ML20247A630
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Site: | Fermi |
Issue date: | 12/31/1997 |
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Text
O FERMI 2 NUCLEAR POWER PLANT DETROIT EDISON COMPANY OPERATING LICENSE NO. NPF - 43 l
Fermi 2 - 1997 Annual l Radioactive Effluent Release and Radiological Environmental Operating Report I
for the period of i
( January 1,1997 through December 31,1997 i
l l
l Prepared by:
Fermi 2 l
Radiological Health
, O 9805060191 900430 PDR ADOCK 05000341 R PDR
Fermi 2 - 1997 Annual Radioactive Effluent Release and l Radiological En vironmental Operating Report i
Table of Contents Page l
introduction 1 Nuclear Energy Basics 2 l The Atom 2 Fission 2 Nuclear Reactor 3 Reactor Safey Equipment 6 Radiation 7 l Sources ofRadiation 8 BiologicalEffects ofRadiation 8 l
Benefits ofNuclear Power 11 Sources ofRadioactivity Releasedfrom Nuclear Power Plants 12 Noble Gases 12 lodines andParticulates 12 1 Tritium 13 Plant Effluent Afonitoring 13 Exposure Pathways to People 14 Dose Assessment 15 PreoperationalSurveillance Program 16 l( OperationalSurveillance Program Objectives 17 Program Overview 17 Sample Analysis 18 QualityAssurance 20 Radiological Effluent Program Results 22 Radiological Environmental Monitoring Program Results 26 Direct Radiation Afonitoring 26 Thermoluminescent Dosimeters 26 Atmospheric Afonitoring 27 Air Sampling 28 Terrestrial Afonitoring 30 l AfilkSampling 30 Groundwater Sampling 31 Garden Sampling 32 Aquatic Afonitoring 33 Drinking Water Sampling 33 Surface WaterSampling 35 Sedimen: Sampling 36 Fish Sampling 38 O-U ii l
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Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report 1
'n Table of Contents Page l Land Use Census 41 j 1997 Land Use Census Results 42 AppendixA Sampling Locations A-1 Appendit B EnvironmentalData Summary B-1 Appendit C EnvironmentalData Tables C-1 Appendit D EnvironmentalProgram Execution D-1 Direct Radiation Afonitoring D-1 Atmospheric Afonitoring D-l Terrestrial Afonitoring D-2
>f Afilk Sampling D-2 G Garden Sampling D-2 Groundwater Sampling D-2 l
Aquatic Afonitoring D-2 Drinking IVater Sampling D-2 l
Surface IVater Sampling D-3 l Sediment Sampling D-3 l Fish Sampling D-3 Appendix E Effluent and Radwaste Data E-1 Regulatory Limitsfor Radioactive Effluents E-1 l Gaseous Effluents E-1 Liquid Ej]luents E-2 Afeasurements and Approximations of Total Activity in Radioactive Effluents E-3 F E-3 Gaseous Effluents Fission andActivation Gases E-3 Radioiodines E-3 Particulate E-3 Tritium E-4 Gross Alpha E-4 Liquid Effluents E-S Statistical Afeasurement Uncertainties E-S f
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Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report I
l Table of Contents Page Gaseous Release by Individual Nuclide E-5 Particulate Radionuclides E-5 Noble Gases E-6 l Radioiodines E-7 Shipments ofSolid Radwaste E-7 l
Spent resins, sludges, etc. E-7 Class A quantities E-8 l Class B quantities E-9 ;
Dry compressible waste, contaminated equipment, etc. E-9 Irradiated components, control rods, etc. E-10 Appendix F 1 Quality Assurance Data F-1 l Interlaboratory Comparison Programsfor 1997 F-2 l Fermi 2 andNRC TLDIntercomparison F-7 l Independent BlindSpiked Cross Check Program F-9 Appendix G i MeteorologicalData _ G-1 Fermi 2 Joint Frequency Distribution Tables - 1997 G-1 1997 WindRose G-8 Appendix H Glossary of Terms H-1 1
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Fermi 2 - l997 Annut!
Radioactive Effluent Release and Radiological Environmental Operating Report lO Introduction l This report is published to provide the public and regulatory officials with information regarding radiological environmental monitoring at the Fermi 2 Nuclear Power Plant.
l This information is intended for members of the general public who may be interested in i obtaining information on specific radiological environmental sam; ting and effluent I monitoring performed at Fermi 2. It also contains information for the Nuclear Regulatory Commission (NRC) to demonstrate regulatory compliance.
Safety is our top priority at Fermi 2. We want to assure all of our neighbors that our staff is dedicated to protecting the environment. This dedication has been demonstrated in the fact there has not been a liquid radioactive effluent discharge from Fermi 2 since 1994.
Fermi 2 is dedicated to being a liquid effluent zero discharge facility.
The Radioactive Effluent Release and Radiological Environmental Operating Report is produced annually, as required by the Nuclear Regulatory Commission, to present ,
detailed results of careful monitoring and measuring of radiation in the environment l around the plant. This report also includes details of the independent oversight incorporated into the Radiological Effluent and Environmental Monitoring Programs to l
( ensure program accuracy.
We at Detroit Edison are proud of the findings of this report, which demonstrate that the operation of Fermi 2 does not produce measurable levels of radiation in the environment.
In addition, nuclear energy's successful record of reducing overall U.S. fossil fuel emissions of sulfur dioxide and nitrogen oxides by over 1.9 billion metric tons continues to support the view that nuclear energy is environmentally friendly.
This report describes both the continual environmental radiation and effluent monitoring of plant systems. Both types of monitoring indicate that the operation of Fermi 2 does not result in exposure of people or the environment surrounding Fermi 2 to measurable amounts of radiation and therefore is well below the levels set by the Nuclear Regulatory Commission and the Environmental Protection Agency.
This report also contains detailed technical data that are included in the Appendices for review. But first, because we get a lot of questions, here is some basic information about nuclear energy and how nuclear power plants work.
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Fermi 2 - 1997 Annux!
Radioactive Ej]Tuent Release and -
Radiological Environmental Operating Report O Nuclear Energy Basics The Atom An atom is the smallest unit of matter that is recognizable as a chemical element. Atoms of different elements may also combine into systems called molecules, which are the smallest units of chemical compounds. In all these ordinary processes, atoms may be considered as the ancient Greeks imagined them to be: the ultimate building blocks of matter.
When strong forces are applied to atoms, however, the atoms may break up into smaller parts. Thus atoms are actually composites and not units, and have a complex inner structure of their own. By studying the processes in which atoms break up, scientists in the 20th century have come to understand many details of the inner structure of atoms.
i Simply described, atoms are made up of positively and negatively charged particles and particles that have no charge. These particles are called protons, electrons, and neutrons, respectively. The relatively large protons and neutrons are packed tightly together in a cluster at the center of the atom called the nucleus. Orbiting around this nucleus are one O er -ere - iier ei ctrees. 1 iectric iiv e tr i te- the 8 tive ca r8 er the electrons are balanced by the positive charges of the protons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other, which helps hold the atom together. Other attractive forces between the protons and neutrons keep the densely packed protons from repelling each other, thus preventing the nucleus from breaking apart.
Fission 1 As discussed above, in the nucleus of . not an atom, attractive forces between the protons and neutrons keep the protons from repelling each other which Neutron
[O riision Mwu g
Free Nutmns prevents the nucleus from breaking apart. These attractive forces are Atom \ .
known as the binding energy. If the binding energy is weak enough, the O .,_
nucleus can be split when bombarded 3 ,,,,
by a free neutron. When the nucleus splits or fissions, two or more smaller O
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l Fermi 2 - 1997 Annual Radleactive Effluent Release and \
Radiological En vironmental Operating Report n l b
atorm called fission products, form along with the release of more neutrons and energy in tne form of heat. The neutrons that are released during the first fission are then available to fission other atoms producing a chain reaction. Enrico Fermi is credited with achieving the first sustained nuclear chain reaction on December 2,1942. He and 42 other scientists constructed an " atomic pile" or nuclear reactor beneath the University of Chicago's athletic stadium.
Nuclear Reactor A nuclear reactor : a device in which a controlled nuclear fission chain reaction takes place. The fission reaction is initiated by the absorption of a neutron in a heavy nucleus l such as uranium-235. 'ihe process produces additional neutrons that can be used to induce further fissions, thereby propagating the chain reactien. When the reactor l components are appropriately adjusted, it is possible for the chain reaction to be self-sustaining.
Nuclear reactors are most commonly used to produce electric energy, although they are occasionally used as sources of thermal energy for heating. They are also designed as sources of neutrons used in research or for the production of radiopharmaceuticals.
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The typical U.S. power reactor is termed a light-water reactor (LWR) because it uses water in the form of H O2 as a moderator and coolant. Another type of power reactor uses an isotope of hydrogen know as deuterium D2 0 as a moderator; it is called a heavy-water reactor. As the name suggests, deuterium has twice the mass of hydrogen.
The engineering aspects of the design seek to convert the fission energy into a useful form of heat, usually high-pressure steam, to drive a turbine which is connected to an electric generator. The economic aspects of the design seek to optimize the physical and engineering design so as to minimize the cost of energy from the plant.
The core of a reactor is the region that contains the nuclear fuel. Neutrons from the fission process are released with relatively high energy. However, the probability of a neutron causing a fission in the fuel nuclei is much larger for low energy neutrons than for high energy neutrons. In order to slow neutrons down, it is common to surround the fuel with a moderator. Neutrons can interact with nuclei much like collisions between hard spheres. The neutron will lose energy most efficiently, i.e., in the fewest collisions, if the moderator nuclei are close to the mass of the neutron. Thus, moderators are made from light materials such as hydrogen in water, deuterium in heavy water, or carbon in f graphite. The physical arrangement of the fuel and moderator is a major element of l reactor physics.
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Fermi 2 - l997 Annual Radioactive Effluent Release and ;
Radiological Environmental Operating Report i/ %
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The LWR uses H O as the moderator and uranium dioxide, UO 2 2
, as the fue!. The fissionable isotope of uranium is U-235, which makes up only 0.7% of natural uranium.
It is not possible to design an LWR that uses natural uranium. In order to increase neutron produx n, the U-235 concentration in the fuel is increased. Such fuel is called
" enriched."
l Fuel for an LWR has a relatively simple structure. Uranium is pressed into small l
cylindrical pellets that are stacked in zirconium alloy tubes, referred to as " cladding", that are about 3.05 m (10 fa in length. The tubes are arranged in a square array called a " fuel assembly". A modern light-water reactor has hundreds of fuel assemblies in its core.
Reactor control is achieved by carefully balancing the neutron production rate from fission with the neutron loss rate. The common process for obtaining control is to adjust the amount of neutron absorber in the core. Control materials are placed in rods with the same dimensions as fuel rods and the set of control rods are inserted in the middle of a fuel assembly. The control rods are attached te a drive mechanism that moves the control i rods into or out of the core region. A typical set of control rods contains materials that are highly absorbent to neutrons such as silver, indium, boron carbide, and cadmium.
The control rods are inserted into the core when reactor shutdown is desired. The rods g are also inserted automatically in the event that unexpected conditions are detected.
! V The core, including fuel assemblies, control rods, and moderator, is a very large system.
The entire assemblage fits into a thick-walled steel pressure vessel, designed to withstand very high pressures, up to 2,500 psi. For LWRs, water is both the moderator and the coolant, that is, the agent used to remove fission energy from the core and transfer it to the electric generating segment of the system.
In the U.S. there are two types oflight-water reactors used for the generation of electric power. The most common type of reactor in use is the pressurized water reactor (PWR).
In a PWR plant, the coolant is heated by fission under pressure and then sent via the primary loop to a steam generator. In the steam generator, the hot water from the reactor transfers its heat to the secondary loop. The secondary loop is under low pressure and the water is transformed into steam, which in turn is fed to turbines to drive a generator. The second most common reactor is a boiling water reactor (BWR). In this type of reactor the coolant is permitted to boil within the reactor core. The steam emerging from the core is sent directly to a turbine rather than through a steam generator. Fermi 2 is a boiling water reactor.
1 I
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4 l
Fermi.1- H97 Ann =l Radioactive Ef]Tuent Release and l Radiological Environmental Operating Report O Fermi 2 is a General Electric class 4 BWR with a pressure suppression Mark I contair. ment. Fermi 2 has a generating capacity of approximately 1,100 megawatts at 22,000 volts of electricity. The reactor contains 185 control rods and 764 fuel assemblies. In the Fermi 2 BWR system, water is boiled within the reactor pressure vessel, producing saturated steam that passes through internal steam separators and dryers before continuing directly to the turbine. As the steam strikes the turbine blades, it spins both the turbine shaft and the generstor rotor. As the rotor turns, it passes through a magnetic field which transforms the mechanical energy into electrical energy.
The steam is then transformed back into water in the condenser and pumped back to the reactor vessel to start the heating process all over again. The cooling water has a separate cycle ofits own. It is pumped from a 30-million gallon water reservoir to the condenser.
The cool water passes through the condenser which removes the heat from the steam and is then pumped to the cooling towers.
1 The cooling towers use natural convection to return the water to its original temperature.
The water is then pumped into the reservoir to repeat the cycle. Since the cooling water does not come in direct contact with the steam from the reactor, the water in the reservoir ;
and cooling towers is not radioactive. Figure 2 illustrates the basic plant schematic for Fermi 2.
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l Figure 2 - Fermi 2 Nuclear Power Plant Basic Plant Schematic l s 1
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Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O ReactorSafety Equipment As the reactor operates, a large inventory of radioactive fission products accumulates in plant systems and represents a potential hazard. A fundamental objective of nuclear reactor design is to prevent accidents that could allow the escape of radioactivity. In l order for fission products to reach the environment several barriers must be overcome.
For an LWR, the first barrier is the fuel cladding that contains the fuel as well as the fission fragments. The cladding material is a high-strength alloy of zirconium capable of withstanding high pressures and high temperatures, well beyond normal reactor conditions. The second barrier is the pressure vessel, which is exceedingly strong. The third barrier is the containment building, which is a large, reinforced concrete building designed to withstand substantial pressure.
In order for any barrier to be breached, the system must lirst become overheated. There are two possible ways for this to occur. The first is for the fission rate to grow too rapidly for the coolant to remove all of the energy being created. The second is for the coolant system to fail and lose the ability to cool the fuel. Excessive fission energy production is monitored by numerous sensors throughout the core region; if they detect a rapid rate of increase in the fission process, the control rods are automatically inserted into the core to absorb the neutrons and this shuts down the reactor.
O There is another important design element that protects against the possibility of an uncontrolled chain reaction. The heating up of a local region of the reactor would cause p the nearby cooling water to boil, thereby reducing the water density through the creation of bubbles, or voids. It is a safety requirement of U.S. reactors that creation of coolant voids must, by itself, reduce the fission rate. The water space that surrounds a fuel rod is carefully designed so that a void reduces neutron moderation and hence reduces the fission rate. This property is not required in the Soviet Union and is a fundamental reason for the Chernobyl accident. The basic design of LWRs makes them safe against an uncontrolled chain reaction. Reactor design inherently limits positive reactivity, but an increase in reactivity is possible if multiple failures occur.
The design of safety systems begins by hypothesizing a number of different failures and then developing systems to mitigate the consequences of these failures. Such failures are known as design basis accidents. In order to obtain a license, a plant must show it is protected against the class of design basis accidents. The broad areas of concern include accidents within the plant as well as accidents involving the handling of radioactive spent fuel. Initiating events must include hardware failures, operator failures, and external events such as tornadoes.
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Fermi 2 - l997 Annu:1 Radioactive Effluent Release and Radiological En vironmental Operating Report O
One of the more important design basis accidents is the loss of coolant accident, or LOCA. The fission process itself ceases if a reactor loses its cooling water because the reactor goes suberitical. However, the fuel continues to heat up due to the stored thermal l
energy as well as from the decay heat of radioactive fission products. Without any l l coolant the cladding heats up and ultimately melts. Multiple safety systems have been designed and installed in all U.S. plants to prevent the clad from overheating by providing emergency cooling water. Such systems are collectively known as emergency core cooling systems, or ECCS. All such systems have multiple pathways for introducing water into the vessel under high-pressure or low-pressure conditions.
Radiation Radiation is energy emitted in the form of waves or particles. The term is used in a variety of ways, and sometimes refers to light and radio waves. But most often it refers to " ionizing" radiation, which is radiation that can produce charged particles, called ions, in materials it hits. In the ionizing process, electrons break away from atoms, giving the atom an electrical charge.
,3 When an atom breaks down - either naturally or in a controlled situation like a nuclear-Q power plant - and it releases waves or particles of energy, it is said to be radioactive.
Radioactive elements release five main types of energy:
Alpha radiation: positively charged particles that are barely able to penetrate the surface of the skin. It is the least-penetrating kind of radiation, and can be stopped completely by a single sheet of paper.
Heta radiation: More penetrating than alpha radiation, beta particles can be stopped by a thin sheet of aluminum.
! Gamma radiation: A penetrating radiation that can pass through the human body, but can be stopped by dense materials such as lead or concrete.
Neutron radiation: Produced during the fission process in a nuclear-power plant, but does not occur when the reactor is shut down.
X-ray radiation: Widely used in medical applications, it accounts for the major part of the public's man-made radiation exposure and corresponds to about 20 percent of the average annual exposure to man.
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Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O
Sources ofRadiation We are always in the presence of Typical Radiation Exposures radiation. Cosmic radiation from space uiiiirem annuaiiy per individuai covers the earth. Many rocks and average per a6ity minerals give off small amounts of radiation, including radon gas. Small UMNeleiREn'^r6HC] e Less than I amounts of radioactive materials are in EcoiisiineFPrsdstsB'M the air we breathe, and in the fbod and Television I liquids we eat and drink. The materials we use to build our homes, schools and F ' i r s6cWAit v tib i
' ' isining and farming T businesses also contain radioactive Burning fuels 2 materials. Even our bodies are mildly water supply 3 radioactive. Lumped together, these Building materials 7 d,,._
fi[, ;7]d things are called background radiation.
Diagnostic x-rays 40 Radiation is invisible, but it can be ;7Niitiiral_Biclig75iiiid2Q measured with special instruments. The Food and water 40 amount of radiation a person receives is cosmic rays 27 calculated in millirems (mrem). One Radon r t e air 200 mrem is quite small. It's the equivalent of viewing color television one hour a day ngure 3 - Typical Radiation Exposures: Source:
for one year, or spending five days in the #"d"""' C"""'" "" #"##"#"" #'"'"d"" ""#
, Measurements mountams.
On average, a person living in the U.S. receives about 300 to 360 mrem per year from all radiation sources. On the other hand, because of the low elevation and the absence of radioactive geologic formations, a person living within 10 miles of Fermi 2 receives an average of only about 125 mrem per year of background radiation as measured by thermoluminescent dosimeters (TLDs).
Natural exposure might come from cosmic radiation,25-30 mrem per year; food and water,40 mrem; the earth,28 mrem; the air,200 mrem; and building materials,7-10 mrem. Man-made radiation sources include chest x-rays, 40 mrem; a coast-to-coast airplane flight,5 mrem; watching color television,1 mrem; or living next to a nuclear power plant, less than 1 mrem.
BiologicalEffects ofRadiation When living tissue is exposed to large amounts of radiation, the tissue's molecular structure may be disrupted, triggering a chain of events that can destroy living cells, produce chromosomal damage or other injury which will overwhelm the natural repair 8
Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report f%
t i i
U processes. On the other hand, small amounts of radiation, such as natural background 2 levels, can be repaired via the same natural repair processes. The amount of radiation absorbed per gram of body tissue is expressed in rad (radiation absorbed dose). The unit i of measurement used to quantify the expected biological effect from radiation exposure in human son tissue is rem, or roentgen equivalent man.
J The effects of radiation on humans can be divided into two categories, somatic and genetic. Somatic effects are those which develop in exposed individuals, including a developing fetus. Genetic effects are those which may be observed in, or passed on to, offspring of the exposed individual.
Somatic effects can be divided further into acute and chronic effects. Acute effects are those that result from high radiation exposures in a short period of time. Chronic effects are those that result from radiation exposure over an extended period of time.
Much of our current knowledge of the biological effects of radiation comes from extensive laboratory animal experiments. Under laboratory conditions many crucial variables can be accurately controlled. These include, for example, the total dose, time interval and quality of radiation and characteristics such as age, sex and health status. l f
Q) While laboratory animal experiments serve as valuable models for human studies, there are limitations in drawing conclusims from biological effects observed in irradiated animals to potential health effects in numans. Thus, the most relevant studies are the epidemiological surveys that have focused on human populations who received radiation exposure under a variety of conditions. Most of these epidemiological studies involved population groups ranging from several hundred to more than 100,000 individuals. The i most important studies have involved the following groups:
Survivors of the Atomic Homb and Nuclear Weapons Tests - The most intensely studied human populations are the Japanese survivors of the atomic
- bombs in Hiroshima and Nagasaki. These people were exposed to radiation from the bombs. Studies have also been made of natives of the Marshall Islands who were accidentally exposed to fallout from nuclear weapons testing in 1954.
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t Medical Radiation - Large doses of radiation were given to treat various health l .
problems, such as ankylosing spondylitis (spinal impairment),. thymus !
enlargement, ringworm of the scalp, postpartum mastitis (breast inflammation) and cancer of the cervix. Routine chest fluoroscopic examination of women being treated for tuberculosis resulted in significant doses to the breast. Children whose mothers were irradiated during pregnancy have also been studied. i V
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Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological Enviro amental Operating Report Radium Dial Painters - Workers early in this century ingested radium-containing paint during the manufacture ofluminous watches, clocks and aircraft instruments through a practice of" tipping" paint brushes with their lips.
t Uranium Miners - Early in this century, certain large mines in Europe were worked for pitchblende, a uranium ore.
Radiologists - Pioneer medical scientists and physicians using x-rays, unaware of the potential hazards, accumulated large radiation doses principally to their hands.
These and other populations, many of whom continue to be studied, add to our current understanding and provide reliable data on health effects resulting from large doses of radiation. Among radiation scientists, there is strong agreement on the health effects and risks associated with large radiation doses (>100 rads). What remains uncertain and controversial is the assessment of potential health effects that may result from chronic doses of radiation. Since we cannot, at the present time, detect health effects in human populations exposed to low doses of radiation, it is conservative and appropriate to assume that there are risks associated with low level radiation exposure. However, it is l known that even a large dose given in small amounts over a prolonged period of time l l allows the body's natural mechanisms to replace or repair damaged cells, as it would l l( following many injuries.
Acute effects require radiation doses some thousands of times greater than those received j from natural sources. An acute whole-body dose of more than 450 rads, in the absence of l medical treatment, may be fatal in about half the individuals exposed. These effects may l appear within days or weeks of the exposure. Generally, a dose of at least 100 rads to the l l whole body within a short time is required to cause even the mildest symptoms. The j small amount of radioactivity routinely released from Fermi 2 is only a tiny fraction of !
l what is needed to produce even the mildest health effects.
l Genetic changes in the sperm or egg cells can result in health effects appearing in future
( generations. The fertilized egg contains all the genetic information necessary to produce I
the organs and tissues of a new individual. This information is carried in the cell's nucleus in small chromosomes, of which equal numbers are contributed by both parents.
r The chromosomes transmit the genetic information from one generation to the next.
The genetic material contained in the cell nucleus can be altered by a large variety of agents, including heat, chemicals, and both natural and man-made radiation. Genetic mutations occur randomly in all plant, animal and human populations and are considered 10
l l
Fermi 2 - l997 Annual 1 Radioactive Effluent Release and l Radiological Environmental Operating Report O l C to be the primary mechanism for evolutionary changes in all species. Epidemiological j
studies have shown that about five percent of all people are affected by a genetically transmitted or spontaneous disease at some time in their lives.
l Although laboratory studies of mice exposed to large doses of radiation for many ,
generations have shown genetic effects, d.tudies of humans have not yet produced reliable evidence of effects on man. It is difficult to measure most mutations because they are difficult to observe and are randomly distributed within a population group. Of the 35,000 children born to parents irradiated at Hiroshima and Nagasaki, at an assumed average parental dose of 25,000 to 35,000 millirads (25 to 35 rads), there has been no observable increase in genetic defects. Using all the information available, scientists have estimated that about 100,000 millirads (100 rads) to each person in a large
( population would be required to double the genetic mutations occurring naturally in a non-irradiated population.
1 Benefits ofNuclear Power Nuclear power plays an important part in meeting today's electricity needs, and will continue to serve as an important source of electric energy well into the future. Nuclear power entered the 1980s as an alternative energy source and emerged from the decade as (j the second largest source of U.S. electricity, meeting over 20 percent of national demand.
Nuclear power plants reduce U.S. dependence on foreign oil. Currently, the U.S. imports almost half of the oil it uses - at a cost of nearly $1 billion per week. However, nuclear power cuts the demand for foreign oil by more than 300 million barrels armually.
Studies show that U.S. economic growth has been fueled largely by electric power.
There is a close and continuing connection between the growth of the economy and the supply of electricity. Nuclear energy is an important contributor to maintaining the US's j economic and industrial strength. !
l As the population grows, the demand for electricity increases. Since 1973, the U.S. l population grew from 212 million to 250 million and electricity demand rose 61 percent. i The U.S. Department of Energy (DOE) projects that our need for electricity will increase 24 percent between 1989 and the year 2000, and 51 percent by 2010. Nuclear power plants will be an important part of meeting that need.
Because nuclear power plants do not bum fossil fuels, they do not emit combustion by- j products. By substituting for other fuels in electricity production, nuclear power has i significantly reduced U.S. and global emissions of carbon dioxide, the chief" greenhouse" gas. Since 1973, U.S. nuclear power plants have reduced the cumulative amount of
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l Fermi 2- l997 Annual Radioactive Effluent Release and l Radiological Environmental Operating Report
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l V carbon dioxide emissions by 1.6 billion metric tons. In 1993 alone, U.S. nuclear power l plants prevented the discharge of 133 million metric tons of carbon into the atmosphere. l l
All methods of producing electricity affect the enviro.1 ment to some degree, but the impact of nuclear power is minimal.
Sources ofRadioactivity Releasedfrom Nuclear Power Plants l During the normal operation of a nuclear power plant, most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces which have been activated are present in the primary coolant water. The four types of radioactive material released are noble gases, iodine, particulate, and tritium.
Noble Gases Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. These noble gases are released continuously at g)
(
low levels while the reactor is operating, and releases may be increased when the reactor is depressurized or when there are leaks in the fuel cladding. Noble gas releases to the environment are reduced by plant systems which delay release of these gases from the plant, which allows a portion of the noble gas activity to decay within plant systems after i it is released from the fuel. I Noble gases are biologically and chemically nonreactive. They do not concentrate in humans or other organisms. They contribute to human radiation dose by being an j external source of radiation exposure to the body. They are readily dispersed in the atmosphere. In 1997, krypton-85m, krypton-87, krypton-88, xenon-129m, xenon-133, xenon-133m, xenon-135, xenon-135m, xenon-137, and xenon-138 were detected in gaseous etiluent samples. The half lives of these noble gases range from 4 minutes l (xenon-137) to 9 days (xenon-129m).
Iodines andParticulates '
I l
Fermi 2 is required to calculate offsite dose due to releases ofiodine-131 and iodine-133, which are radioisotopes ofiodine with half lives of 8 days and I day, respectively, and particulate with half-lives greater than 8 days in gaseous and liquid effluents. The principal radioactive particulate released are fission products (e.g., cesium-134 and cesium-137) and activation products (e.g., cobalt-58 and cobalt-60). Annual releases of j (v
) these isotopes are small. Factors such as their high chemical reactivity and solubility in 12
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Fermi 2 - 1997 Annux!
Radioactive Effluent Release and Radiological Environmental Operating Report water, combined with the high efficiency of gaseous and liquid processing and radwaste systems, minimize their discharge.
The main contribution of radioactive iodine to human dose is dose to the thyroid gland, where the body concentrates iodine, resulting from inhalation or ingestion of these )
iodines. Radioactive cesituns and cobalts, when ingested or inhaled, contribute to radiation exposure of tissues such as the muscle, liver, and intestines. These iodines and particulate are also a source of external radiation exposure if deposited on the ground.
Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclides in liquid effluents. It may also be present in gaseous effluents, but it has usually been at such low levels that it has been below detection limits in gaseous effluent samples at Fermi 2. !
Tritium is produced in the reactor coolant as a result of neutron interaction with deuterium (also a hydrogen isotope) present in the water, and it is also a fission product.
Plant Effluent Monitoring Effluents are strictly controlled to ensure that radioactivity released to the environment is l as low as reasonably achievable and does not exceed regulatory limits. Effluent control includes the operation of meritoring systems, in-plant and environmental sampling and analyses programs, quality nssurance programs for effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring.
The radioactive waste tretunent systems at Fermi 2 are designed to collect, process, and/or delay the release ofliquid and gaseous wastes which contain radioactivity. For example, the 2.0 and 2.2 minute holdup pipes delay the release of radioactive gases so that radioactive decay can occur prior to release. The offgas system provides additional delay for such gases.
Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits. These instruments provide a continuous indication of the radioactivity present at the release points. Each instrument is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure that applicable limits will not be exceeded. In some cases these alarms restrict the release. For example, if the liquid radwaste effluent monitor alarms, a release in progress is automatically stopped. Also, f
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Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report
' several alarms cause building ventilation systems to be shut down and/or gaseous releases to be diverted to the standby gas treatment system.
l All wastes are evaluated to identify the specific concentrations of radionuclides being i released. Sampling and analysis provide a more sensitive and precise method of l
determining effluent composition than monitoring instruments.
l A meteorological tower is located on the Fermi 2 site. It is linked to computers which
! record the meteorological data. These data are used in calculating dispersion and deposition factors, which are essentially dilution factors between plant release points and points offsite. Coupled with the effluent release data, these factors are used to calculate dose to the public.
- Beyond the plant, devices maintained in conjunction with the Radiological l Environmental Monitoring Program constantly sample the air in the surrounding l l environment. Frequent samples of other environmental media, such as water and '
! vegetation, are also taken to determine if buildup of deposited radioactive material has occurred in the area.
I
- O.
O Exposure Pathways to People Radiological exposure pathways define the methods by which people may become exposed to radioactive material. The major pathways of concern are those which could cause the highest calculated radiation dose. These projected pathways are determined j from the type and amount of radioactive material released, the environmental transport
- mechanism, and the use of the environment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area.
An important factor in evaluating the exposure pathways is the use of the environment.
This is evaluated in the annual Land Use Census. Many factors are considered, such as the locations of homes, gardens, and milk or meat animals in the area.
The release of radioactive gaseous effluents involves pathways such as external whole body exposure, deposition of radioactive material on plants, deposition on soil, inhalation
~ by animals raised for human consumption, and inhalation by humans. The release of radioactive material in liquid effluents involves pathways such as drinking water and fish consumption.
l l 14 l
E_____---_---___-__--_-__-._--.___
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O
G l Although radionuclides can reach humans by many different pathways, some result in i greater dose than others. The most significant pathway is the exposure pathway which will provide the greatest dose to a population, or to a specific individual. Identification of
- the most significant pathway depends on the radionuclides involved, the age and diet of the individual, and the location of the individual's residence. The doses calculated may
, be delivered to the whole body or to a specific organ. The organ receivmg the greatest )
I fractior, of the dose is important in determining coinpliance with dose limits.
Dose Assessment Dose is energy deposited by radiation in an exposed individual. Whole body exposure to radiation involves the exposure of all organs. Most exposures due to external sources of radiation are of this type. Both non-radioactive and radioactive elements can enter the I body through inhalation or ingestion. When they do, they are usually not distributed evenly. For example, iodine concentrates in the thyroid gland, cesium collects in muscle l . and liver tissue, and strontium collects in bone tissue.
The total dose to organs from a given radionuclides depends on the amount of radioactive
'A material present in the organ and the amount of time that the radionuclides remains in the h organ. Some radionuclides remain for very short times due to their rapid radioactive ,
decay and/or elimination rate from the body, while other radionuclides may remain in the I body for longer periods of time. Also the form of the radionuclides (soluble vs. insoluble) and the method of uptake influence residence times in the body.
The dose to the general public in the area surrounding Fermi 2 is calculated for periods of gaseous release and for each liquid release. The dose due to radioactive material released in gaseous effluents is calculated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, the locations of exposure pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inhalation, food consumption). The dose due to radioactive material released in liquid effluents is calculated using factors such as the total volume ofliquid, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption). These calculations produce a conservative estimation of the dose.
l The Radiological Environmental Monitoring Program (REMP) was established at Fermi 2 for several reasons: to provide a supplementary check on the effluent controls, to assess the radiological impact of the plant's operation on the surrounding area, and to determine compliance with applicable radiation protection guides and standards. The REMP was established in 1978, seven years before the plant became operational. This preoperational surveillance program was established to describe and quantify the O
l 15 L . . . . . _
Ferm!2 - 1997 Annu:1 Radioactive Effluent Release and Radiological Environmental Operating Report f'"%
d radioactivity, and its variability, in the area prior to the operation of Fermi 2. After Fermi 2 became operational in 1985, the operational surveillance program continued to measure radiation and radioactivity in the surrounding areas.
i A variety of environmental samples are collected as part of the REMP at Fermi 2. The
{
selection of sample types is based on the established pathways for the transfer of radionuclides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population characteristics, and land usage in the area of interest. The selection of l sampling frequencies for the various environmental media is based on the radionuclides of interest, their respective half-lives, and their behavior in both the biological and ]
physical environment. l Preoperational Surveillance Program The federal government requires nuclear facilities to conduct radiological environmental I monitoring prior to constructing the facility. This preoperational surveillance program is I aimed at collecting the data needed to identify pathways, including selection of the radioisotope and sample media combinations to be included in the surveillance program bq conducted after facility operation begins. Radiochemical analyses performed on the environmental samples should include not only those nuclides expected to be released during facility operation, but should also include typical fallout radionuclides and natural background radioactivity. All environmental media with a potential to be affected by facility operation, as well as those media directly in the major pathways, should be sampled on at least an annual basis during the preoperational phase of the environmental surveillance program.
The preoperational surveillance design, including nuclide/ media combinations, sampling frequencies and locations, collection techniques, and radioanalyses performed, should be l carefully considered and incorporated in the design of the operational surveillance program. In this manner, data can be compared in a variety of ways (for example: from year to year, location to location, etc.) in order to detect any radiological impact the facility has on the surrounding environment. Data collection during the preoperational phase should be planned to provide a comprehensive database for evaluating any future i changes in the environment surrounding the nuclear facility.
- p J
16
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report O
Fermi 2 began its preoperational environmental surveillance program seven years before the plant began operating in 1985. Data accumulated during those early years provide an extensive database from which environmental monitoring personnel are able to identify trends in the radiological characteristics of the local environment. The environmental sc veillance program at Fermi 2 will continue after the plant has reached the end ofits econo 4nically useful life and decommissioning has begun.
1 OperationalSurveillance Program Objectives The operational phase of the environmental surveillance program at Fermi 2 was designed with the following objectives in mind:
e to determine whether any significant increase occurs in the concentration of radionuclides in major pathways; e to identify and evaluate the buildup, if any, of radionuclides in the local environment, or any changes in normal background radiation levels; O e to verify the adequacy of the plant's controls for the release of radioactive materials; e to fulfill the obligations of the radiological surveillance sections of Fermi 2's Offsite Dose Calculation Manual.
Program Overview The Radiological Environmental Monitoring Program (REMP) at Fermi 2 is conducted in accordance with Title 10, Code of Federal Regulations, Part 50; Regulatory Guide 4.8; the Fermi 2 Offsite Dose Calculation Manual (ODCM) and plant operating procedures.
Samples are collected either weekly, monthly, quarterly, semiannually, or annually, depending upon the sample type and nature of the radionuclides of interest.
Environmental samples collected by Fermi 2 personnel are divided into four general types:
O 17
l l
l Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological En virenmental Operating Report
(
h
- x. s e direct radiation - measured by thermoluminescent dosimeters (TLDs). l
- atmospheric - including samples of airborne particulate and I airborne radioiodine.
e terrestrial - including samples of milk, groundwater, and broad leaf vegetation.
e aquatie -- includ ng samples of drinking water, surface water, fish, and shorr. sine and bottom sediments.
REMP samples are col.'ected onsite and offsite up to 20 miles away from the plant.
Sampling locations are dialed into two general categories: indicator and control.
Indicator locations are those which would be most likely to display the effects caused by the operation of Fermi 2. Generally, they are located within ten miles of the plant.
Control locations are those which should be unaffected by plant operations. Typically, these are more than ten miles away from the plant. Data obtained from the indicator locations are compared with data from the control locations. This comparison allows
{n)
REMP personnel to take into account naturally occurring background radiation or fallout from weapons testing in evaluating any radiological impact Fermi 2 has on the surrounding environment. Data from indicator and control locations are also compared with preoperational data to determine whether significant variations or trends exist.
SampleAnalysis When environmental samples are analyzed, several types of measurements may be performed to provide information about the radionuclides present. The major analyses that are performed on environmental samples collected for the Fermi 2 REMP include:
Gross beta analysis measures the total amount of beta emitting radioactive material present in a sample. Beta radiation may be released by many different radionuclides.
Since beta decay gives a continuous energy spectrum rather than the discrete lines or
" peaks" associated with gamma radiation, identification of specific beta emitting nuclides is much more difficult. Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal concentrations of beta emitting radionuclides; it does not identify specific radionuclides. Gross beta analysis merely acts as a tool to identify
! samples that may require further analysis.
rm
)
18
1 Fermi 2 - 1997 Annurl Radioactive Effluent Release and j Radiological Environmental Operating Report Gamma spectral analysis provides more specific information than does gross beta analysis. Gamma spectral analysis identifies each gamma emining radionuclides present in the sample, and the amount of each nuclide present. Each radionuclides has a very specific " fingerprint" that allows for swift and accurate identification. For example, gamma spectral analysis can be used to identify the presence and amount ofiodine-131 in a sample. Iodine-131 is a man-made radioactive isotope ofiodine that may be present in l the environment as a result of fallout from ' nuclear weapons testing, routine medical, or routine releases from nuclear power stations.
Tritium analysis indicates whether a sample contains the radionuclides tritium (H-3) and the amount present. Tritium is an isotope of hydrogen that emits low energy beta particles.
Strontium analysis identifies the presence and amount of strontium-89 and strontium-90 in a sample. These man-made radionuclides are found in the environment mainly as a result of fallout from nuclear weapons testing. Strontium is usually incorporated into the calcium pool of the biosphere. In other words, strontium tends to replace calcium in living organisms and becomes incorporated in bone tissue. The principal strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition jh from airborne releases.
!( )
Gamma Doses measured by thermoluminescent dosimeters while in the field are determined by a special laboratory procedure. j Oflen samples will contain little radioactivity, and may be below the lower limit of detection for the particular type of analysis used. The lower limit of detection (LLD) is the smallest amount of sample activity which can be detected with a reasonable degree of confidence, at a predetermined level. When a measurement of radioactivity is reported as j less than LLD (<LI.D), it means that the radioactivity is so low that it cannot be ?
accurately measured with any degree of confidence by that particular method for an individual analysis. I 1
Many radionuclides are present in the environment due to sources such as cosmic j radiation and fallout from nuclear weapons testing. Some of the radionuclides present l are:
e tritium, present as a result of the interaction of cosmic radiation with the upper atmosphere and as a result of routine release from nuclear facilities. i
. beryllium-7, present.as a result of the interaction of cosmic 1 V) radiation with the upper atmosphere. l 19 3
Fermi 2 - I997 Annual Radioactive Effluent kelease and Radiological En vironmental Operating Report e cesium-137, a man-made radionuclides which has been
- deposited in the environment, (for example, in surface soils) as a result of fallout from nuclear weapons testing and routine releases from nuclear facilities.
e potassium-40, a naturally occurring radionuclides normally found throughout the environment (including humans) e fallout radionuclides from nuclear weapons testing, including strontium-89, strontium-90, cesium-137, cerium-141, cerium-144, and ruthenium-106. These radionuclides may also be released in minute amounts from nuclear facilities The radionuclides listed above are expected to be present in many of the environmental samples collected in the vicinity of the Fermi 2. The contribution of radionuclides from the operation of Fermi 2 is assessed by comparing sample results with preoperational data, operational data from previous years, control Ic. cation data, and the types and amounts of radioactivity normally released from the Fermi 2 in liquid and gaseous effluents.
p%)
QualityAssurance
- An important part of the environmental monitoring program at Fermi 2 is the Quality Assurance Progre.n (QA). It is conducted in accordance with the guidelines specified in NRC Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring l Programs." The QA program is designed to identify possible deficiencies in the REMP so that corrective actions can be initiated promptly. Fermi 2's Quality Assurance program also ptovides confidence in the results of the REMP through:
e performing regular audits (investigations) of the REMP, including a careful examination of sample collection techniques and record keeping; e performing audits of tH wndor laboratory which analyzes l
'the environmental samples; e requiring the analytical vendor laboratory to participate in an approved Cross-Check Program; l'
())
r 20
Fermi 2- 1997 Annual Radioactive Effluent Release and
[ Radiological En vironmental Operating Report
- splitting : samples prior to analysis by an independent laboratory, and then comparing the results for agreement, and, finally;
- requiring the analytical laboratory to perform in-house spiked sample analyses.
QA audits and inspections of the Fermi 2 REMP are performed by Fermi 2's QA department and the NRC, respectively. In addition, the NRC also performs independent environmental monitoring in the vicinity of Fermi 2. The types of samples collected and the sampling locations used by the NRC were incorporated into Fermi 2's REMP. Hence, the analytical results from the different programs can be compared. This practice of comparing results from identical samples, collected and analyzed by different parties, provides a valuable tool to verify the quality of the laboratory's analytical procedures and the data generated.
O Q
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Fermi 2 - 1997 Annual Rt.dioactive Effluent Release and Radiological Environmental Operating Report O
Radioactive Effluent Monitoring Results This section summarizes the results of effluent monitoring and offsite dose calculation for the year 1997, as well as a listing of radioactivity contained in Fermi 2 wcste shipped for l
burial. Calculations of offsite doses are compared with Nuclear Regul. wry Conunission limits, and these limits are summarized in Appendix E. Appendix E also contains a detailed discussion of the methods used to determine quantities of radioactivity released in effluents, the types of solid radwaste, as well as tables of individual radionuclides released in effluents and shipped as solid radwaste.
There were no releases ofliquid radioactive effluents from Fermi 2 in 1997. In fact, there has not been a liquid radioactive discharge from Fermi 2 since 1994. The 1997 gaseous effluent releases are summarized in the following tables. There were no abnormal releases of radioactive material, i.e. releases not perfonned in accordance with the Fermi 2 license and implementing procedures, in 1997.
The data in the following tables represent continuous releases; batch gaseous releases (containment purges) did not contribute significantly to the totals. In 1997, there were 3 containment purges in which radioactivity was detected. Of these, one purge of the torus lasted 228 minutes, another lasted 3095 minutes, and a drywell purge lasted 1693 O minutes. The total duration of these purges was 5016 minutes, and the average duration was 1672 minutes.
Note that values in the tritium summary table are preceded by the "less than" symbol.
These values represent the lower limit of detection (LLD) in units of microcuries per cubic centimeter (uCi/cc) for individual samples, and indicate that tritium was not detected in gaseous effluent samples in 1997.
Table 1 - Fission and Activation Gases (Noble Gases) Summary
~ Quarter 1 ~ Quarter 2 ' : Quarter 3 : Quarter'4 ;
Total Release 0.00E+00 3.16E+01 3.35E+02 4.48E+02 (curies)
Average Release 0.00E+00 4.02E+00 4.21 E+01 5.64E+01 Rate for Period (pCi/sec)
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Fermi 2 - l997 Annual Radioacthe Effluent Release and Radiological Environmental Operating Report O
Table 2 - Radiciodines Summary
^
' . , Quarter 1 Quarter 2. Quarter 3 > = Quarter 4 Total I-131 7.83E-06 2.12E-03 4.72E-03 5.59E-03 (curies)
Average Release 1.01 E-06 2.70E-04 5.94E-04 7.03E-04 Rate for Period
( Ci/sec)
Table 3 - Particulate Summary w Quarter 1- Quarter 21 ' >: Quarter 3 t ' Quarter'4?
Particulate with 1.98E-05 1.58E-04 1.77E-03 1.40E-03 halflives > 8 days (curies)
Average 2.54E-06 2.01 E-05 2.23E-04 1.76E-04 Release Rate for O Period ( Ci/sec)
Gross Alpha 1.63E-06 1.75E-06 1.90E-06 1.81 E-06 Radioactivity (curies)
Table 4 - Tritium Summary W Quarter 1- Quarter 2LL ; Quarter 31 .! Quarter.4 Total Release <3.2E-08 <3.2E-08 <3.2E-08 <3.2E-08 (LLD in uCi/cc)
The offsite dose impact of the above releases was evaluated by calculating organ doses to the most highly exposed individual living near the plant due to I-131,1-133, tritium, and particulate with halflives greater than 8 days. This exposure is assumed to be occurring via the pathways of inhalation, vegetation ingestion, and direct radiation from material deposited on the ground. The results of this calculation are shown in the following .able:
l l
l l
O l i
23
Fermi 2 H97 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O
Table 5 s 9 41997 Gaseous EfBuent Dese topwW Organi f 7dP3ceht EsittiHQtsiesSingleifrMS y,
qyo,,mye My:;yyyyyumqp
. Bone t w 2,. , j 0.01 mrem Livert i 1 0.0009 mrem Thyroid . , 0.15 mrem Kldney ; 0.001 mrem Lung 7 0.0006 mrem GI-LLI a- J 0.001 mrem lTstal'liddy . 2 0.002 mrem The highest single organ dose is 0.15 mrem to the thyroid. This is 1% of the federal limit of 15 mrem specified in 10CFR50, Appendix 1.
Another dose calculation performed on the above relcase data is that fer gamma and beta air dose et the 'ite boundary due to noble gases. In 1997, gamma air dose was 0.2 mrad and beta air dose was 0.3 mrad. These doses represent 2% and 1.5% of the 10CFR50 gamma and Feta annual air dose limits, respectively. (The gamma dose limit is 10 mrad and the beta dose limit is 20 mrad.)
Title 40, Part 190 of the Code of Federal Regulations requires that dose to an individual in the unrestricted area from the uranium fuel cycle, including direct radiation dose, be limited to 25 mrem / year to the total body and 75 mrem / year to the thyroid. During 1997, there was no measurable direct radiation dose beyond the site boundary as shown by offsite TLD readings. Also, offsite dose due to effluents is an extremely small fraction of the 40 CFR 190 limits. Therefore, Fermi 2 was in compliance with 40 CFR 190 in 1997.
Potential dose to visitors at Fermi 2 due to all radioactive effluents, including noble gases, was also calculated. The ODCM considers persons visiting the Fermi 2 Visitors Center (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> / year), and persons ice fishing on Lake Erie near the plant (240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> / year), to be visitors. Using ODCM assumptions about these categories of visitors, the maximum potsatial dose to a visitor to Fenni 2 in 1997 was 0.02 mrem to the maximally exposed organ (thyroid) and 0.01 mrem to the total body.
Also, the dose to the entire population within a fifty mile radius of Fermi 2 (about 6 million people) was calculated. This dose was estimated to be 1.6 person-rem for 1997.
This dose is insignificant compared to the background radiation dose to this population of approximately 1.8 million person-rem.
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Ferm!2 - l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O
The radioactivity and volume of Fermi 2 solid waste received at the Barnwell, SC, burial l facility in 1997 is summarized in the following table.
Table 6 - Solid Waste Received At Barnwell, SC $
g .
,, ,;;,. ;ggg;gogg;_
h [ _.
. Type of waste N S.
Unit '
's tl2 morilthp
- period %
jastivityp error,%
Spent resins, sludges, etc. m' l.13E+02 curies 6.29E+02 1 25 Dry compressible waste, m' 4.39E+01 contaminated equipment, etc. curies 2.82E+00 1 25 Radioactive solid waste shipments from Fermi 2 in 1997 are summarized in the following table.
Table 7 - Solid Waste Shipments Type;ofshipment/, , Number of . Mode of w > D_estination y T s .
s' solidification proc'ess ' -
'shipmenis:
transportation 9 ' c-s W "i 'S P .>
O Spent resin, sludges, etc. 22 tractor trailer, tractor trailer Barnwell, SC, GTS Duratek (SEG), and Molten Metal with cask Technologies Dry compressible waste, etc. 20 tractor trailer GTS Duratek (SEG), Hake, Manufacturing Sciences, Chem Nuclear Consolidation Facility, and ALARON In 1997, no radiation instrumentation was out of service longer than the time limits specified in the ODCM. Also, there were no mejor changes to radioactive waste systems in 1997, and no outside temporary tank exceeded the 10 curie content limit. There was one revision to the ODCM in 1997, and the entire revised ODCM is being submitted to the NRC concurrently with this report. The only change made in this revision was to extend the allowable date for submittal of the Annual Radioactive Effluent Release Report to the end of April.
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Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report (3
U Radiological EnvironmentelMonitoring Program Results i
Direct Radiation Monitoring Radiation is a normal component of the environment resulting primarily from natural sources, such as cosmic radiation and naturally occurring radionuclides; and to a lesser extent, from manmade sources such as fallout from past nuclear weapons testing. The earth is constantly bombarded by cosmic radiation in the form of high energy gamma rays and particulate. The earth's crust also contains natural radioactive material, such as uranium and potassium-40, which contributes to the background radiation. Direct radiation monitoring primarily measures ionizing radiation from cosmic and terrestrial sources.
Thermoluminescent Dosimeters Detroit Edison uses thermoluminescent dosimeters (TLDs) to measure direct gamma radiation in the environs of Fermi 2. Thermoluminescence is a process by which ionizing Q
V radiation interacts with a phosphor which is the sensitive material in the TLD. Energy is trapped in the TLD material and can be stored for several months or years. This provides an excellent method to measure the dose received over long periods of time. The energy that was stored in the TLD as a result of interaction with radiation is released and measured by a controlled heating process in a calibrated reading system. As the TLD is j heated, the phosphor releases the stored energy in the form oflight. The amount oflight detected is directly proportional to the amount of radiation to which the TLD was exposed. This reading process then rezeros the TLD and prepares it for reuse.
Fermi 2 has 67 TLD locations within a 15 mile radius of the plant. The TLDs are thoroughly tested to comply with NRC Regulatory Guide 4.13 and American National Standards Institute's (ANSI) publication N545-1975, which assure accurate measurements under varying environmental conditions before being placed in the field. ]
Indicator TLDs are located within a ten mile radius of the plant and control TLDs are l located at a distance that is outside the influence of the plant. While in the field, TLDs are exposed to background radiation and, if measurable, gaseous effluents and direct i radiation from Fermi 2. Environmental TLDs are exchanged and processed on a l quarterly basis. The TLDs' data are reported in terms of milliroentgen per standard .
quarter (mR/std qtr), a standard quarter being 91 days. Regardless of the duration of TLD exposure in the field, the data have been normalized to a standard quarter to allow convenient intercomparisons with the net value. I t
v i
26 !
Fermi 2 -!997 Anna:I Radioactive EDluent Release and Radiological Environmental Operating Report O In 1997, the average exposure for TLDs at all indicator locations was 15.8 mR/std qtr and for all control locations was 14.3 mR/std qtr. These exposures are consistent with preoperational and past operational measurements as show in Figure 4.
Formi 2 Annual Average TLD Gamma Exposure 25 20 l 15- l gQ g 10 E
Preoperational Operational 5, l l
0
$$@ EE@ ES$5EEEEEOEO$$ l Year
-o-Indicator --o-Control Figure 4 - Fenni 2 Annual Average TLD Gamma Exposure; The similarity between indicator and control results demonstrates that the operation of Fermi 2 has not caused any abnormal gamma exposure.
I i
Atmospheric Monitoring A potential exposure pathway to people is inhalation of airborne radioactive materials.
Detroit Edison continuously samples the ambient air surrounding Fermi 2 for radioactivity. Air sampling began in 1979, during the preoperational program. At each sampling location, a mechanical air sampler is used to draw a continuous volume of air through two filters designed to collect particulate and radioiodines. Air samples are collected weekly and analyzed for gross beta radiation and iodine-131 gamma radiation.
The particulate filters for each sampling location are combined on a quarterly basis to form a " composite sample" and are analyzed for strontium-89/90 beta radiation and gamma emitting isotopes. There are four indicator sampling locations which were selected based on an evaluation of the predominant wind directions. A fifth sampling location is approximately 14 miles west of the plant and is considered to be in a location i unaffected by the operation of the plant.
27 L___________ _____ _ _ _
i Fermi 2 - 1997Annu11 Radioactive Effluent Release and Radiological Environmental Operating Report fh v
AirSampling On October 16,1980, the Peoples Republic of China conducted an atmospheric nuclear weapon test. The fallout from this test was detected in Fermi 2 preoperational environmental air samples in 1981 (see Figure 2). The average gross beta for 1981 was 1.60E-1 pCi/ cubic meter for indicator samples and 2.40E-1 pCi/ cubic meter for control samples which was a factor of ten times greater than background gross beta. Ganuna spectroscopic analyses of the particulate filters indicated cesium-137, cerium-141, cerium-144, ruthenium-103, rutheniam-106, zirconium-95, niobium-95, manganese-54, and antimony-125 in the atmosphere as a result of this test. In 1986, as shown in Figure 5, there was a slight increase in gross beta activity and a 2.70E-1 pCi/ cubic meter " spike" i in the iodine-131 activity. These elevated levels in 1986 are attributed to the nuclear l accident at Chernobyl on April 26,1986. For all other years, the iodine-131 activity was l below the lower limit of detection (LLD) of 7.0E-2 pCi/ cubic meter.
During 1997, two hundred and fifty-seven (257) particulate air filters were collected and analyzed for gross beta activity and two hundred and fifty-seven (257) charcoal filters I were collected and analyzed for iodine-131. The average gross beta for indicator samples was 2.54E-2 pCi/ cubic meter and 2.49E-2 pCi/ cubic meter for control samples. None of
_g the charcoal filters collected showed detectable levels ofiodine-131. The following table V contains the annual average gross beta results of all five sample locations for 1997.
1997 Average Gross Heta Concentrations in Air Particulate I (pCi/m')
Table 8 StationE 'De-..pGons(sector / distance):Y+ **s? Annual AverageP API-l (I) Estral Beach (NE/1.4 mi.) 2.55E-2 API-2 (I) Site Boundary (NNW/0.6 mi.) 2.58E-2 I API-3 (I) Site Boundary (NW/0.6 mi.) 2.41 E-2 API-4 (C) North Custer Rd. (W/14 mi.) 2.49E-2 API-5 (I) Eric St. (S/1.2 mi.) 2.60E-2 (I) = Indicator Station (C) = Control Station Twenty (20) quarterly particulate filter composites were prepared and analyzed for strontium-89/90 and gamma emitting isotopes. Only naturally occurring potassinm-40 and beryllium-7 were detected in both indicator and control samples.
p d
28
Fermi 2 - l997 Annuil Radioactive Egluent Release and Radiological Environmental Operating Report O In conclusion, the atmospheric monitoring data is consistent with preoperational and prior operational data and shows no adverse long-term trends in the environment attributable to Fermi 2 as illustrated in Figures 5 and 6.
H6sv J Gross Beta and lodine-131
,dvity in Air Samples 3.0E41 - Chinese Weapone Test Chemobyl Event 2.0E41 -
1.0E41 -
g no d b : :^ : : : : : :
!!8a!8EEE!!8888888 Year
- Indicator Gross Beta -+--Control Gross Beta lodine - 131 Figure 5 - Historical Gross Beta and Iodine-131 Activity in Air Samples; The similarity between indicator and control gross beta results demonstrates that the operation of Fermi 2 has had no adverse long-term trends in the environment. The lower limit of detection (LLD) for iodine-131 is 0.07 pCi/ cubic meter.
Fermi 2 l Air Particulate Gross Beta for 1997 l
6.0E42 -
5.0E42 -
l 4.0E42 -
t 3.0E42 -
g 2.0E42-S 1.0E42-0.0E+00 , ,,,, , , , , , , , , , , , , , , ,
5k@$EEEEE555k33$$
akas s=skss6k nas$$$8kEE$5assinskak Collection Date
--o-Indicator --o--Control l Figure 6 - Fermi 2 Air Particulate Gross Beta for 1997; The concentration of beta emitting radionuclides in airbome particulate samples was essentially identical at indicator and control locations. Gross beta activity varies throughout the year and is primarily
'O an effect of seasonal precipitation.
29
Fermi 2- !997 Annual ^
Radioactive Effluent Release and Radiological Environmental Operating Report O
g Terrestrial Monitoring Radionuclides released to the atmosphere may deposit on soil and vegetation, and therefore, may eventually be incorporated into the human food chain. To assess the impact of Fermi 2 operations to humans from the ingestion pathway samples of milk, breen leafy vegetables, and groundwater are collected and analyzed for radioactivity. The following sections discuss the type and frequency of terrestrial sampling, analyses performed, and a comparison of 1997 data to previous operational and preoperational data.
Milk Sampling The milk sampling portion of the REMP is perhaps one of the most important aspects of the program. This is because a major pathway in the human food chain is the j consumption of milk from grazing animals (dairy cows or goats) due to biological concentration and the short turn around time in this pathway. Milk is collected from one indicator location and one control location semimonthly when animals are in the pasture, I and monthly when the animals are on stored feed. The milk is analyzed for iodine-131, O gamma emitting isotopes, and strontium-89/90. At times when milk samples are not available, grass samples are collected at both the control milk sample location and the.
location.where milk is not available. Grass samples are analyzed for iodine-131 and other gamma emitting isotopes.
Milk sampling began in 1979 during the preoperational program. .During this time period, milk samples were analyzed for iodine-131 and other gamma emitting isotopes.
Cesium-137 and naturally occurring potassium-40 were the only isotopes detected in milk -
samples during the preoperational program. The' cesium-137 concentration averaged 3.60E+0 pCi/ liter and is due a past atmospheric nuclear weapons testing. In 1986, after.
the_ nuclear accident at Chernobyl iodine-131 and cesium-137 were detected in both indicator and control milk samples. The average concentration for iodine-131 was 3.70E+0 pCi/ liter and 6.60E+0 pCi/ liter for cesium-137. ;
The analysis for strontium-89/90 began in 1988, and strontium-90 is routinely detected in both indicator and control milk samples because of past atmospheric nuclear weapons 1 testing. Since 1988, the average concentration for strontium-90 has been 1.90E+0
. pCi/ liter, During 1997, thirty six (36) milk samples were collected and analyzed for iodine-131,
. gamma emitting isotopes, and strontium-89/90. No iodine-131 was detected in any of the q samples. Strontium-90 was detected in both indicator and control milk samples and is Q due to fallout from past atmospheric weapons testing (see Figure 7). The indicator 30-
Ferms 1 - 1997 Annri Radioactive Effluent Release and ~
Radiological Environmental Operating Report O samples had an average strontium-90 concentration of 1.21E+0 pCi/ liter and the control samples had an average concentration of 1.54E+0 pCi/ liter. During 1997, no grass samples were scheduled or collected for the REMP program.
In 1970, the concentration of strontium-90 in Monroe County milk was 6.00E+0 pCi/ liter according to the Michigan Department of Health's " Milk Surveillance", Radiation Data and Reports, Vol. 11-15, 1970-1974. Figure 4 shows the calculated radiological decay
- curve for the 1970 concentration of strontium-90 and the average concentrations since l 1988. Figure 7 illustrates that the inventory of strontium-90 in the local environment is l decreasing with time and closely follows the calculated decay curve. This supports the l fact that the inventory of strontium-90 in the environment is due to fallout from past i atmospheric nuclear weapons testing and not the operation of Fermi 2.
Historical Strontium-90 Activity in Local Milk Samples s.o ..
j 4.o l s n O
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p q c' e.o , , , , , , , , , , , ,,,: : , , , ; ;O I ;:
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Year a Average Sr-90 Activity Calculated Decay Figure 7 - Historical Strontium-90 Activity in Local Milk Samples; The concentration of strontium-90 in local milk samples is decreasing with time and is below the calculated decay curve. This supports the fact that strontium-90 in local milk is due to fallout from past atmospheric nuclear weapons testing and not the operation of Fermi 2.
Groundwater Sampling In areas not served by municipal water systems, water supplies for domestic use are generally obtained from private wells. The network of private wells presently in use forms the source of water for domestic and livestock purposes in farms and homes west and north of the site. However, with the construction of new water plants and distribution systems, the water use trend in the area is from groundwater to surface water.
l 31
Fermi 2- 1997Annutl Radioactive Effluent Release and Radiological Environmental Operating Report O Groundwater is collected on a quarterly basis from four wells surrounding Fermi 2. The groundwater is analyzed for gamma emitting isotopes and tritium. Sampling location GW-4 which is located approximately 0.6 miles west north west is designated as the control location because it is up-gradient and is least likely to be affected by the operation of the plant. The other three sampling locations are down-gradient from Fermi 2 and designated as indicator locations.
Groundwater sampling began in 1987, during the operational period of the REMP program. From 1987 to 1996 naturally occurring potassium-40, cesium-137, and tritium were detected in both indicator and control samples. The average concentration was 7,71E+0 pCi/ liter for cesium-137 and 1.50E+2 pCi/ liter for tritium. The presence of cesium-137 and tritium in groundwater samples is due to fallout from past atmospheric nuclear weapons testing leaching into the soil and becoming incorporated into the groundwater.
In 1997, sixteen (16) groundwater samples were collected and analyzed for gamma emitting isotopes and tritium. No activity was detected in any of these groundwater samples.
Garden Sampling Fermi 2 collects samples of broad leaf vegetables from indicator locations identified by the Annual Land Use Census. Samples are also collected at a control location that is at a distance and direction which is considered to be unaffected by plant operations. Samples I are collected once a month during the growing season (June through September) and are analyzed for iodine-131 and other gamma emitting isotopes.
- Vegetable sampling started in 1982. During the preoperational period from 1982 to 1985,
, only naturally occurring potassium-40 was detected in both indicator and control
! vegetable samples. During the operational period from 1985 to 1990 and 1994 to 1995, only naturally occurring potassium-40 was detected in both indicator and control !
vegetable samples. However, in 1991,1992, and 1993 cesium-137 was detected in one l
indicator sample each year and had an average concentration of 1.2E+1 pCi/ kilogram.
Cesium-137 may become incorporated into plants by either uptake from the soil or direct deposition on foliar surfaces. Since cesium-137 is normally not detected in gaseous effluent samples from Fermi 2, and there have been no recent atmospheric weapons testing or nuclear accidents, the incorporation of cesium-137 by direct deposition is highly unlikely. The most probable source of cesium-137 in vegetable samples is the
- uptake of previously deposited cesium-137, which has leached into the soil. This cesium activity is attributed to fallout from past atmospheric weapons testing and to the nuclear accident at Chemobyl.
, 32
l Fermi 2 - 1997 Annzzi Radioactive Effluent Release and Radiological Environmental Operating Report i During 1997, twenty-three (23) vegetable samples were collected and analyzed for iodine-131 and other gamma emitting isotopes. No iodine-131 was detected in vegetable
!- samples during 1997. The only gamma emitting isotopes detected were naturally occurring potassium-40 and beryllium-7 in both indicator and control vegetable samples.
i L
i Terrestrial monitoring results for 1997 of milk, groundwater and leafy garden vegetable samples, showed only naturally occurring radioactivity, and radioactivity associated with
- i. fallout from past atmospheric nuclear weapons testing. The radioactivity levels detected l- were consistent with levels measured prior to the operation of Fermi 2 and no l
i radioactivity attributable to activities at Fermi 2 was detected in any terrestrial samples.
In conclusion, the terrestrial monitoring data show no adverse long-term trends in the terrestrial environment.
Aquatic Monitoring i'
Lake Erie, on which Fermi 2 borders, is used as a source for drinking water, as well as for recreational activities such as fishing, swimming, sunbathing, and boating. For this reason, Lake Erie and its tributaries are routinely' monitored for radioactivity.
The aquatic monitoring portion of the REMP consists of sampling raw municipal 3 drinking water, surface water, lake sediments, and fish for the presence of radioactivity. I t
The following sections discuss the type and frequency of aquatic sampling, analyses performed, a comparison of 1997 data to previous operational and preoperational data.
Drinking Water Sampling I- ' Detroit Edison monitors drinking water at one control location and one indicator location using automatic samplers. The automatic samplers collect samples, known as aliquots, at time intervals that are very short (hourly) relative to the sample collection period (monthly) in order to assure that a representative sample is obtained. Indicator water
- samples are obtained at the Monroe water intake located approximately 1.1 miles south of the plant. Detroit municipal water is used for the control samples and is obtained at the
. Allen Park water intake located approximately 18.6 miles north of the plant. Drinking j water samples are collected on a monthly basis and analyzed for gross beta, strontium- i 89/90, and gamma emitting isotopes. The monthly samples for each location are combined on a quarterly basis and analyzed for tritium activity.
l 33 L
i__ _ _ _ _ _ _ _ _ _ _ _ _ _ .
Fermi 2 -l997Annux!
Radioactive Effluent Release and Radiological Environmental Operating Report O In late 1980, as shown in Figure 8, an atmospheric nuclear weapon test was conducted by the Peoples Republic of China. As a resul~ "this test, the average gross beta for 1981 was 9.80E+0 pCiAiter for water samples. . igure 8 also shows that, except for the Chinese weapons testing, the historic drinking water sample data is below the lower limit of detection (4.00E+0 pCi/ liter) required by US Environmental Protection Agency's l
National Interim Primary Drinking Water regulations. Even during the Chinese weapons 1 testing, the drinking water samples did not exceed the USEPA's maximum allowable criteria of 5.00E+1 pCi/ liter gross beta. In 1980 and 1983, cesium-137 was detected in drinking water samples at levels ranging from 5.40E+0 pCi/ liter to 1.90E+1 pCi/ liter. ;
Tritium was also detected during the preoperational program and had an average of j l
3.25E+2 pCi/ liter. The presence of cesium-137 and detectable levels of tritium in these j water samples is due to fallout from past atmospheric nuclear weapons testing and I naturally occurring tritium.
l i
From 1985 to 1996,' the average annual gross beta activity for indicator samples was 3.13E+0 pCiditer and 2.59E+0 pCi/ liter for control samples. The analysis for strontium-89/90_ began in 1988 and strontium-90 has been detected in both indicator and control l
samples. fhe average strontium-90 activity for indicator samples was 7.25E-1 pCiditer and 7.56E-1 pCi/ liter for control samples during this time period. Tritium was also f-,.
detected in both indicator and control drinking water samples during this time period.
The average tritium activity for indicator samples was 2.70E+2 pCi/ liter and 3.00E+2 pCi/ liter for control samples. The presence of strontium-90 and detectable levels of tritium in these water samples is due to fallout from past atmospheric nuclear weapons testing and naturally occurring tritium.
In 1997, twenty-six (26) drinking water samples were collected and analyzed for gross beta, gamma emitting isotopes, strontium-89/90, and tritium. The average gross beta for indicator samples was 2.98E+0 and 2.45E+0 pCiditer for control samples. No gamma emitting isotopes or strontium-89/90 activity was detected in drinking water samples during 1997. Eight (8) quarterly composite drinking water samples were prepared and analyzed for tritium. Two indicator samples showed an average activity for tritium at 3.25E+2 pCiAiter and one control sample showed detectable activity of 2.60E+2 pCi/ liter. ,
This tritium activity is consistent with background levels measured during the I preoperational program.
(
34
Fermi 2 - 1997 Arnu:1 l Radioactive Ef]Tuent Release and Radiological Environmental Operating Report l
Historical Gross Beta Activity l 12.o. In Drinking Water Samples 10.0 - cranese w rest s.o .
3 S 6.0 -
l y ... ...... ..... . ...................... .... .... ..
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0.0 , , , , , , , , , , , , , , , , , , ,
S $ @ E E 2 E $$SEE 8E E 2 & $ $ S Year l---v--Irdestor Gross Beta --o- Cordrol Gross Beta - -EPA LLD l Figure 8 - Historical Gross Beta Activ'ity in Drinking Water Samples; Since 1982, the annual concentrations of beta emitting radionuclides in drinking water samples collected {
p N
from indicator locations have been consistent with those from control locations. i This shows that Fermi 2 has had no measurable radiological impact on local drinking water and that the water meets the US Environmental Protection Agency's lower limit of detection (LLD) of 4.0 pCi/ liter.
l l Surface Water Sampling i Detroit Edison monitors surface water at two locations using automatic samplers. As with drinking water, surface water samples are collected at time intervals that are very short (hourly) relative to the sample collection period (monthly) in order to assure obtaining a representative sample. Indicator surface water samples are obtained at the Fermi 2 General Service Water building, located approximately 0.3 miles south southeast from Fermi 2. The control surface water samples are obtained from Trenton Channel l Power Plant's cooling water intake on the Detroit River which is approximately 11.7 miles north north east of Fermi 2. Surface water samples are collected on a mcnthly basis i and analyzed for strontium-89/90 and gamma emitting isotopes. The monthly samples for each location are combined on a quarterly basis to form a quarterly composite sample and are analyzed for tritium.
O 35 w_______________ . _ _ _ . ._
I 1
Fermi 2-l997 Annual ,
Radioactive EffluentRelease and l Radiological Environmental Operating Report O
Surface water sampling began in 1979 and the samples were analyzed for gamma I emitting isotopes, and tritium. During this preoperational program no gamma emitting
-isotopes, except for naturally occurring potassium-40, were detected. Tritium was detected in both indicator and control samples during this time period and had an average concentration of 3.15E+2 pCi/ liter. This tritium activity represents the background concentration due to naturally. occurring tritium and tritium produced during past atmospheric nuclear weapons testing.
From 1985 to 1996, as part of the operational program, surface water samples were analyzed for gamma emitting isotopes and tritium. The analysis for strontium-89/90 did
,_ not begin until 1988, and strontium-90 was detected in both indicator and control samples. The average strontium-90 concentration for this time period was 1.13E+0 pCi/ liter. = In 1990, two indicator samples showed detectable activity for cesium-137 at an i average concentration of 1.20E+1 pCi/ liter. The presence of cesium-137 and strontium-90 in these water samples is due to fallout from past atmospheric nuclear weapons I testing. Tritium was detected in both indicator and control surface water samples during I
this time period at a concentration of 2.34E+2 pCi/ liter. This tritium activity is consistent with background levels measured during the preoperational program.
In 1997, thirty-one (31) surface water samples were collected and analyzed for gamma emitting isotopes and strontium-89/90. From these samples, eight (8) quarterly composite samples were prepared and analyzed for tritium. During 1997, no gamma emitting isotopes were detected. Tritium was detected in one indicator sample at a concentration of 3.50E+2 pCi/ liter and one control sample at a concentration of 2.20E+2 pCi/ liter. This tritium activity is consistent with background levels measured dur'mg the preoperational program.
Sediment Sampling Sediments often act as a sink (temporary or permanent) for radionuclides, but they may also become a source, as when they are resuspended during periods of increased turbulence or are dredged and deposited elsewhere. Sediment, in the vicinity of the liquid discharge point, represents the most likely site for accumulation of radionuclides in the aquatic. environment and, with long-lived radionuclides, a gradual increase in radioactivity concentration would be expected over time if discharges occur. Sediment, therefore, provides a long-term indication of change that may appear in other sample media (i.e., water and fish samples).
36
Ferrni2 - 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report O
Lake Erie shoreline and bottom sediments from five locations are collected on a semiannual basis (Spring and Fall) and are analyzed for gamma emitting isotopes and strontium-89/90. There is one control location and four indicator locations. The control sample is collected near the Trenton Channel Power Plant's cooling water intake. The l indicator samples are collected at Estral Beach, near the Fermi 2 liquid discharge area, the shoreline at the end of Pointe Aux Peaux, and Indian Trails Community Beach.
During the preoperational program there was not a control location, and indicator samples were analyzed for gamma emitting isotopes. During the preoperational program, except
'for naturally occurring isotopes, only cesium-137 was detected in sediment samples. For this time period the average cesium-137 concentration was 3.27E+2 pCi/ kilogram. The presence of cesium-137 in these sediment samples is due to fallout from past atmospheric nuclear weapons testing.
From 1985 to 1996, cesium-137, strontium-90, and naturally occurring isotopes were detected in sediment samples. The average cesium-137 concentration for indicator samples was 1.77E+2 pCi/ kilogram and 1.27E+2 pCi/ kilogram for control samples. The analysis for strontium-89/90 began in 1988, and strontium-90 has been routinely detected at similar concentrations in both indicator and control samples. The average strontium-90 activity for indicator samples was 7.56E+1 pCi/ kilogram and 1.98E+2 pCi/ kilogram for O control samples. The presence of cesium-137 and strontium-90 in these sediment samples is due to fallout from past atmospheric nuclear weag - : sting.
In 1990 and 1991, the Spring samples taken at the Fermi 2 liquid discharge line (Location S-2) showed activity for plant related isotopes (manganese-54, cobalt-58, cobalt-60, and zine-65) and was determined to be a result ofliquid effluent from Fermi 2. The sample results were well below any regulatory reporting limits and were consistent with the activity released from the plant in liquid effluents and the dose impact was negligible.
In 1997, ten (10) sediment samples were collected and analyzed for gamma emitting isotopes and strontium 89/90. Strontium-90 was detected in two indicators samples with an average concentration of 3.40E+2 pCi/ kilogram. Also cesium-137 was detected in two control samples with an average concentration of 1.07E+2 pCi/ kilogram. The presence of cesium-137 and strontium-90 in sediment samples is due to fallout from past atmospheric nuclear weapons testing. Naturally occurring isotopes of potassium, beryllium, radium, and thorium were also detected in both indicator and control sediment samples for this sampling period.
O 37
Fermi 2 - 1997 Annul Radioactive Ef]!uent Release and Radiological Environmental Operating Report ,
O Q Historical Cesium-137 Activity in Sediment Samples 7.0E+02 -
6.0E+02 - h j 5 0E+02 -
4.0E+02 - i
\o .
g 3.0E+02 - 5 e o [
q 1
h, q
(
g ;2.0E+02 -7 ,',' ;n; u
,: n; ;n;( n; U n*r %
ssaaaaaaaaaaa=aaaaaa cx:::1 Average Activity -o-Calculated Trend l l k
l Figure 9 - Historical Cesium-137 Activity in Sediment Samples; As the calculated trend shows, the concentration of cesium-137 in Lake Erie sediments is decreasing with time. This supports the fact that cesium-137 in Lake Erie sediments is due to fallout from past atmospheric nuclear weapons testing and not the operation of Fermi 2.
i Figure 9 shows the historical concentration of cesium-137 in sediment samples from
{
1978 to 1997. Using the data from these years, and the statistical method of least squares, an exponential curve can be calculated that represents the cesium-137 concentration in sediment. This curve has a negative slope which indicates the overall concentration of cesium-137 in the environment is decreasing with time. This supports the fact that the inventory of cesium-137 in the environment is due to fallout from past atmospheric nuclear weapons testing and not from the operation of Fermi 2.
{
Fish Sampling Samples of fish are collected from Lake Erie at three locations on a semiannual basis.
There are two control locations and one indicator location. The two control locations are offshore of Celeron Island and in Brest Bay. The indicator location is approximately 1200 feet offshore of the Fermi 2 liquid effluent discharge. Edible portions of the fish are analyzed for gamma emitting isotopes and strontium-89/90.
- During the preoperational program fish samples were analyzed for gamma emitting isotopes. Only cesium-137 and naturally occurring potassium-40 were detected during this time period. The average concentration of cesium-137 for indicator samples was 3.53E+1 pCi/ kilogram and 4.20E+1 pCi/ kilogram for control samples. The presence of ,
cesium-137 in these fish samples is due to fallout from past atmospheric nuclear weapons l testing.
38 l
l Fermi 2- 1997 Annut!
Radioactive Egluent Release and Radiological Environmental Operating Report O From 1985 to 1996, cesium-137 and naturally occurring potassium-40 were detected in l
fish samples. The average cesium-137 concentration for indicator samples was 4.51E+1 pCi/ kilogram and 4.54E+1 pCi/ kilogram for control samples. Figure 10 shows a graphical representation of cesium-137 comparing preoperational and operational average concentrations. The analysis for strontium-89/90 began in 1990, and strontium-90 has been routinely detected at similar concentrations in both indicator and control samples. The average strontium-90 concentration for indicator samples was 3.84E+1 pCi/ kilogram and 3.39E+1 pCi/ kilogram for control samples. The presence of cesium-137 and strontium-90 in these fish samples is due to fallout from past atmospheric nuclear weapons testing. j In 1997, twenty-three (23) fish samples were collected and analyzed for gamma emitting isotopes and strontium-89/90. Cesium-137 and naturally occurring potassium-40 were detected in fish samples. Both indicator and control samples showed detectable activity for cesium-137. One control sample showed detectable activity at a concentration of !
1.98E+1 pCi/ kilogram and two indicator samples showed an average activity of 2.24E+1 l pCi/ kilogram. Figure 10 shows a graphical comparison of cesium-137 average concentrations between preoperational, operational, and 1997 data. The presence of cesium-137 in the 1997 fish samples is due to fallout from past atmospheric nuclear l weapons testing. {
O Cesium 137 Activity in Fish Samples Historical Averages 5.0E+01 - Operational m m 4.0E+01 - [E %
(N
- ]igi M
! 3.0E+01 - k[d hh h- 1997 1 9 f$ % $P 2.0E+01 - M>
n' y
Mi M
gg Y g -
w ;
1.0E+01 -
(
w 1 o o A Indicator Control Indicator Control Indicator Control Figure 10 - Cesium-137 Activity in Fish Samples Historical Averages; Average concentrations of cesium-137 in fish samples were similar at indicator and control locations and were within the expected range of results of previous years.
39
Fermi 2- 1997 Annual l Radioactive Effluent Release and Radiological Environmental Operating Report f
l %/ I
\
l Aquatic monitoring results for 1997 of water, sediment, and fish, showed only naturally l occurring radioactivity and radioactivity associated with fallout from past atmospheric nuclear weapons testing and were consistent with levels measured prior to the operation of Fermi 2. In conclusion, no radioactivity attributable to activities at Fermi 2 was detected in any aquatic samples during 1997 and no adverse long-term trends are shown in the aquatic monitoring data.
i i
l l
l l
1 l
I l
l 1
l l
!O 40 f
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O Land Use Census The Land Use Census is conducted in accordance with the Fermi 2 Offsite Dose Calculation Manual (ODCM), control 3.12.2, and satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. This census identifies changes in the use of unrestricted areas to permit modifications to monitoring programs for evaluating doses to individuals from principal pathways of exposure. The pathways of concern are listed below:
. Inhalation Pathway - Internal exposure as a result of breathing radionuclides carried in the air.
- Ground Exposure Pathway - External exposure from radionuclides deposited on the ground.
- Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material, e Vegetation Pathway - Internal exposure as a result of eating vegetables which have absorbed deposited radioactive material or O which have absorbed radionuclides through the soil.
- Milk Pathway - Internal exposure as a result of drinking milk which may contain radioactive material as a result of dairy animals grazing on a pasture contaminated by radionuclides.
The Land Use Census is conducted during the growing season and is used to identify, within a radius of 5 miles, the location of the nearest residences, milk animals, meat animals, and gardens (greater than 50 square meters and containing broad leaf vegetation) in each of 16 meteorological sectors surrounding Fermi 2. Gardens greater than 50 square meters are the minimum size required to produce the quantity (26 kg/ year) ofleafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden is used for growing broad leaf vegetation (i.e., lettuce and cabbage); and (2) a vegetation yield of 2 kg/ square meter.
O 41
Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report O 1997 Land Use Census Results The Land Use Census is conducted in accordance with ODCM control 3.12.2 and
, satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. This
! census identifies changes in the use of unrestricted areas to permit modifications to monitoring programs for evaluating doses to individuals from principal pathways of exposure. The annual Land Use Census is conducted during the growing season and is used to identify, within a radius of 5 miles, the location of the closest residences, milk animals, meat animals, and gardens in each of the 16 meteorological sectors surrounding Fermi 2. While this evaluation is designed to qualify the " critical receptor" with potential ,
dose calculations, it does not represent the individuals actual annual dose due to effluent releases.
The 1997 Land Use Census was performed during the months of August and September.
The 1997 census data was obtained with the use of a hand-held Global Positioning System (GPS). This data was compared to the 1996 data to determine any significant s changes in the use of the land. This information is tabulated in Tables 1-4 of this report.
There were slight changes in the category of closest residences due to the increased accuracy associated with the use of the GPS unit. All but the North-East and North sectors had changes to garden locations. Two milk locations were identified in 1997 as O opposed to one location in 1996. Three beef cattle locations were identified with a distance change in the West-North-West sector of 4,576 meters. In 1996 four beef locations were identified. This census also identified new residential housing construction in the North-West sector at 3,962 meters from Fermi 2.
The potential dose for each 1997 location from Tables 9-12 were calculated using equation 7-14, of section 7.8.1 of the ODCM. The effluent data and the meteorology data for 1997 were used to perform the calculations. Two locations with different pathways were calculated as having the highest potential dose and are as follows:
Azimuth Distance Age Group Organ Pathway Sector (degrees) (meters)
Ingestion (goat milk) WNW 301.1 3669 inf' ant thyroid Ingestion (vegetation) WNW 304.6 1110 Child thyroid After further investigation, it was determined that no infant resides at the milk location.
However, there is a child residing at the garden location which becomes the new " critical receptor". The exposure pathways to this receptor include inhalation, ingestion (vegetation), and ground plane with the maximum exposed organ being the thyroid.
O 42
Fermi 2 - 1997 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperating Report 1997 LAND USE CENSUS Closest Residences Table 9
,, Change?
.. ~ _
.m Distance -
~
_ Year' Sedtor ' Azimuth (degree's)? *(meteri)': ' '(meters)"
l996 NE 34.9 1825 1997 NE 34.8 1770 55 1996 NNE 16.9 1723 1997 NNE 11.2 1658 65 1996 N 10.4 1762 1997 N 7.7 1770 8 1996 NNW 333.5 1760 1997 NNW 332.9 1738 22 1996 NW 314.2 1679 1997 NW 311.4 1706 27 1996 WNW 302.7 1074 O 1997 (a) WNW 304.6 1110 36 1996 W 259.2 1787 1997 W 259.2 1787 0.0 1996 WSW 236.5 2241 1997 WSW 238.3 2543 302 1996 SW 236.5 2056 1997 SW 230.3 2028 28 1996 SSW 201.0 1803 1997 SSW 201.0 1803 0.0 1996 S 170.7 1671 1997 S 170.1 1641 30 l ESE-SSE l Lake Erie l l (a) = Calculated Critical Receptor and participant in REMP program 43
O Appendix A Sampling Locations l
O O
Fermi 2 - 1997Annu11 Radioacthe Effluent Release and Radiological En vironmental Operating Report Direct Radiation Sample Locations Table A-1 Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrecs) (Approx.) Description Frequency Type Tl NE/38' l.3 mi. Estral Beach, Pole on Q l Lakeshore 23 Poles S of Lakeview (Special Area) l T2 NNE/22' l.2 mi. East of termination of Q l l Brancheau St. on post I (Special Area)
T3 N/9* 1.1 mi. Pole, NW corner of Swan Q l Boat Club fence (Special Area)
T4 NNW/337' O.6 mi. Site boundary and Toll Rd. Q l on Site fence by API #2 l
T5 NW/313' O.6 mi. Site boundary and Toll Rd. Q l on Site fence by API #3 l
> D \
(d . T6 WNW/293* 0.6 mi. Pole, NE corner of Bridge Q l i over Toll Rd.
T7 W/270* 14.0 mi. Pole, at Michigan Gas Q C substation on N. Custer Rd.,0.66 miles west of Doty Rd.
T8 NW/305' l.9 mi. Pole on Post Rd. near NE Q l corner of Dixie liwy. and Post Rd.
T9 NNW/334' l.5 mi. Pole, NW corner of Q l Trombley and Swan View Rd.
T10 N/6' 2.1 mi. Pole, S side of Massarant. Q I 2 poles _W of Chinavare.
L = Indicator C = Control Q = Quarterly A-1
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O Direct Radiation Sample Locations (Table A-1 continued)
V Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type Tl1 NNE/23* 6.2 mi. Pole, NE corner of Q l Milliman and Jefferson T12 NNE/29' 6.3 mi. Pointe Mouille Game Area Q !
Field Office, Pole near tree, N area of parking lot T13 N/356' 4.1 mi. Labo and Dixie Hwy. Pole Q l on SW corner with light T14 NNW/337' 4.4 mi. Labo ard Brandon Pole on Q I l SE corner near RR l Tl5 NW/315' 3.9 mi. Pole, behind Newport Post Q l ,
Office.
l l
T16 WNW/283* 4.9 mi. Pole, SE corner of War and Q I Post Rd.
T17 W/271' 4.9 mi. Pole NE corner of Nadeau Q l s and Laprad near mobile home park.
T18 WSW/247' 4.8 mi. Pole, NE comer of Mentel Q l and llurd Rd.
T19 SW/236' 5.2 mi. Ist pole E of Fenni siren Q I l on Waterworks Rd. NE corner ofintersection -
Sterling State Park Rd.
Entrance Drive / Waterworks (in Sterling State Park)
T20 WSW/257' _2.7 mi. Pole, S side of Williams Q I Rd,8 poles W of Dixie liwy.(Special Area) l T21 WSW/239' 2.7 mi. Pole, N side of Pearl at Q I Parkview Woodland Beach
.(Special Area) i = Indicator C = Control Q = Quarterly
)
A-2 l
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report Direct Radiation Satnple Locations (Table A-1 continued)
Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T22 S/172' l.2 mi.' Pole, N side of Pointe Aux Q l Peaux 2 poles W of Long -
Site Boundary T23 SSW/195* 1.1 mi. Pole, S side of Pointe Aux Q !
Peaux 1 pole W of Huron next to Vent Pipe - Site Boundary T24 SW/225' l.2 mi. FermiGate along Pointe Q l Aux Peaux Rd. on fence wire W of gate Site Boundary
'T25 WSW/251' l.5 mi. Pole, Toll Rd. - 13 poles S Q l I of Fermi Drive T26. WSW/259* 1.1 mi. Pole, Toll Rd. - 6 poles S Q l of Fermi Drive
- y T27 SW/225' 6.8 mi. Pole, NE corner of Q l McMillan and East Front St. (Special Area)
I T28 SW/229' 10,7 mi. Pole, SE corner of Mortar Q C
, Creek and LaPlaisance.
T29 WSW/237* 10.3 mi. Pole, E side of S Dixie,1 Q C pole S of Albain.
i T30 WSW/247* 7.8 mi. Pole, St. Mary's Park Q l !
corner of Elm and Monroe l St., S side of parking lot ;
next to river (Special Area)
T31 WSW/255' 9.6 mi. Ist pole W of entrance Q C drive Milton " Pat" Munson Recreational Reserve on i North Custer Rd.
1 = Indicator C = Control Q = Quarterly A-3
Fermi 2 - l997 Annual Radioacthe Effluent Release and Radiological En vironmental Operating Report Direct Radiation Sample Locations (Table A-1 continued)
Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T32 WNW/295' 10.3 mi. Pole, comer of Stony Q l Creek and Finzel Rd.
T33 NW/317' 9.2 mi. Pole, W side of Grafton Q l Rd. I pole N of Ash and Grafton intersection.
T34 NNW/338' 9.7 mi. Pole, W side of Port Creek, Q l i pole S of Will-Carleton Rd.
T35 N/359' 6.9 mi. Pole, S Side of S IIuron Q l River Dr. across from Race St.(Special Area)
T36 N/358' 9.1 mi. Pole, NE corner of Q l Gibraltar and Cahill Rd.
T37 NNE/21' 9.8 mi. Pole, S corner of Adams Q I O and Gibraltar across from Humbug Marina.
T38 WNW/294' l.7 mi. Residence - 6594 N. Dixie Q I Hwy.
T39 S/176* 0.3 mi. SE comer of Protected Q I Area Fence (PAF).
T40 S/170* 0.3 mi. Midway along OBA - Q l (PAF)
T41 SSE/161* 0.2 mi. Midway between OBA and Q I Shield Wall on PAF.
T42 SSE/149' O.2 mi. Midway along Shield Wall Q l on PAF.
T43 SE/131' O.1 mi. Midway between Shield Q l Wall and Aux Boilers on PAF.
T44 ESE/109' O.1 mi. Opposite OSSF door on Q I PAF.
I = Indicator C = Control Q = Quarterly A-4
1 l
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report r Direct Radiation Sample Locations (Table A-1 continued) 1 l
Meteorological Distance l i Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type l !
T45 E/86* 0.1 mi. NE Corner of PAF. Q I l T46 ENE/67* 0.2 mi. NE side of barge slip on Q I l fence.
T47 S/185* 0.1 mi. South of Turbine Bldg. Q I l rollup door on PAF.
T48 SW/235' O.2 mi. 30 ft from corner of AAP Q l on PAF. ,
T49 WSW/251* 1.1 mi. Corner of Site Boundary Q I I fence north of NOC along l Critical Path Rd.
T50 W/270* 0.9 mi. Site Boundary fence near Q l main gate by the south Bullit Street sign.
(N T51 N/3' O.4 mi. Site Boundary fence north Q l of north Cooling Tower.
TS2 NNE/20* 0.4 mi. Site Boundary fence at the Q I corner of Arson and Tower.
T53 NE/55* 0.2 mi. Site Boundary fence east of Q l South Cooling Tower.
l T54 S/189* 0.3 mi. Pole next to Fermi 2 Q l i Visitors Center.
T55 WSW/251* 3.3 mi. Pole, north side of Nadeau Q I Rd. across from Sodt Elementary School Marquee T56 WSW/256* 2.9 mi. Pole, entrance to Jefferson Q l Middle School on Stony Creek Rd.
l l
1 = Indicator C = Control Q = Quarterly l
D)
L A-5 L ____ __ . _ _ _ _ _ _ _ .
Fermi 2- l997 Annual Radioactive Ef]!uent Release and Radiological Environmental Operating Report p Direct Radiation Sample Locations (Table A-1 continued)
~
Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T57 W/260' 2.7 mi. Pole, nonh side of Q l Williams Rd.across from Jefferson liigh School entrance.
T58 WSW/249' 4.9 mi. Pole west of flurd Q l Elementary School Marquee
]
T59 NW/325' 2.6 mi. Pole north of St. Charles Q I Church entrance on Dixie I liwy.
T60 NNW/341* 2.5 mi. Ist pole nonh of North Q l Elementary School entrance on Dixie Hwy.
T61 W/268' 10.1 mi. Pole, SW corner of Stewart Q I and Raisinville Rd.
O T62 SW/232' - 9.7 mi. Pole, NE ccmer of Albain Q l and liull Rd.
T63 WSW/245' 9.6 mi. Pole, NE corner of Dunbar Q I and Telegraph Rd.
T64 WNW/286* 0.2 mi. West of switchgear yard on Q I PAF T65 NW/322' O.1 mi. PAF switchgear yard area Q I NW of RilR complex.
T66 NE/50' O.1 mi. Behind Bldg. 42 on PAF Q l T67 NNW/338' O.2 mi. Site Boundary fence West Q I of South Cooling Tower 1 = Indicator C = Control Q = Quarterly f
(
A-6
Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report Air Particulate and Air Iodine Sample Locations Table A-2 Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type API l NE/39* 1.4 mi. Estral Beach Pole on W I Lakeshore,18 Poles S of Lakeview (Nearest Community with highest X'Q)
API-2 NNW/337* 0.6 mi. Site Boundary and Toll W I Road, on Site Fence by T-4 API-3 NW/313' O.6 mi. Site Boundary and Toll W I Road, on Site Fence by T-5 API-4 W/270* 14.0 mi. Pole, at Michigan Gas W C substation on N. Custer Rd.,0.66 miles west of Doty Rd.
API-5 S/191* 1.2 mi. One pole south of Pointe W I O Aux Peaux Rd.on Erie St.
I = Indicator C = Control IV = IVeekly Milk Sample Locations Table A-3 Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type
(
M-2 NW/319* 5.4 mi. Reaume Farm - 2705 E M-SM I Labo M-8 WNW/289* 9.9 mi. Calder Dairy - 9334 Finzel M-SM C Rd 1 = Indicator C = Control Ai = Aionthly SAi = Semimonthly O
A-7
Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological Enviror. mental Operating Report Garden Sample Locations Table A-4 Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type FP-1 NNFJ21' 3.8 mi. 9501 Turnpike Highway M i FP-3 NNE/12' l.1 mi. 6441 Brancheau M I FP-7 WNW/302* 0.7 mi. 6200 Langton M i FP-9 W/261* 10.9 mi. 4074 North Custer Road M C I = Indicator C = Control Af = Afonthly(whenavailable)
O Drinking WaterSample Locations Table A-5 Meteorological Distance Station Sector / Azimuth from Reactor Collection
, Number (Degrees) (Approx.) Description Frequency 'lype DW-1 S!!74* 1.1 mi. Monroe Water Station N M i Side of Pointe Aux Peaux 1/2 Block W of Long Rd DW-2 N/8" 18.5 mi. Detroit Water Station M C 14700 Moran Rd, Allen Park I = Indicator C = Control A1 = Afonthly 0 i A-8
_ _ _ _ _ _ _ _ _ _ _ _ _ \
/ -
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O
Surface if'aler Sample Locations Table A-6 Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type SW-2 NNE/20* 11.7 mi. DECO's Trenton Channel M C Power Plant Intake Structure (Screenhouse #1)
SW 3 SSE/160* 0.2 mi. DECO's Fermi 2 General M i Service Water intake Structure 1 = Indicator C = Control hf = Afonthly Groundwater Sample Locations Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type G W-1 S/175* 0.4 mi. Approx.100 fl W of Lake Q l Erie, EF-1 Parking lot near gas fired peakers G W-2 SSW/208* 1.0 mi. 4 ft S of Pointe Aux Peaux Q l (PAP) Rd. Fence 427 fl W of where PAP crosses over Stoney Point's Western Dike G W-3 SW/226* 1.0 mi. 143 ft W of PAP Rd. Gate, Q l 62 ft N of PAP Rd. Fence GW-4 WNW/299 0.6 mi. 42 fl S of Langton Rd,8 ft Q C E of Toll Rd. Fence I = Indicator C = Control Q = Quarterly O
A-9
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Sediment Satnple Locations Table A-8 Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type 1
S-1 SSE/165* 0.9 mi. Pointe Aux Peaux, SA I Shoreline to 500 ft offshore sighting directly to Land Base Water Tower S-2 E/81* 0.2 mi. Fermi 2 Discharge, approx. SA I 200 ft offshore S-3 NE/39* 1.1 mi. E.< tral Beach, approx. 200 SA 1 ft offshore, off North shoreline where Swan Creek and Lake Erie meet S-4 WSW/241' 3.0 mi. Indian Trails Community SA I Beach S-5 NNE/20" 11.7 mi. DECO's Trenton Channel SA C Power Plant intake area.
1 = Indicator C = Control SA = Semiannually Fish Sample Locations Table A-9 Meteorological Distance Station Sector / Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type F-1 NNE/31* 9.5 mi. Celeron Island SA C F-2 E/86* 0.4 mi. Fermi 2 Discharge (approx. SA I 1200 fl offshore)
F-3 SW/227' 3.5 mi. Brest Bay SA C I = Indicator C = Control SA = Semiannually l
O A-10
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8 FP- FOOD PRODUCTS C F- FISH SCALE IN MILES
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o e et x a eh A'L LMe oo l
b T
a NL mca a o n
Ef S[HFiC p i ,*
s L < MLN N
i i
l l
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report lQ l(/
1997 LAND USE CENSUS Closest Gardens l !
Table 10
.,c.i ' R ; ' .
27Distancey l ChangeLa
> Year 5 ' ' Sector; ~ Azimuth (degrees)2 ' f(meters) L -l(meters);
l 1996 NE 38.9 3157 1997 NE 38.9 3157 0.0 l i 1996 NNE 33.0 3227 !
1997 NNE 16.0 1754 1473 1996 N 0.3 2736 l 1997 N 0.3 2736 0.0 1996 NNW 329.3 2170 1997 NNW 332.4 4088 1918 )
l 1996 NW 309.9 1706 l 1997 NW 309.9 1706 0.0 l l
7g 1996 WNW 301.2 3661
(/ 1997 (a) WNW 304.6 1110 2551 1996 W 258.0 1854 1997 W 270.4 1963 109 1996 WSW 248.8 3154 1997 WSW 256.9 1854 1300 1996 SW 224.0 2350 1997 SW 233.9 7033 4683 1996 SSW 198.0 2136 1997 SSW 197.0 2430 294 1996 S 170.7 1671 1997 S 170.1 1641 30 i l ESE - SSE l Lake Erie l l l
.) = 1997 Calculated Critical Receptor and participant in REMP program
[v) 44
Fermi 2 - 1997Annux!
Radioactive Effluent Release and Radiological En vironmental Operating Report
/~h
(.s' 1997 LAND USE CENSUS Milk Locations Table 11 32 <
- n, a- ;DistanceL ;ChangeV Tear? N-#' MSectorN UAhmuth~(degreesp 4(ineters)% *inieters)?f 1996 NE None 1997 NE None N/A 1996 NNE None 1997 NNE None N/A 1996 N 6.5 6663 1997 (a) N 6.5 6663 0.0 1996 NNW None 1997 NNW None N/A 1996 NW None 1997 NW None N/A es WNW
()
1996 None l
1997 WNW 301.1 3669 N/A i 1996 W None 1997 W None N/A 1996 WSW None 1997 WSW None N/A 1996 SW None i 1997 SW None N/A l 1996 SSW None 1997 SSW None N/A 1996 S None 1997 S None N/A l ESE - SSE l Lake Erie l l (a) = Participated in REMP sampling program in 1995 and part of 1996 45 i
L
l Fermi 2- l997Annut!
1 Radioactive Effluent Release and l
Radiological Environmental Operating Report
,r\
() 1997 LAND USE CENSUS Closest Beef Cattle Locations Table 12 2 ovd eu , ,- Ec flg.e- :.j; J Distance E;ChangeT t y g g:Gi g ; 4TSect3i3@ f M u dthT @ )"i 1(ss)h if(s M )?k 1996 NE None 1997 NE None N/A 1996 NNE 18.8 6164 1997 NNE None N/A __
i 1996 N 1.2 2897 1997 N 1.2 2897 0.0 1996 NNW None 1997 NNW None N/A 1
l 1996 NW None 1997 NW None N/A 1996 WNW 289.9 7183
/ ~\ 1997 WNW 285.7 2607 t
- x. 4576 1996 W- None 1997 W N/A 1996 WSW 248.6 4602 1997 WSW 248.6 4602 0.0 1996 SW None 1997 SW None N/A .-
1996 SSW None 1997 SSW None N/A 1996 S None 1997 S None N/A l ESE- SSE l Lake Erie l l O
v i
46
1 1
O Appendix C Environmental Data Tables l
i l l O
O
l Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report (q/ FERMI 2 TLD ANALYSIS (mR/Std Qtr)
STATION. -: FIRST ;x : SECONDE MTHIRDw ~.. FOURTH 2 NUMBER kQUARTERU' TQUARTER8 TQUdRTERT IQUARTERT., 3 T-1 14.0 14.8 13.3 12.2 T-2 16.5 17.I 17.0 15.1 T-3 13.6 12.4 13.2 11.0 T-4 14.9 13.4 15.2 12.7 T-5 15.5 15.7 15.9 14.3 T-6 14.3 10.5 12.9 13.2 l' T-7 14.2 12.8 14.3 12.8 15.8 14.7 17.0 14.5 i
I 4.6 . I3.3 15.6 12.9 l 15.I 14.6 16.3 13.2 14.6 12.8 15.0 12.4
'l-12 14.0 12.4 14.2 12.2 l T-13 15.7 14.3 16.3 13.8 T-14 14.8 14.5 16.4 14.0 T-15 14.9 12.6 14.6 12.3 T-16 15.2 14.6 16.0 13.4 T-17 14.1 12.5 13.7 12.0 T-18 14.6 13.2 16.4 13.6 T.19 16.2 14.7 18.5 14.3 T-20 17.7 15.8 19.3 16.3 5O T-21 T-22 14.5 15.2 12.6 13.2 15.5 15.2 12.4 13.2 T-23 15.5 13.4 16.1 13.5 l T-24 14.5 15.8 15.3 12.8 I T-25 17.0 15.8 18.1 16.5 T-26 17.4 17.0 18.8 15.8 l
T-27 (a) 11.6 13.4 11.5 i T-28 14.4 13.0 14.5 13.5 T-29 15.5 14.I 17.4 13.9 T-30 15.0 14.3 (a) 13.5 T-31 15.5 13.8 16.1 13.7 T-32 15.3 14.7 16.6 13.7 T-33 14.9 14.6 14.6 13.0 T-34 14.3 12.8 15.3 12.4 T-35 14.3 13.6 15.1 12.4 T-36 15.2 14.3 16.0 13.9 T-37 14.6 13.8 14.7 14.0 T-38 15.5 14.8 17.3 14.6 T-39 12.2 13.9 21.7 23.5 T-40 12.7 12.4 19.9 19.3 T-41 12.8 16.0 30.2 32.2 T-42 14.8 16.7 30.5 32.4 T-43 13.1 15.7 31.3 35.7 T-44 12.0 15.4 27.6 31.0 T-45 12.2 13.3 21.7 23.2 l C/
O T-46 T-47 13.3 13.!
12.8 19.4 26.6 19.9 16.5 31.1 l l
C-1 c____________ . _ _ _ - - _ _ _ .
Fermi 2- l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 G TLD ANALYSIS (CONT.)
(mR/Std Qtr)
' STATION .. FIRST .- SECOND ( . . ETHIRDT FOURTHL -
NUMBER " QUARTER' / QUARTER- QUARTER?' T QUARTER T-48 13.4 13.9 20.1 20.6 T-49 18.6 18.8 21.4 19.8 T-50 15.6 16.6 17.1 15.3 T-51 12.3 11.5 13.I 11.4 T-52 13.8 12.6 15.4 14.5 T-53 13.7 13.5 16.7 16.9 T-54 13.9 12.4 14.6 13.5 T-55 15.9 14.4 16.I 14.9 T 56 15.1 13.8 15.1 13.9 T-57 16.9 16.7 18.7 16.5 T-58 15.0 12.5 15.2 13.5 T-59 14.1 13.2 15.5 13.0 T-60 16.2 14.6 15.8 14.9 T-61 15.1 14.0 16.5 15.1 T-62 16.5 15.0 16.8 15.0 T-63 14.9 13.3 14.5 13.1 T-64 13.9 12.3 16.0 14.4 T-65 13.3 12.3 15.5 15.3 T-66 13.5 20.2 39.3 45.9 T-67 14.5 13.9 16.2 14.9 (a) Sample no! collected, see Appendix D - Program Execution.
O C-2
Fermi 2 - l997Annu:1 Radioactive Effluent Release and Radiological Environmental Operating Report
, h.
( )
FERMI 2 AIR PARTICULATE GROSS BETA (pCi/ cubic meter)
API-l FIRST QUARTER l StartDateStad Dateil25.iSActMeym'Rh1 12/30/96 01/07/97 i 3.10E-02 +/- 3.00E-03 01/07/97 01/14/97 +/- 4.00E-03
{ 3.70E-02 01/14/97 01/21/97 _j 3.30E-02 +/- 4.00E-03 p_1/21/97 }01/28/97 j 2.80E-02 +/- 3.00E-03_
01/28/97 l02/04/97 I 3.40E-02 +/- 3.00E-03
~
~d5T04/97 Id2/ll/97 1 2.20E-02 +/- [37605 65~
7 p2fil/97 02[18/97 _ ,_ ,_3.10E-02 +/- 3.00E-03 02/18/97 02/25/97 4.10E-02 +/- 6.00E-03 02/25/97 03/04/97 2.70E-02 +/- 4.00E-03 03/04/97 103/11/97 ' 2.70E-02 +/- 3.00E-03 i03/18/97 2.60E-02 +/- 3.00E-03
[57[U97 03/18/97 03/25/97 1.90E-02 +/- 3.00E-03 03/25/97 04/01/97 2.00E-02 }+/- 3.00E-03
'Y '
API-1 SECOND QUARTER l: Start Date I tad Date:I m m 4ctMtf2 % &l 04/pl/97 ___ p4/0_8/97. _ _2.20E-02 +/-
. 3.00E-03_
p4/q8/97 04/15/97 ___ 2.50E-02 +/-
_ 3.00E-03_
04/15/97 04/22/97 2.50E-02 +/- 3.00E-03 04/22/97 04/29/97 2.20E-02 +/- 3.00E-03 04/29/97 05/06/97 l 2.10E-02 +/- 3.00E-03 05/06/97 05/13/97 l 1.90E-02 +/- 3.00E-03 05/13/97 05/20/97 2~ +/- 3.00E-03 f0TE 02 05/20/97 05/27/97 y 1.30E-02 +/-
2.00E-03 05/27/97 06/03/97 l 1.50E-02 +/- 2.00E-03 06/03/97 06/10/97 i 2.00E-02 l +/- - 3.00E-03 06/10/97 06/17[97-~I~5.(5dE[7 d65[
06l17/97. _ 06/24/97_ _ _ L2.00E-02 +/- 3.00E-03 I
LO6/24/97 l07/01/97 l 2.40E-02[+/- 3.00E-03 l
gs
- k. )
C-3
Fermi 2- 1997 Annual l Radioactive Effluent Release and Radiological Environmental Operating Report (D
'%)
FERMI 2 l
AIR PARTICULATE GROSS BETA (pCi/ cubic meter)
API-l TillRD QUARTER Start Date!l Tend DateTE 1 :WActMtyqGMA l 07/01/97 i07/08/97 6 1.90E-02 +/- 3.00E-03 Of768/97IO7T59f 2XUEd2 +/- 3.005! 0 f]
i07/15/97 07/22/97 l 3.40E-02 +/- 5.00E-03 07/24/97 ]7](9791[ 2.50E-02 +/_
3.00E-03
-07/29/97 08/05/97 2.40E-02 +/- 3.00E-03 08/05/97 08/12/97 (a) 08/12/97 08/19/97 1.40E-02 +/- 2.00E83~
08/19/97 08/26/97 2.40E-02 +/- 3.00E-03
~ ~* ~
08/26/97 09/02/97 2.40E-02 +/- 3.00E-03 09/02/97 09/06/97 3.10E-02 +/- 5.00E-03 l
09/09/97 09/16/97 , 4.40E-02 +/- 8.00E-03 09/16/97
- l09/23/97 1 1.70E-02 +/- 2.00E-03 U972557 j09/30/97 ))0E-02 +/- 2.00E-03 _
API-l FOURTil QUARTER
[StartDasetEnd Date 1 , w AssivisfMmps!
09/30/97 10/07/97 ! 2.10E-02 +/- 2.00E-03 1 10/07/97 10/14/97
}]3]26E323/- 3.00E-03 I.0/14/97 _
10/2I/97 2.10E-02 +/, 3.00E_03g 10/21/97 10/28/97_ 6 1.90E-02 +/- 3.00E-03 J 10/28/97 11/04/97 7 3.00E-02 +/- 3.00E-03 11/04/97 1I/11/97_ 710E-02 +/- 3.00E-03 11/11/97 1I/18/97 1.90E-02 +/- 3.00E-03 11/18/97 11/25/97 4.70E-02 +/- 4.00E-03 11/25/97 12/02/97 3.30E-02 +/- 3.00E-03 12/02/97 12/09/97 2.10E-02 +/- 3.00E-03 12/09/97 12/16/97 3.40E-02 +/ ,3.00E-03.
[12/16/97 12/23/97]_3.80E-02 +/- '4.00E-03 _
l12/23/97 12/30/973_2.70E-02[+/- 3.00E-03 (a) Sample not collected, see Appendix D - Program Execution.
C\
L) c-4
I Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report f%.
b FERMI 2 AIR PARTICULATE GROSS BETA (pCi/ cubic meter)
API 2 FIRST QUARTER StartDate ifEndDate I frWmJettvityMA 12/30/96 01/07/97 L3.60E-02 +/- J4.00E-03 01/07/97 01/14/97 4.10E-02 +/- l4.00E-03 !
UI/I45f701/21/97 3.70E-02
+/- f4.00E-03 01/21/97 101/28/97 3.00E-02 +/- '4.00E-03 l d~l 2if/E7[]62)d097 ' ))~3Jd65-Ui[+/
~
4.00E-03_.
, l 02/04/97 02/11/97 , 2.50E-02 +/- 3.00E-03 I)2 it'/97- 62)[8/97~ l 3'.10E-52 W~ 4506E-03~
~
02/18/97 +/- 3.00E-03 02Ii5/97][][2}20E-02 _
02/25/97 03/04/97_f _2.60E-02 +/ _3,.00E-03_
l 03/04/97 __ 03/11/97__ j 3.20E-02 +/- 3.00E-03 03/11/97 03/18/97 i 2.90E-02 +/- 4.00E-03 i 03/18/97 03/25/97 I 2.30E-02 +/- 3.00E-03 03/25/97 _
. 04/01/97] 2.30E-02 +/- 3.00E-03 _
l
('~))
API-2 SECOND QUARTER SimrtDese+Emd DateilmasW@fERl
_04/01/97 04/08/97 2.50E-02 +/- 13.00E-03 04/08/97 04/15/97 2.50E-02 +/- 3.00E-03 04/15/97 04/22/97 2.80E-02 +/- 3.00E-03 04/22/97 04/29/97 2.10E-02 +/- 3.00E-03 04/29/97 05/06/97.
_2f0E-02 +/- 3.00E-03_
05/06/97 05/13/97 2.20E-02 +/- 3.00E-03 y[lpf 05/20297
[}2.265-Id}/~ 3'.[d6if-k]
05/29 @ 7 05/27/97 l 1.70E-02 +/. 3.00E-03 _
05/27/97 106/03/97 __ ! ..1.70E-02 +/- 3.00E-03 06/03/97 06/10/9 7 5.I)dE-02 +/- 4.00E-03 "
196/10/97 _ 06/17/97 _ _2.60E-02 _+/ . 3.00E-03_
'06/17/97 06/24/97 2.40E-02 +/-
~
3.00E-03 yI2i/97 6f/UT/9f~[i.'76E 62~ +/- 37 65~U5 -
i ! s.
L )
c-5
Fermi 2- 1997Annut!
1 Radioactive Effluent Release and Radiological Environmental Operating Report
,o I
FERMI 2 AIR PARTICULATE GROSS BETA (pCi/ cubic meter)
API-2 THIRD QUARTER i
l Start Date l:End Date - l" 6! ActMtybMA .l {
07/01/97_ j07/08/97 _ j_2 20E-02}+/- 13.00E-03 pl[08/9? _ p]/15/97__ L2.30E_-02[+/ _{3.00E-03
[07/15/97 [07/22/97 2.30E-02 +/- l3.00E-03 l 07/22/97 [07/29/97__ _ 2.30E-02 +/- p.00E-03 l 08/05/97 2.8pE-02 +/- 3.00E-03 _
l E709/97_08/12/97 08/05/97 08/12/97 08/19/97 2.20E-02 +/- 3.00E-03 _
l 1.80E-02 +/- 3.00E-03 08/19/97 08/26/97 ' 2.00E-02 +/- 3.00E-03 08/26/97 l09/02/97 __2.40E-02 +/ _ 3.00E-03 09/02/97 09/09/97
_2.50E-02_
. +/ _ 3.00E _03_
.09/09/97.__^ .09/16/97 2.60E-02 +/- 3.00E-03
~
09/16/97 +/- 3.00E-03 09/23/57]~~] 3.10E-02 (09/23/97 09/30/97_L2.20E-02_ +/- 3.00E-03 J l APJ-2 FOURTII QUARTER
%*umsapEnd Date l n:222:mActMtysh'aunl 09/30/97 3.00E-03 10/07/97 ] 3.30E-02 l +/-
10/07/97 10/14/97 2.90E-02 +/- 3.00E-03 I9/14/97_ 10/21/97
. . _ l.90E-02 +/- 3.00E-03_
l 10/21/97__ 10/28/97__ 1.60E-02 +/- 3.00E-03 10/28/97 11/04/97 _.2.80E-02._+/- 3.00E-03._
~I'l/04/97 T 0 11/11/97]__ 2.00E UE"II-]fU~E-03 11/11/97 11/18/97 1.50E-02 +/- 3.00E-03 11/18/97 11/25/97 4.50E-02 +/- 4.00E-03
~
^
Ii65/97 i'57 2/97 3 3.20532 +/- 3.00E-03 12/02/97 12/09/97 1.70E-02 +/- 3.00E-03
( 55/09/97 i2/16/97 3.30E-02 +/- 3.00E-03 II2I6/51 ]IEIE3/97' ~ 32 ~ ~d'E 52}[+I~ EUUE-03 12/23/97 _12/30/97 [_2.40E-02l+/- l3.00E-03 g l
I p) u C-6
Fermi 2 - 1997 Annz"!
Radioactive Effluent Release and Radiological Environmental Operating Report (m.
(-) FEIG1I 2 AIR PARTICULATE GROSS BETA (pCi/ cubic meter)
API-3 FIRST QUARTER l hDate l Mad Date t::: cars AstMayid.eistm]
l 12/30/96 1/7/97 { 3.60E-02 +/- 4.00E-03
]~/7/97__ . 17iT[97[] 3.40E-02 +/- _
4.00E-03_
I/I4/97 l
1/21/97
. ] 3.40E-02 +/- _
4.00E _03_3
.1/21/97 _ __ ]If28/97 _ _! _3.70E 02+/- .
6.00E-03_ _
!1/28/97 12/4/97 i 3.50E-02 +/- 4.00E-03
~~
I2/i/57[ 2
~ 71iI97} I; ~2[2dE-02li{l]0'_0E 05 {2/11/97 2/I8/97 < 3.10E-02l+/- 3.00E-03 I2/18/97 2/25/97 j 2.20E-02 +/- 3.00E-03 2/25/97 3/4/97_ _[2.30E-02 +/- 3.00E-03 3/4/97 3/1I/97 l 2.70E-02 +/- 3.00E-03 l IliT/N 3/18/g r 2.80E-02 +/- 4.00E-03 l 3/18/97 3/25/97 2.40E-02 +/- 3.00E-03 3/25/97 4/1/97 . 2.20E-02 +/- 3.00E-03 0 \ V API-3 SECOND QUARTER StartBatsfXad Date !l5ssdHMif3f;Mih 4/1/97 4/8/97 2.00E-02 +/- 3.00E-03 4/8/97 4/15/97 2.60E-02 +/- 3.00E-03 4/15/97 .4/22/97 2.40E-02 +/- 3.00E-03 1 4/22/97 4/29/97 3 2.10E-02 +/- 3.00E-03 4/29/97 5/6/97 J 2.00E-02 +/- 3.00E-03 5/6/97
.5/l3/97 _
5/20/97
$/13/97 5/20/97
{f27/97 [l 1.90E-02. +/-
~
E 1.50E-02 +/- 3.00E-03 IdOE d2 +/- 3.00E-03_ i 3.00E-03__ l 5/27/97 16/3/97__ i 1.80E-02 +/- 3.00E-03 I6/3/97 I6/10/97~ ~ 1.90E-021+/- 3.00E-03l
~
IUidl9"f 6/17I9 7 ~~2.'E6E-d2*+/- 3.00E-03 I6/17/97 6/24/97-Y 536El} 06E-03 [6/24/97 7/1/97 l 2.30E-02 +/- +/- $l3 00E 03 A C-7
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report m FERMI 2 AIR PARTICULATE GROSS BETA (pCi/ cubic meter) API-3 TillRD QUARTER l Start DatelEnd Date l ew WActMayr&rm cl
,7/1/97 _ _7/8/97 _ _ _ L 1.90E-02 +/- 3.00E-03 j 7/8/97 7/15/97 ! 1.30E-02 +/- 2.00E-03 '7/155) 7/22/97 [ 2.20E-02 +/- 3.00E-03 7/22/97 7/29/97 l 2.40E-02 +/- 3.00E-03 7/29/97 8/5/97 i 2.50E-02 +/- 3.00E-03 8/5/97 8/12/97 l 2.10E-02]+/- [3.00E-03 8/12/97 8/19/97 _j 1.90E-02 +/- "3.00E-03 8/19/97 8/26/97 1.90E-02 +/- 3.00E-03 2.20E-02 +/-
8/26/97_Q9/2/97_ 9/2/97 2.50E-02_, +/- 3.00E-03 _ l j9/9/97 3.00E-03 9/9/97 9/16/97 2.40E-02 +/- 3.00E-03 9/16/97 9/23/97__ l 2.60E-02 +/- 3.00E-03 9/23/97 9/30/97_]~]2 idE~0]+/- 3.00E-03 ~ l API-3 FOURTil QUARTER ; i I?StartDate;l:End Date~ l117 'ActMay? R il al ! 9/30/97 10/7/97 2.90E-02 +/- 3.00E-03 J l l_0/7/97 10/14/97 ._ 2.70E-02 +/- 3.00E-03 J j 10/14/97 _ 10/21/97 _ , {_ _ l.90E-02 +/- __ 3.00E-03_ 10/21/97 10/28/97 2.00E-02 +/- 3.00E-03 10/28/97 11/4/97 _ 2.70E-02 +/- __ 3.00E-03_ ; 11/4/97 11/11/97 1.90E-02 +/- 3.00E-03 l 11/11/97 1I/18/97 1.80E-02 +/- 3.00E-03 il1/18/97 11/25/97 7 (a) - i IIllf579I 12I2N1 T 3.iOE-02 +/- 3.00E-03
'12/2/97 12/9/97 ! 1.70E-02 t +/- 3.00E-03 ~;
!- 12/9/97 12/16/97 ~TT20E 0i[+/- 3.00E-03 ! 12/16/97 12/23I97~ ~ I3.70E 52 I/IlD652 05 ~ Ifl}j57 +/- 1 /50I97]{2.70E-02 _ 3.00E-03 J (a) Sample not collected, see Appendix D - Program Execution. (a\ C-8
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report l ! ) v , FERMI 2 AIR PARTICULATE GROSS BETA (pCi/ cubic meter) API-4 FIRST QUARTER fMWTEmlDakt M96WWMMs?j 12/30/96 ' 1/7/97 3.50E-02 +/- 14.00E-03
'I'/7 57 ~ Til/57))[
1 _3.90E-02 +/ '4.00E-03 1/I4/97 1/21/97 ! 3.30E-02 +/- 4.00E-03 TI2iI9t} ,_[1/28/97 i _ _(a) . __ _ _ _ _ _ _ _ , 1/28/97 2/4/97 5.00E-02 +/- 6.00E-03 s/k9b [0DEj{2{+[fdO5-UI 2/11/97 N 97 ._ l2/18/97 -- ; 3.10E-02 l+/-4.00E-03
-3 f./25/57 5 I4'79 7~~ ~ ~5E-022.3 +/- f6DE-03 }T4'/97 3/11/97- 3.1OE-02 +/- 3.00E-03 3/11/97 3/18757 3.00ET2~ +/- '4.00E-03 3/18/97 ~I3/25/97 3.00E-03 ! 2.10E-02}+/-
Nk(_. 5k . ... 2]@ly2]/{3.005-~63[ Ch a API-4 SECOND QUARTER [ggarfDateT1blDatet'OESWh$$WifESW"f] 4/1/97 4/8/97 l 2.30E-02 +/- 3.00E-03 4/8/97_ 4/15/97 ] 2.70E-02 +/- 3.00E-03 4/15/97 4/22/97 2.70E-02 +/- 3.00E-03 4/22/97 4/29/97 2.30E-02 +/-
~
3.00E-03 4/29/97 I37679 7~ ~~[~iUU5~02 +/- 3.00E-03 576 67~~~}5/13/9f , 2.105-02 +/- 3.00E-03 1 jg3]i((_]y6K / {l].9(5yi}/[_~~ 3 1 E-03 5/20/9_7_ 5/27/97 41.40E-02 +/- 3.00E-03 5/27/97 6/3/97 1 1.50E-02 [+/- 3.00E-03 6/3/97 6/10/97 -~l 2.40E-02[+/ T00E-03 6/10/97 6/17/97 2.30E-02 +/- 3.00E-03 6/17/97 6/24/97 2.20E-02 +/- 3.00E-03 6/24/97 7/1/97 _i 2.00E-02]+/- 3IUUE-03_ (a) Sample not collected, see Appendix D - Program Execution. Eh ) i
%J C-9
Fermi 2 - 1997 Annual Radioacth'e Effluent Release and Radiological Environmental Operating Report O FERMI 2 AIR PARTICULATE GROSS IIETA (pCi/ cubic meter)
' API-4 TillRD QUARTER l StartDate l End Date l sr WActMtym:Wvl 7/8/97 !?/1/97.._ 7/15/97.. 11.70E-02j+/- J3.00E_-03 j 7/8/97 j 1.90E-02 +/ _2.00E-03_J .
7/15/97_ {7/22/97 i 2.20E-02 +/- 3.00E-03 (7/22/97 _ ___ 7/29/97 2.00E-02f+/- f 3.00E-03
- 7/29/97 .,8/5/97 2.10E-02 l +/- 3.00E-03
; _ 2.20E-02 f +/-3'.'00E-03 '
8/5/97 i8/12/97~
+ ~
8/12/97 18719I97 I ~I.70E-d2iiI ~ I3 06E-d3 - 8/19/97~~Y8/26/97 ; 1.90E-02l+/- 3.00E-03 ~ jI25/97. 9/ff97} ~ ((130E d2i+/- [3]00E-03 9/2/97 9/9/97 2.20E-02 +/- 3.00E-03 579797 9/16/97~ 21505-027/- 3.00EW 9/I6M7 9/23/97._ _ _2;10E-02 +/ __j3.00E-03__ . 9/23/97_ 9/30/97 l 1.80E-02i+/- J3.00E-03 _ O api-4 FOURTil QUARTER l Start Datet.End Date . lPW8:ActMty >$04 :l 19/30/97 10/7/97 i 3.20E-02 +/- 3.00E-03 10/7/97 10/14/97 [ 2.90E-02" +/- 3.00E-03 10/I4/97 10/21/97 . _ j _l .70E-02 +/- 3.00E-03_ p/21/97. _ , . l0/28/97 _. g 110E-02[+/ _ 3.00E@ 10/28/97_ 11/4/97_ _ _ ! 2.60E-02{+/- 3.00E-03 _j 11/4/97 3.00E-03
- - . - 11/1.1/97 .{ 2.40E-02 l +/- ~
I1718/97~~
.lIl'/25/97 ~ .
I T60E52[i/7ld.00EW . .. I5/i/9f~'~fI557N I?/05-02+/O 3?UD5~'OT~l I2 / 97 . ] l 271[629 7 3}05-02 +((6 E}d[
... . ^
12[16/97 ] I2/23/97 _ ; 3.30E-02_ +/- 3.00E-03 [12/23/97 fl2/30/97 1 4.80E-02[+/- 14.00E-03 O C-10
)
l
. ._ 1
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radioivgical En vironmental Operating Report O FERMI 2 AIR PARTICULATE GROSS BETA (pCi/ cubic meter) API-5 FIRST QUARTER l: Start Date l'? End Dated lrtO " Activity;f%::M::il 1/7/97 [12/30/96 __ __ f _3.20E _02}+/- 13.00E-03 1/7/97 1/14/97 4.80E-02 +/- [4.00E-03~
23bE-02{f/~i4l6d5-~d3_. ~~
[f/13/97 ' ~ 1721/97~
~
IIi[/91-~iil2'8297~.
-. 3! U5-65l+/- j4.00E-03.- ~ '5/4T97~ ~ ~ I2[l'iI97 I2.T0E-627/7!5dU~E-6f~l ~
lil797 '5Tl8I9' 7~ '3.d0Ed2 i
-~+/ -^5.06E- 5 ~l 2/18/97 2/25/97 , 2.60E-02 +/- 3.00E-03 -. . . _ - +
3hiI97~ '!3/11/97 2.60E-02 +/- - 3.00E-03 7 3 li/97~ ~l3/18797'~ ~~'65-02 2.8 II-Ti.~605-55 I3/18/97 ] 3/25/97 _[ 2.30E-02 +/ _ j _ _2.20E-02j+/- ]_i3.00E-03 [3/25/97 l4/1/97 _ 3.0DE}03 : O API-5 SECOND QUARTER l Start Date%End Date- l', a ActiFityEin d 4/1/97 4/8/97 [ 2.00E-02 +/- J3.00E-03 l
.4/8/97 _ . 4/I5/97 . L 2.30E-02 +/-
3.00E-03 J 4/15/97 4/22/97 ! 2.60E-02 +/- 3.00E-03 14/22/97 4/29/97
~ ! 2.20E-02 +/- 3.00E-03 4/29/9f ~ SI6/97((_[2'.id5d 4/- i.06E-6f ~
5/13/97 3.00E-03
$$97___5/20/97__
5/13/97 . {_2.10E-02
, _ _2.00E-02 .+/-]3.00E-03_
5/20/97_ 15/27/97 , +/ _'[!
~
i 1.60E-02i+/- 5.00E-03 !
~5 27797 6/379"f El'.555dli+/- [3.00E-03' 6/3/97 6/10/97_j 27053ii+/- j3.00E-03 6/10/97 6/17/97 l 2.40E-02i+/- 13.00E-03 KIN bI97 2}}d532]fgj3 00E-03 @M91_ __ 7/1/97 _ [ 2.30E-02j +/- [3.00E-03 _
O 1 C-11
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O FERMI 2 AIR PARTICULATE GROSS HETA (pCi/ cubic meter) API-5 TillRD QUARTER l Start Date:l' End Date' l"R= " Activity K %V Cj i7/1/97 !7/8/97 2.10E-02 i +/- 13.00E-03 i
~
7/ I!3bb 2.40E{dk/{}5%Q3 [7/l5/97 _j7/22/97_ _ j_ _2.20E ,02 t +/ ___g.00E-03 y 7/22/97 j7/29/97 _{__2.60E 02{+/ j3.00E_03 J 7/29/97__ . l8/5/97 1 2.30E-02 i +/- l3.00E-03 I ' I8I5797~ ~ ~ ~'!8/i2I97 2.50E-OihI-~'i3l60s-dfl
~
8/12/97 [8 i929 7~~ f~~'~150E-62 +/ "3565~-~63 8/19/97 l 2.20E-02 +/- 3.00E-03 l8/26/97 8/26/97 19/2/97_ _ [-[_2.20E-02 _ +/ _ 3.00E-03_ 9/2/97 19/9/97 j 2.70E-02 l+/- 3.00E-03 9/9/97 9/16/97 2.70E-02i+/- i3.00E-03 9/16/97 9/23/97 2.30E-02[+/- [3.00E-03
@j/(( ~ ~~
9/30/9{]_ _ ]2 E[2[+/- l3.00E-03 O API-5 FOURTII QUARTER [ Start Date lr End Date -F e ActMtyo- d 9/30/97 3.60E-02 +/- 4.00E-03 10/7/97 10/7/97 y_2 10/14/97 i 80E-02 +/- 3.00E-03
- v- - ~
10/21/97 10/28/97 1.80E-02 +/- If005~-i)f~ l10/28/9711/4/97 i l 2.70E-02 +/- 13.00E-03 ~~
.I I/4/97-___.J [_lf! 1]_97 i.iOh- ijs-{]3700E{d}[1 ]1/11/97 ~ lI/18/97 ! 2.10E-02 ! +/- 3.00E-03 i
_[1IiU9"I- 11/25297 '_ {d.40E-02]{T-],[4.'dUE[l l_1/25/97 _ 12/2/97._ L 3.20E-02Q/_{3.00E-03 12/2/97 12/9/97 : 1.80E-02 i +/- 3.00E-03
'iEIU97 157165 7' 3.30E-02 +/- 3.00E-03 ' FIT 6/97 127 3 S 7 ~~
I~~~~336E'62 IT"370I)s-03 Liia3Mf71Y/i5/97 [6.NE-U2[ 3 6dtI-~6f] O C-12
Fermi 2- l997 Annual Radioactive Efflue st Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/ cubic meter) API-l FIRST QUARTER l Start Date l End Date 4;;7 Activity?;j 12/30/96 [1/7/97 ___j _< J2.00E-02 _J 1/7/97 j < 13.00E-02 [l/l4/97 _ 1/14/97 1/21/97 < l .00E-02
} I/2I/97_ _ . 1/28/97 _
1.00E-02_
.2/4/97 _ !<. l .00E-02 t i/28/97
[2/4/97__]2Il1797[][2.00E-02_
!2/I1/97 !2/18/97 ! < l2.00E-02 ~
2/j'8'797~ ~ ~i2/25/97 ~~I < l5.0dE-U3-2/25/97 < i4.00E-02 3M/97~ 13/I'l/97 f3/4/97 '~ 7~ < ~I2'.UUE42~~ 3?[l/9"f .{3/18/97~~[ <]3[00E-y2 ] [3/18/97 l3/25/97 : < !2.00E-02_ l i3/25/97 i4/1/97_j < }l.00E-02_l API-l SECOND QUARTER l' Start Date l End Date$ cActivity+#1 4/8/97 j _ <j2.00E-02_ [4/1/97_ _ _ _ _ M/8/97. _ _ _ 4/15/97_ _ i <g 3.00E_02__ _ 4/15/97 _ .4/2.__ _ _2/97 j < l2.00E-02 4/22/97 4/29/97 < 2.00E-02_ 4/29/97. _ _ _ _ 5/6/97 _ _ _ _ <_2.00E-02__ [5/6/97_ _ _ _ _ 5/13/97. _ _
.. 2.00E_02 __ _ _ _
5/13/97 __ . 5/20/97 _
< 2.00E-02 5/20/97 5/27/97 _ __g2.00E-02_ < g 5/27/97 6/3/97 < 3.00E-02 6/l0/97_ < 2.00E-02 _
l6/3/97_ _ _ _ .6/17/97_ i_<_ _ . (6/10/97
;$/I7/97 ,3.00E-02 ;6/24/97 . _.M6/24/97
_ L7/1/97 _ _j[ _j3.0C"-02g
<< !1.00E-02 O
C-13
Fermi 2- l997 Annuri Radioactive Effluent Release and Rediclogical Environmental Operating Report (,) FERMI 2 AIR IODINE - 131 (pCi/ cubic meter) API-1 TillRD QUARTER [ Start Date Fend Date-[7 2 Activity %-l i7/1/97 7/8/97 j < l2.00E-02 [7/8/97 7/15/97 l < [3.00E-02 7/15/97 7/22/97 1 <j6.00E-0._ 7/24/97 __ 7/29/97. _ .. ! < l2.00E-02 i
'~(a C 18/5D7 18/12/97' [
57i /f7
~
38Ii9/97 ~i < l.00E-02 5/i5797 [8/2'6797 ~~~I< 2.00E-02 8/26/97 ~i 579[9 < 3.00E-02 9/2/97 9/6/97 < 3.00E-02 9/9T97 9715/97-~ < 4.00E-02 9/16/97 9/23/97 < 2.00E-02 9/23/97 9/30/97 < 2.00E-02 API-l FOURTH QUARTER [StartData=l EndDateS ActiMiy4 9/30f97 ,10(7/97__ < l.00E-02 l_0/7/97 10/14/97 < 2.00E-02 10/14/97 l_0/21/97
< 2.00E-02 10/21/97 __ l038/97_ < 2.00E-02 10/28/97 11/4/97 < 2.00E-02 11/4/97 11/11/97 } < '2.00E-02 .I.1/11/97 11/18/97 11/I8/97 11/25/97
[< l.00E-02] 2.00E-02 11/25/97 12/2/97 < 3.00E-02 12/2/97 12/9/97 < 2.00E-02 (279X7_ ll/I6797_ 3.00E-02
< l.00E-02
_I2/16/97 12/23/97 12/23/97 12/30/97 __
< l.00E-02 (a) Sample rc . collected, see Appendix D - Program Execution.
l i O C-14
l l 1 Fermi 2- l997Annurl Radioactive Effluent Release and Radiological Environmental Operating Report l FERMI 2 l L AIR IODINE - 131 (pCi/ cubic meter) API-2 FIRST QUARTER h8tartDate l{'Ead Date Itt Aa MgaEl 12/30/96 < 2.00E-02 ._j
}l/7/97 l 1/7/97 1/14/97 < 3.00E-02 l
1/14/97 1/2I/97 < l.00E-02 NNY N8/97 < 2.00E-02_, 1/28/97 2/4/97 I< 2.00E-02 < 2~ [~ /4797 I/IiT97 IY2.00E-02
!2/11/97 2/18/97 !< 2.00E-02 i -
[gjg797- ~ - - 2/25/97 ~ l T 166E df~ 2/25/97 .- 13/4/97
- - . .l < 13.00E 13/11/97 T< 3.00E-02
[37f8797]}j3/18/97~~
~
3/25/97 A XD6E-02 [3/25/97 l4/1/97 < 2.00E-02 { API-2 SECOND QUARTER [StartDate l End Date Ic - AetMtyEdij l 4/1/97 4 4/97 _ < 13.00E-02 j 4/8/97 4/15/97 < j3.00E-02_ . 4/15/97 4/22/97 < 3.00E-02 I4722/97 4/29/97 < 3.00E-02 l
~
[d/29/97 576I9'/' < 3.00E-02 5/6/97 5/13/97 < 2.00E-02 L5/13/97 5/20/97 < 3.00E-02 {5/20/97 5/27/97 < 3.00E-02 57597 < hMI/97 _ 3.00E-02 _ 6/3/97 6/10/97_ < 2.00E-02
~
6/10/97 16/17/97~~ T 3.U E-6f -
;6/17/97 6/24/97 l <bT00505~
L6#w M971 Hy10;E1627i _ (m C c-15 l l _ _ - _ _ _ _ _ _ _ _ _ -
Fermi 2- 1997Annu:1 Radioactive Effluent Release and Radiological Environmental Operating Report tO (_) FERMI 2 AIR IODINE - 131 (pCi/ cubic meter) API-2 TlilRD QUARTER l Start Date l End Date~ l=ActMty //a l [7/1/97 7/8/97 i < 12.00E-02
~ !7/8/97 7/15/97 17/15/97 !7/22/97 Il{3[005-Ol]
[ < 13.00E-02 7s29[ 7/29/97
< 2'.'d0[0}]j
[7/29/97 8/5/97 [8/5/97 Q< 2.00E-02 2.00E-02 l8/12/97 "8T15797 8/l9 97 -[~C 2.00E-02 8/19/97 8/26/97 < il.00E-02 8/26/97 9/2/97 l2T00E-02 9/2/97 9/9/97 f~<l1.00E-02 E 9/9/97 9/16/97 < II.00E-02 9/16/97 9/23/97 < !2.00E-02 [9[/2357 ~]9730/97] ~Ti2T6 5-05] (]'8 API-2 FOURTil QUARTER
- l. Stas 6 Date$End Date lwAstMeykhj 9/30/97 10/7/97 < 12.00E-02 )
10/7/97 10/14/97 < [2.00E-02 i10/14/97 1Oi21/97 I_< !2.00E-02 l t 10/21/97 10/28/97 [ElIT0DII6I [10/28/97 jll/4/97 I < 12.00E-02 [11/4/97 ._ _ 11/l1/97 ][,[2.00E-02
. I
[11/11/97 _ 11/18/97 l < _1.00E-02] i 11/I8/97 11/25/97_ _ ' < 2.00E-02 l 11/25/97 12/2/97 ~
< 3.00E-02 l
III5/9f "Ii/9797- ~ ' < 2.00E-02 12/9/97 12/16/97 < 3.00E-02 l2/16/97 12/23/97 < l .00E-02 12/23/97 12/30/97 < l .00E-02 o C-16 w____--
Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/ cubic meter) API-3 FIRST QUARTER 5 l StartDate~l EndDate lM Activitye l Q2/30/96_ , _ _ 1/7/97 < 2.00E-02 1/7/97 1/14/97_ _ _ _ ., < 3.00E-02 _
. !!..I4/97 .l/28/97 I/21/97__[_<j l .0_0E-02._
l/21/97 < 2p0E__02
!!/28/97_ , _ . 2/4/97 ; _ < _,2.00E ,02,._
J[2/11/97> < !2.00E-02
!2/4/97 ~ ~
[2/11797 ~ !2/18/97 ]i<< I2.00E42] l2/18/97 2/25/97 2.00E-02 12/25/97 3/4/97 i < 2.00E-02 3/1II97 [3/4/97 < 4 200E-02 13/11/97 3/18/97 < ' 3.00E-02 I37f857~~ 3/25/97' i iO0E55~' (3/25/97 _ 'l/97 4 < l .00E-02 API-3 SECOND QUARTER l Start Date l End Date.t- :JActlyityJsj 4/1/97 4/8/97 < 2.00E-02 4/8/97 4/I5/97 < 3.00E-02 4/15/97__ V22/97 < 2.00E-02_
..f/22/97_ __yM7 __ _]~}~2 00E-02_ < 2.00E-02
{/29/97__ 5/6/97 5/l3/97 ., 5/6/97
< 2.00E ,02__
5/l3/97 . _ _ _ 5/20/97 _ _ _
< 3 20_0E-02__
5/20/97_ _ _ _ 5/27/97
. - . . - . . _ _ < 12.00E-02 . i ;6/3/97 6/10/97 l < l2.00E-02 i (610/{ 6/17/97' ~i' < ~I3.U6E32~l
[6/17/97 6/24/97 _ _J2.00E-02 J
@ @ 419 7_ . _.7/I/97 . _ _
_ j2.00E-02 l O C-17
l Fermi 2- l997Annu:I l Radioactive Effluent Release and Radiological Environmental Operating Report rm b FERMI 2 AIR IODINE- 131 i (pCi/ cubic meter) API-3 THIRD QUARTER l Start Date l End Date k' ActMtys:l 4 7/ l!97 ._._. ! . . . . _J.. .i . Jat_ 17/15/97__ [_ < jl.00E-02]J _
- 7/15/97 17/22/97 !< 3.00E-02 i I7/22I97~ ~ ~17/29/97 ' I<^2.0d'E-D2 ~
17/29/97 j8/5/97 i < 2.00E-02 [8/5/97 8/12/97 3.00E-02 8/12/97 8/19/97 i~{32 00E 02 8/19/97 8/26/97 < lI.00E-02 8/26/97 '9/2/97 < l2.00E-02 9/2/97 9/9/97
< l .00E-02 9/9/97 9/16/97_ < l .00E-02 9/l6/97 9/23/97[] <___ 2.00E-02 9/23/9 { _ _{9/30/97 j_< 2.00E-02 API-3 FOURTH QUARTER l: Start Date l tend Dateel?" Actlyltyutd
[9/30/97_ _10/7/97 _ _, <_2.00E-02_
> 10/7/97 10/14/97 < 2.00E-02 j 10/14/97 l 10/21/97 < 2.00E-02 10/2I/97 ~ 10/28/97 < l .00E-02 ~~
II6/25I9f'~ ~ ~ 'i1/4/97 i TiiO0E-Of ~ i1/4/97 11/1D97 ! < 12.00E-02 l 11/11/97 I < ' l.00E-02 11/18/97 l1/18/97 11/25/97 l (a) 11/25/97 12/2/97 I2722f] <_ 3.00E-02
< 2.00E-02 l
12/9/97 12/9/97 12 I~6797N < 3.00E-02 12/16/97 12/23/97 ~T<~[I.60E-02 J272T/97] 12/3dT9f~] <j1.00E!df] (a) Sample not collected, see Appendix D - Program Execution. (D
\
C-18
l 1 Fermi 2 - 1997 A;:nual Radioacdve Effluent Release and Radiological Environmental Operating Report ( h FERMI 2 AIR IODINE-131 (pCi/ cubic meter) API-4 FIRST QUARTER l StadDate l End Date -]v AetMay A i12/30/96 1/7/97 < 2.00E-02 k757' I/14/97 < 3.00E-02 1/21/97 < l .00E-02 ji/14/97 1/21/97
~
1/28/97 i
~ (a)
[1I28l97 2/4/97]~ {3. dE'62" l2/4/97 l2/11/97 i < i2.00E-02 ~ i2/1i757' l218/9'?~~ [ ] 230}E02{ 2/18/97 [ < '3.00E-02 2/25/97J3/4/97 _J2/25/97 _] <<_,. 3.00E-02 J 3/4/97 3/11/97 i 3.00E-02 3/11/97 3/18/97 I< 3.00E-02 3/18/97 .- 3/25/97 < 2.00E 02 i l' ( API-4 SECOND QUARTER [StadDateSEnd Date SH C*t41 4/1/97 4/8/97 3.00E-02 i 4/8/97 4/1579) (~<J 3.00E-02 4/15/97 4/22/97 < 3.00E-02 4/22/97 4/29/97 ,
< 2.00E-02 4/29p?_
_ 5/6/97 __<_ 3.00E-02_ __ 5/6/97 5/13/97 < 2.00E-02 5/13/97 5/20/97 < 2.00E-02 5/20/97_ _ , 5/27/97
.-l<
_ [ < l3.00E-02l 2.00E-02_ 5/27/97 6/3/97 6/3/97 _ _ . . - . _ . 6/10/97 . . .-,l ~ < .. 2.00E-02 ..
"6/17/97 < 1.00E-02 4 6/24/97 _
_j, <3_2 6/24/97 7 3 _/1/97, 00E-02 (a) Sample not collected, see Appendix D - Program Execution.
/^s V
! C-19
l Fermi 2- 1997 Annual l Radioactive Effluent Release and Radiological Environmental Operating Report ' /O kh FERMI 2 AIR IODINE - 131 (pCi/ cubic meter) API-4 TillRD QUARTER [ Start Date lf End Date :l9:ActMtyM] l 17/1/97 7/8/97 l < 12.00E-02 I [7I8/97 7 1597-^lZiddE-02
,7/22/97. _ j_ <_ . 3.00E-02 _ !7/15/97 ._,J7/2_9/97_ .
7/22/97 < 2.00E-02_ 7/29/97 8/5/97 < 2.00E-02 8/5/97 8/l_2/97 < 2.00E-02 t _ , l '8/12/97 8/19/97 < 2.00E-02 8/19/97 8/26/97 < l .00E-02 8/26/97 9/2/N ~ ~ ~ ~<-
^-
2.00E-02 UI2/97 l.00E-02 _ _ _ . 9/9/9f ._.I < u -- --. t_.-. l l ( API-4 FOURTH QUARTER { l l Stan Date l End Date lW AetMty Mj l
!9/30/97 10/7/97 i < 12.00E-02 j f10/7/97 10/14/97____ i<_ ' 2.00E-02 (10/_14/97_
10/21/97 110/21/97] 110/28/97
< .2.00E-02] < l .00E-02 l 10/28/97 11/4/97 < 2.00E-02 1 't i~[.U97 11/II/97 7 UOdE~I O2' l 11/11/97 11/18/97 < l .00E-02 11/18/97 11/25/97 < 2.00E-02 l 11/25/97 12/2/97 3.00E-02 l 32,5;4j ~ ' J219,4j'"'~j < }[ffg.92 fi i 12/9/97 12/16/97 ~l < 3.00E-02 I Il2/16/97 12/23/97 l < l .00E-02
[12 25/97 3 _2/30/97_ 1 _j_<_ l.,00E-02
'/ \
V l C-20
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operatin g Report O V FERMI 2 AIR IODINE- 131 (pCi/ cubic meter) API-S FIRST QUARTER l StastDale llEnd Date $ tin.AgIMtyMj I.2/30/9p___,[I/7/97 _ .
}_< l .00E-02 l ._
l.00E-02_j i dI7(97 _I./21/97 (I!.I4/97.___dl/14/97_ _ _ _. _ {<_ l .00E-02_; f i,1/2 I/97_ 1/28/97 < J2.00E-02 y , i1/28/97 .12/4/97 < ; i.00E-02 ' 2/11/97 f2/4/9Y.
} <)).00E-02] <
l2/11/97 .2/18/97 l .00E-02 I ~' ~ 2 18297~ 2/25/97 ~~ < 'l.0U5T62-~ , 2/25/97 3/4/97 < 2.00E-02 I r3/4/97~ 13/11/97 < 2.00E-02 [3 /1 i79 7^l3/l.8/97 '~ T < ~i6U5-~ 2~ 3/18/97 3/25/97 l< l .00E-02 3/25/97 4/1/97 !< l .00E-02 ( . i) API-5 SECOND QUARTER l StartDate l End Date-l*W r]
'4/1/97 4/8/97 , < 2.00E-02 4/8/97 4/15/97 < 2.00E-02 4/15/97 4/22/97 < 2.00E-02 I ~ '
375 I97 i/25/97 < l.00E-02 1 4/29/97 5/6/97 < 2.00E-F2-
}/6/91 5/13/97 5/1367[
5/20/97 [lUU5' : < 2.00E-02 5/20/97 __ 5/27/97. __J_<. _1.00E _02_ , J/27/9]_ _ _ _ 6/3/97 __ !< ,1.00E-02_ l p/3/97 i< 1.00_E-02_ 6/l 0/97__i_<_ l 6/10/97 6/17/97 _l .00E-02 6/17/97 6/24/97 l< l .00E-02 6/24/97 _ 7/1/97 _ ._ i < _ If0E-02_ O C-21
Fermi 2 - 1997 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperating Report C\ V FERMI 2 AIR IODINE- 131 [pCi' cubic meter) API-5 ThlRD QUARTER l StaatDate}End Date I w ActMar5@ j 7/l_/97_ _ 7/8/97. _ , _ < 2.00E-02_'
!7/8/97 7/15/97 < l .00E-02 j 7/15/97 _ _7/22/97_ (< 2.00E-02_
j< 7/22/97 7/29/97 l .00E-02 7/29/97 8/5/97 )< l .00E-02 [kkkb.__ .8/i225[7_[<-IT5U5-02 8/19/97 < l.00E-02 (8/12/97 8/19/97 8/26/97 < l.00E-02 8/26/97 9/2/97 < l.00E-02 V/557 579797~ ~ ~ ~ ^ - ~< f5.00E-03 9/9/97 9/16/97 < 9.00E-03 i 9/16/97 9/23/97 < l .00E-02 Vf23797 ~ 9 730/5F ~ ~ T iT0542~J l
/ ' I h API-5 FOURTil QUARTER ltStart Date!l; End Datet=TActMtysEl 10/7/97 < ,1.00E-02_
[9/30/97__.10/14/97___ 10/7/97 < l .00E-02 10/14/97 10/21/97 _
< l .00E-02 10/21/97 10/28/97 < l .00E-02 10/28/97 11/4/97 < l .00E-02 11/4/97 11/11/97 < l.00E-02 II[I.I/92 I.1/18/97 1< l .00E-02 11/18/97 11/25/97 < l .00E-01 11/25/97 12/2/97 < l .00E-02 l2/9/97 <
[12/2/97_ l.00E 02_
..12/16/97_ < l .00E-02 (12/9/97 112/16/97 12/23/97 i _<_ 8.00E-03 2sN97 ._._ J2/3g79{],[8.00E-03 , _
j I
' /.
l C-22 l l ? __________
Fermi 2- l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-l (indicator) (pCi/ cubic meter) lNuclide - -l- - First Quarter l, t Second Quarter - 'l 889_ .l._5!._2 p E-03) ! < 3.00E-03{ __ _
- SR-90 i <i 3.00E-04! ! i < 5.00E-04 !
IBE~~ ~ - 7 ' i' i 1.'12E-0liU-~ il.10E-02' !~ '1565-61 +T~II.705-~023
~ !K'-40 ~ Y ~ I~ 952E-63!O-~ "4.15E-03^~ [~ 'dI.0UE-d2 E l~ ~ - ~~ ~ ~~'l iMN-54^ I2I 300E U4I ~
l AI6 00E-04I~ i ~ ;
!CO-58 ~ 'i k!' li.005-Si' l 1 '~'i~2[I230EdO5-U3} ~
T<
~
IFE-59~ ~ ' AI25 5U3!~~
~ ~
1 ~3 ~
~~'l ~ '~ 'CO-60 ' <i 6.00604I I ' i < ^ 6.0 E-U4 IIN-55~~ <!~T5b5:53" T - T'<flTd55~63 l 'ij( 95 I~ <i 8.00E-04 E < ;R'O-IUj ~ [ < i.DdE-Ui '~ ~ j 8.00ET4"Y 7 ~~' <i 2.005~U3 l
- 'E $5U5'U3T 7 ~ ~ ~~ 'l IRO-f06T~~~ Ef100E-03i ~~ i$ ~~~ ~~~~~! ~<{I6565TM
[d5I3T i <I 6.00E-64
~
i
'CS-ij7 ' i EI ~5.00E-04 ~ ~! ~ d 6Tdd5ZO4 . - ~R f BA"-146 4 <!IT0dE-02}~{ i< ~ ' "~~ ~
T 0dE-U2 ~~
!CE-idt' T f~ 'I~ ~dl'2.00E 0'3 l ~ Ii ~350E'U3' ~ ~l
(['
~~
kE-ldi' ~ ~~dI230E 63 i~
~ ^ < 3.005'-If3 !RA-226 ' M 750543 < 9.00E-03 @ (UE[04 .. _ n [ ] ]_ 3 _9 p E-0 { , t___,
API-l (indicator) (pCUcubic meter) lNuclide - -l: 1
' 1hird Quaner (a) 1 ' , - Fourth Quanera 4 ..]
- SR-89 <l 2.00E-03 , i < 2.00E-03 fSFf^90 ~ <l' i 4 00E-04f'
~
I ^< ' 7 065164
. ' .i '~' ~ ' ! . ~[ ~ ~ ~A IMS-54~ 5565-~04 < ~d.UD5704 l f
[CO-58 w_ .-. EI7.UU5-04I.-_v -+ i '_-~ A 4~T ~ ~4 l - _N_565!- - . . -2.00E-03_[ [FE-59_ _ _ {<_ j2._ ,00E-_03 { _j _ _ _ < _ j CO-60 ! <! 6.00E-04! l < 4.00E-04 ; !
~ !ZNd5~~I'di~17UE-03I~l < 156E43 ~~ I ~~l ~ T<[!7.00E-04 ~
IIl{-95 i ~ <I~ 8.005-04I' I i i II(0-i~05 ~~i EF'l.~ E-U31~~ i
~~ I < l.065~-03 I7 ~ ~~
Ilio-ID5-~~~i~ <i'~450E43 1
~ ' 'iTUU5163< i~
ICS-i3i 2I~5.U05-63J ~ I ~'<I~i3U5~63 ~' I ~ - [Csi37 ~ YS505-~04
~ --
l~~~~" ~ 7 ~ih65104 ~ ~~ ~- BX-fid ~ ~"si~~15DE-U2 C ~ I2~2.'Ud5'U2 IC -141. -. . . _ ~~ 2I2. 05~-03[~
~ ~~ .__ ~~i _ ~IT27005!d3 ~~~i . _ _ _ _ _ ~ !}Q~.~226' ~-' 2 97005203 1 ~~~ < ~-8005-0'3 I~
fTild28]_]<{]8.00E-O' _j_ (a) Sample less than representative, see Appendix D - Program Execution. 4 ij _ [ __< ~7505-64]I ~~~ ] C-23
1 i Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report
T FERMI 2 (V AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS I
I API-2 (indicator) 1 (pCi/ cubic meter) l 1 INuclide H l - - First Quarter 1l Second Quarter:: - tl l lSR-89 - . - l. <! - 2.00E-03[ -. ! .- . - - a i <' 3.00E-03 - .- i . ! bey __ [ 7.~i2Ey_j y-]j.3)(U5] g 2.02E-01 +/- 2.00E-02_ i
!K-40 l 1.17E-02i+/- l4.40E-03 i < l.00E-02 I# " l !MN-54 < 7.00E-04I I'-~ 'IY6.00E-04 ' ~~'['~ ~ ~~ 'COTii 5 ~~~ ~ <!~1.' DOE-U3 ~ ~ i^< ~9'.065104 ~
(5{)) yo52)3^ (()){ .
~<< 3.00'5-53--
7.00E-04 _6.00E,,04 CO-60_4 <l < hN-65 2.00E-03 _ 2.00E-03 l2R-95 < l.00E-03 < l.00E-03 11U-103 < 2.00E-03 < 2.00E-03
< 6.00E-03 < 5.00E-03
_RU-106 _ CS-134 < 6.00E-04
<[ 7.00E-04l_ i __
CS-137 ; < 5.00E-04 BA-140 <{7'6d5~dif
< l.00E-021 < 3.00E-02 ~
- CE-141 < ! < 3.00E-03 l 2.00E-03'!
ICE-144 < 3.00E-03 I < 3.00E-03
~
(~N RA 226 <I8.dO5~ ~03 ~1 ~ ~ ~ < 9.00E-03
$$1 Y$.9b $ N. Y ~ I~ 55T03 A API-2 (indicator)
(pCi/ cubic meter) l lNuclide . !l : aThird Quarterm xl? w : Fourth'QuarterWA %l
!SR-89 < 2.00E-03 SR-90 < 4.
[<< 2.00E-03 ~ l _ _ 00E_-04 ._
._ _ __}_ _5.00E-04 BE-7 __ l.17E-01 +/- {l.20E 02] 8.57E-02 +/- 1.02E-02 K-40 ~~
(6.15E-03 +/- 13.14E-03 7.68E-03 +/- 3.62E-03
$1N-54 < 0 < 4.00L 04 4.0d5T 4I'T~ ~ ~ ~
FD C 58 < 6.00E-04}~ ~ < 5.00E n4 fli k-59
~~
I~ iO0E-03I~ ~ < 2.00E-03 CO-60 [3(1[5.00E-04-'<<L6.00E-04_._ j ZN-65 < 9.00E .04,_ l.00E-03 J ZR-95 < 8.00E-04 J
.RU-103 _<l _9.00E-04l 7.00E-04] [ _ __ _<. < l .00E-03 E .I_06 _ <l 3.00E-03l_j___ <
4.00E-03 _ _ _ CS 4 ._j_ 0EO ,_ 0 0 _ _ _ , _ _ _ _ _
~
IIIA'-T40~[< i'.0ds'-'d2I' 1 ~ ~ ~ 4 <i 1.00E-02 "CE-141 '~< I~16d5-'U3I~ l 3.00E-03 DE idi ~~[~"<I ~1005-03[~ ~ [< ~ [
~
3.00E-03 ~~ '~~ IRA-2}i ~< ~ l 7.00E-D3 'I !< l'.d 5'~02 - ~1 fTil-228~))3U5- {[ .
] ))~~8365-~04 {~~
C-24
Fermi 2 - 1997 Annual I Radioactive Effluent Release and Radiological Environmental Operating Report
~} FERMI 2 (V AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS l API-3 (indicator)
(pCi/ cubic meter) lNuclide." t - : First Quarter . -l wSecond Quarter 1 SR-89 ! <l 2.00E-03 )
^
l ' <> 5.00E-03 I I I~
~
SR-90 __ ..}~._2f~5.~UD5! 0 . 3 .. . ~ . . 2 7. 00E.04 N ~4 T - ^l 9.18E-037/- 14.19E43 < l .00E-02 ~ i- ~~ -~ lMN-54 [< 5.00E-04i ~I ~ [< 5.ED5~5ill - FC~OT 5 ff~ ' ~2I~7305T4 [' ~' ~ '~ { 7 ~5 6d5df ~ pg7gf-- T ~ ~ _ . _ 2 N 3 563. '_. _ _ __]_ 2 ._ 3.00E-01 -.___ __ _4.- u _.___ _ ZR-95 < 7.00E-04 l .00E-03
~~ <i ]~ i30E 03 ~~
RO! .!~0 - - . . .. T
-~f'~^'~.~.<<
2.00E-03 5 7 157~ ~ ii~53 5-U3-
-~ ~
[CS < ~Tii5:6i 5 pA-140 <i 1.00E-02 1 < 3.00E-02 p -141 Tif 1.00E-03Q__ CE < 2.00E-03 CE-144 < 2.00E-03 2.00E-03 e < 6.00E-03 __ ( < RA-226 l < 7.00E-03 ;
,, TH-228 < , 7.00E-04 l< 7.00E-04
_ l 1 API-3 (indicator) (pCi/ cubic meter) l I lNuclide3 . lh m Third Quarter < , 4ls 4 e Fourth Quarter (a) v 9 t l S,R-89 _j < 2.00E-03 ! _ ,_j __ _< _3.00E-03_ _ { _ _ _ SR-90 < 3.00E-04 i l < 6.00 E-04 i BE-7 9.1957 02 [il-1930545 - 832E-02 +/- 9.20E-03 l -
< 0 0 k8 3.. M 5kb4 __. . _ . .__ _n_1_ 8.QgE L ,_ _ _ _ , _ _ , _
pFE-59 <; 2.00E-03L_ _ i < 2.00E-03
,CO-60 < 3.00E-04; 9305~04I" ~ '~ ~ L<; 5.00E-04.
I I IZST65~~~T~~<j f <l 1.00E-03 l
'Eli35- MI'T db5-64I~ " ! ~ ~~ [l 2 8.U0ET0I RU-103 ]~iI 1.0 ~i'5~d3 ~ '---~ ~I~2[i3dE T65 f ~ 'RU-106 <' 4.00E-03 ['< 4.00E-03 l CS-134 < 4.00E-04 T < 5.00E-04 l CS-137 < 4.00E-047 < 5.00E-04 l 'BA-140 < l.00E-02 < 2.00E-02 CE-141 < l.00E-03 < 2.00E-03
_2.00E-03[_g, lCE-144 < i < 2.00E-03
~
RA-226 i < 5.00E-03l 1 i < 6.00E-03 [<]l 5.00E"df~~ $T "'iI~7.6U5-~63b'~ '
~~
l Til-228
~
(a) Sample les's'tVaseir'e~sintaifvi,'see A ndiiDT rograriEYecution. P C-25
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 G AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-4 (control) (pCi/ cubic meter) INuclidea - l x ' First. Quarter (a) -4% Second Quarter m ..i] SR-89 SR-90
<[ 2.00E-03_{_ <
3.00E-03 ( __ __<! . 3.00E_04 i 4.00E-04 . K-40 ]-(8[5,563 3,.98_5ii3]_< 2.00EIU2_, j j (MNj{_ _ __$i_4.00E-04 _ _ _
! <i 7.00E-04] j }
jCO-58__<(6.00E-04]_,4 _ _ __
< l.00E-03 ] _]
FE-59 < 3.00E-03
<i 2.00E-03L (CO-60
( <[ 4.00E-04_ i _ _. L<y 6.00E-04 lZN-65 <l 1.00E-03 i (< 2.00E-03
< l.00E-03 IZR-95 _$ __7.00E_-04._[
RU-103 < l.00E-03 < 2 00E-03 RU-106 < 4.00E-03 < 5.00E-03 CS-134 <, 4.00E-04 j 6.00E-04 , _ _g_ _S.00E-04 < fS?I37_, _$ 4.00E_-04 _ _ pA:140, < l .00E-02 [ _<_4.00E-0{_ , _
!CE-141. ,l _<g__2.00E-03__ L< _3.00E-03 < 3.00E-03 _4i _ _1<g3.00E-03 lCE 144 <}i 7.00E-03 G RA 226 '~ ~ ~~ ~ < 8.00E-03 ~ ~Ti l!f28] j[7.bd5703 ~^ ~E '~7.UUE-54 API-4 (et ntrol)
(pCi/ cubic r.ieter) lNuclide; Im , < nird Quarter F 3ln ~ f Founh Quarter " "1
< i $j _2.00E-03
[SR-89 _
< _2.00E-0}I 4.00E-04 < 5.00E-04 (SR-90 _ _ _ _ _ !BE 7 1.14E-01 +/- 1.10E 02 ; 9.10E-02 +/- 1.06E-02
, < 2ASE-021 1.38E-02 */- 4.70E-03 i (K-40 '~ iMN-54 <f'610Uh-DT~ i< 6.00E-04 M8~~ ~ANU5~03
~ ~ ~ ~ "l < 8.00E-04 f5~5W~ _iUUi5-}0g]i[_~((- < 3.00E-03 'CO-60 <
ZN-65 4<l 6.00E-04[_ 2.00E-031 < 6.00E-04 l .00E-03 ZR-95 <j l.00E-03[ ~
< 9.00E-04 (RU-103 !RU-106 li<l 1.005 U3(([-{' 2< " 1.00E-03 5.00E-03l p
j 7 , 5.00E-03l ! fCS-134~~ ~il 6.00E-04I I~~
~ < 5.00E-049~~
ti.T37~ ~~EI~~5.00E-04I'T ~ ~ ~~i 2 ~UI U564 IB -14D ~ ~E 2.D 5-U2 I l C'E 141 A ~5dU5-~05i~
~ ~ I < ^2 UUs-~UT I ~~d ~
2.00E-03
]R -- ~~ 'CE 144]~T3500E-53f}I~
T
~ ~ , ~ -]l ~~ ~ ~ ~ ~ ~
7 5UUE 03 b I RA 226 ~2 ~s.~dU5-63T ! [Ei ~8T005165 i [Tif-~ 28 <I Uf0E-04l [_] (a) Sample less than representative, see Appendix D Program Execution.
~~2~8T00hT04 {_ l C-26
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiologicallinvironmental Operating Report A FEIG112 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-5 (Indicator) l (pCi/ cubic meter) [Nuclide svl- - %First Quarter : -
-l -6
- Second Quartera . cl SR-89
<; 2.00E-03p y _ _ < 4.00E-03 SR-90 <( ,3_.00E-04_g j . < . _ _ _ 4.00E_04 BE-7 _ _ , 1.07E-Ol!+/- II.10E-02 1.89E-01 +/- 1.90E-02___
iMN-54 k _. .. . _):Nk9 b. 40Q _~< 1.2SE-02
<! 6.00E-04 f ' +/ g}4.50E - . - - _ - . - - . - . ..- - . 4.00E.04 -
IFE89 ~ T2 ~ - l ~ ' ~ ~~~~ ~ ~~~ ggg - F g! 2.60E'~0}[~~ -ggg j ~ - -- << 2.6UE-U3 4.00E-04 g _._ y- __ .- 97_ - -_
._.g . ,00g,0, .. ~ . . - - . - - < 4.00E-03 M ~106 }' ['.}065-U~5]_ ._
5.00E-04 y < 5.00E-04 [CS-134 ,
- CS-137 1 <<[ 5 00E-04f . < 4.00E-04 BA 140 < 8.00E-03 < 3.00E-02 4 -
fCh-141 <j 2.00E-03
<j 2.00E-03 .] _ <.. 2.00E-03 < 3.00E-03 3
l tQ [s_E-144A-226_ ,_ _<j 7.665[0((_[1 < 8.00E-03 i U
@I*228 ,,_1, <] 7.00E-04 . _ L 8.00E-04 API-5 (Indicator)
(pCi/ cubic meter) ; [Nuclide Wl
- Gird Quarter t *-la ~ ' Fourth QuarterW 4 xl )
f_ .. ._ .___ -_ _ . -_ _ _ . ! . K-40 6.20E-03 +/- 3.26E-03 < 9.00E-03
-~
IiVjRW~~-~~~2lTD0E-04 < 4.00E-04
- - . - -.i.-.. e
[CO-60 iY 4.00E-04 E~ l < 4.00E-04 ES_._L.5j ._1.00E-03{j] _ _ _ _<1_100E-03 _ 1 IZR-95 < j < 8.00E-04
.... . ! .6.00E-041-- .
f __ .-.u i
~
RU-106 <i 3.00E-03 < 4.00E-03
~
(d-134j <l 3.00E-04 < 5.00E-04 CS-137 l <I 4.00E-04 < 4.00E-04 [_ pA 1407 2l 1.00E-02 < 2.00E-02
;CE_-141 < 2.00E-03
(<(2.00E-03 p (CE-144 . , __ (2.00E-03 2.00E-03
.RAg26 <l 7.00E-03 J_ <i 5.00E-03__. g Tll-228_i <! 7.00E-04I j
[$_5.00E-04 i_ J C-27
7 Fermi 2 - 1997Annux! Radioactive Effluent Release and , Radiological Environmental Operating Report l (] FERMI 2 jV MILK ANALYSIS l' M-2 (Indicator) (pCi/ liter) l l l Nuclide't - - r16-JAN:- ' e t - FEB : e;el4re, uredo-MAR e<w 4 l gl31 J <; 2.00E-01i <i 2.00E-01 l < l.00E-Oll l jSR-89 iSR-90 g<[! _2.00E+00 _ _ _ _ ' . 2.00E+00 1.20E+00 +/- 1.00E-01 1.60E+00 +/- 2.00E-01 _ J< _2.00E+00' _ 9.50E-01 +/- 2.10E-01
~ ~~- ~~~
- [lis~-y 7I~3Td65T0iT" ~ < 'f0d5i61 l ' ~ ~2f i~665i01 R 40 ~7375+6N+MiJd5Td2~ ~ I~1.3IsiO3 A/T 1 1.30E+02 l 1.35E+03d/ _1.30E+02
< MN-54 < 4.00E+00; i <; 4.00E+00 <; 4.00E+00l ~
ICO-58 <I .00E+00i 3
<j 3.00E+00f <f 4.00E+00l IFE-59 < 9.00E+00!- -2I'~8Tdd5i60 ~~2f 8.00E+00' dd~60 < 4.00E+007 <ild6570U < 4.00E+00 ~
ZN-65 < l.00E+01 < 9.00E+00 i
< l.00E+01 ~
2R-95 < ~470T)5idd < 4.00E+00
<J 4.00E+06E +
ROT'63 I <! 4.00E+00 <tT00E+00 < 4.00E+00
~t IRU-106 <! 3.00E+01 <! 3.00E+0ll < 3.00E+01 I~
IC5 l34 ~ <I 10054UU I ggg.7- <!N605sOf 4.0dsiO6E - <i 4.00E+00
~~ ~ <%00E+00 TOUEid6~ ~~
fliA-II0 ~
~23UU5AEUI~ ^ ~~ ~~~' E]~~ ~[21T065iUb ' <l 4.00Ei6U ~~ "6665i6 I IC5 [4I~~2 6.00E+00. < < 7.00E+00 p ~
I 2.065sdif~~- 2'.dd546i-~~
^
CE 144 < < < 3 6dh+01 Q RA-226 < 7.00E+0ll < 7.00E+01 <I 8.00E+01
^ ~
Tii-Y28 < ~365i65' 7 < 30]Eyd{_ 1_< 7.00E+00 l>Nuclider l.mw am17-APRv - al- m x8-MAYcu un l4 NAu22-MAYm;45 I-131 < 2.00E-Oli <1 2.00E-01 2.00E-Olj _ [<< l __ i 5R-89 4.00E+00: 2.00E+00
<l 3.00E+00J "5R 90 1.50E+00.+/- i3.00E-01 F T06EidD!+/-
I 1.00E-01 1.00E+ 00 +/- 2.00E-01 BE-7 77i665s61! ~ T~ i 3.66Ei6fC < 3.00E+0i f-IU~ 1.35E+63f+/- 1.40E+02 1.30E+02 1.26E+03 +/- 1.30E+02 NN-54 < ibb5T 6!~~ ~~
~i~i.~1d5Ad~3f+/- ~ <i 3T06EI6 ; ~ < 3.00E+00 CTO-58 < 3.005iO0E < < 3.00E+00 ~ [ 3.00E+00!
FE-59 < 7.00E+00! < 8.00E+00 < 7.00E+00 U 20 < 3.00E+0 f
< 4.00E+00 < 4.00E+00 Z565 <T 7.00E+00i Af 8.00E+00, < 8.00E+00 I ~ZR-95 < 3.00E+00 00T < 3.00E+00 g o-- -
y-d~3.00E+g - IRU-106 < 3.00E+0li~ <I 3.00E+01 [ < 3.00E+01"
~ - - ~
ICS._134 . . __ . ._ < _3.00 E_+00 ; _ c. . ~ _ _ ' ~_< .'3.005iO6I <! _g ~I _ _ _- .. +l .~2~47_00li6d_4_ _ 7... 7 - ._ ._ _ 4.00E+0,0 L 4._00E+00 p_ jBA-140CSy l3_7_L<1 4.00E+00. _ _.
.{_< ~[ 5.00E+00<j 3.00E+00) <g 5.00E+00]L_ _}_ J _< 4.00E+003 _
fE-141 _1_ } <l 6.00E+00 Nd44 _ 2.00E+0_l{,_j __ j 3.00E+01 <[ 6.00E+00j_J _ _ ___ [2.0_0E+01 p
< 6.00E+01 < 7.00E+01 < 7.00E+01
[RA-226_.._ _ lQ [Tily28 _<[5.00E+00 < _ [ 6.00E+00; <i 6.00E+00 j __ l C-28
i l l Fermi 2- l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report G FERMI 2 V MILK ANALYSIS l M-2 (Indicator) (pCi/ liter) l Nuclide n l- c 12 JUN =: Kl ' 27 JUNr , 2l' ' , n 10-JUL2 cnl l_ 131 <[ 2.00E-0I .I <L ,3.00E-0 lj _
< 2.00E-0Il I , <l 2.00E+00; < < 2.00E+00l (SR-89
_12.00E+00 [SR-90 j~ l.30E+0F+/- 5.00E-01
~
l 9.70E-01 +/- 1.80E-01 1.50E+00!+/- 2.00E-01 BE-7 <l ' 3.00E+01 < 3.00E+01 l-(M0 1[<({l~0TEI0i! lj3Ef,03 _ l.40E+02 j l.32E+03l+/ ij t.30E+02 g l.06E+03 +/ _ . l .10E+02 5.00E+00}+/. MN_54,._3 .. < l. _ _ _ _ _ .. _I <i 4.00E+00; <j ._.3.00E+00 p .____[ . _ . _ . . -
<i I~ <b.00E+00 FE.59 . 1.00E+01 I~ ' .. - .---.- -~2i ~8700EI6d -_7- ~
ZN-65 < <l 9.00E+00l < 8.00E+00 i
._{l.00E+01l IR-9$ l < 5.00E+00! <t 4.00E+00l < 3.00E+00 *iiU-103 < 5.005TOU"~I~~ li 4.00E400' <i, 3.00E+00 RU,106. _ __ j{4;,00p{,j ](_3y@k] , _ _ ,
[3.00E+01 S 134 5.00E+00 < < CS-137 < 5.00E+00; J _ [4.00E+00[ _ 4.00E+00 j
< 4.00E+00 < 5.00E+00j <l 4.00E+00C _
I3A-140 < 3.00E+00
< 8.00E+00 <! 5.00E+00[ _
gCE-141 _ <] 6.00E+00- < 5.00E+00
, CE.I44 < 3.00E+01 <! 2.00E+01 < 2.00E+01
( RA-226 < 9.00E+01[_ <l _7.00E+01_
<j 6.00E+01 TH-228 < 8.00E+00l <j 7.00E+00; <l 5.00E+00 DNuclule else ?.24 JULm "rm-:al t m . e 18-AUG n=cm%lvm*w 28-AUG N2we l < _ <L 2.00E-0lj <
(1-13_l, SR-89 < 2.00E-01[ _ 3.00E+00; < ( < _ 2.00E-01 2.00E+00 SR-90 1.705+T~U'+/- O 3.00E-01 2.00E+00j 8.70E-O ll+
/-1.50E-01 1.30E+00 +/- 2.00E-01 B5-7 < 3.00E+01 fi.dDIf+61C < 3.00E+01 IK-4 0 . ._.-. - .
1.41 E+03
+/ .. 1.40E+02 1.19E+03i+/- ._-
1.20E+02 1.28E+03 +/- 1.30E+02 - _ . _- -._ _ _ _ ~. ~ __ FE-59 < 8.00E+00f < 8.00E+00 < 8.00E+00 60-60 < 4.00E+00l TUUO5i d <, 4.00E+00 4 hN_,65__<, _ <l 9.00E+00j < 9.00E+00 9.00E+00L
< 3.00E+00
_[__ 44.00E+00
< 4.00E+004 4
[ZR-95 , . RU 103 _ [ < 3.00E+004 <L4J0E400; <f 4.00E+00i_ RU-106 < <i 3.00E+01 < 3.00E40l! 3.00E+01 j S-134 < 3.00E+00l - <[ 4.00E+00, < 4.00E+00 CS-137 < < 4.00E+00 j 4.00E+00[ <l 4.00E+00l
- IBA-140 < 4.00E+00j <l 4.00E+00 < 4.00E+00 ICE -141 < 5.00E+00l I 8.00E+00 < 7.00E+00 h5-144 < 2.00E+0l j <f 3.00E+01
~ < < 3.00E+01 f RA-226 i < 7.00E+0l < 9.00E+01 < 8.00E+01 O m12>8 .1 < e.eoe+ee}t <
2.: eve +ee: u 1 >.eoe ee< C-29
i Fermi 2 - 1997Annu:1 Radioactive Effluent Release and Radiological Environmental Operating Report Q FERMI 2 b/ MILK ANALYSIS l
)
M-2 (Indicator) (pCi/ liter) l l=NuclideMl x 211.SEP J e 4 4
- - a25-SEP - r m 4cw e w9 OCTnmce vl ll.I3I _ . i <i 2.00E-Ol! _S_2.00E 01 <! 5.00E-01 1 SR-89 <l 1.00E+00; ~ <l 5.00E-01 4 < 8.00E-01 [__ _ _ I 'SR-90 J 6.10E-01;+/_j2.60E-0l_ [_9ME-0lj+/-j4.00E-01 , 1.303+00=+/ T005-01 l .BE-7 <j 3.00E+0lj i <! 4.00E+0ll i <; 3.00E+01 I K-40 l 1.195~+~63[+/- l1.20E+02_i 1.42E+03 +/- . ! ' l .40E+02 1.37E+03 +/- 1.40E+02 MN-54 .
8
<! . 3.00E+00 - I. <! 4.00E+00: < 3.00E+00: j FE-59 < 8.00E+00 < 6.00E+00 <[ 'l .00E+01 f CO-60 < 4.00E+00; < 5.00E+00 < 3.00E+00 I ZN-65 < 9.00E+00) < l.00E+01 <~ 7.00E+00 ~ ~R-95 < 4.005iO0b~~ < ~ 5.505iUU < 3.00E+00 RU-103 < 4.00E+00 < 5.00E+00; < 3.00E+00 RU-106 }<< 3.00E+01 ~i1055701I ~ - < 3.00E+01 'dS-134 4.00E+00! -~-~T~2 ~5.d6EI66 C 7i 3.00E+00j ~
[
< 5 5.00E+00; .CS-137 4.00E+00; <i 4700E+00i j l IBA-140 < 5.00E+00!
[ 7 5.00$idO! 7 ~ [~I l
~ ~ 4.00E+00 <i~8T6570d ~ ~ ~
dE-141 < [7.UdE+[06[ <f 5.00E+00 p CE-_144_ , ._ f. _3ppE+01{_
< 3.00E+01 _
_j .___ < {2.00E+01 _ Q RA-226 9.00E+01l < 8.00E+01y < 6.00E+01 ill-228 7< , 7.00E+00[ 7_
<t .00E+00 l < 5.00E+00 l
1 l:Nuclided lr 123-OCTm wt W l - r13-NOV E % N l ; , + 11-DEC; .- m1 1131 < < 2.00E-01
. _2.00E-011_( < 3.00E+00; <( 2.00E 0lL_ .
SR-89 j j 3.00E+00g . _7.00E-01
- .SR-90 , 1.30E+00 +/ !6.00E-01 1.50E+00 '+/- 3.00E-01 1.20E+00 +/- 2.00E-0 l_ l l BE-7 < 4.00E+01 <. 4.00E+01 <i 3.00E+01 ;
K-40 1.32E+03 +/- 065+02 l!57E+03 +/- 1.60E+02 1.36E+03 +/- 1.40E+02 l 4
- t. MN-54 < 4.00E+00;. _ _ . ._.. ! 4.00E+00;< < 4.00E+00 i F5-59 3 1.00E+01 < 9.00E+00 < 8.00E+00 CO-60 <j 4.00E+00, _ [ 4.00E+004__
< < 4.00E+00 IN-65 ' <T 9.00E+0_0( <
l .00E+0 ! < 8.00E+ 00 ZR-95 < 4.00E+00; < 4.00E+00 j ~< ~ 4.00E+00 ~ RU 103 < 4.00E+00 < 5.00Ei6 < 4.00E+00 l
~
> RU-106 <j 4.00E+0iII--~ 4.065Idii~~ Y 3.00E+01 I i <l 4.00E+00 I- ~ ~ <I4.005iU0
~
Y 4.065+004 I
,CS-134~_ ~~
IDS-137 p ___ _ 5.00E+06I'_- _ __ ._ ~__~~ -~ <I ~5.00E._I0di~ p j __
~~~I . < 4.00E+00I 4 a f
lBA-140 < 5.00E+00j_ _ <{5.00E+00g _ <j 4.00E+00._ [CE-141 8.00E+00: ._ _{<[ .6.00E+00d_ _i 5.00E+00 <
!CE-144 <4 3.00E+01; _ <! 3.00E+01_ l . <j 2.00E+01 g [RA-22613{,9g0E+ 01 L___ <! 8.00E+0i <[ 7.00E+01 J Ell-228., L<j 8.00E+00 _<! 7.00E+00l <i 6.00E+00 C-30
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Coutrol) (pCi/ liter) l Nuchde s l% - il6JANn' M h l'. m13-FEBr aw. :le ddr 20-MARi&Odbel ll 131 <l 2.00E-Oli <- 2.00E-Oli < 2.00E-01 SR-89 < 2.005~4TO < 2.00E+00 7} 5.00E400 L . SR-90 1.20E+00 +/- _ . _4.00E-01 1.40E+00, +/- 2.00E-01 1.40E+00 +/- 2.00E-01 l BE-7 < 3.00E+01 __
<g 2.00E+01 < 3.00E+01 K-40 1.48E+03 +/- 1.50E+02 l1.49E+03 +/- 1.50E+02 1.40E403 +/- 1.40E+02 MN-54 <[ 4.00E+00; __ <I. 2T06E+00.; ._, .
4.00E+00 [FE-59 ,[L,9.00E+00j <4 5.00E+00gj _
< 8.00E+00 'CO-60 .< 4.00E+00; < 3.00E+00 < 4.00E+00 'IN-65 9.00560) < T60E+00 < 8.00E+00 ~ ~ZR-95 < 4.00E+00$ < 2.00E+00 < 4.00E+00 RU-103 < 4.00E+06" T < 4.00E+00
{l.~00E+00 RU-106 < 4.00E+01 -
< < 3.00E+01 - _ ._2.00 E_+ 01 ,CS-134 -< 4.00E+00 < 2.00E+00j < 4.00E+00 ICS-137 < 4.00E+00 < 2.00E+00' < ~
4.00E+00 BA-140 < 5.00E+00 < 3.00E+00 < 4.00E+00
< 6.00E+00l < 3.00E+00 < 5.00E+00 kE-141 < 3.00E+0lj < l.00E+0i < 2.00E+01 (CE-144 .
RA-226 < 7.00E+0jl < 4.00E+0! < 7.00E+01 l TH 228 < 6.00E+00 < 4.00E+001 3 6.00E+00 l i Nuclide :*mesd4T.APR. mehls em8-MAYe:6S nje&2h 22MAYN%sw]
< < 2.00E-01 < 2.00E-0 I l- _I 131 2.00E-01[
l SR-89 < 4.00E+00l < 2.00E+00 < 2.00E+00
'SR-90 1.30E+0 3.00E-01 7.30E-01 +/- 1.50E-01 8.50E-01 +/- 2.00E-01 BE-7 < 3.00E+0}01; +/- < 3.00E+01 < 3.00E+01 K-40 1.31 E+03]+/- 1.30E+02 1.33E+03 +/- 1.30E+02 1.38E+03 +/- 1.40E+02 MN-54 < 4.00E+00 < 4.00E+00 g. < 3.00E+00 3.00E+00l' ..CO-58 < _ <; 4.00E+00 < 3.00E+00 ~ ~
FE-59 < 8.00E+00 < 1.00E+01 < 7.00E+00 DO-60 < 4.00E+00! < 4.00E+00 < 3.00E+00 b NT
~ < 9.00E+00I~ < "I 06501l < 7.00E+00 < < < 3.00E+00 ZR-95 4.00E+00j RU-103 < 4.00E+00;- < 4.00E+00(
4.00E+00, < 3.00E+00
- ~
RU-106 < 3.00E+01 < 3.00E+01
<I 4.00ET0]1 j
l US-134-CS-137 < 4.00E+00{4 4.00E+001
< 4.00E+00j < 4.00E+00f < 3.00E+00 < 4.00E+00 B A-140 < < 5.00E+00 < 4.00E+00 l' 4.00E+00l _
CE-141 < 7.00E+00! < 8.00L+00 < 5.00E+00 CE-144 < 3.00E+01 .
<} 4.00E+01 < 2.00E+01 '. i RA-226 - <LI.00E+02_ < 6.00E+01 t [TH 228 g<[ -J.00E+0,l_I l 7.00E+00a <lu9.0_0E+00j < _5.00E+00 n
C-31
Fermi 2-l997Annu 1 Radioactive Effluent Release and Radiological En vironmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Control) l (pCi/ liter) l Nuc!kle el4 - - A12-JUN + , , 4 1J zM 27-JUN.xn > Ml.: mwilo JUL+av w
< 2.00E-01i <!
Q-131 2.00E-Oll <[ 2.00E-01j SR-89 < 4.00E+00: <' 4.00E+00 i <f 3.00E+00l ._
'5R-90 5.305sdb +/ I_30E+00 I. [_ { _8,.80E-Ol}+/- 1.90E-01 1.40E+00' +/- 4.00E-01 BE-7 < 3.00E+0ll . <! 3.00E+0ll j <l 2.00E+01 K-40 1.78Ei~3}Il~ I3d5IU2~{ljE[0[i/ :1.30E+02 j 1.41E+03 +/- 1.40E+02_
MN-54 < 4.00E+00 . <j 4.00E+00j
< 4.00E+001 <' 2.00E+00 1 .CO-58 <g 4.00E+00 _ < 2.00E+00 FE 59 < 9.00E+00 < 9.00E+00i < 5.00E+00 r < < 4.00E+00 CO-60 4.00E+00! < 3.00E+00 ZN-65 < l.00E+01 < l.00E+01 < 5.00E+00 ZR-95 < 4.00E+00; < 4.00E+00 < 2.00E+00 IRU-103 < 4.00E+00' < 4.00E+00 < 2.00E+00 ilU-106 < 4.00E+01 < < 2.00E+01 ~{5.00E+01 dS-134 < 5.00E+00: T <' 4.00E+00' < 2.00E+00 CS-137 < 5.00E+00 4.00E+00 < 2.00E+00 BA-140 < < 2.00E+00 ! 4.00E+03 $_513E+00 141 < 6.00E+00: <j 6.00E+00 < 3.00E+00 . CE-g 144 O < 3.00E+01 <' < l .00E+01 V ~ 4[2.00E+01< 7.D0 E 4.00E+01 I 6["~ ~
RA-226 < 8.00ET6i- < TH-228 < 7.00E+00; <[ 6.00E+00, < 4.00E+00 l'Nuclklerlm a w 24-JUL*./ e%. tl: - .a ,14-AUGs vW rim wtd8 AUGN wwMl [I-131 _ 2.00E-0l}_ _l.00E-01[ <[ 4.00E-01l
< 2.00E+00 < 2.00E+00
[SR-89 SR-90 . 1.80E+00 3.00E+00j+/- 3.00E-01 5.70E-01 +/- 2.10E-01 1.10E+00 +/- 2.00E-01 BE-7 < 3.00E+01 < 3.00E+01 < 3.00E+01 J K-40 1.37E+03 +/- 1.40E+02 . 1.27E+03 1.26E+03 +/- 1.30E+02
+/- {l.30E+02 MN-54 < 3.00E+00 1 . <1 3.00E+00 < 4.00E+00 <l 3.0DE+00 <
_CO-58 13.00E+00l 3.00E_+00 FE 59 < 8.00E+00l < 7.00E+004 < 9.00E+00' C -60 < 4.00E+00 < 3.00E+00) < 4.00E+00' ZN-65 q,, 9.00E+6d, < ' 6.00E+007 < 8.00E+00 ZR-95 < 3.00E+00; < 3.00E+00! < 4.00E+00 RU-103 RU-106
<, 4.00E+00 I_ ~{[<i 3.00E+01 f.0UE[+Udl < 4.00E+00 < 3.00E+01 <1 3.00E+0l t < 4.00E+0 i : 5~-T34 . TIUUEi6Uf__-_ . _ _ <j 3.00E+00-t CE-141 < < 8.00E+00 - -- 6.00E+00l-. ~ - - <l 5.00E+00' . I7.-
it -226 <TUU5idlT~
<! 7.00E+01 < 9.00E+01 ~
T[
< 7.005 iud q Y66E700
[hl-228 _ [_< E065T06[ C-32
Fermi 2- l997Annux! Radioactive Effluent Release and l Radiological Environmental Operating Report O FERMI 2 MILK ANALYSIS M-8 (Control) (pCi/ liter) l Nucikle5lT- . W &11-SEP rF :19l. 425-SEP A *
%~ TN9 0CT4sr wl !
l-131 <! 2.00E-0!! t 2.00E-Oll i
<L 4.00E-01 SR-89 SR-90
_j_1.00E+00 _ <$(2.00E+00J _t <[_3.00E+00 1.10E+00f+/- 3.00E-01_ _ _ 1.10E+00 +/- 4.00E-01 7.40E-01 +/- 2.00E-01 BE-7 < < 3.00E+01 < 3.00E+01 3.00E+01{~ ^~ ~ K-40 1.42E+031+/- I4Uhi0i _1.23Ej03[T/[1.20E+02 1.32E+03 +/- 1.30E+02
<i 3.00E+00; < 3.00E+00 < 3.00E+00 iMN-54 _
- CO-58 _ _b3.00E+00 <
__L<[3.00E+00 < 3.00E+00 l IFE-59 <{7.00E+00 < 8.00E+00
<L8.00E+004 _
0-60 < 4.00E+00' l < 4.00E+00 l < 3.00E+00 IZN-65 < 7.00E+00! i < 8.00E+00, _ ~~~! < 8.00E+00
< 3.00E+00M TiUO576di IR IRU-103 ~ < 3.00E+00 d- Y fU65iddb
[<< 3.00E+00 4.00E+00 RU-106 < 3.00E+01 < 3.00E+01 < 3.00E+01 CS-134 -< 3.00E+00j < 3.00E+00 < 4.00E+00 CS-137 < 3.00E+00I < 4.00E+00 < 4.00E+00 BA-140 < 4.00E+0N0 < 4.00E+00,4 < 4.00E+00
< 6.00E+00 < < 5.00E+00
[C}E-141 _ 6.00E+00[ p( CE.144 RA 226
< 2.00E+01 < 7.00E+01 < 3.00E+01 < 7.00E+01 2.00E+01 7.00E+01 TH-228 < 6.00E+00! <[~73d5+00y < 6.00E+00 Nuotido nlcMh 23 0CT M& ele + s + 13-NOVewaylw wind 1 DECWsMif, 1-131 <-
2.00E-Olj < ~ 2.00E-01 < 2.00E-01 SR-89 < 2.00E+00' < 2.00E+00 < 2.00E+00
~
SR-90 2.50E+00 +/- 5.00E-01 1.105IU +/- 4.00E-01 3.30E+00 +/- 4.00E-01 BE-7 < 3.00E+01 < 2.00E+01 -
< 2.00E+01
! K-40 1.33E+03 +/- 1.30E+02 1.47E+03 I/- 1.50E+02 1.47E+03 +/- 1.50E+02 51N-54 < 3.00Ei60
~{iF0}si60 <j 3.00E+00
- CO-58 < 3.00E+00 _, <p 3.00E+004 <' 2.00E+00 ,
< } <
3-59 7.00E+00l <} 6.00E+001 6.00E+00 l [ 30-60 < 4.00E+00 l < _j 3.00E+0j0 < 3.00E+00 l ZN-65 < 8.00E+00 < < 6.00E+00 _ [7.00E+00l _ ZR 95 < 3.00E+00 3.00E+00 l 3 J_3.00E+001 5 RU-103 < 3.00E+00 l <[ 3.00E+00! <{ 3.00E+00t RU-106 < 3.00E+01 < 2.00E+01 l <[ 2.00E+01 CS-134 < 4.00E+00, <l 3.00E+00 < 3.00E+00 CS-137 < 4.00E+00' < 3.00E+00 < 3.00E+00 BA-140 < 4.00E+00I <T U0E+00 < 3.00E+00 _CE-141
< 6.00E+00! <300E+00 < 4.00E+00 1CE-144 < 3.00E+01 < 2.00E+01 < 2.00E+01 p IRA-226 <l 8.00E+01 <i 5.00E+01 < 5.00E+01 j 7.00E+00[
[Tif-228 _
<j 5.005i D < 4.00E+00; i
C-33 I C______._._____ a
Fermi 2 - l997 Annual Radioacthe Effluent Release and Radiological Environmental Operating Report 3 FERMI 2 (V VEGETABLE ANALYSIS FP-1 (Indicator) (pCi/kg wet) l Nuclide < [1 + v24-JUL Cabbage 4 - -l- > 24-JUL Lettuce wel ~ e24-JUL Broccoliw+4l i 1-131 <j 1.00E+01; l <; 1.00E+0l} < l .00E+01 555~-~7 ~ I 1.37E+02!+/- I.40E+01 6 2.53 E+02 '+/- 7.50E+01 1.49E+02 +/- 6.50E+01 K20 ~
~I56Ei03I i/d3.00E+02 4.36E+03;+/ <4.40E+02 3.21 E+03 +/- 3.20E+02 Mf5f~~i]~<i CO-58 < 9.00E+00' l!0UEidi! ~T~(((_[00EIUl[] <: 1.00E+01; 1 <l 9.00Eiddf <i 8.00E+001 ~~
LF g-59 _ _$_ 2.0pE+01[,_, _.__,[]((2,.00E+0IL _ .
))<[2.00E+01 < _ l .00E+0 l } <l 1.00E+01 < 9.00E+00
[CO-60 iZN-65 _<j 2.00E+01l <j 2.00E401 _
< 2.00E+01 Z
I~R-95 < l.00E+01 < < 9.00E+00 __ _ _l.00E+01 IRU-103 < l .00E+01 j 1.00E+01 < 9.00E+00
<l 9.00E+01 < 8.00E+01 fRU-106 _ _ _ $_9.00E+01
[CS-134 I_A}1.00E+01 _ [l.00E+0l[ _ _
. _ { 9.00E+00 CS-137 <{l.00E+01 <l 1.00E+01 - <' 9.00E+00 BA-140 < l .00E+01 <} 1.00E+01 Q <[ild0E+01 .
CE-141 < _jl.00E+0li < l .00E+01
<{ 2.00E+01 __
CE-144 <! 6.00E+0ll <i 7.00E+01 < 6.00E+01 l
.RA_-226 <l 2.00E+02 .<l 2id5T62 7 2.00E+02 {
L _ _ <! _2.00E+0l{f [TH,-2_28_ _<{ 2.00E+01 _ { < 2.00E+0 t l V , l FP-1 (Indicator) (pCi/kg wet) l.Nuclide w lu , J 28-AUG) Cabbagem /ln ' 28-AUG Swiss Chard %Nl m m 23-AUG LettuceWW Jl 1 ff.131 l .00E+0 t i _ _l00E 0I L i_
< _2_.,00E+0 lj l j (BE-7 1.40E+02l+/- 5.40E+01 2.16E+02i+/- 6.90E+01 ~
3.25E+02 +/- l8.30E+01
!K-40 I~ 2.73E+03!+/- [2'.3dEiO2~ 5.295Ad3 4.48E+03 +/- '4.50E+02~
fMN 54 CO-58
<I 9.00Ei6U[~] <! 9.00E+00'
[9.0 ET00{f/-}[5.30E+02
<L l_.00E+01 ~2} 1.00576l" < l.00E+01 FE-59 <j 2.00E+01 g2.00E+01 < 2.00E+01 CO-60 <; 1.00E+01 < l.00E+01
_ <( 9.00E+00 ZN-65 < 2.00E+01 < 2.00E+01 <l 2.00E+01 ZR-95 < l.005i0l'[ 2~lld65+01
<]1.00E+01 g RU-103 < l .00E+01 <
1.00E+01 ,
<3 1 00E401
{ RU- 106_ _ _ _g _8.00E_+01 CS-134 9.00E+0 I. _ . g <] 9.00E+0I g <[1.00E+01 ,1.00E+01 <j 1.00E+01 lCS-137 <j1.00E+01 < l .00E+01 j (BA-140J~<[!1.00E+01
< 1.005+Tdi~ ~~ - ~ ~ 2' l.00E+0ll F~ < l.00E+01 ~ ~j ~Y 2 dOEiUIIY ~Y2~2T0 ETA 1 ~
- ;CE! iii-li 1.00E+01 . (CE-144 ] < 6.00E+01 f <(6.00E+01{_j .
<(6.00E+01 < 2.00E+02! <! 2.00E+02i i < 2.00E+02 - [RA-226 7 270Ei0l!-
[TH-228 32.00E+0l[_[ < 2.00E+01 l l C-34 L______--------------_------__- - - - - - - - - - _ - - - . - - _ - - - - - - - -
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 VEGETABLE ANALYSIS FP-3 (Indicator) (pCi/kg wet) l Nuclide r . l - 24-JUL' Cabbage - 4 . 24-JUL Collard Greens , ds 28-AUG Cabbage a rl 1 <; 1.00E+0 l i <, <l
!.!-131 - . . . . _1.00E+0 l l i .-- .--2.00E+0ll .
_K.40 l _.l _ 2.22E+0 _ __ _ 3!+/ _ _2.20E._+02 . . _ _ 2.99E+03l+/- 3.00E+02 1.49E+03l+/- 1.50E+02
*- ~
i MN-54 l <i 1.00E+01. __ _..T < 7.00E+00l l <! 9.00E+0i0"~~~j
;CO-5_8_ {<[1.00E+0l_j __ ___ { !<6.00E+00j
{ <!_1.00E+0 (_ TE-59 i
<f 2.00E+01l .
I <; 2.00E+0ll ~~ ~~ ~ i <! 2.00E+0l j
$"<fI.dO5+0'lE T ~
[CO-60 ' I < 7.00E+00' , i dei.605Adi f 7 ~ ~ l IZNT 65 ~I"T~270Us+0l! ! <. 2.00E+0l! , , <. 2.00E+0ll T ~! IZli-95 I<f 7 '75 Eid0" I i <; 1.00E+01 i fROT df[<f ~T.d05idil~ ~ I~ ~ ~~
~
i ildd5iUil '[~~~ <}1.00E+01 I '- <! 7.0dE+00[
<I6 0Ei0ii~ I- ~ [- ~ ~{~2i 5.UUh+01 ~ ~ ~ ~ ~
(fiU-106 <T T UdsiU2 ~ l
.CS-I3T~~2 T.UUEid~l' ~ '~ <~ I7.dOETO0 - -
F CSl57 YlUU5idi~ 2 8505IDU
<[T.UU5fdl ~ ^ ~- <l 1.00E+01 BA-140 <!l.00E+01[~- ~<! '.~ 8.0dE+00"_~~ _ - --- . . .- ~-. - <i 1.00E+01 . - <; 4.00E+01 ! ! <I 7.00E+01 (CE;lj4 jRA-226 __$[_p.00E+0!(( <l 2.00E+02 <! 1.00E+02; I <i 2.00E+02 j
[Ti{25 . [ 2'.UD5Adl { {4~~ j ~ <! 1.dO5+0l[~~ I ~ (( ~<Q055761_ _))_, j TP-3 (Indicator) (pCi/kg wet)
;Nuclidenln 228-AUG Lettuce l AUG Collard Greens -
1-131 ! <! 1.00E+01' i < 9.00E+00! 55-7 l1 4.135i02 i7-~' #65DEAUI~}~ [l 2.19E+02f+l~~ 4.30E+01~ NA.0 . j , _2.8lE+03(+/- 12.80E+02 .
. _ l 2.64 E+03[+/ _ 2.60E+02_
MN-54 l < 9.00E+00j i <j 6.00E+00 C658~ T E;~8505idU ^
~ ~~ ~ ~ ~ ~
i T T UE+6d fi5-5F f T<I2.d~0Ei0lI
~~~ ~ ~
T1 Y 'I.00'556I [ ICO-60 ~I <! 8.00E+00: ~
<; 6.00E+00 I ~i ~< I5 Eidl(( ~ ~~
IZN-65 l <I~2.0dE+Ui! ZI65
. _._ _5~ IY ~9.ddE+U .I.._.- _._._ ._ . _ __.._m_. ,i .
_'_.',I <i'7555 _AdDI _ -~-~__
; ___ ~ _
RU-1,03__;__5L9.00E+00Lj _ _y i 6.00E+00 _ RU..106 . -' <j .8.00E+01{_ - i
! <i 5.00E+0ll- ~
hSl37 ']pUU5i6U
~
BA-140
~[ ][~(005idU { ~
l_$[1.00E+01 _ ___{<{ 8.00E+00j (CE-141
; [< ;CEg441<j 1.00E+0iLj t5.00E+0il _. _
_l _____, _ t L<}_8.0_0E+00;
<t3_.00E+0i n __
(RA-226_! <j_2g0E+02 C< _ J <[1.00E+02 Li.00E+0iL n, _ _ _ Tit 228 _ [ <L2.00E+0i(t _. . L _ O C-35
Fermi 2- 1997 Annual Radioactive Effluent Relea.se and Radiological Environmental Operating Report (] V-FERMI 2 VEGETABLE ANALYSIS FP-7 (Indicator) (pCi/kg wet) Nuclide n l ~ 124-JUl< Swiss Chard - j. e . 24-JUL : Lettuce t >
'l4 24-JUL Collard Greens v l
( 13I ,_j <j l.00E+01: [._ _jj 5.00E+00 1
< 7.00E+00; . B E-7 - . - --.! 167E402 +/ '6.40E+01 . ! 2.29E+02;+/ i3.50E+01 1.51E+02 +/- 4.20E+01_ 1
[hiN-54 j_<L.00E+00 9 __ j _ j _< 5.00E_+00g ! < 5.00E+00
'CO-58 <l 9.00E+00! < 5.00E+00 4
IFE-59 < 2.00E+01
<L4.00E+00] __ << l.00E+01t l <! 1.00E+01 l ICO-60 < 9.00E+00, < 5.00E+00 M~
Q' 6.00E+00 b-65 < _2.00E+01] ~~21]i.6,0]ET0(( < l.00E+01 ZR-95 < 9.00E+00l <[5.00E+00j < 5.00E+00 RU-103 < l.00E+0lj < < 6.00E+00
~1 4.00E+00l RTJ-106 < < 4.00E+0l j < 5.00E+01 8.00E+0l} "
CS-134 7 <,1.00E+0ll <; 5.00E+00, < 6.00E+00 4 ICS-137 < l.00E+0ll <l 5.00E+00 <i 6.00E+00 BA-140 < _l .00E+01 ._
<l 5.00E+00 3 6.00E+00 CE-141 < 2.00E+01 <l 6.00E+00) <' l .00E+01 CE-144 < 6.00E+01 < T < 4.00E+01 RA 226 < 2.00E+02! ~~ ~ < [j 9.UdE+01 3.00E+01 1 < l.00E+02 TH-228 < l.00E+01 l <[ 2.00E+0[ <l 9.00E+00[-
V FP-7 (Indicator) l (pCi/Kg wet) ' l-Nuclide La l; z28-AUG Cabbage? v l ' '~28-AUG Swiss Chard @ l W 28-AUG iCollard Greens"
< 1.00E+01 l.00E+01 (I"I_3_I_.
_ _ f _1.00E+0ll _ _ _ _ _< jBE-7 _.. 1.06E+02'+/- -4.50E+01 1.09E+02[+/- 5.40E+01 2.27E+02 +/- 4.80E+01_ 3-40 l.89E403f+/-l_.90E+02 . _j_l.95E+03'+/ !2.0JE+02 2.25E+03 +/- 2.30E+02 MN-54 _
< 6.00E+00 . <l 7.00E+00! _j__ [_< 6.00E+00 iCO-58 < 6.00E+00 <l 7.00E+00 < 6.00E+00 < l .00E+01 <l 2.00E+01 < l.00E+01 fFE-59 CO-60 < < 7.00E+00 6.00E+00, <h00E+00, ZN-65 < l.00E+01l <l 2.00E+0l[ < l.00E+01 IZR-95 < 6.00E+00 < < 6.00E+00
_ [7.00E+00{ RU-103 < 7.00E+00
< _7.00E+00j <{ 7.00E+00 j
RU-106 5.00E+01[_ 5.00E+01 p CS-134 _< 6.00E+0IL < i <{7.00E+00 <! 8.00E+00g I 6.00E+00 iCS-137 <l 7.00E+00 <j 7.00E+00
<i 7.00E+00L _{
BA-140 < 8.00E+00; <! 9.00E+00 i <i 8.00E+00 CE-141 < l .00E+01 < l.00E+01 < 3 rCE-144 <. < 4.00E+01 9.00E+00]
< 3.00E+01 ~
h26 <(5.00E+01I~d~0E[+)) l.001502[~ < l.00E+02 [TH-228 <j 1.00E+01. [ {l 100E40l[
< l.00E+01 O
C-36
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 O' VEGETABLE ANALYSIS l FP-9 (Control) (pCi/kg wet) l Nuclide ; l . ^ 24-JULL Swiss Chard ' - -l . 24 JUL Lettuce " - l- 0 24-JUL Cabbage '
;l 'I-131 <! 8.00E+00 ; 8.00E+00, '
I <t 1.00E+01 {_<' .
~ ~
IK-40 l ~i 525EIO3II/-]5.35i02 i '4.89hT03is/~ !43U5i62 ~d.758IU5I IdT865id2 ~ lMN-54 ! q 7.00E+00. i
~~ <1 6.00E+00"~~T- - 7i~i66tT0i L 1
{C<I'6. UE+[~ T 7~2[1.00E+0lf
~ ~
TCOJ8~~~ I~ di~~776U5i6U I fpE 39~~~T~ii
~
50Ei61I~ T - ~ 7 El.0 dei 0lf I 7 ~2I'lU65T6ii fCO-60~ ~i T iOUE+00' ~ i [ ~ <. 7.00E+00' b ~ ~i ~di ~i.~UdEidi i - ~I~"-
!ZN-U D ~<I 2.00E+0ll i ! <! 2.00E+0l! [ T E! ~2.00EiUI [ ~- l 'IR55 [~ <[~7706570 I l ' ~ ' ~ ~i~ <! 7'.0dE+06^ ~
l~~~~ l ~ii~I.UU576if[~ - ~~
'~"
RU-103 ~I~2I ~7.66E+0 i~ di 6'.00E+00 [RU-106 l ~ ?UO5iU1[~ ^ [ ~ ~~ I~[~II 7
~~I6:00EidI - - [{j 9.00E+0I ~ <<{l!6dh+0)j !CS-134 < < ! <! 1.00E+01
__% _ . L' 6.00_E+00.! _. fg_S-137__-_8.00E+00. _._.t.
< 9.00E+ 00, < < 7.00E+00! <L7.00E+00{ _ _ _j l.00E+01 ! !BA-140 <; 7.00E+00! < l.00E+01 j C5-lil ]. [ '. [<j 8.00Ej00{ ))]<[_1.605IU[{j ~~ <].00E+i
[CE-144<[5.00E+01l 9 4.00E+01l I < {_~ RA-226 <! 1.00E+02; I <j l6.00E+0I 2.00E+02
~ - - - - + -- - ---- - - <IlidO5iO[I- -4'~ -- - l ---
r lf-228_ (T ----- - -- _. "[1.00E+01l <: 1.00E+01j _ .__"L <; 2.00E+01 i , FP-9 (Control) (pCi/kg wet) l Nuclide : .l2 m28-AUG Cabbage. :l AUG Swiss Chard / d ' 28-AUO: Lettuces d
'l-131 {~<i 1.00E+01; < l .00E+01 < l .00E+01 B5-7 j Ef 8.00E+0!! 2.28E+02 +/- 6.00E+01 4.02E+02 +/- 5.90E+0i K-40 l T 1.87E +031+/- 1.90E+02 4.17E+03!+/- 4.20E+02 4.37E+03 +/- 4.40E+02 7 <1 8.00E+00' ~
iMN-54 ~ ~ ~ ~
< 8.00E+66 < 8.0UE+00 ~~ I 7.00sT00I ~ !CO58~ EI8.6U5+60 _ . . - ~2I"T.UUEAUU _. ~ ~
CO-60 1 <Y9.I)0EI6UN ~YY ~ 9.005i60
~
Ti[8TOU5I6 IS-65 [~Y~2IU0E+01i _ _ i _ <I 2.00E+01 i _ . i _ _ _i<l 2.00E+0 l _+ . .
<j1.00E+0i[~~[~~~ ~
IRU-103 ~ ~ 2i'9'.065 idO I T ~ ~ 'i[~L 60EiUUI 1
$UTl06 i <; 8.00E+01l <
l l <[ ~7.00E+0ll ^-
< 9'.0dEIO0I 7.00E+01 I (C5 i54--~ 9.00E+00' l < 8.00E+00 Y" E{l lI00E+ 1I~l <l~~9[~~ ~
tS- ~ . Oli60 f~ ~ i I'BA i3t~'~ ~I- ~ CE-141 IT6 I~M l.0d5T6iI I~' ~2II.605AUI
<i 1.00E+01 ~~T[i ~1605iUU) <F956EIUU' <i 1.00E+01! l l {<'l.00E+01 ICE-144 - - 5.00E+0lf ..- - - . . _ _ _ _ . . <i 5.00E+01 ..}T4.UUhid!
l
.__. ________..m m _ __ .a._.___ m p 228_ _ . __ r. _ .__..~. _!_ . ___ _ < ! ___ _ 1 _<j l.00E+0l A_l.00E+011 __, ' l.00E+01[ l l C-37
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report O DRINKING WATER ANALYSIS FERMI 2 DW-1 (Indicator) (pCi/ liter) l Nuclides l.
;GR B 27-JAN . -l 2.70E+00.+.
24-FE3
- ;l.10E+00 i l MAR . R i 3.30E+00 +/- i t.10E+00 } '
i 5.50E+00:+/- i t.10E+00 ,
!SR-89~ F kI 2.00E+00' ~
i ~'~ I <i 2.00E+00! I ~ AI2. dEidO I 7 ~!
~I~ ~ ~Tii 8.U~ E 0 0i l ~ ~
iSR 90 l ~~2I ~ 930E-Ul[~ I ' ~ ~~I [BE-7 '~~ ~
~
EI~i'0'05I0ii I ~f~ <!I k 3.00EA0l[9.00E-Oli [ ~~T~d[3 OEidl
~
i [Ky0] ~ ~ [E 5.UO5jUl{ (( ~Ef ~ 6.0 E+01 SidO5ioi (([]
;CR-51 ~ <, 3.00E+0li <! 3.00E+01; i <j 3.00E+01 l ~
IN 5'd] )) 2{3 00E+0Uy__ _ go-58__ _13
!FE-59 ].U0i5dd]((((
00E+00
<l 6.00E+00
__ [ <{<i [3.0d5@d
<l 3.00E+00 7.00E+00 <j 3.00E+00g_[__ ~ ~
1 l <j 6.00E+00j IC -60 ~d[ 3.005iUdI~~ -~ i~<IOU 5IUU! l <j 3.00E+00l IIN-65 <! 7.00E+00: ~2iTU0E+00T } < ~ 6.00E+00l l
!ZR 95 i < 3.00E+00 <; 3.00E+00, < 3.00E+00l '~~~ ~~]
[RU iUf T<j 10dE+6U [ ~ l~ ~ ~
<! 3.00E+0vP i{ ~ ~ ~ T 4.UU5iUUF ~ ~ ~ ~~
j RU-106 I <i 3.00E+ 0ll i ~TA! ~ 3 UUEihi!~~ Ei~1UUhlbi-- I CS 134 EI 3.00E+00. <j 3.00E+00; 2"lD0E+00
~
T
~~ ~ ~ ~ ~
2 dF0EAUd[
- ' ~~'
CS-I37 <Id.00E+00I'~ < ~3 d0ETUU~~
~ -
BA-140 <1 4.00E+00' ~' ~ ~
' <l '5.0UEiOO' ~~ ~ ~ - ~ < ~16UEIUU l
CE 141 < 5.00E+00E ~ 'EI 7.'005iU0 ~ 6 ICE 144
<! < 3.00E+0l! '[ ]~655+00 <! 3.00E+01 2.00E+01}I ~ ~ ~ ~
f
,RA-226- -< .7.00E+0 .. - [. -.- l 4_ g _- -- _<[ 8.0'0E+0l! _
l <; 7.00E+01 ITil-228l <[ _7.00E+00 _ _ 1_. _ j_< 7.00E+00, _ J __ . <{6.00E+00 _ _ C__ l:Nuclide ab m e 28-APR - .- -l ~ 27-MAY - 1w . 4 25-JUN 3 4 <
'l
[GR B _ . _ [ 2.70E+00 +/ _ j9.00E-01 4 j . _(a) _ !
! l 3.60E+00 +/- 1.00E+00j iSR-89 .- . <j.-.2.00E+00 i .i<, 1.00E+00 {_ _i <l 2.00E+00 t ~" - ~
BE-7 ~_<I.. , 2.00E+01 _. . - _1 . _ . _ .
<1 3.00E+01 l L -40_ _ _7.00E+0_l{
K < _ __. [_3_.00E+01 _ _ _ _ <L4.00E+0ll i __ _
<j 5.00E+01 .
[ yR;51__ _ _ _ <[3.00E+01{ _ ___ _ <j 2.00E+0l[ _ ___ ._<[3.00E 01._ _ _ _ MN-54 . <j 3.00E+00(n_,_] <; _3.00E+00
< 3.00E+00
- CO-58 <! 3.00E+00' I <i 3.00E+00 < 3.00E+00 IFE-59
~5655iUU 6 ~ }~ <f~l65ETU6 < 7.00E+00 rCO-60 u __ 7 I i~005_%_3_ . . . 0 . ..6 7u.- _~ ~ ._;___ <i 3 OdEAUU
_ 4 _l
< 4.00E+00 7N_-65_, _<[ [_ 7,.00E+00 i <, 7.00E+00_ {_ _,
_ <! _6.00E+00 _ _. __ _ , _ _ _ . i <. i 3.00E+00 ..._.g '. <i 3_.00E+00 1 l l _ . __ .7.. ZR .95_._L' (( .3_.00E+00_. RIJ-103_ _ < 3.00E+00 <[ 3.00E+00 <[ 4.00E+00; _ ~_ . _ _ , _ _ _ j RU-106 < 3.00E+0l! <t 3.00E+01 ! <l 3.00E+01 ]l
- -- T<! -_ a 3.00E+00 Ii ~1005A00F ~ ~ < 5U0Ei60' - ~ .CS 13d'~Q<L3.00E+00; .- .- - -.a..-._ .- - _ . . - w. -[_ .~~~-+- t <i 3.00E+00
[CS-137
< 3.00E+00l <l 4.00E+ 00;
_L__J <[ 3 00E+00L _( [BA-140 l ! ! <! 5.00E+00 l ! CE-141
.CE-144 _ <j _5.00E+00; <i 2.00E+0!l J___ <L4.00E+00; <i 2.00E+01i I
j ( <{8.00E+00; j <i 3.00E+01 i O l ~
'RA-226 < 6.00E+0l! <I 6.00E+0li l < 9.00E+01 I
[Til-228[ [k[ "5.00E+U0((] ~ ~ ~ ' kf 5.00E+00l _ l~ ~ ~ ~ ][2[l ~~7.665+U6) 1
~
(a) S:r: Appendix D - Program Execution. C-38
1 Fermi 2- l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FEIG1I 2 DRINKING WATER ANALYSIS DW-1 (Indicator) (pCi/ liter) l Nuclide l , 28 JUL- . l --- 25-AUG . l' J23-SEP' , l G R.B l 3.00E+00.+/- 19.00E-01 1 3.10E+00:+/ i9.00E-01
~
(~l.90h+00 +/ '9.00E-01 { ~~- ~
'El 1065i 0i 7 '~~ .ISR-89 <! 1.00E+00 <! 305i66 ~
ISR-90 <l 7.00E-Oli ~l <1 7.00E-Oll <I1.00E+0 IB5-'7 ~di~lbd571j i <! 5005~+ 61i l <l 3.00E+01 M.o'.~_.'a.7 p._.. i f$00ET0ii. '._~~ -~
~ ~ <I.5.UUEidlI'~. _. .'_'~ _ "T.. _ . _lUdE_+01 i
3
.___.4 . . _. . .- .l _ .
yR-51 l < 3.00E40ll n ! <; 3.00E+0l! < 3.00E+01 f___
;MN-54 'CO-58 j <; 3.00E+00,. < <; 3.00E+00 i
i
<j 3.00E+00, <: 3.00E+00, j___ [<[<t[3.00E_+00L_ _ __
I 3.00E+00l 7I 6.D05+ d' I
<! 6.00E+00' i ~~ l FE-59' ~ "i dI~3 00E+0dfN ~3.00EidOI 'l ~ ~'~' 'CO 60T~-' . }~7iT.6ssiU6<[
j
~T - 6.dOEIO0Ei 1 i <l 7 UU5iddi~~T-
[ N-65 <! ' TU0E40dl ~ ! ~ I li'100E+00! i l f~
~~ ~
ZR-95 i ~~<T3T06Ei60I <l ~ 3.00E+00 ~ ~ ~ ~ ~ ii~3.db5iUU ~~
.liU-iU3 ~ i 2i~iUU5+00 - -. - . . - . - . - . . - . <i 4.00E+d0 ~~ ~~ ~3.60E Od T~ ~
d5J34 .<i 3.00E+dif ~2i ~3 665IUUi~ ~ <i 3.00E+00 l 3 {, ] $ 3 6 5f06[' [ [J.005A0 _ [ ][ [ ]I 4.00E+00 __ _ _ _ l
<L4.00E+00, _ <. 4.00E+00 (BA _i40_ . _ _
CE-141 <! 6.00E+00;
. [ 4.00E+00 _ [ ___ ~ <! 7.00E+00' ! <! 5.00E+00 Ids-144 l <! 2.00E+0l! <E 3.0dEiUlil <j 2.00E+01 i !
[R -556~~ !~iI~f065+0lI"~ M 8T]~~ 06ET0l[ l <j 6.00E F01 i [Tl5228'^al' Ai~5.~0U540dC [_ <l 7.'005+00 I _ ~_t_J
~ ~i 500EIU [~ 1 J
l Nuclide ; :l 3 'n 30 SEP - l 27-OCTm . wl1 - < M4-NOV4 , a 'l , 3 G R-B ~~ l 2.10E+00,+/- 19.00E-01--- 2.60E+00j+/- 8.00E-01 > 2.20E+00 +/- 8.00E-01
$R-86~ ~~ < TUdfiUUi 7 2.UU5Iddl < 2.00E+00 Sii~-90 < 2.00EiUUF~l <j l.00E+00: < l.00E400 iBE-7 5.00E+0ll i <i 3.00E+01 T-40~ -[ ! <{~'2TdO5702I <4 ~~ ~ <i~ 2Tdd576if~~I ~ <IS00Ei6il 3 5.00E+01 Cli~-5I~ ~Af5.0 EIUII ~i ~' <i 3.60Es0l! ~ T~~ i'~ <l 3.00E+01 M S-T4 R ~ 7 5665i66 7 ~i-_. - ___.~~7i ~ 2.0 DEI 60I. 'l- [' <l 3.00E+001 ; ~ ~~
FE-59 <; 5.'00E+0D5 ~
- . - li~Ild65i0l[ " i~- . - . . . . - . " - . - - . - -~ ~I '2! '.73dE+U0 ~ ~ - ~
Nd5 '~ #2Ii!00EA01 ~
~~ ~ ' <i 5.00E+00 <i ~~670 5760 t IZR-95 <! 5.00E 500 <! 3.00E+00' <j 3.00E+00' f@U-106 ;R I.03 _ ,_] <l 5.00E+0lf { @(p })) [3.D05A0Uf <i 1 60I: OU T- ~ 2.00E+0l[ <! 3.00E+01
[C5'IN l~~~d[ X6U576UQ 7 ~2I~3.0 E460L <{ 3.00E+00 g
<i 6.00E+00 .CS-137 --- . .. - - - <! 3.00E4 00;-- <l 4.00E+00, --1 - ~~
DE-l41
~ !' ~di 9.605+60I ~ i" di 5.'Od850Di 7.UU5iU0i ~ ~~~ ~ 7~~~ < ~.~ ~ 'i ~<{C3 UUEidi ~ ~ - ~ ~ ~ ~ ~
fCE-144~ ~ l <i'1005A01'~ ~
~ ~~'I <I ' 2.00E+DU ~
I7!l.0DE+02T
~~
- RA-226 i <l 7.0dE+ 1
~~
l ~ ~ ~ 7 <[ K005idi~ 5kk_ 9 00E+Uf . 6.'h0Efo { [ ] [} ~16.00E+001 _ _ C-39
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-1 (Indicator) (pCi/ liter) l Nuclide [ 24-DEC .] G R-B ; . 3.00E+00 +/- ;1.00E+00 i
~
ISR-89~ f ' <! '2.' dei 0 ' i i iSR-9d ~ ~l <i 6'00E-Oli . i~ ~ ~l
'B E-7~~ I <I ~2.00E+0i! T K-40 I <. 4.00E+0l! '
I ICR-51' < 2. DOE +Ull i
~ ~ '~~'
MN'-5F ~l ~ ~ <I 2.00Eid * ~
~ ~ ~j
[CO!58 '! ~ <i 2.005+00! [ ' [E-59 <i4.00E+00y "~~~~
;CO-60 < 3.00E+00- !ZN-65 <, 4.00E+00I-~^l ~ ~ ~ ~ ~ -
IZifl)5~~* <I2.00EiOO! ~~ [RU2103 ' <! 3.00E+00I ^I I RU-Id6- <I ~2.60EAdlb ~[~~ ~~~
~
Ds.T3T~
~ <~ ! ~ 2.00E A~ 00' ~ ' i ~~~-~~ !CS-l3'7 <I 3.00E+00 'I ~~
[Bh-14 ' ~ ~ <I 3. DOE + 0'~ ~ IC5-141 ~i Id65idd
^ ;CE-144 < 2.00E+01 ~ ~~ - ~ ~ ~
IRA-22i~ '~<I l~dE+di' [Tijd28]<I5.00Ey0dl _
~'~ ~ ]
C-40
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report l FERMI 2 DRINKING WATER ANALYSIS DW-2 (Control) (pCi/ liter) l Nuclide . l- 27-JAN 24-FEB . -lH > J31-MAR" - l
;GR-B ~' i ( 2.20E+00 +/- 1.00E+00 ~~ ~ ~ ~ 'l' , 2.40E+00 +/- l1.00E+00 1 4.80E+00 +/- 1.00E+00 i ~3 50s70D'--~ ~
ISR-89 ~<I' ~2.00ETOO' ' ~ ' ~ k! 4:00E+60} ~[~' < SR-90_ _ <j_,1.00E+00
, B E-7 ; <i 3.00E+014
_____ {l0d546 < C I- dl 1.00E+00~
~ ~ <! 3.00E+0ll ~ <j 3.00E+0! -
IK-46'_~ 4 ~ ~ I'.' <._! "950dE+ 01i ~ __ ....
<i 7.'00E+0 lf k ~ ~~ I ~ ~
r ._ __
. _ . . ._ _'7_.'005T61 _4 __.
__ h LC _Ryl.___1 g ,3p0E+0v __ _ f <3 00E+0l+L__ _ _
< 3.00E+01 ] $1N-54 __i <L3.00E+00 _ J _ <' 3.00E+00 4_ _
[_ <'_3.00E+00: ; 3.00E+00{ {
;CO-58 i <i 3.00E+00. . ' < 3.00E+00' ~~^~ ' ~ '~ ~~~~
[fE'~59 - dI73dE+00 <l 6 00E+00 T6 505i66 I-~~
~
(CO-60 ~2IT60EIUd
~ ~4 d OUE+00l < 3.00E+00 jIRT5'5 Y 8.005i~0bT~ Y 7.0U560Ii 2[~5.00E+00 I [ ~ !IR ~ ~+j..;.
- 95. . . .. [7!'.4.00E+00: <! ' 4.00E+00! ~~i " AP~
. 4 _ > ~, I_ ~ ~ ~ } . 4.00E+00; 4_ ._4.a_5..0dE+D~0}._
y
!RU-103 J <j 4.00E+00; <: < _j . _13.00 E+ 00 _ _ .RU _-106 _ <! 3.00E+01 L L__ <
_3.00E+01 CS-134 [ <[l 3.00E4;01{
< 4.00E+00 <! 4.00E+00' ! < 3.00E+00 F ~ ~
i-oCEl~ _ _3_'1. _~_2 . ~~43U5dd _ . _ _ ..a . _ . _ . .
<i 4.00E+00 E ~3 ._ _.U0 EId6 BA-140 < 4.00E+00 - # ._ <L5.00E+00 L ....._. l _ .I_<. .4 5.00E+00 (CE-141 l <i 5.00E+00. <, 8.00E+00 l l <l 5.00E+00 j-~
CE-144 _ _ _]{I]0 540j{ } ~ _ _ , k { 3.00E+0U _ _ j <! 2.00E+01
- RA-226 <l 6.00E401: l l <~ 1.00E+02i I ! 6.00E+01
' ~
[Tif-228~ <Id.~0dE+00[ .L ,
< 8.00E+00[ [l ] ~[l{ < <i 6.U0E+00f[_[ ~
l Nuclide: - l1 =21-APR (a) . - l- 28 APR: 'l. - . a 27-MAYS ,l G R-B l l 2.40E+00 +/ 18f 3E-01 ' 2.60E+00:+/- 9.00E-01 (a) Sp 8f~~I~N~~236lN00I~ I~
~
I
-- < 2'.00570 ~ ~ ._+ . < l.00E+00{ ~
IBEl-~~~~2l 3.00E+0l! ~~ ~ ~ ~ EI5365TO1F[
~ < 3.00E+01~ ~
g-40 _ _ _ _~~ 2[ .5.0d50i __- . ~kl 4.00E+Ulb_~~l_ _ . _ . _
. ^2~850h+01__._..____
iMN-54 ~ di 3.00E+00! l~ <! 3.00E+00; Ej 3.00E+00j [CO58~~ ~2i~3.00EiddI-~
~~~ ~ ~~ <I 2. OEi6d : ~ ' <I3365+6U '- ' ~ ~ ~ ~
FE-59~~ > <U i <! 5.'005 ado' <! ~d50hid0
~~
- C' LZN-65 O
~65~Y_a<!"_6.0U5+6dl3.~
6.00E+00,_ (_ _j <; 5.00E+00; _ _.! 3.0Dhid0'__. .._
.<} . _ _}... _06E40 ~2 .!'5.~ddETO~ I ~~~ ~ ~ ! <! 6.00E4 ,0"_.__f. _ _ _~ ;!
{
!ZR-95 [ <j 3.00E400. ! l <! 3.00E+00 i ' <j 3.00E+00 < l ,
fRU-1,03_{2((i.UUlshd[~} ]} ~<f 3.00E+00L _ [_ __ _ . . . UUh,+00_[_ .
}
RU-106 l <l 3.00E+01{ _j <; 3.00E+0] '
<! 2.00E+01{ l C5}i4~ I <j 3'UU 5 UU[ ~ f ~k} ~ 3 005i60: <} 3.00E+00 -
(BA _140_. < f.00E+00; b 37
}]p@6[]j))))U05}U0[ <l 5.00E+00 .j <[ 3.00E+00; f _ <[33dhiUU < l 3p0E+00{ 'CE-14 ] : ! <i 4.00E+00 . <! 6.00E+00! ;
J b5-144 [~2I3. OEI II b ~~ ~~ I <I 3d 2 5 61I ~ f ~ ~ i 3.06E+iii I i
~~T IR5256 EI'7.00E+Dl! ! <i 5.00E+Ol(( l' N< 8. UE701{ I' "
[TI{@8]_ $,pdE,I00{ [_ ~ ~ <[ 4'.00E+00l _ ( [ ~~ ~ ~ l ~ [~ 5 5+ U{(( ~ ] 7 (a) See Appendix D- Progra:n Execution. C-41
)
Fermi 2 - 1997 Annut! l Radioacth e Effluent Release and Radiological Environmental Operating Report O L./ DRINKING WATER ANALYSIS FERMI 2 l DW-2 (Control) (pCi/ liter) l.Nuclide u li , < ~ J 25-JUN A - 4 , a 28-JULn , w [w c2 425-AUGii Wl l ' G R_-B__ ,_2.50E+00 _ _
+/-j8.00E-01_ _12.10E+00g/-j8.00E-0l_ j l.80E+00 +/- i8.00E-01_ < !_ I l (SR-89 _ i 2.0_0E+00 _ , <L 2 .00E+00' <{ 2.00E+00 l . i<8.00E-01 SR-90 <l 2.00E+00: - 7.00E-01 .{.--. <! 1
_ s .._. _ .. _ ..___ _ ..._ _ ._. . - _ .e .._. _ _p._ _. _ _ l g _4S _ ._d_.-_$_.5.00_E_+01(j _ _ _ _$L9.00E+0lp .
<j_500E+01 . .j_
CR-51 <! 3.00E+0li l <l 3.00E+0lj ! <1 3.00E+0l + MN-54 <j 3.00E+00; 7 ii~4.UU5iOO*7 <! 3.00E+06f
!CO <j 3.00E+00' ~2! 4.00E+00 l <l 3.00E+00! l IFE59 < 6.00E400; <j 7.00E+00 U36hiUU ICO-60 < 3.00ET di < 6.00E+005 <~E DE+00l 2[f3.00E+00 IZN-65 ~~2~ILO0E+00i <! 6.00E+00 IZiU95 <i 3.00E+00! < 4.00E+00l ~ <['15U5+00, !RU-103 < 3.00E+00' ! 4.00E+00 <! 3.00E+00' ~ ~
[RU-106 < ~fdDUiOI 4 ~<i~ 3 06570i
< 2iT00E+01 < <l 4.00E+00 g<i 3.00E+00 CS-134 3.00E+00' _._. _
_4 j. 65II0 <~d.~005i06 T4.d6E+ Oi
~ < 4.00E+00 l ~CE-141 < 6.00E+0dI < ~550Ei6U < 5.00E+00
,( CE-144 < 2.00E+01. < 2.00E+01 <l 2.00E+01 RA-226 < 7.00E+01 < 7.00E+01 <l 7.00E+01 ! TII-228 <q 6 T 0'E idD ~2 ~6.5d5I6 l 1 <lTU65+00L l l Nuclide $
- uww23eSEPr uw l1 : 27-OCT& - t 4 - l NW / 224-NOW W 'el G R-B <l 1.00E+00,_ { _, _ _j_l.90E+00 +/- 8.00E-01 1.80E+004/-
8.00E-01
'SR-89 <! 2.00E+00- <! 2.00E+00; < ~
2.00E+00j l l Sli-90 ~<I 1.6 Ei00" ~ EI' 2.00E+00 I
][. 4.00EiO{.9MO$-DlII < - [} ~ ' ~
Bh-7 -
. ~ _ - - - . . ~ I'<3.bdETO'lI~
3.00E+01 MN-54 < 4.00E+00j 3.00E400j < 3.00E+00; CO-58 < 4.00E+00 <i 3.00E+001
<; 3.00E+00]
- FE-59 < l.00E+01 < 7.00E+00j < 7.00E+00
< 4.00E+00g < 4.00E+00 l $0-60 ~~7].~00Edd]
ZN-65 < 9.00E+00 < 7.00E+00 ( <{7.00E+00} ZR-95 < 5,.00E+00 <[ 4.00E400j j_< 4.00E+00q l pU-lp3 _<j 5.00E+00j <[ 4.00E+00[ _ .__$ < _4.00E+00_ iRU-106- . <l 4.00E+0lj <t 3.00E+0ll j 3.00E+0! ids 134 21 5.00E+00, N "4.665I66 N 4.00E+00
< 100E+00i ~ I<I.~dd570U ^
CS-137 < 4.00E400 BA-140 [< 7.00E+00
))}i.UU5{_ < 5.00E+00 (CE-141 _ _ _ < 7.00E+00 <l 5.00E+00' < 5.00E+00 ~ .p CE-144 ~2~3T05Ib~1 ~ [ <2.00E+01 < 2.00E+01 Q RA 226 < 9.00E+0i < 6.00E+01 Til_-228
_8.00E+00C __ _ _)) f. 0 <[56.00E+00; Td,1 ] _ [
< 5.00E+00 3 C-42 l-l _ _ _ - _ _ _ _ _ _ _
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-2 (Control) (pCi/ liter) 1:Nuclide xl - - :-24-DEC 3 "~ rtm l
< G R-B <! 1.00E+00; <Ii ~ ~
I LSR _-89 _. _.u. _ _ _T00_ETOdI~~
.___q ~
(SR1 90 {2.00E+00 ___
, BE-7 <j 3.00E+01 ,K-40 <i 8.00E+01 ~
IUR-51 ~~2!~2 065 TDT (MN-54 <! 3.00E+00.
;CO-58 <! 3.00E+00' iFE-59 ~< K UEiUU ICO-60 <- {O.~6dE+00 ~
ZN-65 <[~[6T6D5+00j__
;ZR _95__ _
_g 3.00E+00[_ (RU-103 < i3.00E+00j 3.U-106 _3 3.00E+01{ , _. [CS-134 <l 3.00E+00
'CS-137 <j 3.00E+004 B A-140 <i 3.00E+00j ldE-141 EIU60E+00)
( lCE-144 <! 2.00E+01 rfA226 l
<[~55U5I6i-DI-228 <!55UUETON O
1 C-43
Fermi 2-l997 Annual Radioactive Effluent Release and RadiologicalEnvironmental Operating Report FERMI 2 ( SURFACE WATER ANALYSIS SW-2 (Control) (pCi/ liter) l NuclMe t =l w 1 713-JAN (a) / 'm ?l ' L 27-JAN a % TA::3l&# 13-FEB(a)w m SR 89 l 2 00E+00
<4 <L2.00E+001 <l 2.00E+00 _
SR-90 <j 1.00E+00; , <j 9.00E-01 <l 3.00E+00 BE-7 "
<l 3.00E+0l! <! 3.00E+01 1 <i 3.00E+01 K-40 {_Al,_9 00E+0.ll <i 5.00E+ 0_1. T~ <l 9.00 q<
_n _ q <. r . _E+01. __. . . . _ __
. ! 3.00E+0t _i _ 3 L .00E+01._
{CR-51_1<j _3.00E+0l[ L_ _ j_3.00E+00 _ <j _3.00E+00. yN-54_ y,g 3.00E+00 jf_ ___i <[l_ <3.00E+00 4 [CO _ _ _ . _ <( 3.00E+00 _ _3.00E+0 FE-59 i < 8.00E+00 < 6.00E+00; <t 7.00E+0 CO-60 I E[i 4.00E+00j
~ < 3. DOE +00 ~~ ~ ~ <F 3.60Eib6 IN-65 <%006 0) ~dITUO5+~0Dl 'El 7.00E+00 .ZR-95 < 4.00E+0T 51)d5+00j < <' 3.00E+00: 3.00E+004 < 3.00E+00 tRU-103_ . <{ 4.00E+00 I ' RU-106 < 3.00E+01, < 3.00E+01 < 3.00E+01 ~
L USW34 < 4.00EiO0! <
~ [ 3TdO 5 5 6 < 4 (CS-137 < 4.00E+00 $L3.00E+00g _ _ ] _ [_ .00E+00 < 4.00E+00 _ < . 4.00E+00, <! < 4.00E+00 'BA 140 _
_ . _ , . 3.00E+00; _j CE-144 <l 2.00E+01! I <j 2.00E+01 < 2.00E+01 y RA-226 _}<7.00E+0lj <! 7.00E+01 < 7.00E+01 TH-228 <j 6.00E+00l { ,l< 6.00E+00 t
< 6.00E+00 l Nuclidealaw al7-FEB(a); , "It _ 24-FEB; ,
t' . 131-MARC.;m d SR-89 i < <j 2.00E+00j ~ <} 2.00E+00 SR-90 {_{l 8.00E-Ol[ 2.00E+00i <[i.'6U500[ _
<' 8.00E-01 < 3.00E+01 l pE-7___, <(2.00E+0l[ ,_ <l 4.00E+0lj _ __ _
iK-40 .
<{4.00E+01_ _ _ _ , _ ._<;1.00E+02L < 5.00E+01 CR-51 <j 2.00E+01_ <l 4.00E+01f < 3.00E+01 MN-54 <! 3_.00E+00 ,_ __ Jg4.00E+00 , < 3.00E+00 CO <I_2.00E+00 <; 4.00E+00! < 3.00E+00 g-589 ~ ~<f 9'.Ddsi0d < 7.00E+00 tCO-60 N 0dE'+U0"H <t 3.00E+00 l
3 L _$ 4.00E+00LI 4.00E+00 i ZN-65 < 9.00E+00) < 7.00E+00
] 6.00E+00y_ .
ZR-95 <j 3 00E+00: < 4.00E+00; ~ _<1 4.00E+00;
< 4.00E+0 T
{5U-103 RU-106 5.D}5UOf ~~ _(5.5 E+dd[ < 3.00E+01
<l 2.00E+0lp <! 4.00E+0l
[CS-134
<i 5.00E+00[- <l 3.00E+00: <3 4.00E+00 ~
CS-137 1
<[ 3.00E+00 ~~ ]<{5.0dhiO( < <j 4.005+00 gBA-140 <! 3.00f;+00,n _
5.00E+00 _ _(< 6.00E+00 4
<j 4.00E+00; < _7.00E+00; ,_I (CE-141 L I < 6.00E+00 !CE-144 J <! 2.00E+01 J <i 3 00E+01 7 <! 2.00E+01 <! 5.00E+01, RA-226 < 7.00E+01 <] ~~8.00E+0l i <j 7.D 5i00 [ ~~ '~d{l56d5400 O Ti w...l-228~7 ._ 4.00E400!
n . a (a) See Appendix D - Program Execution. (] C-44 1 1 I
Fermi 2 - 1997 A nux! Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 l 1 p/ y SURFACE WATER ANALYSIS , SW-2 (Control) l (pCi/ liter) l l Nuclide r ] r:r ' 28-APR.: ^- r. l ' r 27 MAY '~ .m l-~:r m 25-JUN U+ m al _<j 2.00E+00 i <j 2.00E+00; < 2.00E+00 (SR-89_ SR-90 <L8,00E-01{ } < l .00E+00 < 8.00E-01 l BE-7 j_$[ 3.00E+01__}_ ___5 3.00E+0I l 3.00E+01 K-40 <l 9.00E+01 < 6 J' <j
< 5.00E+01 DR-51 ~ <; <!q.00E+01 <! 3.00E+01 +-- . 3.00E+0l l -- !
3.00E+0l.7_ - [ -
-+ .-
4 l CO-58_. a__.<g 3.00E+00 __ _ _ . _ . . __
<l
- 3. 00E+00 . - _ . . _ _ _ l< 3.00E+00 I
L_._. . _ ZN-65 < 8.00E+00: <t 8.00E+00) <l 5.00E+00 ZR-95 < 4.00E+00! <i 4.00E+00! <I 3.00E+00 RU '03 _
< 4.00E+0Y _ _ , _ <j _4.00E+0$ _ .
(<< 3.00E+00 RU 106 < 3.00E+0Il <i 3.00E+01 2.00E+01 D5~[M < ~700E+60i 4~ <! 4.00E+00 < 3.00E+00 l C_S-137 _ 4.00E+00j <f 4.00E+0_0 < 4.00E+00 BA-140 < 4.00E+00 < _{4.00E+00g < 4.00E+00 4 _ _ CE-141 < 5.00E+00, < 5.00E+00 i <! 7.00E+00[
- ICE-144 < 2.00E+0lf. <I 3.00E+01l < 2.00E+01 ~
RA-226 < 7.00E+01T IH-228 _ <f 9.00E+0th_. _[6.00E+01 j_ _ L< 6.00E+00I __ _4 8.00E+00n _ <[5.00E+00 l,Nuclide P. j e . : 28-JULv
<l: 4 e 25-AUG i Jl6 ,_
d23-SEPr 3 K al jSR 89 < l .00E+00 <i 2.00E+00 _ __ <Ll.00E+00:
$90 __$_,4.0pg;01j_ _ <
_17.00E_-01 _ .
< l.00E+00 BE-7 < 3.00E+0ll < 3.00E+01
_( 2.00E401 K-40 < 5.00E+01' <! 4.00E+01 < l.00E+02 l DR-51 < 3.00E+01 <f2.00E+01 < 3.00E+01
<i 3.00E+00, < 4.00E+00
{MN-54 <[2.00E+00
< 4.00E+00
[CO-58 <Q.00E+00l <[ _2.00E+00 _ lFE-59 <j_5.00E+00
. ._ g __ < 8.00E+00 <l 6.00E+00C J [ <i 4.00E+00 <!_ 3 00E+00 < 5.00E+00 <
4.00E+00 8.00E+00 ZN-65_{$ 7.00E+00j g
< 4.00E+00 ZR-95 <[ 3.00E+00 _ 3 00E+00l RU-103 < 4.00E+00 < 3.00E+00 < 4.00E+00 2.00E+01 } < 3.00E+01
[CS-134RU-106 3.00E+01{ y
< 3.00Et00: < 4.00E+00 <( 2.00E+00 1CS-137 < 4.00E+00; <f 3.00E+00; <I. 4.00E+00 ~
BA 140 < < 5.00E+00 4.065 i00 { [<I3.00E+00{ lCE-141 < 6.00E+00; <j 4.00E+00 < 6.00E+00 g 3.00E+0l}___ < <- 2.00E+01
$Ed44. ,
_ <[5.00E40lj_ [2._00E+0lp_!_ RA-22_6_ _<i 8.00E+0lj_ _ ,
<j, 7.00E+01 ! ;TI1-228 < 7.00E+002 j <[ 4.00E+00} l l <l 6.00E+00j v
l C-45
Fermi 2- 1997Annux! Radioactive Effluent Release and Radiological Environm*ntal Operating Report FERMI 2 (Q/ SURFACE WATER ANAINSIS SW 2 (Control) (pCi/ liter) l Nuclide r l .eh 'a v27-OCTc - ra.- cl r e24-NOVestwax lmmemc24-DECmm:uS 9 _ <j 2.00E+0_0 <j 2.00_E+00_1
@M_ __$ 3.00E+00 < l .00E+00, j ___
ISR-90 ~ ~
< 6.00E-01 <l 7.00E-01 5E-7 _
3665TO.il __ _ _
< 100E+01 72I665idl ~ ~CR- ' 51 <1 2 005Ul! '~ < ~3 365Uf~ <[ 2.00E+01 M N-54 N 3.00E+00! <N3.00E+00 l <j 2.00E+00 'CO-58 ! <I 3.00E+00; ~ ~~ T< 005+UU ! <I 2.00E+00 ~
IFE-59 _ . _[ <n; 6.005_ DOI. _~~.._~ + _ ~..
~Y '.._ 7. OE+00I 7~- _ ~_T<[ .. .
4.00E+00 i 7 ZS35 '< <
~-
ZR-95
- 6.00E+00l < 3.00E+00! ~ ((8[.U0EMO[]-~~~D365DU[ <! 4.00E+00' < 2.00E+00' ~ < <j 4.00E+00f <
11U~153 3TO5h 2.00E+00 i RU-h ' < 3.00E+0ll <l 3.00E+01 < 2.00E+01 CS-134 < 3.00E+00j < 2.00E+00 l p ~E[4.00E+00
. < 3.00E+00' CS-137 <l 4.00E+00j ~ < 2.00E+00 f ~ ~ ~ ~ ~ ~
i BA-140 I ~2i~43 dei O U - ~~~ <I5.00EMD ~~< 16U56 CE-141 M 5.00E+00
<' 2.00E+01 ^ ~AI6 6050 ~
Y < 3.00E+00 CE-144 l <! 2.00E+01~ I ~ ~~
<((.00E+01 }
(- RA-226 < 6.00E+01 l <' 7.00E+01 l < 4.00E+01 1, TH 228 < 5.00E+00l l < 6.00E+00) l < 4.00E+00, i l l l p-V C-46 L___-_-_:___________
Fermi 2 - 1997 Ann::11 Radioactive Effluent Release and Radiological En vironmental Operating Report FERMI 2 O\ SURFACE WATER ANALYSIS SW-3 (Indicator) (pCi/ liter) l Nuclide i .l < < a JAN - -n l',i FEB i ~ l; - (aT3-2.4*b a al
<! 2.00E+00, .i <
jSR-89 . - i . .<j .2.00E+00 . . - .
--. -.. ! _2.00E. 4 00[ l - --.I < 4.00E+01 . _q
_..__.__t.__..__.._._t._. ...._,...__...a .__ _ _ _ . . 05"7._ _ 1.3pgE+pl. _ . . __ __ { <! 3.00E+01 K_-4.0_ _ __ _ <[ [I 7.00E+01 < 7.00E+01 _<f 2.00E+0l!E7,.00E+01_ __, CR-51 < < 4.00E+01
<' 2.00E+01(_
i MN 54 < 3.00E+00' } < 3.00E+00l
< 5.00E+00 CO-58 <j 3.00E+00: _ <, 3.00E+00 i < 4.00E+00 i
[Ep _ $[,6p0E+00 _ _ _ ,[ < 9.00E+00f_ 3[ 6.0653d[ CO-60 < 3.00E+00 < 3 00E+00 < 4.00E+00 ZN-65 < 6.00E+00l <L6.00E+00j < 9.00E+00 ZR-95 <, 3.00E+00 < 4.00E+00
<i 3.00E+00 RU-103_ _< 3.00E_+00g _ < 3.00E+00 < _5.00E,+00_
_ _ __ _<[j. _
< 3.00E,+01 Q 3.00E+0 l < 4.00E+01 .RU.106 CS-134 _I<3.00E+00 <1 3.00E+00 i < 5.00E+00 CS-137 < 3.00E+00 <j 3.005{UU{ < 5.00E+00 g .
BA-140 < 3.00E+00; <' 3.00E+00; < 7.00E+00 CEJ4'l-~ ~E~4.00E+00l ~2 ~53U5iU6 < l .00E+01 ; p ,CE-144 < 2.00E+5II < 2.00E+01 < 4.00E+01 V RA-226 Til-228 6.00E+01l_ 5.00E+00g
<! 6.00E+01 < l.00E+02
__3. 6.00E+00C .
<1 1.00E+01 bNuclide *lt s%7 APR(a)2 m e il - 228-APR ? uwel : Me27-MAY a m rl SR-89 <
I
<( 2.00E+00{__ __ _ <[ 3.00E+00 J 2.00E+00l
[SR-90 1 <[ 7.00E-0l! <i 1.00E+00 1
~ ~ ~ < l.00E+00j
[~
~
BE-7
<(4.00E+01 .
[3.00E+di ]< T8.00E+0) 605I6I'
.K40 <! 1.00E+02 g
_ <[5.00E+01{ _
< 3.00E+01 pCR-51 <l 4.00E+0lb _ _ _
_ <[3.00E+0lf- _
'MN-54 <l 4.00E+00: <l 3.00E+001 < 3.00E+00 58 ~~2 M O{ -~ ~ ~ ~ ~ ~ - i6( < us00 ~
FE-59 CO-60
< 9.00E+00j
_{5.00E+00L
@0E+00] <l7.0 <! 4.00E+00 < 7.00E+00 < 3.00E+00 i
ZN-65 < l.00E+0l! <! 7.00E+00i < 7.00E+00 _jj.Ud5i% ]
~
l < < 27.00E+00 ZR-95 RU-103 _l <- 5.00E+00:4.00E+0,0[- <l 4.00E+00, l< 4.00E+00
%-106_ .
__,$__4.00E+0[ _ _[3.00E401 _j <; 3.00E'+01 CS-134 < 5.00E+00 <i 4.00E+004 _j<4.00E+00
< 4.00E+00; CS-137 < 5.00E+00, < 4.00E+00 BA-140 < < ~5iO6Ei60 < 3.00E+00 5.00E+00[ >
(CE-141
< 7.00E+00; <! 6.00E+00[l < 6.00E400 CE-l_44_ < 3.00E+01 _<[2.00E+0lf,_ < , 2.00E+01 RA-226 <l 9.00E+01 ~ ~~
p T III 2Y8[2i~8.00E+00 (a) See Appendix D- Program Execution. 7.00E+0l((1 l <d[ 7.00E+01305idU;
<i7'005A66 C-47 a_ -_- _____ - _ - - _ _
l. [ Fermi 2- 1997Annust Radioactive Effluent Release and l Radiological Environmental Operating Report
! -C FERMI 2 t .( SURFACE WATER ANALYSIS
- SW-3 (Indicator)
! (pCi/ liter) l1Nuclide1b w. 2-JUN (a)m ;
'l- e 9-JUN (a)0 ~ml- - 1G0 25-JUN + =:l l < < 2.00E+00 SR 89_ . ,5 2.00E+00j _ ____
2.00 _ _ E+00 L__ _. SR-90 < 6.00E-Oli <. 1.00E+00 < 8.00E-01 BE-7 j < 3.00E+01{ <b3.00E+01 < 4.00E+01 lK-40__ _< _ 5.00E+01' , _
<[5.00E+0i _ _ _< {_ 100E+02 _ _[ ,
jCR-5 l___ _$ 3.00E+01_ ! 3.00E+01, .<jA0_0E+01 _<i 3 00E 0g__ l yN-54 <! 3.00E+00 < . + <j 4.00E+00 4 ,
<(3.00E+00, ,_ ___ <; 3.00E+00. < j .CO-5 8 4.00E+00(
FE-59 g <l 7.00E+00l < ' _# 9.00E+004 l <$[ 6.00E+00L_
-CO-60 i 3.00E+00! < 5.00E+00 <! 4.00E+004 fi-65 <
f6 5%_ 1730lNDO <TUUEi61
< 5.,00E+00 ZR-95
_ [ 3.00E+00 . _ <j 3.00E+00;_ . RU-103 <j 4.00E+00 _. < 00E+p0[__ _ (3 _ _$_5.00E+00 _
<j 3.00E+01 < 4.00E+01 .RU-106 <[_3.00EiOlL_ _
CS-134 <! 4.00E+00 < < 5.ME+00 CS-137 BA-140 4.00E+00[_
< 4.00E+00
_<h( .400E+00
<! 4.00E+00 3.00E+00 _ < 5.00E+00 < 6.00E+00 ~ ~ ~ ~ ~ ~
CE-141 ~~< ! 6.'005iOO <, 8.00E+00
~ <[~6.00E +00: ~ - -~~
p [CE 144 <l 2UU55I Y f 05+01 RA-226 <[ 7.00E+01 [!< 8.00E+01j3'.)U5,i0'l[ < 9.00E+01 Til-228 <l 6.00E+00, < 8.00E+00, l _ _$L6.00E+0_01 l Nuclidenlm . '
- 28 JUL :
m .ul .25-AUGe w Mtc "emx23-SEPm *e +l , SR-89 l < l.00E+00; <i 1.00E+00 <l 2.00E+00 I 5R-90 < 8.6 E-Oll Yf60E-01 <i 1.00E+00 BE-7 <i 3.00E+01i < 3.00E+01 < 3.00E+01 K-40 <l 5.00E+01 < 5.00E+01 < 5.00E+01 l'R-51 ~i <3.005+01 < ~ 2TO6E+0T ~ < 3.00E+01 MN-54~ ]< @ U5 5 { }- ~ ~ ~ 32.}00Ej00 [- _
< 5.D0E+00 <j 3.00E+00, .qO-5_ 8_ , _ _ _
_${3 00E+00{ _ ____ <g ,3.00E+00_ _ . _ FE-59 <i 7.00E+00- <: 5.00E+00 <! 7.00E+00 C_O-60 __ L' ._3__.00 - ~ Il 3.00E+00
.. mE. .+. 00. __a... ._ .___p..u_._.___I <! 3.6d55dT ZN 65 < 6.00E+00 4 _ _j <l 5.00E+00, _ _ .__6.00E+q._ < 00
_<l[ 3.00E+00, [ZR-95 { <g{3.00E+00; q LRU-103 3._74.00E+00' RU-106 3.00_E+00(_
<i 3.00E+01 4
3.00E+00L]
<L .00E+00 < 3.00E+01 1 <l 3.00E+01
_CS-134__14.00E+00, < < < 3.00E+00 CS-137 < 3.00E+00i _ f 3.00E+00 . _
< 4.00E+00 3.00E+00j_
BA-140 } < 5.0dE+00] < _ ] '00Ei00] _ __ ~ T5.00E+00
~
CE-14 i L< j 7.00E+00, <i 5.00E+00; i <L 6.00E+00_g LEEI43_L <! 3.00E+plE ,___ <j 2.00E+0l[ _ _ _ _. { _2.00E+01 _ j lRA-226 l <! 8.00E+0l! <; 7.00E+0ll ! <l 7.00E+01 [
#q f $1-228 [<{7.00E+00 _.L__ L <j 6.00E+00 [ _ <] 00E+00,1g Q (a) See Appendix D- Program Execution.
C-48 l
Fermi 2- l997 Annual Radioactive EJJiuent Release and Radiological Environmental Operating Report
/7 FERMI 2 d SURFACE WATER ANALYSIS SW-3 (Indicator)
(pCi/ liter) l l Nuclidealt -
- 27-OCT ;L a 24-NOVJ w e l rn T
- 17-DECm 2a El
<SR. _-89 _ j _ <L2.00E+00 g <
_[,1.00E+00, ; <t __j
. _ _ _ _ 2.00E+00C t SR-90
_ _{_ << LI.00E+00, _ __
< 8.00E-01.
__j. }_M 6.00E-01 B E-7_ K-40 _ [ 2.00E+0ll,, <l 3.00E+01
< 5.00E+01
_ }l _ < 3.00E+01 t
<{ ,4.00E+0l! ,_ ,__[ 6.00E+01
[CR-51. _ _ <; 2.00E+0l } _
._ <. 3.00E+01 ~ ~ < 3.00E+01 SIN 3i <l 3.00E+00: < < 3.00E+00 7[3.00EiO0I- ~ -
I
'CO-58 < 2.00E+dd _.4._ 3 055+6UY~ < 3.00E+00 t t FE-59 < 5.00E+00: < . 7.00E+00: <j 7.00E+00
[CO-60
<' 2.00E+00{ <(3.00E+00l . <! 4.00E+00 ZN-65 < 6.00E+00; < 6.00E+00l <l 7.00E+00 I'R-95 < 3.00E+00: < ~7065W07 3 <;
3.00E+0} RU 103 < 3.00E+00 '~ -
< 4.00E+00I- ~ < 4.005+001 ^'< 3.00Ei0lf' R{f-'iO6][~T2.Ud5+6i ~ -
3.00E+01 4.00E+00 hCS 1 134 - ] 3.00E+ppj__,_ $ 4.00E+0[0
;CS-137 < 4.00E+00: <! 4.00E+0 ' < 4.00E+00 ~~ ~
fBA-140 < 3.00E+00I~~7 N fUUE+d ~~
< 4.00E+00 IC5!ifl~ N< ~
5.00E+00 ~
< ~ 8.66ETd0 < 6.00E+00 'I CEldi~~I~ [2.00E+01 < 3T6U5+0F < 2.005+01 < 9.00E401 < 7.00E+01 RA-226. _ L<[ 6.00E+01 TH-228_j _< [ 5.00E+00, .
_ <n 7.00E+00n,
< 6.00E+00 l
l Nuclide Rlm 24 DEC# M +1 y-89, _ _ . $g2,00E+00[ _ . _ {SR_90_ _j< 8.00E-0lj j_ iBE-7 __ <l 2'005+01
!K-40 <[ 4.00E+01 < 2.00E+01 ICR-51 ..- _ -. . - - - - - -
CO-58 <i 2.00E+00 , FE-59 < 4.00E+00l CO-60 < 2.00E+00! I
.ZN-65 _. <{4 00E+00!
3R-95 __ _, _$[,,230Ej0[,_[_
.RU-103 __ <[ _2.00E+00j_ _j yU-106 _ _$[ 2 00E+0lj_ _ ;CS _i34 _ <l,_2.0_0E+00 _
[CS-137 <! 2.00E+0 [ l !BA-140 <l 3.00E+ 1
'CE-144 5:i4l~ ~i~~5.05W0[]{ <l 2.00E+01
[RA-22F 4 6.00E+01
. !Til-228 <, 5.00E+00; C-49
FermiJ - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 DRINKING AND SURFACE WATER QUARTERLY COMPOSITE SAMPLES Tritium (pCi/ liter) l Station ;l' ' First Quarter el Second Quartern 51 L I __ . _ . DW1 J3.10E+02[+/- 1.40E+02 < 2.00E+02 I
.i _ _ ..___ . _ . . .
__._.-.._3. _ ._.. _ _ . _ .. L _ -.L _. _ _ _ 1_ ! . . _ _. . _ _ _ _ . _ _ _ . _ . . _ . ._.._ SW-2 <t 2.00E+02
._. .2.00E+02{(a). , _ _ _ _ _. . . . .. _ _. - .-_ . L _ 4 - .- .- . _ . -
1
.-SW-3 2.00E+02} }_ .-2.00E+02 ---. -- [(a)
Station + ' l ~ 51hird Quarter 4 . l - v' ' TFourth Quarter + * <
.._.}...__.-_.. _ , . _ _ . _ _ .-_ j _3.40E+02 . _ _ . _ . . _ _ . _ ,q . - _DW-1 <j 3.00E+02, _ j _ __ t +/-._ 1,50E+02 ~
iDW-2 1 5.5U5idi U 13U5+02~ 2 dd~E+021---.. y
~ -
W-2 _ME32 [__]l _ __ __ _, 2 5d5+02 +/- iT0E+02 i.
,S,W-3 [13.00E+02L_ _ _ _ (a)t .50E+02,+/-
3 i.50E+02 (a) See Appendix D - Program Execution. i l l l I l C-50 t C _____. _ _ _ _ _ _ . _
Fermi 2 - 1997 Annu:1 Radioactive Effluent Release and Radiological Environmental Operating Report n i ( FERMI 2 GROUNDWATER ANALYSIS
/
GW-1 (Indicator) (pCi/ liter)
.Nuclide l A 4 First Quarter- -
Qili aw Second Quarter .: l B E-7_ K-40 j i <
<[ 3.00E+01_1 l <l 3.00E+01 <! 6 00E+01
_ _]
.l _J 'CR-51._,_!_[5.00E+01, <; 3.00E+01 l ! <j 3.00E+01 MN-54 l <l 3.00E400 i <j 3.00E+00 C458___[_,< 3.00E+00; _ _L ___. < 3.00E+00 FE-59 .
_p< 6.00E+00g _ < 6.00E+00 4, _ CO-60 < < 4.00E+00 _ p' 3.00E+00;. , __,[ ZN-65 < 6.00E+00 < 6.00E+00 ZR-95 < 3.00E+00 < 3.00E+00l RU-103 < 4.00E+00 < 4.00E+00' RU-106 <l 3.00E+0if i < 3.00E+01 _CS_1_3'4 I< I f005T00I
.._ 4_. ~i,' ~
L___p
~i~f6657UO <
CS-137 j <l 4.00_E+00L _
<(4.00E+00l BA-140 6.00E+00( 3. 4 Q <<1,5.00E+00 _.
CE.I41__ 7.00E+00 7.00E+00 ; CE-144 < 3.00E+01 < 3.00E+01
~
RA-226 <l 7.00E+01 < 9.00E+01 l 1 TH-228 < 7.00E+00 < 7.00E+00 11-3 < 3.00E+02 < 2.00E+02 l-Nuclide al: 4 Third Quarter ' s , ? lV:0+FourthQuarter - d. lBE-7 L<j 3.00E+0l! j' 4<j 3.00E+01 K-40 <! 5.00E+0lj l 2 5.00E+01 (fii-Ti [ Y3.60ET0Y ~ ~
~ ~ <f 3.00E+0l! ~
ISN54 j T 3.00E+00: <j 3.00E+00l CO-58
))?Q0U5+00l ~~~{3[f 7.00E+00;MU5TO}0{
FE-59 < < 7.00E+00 CO-60 < 3.00E+00 < 3.00E+00j ZN-65 y < 6.00E+0_0pl___ <j 7.00E+00 ZR-95 < 3.00E+00 < 3.00E+00 RU-103 <l 4.00E+00 }~ < 4.00E+00 IUT106 <' 3.00E+01 < 3.00E+01 CS-134 T3I065+66I li 3.00E+00' CS-137' ~Y 3.00E~ 0(( ^[ 3.00E+00 < [CE-141Bgl40___$ _ _7_.00E+00[,j 4.00E+0}_ __
< 8.00E+00' <. 7.00E+00 CE-144 < 3.00E+01 <, 3.00E+01 RA-226 < 8.00E+01 7 - 8.00E+01 til-228 *< 7.00E+007 ~" < 7.00E+00 '11-3
((2.00E+02[]_] < 3.00E+02 O C-51
Fermi 2 -l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-2 (Indicator) (pCi/ liter) [Nuclide ~ . l1 ~ First Quarter .l~ ' Second Quarter :.: -l 1BE-7 <i
! < 3.00E+01 . - . . 4.00 E+0 l l .. --. _ . y - -- - . _ . . - . - . - . . _ _ . . . _ _ _. J__.._-_..___g _ . . _ . . .CR-51 l 3.00E+01
__g<[ 4.00E+0+1{ j _<<I 3.00E+00 . _ _ MN-54 <i 4.00E+00 , b
.CO l8 l AI~iOUEI00' ~
T d~iOO5Idd ~ ~~ ~ ~ ~ ~ IFN~~59 ~ ~ di 9.00E+0U . . _ _ . .~' l dI'750E+U0 - r _ . . ._ t _ _ -- . 3
~* ~ ~ ~~
IN.65 _ _. <3 .00E+dd l . , . -
<I ~8.U0Eid0I~ ' . _ _ _ . . ~ ~ ~ ~ - ~ ~
R{i-Id5] [556D5idd[ [_ <[1005idd RU-106 i <j 4.00E+0ll ' I <! 3.00E+0ll [CS!i'3T~~<3 I~i3dhi d' ~ '
~ ~ ~ ~ ~ < 3.00E+00I CSd57' d! 450EiOO , ~ < 4.UO5'+bOI ~ ~ ~ 'B'A ij4U~ ~ ~<~ f 500Ei0 I~ '
l I <[ iUU5+~ UI ~ - ~
~ ~ ~ ' ~ ~
CE-141 <t 6.00E+00' ~ ~i~2I650EiOUf - ICE'~lli "~ dI250Eidl
~ ~ ~ ~ ~~~ ~
I <[~2. D~Ei0l! ~~ ~ ~ ~ fRA-226 - ~ <I '7.00E+U I { ~~
<f ~7 D0E+0ii~~-
[Til-228 [<i '7.Dd5+00E ! <
~ I ~ 7505+~d0 1 A2 ~ ~ ~ ~ ~
lg ._.-. - o 505I62i ~< I'25dETU2
, -.T . _ _ . 1 m. _ _ . -
l Nuclide - l 7 ffhird Quarter ;l ' % cfourth Quaiter ! ,
+
4 B E-7 <l 3,00E+01 <l 3.00E+01 K-40 1 <i 5.00E+01 < 5.00E+01
.__]
C5-~51 i <>f 3.00E+01
< 2.00E+01 ~'~ ~ ~ ~ ~ ~
CO-58 < 3.00E+00I' ~l ~2['25 dei 0 i ~ FE-59 ' ~ ~ di 6.0dE+d0" ! ~
~!"5.005i00 "~~
CO'50~~ ~ ~ i
<!idOE+00 I AI ~350EiOO ~
I'IN-65 ~' ~ f ~ <I ~6'005+00" [ '<i'57005IO0I~
~ ~ ~ ~ ~ ~
[IR 55-~~~~~~~E 3 00EiOD ' i' ~~~ T Ai~i~06EA00I-~~ IRUj03 ' ~
... h! ._ .'4.00 I . _ _ _ _ . _ _ .. _ E + 00_ . _ , ___ o _f __<! . _ .'_3.00E+005 RU-106 __ _ _ , _ ! _ <; 3.0001 E+y __1 _ ._ _ __ _ _ <L3.00E+0l[_ _ ! _
CS-134,_l <i 3.00E+00, I <! 3.00E+00; ~~~ CS-137 ~
! ~dI 45d5iddi ! ' ~~
I <l'5565iUDI BA-146~ ~ i~550Ei d
~ d~ d50EA60i " ~~ ~ ~
C5-lij }l' A ~ 65DEIU0I
~ i~E{l 650ETOM~-' - ~~~ ~ ~~
CE-144 < 2.00E+01 <[2T665{U RA-226 ], <: . { _
~
7.00E+0ll ; l <l 7.00E+0lf ~~ k j .[5.0E+00[_
$2281<{ }6}00E[+}00f .
S*.3__ __,_ _,1 <! 2_.00E402! l <; 3.00E+02 , C-52
Fermi 2 - l997Annux! Radioactive Ef]Iuent Release and Radiological Environmental Operating Report
/N FERMI 2 V, GROUNDWATER ANALYSIS GW-3 (Indicator)
(pCi/ liter) l:Nuclide7 lm ' : First Quarter , l; Second QuarterU ~ l
.B _,, ,_ .
0 . _ _ _ 3 [']_[<iT0DE+00I-- MN-54 <g 2.00E+00g CO-5 8___
, <L2.00E+00{_ { _ _ ,__ <[ 3.00E+00 FE 59 <! 6.00E+00, __ __ { 5.00E+00; <
CO-60 l <j 3.00E+00l ; - <! 3.00E+00! ZN-65 i <I 5.00E+00 ~ i
-[f065iO0I 5Rlf -~~} EI 3 65IU 7 3.00E+00 RU-103 < < 3.00E+00
__ _.3.00E+00.. . _ . . . . _ . _ . lCS-134 <. 3.00E+00i ~d[ 3.00E+00I tCS'.Bf~ - - .
~ 2 ~3 0DE .i0 -- k-.j.'~2I F~~^ ~i 3.00E+00 ~ ~ ,CE. I 41 [ << 4.005+00TY <j 5.00E+00 < 2.00E401 CE-144 2.00E+01 _ _ .RA-226 _ < 5.00E+01 < 6.00E+01 (q TH-228 H-3 5.00E+00 3.00E+02[ , < 5.00E+00 < 2.00E+02 l Nuclide-: b ea. Third Quarter ;_.:4 , Fourth Quarterend ' q BE 7 1 < 2.00E+01 <' 3.00E+01 K-40 i < 3.00E+01 < 8.00E+01 l 5C))_ {2p5M]((. __ < , 3.00E+01(_
MN-54 l< 2.00E+00 {___<< 3.00E+00 _3.00Ej0j l CO-58 {_<{ 2.00E+00_j FE-59 < 5.00E+00i < 6.00E+00 CO-60 < 2.00E+00l < 3.00E+0 ZN-65 g5.00E+00' _ < 6.00E+00 ZR-95 < 2.00E+00 < 3.00E+00 RU-103 < 3.00E+00 i < 3.00E+00 RU-106 < 2.00E+01 < 3.00E+01 i _ [_ < 3.00E+00
'CS-134 _
2.00E+00g l CS 137 < 2.00E+00; < 3.00E+00 T.005sdUI {_
~ ~ 'B A-140 < < 4.00E+00 g,g r{ j~4.'605+05 ~ ~ ~ < 5.d6ETO0 ~
CE-144 tit 0 lie +01 < 2.00E+01 RA-226 < 4.00E+01 < 6.00E+01 TH 228 < 4.00E+00: < 5.00E+00 H-3 < 2.00E+02 < 3.00E+02 O C-53
Fermi 2- l997 Annual Radioactive Effluent Eelease and Radiological Environmental Operating Report FERMI 2 O GROUNDWATER ANAINSIS GW-4 (Cor trol) (pCi/ liter) l Nuclide" l First Quarter .i~l- . Second Quarter -
< 3.00E+0 ] <
BE .7 . -.
.-l .j-2.00E+01 ' ..- . _ _._ 4 ,. _ _____
MN-5_4_ ! _< _3.00E+00 . j _ _ _1 < 3 00E+00_ _ _ . _ . _ . . _ . . _ . . _ _ _ _
,CO-58 < 3.00E+00: ! < 3.00E+00 _ ~ ~ ~
IFEd9~~ '
<I ~5. DOE +dOU ! ~ <I~550EiOO
[CO-60~ ~~l ~ 2 3.06E+d0' ' Yld 546d ' ~ ' ' ~ ~ [ZN45~~ ~~AI ~6.0054 00I ~< i~5Tdd5+0'0 ~
<[55dh+ DF--~
I2R 5I5- <I~100Ei0 , Ri.f-lb3~ < 3 < 3.00E+00
"{~.6bE+6 ][~
RU-106 <j 3.00E+01 i < 3.00E+0i - fCS -134 < 3.00E+00E7 '~d[35565+00 fds~ilf~~f 2{1 j~6dE.T UI^ ~_ <l _ 4.005
~
p _.. .. y _ ION j BA 140 _ .. _.s _. _ _{_.__ L {_<L4.00E+00L_j. _
<j 4.00E+00, !CE- 141 ! <1 6.00E+00l l <l 5.00E+00' ^
I CN id4 1 <I~i(6U5jdl{ ~'[ RA-226 l <l 7.00E+0l! ! [<[2.D05{0i
<l 7.00E+0lj ~ ~ ] ((_ ~~ - ~ ~ - -
TH-228 TELX065s60! ~ ~ ~ l '<f ~6.605700; LH-3, _ _ _ . N 2.005iO2[ _ [ <L2.00E+021 1_ l-Nuclide -l ' c Third Quarter < 'l- Fourth Quarter u z
< 3.00E+01 '
l' B_E-7_
. _. o._2_.00E+01<i . .__ l.. . . <
J [K-40 _ 4 <j 5.00E+01 l 6.00E+01l _ CR-51 2.00E+01 < 3.00E+0ii_ MN-54 _
<[~1U0E+00 { ~ <j 4.00E406 ._ . _ . _ _ ~ ' ' ~ ~ ~ ~
FE-59
<I5U054D0' .a 4 L <.. . _. _..._.L_.
8.00E_+00 ~~~ ___ [CO-60__{<{, . . .. _ . ..2.00E_+00 _ 9 q _<j 4.00E+00 _ _ . iZN-65 i <! 5.00E+00. ! <' l .00E+01
. Il ,RU-103 ! < _3.U 5{00,i ' <[ 3.00E+00; ]I <[~4.U0h[iU <! 4.00E+00' [ )) ~ ~ ' - ~ ~
[RU-106 l < 2505+Di E[3505iOI ICS-134 '
"7[IU65iUU[; ! <! 4.00E+00, 'I ~ ~ ~
CS'-i57~ ' <f3.UD5+0 ' ^
~ ( 74.UU5T6dI~- ~ -
BA-140 i <j 4.00E+00 ~ 7 7 T0ii8TO0I- - d5-lii~~j~ 7[~j.DdhiOO
~i 7[5555iO6I-~
CE-144 l <I 2.00E+0i ~I 17 3.00E+01
! ~ 'RI-2i6l'A[6.U0EI0l}'~l ~ ~ T AE8.005+01'~~'~ ~ ~
TH-228 ~T <l 5.00E+00l i i < 3 605i00 H-3[)) < 2505+02! <[i~00E+02(~~ O C-54 a
Fermi 2 - l997 Annu11 \ Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 SEDIMENT ANALYSIS ( ;. ( l S-1 (Indicator) (PCi/kg dry) 1 l:Nuclide J l / al3-MAY2 .
"ls - , , c15-SEP : m er (SR-89 j <! 5.00E-01 3 1.00E+03l .SR-90 _ [2.00E-O l _ <{ 4.00E+02 BE 7 . _ _ , _ <i 3.00E+02_._ ._J< 2.00E+02 l M.._..l . I .21 E+04]+/ 1.20E+03_ . _ _1.26E+04 +/ _ l.30E+03_
MN-54 I <i 2.00E+0li _ <i 2.00E+01 C~ I~O-58~~T~~<[ _ . ". T_.iiO5_70l{._ -. E ~ ~~ ~7_ _2.00E+01 fCd-~6'O < r 3$UD E id I ~ f < 2.00E+01 ZN-65 < 6.00E+01 < 6.00E+01 ZR-95 < 3.00E+0 s < 3.00E+01 l (RU-103 <13.00E+01 !~ < 3.00E+01 i RU-106 < 2.00E+02 1 < 2.00E+02
-,.. 7. q . - -- .- ,-~- -- _-. --_._---w-_.-..--_.2.00E+01 \
CS-137 < 2.00E+01_ ,_, _ _{_<__ BA-140 < 9.00E+01
< 5.00E+01 ]
4___ E-141 I <. 6.00E+01 _ L ___ < 4.00E+01
~
CE-144 < l.00E+02 l < l.00E+02 ; RA-226 9.81E+02 +/- 5.iSE+02 < 3.00E+02 l [TH-228 3.52E+021 +/- 4.00E+01 2.07E+02 +/- 2.40E+01 S-2 (indicator) l (PCi/kg dry) l l Nuclide:.+lo A~ 15-MAL a lan es SEPMWN SR-89 < l _ L9.00E-01 _{ _ _ <i 8.00E+02J l SR-90 +/- 1.90E+02
- <l 4.00E-01 i _.- - . { 3.80E+02 ~
K-40 __ T1.96E+0447-R2305+03_ 1.79E+04 +/- 1.80E+03 l CO-58 < 4.00E+01 < 3.00E+01 l FE-59 CO-60 _
< l.005i62 < 3.00E+01 ][ < < 1.00E+02 3.00E+01 ZN-65 < 8.00E+01 < 8.00E+01 ZR-95 < 4.00E+01 < 4.00E+01 RU-103 < 5.605+01 [ < ' 4.00E+01 liU-106 <i 3.00E+02 '~i--~R ~ ~ ~ ~ - < 3.00E+02i ~
DS-135~ ~~<i 4.00E+01 < 4.00E+61~
~
CS-137 _< [dM5T6i(( BA-140 l.00E+02
))]<< 3;00E+01 l.00E+02 l CE-141 < 7.00E+01 < 6.00E+01 ~
i CE-144 < 2.00E+02 ~3 2.00E+02 i RA-226 1.77E+03 +/- j4.20E+02 ~ 1.50E+0 +/- 4.60E+02 Til-228 f O, y 1.20E+03f7~ li~205+02 .- 9.16E+02 +/- 19.20E+01 1 C-55
Fermi 2- 1997Annuil Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 O SEDIMENT ANALYSIS S-3 (Indicalor) (pCi/kg dry) l Nuclide U ln - , .!!5- M A Y n -
- l -, W- SEP whau SR-89 < 7.00E+02 l< 9.00E-OlL !
,SR,-90 }, <4 2.00E-01 3.00E+02 +/- 1.60E+02 BE-7 < 4.00E+02 < 2.00E+02 K-40 1.92E+04 +/- 1.90E+03 9.15E+03 +/- 9.10E+02 4_
MN-54 1 < 3.00E+0ll ! i < 2.00E+ 01 ~~ C6-T8_7-_ . V4.UdEidi[]._-_._~ ~-[~$"270'd5idl~' _ . D 75U - '< 3.065IUli' l'
~ ~~~~~~ ~ ~l Ti.Ud5761 ~ -~
ZN-65 I~<~8.OEidli_'~ E
- g. __
<[5065T01 RU-103 < 5.00E+01 7 ~8 3.00E+01 RU-106 < 3.00E+02 < 4.00E+01 ~[ < 2.00E+02 CS-134 . < 2.00E+01 CS-137 < 4.00E+01 < 3.00E+01 l.00E+02 <
BA 140] < 7.00E+01 C E _i_41_<[ 9.00_E+01_ ___ <} 5.00E+01 _ CE;_I41_ _ _ < _2.00E+02 _ <{l.00E+02 . _ _ ___ RA-226 1.95E403 +/- i4.90E+02 j _< 4.00E+02 y TH-228 9.33E+02
. - . - . -+/ - .~;9.30E+01 _----w i i 2.24E+02 +/- 3.40E+01 S-4 (Indicator)
(pCi/kg dry) (Nuchdee.le W27-MAY+ . sl - Wea23-SEPnd Wbl SR-89 l < l .00E+00' < 7.00E+02
'5R-90 r< 4.00E-01 < 3.00E+02{- ~
I5E-7 7 2.00E+02 < 2.00E+02 K-40 1.07E+04 +/- ' l.10E+03 < l.00E+03 yN-54 2.00E+01_ ____ g <__ 2.00E+01 __
- CO-58 < 2.00E+0li < 2.00E+01
< 5.00E+01
[FE-59 , <1 5.00E+01 j CO-60 <i 2.00E+01 } < 2.00E+01
< 5.00E401 <
ZN-65 4.00E+01 ZR-95 < 2.00E+01 < 2.00E+01 RU-103 < 2.00E+01 < 2.00E+01 RU-106 < 2.00E+02 ' < l.00E+02 US-134 < 2.00E+01 I~ CS-137 < 2.00E+0 ! ! 8[iiOT15+01
< 2.00E+01 p
BA-140 <[ 3.00E+0T I" ~ L<<l 4.00E+01 CE-141 3.00E+01
<[_3.00E+01 [
CE-144 I < l.00E+02 i [ Ni'6U5IU2
'~5 53si 2}iI-~ ]2j9EI62~{~~ 3isi0i[57-~
H~i2id 5 i~655A62~ l TH-228 L J 1.63E+02,i+/ .,!2.00E+01
- - - - ..- _- __a-i 1 48E+02[+/ _
1.90E+01 C-56
l Fenni2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report
. /~ FERMI 2
( SEDIMENT ANALYSIS S-5 (Control) (pCi/kg dry) l Nuclide+ t +A 7-MAYA - < ~ $ *M19 SEPi ese < lSR-89 I <i 1.00E+00; <. 1.00E+03 I51i-9T) ~I~<[ ' 3.00E-01 < 5.00E+02 BE-7 <! 3.00E+02 +i- 3.12E+02 90 _ __,_ { 1.24E+04 MN-54 <l 3.00E+01
+/- - 1.20E+03
(( 8.89E+02 i < I.11E+04IU- 1.1,0E+03 DO-58 , <l 3.00E+01 79[ 4.00E+01 4.00E+01 [~ FE-59_j[8}.6'05'+6i{ } I~ < l.00E+02 ICO-60 (<< 3.00E+01
. _ _[ < 3.00E+01 ZN-65 6.00E+01 _ }L . - - . - .< -
9.00E+01 RU-103 < 4.00E+01 I~ < 5.00E+01 INIJ-106 < 2.00E+02 i <i 3.00E+02 CS-134 < 3.00E+01 I i 4.00E+0I} l 5 5-157 1~ 1.21E+02 +/- 2.60E+01 ~9.25 < E+01 +/ .2.96E+01 BA-140 < l.00E+02 < 2.00E+02 -~1 E-141 <
~((87 [0}$+0i ' ] ] ]~j,~5 TOE +01
[CE-144~ <i 2.00E+02 < 2.00E+02 RA-226 ! 8.53E+02 3.62E+02 1.08 E+03 +/- 4.60E+02
,g TH-228 , +/
l - 4.29E+023/ , j4.3_0E+01 5.27E+02 +/- 5.40E+01 L I C-57 l
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O (j FEM 112 ; FISH ANALYSIS F-1 (Control) (pCi/kg wet) l Nuclide ^ t l 2 L5-MAY CrappieW -l" < 5-MAY: Walleyou wlv r21-MAY: Rock Bass? :l
'S R-89 1 <l 2 <
2.00E+0lj <l 3.00E+0ll 90 N j.00E+0llfd( h.6 p_Q,,_ _
~ ~Q6 {57 ,,
BE-7 <i 2.00E+02! < 2.00E+021 <i 3.00E+02 i
~
K-40 f215 5iU5[Al~If.365IU2' 2.395AU3 I +/3 2 305+62 IN 2.54E+03 +/- 12.60E+02 bb_ bkbI i,CO-58_,_]<{ 2.00E+01( _
<!) .bb5 0'1,[ I_ _.
i [,f605i61
<1 3.00E+01 ]_ _ _1l
__ <[ 2.00E+01. FE-59 <l 5.00E+0li . <! 4.00E+01 l <t 7.00E+01 i [CO-60" <l1.00E+0ll~
~ ~ ~2[ ~1.ddsi0i[-~l -T 2TO 5i01 ^
ZN-65 <l 3.00E+01 _ <<[ .565[+01 < 5.00E+01 ZR-95 <l 2.00E+01 _ {2.00E+0l[j _
< 3.00E+01 RU-103 h 3.00E+01 < 3.00E+01 < 3.00E+01 9 _13 6 1CS-134___,5W40E+02 _ < ((i505+q2 ~U I E+02, _ _. <! 2.00E+01- < l .00E+01 < 2.00E+01 < <i 3.00E+0i (CS-137 __ L2.00E+0i <1 2.00E+0 i BAp0,,_ _5L7 00E+;01_ _
_ <j l.00E+02; _j 3. 8.00E+0 t , SE_-141_ <p.00E+01I __ ___
<j _4.00E+01 ! <
_ (< 9.00E+0l[___ ,_ < 3l 4.00E+01 {qf CE-l_44. RA-226
<! 3.00E+02!
____ [ 8.00E+01[ <l 2.00E+02; L <L2.00E+01{_,j
] < 4.00E+02 1.00E+02 TH-228 ,<[ 2.00E+0ll J [ _ < 4.00E+01]
l.Nuclide t . l- v21-MAY1 Sucker 2 'lz 19-SEP Carpm + ,l / 2 9-SEP Rock Bass ; , -l
< < i <i 6.00E+01 SR _89_
2.00E+01 Q. _ p4.00E+011] _ l SR-90 6.00E+00: < 100E+01
<p9.00E+00{
BE-7 . < 2.00E+02! < l.00E+02l < 3.00E+02 _ K-40 3.40E+02
._ , 3.3 8 E+03 +/- 2.36E+03]+/- 2.40E+02 2.24 E+03 +/- i_2.90E4 02_
MN-54_ <i 2.00E+01: <
-.j1.00E+01 <. 3.00E+01 i .I -.
IF5~59 <l 5.00E+0l! <! ~3.00E+01 < 8.00E+01 I
~ 'CO'-id EI~f665i011 ~EI ~ i~6diiT0i"~l T i~0U5+01 ZS~~65 < ~ T~5.00E+01 ~ <j 3.00E+01 < 6.00E+01 ~~ - < I~0 5+61 .ZR-95 <F 2.00E+01 <, 3.00E+01 RU-103 < 3.00E+01 <, 2.00E+01 <! 4.00E+01 RU-106 < 2.00E+02) <f~1.00E+02' < 3.00E+02 CS-134 < 2.00E+01 < 3.00E+01 t <j1.00E+01 l
fS-137 < 2.00E+01 j << l.00E+01 < 3.00E+01 C-~ BA-140 < 6.00E+01 <l 4.00E+01 -
< 1.00E+02 ~
{ IC5-141 3 4.00E+01" _{5.655+01
} ]2[f005fd1))_ _ <g 1.00E+02 ))l 'CE ,144 _ <j_1.00E+02 __ <j 9.00E+01 _ __
RA 226_ ! <l 3.00E+02 } l <! 3.00E+02;, <i 4.00E+02 ! I
~
A .T_i.l_-228.__
. Lx i 2 3._00E__+01]_ } _ [_<I '2.66Ei6.i.a .
a _. ~]T005i6i ~ ~]~ _ _ _ _ _ _ . . _, l C-58 l
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FEIG112 O* FISil ANALYSIS F-1 (Control) (pCi/kg wet) l Nuclide , - l 9 SEP Walleye ' r --l
;SR-89 <; 2.00E+01(_j _ ;SR-90 <l 4.00E+001 ~
lBE-Y~~ E
- - . ~~ - -. - - .<[ 1.'00E+D2[ ~
NN 34~~I'<[1.00Eid1[~
~~
f IC O-5 f ~~~I T 1.0'0Eidl I ~ I
~~ ~l ~~
[FE-5F I [ ICO-60
~ 'f~<!1.00E+0ll3.00E+01,![
l< i
~
ZN-65 ' <. 3.00E+0 ] " ~ ~ ~ ~ - ZR 9f-'
<I ' l .00Ei01 ~
RU-103 I <' l.00E+0lI~ ~ T - IRU-IO6~ ~~ ' I 9.00E+0l! ' ~ h~~ CS-i54~~ <! l.'dOEidi I ~i gg)g- - i,98Ei01 UN00570d' ' ~~- [B5-l4' 0~
~ <! A0dE+UI - ' ~ ~ "CE i41 ~~< 3.005761 ICE 144 ~Ai'T.dD5IU2I~
RA-226 []~2I ~iD0EIUI
~
fii-[228
~f0U5i01 O
C-59
l Fermi 2 - 1997Annu:1 Radioo:tive Effluent Release and Radiological Environmental Operating Report
.m FERMI 2 V FISH ANALYSIS F-2 (Indicator)
(pCi/kg wet) l Nuclide @ ' 13-MAYiCatfish " :l^ , cl3-MAY. Carp c 2
- 4. ~ ' n13-MAY Drum?
jSR-89
~ ! <! 3.00E+0l! <{ l .00E+0l l <j 8.00E+01 ISR-90 72I~7.00E+00{ <[2.06E}UU['[ . _ <[ 2.00t+01 l
QE-7 <{2.00E+02 _ _ _ .. _ j 2.00E+02L _ __
<i 4.00E+02 K-40 gl_2.7_5E+034/- 2.70E+02_ _ L_2.55E+03{+/ ,2.50E+02 1 ! 2.46E+03 +/- 3.50E+02 MN-54 _- l. <[ 2 00E.+0li--i.- << 2.00E+01l -
i
! <l 3.00E+01 I
_.4_____ _ .,.__ _ _ _ . IZN-65 < 4.00E+01 <j 4.00E+01 <I8.'66E+0! l 5R-95 < 2.00E+01 F 2554~1 < 4.00E+01
~RU-103 < 3.00E+0 i [- <[C3T60E+01 < < 5.00E+01 RU-106 < 2.00E+02 <! 1.00E+02 < 3.00E+02 CS-134 <! 2.00E+01 < 2.00E+01 < 3.00E+01 CS-137 2.00E+01 ___ _ < 2.00E+01 < 3.00E+01 tBA-140 , , _<j 9.00E+0,l[_ __
_ L< 7.00E+01_, _{<] 2.00E+02 CE-141 < <l 4.00E+0ll _{5.00E+01{ l <! 6.00E+01 j CElR___fj_1.00E_+02(_ _
<j 1.0_0E+02! ' <L2.00E+02_
_ <j 3 00E+02[__ m RA-226 <j 4.00E+02i <! 5.00E+02 LTH-228 _ <[ 3.00E+0l[ j <j_2.00E+0ll. < k _ {5.00E+01 l l ,Nucliden l, al3 MAY~ Perch r:mc l : 13-MAY Silver Bass e 4: . 13-May Walleye uw 2l SR-89 < 2.00E+0lj <l 3.00E+01 < 2.00E+0l j l
< < 5.00E+01 < 4.00E+00'
[ SR-90 BE-7 < 5.00E+003
< < , 2.00E+02
[ _ i _2.00E+02] 3.0_0E+02 _ lK-40 2.97E+03 /- 3.00E+02 ___ ! 3.64E+03 +/- 3.60E+02 3.71E+03 +/- 3.70E+02 MS'Si~ II2'0EUhl+~~ <I 2.00E+0i < 1.00E+01 IUO!5I <! 2.00E+0l! ^ AI f60Eidi~~~~~ 7 ~25E+6I7 ~ ~ FE-59 ~] 6.00h}0i[ _[D.00E+01
]((U) EU[1]
CO-60 < 2.00E+01 <g 2.00E+0! < l .00E+01 2
. (N-65 <' 4.00E+01 <j5.00E+01 < 3.00E+01 i ZR-95
(<< 2.00E+01 <! 3.00E+01 <j 2.00E+01 1 RU-103 3.00E+01 _ <j 3.00E+01 < 2.00E+01 i RU-106 < 2.00E*02 < < l.00E+02 _ {2.00E+02 CS-134 < 2.00E+0li < l .00E+01 p <L2.00E+01 iCS-137 < 2.00E+01j _ 2.01 E+01 +/- ___ _<[ 2.00E+01 . _ 1.15 E+01_ BA-140 . l <j 9.00E+01{. g6.00E+01 {J 1.00E+02 (CE-141_ <l 6.00E+01 {_._ <i 5.00E+01 { .
<' l.00E+02j _ L
_. _ <[ 4.00E+01
<! 1.00E+02 l CE-144 1 <{ l.00E+02 _
l _ _.l l L RA-226 l <i 4.00E+02j _<j 4. 00E+02}_L <} 3.00E+02, } j [TH-228 l <I 4.00E+0ll <i 3.00E+0lj_ i _, <j 3.00E+0lj j_ j G 1 C-60
Fermi 2 - 1997Annu 1 Radioactive Effluent Release and l Radiological Environmental Operating Report l l( FERMI 2 I FISH ANALYSIS i i l F-2 (Indicator) (pCi/kg wet) l Nuclideel ' :.10-SEP Catfisha l. n 10-SEP Drum c _ , l ! - u 10-SER: Walleye " l iSR 89 <i 3.00E+0li 2 i <:< 2.00E+01( !
<i 00E+01 l
, SR-90 _2} 7.00E+00 1 5.00E+0_0 < 4.00E+00 l BE-7 7 1.00E+02Q_ _ _ _ 2.60E+02
<{i2.00E+02 < l.00E+02 i .K-40 2.64E+03j+/- 2.42E+03 +/- 2.40E+02 3.28E+03 +/- 3.30E+02 l M@54 ~l < l.00E+0lf <i _2.00 E+01 < l .00E+0_1 CO-58 ~ <g .00E'OI!
1 < 2.00E+01 < l.00E+0i V5-59 <! 3.00E r0ll
~ ~ << 5.00E+01 l7 3.00E+01 l CD-60 i!605+Uii ~ <! 1005I 1 ' ~ -[ }< l.005+01 ZN-65 ((2.00E+0i{
l < 4 _ .00E_+01 j < 3.00E+01 [_<J1.00E+01l l ZR-95 i < < 2.00E+0l} < l.00E+01 RU_-103 [${2.00E+0l{ _ <; _3.00E+0l[ _ < 2.00E+01 [RU-106 <LI.00E 02 , __. <L2.00E+02' l.00E+02 CS-134 <[1.00E+0ll < 2.00E+01 _
< l.00E+01 .CS- 137_ _<{ 2._00E_+01
_ __ _< _2.00E+01' _ . ____. 2.47E+0_1_ +/- 1.05E+01_ BA-140 < 4.00E+01.. < 6.00E+01 < _ 3.00E+01 ICE-141 < 3.00E+01 <} ,4.0dE+01 < 3.00E+01 CE-144 < 8.00E+01 <{ l.00E+02 < 9.00E+01 [ RA-226 < 2.00E+02 <j 3.00E+02 < 3.00E+02
~
! fil-228 < 2.005+01,_ _
<{3TO0E+01 l < 2.00E+01 l,Nuclide6 l - 10-OCT sWhite Bass %.mj gR-89 <L 4.00E401 ' , <{l_.00E+01 lSR-90 _
BE-7 <! 2.00E+02
,K-40 _3.66E+03 .+/- 3.70E+02 < 2.00E+01 l %N-54 $0-58 <i 2.00E+0l ,
IF5-59 <I5.00E+01_ fC6-56 ~< l fU6Ei0i}' [-~~~ IZN-65 <i s.~UO5+6iT l l f2_R-95 _g _2.00 _ _ E+01_! l iRU-103 <I 2.00E+01
;RU-106 <! 2.00E+02:
l JS:iT4-~ T2;06p61ii] [CS-137 <j _2.00E+0l[g l ' !BA-140 <j00E+01 l (CE-141 < 3.00E+01 j CE-144 < 9.00E+01) RA-226 < 3.00E+02"
~
Til-228 < 2.00E+01 j% I l l C-61 w__-_-______-__.
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FEIG1I2 FISil ANALYSIS F-3 (Control) (pCi/kg wet) l'Nuclide ' ; l . u14-MAY Drum 7 :l 14-MAY Silver Bassa , t il4-MAY< Sucker :" :l [SR,89 l $ 6.00E+0lg _ __ . _
<j _2.00E+0l[ __j _ <L2.00E+0ipj ~ ~ ~~ ~ y lSR-90 l < l .00E+01 ' < 6.00E+00. <t 8.00E+00 i ~-'TA! TU 5702 I ~ ~~~
IBE-7 Y AI 160Ei02 A 2.00E+02l ~ h M y 3h{ y9dE+02]_ j 3.04E+d3{T/- [00E[+[62))I 3.iSEjU3Ii/-15.10sid2] _
;MN-54 !_ <: 3.00E40li i <. 1.00E+0li ; <! 2.00E+0lf ^ ^~ !C05f~~ ~ -~~
1 <i ~ 35U0Ei0li ~ Al 2.00E+0l! T ~' ~< I 35 DE+0If ^ [FE 39- <!T00E+01 <l 4.00$+0'l!' <!EUdEA6i l t 6e6 -~ 15 .00E+0i, <: i.00e+0ir- et 2.00E+0i IZS~65 7. <.; 7.00E+0ll. _i< 3_.00E+0l_b~ I <l 6.00E+01 [ZR-95 j <! 3.00E+01{_ <l 2.00E+0ll _ _ {3.00E+01 4 < 4.00E+01
<! 2.00E+01 (RU-106RU-103]_<L _.00E+0l! <! 3.00E+02 < l .00E+02, < 2.00E+02 (CS-134 ~ <' 3.00E+01 ~~ <i~ 15065idii ~ ~ <[ 2.00E+01 ICS-i31- } '~ ~3 365+Ui[~ ~<I '2.bOE+dli~~ ~~2I2305~idi I I . 3[][0@y[, 2 6.0054d1,[ ~ ~ "_] ]}i505i0'2]~[~~~ .
lCE-141 i <i 5.00E+ 0 l i <! 3.00E+0l! i ! <i 6.00E+0lj i
$E{j(({ .pdp0{}))__. ~ ][8'.00,E+01{ !
L<j_l.00E+02_ _ ___]
.RA 7226 l <g_4.00E+02 _
i_ <; 2.00E+02( __ _] <[ 4.00E+02 __ __
%228 ._,__[_ $j 4.00E+01] < 2.00E+01 _
l <j 4.00E+01 l Nuclide- A c 214-MAYc Walleye - cl Il-SEP Walleyet w - l 2 SEP White PerchS sl MJ.89____j__g J.00E+0]( j _ _ l <l 2.00E+0l[ __. lSR-90 ..
- < 4.00E+00. -- - - . .-
I [ 5L_1.00E+01(__
<' 3.00E4 00 - - ..
dC .- 5.00E+00I . - - _ . -
~
MN-Si <F 2.00Ei0'l l < "Y.U0Eidi ~ [ ~ ~ ~ ' E8 2 2I UF30ii i[~~ ~ I <[!~'2.U0E+0li <i 2.00E+01 < 3.00E+01 l [F5[5[
- CO-60
] {] 5.60E+[^
c 2.00E+01i i[ <f 5.00E+0l[ ~[ ~~~[ ]E l7 5 Esbl ] [} [~ ] ~_
<; 2.00E+01 < l
_ J 2.00E+01 ZN-65 , < 4.00E+0l! <! _4.00E+01. < 6.00E+01 ZR-95 [A[l 2.00E+0l! <I2.00E+01 < 3.00E+01 RU-103 <I 3.00E+0l! <! 3.00E+01
<! 2.00E+02 4.00E+01 (( l Rl5IUf]. $ 2.005iO2I ~ . - . - .
3.00E+02 .- l lCS-137 l <! 2.00E+01- I <! 2.00E+01 ' I i <! 3.00E+01 I
~ l <! 55U5+Ul ~
IBA-140 I~< 63 Esdll '~ '} ~ !' Ail 505A01 [CE 141 i~2i~10 dei 0i A 4.00E+0li -[ <I' 6.0DET01
~ ~~
7~~~ I~ hE_-idl] <AI~950E+01((3__ ___ _<<[_ []}
' RA-226. i 3.00E+02; . 1.00E+02{ < 3.00E+02, i 2.005I 2 5.00E+02 i p k2 05+0l!
[ ] }{ <i 3.00E4}0lj j ~' ] }< ]5.00EA01 j _ {~ [ } C-62
1 i O Appendix D Environmental Program Execution 1 l \ \ \ b G O
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report EnvironmentalProgram Execution On occasions, samples cannot be collected. This can be due to a variety of events, such as equipment malfunction, loss of electrical power, severe weather conditions, or vandalism In 1997, missed samples were a result of missing field TLDs, air sampling equipment malfunction, loss of electrical power to air and water sampling equipment, and the freezing of surface water sample lines. The following sections list all missed samples, changes and corrective actions during 1997. These missed samples did not have a significant impact on the execution of the REMP. l L Direct Radiation Monitoring All TLDs are placed in the field in inconspicuous locations to minimize the loss of TLDs due to vandalism. During 1997, two hundred sixty-eight (268) TLDs were placed in the field for the REMP program and all but two TLDs were collected and processed. T-27 was found missing during the first quarter collection and T-30 was found missing during the third quarter collection. Both TLDs were missing as a result of vandalism. O
& Atmospheric Monitoring In the Atmospheric Monitoring program, two hundred and sixty (260) particulate and charcoal cartridges were scheduled to be collected in 1997. All samples were collected j and analyzed except for three (3) particulate filters and four (4) charcoal cartridges.
l e On January 28, air sampler API-4 was found to have insufficient volume, due to loss of power, for analysis. For this reason the first quarter composite sample for this l location is considered to be less than representative. 1 e On August 12, air sampler API-l was found to have insufficient volume, due to equipment malftmetion, for analysis. The sampler was replaced with a spare sampler. I For this reason the third quarter composite sample for this location is considered to be less than representative. l ! ! e On November 25, air sampler API-3 was found to have insufficient volume, due to f loss of power, for analysis. For this reason the fourth quarter composite sample for this location is considered to be less than representative.
. On July 8, the charcoal cartridge for API-3 was inadvertently not collected. The cartridge was collected on July 15 and represents a two week sampling period from July 1 to July 15.
! D-1 l l
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O e During the month of June all air sampling equipment was replaced with new electronic portable samplers. TerrestrialMonitoring During 1997, all scheduled Terrestrial Monitoring samples were collected. There were no changes to the Terrestrial Monitoring program during 1997. Milk Sampling All scheduled milk samples were collected in 1997. Garden Sampling All scheduled garden samples were collected in 1997. GroundwaterSampling All scheduled groundwater samples were collected in 1997. k Aquatic Monitoring During 1997, twenty-four (24) drinking water samples, twenty-four (24) surface water samples, and ten (10) sediment samples were scheduled to be collected. In addition, twenty-three (23) fish samples were collected for the Aquatic Monitoring program. Due { to loss of electrical power, ice and sediment blocking sample lines, and equipment I malfunction, eight (8) grab samples were collected; one drinking water sample and seven l surface water samples. There were no changes to the Aquatic Monitoring program during 1997. I)rinking M'aterSampling e On April 21, drinking water sampler DW-2 was found not operating due to loss of electrical power. A grab sample was taken and the sampler was reset and put back into service. For this reason the second quarter composite sample is considered less than representative. I D-2 l
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O e Both samples, DW-1 and DW-2, collected on May 27, were not analyzed for Gross Beta by the Laboratory Instead the surface water samples were analyzed for Gross Beta. Surface WaterSampling
. On January 13, February 3 and February 17, surface water sampler SW-2 was found not operating due to ice blockage inside the sample line. Grab samples were taken and the sampler was reset and put back into service each time. For this reason the first quarter composite sample is considered less than representative. . On April 7, surface water sampler SW-3 was found not operating due to sediment blockage inside the sample line from dredging operations. A grab sample was taken and the sampler was reset and put back into service. For this reason the second quarter composite sample is considered less than representative. . On June 2, June 9 and December 17, surface water sampler SW-3 was found not operating due to loss of electrical power to the equipment from maintenance activities in the building. Grab samples were taken, power was restored and sampling O equipment was put back into service each time. For this reason the second and forth quarter composite samples are considered less than representative.
Sediment Sampling All scheduled sediment samples were collected in 1997. Fish Sampling All scheduled fish samples were collected in 1997. L l O D-3
- 1. ,
s . 4
~
O Appendix E Effluent and Radwaste Data O O
e t Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O Regulatory Limits for Radioactive Effluents The Nuclear Regulatory Commission limits on liquid and gaseous effluents are incorporated into the Fermi 2 Offsite Dose Calculation Manual. These limits prescribe the maximum doses and dose rates due to radioactive effluents resulting from normal operation of Fermi 2. Tbse limits are described in the following sections. A. Gaseous Effluents I. Dose ate due to radioactivity released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following: a) Noble gases Less than or equal to 500 mrem / year to the total body Less than or equal to 3000 mrem / year to the skin b) Iodine-131. Iodine-133, tritium, and for all radionuclides in particulate O form with halflives greater than 8 days Less than or equal to 1500 mrem / year to any organ. II. Air dose due to noble gases to areas at and beyond the site boundary shall be limited to the following: a) Less than or equal to 5 mrad for gamma radiation Less than or equal to 10 mrad for beta radiation
- During any calendar quarter b) Less than or equal to 10 mrad for gamma radiation Less than or equal to 20 mrad for beta radiation - During any calendar year Ill. Dose to a member of the public from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with halflives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
O E-1
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report O a) Less than or equal to 7.5 mrem to any organ
- During any calendar quarter b) Less than or equal to 15 mrem to any organ - During any calendar year Note: The calculated site boundary dose rates for Fermi 2 are based on identification ofindividual isotopes and on use of dose factors specific to each identified isotope or a highly conservative dose factor. Average energy values are not used in these calculations, and therefore need not be reported.
B. Liquid Effluents J. The concentration of radioactive material released in liquid effluents to
- unrestricted areas shall be limited to ten times the concentrations specified in l Title 10 of the Code of Federal Regulations (10 CFR) Part 20 (Standards for p Protection Against Radiation), Appendix B, Table 2, Column 2 for ld radionuclides other than dissolved or entrained noble gases, as required by the Fermi 2 Offsite Dose Calculation Manual. For dissolved or entrained noble
! gases, the concentration shall be limited to 2E-4 (.0002) microcuries/ml total l activity. This limit is based on the Xe-135 air submersion dose limit converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP) Publication 2. II. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following: a) Less than or equal to 1.5 mrem to the total body Less than or equal to 5 mrem to any organ
- During any calendar quarter b) Less than or equal to 3 mrem to the total body Less than or equal to 10 mrem to any organ - During any calendar year E-2
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report O Measurements and Approximations of Total Activity in Radioactive Effluents As required by NRC Regulatory Guide 1.21, this section describes the methods used to measure the total radioactivity in effluent releases and to estimate the overall errors associated with these measurements. The effluent monitoring systems are described in Chapter 11.4 of tne Fermi 2 Updated Final Safety Analysis Report (UFSAR). A. Gaseous Effluents I. Fission and Activation Gases Samples are obtained from each of the seven plant radiation monitors which continuously monitor the six ventilation exhaust points. The fission and activation gases are quantified by gamma spectroscopy analysis of periodic samples. O The summary values reported are the sums of all fission and activation gases quantified at all monitored release points. II. Radiolodines Samples are obtained from each of the seven plant radiation monitors which continuously monitor the six ventilation exhaust points. The radiciodines are entrained on charcoal and then quantified by gamma spectroscopy analysis. For each sample the duration of sampling and continuous flow rate through the charcoal are used in determining the concentration of radioiodines. From the flow rate of the ventilation system a rate of release can be determined. The summary values reported are the sums of all radioiodines quantified at all continuously monitored release points. 111. Particulate Samples are obtained from each of the seven plant effluent radiation monitors which continuously monitor the six ventilation exhaust points. The particulate are collected on a filter and then quantified by gamma O spectroscopy analysis. E-3
Fermi 2- 1997Annux! Radioactive Effluent Release and Radiological Environmental Operating Report O For each sample, the duration of sampling and continuous flow rate through the filter are used in determining the concentration of particulate. From the j flow rate of the ventilation system a rate of release can be determined.
. Quarterly, the filters from each ventilation release point are composited and then radiochemically separated and analyzed for strontium (Sr)-89/90 using various analytical methods.
The summary values reported are the sums of all particulate quantified at all monitored release points. IV. Tritium Samples are obtained for each of the seven plant effluent radiation monitors , which continuously monitor the six ventilation exhaust points. The sample is l passed through a bottle containing water and the tritium is " washed" out to the collecting water. Portions of the collecting water are analyzed for tritium using liquid scintillation counting techniques. For each sample, the duration O. of sample and sample flow rate is used to determit e the concentration. From the flow rate of the ventilation system a release rate can be determined. \ l The summary values reported are the sums of all tritium quantified at all monitored release points. V. Gross Alpha l The gaseous particulate filters from the seven plant effluent radiation monitors are stored for one week to allow for decay of naturally occurring alpha emitters. These filters are then analyzed for gross alpha radioactivity by gas proportional counting, and any such radioactivity found is assumed to be plant related. The quantity of alpha emitters released can then be determined from sample flow rate, sample duration, and stack flow rate. The summary values reported are the sums of all alpha emitters quantified at all monitored release points. j l l l' O l l E-4
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O B. Liquid Effluents The liquid radwaste processing system and the liquid effluent monitoring system are described in the Fermi 2 UFSAR. Fermi 2 released no radioactive liquid effluents in 1997. l
)
C. Statistical Measurement Uncertainties The statistical uncertainty of the measurements in this section has been calculated
)
and summarized in the following table: ! Measurement Type Sample Type One Sigma Uncertainty Fission and Activation Gaseous 30% Gases l Radiciodines Gaseous 17 % Particulate Gaseous 16 % Tritium Gaseous 30% Gross Alpha Gaseous 16 % Gaseous Release by Individual Nuclide Values in the following tables which are preceded by the "less than" symbol represent the lower limit of detection (LLD) in units of microcuries per cubic centimeter (uCi/cc) for individual samples, and indicate that the nuclide in question was not detected in gaseous effluent smnples in the indicated quarter of 1997. A. Particulate Radionuclides (Curies) i l l! Cr-51 ll <l .7E-13 ll < l .7E-13 ll 4.74E-05 ll 2.17E-05 l Mn-54 l 1.22E-06 l <3.4E-14 l <3.4E- 14 l 2.37E-06 l l Co-58 l <3.4 E- 14 l <3.4E-14 l 1.06E-05 l 2.88E-06 l l Co-60 l 1.51 E-05 l 9.45E-06 l 9.46E-06 l 7.57E-06 l l Na-24 l <l .2 E- 13 l <l .2 E- 13 l 1.09E-04 l <l .2 E-13 l , l Tc-99m l <2.0E-13 l <2.0E-13 l 2.62E-04 l 1.63E-04 l l l Ila-139 l 3.30E-03 l 1.43E-01 l 1.46E+00 l 1.26E+00 l l l La-140 l <l .4E-13 l 1.33E-04 l 1.89E-03 l 1.64E-03 l v l Ba-140 l <7.9E-14 l 8.57E-05 l 1.04E-03 l 8.26E-04 l E-5
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O L Y-91 m ll 2.20E-04 ll 2.32E-02 ll 2.27E-01 ll 1.76E-01 l Sr-91 l <4.8 E- 13 l 1.83E-03 l 2.12E-02 l 1.32E-02 l Sr-92 l <2.6E- 12 l 4.09E-04 l 7.80E-03 l 1.47E-03 l Np-239 l <6.8 E-14 l <6.8 E- 14 l 5.94E-05 l <6.8 E-14 l Rb-38 l <2.6E-08 l 2.01E-02 l <2.6E-08 l <2.6E-08 l Rb-89 l 8.51E-03 l 2.79E-01 l 2.56E+00 l 2.12E+00 l Cs-138 l 6.22E-03 l 1.07E-01 l 9.07E-01 l 9.16E-01 l Cs-139 l <l .2E-08 l < l .2 E-08 l 1.10E+00 l <l .2E-08 l Br-82 l <3.7E- 14 l 3.60E-05 l <3.7E-14 l <3.7E-14 l As-76 l <2.3 E-13 l <2.3 E-13 l 4.08E-04 l 6.96E l Mn-56 l <4.3 E- 12 l <4.3 E- 12 l <4.3 E-12 l 2.78E-04 l Sr-89 l 3.43E-06 l 6.22E-05 l 6.63 E-04 l 5.35E-04 l Sr-90 l <4.0E-16 l 3.85E-07 l 3.29E-06 l 3.12E-06 l Cs-134 l <2.7E-14 l <2.7E- 14 l <2.7E- 14 l <2.7E-14 l Cs-137 l <2.8 E-14 l <2.8 E-14 l <2.8 E-14 l <2.8 E- 14 l Ce-141 l <2.0E-14 l <2.0E-14 l <2.0E-14 l <2.0E-14 l Cc-143 l <l .7E-13 l <l .7E-13 l < l .7E- 13 l <l .7E-13 l Ce-144 l <l.0E-13 l <l.0E-13 l < l .0E-13 l <l.0E-13 l Total l 1.83 E-02 l 5.75E-01 l 6.29E+00 l 4.49E+00 B. Noble Gases ll Kr-85m ll <2.0E-08 l <2.0E-08 ] 5.09E-01 ll 4.35E-01 ll l Kr-87 l <4.3 E-08 l 9.84E-01 l 7.04E+00 l 7.72E+00 l l Kr-88 l <9. l E-08 l <9. l E-08 l 3.75E+00 l 4.40E+00 l l Kr-89 l <5.7E-05 l 5.23 E+00 l 7.90E+01 l 7.89E+01 l l Xe-133 l <5.4E-08 l <5.4 E-08 l 2.07E-01 l 3.82E+01 l l Xe-135 l <2.8 E-08 l 6.61 E-01 l 9.23 E+00 l 2.29E+01 l i l Xe-135m l <l.lE-07 l 2.94E+00 l 2.77E+01 l 6.65E+01 l l l Xe-137 l < l .4 E-05 l 1.53E+01 l 1.37E+02 l 1.46E+02 l l Xe-138 l <2.3E-07 l 6.44E+00 l 7.01 E+01 l 8.30E+01 l l Total l N.A. l 3.16E+01 l 3.35E+02 l 4.48E+02 l O E-6
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological En vironmental Operating Report l C. Radiolodines l L I-131 ll 7.83E-06 ll 2.12E-03 ll 4.72E-03 ll 5.59E-03 ll l I-132 l <5. l E-13 l 5.23E-03 l 2.62E-02 l 2.97E-02 l l l-133 l 2.05E-05 l 7.47E-03 l 2.88E-02 l 3.78E-02 l l l-134 l <l .3 E-I l l 4.22E-03 l 7.16E-02 l 8.29E-02 l , l I-135 l <l .9E-12 l 6.60E-03 l 4.68E-02 l 6.08E-02 l l l Total l 2.83E-05 l 2.56E-02 l 1.78 E-01 l 2.17E-01 l l Shipments of Solid Radwaste Fermi 2 complies with the extensive federal regulations which govern radioactive waste shipments. Radioactive waste shipments from the Fermi 2 site consist of waste generated during water treatment, radioactive trash, irradiated components, and waste oil. Shipment destinations are either licensed burial sites or intermediate processing facilities. Waste shipped to intermediate processing facilities is shipped directly from these facilities to licensed burial sites after processing. The following tables contain estimates of major nuclide composition, by class of waste, of Fermi 2 solid radwaste received at the Barnwell, SC, burial facility in 1997. 1
- a. Spent resins, sludges, etc. (Total of Class A and Class B waste: All spent resin waste in this category was shipped in liigh Integrity Containers. Ash from resin incinerated at an intermediate processing facility and solid residue from waste water l processed at an intermediate processing facility is also included in this category.
Some waste in this category was encapsulated in concrete. All quantities were determined by measurement.) l C-14 4 0.3 ll 1.94E+00 l l l Ce-144 l 0.5 l 3.28E+00 l l Co-57 l <0.1 l 2.50E-03 l l l Co-58 l 0.6 l 3.98E+00 l l Co-60 l 34.2 l 2.15E+02 l j l Cr-51 l <0.1 l 3.35E-01 I i l Cs-134 l 0.8 l 4.96E+00 l Cs-137 l 2.2 l 1.39E+01 - l Fe-55 l 40.9 l 2.57E+02 l Fe-59 l <0.1 l 2.18 E-02 ; O' l 11-3 l <0.1 l 2.36E-01 E-7
t Fermi 2 - 1997 Annual l Radioactive Effluent Release and Radiological Environmental Operating Report O ll Hf-181 ll <0.1 l 3.21 E-02 ll l l l-129 l <0.1 l 2.05E-03 l l l Mn-54 l 7.6 l 4.75E+01 l l Nb-95 l <0.1 l 3.72E-03 l l Ni-59 l <0.1 l 5.45E-04 l l Ni-63 l 2.8 l 1.76E+01 l l Sb-125 l 0.2 l 1.05E+00 l l Sr-90 l <0.1 l 2.08E-02 l l Tc-99 l <0.1 l 3.16E-03 l l l Zn-65 l 9.9 l 6.20E+01 l l Zr-95 l <0.1 l 1.27E-02 l Note: The following is a breakdown of the above quantities into Class A and Class B waste as required by Fermi 2 Technical Specifications. Class A quantities: Consists of dewatered resin, ash from resin incineration, solid residue from processing contaminated water, etc. (total volume: 101 m') ll C-14 ll 0.7 ll 1.94E+00 l-l Ce-144 l 0.6 l 1.55E+00 l l Co-57 l <0.1 l 2.50E-03 l l Co-58 l 0.5 l 1.45E+00 l l Co-60 l 33.8 _l 9.27E+01 l l Cr-51 l 0.1 l 3.35E-01 l l l Cs-134 l 0.3 l 7.68E-01 l I l Cs-137 l 1.5 l 4.24E+00 l l Fe-55 l 41.6 l 1.14E+02 l l Fe-59 l <0.1 l 2.18E-02 l l l H-3 l <0.1 l 2.31 E-01 l l Hf-l 81 l <0.1 l 3.21E-02 l l I-129 l <0.1 l 1.95E-03 l l Mn-54 l 6.9 l 1.88E+01 l l Nb-95 l <0.1 l 3.72E-03 l l l Ni-59 l <0.1 l 5.45E-04 l l Ni-63 l 3.0 l 8.20E+00 l l Sb-125 l 0.4 l 1.05E+00 l l Sr-90 l <0.1 l 7.87E-03 l l Tc-99 l <0.1 l 2.54E-03 l l Zn-65 l 10.5 l 2.89E+01 l l l Zr-95 l <0.1 l 1.27E-02 l l E-8
Fermi 2 - l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O 3 Class B Quantities: Consists of dewatered resin (total volume: 11.8 m ) C-14 ll <0.1 ll 2.83E-03 [ l Ce-144 l 0.5 l 1.73E+00 l l Co-58 l 0.7 l 2.53E+00 l l Co-60 l 34.4 l 1.22E+02 l l Cs-134 l 1.2 l 4.19E+00 l l Cs-137 l 2.7 l 9.66E+00 l l Fe-55 l 40.4 l 1.43E+02 l l H-3 l <0.1 l 5.13E-03 l l I-129 l <0.1 l 1.02E-04 l l Mn-54 l 8.1 l 2.87E+01 l l Ni-63 l 2.6 l 9.35E+00 l l l Sr-90 l <0.1 l 1.29E-02 l l Tc-99 l <0.1 l 6.23E-04 l l Zn-65 l 9.3 l 3.31E+01 l
- b. Dry compressible waste, contaminated equipment, etc. (All waste in this category was Class A waste, was shipped in strong tight containers, and was classified as dry active waste (DAW). After incineration by an intermediate processor, some of the residue from this waste was solidified in concrete. All quantities were determined by measurement. Total volume: 43.9 m')
1 Ag-110m ll <0.1 ll 4.01 E-04 ll l C-14 l 0.5 l 1.50E-02 l l Ce-144 l <0.1 l . l .35 E-03 l l Co-57 l <0.1 l 9.40E-06 l l Co-58 l 1.0 ! 2.74E-02 l l Co-60 l 11.3 3.20E-01 l l Cr-51 l 37.8 1.07E+00 ~ l Cs-134 l 1.4 3.85E-02 l Cs-137 l 1.8 4.98E-02 l Fe-55 l 41.5 1.17E+00 l Fe-59 l 0.5 1.30E-02 l H-3 l 0.5 1.52E-0.2 l l-129 l <0.1 4.91E-04 l Mn-54 l 1.4 3.96E-02 l Nb-95 l <0.1 3.45E-11 O V l l Ni-59 Ni-63 l l
<0.1 1.0 1.57E-04 2.83E-02 E-9
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O Sb-124 ll <0.1 ~ ll ' l.63E-03 il l Sb-125 l 01 3.98E-03 l Sr-89 l <o l 9.02E-10 l l Sr-90 l <o I 2.28E-05 l l Tc-99 l <0.1 5.89E-04 l l l Zn-65 l 11 3.04E-02 l
- c. Irradiated components, control rods, etc.: None in 1997.
l l l O l i f i E-10 l
)
O Appendix F Quality Assurance Data O O ! i
I ( Fermi 2- l997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O V
- QualityAssurance An important part of the effluent and environmental monitoring programs at Fermi 2 is Quality Assurance (QA). QA is a program that provides a method to check the adequacy and validity of the monitoring programs. The QA program accomplishes this by independent annual audits by qualified personnel, strict adherence to written procedures, and good record keeping practices. The QA program is designed to identify possible deficiencies in the monitoring programs so that corrective actions can be initiated promptly.
The QA program at Fermi 2 is conducted in accordance with the guidelines specified in NRC Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs". At Fermi 2 the QA program contains three data comparison programs; (1) Interlaboratory Comparison Program, (2) NRC TLD comparison program, and (3) Independent blind spiked cross check program. The following sections describe and present the 1997 results of these programs. O f 1 l l v(D I F-1 (
Fermi 2- l997 Annail Radioactive Effluent Release and Radiological Environmental Operating Report D 0 Interlaboratory Comparison Programsfor 1997 The Environmental Protection Agency (EPA) for many years has been administrating an Interlaboratory Comparison Program for NRC licensee environmental laboratories, free of charge. However, due to reductions in Federal funding and staffing, the EPA has reduced this service to supply only water samples as of December 31,1995. Section 10.3 of the Offsite Dose Calculation Manual (ODCM) and Chapter 2, Section 4.10.3 of the Radiation Protection Conduct Manual requires the environmental laboratory l contracted by the Radiological Environmental Monitoring Program (REMP) to _ participate in a Commission approved interlaboratory comparison program. Detroit Edison contracts Teledyne/ Brown Engineering to perform the analysis of its environmental samples. Teledyne currently participates in the EPA's program and has contracted Analytics, Inc. to supply additional samples that are no longer supplied by the EPA. In an interlaboratory comparison program, participant laboratories receive from the EPA or a commerce source, environmental samples of known activity concentration for analysis. After the samples have been analyzed by the laboratory, the manufacturer of the g sample reports the known activity concentration of the samples to the laboratory. The Q laboratory compares its results to the reported concentrations to determine any significant deviations, investigates such deviations if found, and initiates corrective action if necessary. Participation in this program provides assurance that the contract laboratory is capable of meeting accepted criteria for radioactivity analysis. In 1997, Teledyne/ Brown Engineering perfonned forty-eight (48) analyses of l environmental samples from the EPA and thirty-seven (37) analyses of samples prepared L by Analytics Inc.. All but four of the EPA samples results were within i 3 sigma control L limits. All but one of the Analytics samples were within acceptable limits of the known values. The results are shown in the following tables and all deviations, investigations and corrective actions taken by Teledyne/ Brown Engineering are described in the foot notes. i F-2
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiologictr: % vironmental Operating Report C EPA INTERLABORATORY COMPARISON PROGRAM 1997 Table F-1 Collection Teledyne Brown Date Media Nuclide EPA Result (a) Engineering Result (b) Deviation (c) 01/17/97 Water Sr-89 12.0 5.0 10.00
- 1.00 -0.69 Sr-90 25.0
- 5.0 25.00 i 1.00 0.00 01/31/97 Water Gr-Alpha 5.2 5.0 8.10
- 0.89 1.00 Gr-Beta 14.7 t 5.0 15.00 1.00 0.10 02/07/97 Water I-131 86.0
- 9.0 106.00 4.36 3.85 (d) 02/14/97 Water Ra-226 5.9 0.9 5.27
- 0.23 -1.22 Ra-228 8.2 2.1 8.40
- 0.30 0.16 03/07/97 Water H-3 7900.0
- 790.0 7366.67 378.59 -1.I7 04/15/97 Water Gr-Beta 102.1* 15.3 103.33
- 5.77 0.14 Sr-89 24.0
- 5.0 23.00
- 1.00 -0.35 Sr-90 13.0* 5.0 12.67 1.15 -0.12 Co-60 21.0 5.0 22.67
- 0.58 0.58 Cs 134 31.0
- 5.0 28.67
- 0.58 -0.81
_ q Cs 137 22.0
- 5.0 24.67 1.53 0.92 s Gr-AIpha 48.0
- 12.0 54.67
- 1.53 0.96 Ra-226 13.0
- 2.0 13.00 1.00 0.00
. Ra-228 3.1* 0.8 4.87 0.12 3.82 (e) 06/06/97 Water Co-60 18.0 5.0 19.00
- 0.00 0.35 Zn-65 100.0
- 10.0 99.33
- 1.15 -0.12 Cs-134 22.0
- 5.0 18.67
- 1.15 -1.15 Cs-137 49.0* 5.0 48.67
- 0.58 -0.12 Ba-133 25.0
- 5.0 22.33 + 2.52 -0.92 06/13/97 Water Ra-226 3.0 0.5 3.43 0.49 1.50 Ra-228 3.1* 0.8 3.43
- 0.23 0.72 06/18/97 Water Gr Alpha 3.1* 5.0 2.93 t 0.2 ' -0.06 Gr-Beta 15.1
- 5.0 14.00
- 1.00 0.38 07/11/97 Water Sr-89 44.0 5.0 38.33
- 1.53 -1.96 Sr-90 16.0 5.0 25.00
- 0.00 3.12 (f) 08/08/97 Water H-3 11010 1101.0 12000.00
- 0.00 1.56 09/12/97 Water Ra-226 20.0
- 3.0 20.00 i 1.73 0.00 Ra 228 8.0 2.0 7.40
- 0.17 -0.52 09/19/97 Water 1-131 10.0 6.0 11.00 0.00 0.29 O
V F-3
Fermi 2- 1997 Annut! Radioactive Effluent Release and Radiole ;lcal Environmental Operating Report v Table F-1 (cont) Collection Teledyne Brown Date Media Nuclide EPA Result (a) Engineerir.g Result (b) Deviation (c) 10/21/97 Water Gr-Alpha 49.9
- 12.5 45.67
- 1.15 -0.59 Ra-226 5.0
- 0.8 5.90
- 0.10 1.95 Ra-228 5.0
- 1.3 4.27
- 0.12 -0.98 Gr-Beta 143.4 21.5 136.67
- 5.77 -0.54 Sr-89 36.0
- 5.0 36.00
- 1.00 0.00 Sr-90 22.0* 5.0 21.67 2.08 -0.12 Co-60 10.0
- 5.0 10.67 0.58 0.23 Cs-134 41.0* 5.0 41.33 0.58 0.12 Cs-137 34.0 5.0 36.00
- 1.00 0.69 l
10/31/97 Water Gr-Alpha 14.7 5.0 19.67
- 1.53 1.72 l Gr-Beta 48.9 5.0 50.67
- 3.51 0.61 11/07/97 Water Co-60 27.0 i 5.0 25.00
- 1.00 -0.69 Zn-65 75.0 8.0 71.00
- 3.61 -0.87 Cs-134 10.0 5.0 10.67
- 0.58 0.23 Cs-137 74.0
- 5.0 76.00 1.00 0.69 Ba-133 99.0 10.0 78.67 + 0.58 -3.52 (g)
Footnotes: (a) EPA Results-Expected laboratory precision (1 sigma). Units are pCi/ liter for water and milk except K is in mg/ lite 'Jnits are total pCi for air particulate filters. (b) Teledyne Results - Average
- one sigma. Units are pCi/ liter for water and milk except K is in i
mg/ liter. Units are total pCi for air particulate filters. (c) Normalized deviation from the known. j (d) Erroneously high reading of the stable iodine content by ion specific electrode occurred, causing an erroneously low chemical yield. If the electrode reading is ignored, the average I 131 result becomes 90 pCi/l, in good agreement with the given value. An erroneous electrode reading can be caused by certain chemical species in the sample, such as sulfide. We will investigate suspiciously high electrode readings by performing a gravimetric yield on the sample without the addition of iodide carrier or the I 131 content of active samples can also be verified by performing a gamma spectral analysis. l (e) An investigation discovered a low chemical yield on one sample and the loss of another during
' analysis, in the future we will repeat analyses of samples with yields less than 85%.
(f) Error apparently caused by insufficient training. The strontium separation chemistry was performed on 7/22/97 by a summer employee. Initial results for the three samples did not agree well. so all were remilked by a senior analyst. This was insufficient to correct the problem. In-house QC samples showed satisfactory results at this time. There will be additional qualification of analysts according to performance on in-house blanks and spikes. (g) An investigation is being conducted and Teledyne will report the results shortly. F-4
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report ANALYTICS CROSS CHECK COMPARISON PROGRAM 1997 Table F-2 Collection Analytics Teledyne Brown Date Media Nuclide Result Engineering Result (a) Ratio (b) 03/20/97 Milk 1-131 20 i 1 18 1 0.90 Cc-141 2321 12 232 i 23 1.00 Cr-51 387i 19 381 38 0.98 Cs-134 143i 7 132 i 13 0.92 Cs-137 114 1 6 128 i 13 1.12 Co-58 79 i 4 89 i 9 1.I3 Mn-54 176i 9 1951 20 1.11 Fe-59 1441 7 161i 16 1.12 Zn-65 1651 8 1711 17 1.04 Co-60 176 i 9 179i I8 1.02 03/20/97 Milk Sr-89 25 i i 13 i 3 0.52 (c) Sr-90 19 i 1 16 i 1 0.84 1 06/19/97 Air Filter - Ce-141 132 1 7 143i 8 1.08 ) Cr-51 198i 10 229t 17 1.16 ) l Cs-134 81 i 4 74 i 4 0.91 Cs-137 115 i 6 143 1 8 1.24
^ Co-58 77 1 4 89 i 5 1.16 i Mn-54 84 1 4 1021 6 1.21 Fe-59 75 1 4 98 i 6 1.31 Zn-65 1391 7 1881 11 1.35 1 Co-60 1041 5 113 i 7 1.09 06/19/97 Cartridge 1-131 88 i 4 106 i 6 1.20 06/19/97 Air Filter Sr-90 96 i 5 88 i 5 0.92 l l l 06/19/96 Air Filter Gr-Alpha 93 i 5 1031 6 1.11 I l Gr-Beta 193 i 10 210 i 6 1.09 j 09/18/97 Milk 1-131 87 1 4 97 1 10 1.11 Ce-141 77 i 4 83 i 8 1.08 Cr-51 304 i 15 323 1 40 1.06 Cs-134 102 i 5 98 i 10 0.96
,. Cs-137 107 i 5 117 i 12 1.09 l Co-58 60 i 3 64 i 6 1.07 88 1 4 Mn-54 99 i 10 1,13 Fe-59 119i 6 132 1 13 1.11 Zn-65 196i 10 218i 22 1.11 Co-60 1971 10 2091 21 1.06 09/18/97 Milk Sr-89 15 1 14 1 0.93 Sr-90 14 1 18 1 1.29 F-5
Fermi 2- 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report
\
Footnotes: (a) Teledyne Results - counting error is two standard deviations. Units are pCi/ liter for water and milk. For gamma results, if two standard deviations are less than 10%, then a 10% error is
. reported. Units are total pCi for air particulate filters.
(b) Ratio of Teledyne Brown Engineering to Analytics results. (c ) Caused by incorrect rinsing of the strontium extraction column. Additional training was conducted on 9/5/97 and was documented in the analyst's training file. Subsequent tests on two milk samples spiked with Sr-89 produced good results.
)
t I t
-(
r. l-F-6
Fermi 2 - 1997 Annu:I Radioactive Effluent Release and \ Radiological Environmental Operat!.sg Report 1 { Fermi 2 andNRC TLD Intercomparison The U.S. Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network is operated in cooperation with the State of Michigan's Division of Radiological Health. This program was established in August 1979 by the NRC Office of Inspection and Enforcement (IE) to measure ambient radiant radiation levels around NRC licensed facilities and to provide the NRC staff with prompt, independent data in emergency response and assessments. As part of Fermi 2's REMP Qualhy Control program, TLDs l that are co-located with the NRC TLDs are compared with each other to determine if there is any significant difference between the two direct radiation monitor programs. The NRC maintains 41 TLD locations around Fermi 2, and 21 are co-located with Detroit Edison TLDs. The TLDs are collected by State of Michigan representatives and are analyzed independently of the Fermi 2 TLDs. The results from the NRC monitoring I program are published quarterly in NUREG 0837 titled NRC TLD Direct Radiation ! Monitoring Network. The data for 1997 is tabulated in the tables below. Only the first, second and third l quarters of NRC data was available for comparison. The standard deviation for all data ranged from 0.1 to 1.8, which indicates a good correlation between the two programs. First Quarter (mR/std Qtr) Table F-3 Station Numbers Fermi 2 NRC Std. Dev. T1 NRC1 14.0 10.6 1.7 T4 NRC36 14.9 11.9 1.5 T5 NRC37 15.5 13.6 0.9 T6 NRC38 14.3 16.4 1.1 T12 NRC25 14.0 13.9 0.1 T13 NRC23 15.7 16.7 0.5 T14 NRC22 14.8 16.2 0.7 j T15. NRC21 14.9 12.8 1.0 l T19 NRC16 16.2 16.0 0.1 T20 NRC14 17.7 N/D - l T21 NRC15 14.5 13.9 0.3 T22 NRC13 15.2 15.6 0.2 T23 NRC11 15.5 12.3 1.6 j l T24 NRC9 14.5 11.7 1.4 j T27 NRC17 N/D N/D - T28 NRC32 14.4 14.7 0.1 l T30 NRC18 15.0 15.1 0.0 i T32 NRC29 15.3 13.2 1.1 i T33 NRC28 14.9 13.1 0.9 T35 NRC26 14.3 13.8 0.3 j m T36 NRC40 15.2 14.4 0.4 yb i F-7 i l l 1
Fermi 2- 1997Annux! l Radioactive Effluent Release and ) Radiological Environmental Operating Report Second Quarter (mR/std Qtr) , Table F-4 i Station Numbers Fermi 2 NRC Std. Dev. T1 NRC1 14.8 11.2 1.8 T4 NRC36 13.4 11.6 0.9 ' T5 NRC37 15.7 14.5 0.6 T6 NRC38 10.5 14.0 1.8 T12 NRC25 12.4 N/A - T13 NRC23 14.3 16.3 1.0 T14 NRC22 14.5 17.3 1.4 T15 NRC21 12.6 12.8 0.1 T19 NRC16 14.7 17.5 1.4 T20 NRC14 15.8 17.8 1.0 T21 NRC15 12.6 13.8 0.6 T22 NRC13 13.2 15.3 1.1 T23 NRC11 13.4 14.1 0.4 T24 NRC9 15.8 13.2 1.3 T27 NRC17 11.6 12.6 0.5 l T28 NRC32 13.0 13.6 0.3
- l. T30 NRC18 14.3 13.6 0.4 T32 NRC29 14.7 15.4 0.3 T33 NRC28 14.6 13.2 0.7
,_3 T35 NRC26 13.6 13.2 0.2 T36 NRC40 14.3 17.8 1.8 Third Quarter (mR/std Qtr)
Table F-5 Station Numbers Fermi 2 NRC Std. Dev. T1 NRC1 13.3 11.8 0.7 T4 NRC36 15.2 13.8 0.7 T5 NRC37 15.9 15.3 0.3 j j T6 NRC38 12.9 16.4 1.8 ' T12 NRC25 14.2 15.4 0.6 T13 NRC23 16.3 19.1 1.4 T14 NRC22 16.4 17.2 0.4 T15 NRC21 14.6 13.4 0.6 T19 NRC16 18.5 18.6 0.0 T20 NRC14 19.3 19.7 0.2 T21 NRC15 15.5 15.0 0.3 T22 NRC13 15.2 16.5 0.6 T23 NRC11 16.1 14.4 0.9 T24 NRC9 15.3 13.0 1.2 T27 NRC17 13.4 14.0 0.3 T28 NRC32 14.5 15.7 0.6
- T30 NRC18 N/A N/A -
1 T32 NRC29 16.6 15.3 0.7 ! T33 NRC28 14.6 15.0 0.2 T35 NRC26 15.1 14.7 0.2 (n T36 NRC40 16.0 15.9 0.1 F-8
l Fermi 2- l997Arnual l Radioactive Effluent Release and Radiological Environmental Opercting Report p !b Independent BlindSpiked Cross Citeck Program Analytics, Inc. supplies Detroit Edison's environmental laboratory, TeledyndBrown 3 Engineering, with blind spiked samples containing strontium-89 (Sr-89), stron ium-90 (Sr-90), and iron-55 (Fe-55) on a quarterly basis. As part of the environmental QA q program, these samples are analyzed by the vendor laboratory and compared to the l known values. To determine if the laboratory results are in agreement with Analytics' known value, a ratio is calculated using the following formula: Teledyne value / Analytics value = Ratio The closer the ratio is te (1.0) one, the better tne agreement between the two values. To determine if the ratio falls within acceptable limits, upper and lower limits are established using the sample resolution (supplied by Analytics) and the criteria in following table. Cross Check Agreement Criteria Table F-6 seasResolutiona + _ Agreement;Criteriada less than 4 N/A 4-7 0.5 - 2.0 8-15 0.6 -1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25 greater than 200 0.85 - 1.18 For 1997, all spiked samples analyzed by Teledyne/ Brown. Engineering were in i agreement with Analytics' known values. The results of the Independent Blind Spiked { Cross Check Program are shown in the following tables and control charts. { l l o F-9
Fermi 2 - l997 Annu11 Radioactive Effluent Release and i Radiological Environmental Operating Report l Fermi 2 1997 Environmental Laboratory Cross Check Program Sr-89 Spiked Samples Teledyne Analytics Quarter Value (uCi/cc) Value (uCi/cc) Ratio 1 st 6.40E-03 6.06E-03 1.06 2nd 5.30E-03 5.90E-03 0.90 3rd 2.20E-03 2.31 E-03 0.95 i 4th 5.90E-03 6.31 E-03 0.94 Resolution = 17 Agreement Criteria = 0.75 > = Ratio < = 1.33 1.4 -- Uppw Uma 1.3 - 1.2 - e 1.1 - 1.0 g 0.9
, +
- p. -
F O.8 - 0.7 -- % Uma 0.6 0.5 -- l 0.4 , ; 1st 2nd 3rd 4th Quarter O F-10
Fermi 2 - l997 Annu11 Radioactive Effluent Release and Radiological Environmental Operating Report
\ Fermi 2 1997 1
l Environmental Laboratory Cross Check Program Sr-90 Spiked Samples Teledyne Analytics Quarter Value (uCi/cc) Value (uCi/cc) Ratio 1 st 3.50E-04 3.36E-04 1.04 2nd 3.90E-04 4.15 E-04 0.94 3rd 2.10E-04 2.13E-04 0.99 4th 3.80E-04 3.79E-04 1.00 Resolution = 12.5 Agreement Criteria = 0.6 > = Ratio < = 1.66 l 1.8 - Upper Limit 1.6 - 0 1.4 -
.I h 1.2-e" o~ O 'm /"
- 1 l
- 0. 8 -
ac 0.6 Lower Limit 0.4 0.2 , . 1 st 2nd 3rd 4th l Quarter ; O j 1 F-11
.____________-_O
Fermi 2 - l997 Annu11 Radioactive Ef]Tuent Release and Radiological Environmental Operating Report Fermi 2 1997 Environmental Laboratory Cross Check Program Fe-55 Spiked Samples Teledyne Ananlytics Quarter Value (uCi/cc) Value (uCi/cc) Ratio 1 st 4.20E-04 4.72 E-04 0.89 2nd 3.60E-04 3.88E-04 0.93 3rd 1.90E-04 2.48E-04 0.77 4th 2.60E-04 2.81 E-04 0.93 Resolution = 12.5 Agreement Criteria = 0.6> = Ratio < = 1.66
'O Upper unt 1.6 1.4 f
i 1.2 -
- 7. 1.0 -
g 0.8 -
/.
k m O.6 Lower Umt 0.4 0.2 0.0 , 1st 2nd 3rd 4th Quarter O F-12
l l O Appendix G Meteorological Data ! 1 i l i I i O l O
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il uO T mfafl r eEt W Fe e n v N 0 1 2 6 5 1 0 1 1 0 0 0 0 0 5 3 i t c n m N ao or ii d v W 0 0 3 8 7 3 1 0 0 0 0 0 2 2 a n N REl a W i c 6 g o N 0 0 4 5 1 1 1 1 1 5 0 0 0 0 0 4 l o W i d a R W0 0 2 5 1 0 8 2 0 0 0 0 0 7 2 W 2 S 0 1 3 2 1 1 1 2 1 3 0 0 0 0 0 4 W W 1 0 3 4 3 5 8 2 1 0 0 0 2 7 S W 0 2 S 0 0 0 0 2 1 0 0 0 0 0 0 1 S S 0 0 1 2 5 8 3 0 0 0 0 0 9 1 E O S 0 0 2 3 2 1 0 0 0 0 0 0 8 S E 0 0 1 6 6 8 0 0 0 0 0 2 S 1 2 E S 1 0 3 5 7 4 1 3 0 0 0 0 0 3 3 E E 0 0 0 2 5 1 1 9 6 0 0 0 0 3 3 E N 1 1 1 3 1 1 9 2 2 0 0 0 0 0 3 E E 0 0 2 4 8 9 6 0 0 0 0 0 9 B N 1 3 E N 0 0 4 4 7 0 1 3 1 0 0 0 0 9 2 s s N l a Cy N 0 1 0 4 1 8 3 0 0 0 0 0 7 1 t i l i b t a S H) P 5 5 5 5 5 5 5 5 5 5 5 5 M( 7 0 2 4 6 8 1 4 8 3 0 9 2 1 1 2 3 3 4 2 de 1 O G pe o t o t t o t o t o t o t o t o t o t o t o o lo S t 1 1 1 1 1 l d 6 1 1 1 1 1 O 7 5 5 5 5 5 5 5 5 5 5 a ba in 0 2 4 6 8 1 4 8 3 0 9 t o 2 TW 3 3 T 1 1 1
i l - mfafl r eEt W Fe en 2 3 0 9 _ v N 0 0 8 1 1 1 6 0 0 0 0 0 4 i t cn m N a o or ii d v W 0 2 8 8 1 3 0 0 0 0 3 an N 1 1 1 0 4 RE l a W i c g o N 0 0 7 8 1 5 1 6 1 7 0 0 0 0 0 3 6 l i o W d a R W1 2 0 1 5 1 0 1 5 1 7 0 0 0 0 0 0 6 W 2 5 5 8 1 6 5 2 2 1 3 1 0 0 0 0 7 H W 0 1 5 5 3 2 0 3 8 9 1 0 0 0 2 S 1 9 W 3 2 9 5 S 0 1 5 1 1 1 4 1 0 0 0 0 5 S S 0 0 4 1 1 9 1 8 1 0 0 0 0 0 3 4 E 2 S 3 O 1 1 0 1 1 1 8 0 0 0 0 0 0 3 S E 0 1 6 9 5 5 4 2 0 0 0 0 2 S 1 2 6 E S 0 1 1 1 2 6 1 1 5 2 0 0 0 0 7 4 E E 0 0 3 6 8 9 1 4 2 4 1 0 0 0 5 6 E N 1 0 4 4 0 1 2 1 2 7 0 0 0 0 0 4 E E 0 0 4 4 1 1 8 2 0 0 0 0 0 C N 1 1 2 6 E N 0 1 4 4 9 1 1 1 5 0 0 0 0 5 3 s s N l a Cy N 1 1 4 5 5 5 2 2 0 0 0 0 0 3 4 t i l i b t a S ) H P 5 5 5 5 5 5 5 5 5 5 5 5 M( 7 0 2 4 6 8 1 4 8 3 0 9 2 1 1 1 2 3 3 4 3- de O G pe ie d b n S o t O o t 6 7 t 1 5 o o t 1 5 t 1 5 o t 1 5 o t 1 5 o t 1 5 o t 1 5 o t 1 5 o t 1 5 o t 1 5 o l t a a i 0 2 4 6 8 1 4 8 3 2 0 3 9 3 o TW 1 1 1 f l
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6 1 E 4 N 2 1 4 1 0 3 9 5 6 4 8 1 3 1 a 0 0 7 E 1 E 2 4 8 1 4 3 0 3 0 0 0 0 5 D N 1 8 9 6 3 9 2 E 3 N 0 4 6 3 7 4 2 3 5 3 8 1 0 0 0 0 6 s s N 1 l a Cy N 1 6 8 2 3 3 8 3 9 4 8 2 0 0 0 0 5 6 1 t i l i b t a S H) P 1 5 5 5 5 5 5 5 5 5 5 5 5 3( 7 0 2 4 6 8 1 4 8 3 0 9 2 1 1 1 2 3 3 4 4 de O G pe o t o t t o o t t o t o t o o o o o o S t t t t t le d 6 7 1 5 1 5 1 1 1 5 5
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O Appendix H Glossary of Terms O O
Fermi 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report (3 Glossary of Terms V activation products Radioactive material that is created when stable substances are bombarded by neutron radiation. ALARA Acronym for"As Low As Reasonably Achievable," a basic concept of radiation protection that specifies radioactive discharges from nuclear plants and radiation exposure to personnel be kept as far below regulatory limits as possible. alpha particle A positively. charged particle ejected from the nuclei of some radioactive elements. It is identical to a helium nucleus, and Las a mass number 4 and a charge of +2. It has low penetrating power and short range. Alpha particles are easily stopped by a thin layer of paper or fabric, or the dead outer layer of skin cells. atom The smallest portion of an element that shares the general characteristics of that element and cannot be divided or broken up by chemical means. An atom has a nucleus, composed of positively charged protons and electrically neutral neutrons, around which orbit negatively charged electrons. background radiation The radiation in man's environment, including cosmic rays from space and radiation that exists everywhere--in the air, in the earth, and in man-made materials that surround us, in the United States, most people receive 100 to 250 millitern of background radiation per year. Common sources of man-made background radiation include consumer products such as color televisions, radium dials on watchu or clocks, smoke detectors, coast-to-coast jet flights, construction materials, and certain foods.
- beta particle A charged particle emitted from a nucleus during radioactive decay, with a mass equal to 1/1837 that of a proton. A negatively charged beta particle is identical to an electron. A positively charged beta particle is called a positron. Beta particles are easily stopped by a thin sheet of metal, plastic or wood.-
composite sample A sample made of grab or continuous samples combined to represent a particular location or a set period of time (e.g., four weekly water samples combined to make one monthly composite sample). O. H-1 n_---.- _ _ - - _ - _ . - - __ . _ . _ . - _ _ - _ . - - _ _ . _ . - . - - . . - - _ - . . -
- Fermi 2-l997 Annual Radioactive Effluent Release and b Radiological Environmental Operating Report ;
continuous sample A continuous sample is one that collects samples non-stop and is used to evaluate conditions over a specific period of time. The typical continuous samples collected at Fermi 2 include TLDs and air samples.
)
controllocation A sample collection location generally more than 10 miles away from Fermi ?. Analyses of samples collected at control locations l provide information on normally-occurring background radiation and radioactivity. j coolant A fluid, usually water, used to cool the nuclear reactor core by transferring the heat energy emitted during the fission process into the fluid medium. cosmic radiation Penetrating ionizing radiation, both particulate and electromagnetic, that originates in space. critical receptor The segment of the population that could receive the greatest radiation dose. curie (Ci) The basic unit used to describe the intensity of radioactivity in a sample or material. One curie is equal to 37 billion disintegrations l l O per second, which is approximately the rate of decay of one gram of radium. A curie is also a quantity of any radionuclides that decays at a rate of 37 billion disintegrations per second. l~ dose A quantity (total or accumulated) ofionizing radiation received. l dose rate The radiation dose delivered per unit of time. Measured, for example, in rem per hour. effluent In general, a waste material, such as smo?,e, liquid, industrial refuse, or sewage discharged into the environment. Effluents discharged from the Fermi 2 Nuclear Power Plant include liquid and gaseous media containing extremely small concentrations of radionuclides. i The concentrations released are well below the limits established by the NRC. i electron . An elementary particle with a negative charge and a mass 1/1837 l l L that of the proton. Electrons orbit around the positively charged L nucleus. In an electrically neutral atom, the negative charges of the electrons are balanced by the positive charges of the protons. H-2 __-____________________-__-_______-___-____---_________________-_________________-___-__-_____-_______-a
Fermi 2 - 1997 Annux! Radioactive Effluent Release and Radiological Environmental Operating Report L exposure The absorption of radiation or ingestion of a radionuclides. Acute exposure is generally accepted to be a large exposure received over a shon period of time. Chronic exposure is ww level exposure received during a lifetime or over a long period of time. external radiation Exposure to ionizing radiation when the radiation source is located outside of the body. fission The splitting or breaking apart of a heavy atom into two or more fragments. When a heavy atom such as uranium it., split, large amounts of energy in the form of heat, radiation, and one or more neutrons are released. fission gases Those fission products that exist in the gaseous state. Primarily the noble gases (krypton, xenon, etc.). fission products The fragments formed by the fission of heavy elements, plus the nuclides formed by the fragments' radioactive decay. gamma ray High energy, short wavelength electromagnetic radiation emitted from the nucleus of a radioactive atom. Gamma radiation frequently accompanies alpha and beta emissions and always , accompanies fission. Gamma rays are very penetrating but may be shielded by dense materials, such as lead or concrete. Gamma rays are similar to X-rays, but are usually more energetic. grab samples A grab sample represents a single sample collected in a finite period oftime. half-life The time in which half the atoms of a particular radioactive substance disintegrate to another nuclear form. Measured half-lives vary from millionths of a second to billions of years. indicator location A sample collection locrt.icn generally within 10 miles of Fermi 2. Analyses from samples collected at indicator locations provide information on the radiological impact, if any, Fermi 2 has on the surrounding environment. intemal radiation Nuclear radiation resulting from radioactive substances in the body. p Some examples are iodine-131 deposited in the thyroid gland and strontium-90 deposited in bone tissue. l. l' ionizing radiation Any radiation capable of displacing electrons from atoms or molecules, thereby producing ions. For example, alpha and beta g particles, gamma and X-rays, neutrons, and ultraviolet light. O 11-3
l l Fermi 2- 1997 Annual Radioactive Effluent Release and ) Radiological En vironmental Operating Report l 0 isotope . One of two or more atoms with the same number of protons, but different numbers of neutrons in their nuclei. Thus, carbon-12, carbon-13, and carbon-14 are isotopes of the element carbon; the numbers denoting their approximate atomic weights. Isotopes have the same chemical properties, but often different physical properties (for example, carbon-12 and carbon-13 are stable, while carbon-14 j is radioactive). lower limit of detection The smallest amount of sample activity that will give a net count, (LLD) for which there is a confidence at a predetermined level, that the activity is present. The LLD is actually a measure of the ability of an individual analysis to detect extremely minute amounts of radioactivity in a sample. I t I
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! mean Arithmetic average. In a series of 3 or more numbers, the mean is calculated by the equation: X = (xl + x2 + xn)/n ) Where n is the number of observations in a data set, and x1, x2, ...xn are the various observations. microcurie One-millionth of a curie. O D millirem One-thousandth of a rem. l
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1 neutron An uncharged elementary particle with a mass slightly greater than ! that of a proton, and found in the nucleus of every atom heavier than hydrogen-l. noble gas A gaseous chemical element that does not readily enter into chemical combination with other elements. An inert gas such as krypton, xenon, neon or argon. nuclide A general term referring to all known isotopes, both stable (279) and unstable (about 5000), of the chemical elements. picocurie One-trillionth of a curie. quality control (QC) The field check or verification of work while it is being performed to assure that the task is properly done. I radiation The conveyance of energy through space, for example, the radiation of heat from a stove. Ionizing radiation is the emission of particles I or gamma rays from the nucleus of an unstable (radioactive) atom as a result of radioactive decay. O I L H-4
Ferrni 2 - 1997 Annual Radioactive Effluent Release and Radiological Environmental Operating Report O radioactive decay The decrease in the amount of radioactivity with the passage of time due to the spontaneous emission of particulate or gamma radiation from the atomic nuclei. radioactivity The spontaneous emission of radiation from the nucleus of an unstable isotope. Radioactivity is a process and radiation is the product. radioiodine A radioactive isotope of iodine. The radioisotopes of iodine are among the most abundant of the fission products. All told, 27 isotopes of iodine are known to exist, but only the naturally-occurring iodine-127 is stable. Of the remaining 26 radioisotopes, 12 are produced during fission and these have half-lives ranging from 1.5 seconds to 16 million years, radioisotope The term " radioisotope" is used to specifically describe the relationship between an element and a radioactive isotope of that element. For instance, in describing Cs-137, one could state that Cs-137 is a radioisotope of cesium (stable). rem Acronym for " roentgen equivalent man". The unit of dose of any O ionizing radiation that produces the same biological effect as a unit of absorbed dose of X-rays, terrestrial radiation The portion of natural radiation (background) that is emitted by naturally occurring radioactive materials in the earth. tritium . A radioactive isotope of hydrogen (one proton, two neutrons). Because it is chemically identical to natural hydrogen, tritium can easily be ta).en into the body by any ingestion path. Tritium decays by beta emission. Its radioactive half-life is about 12-1/2 years. D H-5 -__ _ _ _ _ _ _ _}}