (F).

~ .._.

___----_____---m _ _ _ , _ _ _ _ ~ -

_m..m -g wm- 4. rmer -w. e:-- ?wwe_-1 <aow--' w yeT .-e yr w- -y y_w-y-g _e--, g ,_.~.- -w ww -

- . . . - ~ _ . _ _ _ _ _ ._ . - - . - _ _ . . _ . . _ _ _ _ , _ .. __ -. - . _ , - .- . - - - - - - - -

TABLE H-3 FADICACTIVITY I'd CHARC0AL FILTERS PCI/M(3) - 0.037 BC/P(3) sAME OF FACILITv_1g;g;I3t_____ _ _ _ _ _

poCrET NO._1tI2I13Z _____- ___

LOCATICN OF F A C IL IT Y_M!*,1(1 g h_, ____Iggggi;;{ _

REPORTING PERIOD,.13a7 CONTROL %U'?!R OF TYPE AND L0wEA LIMIT ALL LCCATI0h5 1CN8CLTI4!

TOTAL hu9sER OF INDICATCR LCCATICNS _(g[AI]Q3_h1TH_HijMj}T ANNLAL_t{AM __

j PEAN (F) MEAN (F) 2EPCRTED OF ANALYSIS DETECTION KEAh (F) NAME M E A TUm g gE*4T 3 DISTAhCE AND DIRECTICA RANGE RASSE PERFCnMED (LLD) aANGE l

_111 59I1.1 __ _. 111. 5 211_2_ _ ___ ___ MARRIs0N, _ . - - - ._ _ TN_

_ 111.52I1 Z_ ____111_52I1 2 - __

1 = - ___._

2. ole-02 1.25E-02( 3/ 414) .2.39E-02( 1/ 52)__ 2C6 VALUES <LLD 10 DINE-131 l

l 620 I.C7E-C2 - 2.3*E-02 E.75 MILES ssW 2.39E-C2 - 2.39E-02

=

_=

_ - - - = _ _ _ _ _ _

W37E: 1. WCPIhAL LO.ER LIPIT CF DETECTION (LLD) AS DESCAISED IN TABLE E-1.

l NOTE: 2. F. EAT A?40 RANGE 3ASED UPON DETECTAELE MEASUREPEhT5 CNLY. FRACTICN OF DETECTABLE MEASUREMENTS AT $7ECIFIED LCCS 15 IkDICATED IN PARENTHESES (F).

O r

-.m ..

_ _ _ . _ _ _ _ . _ _ _ .____ _ _ _ _ ___ _ _ _ _ _ _ . _ . . , - ~ _ , . - . . . _ _ . _ . . ,.. ., , ,- -- -4 - - + . . +. .__ . _, .. -.

~~ . . . . - ~ ,

4 TABLE H-4 RADI0 ACTIVITY IN FILE PCI/L - 0.037 3C/L NA;15 0F FACILITY _;1g(gI3t___ _ _____ ___

DOCKET NO._12-]2?gj2f ._

L3CATICN OF FACILITY _g3*1(Igh_______ _ ___Ighuiig _ REPORTING PERICD_13f?__ __==_ TVPE AkD LowE4 LIMIT ALL CONTROL MU'?ER OF IN3ICATCR LCCATICN$ ,(g{&llg3_gIIg,MigyI11 gggy1L_gj3g LOCAT10h5 %CNPOLTINE 10TAL AUM3ER OF CF AAALYSIS DETECTICh FEAN (F) NAME MEAN (F) _ MEAN (F) 2(P78T87 PEDF0k*ID (LLD) RAAGE DISTAhCE AND CIRECTICN RANCE RAEGE .4?ATU8ESTNTS

                                    -- ------               _111.3211_1 ---- 1;I_h211.1.                                                     -

111.5CII 2 _ _.- III.L2II I _---_ --- 10DIhE-131 2.0CE-01 74 VALLEs <LLD 77 VALUES < LLC 151 ANALYSIS PEEFOAFED GAMMA (GELI) 151 C5-137 5.0CE+00 5.73E+CC( 3/ 74) HCLDER DAIRY 6.45E+C0( 1/ 25) 77 VALUES <tLD 5.16E+C0 - 6.45E+0C 4.25 EILES uE 6.45E+00 - 6.45E+C3 A-40 1.50E+02 1.26E+C3C 7+/ 74) HCLDER DAIRY 1.33E+03( 26/ 26) 1.39E+03( 77/ 77) 9.24E+02 - 1.72E+03 4.25 MILES 4E 1.20E+03 - 1.72E+03 9.61E+0? - 1.74E*:7 81-214 2.00E+01 2.32E+C1( 1/ 74) JONES FARM 2.32E+01( 1/ 25) 3. 5 9 E + 91 ( 1/ 77) 2.32E+C1 - 2.32E+01 1.25 PILES W Z.32E+01 - 2.32E+01 3. e E + 01 - 3. o n + t PS-214 2.00E+01 2.53E+C1( 1/ 74) H WALKER FAR1 2.50E+C1( 1/ 23) 77 VALuis < TLC 2.50Z+C1 - 2.5CE+C1 1.25 MILES NE 2.50E+01 - 2.50E+C1 TL-208 h0T ESTAS 1.09E+C0( 3/ 74) HCLDEA DAIRY 1.E5E+CC( 1/ $) 1.46E+00( 2/ 77) 1.1SE-C1 - 1.35E*CC 4.25 *ILEs NE 1.45(+0C - 1.35E+00 7.21E 3.62E+0? AC-225 hof ESTAS 4.51 E + CC C 5/ 74) HCLDEE DAIRY 1.17E+C1C 2/ 26) 8.34E+00( 9/ 77) ME 4.43E+CC - 1.63E+C1 4.25 MILES NE 7.15E+00 - 1.63E+01 2.7C E +00 - 1.45 E + 01 SR 89 2.5CE+0G 4.75E+C0( 2/ 12) M WALdER FAAM 5.68E+00( 1/ 4) . 6.f4E+00( 1/ 39) 51 3.E71+00 - 5.63E+0C 1.25 MILES NW 5.6EE+00 - 5.6SE+00 6.24E+0C - f.64E*C0 SR 60 2.0CE+00 7.50E+C0( i2/ 12) JCNES FARh 1. 30 E +01 ( 4/ 4) 3.62E+0CC 4/ 34) 51 2.C4E+C0 - 1.66E+01 1.25 MILES W E.40E+00 - 1.66E+01 2.31E+00 - 7.1?E+0?

                                                                                                                                                          ---- ..._                         __ -     =. . . . . . . - - . . . . . . . . . . . . .
                                              ._=

NOTE: 1. 4CMIN4L LOWER LIPIT OF DETECTICN (LLD) A$ DESC210ED IN TAOLE E-1. 20TE: 2. PEAN AND PANGE EASE 3 UP0h LETECTA?LE MEASUREMENTS ONLY. FRACTI0t. OF D ETECT A3L2 "4! ASUR E*ENTS AT 4 !.I"!.' LCCOTIC%$ IS INDICATEC IN PARENTPCSES (F). -.____.___--_-----n-sw--_.--_____-_. - -- _ _-_--_ _ - - - - - - - _ = - , e

e T ABLE H-5 R4D10ACTIVITV IN VEGETATIch FCI/r6 - C.J37 EC/KG (WET JEIGHT) N4ME of FACILITY,}[j(;14M _ _ ___ DOCKET NO._22:3ZZe}Zl-LOCATICN OF FACILITY _33rILIgh__________ _Ilh31}}C[_ REPORTING PERIOD _I21Z___ TYPE AND L0e!7 LIMIT ALL CONTROL NUM8Ee OF T3T AL hUr1LER OF IA31CATCR LCCATIONS _(G[31193_h113]dI1513I_!!$y3(_Eg&N _ 'LOCATI0h5 h C1r C LT I'J E OF AMALYSIS DETECTION E!AN (F) 4 APE MEAN (F) 9EAN (F) RE*CRTED PEAFOAPED (LLD) F44GE DISTAhCE AND DINECTION R A tJ G E PANSE MEASU1EMENTS

                                       - _111.3CI1.1                      Iii_59II_Z_____                        __=-_              _             _ _ __11E_3GIE_2_____                    ____1EE_$2Ii_I                                          ______

1/ 13) 141 VALUES <tLD IJDIhi-131 4.0LE+00 _____4.2fE+CGt 1/ 177) LM-5 hARL POIhT 4.25E+00( 312 4.23E*C0 - 4.28E+00 1.7 PILES N:sE 4.28E+00 - 4.28E+C0 GAP.MA (GELI) 321 C5-137 2.40E+01 3.35E+C1C 2/ 173) H WALKEA FAEM d.29E+01( 1/ 13) 3.19E+01( 1/ 143) 2.93E+C1 - 6.29E*01 1.25 PILES Nb e.29E+01 - 6.29E+C1 3.19E+01 - 3.19E+G1 K-40 4.0CE+02 5.37E+C3( 176/ 178) LP-5 HARE POIhT 7.C4E+03( 13/ 13) 5.47E+0!( 142/ 143) 1.17E+C3 - 2.4EE*04 1.7 PILES NME 2.71 E+03 - 1.97E+C4 1.23E+03 - 1.15E+04 EI-214 4.!CE+01 5.22E*C1C 7/ 172) EDGAR MALCNE FAR, 6.11E+C1( 1/ 13) 6.29E+31( 9/ 143) 4.E0E+C1 - 6.11E+01 2.5 PILES N t.11E+01 - 6.11E+C1 4.99E+01 - f.53E+C1 tI-212 h0T isTAS 1.75E+C2C 1/ 173) skADy FAPM 1.75E+02( 1/ 12) 2.69E+02( 1/ 143) 1.75E+CZ - 1.75E+C2 2.25 PILES ssa 1.75E+02 - 1.75E+02 2.69E*02 - 2.69E*02 P2-214 S.0CE+01 9.36E*C1( 1/ 178) H WALKER FARM 9.36E+C1( 1/. 13) 8.75E*01( 2/ 143) 9.36E+C1 - 9.36E+01 1.25 9ILES Nb 9.36E+01 - 9.36E+C1 8.72E+01 - 8.79E+01 P8-212 4.0CE+01 5.38t+C1C 5/ 178) MARRI50h, TN 6.6eE+01( 1/ 13) 7.47E+01( 3/ 143) 0% 4.42E+C1 - 6.56E+01

• 8.75 MILES SSW 6.86E+01 - 6.86E+01 4.25E+01 - 2.26t+02 BE-7 2.DCE+02 3.04E+C3( 175/ 173) LEVY FAa1 4.9BE+03( 5/ 5) 2.5EE*33( 130/ 143) 2.ZSE+C2 - 1.87E+04 3.5 PILES 5 4.69E+02 - 1.25E*04 2.13E+02 - 1.80E+04 1L-203 h0T ESTA3 9.33E+C0( 33/ 178) HARE!s0N, Th 2.25E+01( 3/ 13) 1.39E+01( 33/ 143) 1.49E-C1 - 4.29E+01 'E.75 MILE 1 55W 1.00E+01 - 4.29E+01 9.02E 1.01E*02 AC-228 NOT ESTAa 5.32E+C1s 25/ 175) H WALKE4 FAAM 9.25E*01( 4/ 13) 4.5tE*01( 26/ 143) 1.61E+C1 - 2.01E+02 1.25 MILES Nb 2.19E*GT - 2.01E+02 1.43E+0i - 1.03E*C2 SR 89 1.4CE+02 $4 YALU(1 <LLD 44 VALUES <LLD 93 AhALYSI! FEAFCa*ED 5A 90 6.00E*01 1.25E+C2( 16/ 54) H WALKER FARM '.57E+02( 1/ 4) 1.05t+02( 4/ 44) 93 6.14E+C1 - 4.57E+GP 1.25 FILES Hb 4.57E+02 - 4.57E+02 6.66t+01 - 1.43E+0:

                                                                                                                                                                =....-n____...._____6._                                          -        -      -

LOTE: 1. L*FIh4L LChER LIPIT CF DETICTICM (LLD) AS DESCAIEED IN T ABL! E-t. 401Es 2. PIAh AND RANGs BA$CD UF0h GETECTAFLE hEA6UELMENTS ONLY. FRACTION CT DETECTA?LE MEASUREMENTS AT SFECIFIE) LCCATIONS ~

                                                                                                                                                                                                                                                          " " ~  "

IS INDICATEC IN PAREhTHESES If). . ~ - - , - . .,,,v,r,,- . -.- m, , , . . , , , - - , . . , m-, ,m,- , sw. ,. . , - , , - . ,--. . r , , - + - . , , , , ,- .

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

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                                                                                                ~3233      I      I ~~~II      M SALK5& FIEM        3.332    I    7        Il~                   ~III   C        ~ / II 2                                        3.3:E+C3 - 3.3!E*33            1.25 MILES N'.      3.33E+03 - 3.33E+03                          4.14E+03 - 4.1AE*33 GA+.P4 (EELI) 2 K-A3                                          1.5CE*02      1.65E+C3(       1/   1)      M WALKEA FAAM        1.$5E+03(    1/      '3 )                     1.93E+03C         1/   13 1.63E+C3 - 1.$$!+03            1.25 FILES Hb       1.65E+03 - 1.65E+C3                          1.93E+03 - 1.93E+03 h0TE:   1. hCPIhAL L0m!A LIPIT CF DETECTION (LLD) A$ DESCRIEED I4 T A BLE E-l.

NOTE: 2. FIAN AND #Ah6E BASED UPO% DETECTA9LE MEASUREMENTS ONLY. FRACTION OF CETECTABLE MEASUREMENTS AT $FECIFIED LCC*TISts Is INDICATEC IN PAREhTHESES (F).

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                                                                              .311_*9II_I _ _ __ _i ! ! _ !! 91 I 2_ _ __ _ _ __ _ ___ _ _ __-                                                                           ____11E_59IE_Z ____              IE1_h211_I______                                                     - ______

7.0CE+00 3.37E+C3( 1/ 1) M waLKEa FAAM 3.33E+G3C tt 1) _ 4.59E*03( 1/ 1) Ga055 SETA 4.59E+03 - 4.59E+03 2 3.37E*C3 - 3.3?E+03 1.25 FILES Nw 3.39E+G3 - 3.39E+C3 GARPA (EELI) 2 1.5CE*32 2.14E+C3( 1/ 1) H >ALKEa FAAM 2.14E+03( 11 1) 2.2SE+03( 1/ Il K-40 2.25E+03 - 2.25E+C3 2.14E+C3 - 2.14E*03 1.25 MILES f4h 2.14E+03 - 2.14E+03

                                                                                                                                        --=__---         __==_                 __

NOTE: 1. WC*IAAL LosIR LIPIT OF DETECTION (LLD) AS CESCRI5ED IN T A 3 L E E-1. 4011s 2. PEAN AND PANGE BA510 UPON DETECTABLE MEA 50REMEhT5 CELf. FRACTION OF CETECTABLE MEASU8EMENTS AT SPECIFIED LG sT IS INDICATEC IN PARENTHESES (F). I. _ . . _ _ _ _ _ . _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ m + -- -- , _r ____ _________m_ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _

TABLE H.9 RAC10 ACTIVITY IN GREEN 9EAh5 PCI/FG - C.037 63/KG (dET WEIGHT) bA*E OF FACILI17,}gg(;yst_____ ________ __ __ _ DOCKET No._12;}2Ig}28,___________ LOCATICM OF FACILITY,HA}}(Jgh _ __11hg11;[__ _ _ ________ REPCRTING PEaIOD_11fl______ ____ ALL C orJ T A OL %C'2?' 0F TYPE A%D L0w!* LIP IT WONPCLTINE TJTAL AUK (R OF INDICATC4 LCCAT!045 _(G{ATIQJ_h11d_312t1}I_A33kAL_*;*3_ LOCATICAS 21#04TED OF ANALYSIS DETECTION MEAN (F) NAFs PTAN (F) MEAN (F) l DISTANCE ANL CIRECTIch PAUGI RANSC MIA*US:'rNTS l PERF0&P!D (LLD) RAN3E

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3.C i i ~~~Il ~E"5I3Ii'iiiT 32ii i 7 ~~ii~ 5.5 6 ~ 7~~~ii l 2 5.C3Z*C3 - 5.0!E*03 1.25 MILES %b 5.0!E+03 - 5.08E*03 5.5EE+03 - 5.5EE*03 GAMMA (GELI) 2 I K-40 1.5CE*02 2.f7E+C3( 1/ 13 M WALKEE FARM 2.27E*C3( 1/ 1) 2.35E*03( 1/ 1) 2.E7E+C3 - 2.57E+03 1.25 FILES N. 2.57E+03 - 2.87E+03 2.35E+03 - 2.35E+03

                                                                                                                          . . . _ - -                      = -.._.. ...--

I t h3TE: 1. NCMIbAL LO.E8 LIPIT CF DETECTION (LLD) AS DESCRIEED IN T A SLE E-1.

                                                                                                 =0TE:                    2. FEAN A%D AANGE SASED UPok LETECTASLE MEASUREMENTS CNLY. FPACTION OF DETECTABLE MEA 5UaEMENTS AT SPECIFIED LCCATIONS j

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TABLE H-Il RADI0 ACTIVITY IN TCMATOES PCI/tG - C.037 eQ/EG (WET WEIGHT) hAPE OF FACILITY _112LgIIH. _ _________ ______. , DOCKET N O._j Q-)),7g))j __,,___ LOCATION OF FACILITY _gf!}(]gN__ _,,, __,Jiggg}}(( REPCRTING &ERIOD,122?= __ TVFE AhD L3WE2 LIPIT ALL CONTROL teUv?E4 OF T3TAL h u.* 3 E R OF IA3ICATCA LCCATICM5 _Lg[11]S3,kIld_32sN111_&M3WAL,t!AM LOCATIONS  %"NPOUT!*d! LF ANALYSIS DETECTICm EEat (F) ha*E PEAN (F) PEAN (F) *EPC+TE" PERF0KFED (LLD) mAA;E DISTAhCE AND CIRECTION RANGE RANGE  ?!h0U?E*?NTS si3?i'3ITA -!!$E!!!$1 I iikf!3g21I7 f_ ,, , ,,L,i7_7;_q.__ ,,,373gg732Ig;2 ,,_ _77jgg,glII{, , 1, 2 4.59E*C3 - 4.3CE+33 1.25 MILis 4. 4.99E+03 - 4.99E+C3 3.43E*03 - 3.43t+C3 GAM *A (;ELI) 2 K-40 1.5CE*02 2.73E+C3C 1/ 1) H WALKER FARM 2.73E+C3C 1/ 13 1.93E+03( 1/ 1) 2.73E+C3 - 2.73E+03 1.25 PILES h. 2.73E+03 - 2.73E*C3 1.9CE+03 - 1.90E+03 81-214 2.0CE*01 3.35E+C1( 1/ 1) H hALKEa FARM 3.35E*C1C 1/ 1) 1 VALUES <LLD 3.35E+C1 - 3.35t+01 1.25 MILES N6 3.35E*01 - 3.35E+C1 kOTE: 1. NCMIhAL LOhER LIPIT CF DETECTIc4 (LLD) A$ DESCRISED IN T A9LE E-l. m0TE: 2. PEAN AND 2ANGE BASED UPOE SETECTA3LE MEASUAEMENTS OkLY. F8 ACTION OF DETECTABLE MEASUREMENTS AT $FICIFI!D LCCSTIOMS g IS IhDICATED IN PARE %TME$ES (F).

e T ABLE H-12 DADICACTIVITY I4 APPLES PCI/KG - 0.037 90/KG (WET b7) hAnt OF FACILITT_1E3kCI!t____ ---____ _ _____-

                                                                                                                                                                                                                                                '"E"E' "8*                IEN'E-                    -~

(CCATICN OF FACILITT_HA:ILIgs__ ___119511111- -

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TYPE AND LOhff LIPIT ALL CONTROL MUPSTR OF TJTAL hum 3ER OF INDICATem LCCATIcN5 _LGIil123.kIId dIGU1 I_355WAL_E133 LOCATIONS *ess:cTI=E OF ANALYSIS DETECTIC4 MEth (F) hAME REAN (F)- MEAN (F) SEPCOTED PERF0EPID (LLD) EA%3E DISTAhCE AND DIREC'!!ON RANGE RAP.S! P.!ASU'T" 4T1 _ _ _ . _111.5211.1 __ __ _111_S 2H_Z __ __ ___ . -

                                                                                                                                                                                                              " E_hsII_Z                                               _ ___:11_!!2II_ Z              __.__________
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GkO55 BETA 9.0CE+00 2.00E+C3( 1/ 1) H WALKsa FAA9_ 2.07E+03( 1/ 2.42E+03( 1/ 2 2.C7E*C3 - 2.35t+C3 1.25 FILES 4W 2.09E*03 - 2.09E*03 2.42E*03 - 2.42E+03 GAPPA (GELI) 2 E-60 1.50E*32 1.2eE+03( 1/ 1) M WALKER FAR9 1.26E+03( 1/ 13 1.00i+03( 1/ 1) 1.26E*03 - 1.2eE+03 1.25 "ILES Nb 1.26t+03 - 1.26E+03 1.00E*03 - 1.00E+03 l

                                                                                                                                                                     ==_.                             _ _ _         ___                                                           _- ______--                       ---
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h31Es 1. % MIhAL LChEE LIPIT CF DETECTICN (LLD) AS DESCRISED IN TA$LT E-1, NOTE: 2. Pi&N Ah3 RANGE SASED UPON DITECTAPLE MEASUAEMENTS ONLT. FRACTION OF DETECTA8LE MEASUREMENTS AT 5FECIFIES LCC2TIONS I$ INDICATED IN PAREhTHESES (F).

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                                                                          *ACICACTIVITY IN PU3LIC WATER SUPPLY PCI/L - 0.037 eQ/L NAME OF FACILITY _}LCygIAh                  __           ________       _          __

DOCKET NO._1G-}ZZe}Z$_ ___ LOCATICN OF FACILITY gA!;LIgh__ ______,113hg}}ig ___ REP 02 TING PERIOD _122Z_ _____ TYPE shD LOWEA LIMIT ALL C0hTRCL NUr=ES Or T 31 AI. ALFSER OF Ib3fCATC9 LCCATIchs _(Egal]Q3_h11H_3Iigi}I_3332&L_g!aN LOCATIONS NCNFOLTINE CF AhALYS!! DETECTICN NEAN (F) AAFE PEAN (F) PEAK (F) SESC*Trp PiAFCRFID (LLD) EA43! DISTANCE AND CIRECTION RANGE 9AN3E FEA3Uerwegt$

                                           ~

GIO55~5iTA ~ ~ 5 "[!ii C 4 ~~595 ~Ci"[EIU5TRIES ~i!i5[ i i ~I55' 'l!I O i /~~}55 24 1.73E+03 - 7.222+CC Tom 473.0 1.73E+00 - 7.22E*00 1.74E+00 - 4.66E+00 IODIAE-131 1.0CE+00 13 VALUES <LLD 12 VALUE5 <LLD 25 AhALY 11 P!FFCRPED GAFPA (EELI) 64 TL-208 h07 ESTAS 1.3SE+00( 1/ 39) CMICCAMAUGA DA1 1.35E+C0( 1/ 13) 6.57E-01( 2/ 25) 1.3EE+C3 - 1.3EE+00 Tak 405.3 1.38E+00 - 1.35E+00 6.07E 7.07E-01 AC-228 N37 ESTAB 1.04E+C1( 4/ 39) CHIC (AMAUGA CAM 1.44E+01( 2/ 13) 5.62E+00( 2/ 25) 3.70E+C0 - 1.782+01 Ta4 465.3 1.11E+01 - 1.75E*01 4.27E*00 - 6.36E+0C PA-234M ACT ESTA9 5.47E+C2( 11 39) CHICKAMAUGA *A% 5.47E+C2C 1/ 13s 25 VALUES (LLD 5.47E+C2 - 5.47E+02 TAM 465.3 5.47E+02 - 5.47E+G2 SR 89 3.0CE+00 4.04E+C0( 2/ 12) E.I. DUP 0kT 4.44E+00C 1/ 4) 3.30E+00( 1/ 8) 20 3.63E+C0 - 4.44E+C0 tam 470.5 4.44E+00 - 4.44E+C0 3.30E+00 - 3.30E+00 SR 90 1.40E*00 12 VALUE5 <LLD 8 VALUES <LLD g 20 ANALYSIS PEaFoaPED

     *- TRITIUM                   2.5CE+02            12 VALUES <LLD                                                                     E VALuis < LLC 20                     ANALYS!$ PEaFORPED
                    . ... ....--             ..----          ====--__                   _          -__ .                                                               -

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l T A B L E H- 16 l PADICACTIVITY IN C H Ak*JEL C A T F I5M (FLESM) l PrI/G - 0.037 3G/G (D2V WEIGHT) AAME OF FACILITY _11?L2I'k .. DOCKET NO._}C-}ZZe } Z 2_ _ _. ,,, LOCATICN OF FACILITY,3331Ligh__ Ilh51111E __ _ - - - REPORTING PERICD,132Z,. ,_ ___,,,, TYPE AND LOWE8 LIPIT ALL CONT 80L *.U*I'4 0F TOTAL hUMSER OF IN3ICATCR LCCATICAS _(ggilIQ$ h115,$1syg}l.13391L_tf!3___ , LOCATIOk1 *C%*CLTINE OF ANALYSIS DETECTION P.EAN (F) AAPE PEAN (F) MEaN (F) #ESCSTED PERF0EFED (LLD) pahGE DISTANCE AND DIaECTION RANGE p an', E *Tasc**MENTS

                                                                       .111.5211_1                                                      _____Lil_h211 Z_                                                       ______111.5911_2                     2:1_S211_Z______        _______

g,g,, g_77 a C5-137 6.00E-02 4 VALLEs <LLD 9.23E-02( 2/ 2) 6.04E 1.24E-01 K-40 1.00E*00 1.16E+C1( 4/ 4) NICgsJACC RES 1.19E*01( 2/ 23 1.27E*01( 2/ 2) 1.06t+C1 - 1.23!+01 lam *25-471 1.16E+01 - 1.23E+01 1.26E+01 - 1.29E+C1 TL-208 h0T ESTAb 1.20E-C3( II 4) CHICKA*AUGA 4E 1.20E-03( 1/ 2) 2 vatuts <tLD 1.63E-C3 - 1.SCE-03 TAM 471-530 1.dCE 1.80E-03 N3fis 1. NCPIhAL LO.ER LIPIT CF DETECTIog (LLD) As DEICRIbED I% TA!LE E-1. N3TE: 2. MEAN Amp 4ANGE BASED UP0h DETECTABLE MEASUREPENTS ONLY. FRACTION OF CETECTs3LE MEASUREMENTS AT IPECIFIED LOCATICMS g IS INDICATEC IN PARENTHi$E$ (F).

         - _ ~ _                  ,-

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T ABLE M-18 - RADIDACTIVITY IN SMALLPOUTH RUFFALO (FLESH) PCI/G - 0.037 BC/G (D4Y WEIGHT) LA9E OF FACILITY.}ggggIAy _, ___ DCCKET NO._}Q:2Z{g]22 _._ LOCATIC4 OF fACILITV 3A'lLIQ3_ _

                                                                                                                                                                    . T[33111L{;........                                        RcPORTING PERIOD.12jZ _..._=                 _

TYPE AND LOWER LIPIT ALL CCMTROL %C'2F4 3F T3fAL bU53E2 OF INDICATCs LCCATIONS _(gg&I]23.kII5.512t!!11.igiW A.L.EI A.M. LOCATIONS 4C%8tLTIME OF ANALYSIS DETECTION MEAE (F) 4AME PEAN (F) MEAN (F) st_scofgg PERF0AMED (LLD) RANIE DISTANCE AND DIRECTICN R a f4G! RAkSE *EA!Us**!%T5

       .. . ..         .111.5911.1                                                                                                       111.h211.1 =           _ . .                                         . 11I.5911.2-                                 111.52II.Z-             -

GAMP4 (CELI) C5-137 6.0CE-C2 7.26E-C2( 2/ 4) CPICKAMAUEA MEs 7.26E-02( 2/ 2) 2 VALUES <LLD 7.C5E-C2 - 7.47E-02 TRh 471-530 7.05E 7.47E-C2 K-40 1.CCE+00 1.IZE+C1( 4/ 4) CHICEA4AUGA RES 1.29E+C1C 2/ 2) 1.11E+01C 2/ 2) 9.54E+CC - 1. ACE +01 TRM 471-530 1.185+01 - 1.40E*01 1.08E+01 - 1.15E+C1 sI-212 1.0CE-01 1.27E-01( 1/ 4) MICEAJACK RE: 1.27E-01t 1/ 2) 2 vAtuts <LLs 1.27E-C1 - 1,27E-01 Ta4 425-471 1.27E 1.27E-C1

      == .-                                   ...-...-                                                                                      _          . _ . _                                           ..-            -

NOTE: 1. ACMINAL LOWER LIPIT CF DETECTICN (LLD) AS DESCRIEED IN TABLE E-l. NOTE: 2. P.EAM AND 4ANGE BASED UP0h DETECTABLE MEASUREPENTS 04LY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LCCSTIcMS g IS INDICATEC IN PARENTHESES (F).

                          . _ . _ _ _ _ . _ _ _ _ _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ _ . _ - _ . _                                      -___---4         ____-----+eree               _=m*   - -   ._--w-w    -+w--   ->e-   4e-  m

                                   ->- - + _ _ . - _ .                            . . _ .                     -                          . . . . . _ . - .

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• ru a a a  ;

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1

T A B L E H-22

• RADI0 ACTIVITY IN CLAM FLESH PCI/G - 0.037 E3/G (DRY WEIGHT)

NAME OF FACILITY _1{2LQIAM DOCKET NO._}Q-]ZZe}Z2. LOCATICN OF FACILITY _gA*1(Igy_______ _ig33g}}gg REPORTING PERIOD _121?= TYPE AND LOWER LIMIT ALL CONTROL NU49ER OF TOTAL NU.M9E2 0F INDICATCR LCCATIONS _(QQgI]Q$_hlig_HigHijl_g3 hyal _t!AM LOCATIONS NCNPCUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) 9EAN (F) REPCRTED PERFORFED (LLD) RANGE DISTAhCE AND DIRECTIch RANGE RANGE FEASU3E"ENTS

          -        111_5211_1          111 52Ii Z_____          ____            _         -     = 111_5GII_Z      _     111_32I1_1______  ___

GAMMA (GELI) 6 CO-60 1.10E-01 9.76E-C1( 1/ 4) TRM 483.4 9.76E-01( 1/ 2) 2 VALUES <LLD 9.76E-C1 - 0.76E-01 9.76E 9.76E-C1 BI-214 2.5CE-01 3.7SE-C1( 2/ 4) TEM 480.82 4.37E-01C 1/ 2) 3.39E-01( 1/ 2) 3.20E 4.37E-01 4.37E 4.37E-01 3.39E 3.39E-01 PS-214 2.5CE-01 3.27E-C1C 2/ 4) TRM 480.82 3.30E-01C 1/ 2) 4.23E-01C 1/ 2) 3.25E-C1 - 3.3CE-01 3.30E 3.30E-01 4.23E 4.23E-01 TL-208 NOT ESTAB 1.11E-C1( 1/ 4) TRM 483.4 1.11E-C1( 1/ 2) Z VALUES <LLD 1.11E-C1 - 1.11E-01 1.11E 1.11E-01 AC-228 NOT ESTAB 4 VALUES <LLD 6.35E-31C 1/ 2) 6.35E 6.35E-G1 NOTE: 1. NCNINAL LOWER LIPIT CF DETECTION (LLD) AS DESCPIBED IN TABLE E-1. NOTE: 2. FEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F). d

Figure H-1 Direct Radiation Levels m Sequoyah Nuclear Plant R / S 25-l::C^:$$'6hAAv$$N' d 10-5- Begin Plant Operation 1 0 t 76 77 78 79 80 81 82 83 84 85 86 8'i 88 e

                                    ..- Onsite     0- Offsite r

Figure H-2 Direc* Radiation Levels m Sequoyah Nucisar Plant R 4-Quarter Moving Average / 25-20 ............. ... .. . .. ........................... .............. ... ..... OO # 0000'0000000O'00'# 00'0 '000000 0 15- OO'O ogo r d 10-O 5- Begin Plant u Operation 0 76 77 78 79 80 81 82 83 84 85 86 87 88 e ..- Onsite 0- Offsite r

                                           -113-

Figure H-3 Annual Average Gross Beta Activity l Air Filters (pCi/ cubic meter) Sequoyah Nuclear Plant 4 Indicator Control i 0.25 -- l 0.2 - - Preoperational Phase Operational Phase 0.15-I ! 0.1 - M 71 72 73 74* 75 76 77 78 79 80p 800 81 82 83 84 85 86 87 , l Data not collected in 1974. i i

Figure H-4 l Annual Average Gross Beta Activity j Surface Water (pCi/ liter) Sequoyah Nuclear Plant j indicator M Control 6 -- P eoperational operationai Phase

           ~

71 72 73 74 75 il 76 77 78 79 80p 800 81 llijk 82 83 84 85 86 87 i

17 8 18 6 R8 5 8 4

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374o1 SN 157B Lookout Place 10 CFR 50.71(a) U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - OPERATING LICENSES DPR-77 AND DPR-79 In accordance with SQN technical specifications 6.9.1.6 and 6.9.1.7 for j units 1 and 2, enclosed is the Annual Radiological Environmental Operating Report for 1987. This report contains no commitments. If you have any questions, please telephone M. R. Harding at (615) 870-6422. Very truly yours, TENNESSEE VALLEY AUTHORITY gs , l/ Y R. Gridley, Director I l Nuclear Licensing and  ! l Regulatory Affairs Enclosure cc (Enclosure): Mr. K. P. Barr, Acting Assistant Director j for Inspection Programs  ! TVA Projects Division U.S. Nuclear Regulatory Commission l Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. G. G. Zech, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission 1 One White Flint, North ) 11555 Pockville Pike Rockville, Maryland 20852 Sequoyah Resident Inspector g j Sequoyah Nuclear Plant ( 2600 Isou Forry Road Soddy Daisy, Tennesseo 37379 An Equal Opportunity Employer J}}