ML20029D660

Annual Radiological Environ Operating Rept for Davis Besse Nuclear Power Station Jan-Dec 1993.

ML20029D660
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Site:	Davis Besse
Issue date:	12/31/1993
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Davis.Besse Nuclear Power Station 1993 Annual Radiological Environmental Operating Report ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT for Davis-Besse Nuclear Power Station January 1,1993 to December 31,1993 Prepared by:

Radiation Protection Section Davis-Besse Nuclear Power Station Toledo Edison Company Toledo, Ohio I

April 1994  ;

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9405090201 940429

[DR ADOCK 05000346 PDR

Davis-Besse Nuclear Power Station t993 Annual Radiological Environ.T. ental Operating Report TABLE OF CONTENTS Title Page List of Tables iv List of Figures v Executive Summary vii INTRODUCTION '

Fundamentals 1 Radiation and Radioactivity 2 Interaction with Matter 3 Quantities and Units of Measurement 5 Sources of Radiation 7 Health Effects of Radiation 9 Health Risks 10 Benefits of Nuclear Power 11 Nuclear Power Production 11 Station Systems 17 Reactor Safety and Summary 20 Radioactive Waste 20 Description of the Davis-Besse Site 22 The 1993 Summary of Radioactivity Released in Liquid and Gaseous Ef11uents 24 Protection Standards 24 Limits 24 Sources of Radioactivity Released 25 Noble Gas 25 Iodine and Particulates 26 i

Davis-Besse Nuclear Power Station 1993 Anmcal lladiological Environmental Operating lleport Title Page a

Tritium 26 Processing and Monitoring 26 Exposure Pathways 27'  ;

Dose Assessment 29 ,

Results 29 References 31 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Introduction 33 Preoperational Surveillance Program 33 Operational Surveillance Program Objectives 34 Quality Assurance 34 Program Description 36 Sample Analysis 39 Sample History Comparison 41 1993 Program Deviations 44 Atmospheric Monitoring 45 Terrestrial Monitoring 51 Aquatic Monitoring 63' Direct Radiation Monitoring 74 Conclusion 86 References 87 I

Land Use Census Program Design 90 Methodology 90

} Results 91 l

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Davis-Besse Nuclear Power Station 1993 Annual Radiological Environmental Op: rating Report Title Page a

NON RADIOLOGICAL ENVIRONMENTAL PROGRAMS Meteorological Monitoring 97 Marsh Management 102 Water Treatment 104 Chemical Waste Management 110 Waste Minimization and Recycling 114 APPENDICES Appendix A: Interlaboratory Comparison Program Results 116 Appendix B: Data Reporting Conventions 128 Appendix C: Efiluent Concentration Limit of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas 131 Appendix D: REMP Sampling Summary 133 1

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Davis-Besse Nuclear Power Station 1993 Annual Radiological Environmental Operating Report List of Tables Table Page Title Number Number Risk Factors 1 10 Dose Limits to a Member of the Public 2 25 Annual Dose to the Public Due to Radioactivity Released in Gaseous and Liquid Effluents 3 30 Sample Codes and Collection Frequencies 4 37 Sample Collection Summary 5 38 Radiochemical Analyses Performed on REMP Samples 6 40 Air Monitoring Locations 7 47 Milk Monitoring Locations 8 53 Groundwater Monitoring Locations 9 54 Broadleaf Vegetation and Fruit Locations 10 55 Animal / Wildlife Feed Locations 11 56 Wild / Domestic Meat Locations 12 57 Soil Locations 13 59 Treated Surface Water Locations 14 64 Untreated Surface Water Locations 15 66 Shoreline and Bottom Sediment Locations 16 68 Fish Locations 17 70 Thermoluminescent Dosimeter Locations 18 76 Closest Exposure Pathways Present in 1993 19 93 Pathway Locations and Corresponding Atmospheric Dispersion (X/0) and Deposition (D/0) Parameters 20 96 Summary of Meteorological Data Recovery for 1993 21 99 Summary of Meteorological Data Measured For 1993 22 100 iv 1

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Davis-Besse Nuclear Power Station 1993 Annual Radiological Environmental Op: rating Report List of Figures Title Figure Page Number Number The Atom 1 I Principle Decay Scheme of the Uranium Series 2 3 Range and Shielding of Radiation 3 4 Sources of Radiation 4 8 Fission Diagram 5 12 Fuel Rod, Fuel Assembly, Reactor Vessel 6 13 Schematics of DBNPS 7 16 Map of Area Surrounding Davis-Besse 8 22 External Exposure Pathway 9 28 Internal Exposure Pathway 10 28 Airborne Particulate: Gross Beta 11 46 Airborne Sampling i a:ations on Davis-Besse Site 12 48 Airborne Sampling Locations within a Five Mile Radius 13 49 Airborne Sampling Locations within a Twenty-Five Mile Radius 14 50 Milk Samples: Strontium 90 15 52 Groundwater Sample: Gross Beta 16 54 Soil Samples: Cesium-137 17 58 Terrestrial Sampling Location on the Davis-Besse Site 18 60 Terrestrial Sampling Location within a Five Mile Radius 19 61 Terrestrial Sampling Location within a Twenty Five Mile Radius 20 62 Treated Surface Water Samples: Gross Beta 21 64 Untreated Surface Water Samples: Gross Beta 22 66 Fish Samples: Gross Beta 23 69 Aquatic Sampling Location on the Davis-Besse Site 24 71 v

Davis Besse Nuclear Power Station 1993 Annual Radiological Environmental Operating Report Figure Page Title .

Number Number Aquatic Sampling Locations within a Five Mile Radius 25 72 Aquatic Sampling Locations within a Twenty-Five Mile Radius 26 73 TLD Dose Comparison Since 1973 27 74 Comparison of NRC vs. Davis-Besse TLDs Since 1988 28 75 Direct Radiation Sampling Locations on the Davis-Besse Site 29 83 Direct Radiation Sampling Locations within a Five Mile Radius 30 84 Direct Radiation Sampling Locations within a Twenty-Five Mile Radius 31 85 Land Use Census Map 32 92 Water Treatment Plant Schematics 33 105 vi

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l Davis-Besse Nuclear Power Station 1993 Annual Radiological Environmental Operating Report i

Executive Summary The Annual Radiological Environmental Operating Report is a detailed report on the i Environmental Monitoring Programs conducted at the Davis-Besse Nuclear Power Station from January I through December 31,1993. This report meets all of the requirements in Regulatory Guide 4.8, Davis-Besse Technical Specifications 6.9.1.10, and Davis-Besse Offsite Dose Calculation Manual 7.1. Reports included are the l Radiological Environmental Monitoring Program, Land Use Census, and the l Non-Radiological Environmental Programs, which consist of Meteorological Monitoring,

! Marsh Management, Water Treatment, Chemical Waste Management , and Waste Minimization and Recycling.  !

1 Radiological Environrnental Monitoring Program  ;

! The Radiological Environmental Monitoring Program (REMP) is established to monitor the radiological condition of the environment around Davis-Besse. The REMP is conducted in accordance with Regulatory Guide 4.8, Davis-Besse Technical l Specification 6.8.4.e and the Davis-Besse Offsite Dose Calculation Manual Section 6.0.

This program includes the sampling and analysis of environmental samples and ,

evaluating the effects of releases of radioactivity on the environment.

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Radiation levels and radioactivity have been monitored within a 25 mile radius around Davis Besse for more than 21 years. The REMP was established at Davis Besse about five years before the Station became operational. This program provided data on background radiation and radioactivity which is normally present in the area.

Davis-Besse has continued to monitor the environment by sampling air, groundwater, milk, edible meat, egg, fruit and vegetables, animal feed, soil, drinking water, surface water, fish, bottom and shoreline sediment, and by measuring radiation directly.

Samples are collected from both indicator and control locations. Indicator locations are within approximately 5 miles of the site and are expected to show naturally occurring radioactivity plus any increases of radioactivity that might occur due to the operation of Davis-Besse. Control locations are farther away from the Station and are expected to indicate the presence of only naturally occurring radioactivity. The results obtained from the samples collected from indicator locations are compared with the results from those collected from control locations and with the concentrations present in the environment before Davis-Besse became operational. This allows for the assessment of any impact the operation of Davis-Besse might have had on the surrounding environment.

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Davis-Besse Nucicar Power Station 1993 Annual Radiological Environmental Operating Report More than 2000 radiological environmental samples were collected and analyzed in 1993. Only 27 intended samples were not collected during 1993, an explanation for l

missing these samples is discussed in chapter two.

The results of the REMP indicate that Davis-Besse continues to be operated safely and in accordance with applicable federal regulations. No measurable increase in background l radiation is attributed to the operation of Davis-Besse. The sampling results are divided into four sections: atmospheric monitoring, terrestrial monitoring, aquatic monitoring and  ;

direct radiation monitoring. j

• Samples of air are collected to monitor the atmosphere. The 1993 results are similar to those observed in preoperational and previous operational programs. Only ,

background and fallout radioactivity normally present in the environment was detected and only at normal concentrations.

• Terrestrial monitoring includes analysis of milk, groundwater, meat, fruits, vegetables, animal feed, and soil samples. The results of the analyses of the other terrestrial samples also indicate concentrations of radioactivity similar to previous )

years and indicate no buildup of radioactivity due to the operation of Davis-Besse. j Aquatic monitoring includes the collection and analysis of drinking water, untreated l surface water, fish and shoreline sediments. The 1993 results of analysis for fish, j untreated surface water, drinking water and shoreline sediment indicate normal background concentration of radionuclides and show no increase or buildup of radioactivity due to the operation of Davis-Besse.

• Direct radiation averaged 14.4 mrem /91 days at indicator locations and 15.5 mrem /91 days at control locations. This is similar to results of previous years.

The 1993 operation of Davis-Besse caused no significant measurable in the concentrations of radionuclides in the environment and no adverse effect on the quality of the environment. All radioactivity released in the Station's effluents was well below the applicable federal regulatory limits. The estimated radiation dose to the general public due to the operation of Davis-Besse in 1993 was also well below all applicable regulatory limits.

In order to estimate radiation dose to the public, the pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is performed as part of the REMP. During the census, Davis Eesse personnel travel every public road within a five mile radius of the Station to locate the radiological exposure pathways. The one pathway of particular interest is the pathway that, for a specific radionuclide, provides the greatest dose to a sector of the population, and is called the critical pathway. The critical receptor for 1993 remained unchanged from the 1990 Land Use Census. This receptor is reached via a cow / milk pathway at 4,270 meters in the west-southwest sector.

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Davis.Besse Nuclear Power Station 1993 Annual Radiological Environrnental Op: rating Report Non-Radiological Environmental Programs I

+ Meteorological Monitoring The Meteorological Monitoring Program at Davis-Besse is part of a program for evaluating the radiological effects of the routine operation of Davis Besse on the surrounding environment. Meteorological monitoring began in October,1968.

l Meteorologicd instruments are monitored daily by trained personnel.

Meteorological data recorded at Davis-Besse include wind speed, wind direction, sigma theta (standard deviation of wind direction), ambient temperature, differential temperature, dew point and precipitation. Two instrument equipped meteorological l 2

towers are used to collect data. Data recovery for the six instruments required to be 1 l operational by Davis Besse Technical Specifications was 100%  !

i + Marsh Management l

Toledo Edison and the Cleveland Electric Illuminating Company co-own the Navarre Marsh which they lease to the U.S. Fish and Wildlife Service, who manage it as part of the Ottawa National Wildlife Refuge. Davis Besse personnel are responsible for i

inspecting the marsh and reporting on its sta:us monthly.

Special projecis conducted in 1993 included song bird and Canada goose banding. In

! 1993,11,554 individual birds were banded. In addition, unwanted and disruptive plant j species, such as purple loosestrife (Lythrum salicaria) and the giant reed (Phragmities australisi), were controlled in order to enhance the ability of the marsh to support the

, resident wildlife. Several artificial nesting structures were maintained throughout the year.

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+ Water Treatment l

Davis-Bese uses Lake Erie as a source of water for its Water Treatment Plant. The water is treated onsite to provide domestic water and to produce high purity water for use in the Station's cooling systems. During 1993, a baffle system was installed in the water

treatment plant clearwell in order to comply with new regulations and construction of a

! sodium hypochlorite addition system was started.

1 Toledo Edison personnel collected and analyzed water samples from various locations on the station as part of the Zebra Mussel Control Program. Results show that the mussel population was lower than last year.

Wastewater generated by site personnel is treated onsite at the Davis-Besse Waste Water Treatment Plant. The wastewater is processed and then pumped to a basin where further reduction in solid content takes place. Following a settling period, the water is discharged, along with other station waste water, back to Lake Erie. During 1993, Waste 4

Water Treatment Plant (WWTP) Number I was taken out of service because of ix

Davis Besse Nuclear Power Station 1993 Annual Radiological Environmental Op: rating Report decreased flow to the plant . WWTF Number 1 is scheduled to be cleaned and painted during 1994. It will be maintained in operable condition as a backup to WWTP Number 2.

During June the total daily suspended solids limit was exceeded at Outfall 601. The limit was exceeded because of a high algae population. Algae plays an important role in the tertiary cleanup of waste water but a high population has adverse effects on waste water treatment.

+ Chemical Waste Management The Chemical Waste Management Program at Davis-Besse was developed to ensure that the offsite disposal of non-radioactive hazardous and nonhazardous chemical wastes is performed in accordance with all applicable state and federal regulations. Chemical waste disposal vendors contracted by Davis-Besse use advanced technology for offsite disposal of chemical wastes in order to protect human health and the environment.

In ' 993, as a result of waste minimization efforts,1,200 pounds of hazardous waste (used solvents) and 1,600 gallons of waste oil were sent to recycling firms or fuel blenders for reuse as thermal energy fuels.

As required by Superfund Amendment and Reauthorization Act (SARA), Davis-Besse reported hazardous products and chemicals to local fire departments and local and state planning commissions. As part of the program to remove PCB fluid from Davis-Besse, all electrical transformers have been retrofilled and reclassified an non-PCB transformers.

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Waste Minimization and Recycling The Waste Minimization and Recycling Program at Davis-Besse began in 1991 with the collection and recycling of paper. This program was expanded and reinforced during 1993 to included the recycling of paper, aluminum cans, cardboard, and metal.

Throughout the year a total of 3,250 pounds of aluminum cans was collected and donated to the Boy Scouts for recycling. Also collected were 68,704 pounds of paper and 40,000 pounds of card'ooard. The scrap metal collected onsite was sold to scrap companies. This program will be exnanded in 1994.

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l Davis-Besse Nuclear Fewer Station 1993 Annual Radiological Environmental Operating Report i

Appendices l

! I l Appendix A contains results from the Interlaboratory Comparison Program required by l Davis Besse Technical Specification.s. Samples with known concentrations of.

l radioisotopes are prepared by the Environmental Protection Agency (EPA), and then sent

(with information on sample type and date of collection only) to the laboratory

contracted by the Davis-Besse Nuclear Power Station to analyze its REMP samples. The

results are then checked by the EPA to ensure consistency with the known values. The j results from both the contracted laboratory and the EPA are provided in Appendix A.

l Appendix B contains data reporting conversions used in the REMP at Davis-Besse. The l j appendix provides an explanation of the format and computational methods used in

reporting REMP data. Information on counting uncertainties, Efauent Concentration i

limits (EC) and the calculations of averages and standard deviations is also provided. 4 i )

l Appendix C.!ists the maximum permissible concentrations of alpha and beta emitting I radioisotopes and of certain other radioisotopes in air and water samples. These I concentrations are taken directly from the Code of Federal Regulations, and provide 3 comparison values for actual REMP sampling results for 1993. i j Appendix D provides a REMP sampling summary from 1993. The appendix provides a

listing of the following for each sample type

i l j the number and types of analyses performed,.

j the lower limit of detection for each analysis, j

• the mean and range of results for control and indicator locations,

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• the mean, range, and location description for the location with the highest annual mean, 5

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• the number of non-routine results.

i For detailed studies, Appendix D provides more specific information than th.it listed in

Chapter 2 of this report. Additionally, more specific information is submitted to the NRC l in Attachment 1. This attachment is not distributed with the remainder of the Annual

Radiological Environmental Operating Report due to its technical nature. The information presented in Appendices A through D were provided by Teledyne Isotopes

Midwest Laboratories in their Final Progress Report to Toledo Edison (February 1994).

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Davis-Ikw Nuclear Power Station lW3 Annual Radiologic 11 Environmental Opemting Repon l Introduction Coal, oil, natural gas and hydropower are used to run this nation's electric generating stations; however, each method has its drawbacks. Coal-fired power can affect the environment through mining, acid rain and air pollution. Oil and natural gas are in limited supply and are therefore costly, and hydropower is limited due to the environmental impact of damming our waterways and the scarcity of suitable sites in our country.

Nuclear energy provides an attemate source of energy which is readily available. The operation of nuclear power stations has a very small impact on the environment. In fact, the Davis-Besse Nuclear Power Station is surrounded by hundreds of acres of marshland which make up part of the Ottawa National Wildlife Refuge, the only national refuge in Ohio. In order to more fully understand this unique source of energy, background information on basic radiation characteristics, risk assessment, reactor operation and effluent control is provided in this chapter.

l l Fundamentals l

l The Atom i All matter consist of atoms. Simply described, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, j

! respectively (Figure 1). 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 or more smaller electrons. In an electrically neutral atom the negative charges of 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 i the densely packed protons from repelling each other, preventing the nucleus from breaking apart.

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elcarnilly neutral neutmns and me or more negatively charged electors orbiting the nucleus.

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Pmtons and neutmrs are nearly identiall in size and / \

weight. while cadi is about 2000 times heavict than an clearon.

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I i Davis-Ihme Nuclear Power Station 1993 Annual Ihliologica Envinmmental Operating Reprt Radiation and Radioactivity Isotopes and Radionuclides A group ofidentical atoms, containing the same number of protons, make up an element. In fact, the number of protons an atom contains determines its chemical identity. For instance, all atoms with one

! proton are hydrogen atoms and all atoms with eight protons are oxygen atoms. However, the number of- J neutrons in the nucleus of an element may vary. Atoms with the same number of protons, but different numbers of neutrons are called isotopes. Different isotopes of the same element have the same chemical propenies and many are stable or nonradioactive. An unstable or radioactive isotope of an element is called a radioisotope, radioactive atom, or radionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. De excess energy is usually due to the excess number of neutrons in the nucleus. I Radionuclides can be naturally occurring such as uranium-238, beryllium-7 and potassium-40, or man-made, such as iodine 131, cesium 137, and cobalt-60.

Radiation 1

Radiation is simply the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation is another type of radiation and has similar properties to those of the examples listed above. Ionizing radiation consists of both electromagnetic radiation and paniculate radiation. Electromagnetic radiation is energy with no )

measurable mass that travels with a wave-like motion through space. Included in this category are gamma l rays and X rays. Paniculate radiation consists of tiny, fast moving particles which, if uninhibited. travel in !

a straight line through space. He three types of particulate radiation of concem to us are alpha panicles, made up of 2 protons and 2 neutrons; beta particles, which are essentially free electrons (electrons not attached to an atom); and neutrons. He properties of these types of radiation will be described more fully in the Range and Shielding section.

Radioactive Decay Radioactive atoms attempt to reach a stable, non-radioactive state through a process known as radioactive decay. Radioactive decay is the release of energy from an atom through the emission of ionizing radiation.

Radioactive atoms may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several daughter products which eventually result in a stable atom. He loss of energy and/or matter through radioactive decay may transform the atom into a chemically different element. For example, when uranium 238 decays, it emits an alpha panicle and, as a result, the atom loses 2 protons and 2 neutrons. As discussed previously, the number of protons in the nucleus of an atom determines its chemical identity. Berefore, when the uranium-238 atom loses the 2 protons and 2 neutrons, it is transformed into an atom of thorium-234. norium-234 is one of the 14 successive daughter products of uranium-238. Radon is another daughter product, and the series ends with stable lead-206. His example is pan of a known mdioactive decay series, called the uranium series, which begins with uranium 238 and ends with lead 206 (Figure 2).

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Half-life Most radionuclides vary greatly in the frequency v/ith which their atoms release radiation. Some l

radioactive materials, in which there are only infrequent emissions, tend to have a very long half-lives.

Those radioactive materials that are very active, emitting radiation more frequently, tend to have comparably short half-lives. The length of time an atom remains radioactive is defined in temis of half-lives. Half-life is the amount of time required for a radioactive substance to lose half its activity through the process of radioactive decay. Half-lives vary from millionths of a second to millions of years.

Interaction With Matter Ionization Through interactions with atoms, alpha, beta, and gamma radiation lose their energy. When these forms of radiation interact with any form of material, the energy they impart may cause atoms in that material to become ions, or charged particles. Normally, an atom has the same number of protons as electrons. Thus, the number of positive and negative charges cancel, and the atom is electrically neutral. When one or more electrons are removed an ion is formed.

lonization is one of the processes which may result in damage to biological systems.

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11rvis.Ibse Nedcar Power Station 1(M3 Annual Radiologic 11 Envuonmental Opemting Rep 1rt Range and Shielding I

Particulate and electromagnetic radiation each travel through matter differently because of their different '

I properties. Alpha particles contain 2 protons and 2 neutrons, are relatively large, and carry an electrical charge of +2. Alpha particles are ejected from the nucleus of a radioactive atom at speeds ranging from 2,000 to 20,000 miles per second. However, due to its comparatively large size, an alpha panicle usually does not travel very far before it loses most ofits energy through collisions and other interactions with atoms. As a result, alpha particles can easily be stopped by a sheet of paper or a few centimeters of air (Figure 3).

1 Beta particles are very small, and compamtively fast particles, traveling at speeds near the speed oflight (186,000 miles per second). Beta particles have an electrical charge of either +1 or -1. Because they are so small and have a low charge, they do not collide and interact as often as alpha particles, so they can travel farther. Beta particles can usually travel through several meters of air, but may be stopped by a thin piece of metal or wood.

Gamma rays are pure energy that travel at the speed oflight. 'They have no measurable charge or mass, and generainy travel much farther than alpha or beta particles before being absorbed. After repeated interactions, the gamma ray finally loses all ofits energy and vanishes. The range of a gamma ray in air varies, depending on the ray's energy and interactions. Very high energy gamma radiation can travel a considerable distance, whereas low energy gamma mdiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of lead or concrete may be needed to effectively shield gamma rays.

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I Figure 3: As radiation travels, it aillides and interacts with other atoms and loses cncrgy. Alpha putides avi be stopped by a j sheet of p1per, and beta pr.icles by a thin sheet of aluminum. Gamma radiation is shicided by highly dense materiah such as lead. while hydrogervus materiah (thme containing hydmgen atoms), sudi as water and axurte, are usal to stcp neutnxs.

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4 11r.4Ikw Nelcar lbwer StatKx1 IW3 Annual lb:!k)kyiml Dwin timental Operating Reput Neutrons come from several sources, including the interactions of cosmic radiation with the earth's atmosphere and nuclear reactions within nuclear power reactors. However, neutrons are not of environmental concem since nuclear power stations are designed to keep neutrons within the containment building.

Because neutrons have no charge, they are able to pass very close to the nuclei of the material through which they are traveling. As a result, neutrons may be captured by one of these nuclei or they may be deflected. When deflected, the neutron loses some of its energy. After a series of these deflections, the neutron has lost most of its energy. At this point, the neutron moves about as slowly as the atoms of the material through which it is traveling, and is called a thermal neutnm. In comparison, fast neutrons are much mor energetic than thermal neutrons and have greater potential for causing damage to the material through which they travel. Fast neutrons can have fmm 200 thousand to 200 million times the energy of thermal neutrons.

Neutron shielding is designed to skiw fast neutrons and absorb thermal neutrons. Neutron shielding materials commonly used to slow nuetrons down are water or polyethylene. He shield is then completed with a material such as cadmium, to absorb the now thermal neutrons. At Davis-Besse, concrete is used to form an effective neutron shield because it contains water molecules and can be easily molded around odd shapes.

Quantities and Units of Measurement There are several quantities and units of measurement used to describe radioactivity and its effects. Eree terms of particular usefulness are activity, absorbed dose, and dose equivalent.

Activity: Curie Activity is the number of atoms in a sampie that disintegrate (decay) per unit of time. Each time an atom disintegrates, radiation is emitted. %e curie (Ci) is the unit used to describe the activity of a material ar.d indicates thenite at which the atoms of a radioactive substance are decaying. One curie indicates the disintegration of 37 billion atoms per second.

A curie is a unit of activity, not a quantity of material. Rus, the amount of material required to produce one curie varies. For example, one gram (1/28 th of an ounce) of radium-226 is the equivalent of one curie of activity, but it would take 9,170,000 grams (about 10 tons) of thorium-232 to equal one curie.

Smaller units of the curie are often used, especially when discussing the low concentrations of radioactivity detected in environmental samples. For instance, the microcurie (uCi)is equal to one millionth of a curie, while the picoeurie (pCi) represents one trillionth of a curie.

Absorbed Dose: Rad Absorbed dose is a term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and electromagnetic radiation. He rad (radiation absorbed dose) is the unit used to measure the absorbed dose. It is defined as the energy ofionizing 5

IXwis-Ihac Nele:r Iker Station IW3 Annual Radskpcal Environmental Operating itepin radiation deposited per gram of absorbing material (1 rad = 100 erg /gm). he rate of absorbed dose is usually given in rad /hr.

If the biological effect of radiation was directly proporti inal to the energy deposited by radiation in an organism, the rad would be a suitable measurement of the biokigical effect. However, biological effects depend not only on the total energy deposited per gram of tissue, but on how this energy is distributed aking its path. Experiments have shown that some types of radiation are more damaging per unit path of travel than others. Rus, another unit is needed to quantify the biological damage caused by ionizing radiation.

Dose Equivalent: Rem Biological damage due to alpha, beta, gamma and neutron radiation may result from the ionization caused by these radiations. Some types of radiation, especially alpha particles which cause dense local ionization, can result in up to 20 times the amount of biological damage for the same energy impaned as do gamma or X rays. Herefore, a quality factor must be applied to account for the different ionizing capabilities of various types of ionizing radiation. When the quality factor is multiplied by the absorbed dose, the result is the dose equivalent, which is an estimate of the possible biological damage resulting from extxisure to a particular type ofionizing radiation. He dose equivalent is measured in rem (mdiation equivalent man).

An example of this conversion from absorbed dose to dose equivalent uses the quality factor for alpha radiation, which is 20. Rus, I rad of alpha radiation is approximately equal to 20 rem. Beta and gamma radiation each have a quality factor of 1, therefore one rad of either beta or gamma radiation is approximately equal to one rem. Neutrons have a quality factor ranging from 2 to 10. One rem produces the same amount of biological damage, regardless of the source. In terms of radiation, the rem is a .

I relatively large unit. Herefore, a smaller unit, the millirem, is often used. One millirem (mrem) is equal to 1/1000 of a rem.

Deep Dose Equivalent (DDE) l Deep dose equivalant is the measurement of dose from extemal sources that an individual might receive l from radiation and radioactive material. It is what is measured and n corded by film badges and/or thermoluminescent dosimeter (TLD). For example, at Davis Besse or at any hospital that has x- ray equipment, you will see people wearing film badges or TLDs. Rese instruments are worn to measure deep dose equivalent (DDE).

Committed Effectived Dose Equivalent (CEDE)

Committed effective dose equivalent is the sum of the the products of the committed dose equivalent to the organ or tissue multipled by the organ or tissue weighting factor.

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Davis-Ibse Nudex 1%cr Stathn 1993 Annual Radiok viad Envinomental Opemiing iteput  !

l Total Effective Dose Equivalent (TEDE) a i Total effective dose equivalent means the sum of the deep dose equivalent (for dose from sources external l to the body) and the committed effective dose equivalent (for intemal dose). Previously, the dose to the individual was tracked separately for intemal and extemal exposures but under the new 10 CFR20 they are combined to obtain TEDE. De NRC limits occupational dose to a radiation worker to five rem (5000

mrem)TEDE per year.

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Sources of Radiation

Background Radiation

Radiation is not a new creation of the nuclear power industry; it is a natural occurrence on the earth. It is j probably the most " natural" thing in nature. Mankind has always lived with mdiation and always will. In fact, during every second of life, over 7,000 atoms undergo radioactive decay " naturally" in the body of the average adult. In addition, radioactive decay also occurs naturally in soil, water, air, and space. All these i common sources of radiation contribute to the natural background radiation to which everyone is exposed.

He earth is constantly showered by a steady stream of high energy gamma rays and particulate radiation 1

that come from space, known as cosmic radiation. The atmosphere shields us from most of this mdiation, q but everyone still receives atx>ut 20 to 50 mrem each year from this source. The thinner air at higher altitudes provides less protection against cosmic mdiation. So people living at higher altitudes or even

flying in an airplane are exposed to more cosmic radiation. Radionuclides commonly.found in the l atmosphere as a result of cosmic ray interactions include beryllium 7, carbon-14, tritium (H-3), and j sodium-22.

i l l Another common, naturally occurring radionuclide is potassium 40. About one-third of the extemal and i intemal dose from naturally occurring background radiation is attributed to this radioactive isotope of

, potassium.

1 1

> The major source of background radiation is radon, a colorless, odorless, radioactive gas that results from the decay of radium-226, a member of the uranium 238 decay series. Since uranium occurs naturally in all 1 j soils and rocks, everyone is continuously exposed to radon and its daughter products. Radon does not )

typically pose a health hazard unless it is allowed to concentrate in a confined area, such as buildings, J basements or underground mines. Radon-related health concems stem from the exposure of the lungs to j this radioactive gas. Radon emits alpha radiation when it decays, this can cause damage to intemal tissues 1

j when ingested or inhaled. As a result, exposure to the lungs is of greatest concem, especially as the only i recognized health effect associated with exposun: to radon is an increased risk of lung cancer. According

, to the National Council on Radiation Protection and Measurement (NCRP), over half of the radiation dose

! the average American receives is attributed to radon.

1

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i i

' 7 l

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Davs-Iksse Nuclear Power Statim 1993 Annual itxliologiall Environmental Opemting Thptrt Sources of Radiation Radon 54 % Consumer Products 3% \

l Medical X rays 11 % i l

uclear Medicine 1 4% )

Cosmic Internal Others 1 8%

TN 8%  ;

1 on== a== w s==a a m m = = = == .,* ens -

Figure 4:The most signifiarit annual dose reaived by an individualof the public is that recived from naturally ocarnng i rachn. A very small annual dose to the public results from electncity prtxluad by nuclear power plant.

Futher information on radon, its measurement, and actions to reduce the radon concentration in buildings l can be obtained by contacting the state radon program office at the following address:

i l

Radiological Health Program Ohio Department of Health  ;

P.O. BOX 118 Columbus, Ohio 43266-0118 (614) 481-5800 (800)523-4439(in Ohio Only)

Man-Made Radiation In addition to naturally occurring radiation and radioactivity, people are also exposed to man-made radiation. The largest sources of exposure include medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer products such as televisions, smoke detectors, and fertilizers.

Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include strontium-90, cesium-137, and tritium. Less than one percent of the annual dose a member of the public receives is a result of having electricity generated by nuclear power.

8

Dans-lhw: Nudes ther Staion t993 Annual Rmliologim! Envimamenuil Op; rating Repn Health Effects of Radiation The effects of ionizing radiation on human health have been under study for more than eighty years.

Scientists have obtained valuable knowledge through the study of laboratory animals that were exposed to radiation under extremely controlled conditions. However, it has been difficult to relate the biological effects of irradiated laboratory animals to the potential health effects on humans.

he effects of radiation on humans can be divided into two categories, somatic and genetic. Somatic effects are those which develop in the directly exposed inividual, including a developing fetus. Genetic effects are those which are observed in the offspring of the exposed individual.

Somatic effects can be divided further into acute and chronic effects. Acute effects develop shortly after exposure to large amount of mdiation. Much study has been done with human populations that were exposed to ionizing radiation under various circumstances. Rese groups include the survivors of the atomic bomb, persons undergoing medical mdiation treatment, and early radiologists, who accumulated large doses of radiation, unaware of the potential hazards.

Chronic effects are a result of exposure to radiation over an extended period of time. Examples of such groups are luminous clock dial painters, who ingested large amounts of radium by " tipping" the paint brushes with their lips, and uranium miners, who inhaled large amounts of radioactive dust while mining pitchblende (uranium ore). He studies performed on these groups have increased our knowledge of the .

health effects from large doses of radiation received over long periods of time. I Continuous exposure to low levels of radiation may produce gradual somatic changes over extended period time. For example, someone may develop cancer from man-made radiation, background radiation, or some other source not related to radiation. Because all illnesses caused by low level radiation can also be caused by other factors, it is virtually impossible to determine individual health effects of low level radiation. To be conservative, we assume the health effects resulting from low doses of radiation occur proportionally to those observed following large doses of radiation. Some radiation scientists agree that this assumption over- estimates the risks associated with a low level radiation exposure. The effects predicted in this manner have never been actually observed in individuals exposed to low level radiation. herefore, the most likely somatic effect of low level radiation is believed to be a small increased risk of cancer.

Genetic effects may occur as a result of ionizing radiation interacting with the genes in the human cells.

Radiation (as well as common chemicals) can cause physical changes or mutations in the genes.

Chromosome fibers can break and rearrange, causing interference with the normal cell division of the chromosome by affecting their number and structure. A cell can rejoin the ends of a broken chromosome, but if there are two breaks ek>se enough together in space and time, the broken ends from one break may join incorrectly with those from another. This can cause transkx:ations, inversions, rings, and other types of structural rearrangements. When this happens, new mutated genes are created. Radiation is not the only mechanism by which such changes can occur. Spontaneous mutations and chemically induced mutations have been observed. These mutated genes may be passed from parent to offspring.

9

1 lbvis-lhme Nidear Ptwer Station 1993 Annual Rachoksal Environmental Operating Reptxt Health Risks  !

While people may accept the risks inherent in their personal activities, such as smoking and driving to work each day, they are less inclined to accept the risk inherent in producing electricity. As with any industrial environment, it is not possible to guarantee a risk free environment. Thus, attention should be focused on taking steps to safeguard the public, on developing a realistic assessment of the risks, and on placing these risks in perspective. The perceptions of risk associated with exposure to radiation has, perhaps, the greatest  ;

misunderstanding. Because people may not understand ionizing radiation and its associated risks, they may fear it. This fear is compounded by the fact that we cannot hear, smell, taste or feel ionizing radiation.

However we do not fear other potentially hazardous things for which we have the same lack of sensory perception, such as radio waves, carbon monoxide, and small concentrations of numerous cancer causing substances. These risks arejust as real as those associated with exposure to radiation. Most of these risks are with us throughout our lives, and can be added up over a lifetime to obtain a total effect. Table i shows a number of different factors that decrease the average life expectancy ofindividuals in the United States.

Table 1: Risk Factors Estimated Decrease in Average Life Expectancy

• l l l

l Overweight by 30% 3.6 years

! Cigarette smoking: 1 pack / day 7.0 years l l 2 packs / day 10.0 years Heart diseases 5.8 years l Cancer 2.7 years f ,

1 1 i

City Living(not rural) 5.0 years All operating commericalnuclear less than 12 minutes power plants

• 'Ihe typical life span in the United States is now 76 years for women and 71 years for men.

i I

l 10

Davi:,-lhae Nele:r lher Sution IW3 Annual R::cological Environmental Opemting Repm l l

1 i

Benefits of Nuclear Power l Nuclear power plays an important part in meeting today's electricity needs, and will continue to serve as an

! l l important source of electric energy well into the future. In 1980, nuclear power accounted for only eleven percent of the electricity produced in the United States (Figure 4). By the end of 1992, however, this l number was greater than twenty percent. At the same time, dependence on oil as an energy source decreased by more than half. By decreasing the nations' dependence on oil, dependence on foreign oil

, supplies also decreases, thereby ensuring the nation can continue to be self-sufficient in meeting the energy i needs of its private and business sectors.

Nuclear power offers several advantages over altemative sources of electric energy:

l nuclear power has an excellent safety record dating back to 1957 when the first commercial nuclear power station began operating

- uranium, the fuel for nuclear power stations, is a relatively inexpensive fuel that is readily available in the United States 1

- nuclear power is the cleanest energy source for power stations that use steam to produce electricity.

The following sections provide information on the fundamentals of how Davis-Besse uses nuclear fuel and l the fission process to produce electricity. I Nuclear Power Production Electricity is produced in a nuclear power station in the same way as in a fossil-fuelei station with the  ;

exception of the source of heat. Heat changes water to steam that turns a turbine. In a fossil fueled station.

the fuel is bumed in a fumace, which is also a boiler. Inside the t, oiler, water is tumed into steam. In a nuclear station, the fumace is replaced by a reactor containing a core of nuclear fuel, primarily uranium. l Heat is produced when the atoms of uranium are split, or fissioned, inside the reactor.

Whatis Fission?

A special force called the binding force holds the protons and neutrons together in the nucleus of the atom.

The strength of this binding force varies from atom to atom. If the bond is weak enough, the nucleus can be split when bombarded by a free neutron (Figure 5). 'Ihis causes the entire atom to split, producing srnaller atoms, more free neutrons, and heat. In a nuclear reactor, a chain reaction of fission events provides the heat necessary to boil the water to produce steam.

11

Davis-iksse Nele r Power Statkx1 1993 Annual Radiological Envirmmental Operating Rep xt Ent I

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! Neutron /Mision free l

I i Fryment ,O  ;

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~0 < -N Nutron Mom l O l l

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j Figure 5: When a heavy atcxn, sudi m uranium 235 is spit or Ossioned, heat, free neuums, and fission fragments n:sull The fnr i neutmns an then strike neighbonng atrxns ansing them to Ossion also. In the pmper envumment, this prixxss can continue  ;

indefinitely in a diain reaction.

l l Nuclear Fuel l

[

The tissioning of one uranium atom releases approximately 50 million times more energy than the j combustion of a single carbon atom common to all fossil fuels. Since a single small reactor fuel pellet l contains trillions of atoms, each pellet can release an extremely large amount of energy. The amount of electricity that can be generated from three small fuel pellets would require about 3.5 tons of coal or 12 barrels of oil to generate.

Nuclear fission occurs spontaneously in nature, but these natural occurrences cannot sustain themselves l

because the freed neutrons either are absorbed by non-fissionable atoms or quickly decay. In contrast, a nuclear reactor minimizes neutron losses, thus sustaining the fission process by several means:

using fuel that is free of impurities that might absorb the free neutrons, l

enriching the concentration of the rarer fissionable isotope of uranium (U-235) relative to the concentration of U 238, a more common isotope that does not fission easily.

slowing neutrons down to increase the probability of fission by providing a

" moderator" such as water.

! Natural uranium contains less than one percent U 235 compared to the more abundant U 238 when it's I

mined. Before it can be economically used in a reactor, it is enriched to three to tive percent U-235, in contrast to nuclear material used in nuclear weapons which is enriched to over 97 percent. Because of the

! low levels of U 235 in nuclear fuel, a nuclear power station cannot explode like a bomb.

I l

l

( 12

Davis 1km Nurlear Power Station lW3 Annual Ratiologiut! Environmental Opemung Reptxt l

l

After the uranium ore is separated from the earth and rock, it is concentrated by a milling process. A11er l milling, the ore to a granular form and dissolving out the uranium with acid, the uranium is converted to

uranium hexafluoride (UF.). UF, is a chemical form of uranium that exists as a gas at temperatures slightly above room temperature. He UF, is then highly purified and shipped to an enrichment facility

where gaseous diffusion converters increase the concentration of U-235. The enriched gaseous UF,is then converted into powdered uranium dioxide (UO,,), a highly stable cemmic material. He UO2powder is put under high pressure to form fuel pellets, each about 5/8 inch long and 3/8 inch in diameter .

Approximately five pounds of these pellets are placed into a 12 foot long metal tube made of zirconium alloy. The tubes cons.itute the fuel cladding. He fuel cladding is highly resistant to heat, radiation, and corrosion. When the tubes are filled with fuel pellets, they are called fuel rods.

^

The Reactor Core Two hundred eight fuel rods comprise a single fuel assembly. He reactor core at Davis-Besse contains 177 of these fuel assemblies, each approximately 14 feet tall and 2,000 pounds in weight. In addition to the

] fuel rods, the fuel assembly also contains 16 vacant holes for the insertion of control n>ds, and one vacant j hole for an incore monitoring probe. This probe monitors temperature and neutron levels in the fuel assembly. He Davis-Besse reactor vessel, which contains all the fuel assemblies, weighs 838,000 pounds, l has a diameter of 14 feet, is 39 feet high, and has 81/2 inch thick steel walls.

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6: The reactor con: at DavirrBesse contains 177 fuel assemblies Eadussembly contaur,208 fuel rods. Eadi fuel rtxt is filled with approximately five pourxis of fuel pellets, cadt pellet is approximately 3,8 irxt in diameter and 5s3 irx11 long.

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13

Davis-Hee Nudcar Power Station 1993 Annual Radiokgiat! Envinemental Ojrraung Reptm Fission Control The fission rate inside the reactor core is controlled by raising or lowering control rod assemblies into the reactor core. Each assembly consist of "tingers" containing silver, indium, and cadmium metals that absoit free neutrons, thus disrupting the fission chain reaction. When control rod assemblies are slowly with-drawn from the core, fissioning begins and heat is produced. If the control rod assemblies are inserted rapidly into the reactor core, as during a plant " trip," the chain reaction ceases. A slower acting (but more evenly distributed) method of fission control is achieved by the addition of a neutron poison to the reactor coolant water. At Davis-Besse, boric acid enriched in boron-10 is concentrated or diluted in the coolant to achieve the desired level of fission. Boron-10 readily absorbs free neutrons, forming boron 11, removing the absorbed neutrons from the chain reaction.

Reactor Types Virtually all of the commercial reactors in this country are either boiling water reactors (BWRs) or pressurized water reactors (PWRs). Both types are also called light water reactors (LWRs) because their coolant, or medium to transfer heat, is ordinary water, which contains the light isotope of hydrogen.

Some reactors use the heavy isotope of hydrogen (deuterium) in the reactor coolant. Such reactors are called heavy water reactors, or IIWRs.

In BWRs, water passes through the core and boils into steam. The steam passes through separators which remove water droplets. The steam then travels to dryers before entering the turbine. After passing though the turbine the steam is condensed back into water and retums to the core to repeat the cycle.

In PWRs, the reactor water or coolant is pressurized to prevent it from boiling.Re reactor water is then pumped to a steam generator (heat exchanger) where its heat is transferred to a secondary water supply.

He secondary water inside the generator boils into steam which is then used to tum the turbine.his steam is then condensed back into water and retumed to the steam generator. Davis-Besse uses a PWR design.

he following paragraphs describe the various systems illustrated in Figure 7. Major systems in the Davis Besse Station are assigned a different color in the figure.

14

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

. Davis-lh:u Nelcr Pc;wer Station 1993 Annual Radioksicd Envimnmental Op: rating Reput 1

FIGURE 7 LEGEND i GREEN - Reactor Coolant System (Primary Gulant Water)

I RED - Main Steam System .i

, y

.i BLUE - Condensate / Main Feedwater System (Secondary Coolant Water) j 4

YELLOW - Circulating Water System (Tertiary Coolant Water)

ORANGE - Emergency Core Cooling System  ;

SCARLET Auxiliary FeedwaterSystem -

VIOLET - Pressurizer and Associated Structures i

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I 15  !

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Figure 7 Davis-Besse Nuclear Power Station Unit No.1

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16

l Davivlbe Nuclear Ibwer Station 1993 Annual lh!iokgml Envuunmental Operating Repo l

Station Systems Containment Building and Fission Product Release Barriers he containment building houses the reactor vessel, the pressurizer, two steam generators, the reactor coolant pumps and reactor coolant system piping.He building is constructed of an inner 1 inch thick steel l liner or containment vessel, and the shield building with steel reinforced concrete walls 2 feet thick. The l shield building protects the containment vessel from a variety of environmental factors and provides an area for a negative pressure boundary around the steel containment vessel. In the event that the integrity of the containment vessel is compromised (e.g., a crack develops), this negative pressure boundary ensures that any airbome radioactive contamir.nhn present in the containment vessel is prevented from leaking out into the environment. This is accomplished by maintaining the pressure inside the shield building lower than that outdoors, thus forcing clean outside air to leak in, while making it impossible for the contaminated air inside the containment vessel to leak out. The free-standing containment vessel is the third in a series of barders that prevent the release of fission products in the unlikely event of an accident. The first barrier to the release of fission products is the fuel cladding itself. He second barrier is the walls of the primary system, i.e. the reactor vessel, steam generator and associated piping.

]

The Steam Generators I

l Re steam generators perform the same function as a boiler at a fossil-fueled power station. De steam l genemtor uses the heat of the primary coolant inside the steam generator tubes to boil the secondary side feedwater (secondary coolant). Fission heat from the reactor core is transfered to the steam generator in order to provide the steam necessary to drive the turbine. However, heat must also be removed from the core even after reactor shutdown in order to prevent damage to the fuel cladding. Herefore, pumps maintain a continuous flow of coolant through the reactor and steam generator Primary loop water 1 (green in Figure 7) exits the reactor at approximately 606 F, passes through the steam generator, '

transferring some ofits heat energy to the secondary loop water (blue in Figure 7) without actually coming in contact with it. Primary coolant water exits the steam generator at approximately 558 F to be circulated back into the reactor where it is again heated to 606 F as it passes up through the fuel assemblies.

Under ordinary conditions, water inside the primary system would boil long before it reached such temperatures. However, it is kept under a pressure of approximately 2,200 pounds-per-square-inch (psi) at all times. Bis prevents the water from boiling and is the reason the reactor at Davis-Besse is called a Pressurized Water Reactor. Secondary loop water enters the base of the steam generator at approximately 400 F and under 1,100 psi pressure. At this pressure, the water can easily boil into steam as it passes over the tubes containing the primary coolant water.

Both the primary and the secondary coolant water are considered closed loop systems. His means they are designed not to come in physical contact with one another. Rather, the coolant ( water) contained in each loop transfers heat energy by the process of convection. Convection is a method of heat transfer that can occur between two fluid media. It is the same process by which radiators are used to heat homes. De water circulating inside the radiator is separated from the air (a " fluid medium) by the metal piping.

17

1 Dasis-ikse Nerle:r Power Station 19B Annual Itutiolcgicd Envinomental 0;rrating Repxt i

I The Turbine - Generator The turbine, main generator, and the condenser are all housed in what is commonly referred to as the i Turbine Building. He purpor,e of the turbine is to convert the thermal energy of the steam produced in  !

the steam generator (referred to as main steam, red in Figure 7) to rotational energy of the turbine. )

generator shaft. He turbine at Davis-Besse is actually composed of one six-stage high pressure turbine and 1 i two seven-stage low pressure turbines aligned on a common shaft. A tuttine stage refers to a set of l blades. Steam enters at the center of each turbine and flows outward along the shaft in opposite directions  !

through each successive stage of blading. As the steam passes over the turbine blades, it loses pressure.  ;

Thus, the blades must be proportionally larger in successive stages to extmet enough energy from the steam to rotate the shaft at the correct speed.

he purpose of the main generator is to convert the rotational energy of the shaft to electrical energy for commercial usage and support of station systems. The main generator is composed of two parts, a stationary stator that contains coils of copper conductors, and a rotor that supplies a rotating magnetic field within the coils of the stator. Electrical current is generated in the stator raion of the main generator.

From this point, the electric current passes through a series of transformm hansmission and use throughout northem Ohio. l l

The Condenser After the spent steam in the secondary loop (blue in Figure 7) passes through the high and low pressure turbines, it is collected in a cavemous condenser sevemi stories tall and containing more than 70,000 small j tubes. Circulating water (yellow in Figure 7) goes to the cooling tower after passing through the tubes i inside the condenser. As the steam from the low pressure turbines passes over these tubes, it is cooled and  ;

condensed. De condensed water is then purified and reheated before being circulated back into the steam )

generator again in a closed loop system. Circulating water forms the third (or tertiary) and final loop of l cooling water used at the Davis-Besse Station.

As the primary to secor.dary interface, the secondary to tertiary interface is based on a closed loop design.

The circulating water s able to cool the steam in the condenser, without ever actually coming in contact I with it, by the pwess of convection. Even in the event of a primary to secondary leak, the water vapor exiting the Davis-Besse cooling tower would remain non-radioactive. Closed loops are an integral part of the design of any nuclear facility. his design feature greatly reduces the chance of environmental impact from station operation.

The Cooling Tower The cooling tower at Davis-Besse is easily the most noticeable feature of the plant. The tower stands 493 feet high and the diameter of the base is 411 feet. The two pipes circulating 480,000 gallons of water per minute to the tower are 9 feet in diameter.The purpose of the tower is to recycle water from the condenser by coolingit.

I8

Ibvis-Ikac Nuclear Power Station 1W3 Annual Radioksical Enwonmental Op;mung Repm After passing through the condenser, the circulating water has warmed to approximately 100 F. In order to cool the water back down to around 70"F, the circulating water enters the cooling tower about 40 feet above the ground. The water is spmyed evenly over a series of baftles called fillsheets which are suspended vertically in the base of the tower. A natural draft of air blowing up through these bailles cools the water through the process of evaporation. The evaporated water exits the top of the cooling tower in the form of water vapor.

As much as 10,000 gallons of water per minute are lost to the atrr.u.;phere via the cooling tower. Even so, approximately 98 percent of the water drawn from lake Die for station operation can be recycled through the cooling tower for reuse. A small portion of the circulating water is discharged back to Lake Erie at essentially the same temperature it was withdrawn earlier. In 1993, the average difference between the intake and discharge water temperatures was only 4.1 F. De slightly warmer discharge water had no adverse environmental impact on the area of lake surrounding the discharge point.

Miscellaneous Station Safety Systems The orange system in Figure 7 is part of the Emergency Core Cooling System (ECCS) housed in the Auxiliary Building of the station. The ECG consists of three overlapping means of keeping the reactor core covered with water, in the unlikely event of a Loss Of Coolant Accident (LOCA), thereby protecting the fuel cladding barrier against high temperature failure. Depending upon the severity of the loss of pressure inside the primary system, the ECCS will automatically channel borated water into the reactor by either high pressurt idection pumps, a core flood tank, or low pressure idection pumps. Borated water can also be sprayed from the ceiling of the containment vessel to cool and condense any steam that i may escape from the primary system.

l 1

He violet system illustrated in Figure 7 is responsible for maintaining the primary coolant water in a liquid state. It accomplishes this by adjusting the pressure inside the primary system. Heaters inside the pressurizer tum water into steam. This steam takes up more space inside the pressurizer, thus increasing the overall pressure inside the primary system. he pressurizer is equipped with spray heads that shower cool water over the steam in the unit. In this case, the steam condenses and the overall pressure inside the primary system drops. He quench tank pictured in Figure 8 is simply where excess steam is directed and condensed for storage. j i

i ne scarlet system in Figure 7 is part of the Auxiliary Feedwater System, a key safety system in event the '

main feedwater supply (blue in Figure 7) to the steam generator is inadequate. Following a reactor shutdown, the Auxiliary Feedwater System can supply water to the steam generators from the Condensate Storage Tanks. De Auxiliary Feedwater System is housed in the Tuttine Building along with the turbine, main generator, and the condenser.

19

Davis-Ibse Nuclear Power Statim IGU Annual Radiokgel Enytmnmental Operating Repm Reactor Safety and Summary i

Nuclear power plaats are inherently safe, not only by the laws of physics, but by design. Nuclear power plants cannot explode like a bomb because the concentration of fissionable material is far less than is necessary for such a nuclear explosion. Also, many safety features are equipped with several backup systems to ensure that any possible accident would be prevented from causing a serious health or safety l threat to the public, or serious impact on the local environment. Davis-Besse, like all U.S. nuclear units, has many overlapping, or redundant safety features. If one system should fail, there are still back-up j systems to assure the safe operation of the Station. During normal operation, the Reactor Control System 1 regulates the power output by adjusting the position of the control rods. The reactor can be automatically shut down by a separate Reactor Protection System that causes all the control rod assemblies to be l quickly and completely inserted into the reactor core, stopping the chain reaction. To guard against the possibility of a Loss Of Coolant Accident, the Emergency Core Cooling System is designed to pump reserve water into the reactor automatically if the reactor coolant pressure drops below a predetermined level.

The Davis-Besse Nuclear Power Station was designed, constructed, and operates to produce a reliable, safe, and environmentally sound source of electricity.

Radioactive Waste j i

j Many of the activities we depend on in our everyday lives produce radioactive waste by-products. Nuclear j energy, industrial processes, and medical treatments are some of these activities. Thue by-products are  ;

managed and disposed of under strict requirements set by the federal govemment. With the exception of i used nuclear fuel assemblies, these by-products produced at commercial power plants are referred to as low level radioactive waste.

Low Level Radioactive Waste l

Low level radioactive waste consists mainly of ordinary trash and other items that have become contaminated with radioactive materials. It includes plastic gloves and other protective clothing, machine 1 i parts and tools, medical and laboratory equipment, filters, resins, and geneml scrap.

l The radioactive particles in low level radioactive waste emit the same types of radiation that naturally occurring materials tend to emit. Most low level radioactive waste " decays" to background levels of radioactivity in months or years. Nearly all of it diminishes to stable mat rials in less than 300 years.

At this time, all of the country's low-level radioactive waste is sent to a disposal site located in South Carolina. However, in 1980, Congress passed the low level Waste Policy Act. This law requires each i

state to develop an individual disposal site for waste, or to form " compacts" with other states tojointly dispose of their low-level waste. Approximately 10 regional compacts have been formed.

l l

l Ohio is a member of the Midwest Compact, which includes Indiana, Iowa, Missouri, Minnesota, and Wisconsin. Since Ohio is the largest producer of low-level waste in the Compact, it has the responsibility 20 l

Davis-lh:sse Nuclcr Power Station tW Annual thiiokpat! Environmental Opemting Repet to site the first disposal facility, which would receive waste from all Compact states for 20 years. The responsibility then shifts to the Compact's next largest producer of waste, Minnesota, which will host the repository for the second 20 years.

Davis-Besse presently ships its low-level waste to the Bamwell, South Carolina site. However, Bamwell is scheduled to close to out-of-state generators in June,1994. After Davis-Besse is no longer permitted to send its waste to Bamwell, it has the capacity to store the low-level waste it produces on site for several years in the Low-Level Radioactive Waste Storage Facility k)cated inside the protected area of the plant.

However, this storage is temporary and the material will be shipped when a Compact disposal facility becomes available.

HighI2velNuclear Waste Like any industrial or scientific process, nuclear energy does produce waste. He most radioactive is defined as "high-level" waste (because it has high levels of radioactivity). Ninety-nine percent of high-level waste from nuclear plants is used nuclear fuel. The fuel undergoes certain changes during fission. Most of the fragments of fission - pieces that are left over after the atom is split - are radioactive. After a period of time, the fission fragments trapped in the fuel assemblies reduce the efficiency of the chain reaction. About i l

every 18 months, the oldest fuel assemblies are removed from the reactor and replaced with fresh fuel.

1 High-level nuclear waste volumes are small. Davis-Besse produces about 30 tons of used fuel each year.

All the used fuel produced by all America's nuclear energy plants since the first plant started operating over 30 years ago would cover an area the size of a football field about five yards deep. All of America's nuclear plants combined produce only 3,000 tons of used fuel each year. By contrast, the U.S. produces about 300 million tons of chemical waste annually. Also, nuclear waste slowly loses its radioactivity, but chemical waste remains hazardous indefinitely.

Davis-Besse presently stores its used fuel in a steel-lined concrete vault filled with water inside the plant.

De Department of Energy is charged with constructing a permanent high-level waste repository for all of the nation's nuclear plants. At this time, Yucca Mountain, Nevada, is being considered as a possible site.

1 Until the permanent DOE site is developed, nuclear plants will be responsible for the continued safe j storage of high-level waste. At Davis-Besse this will be done in the fuel pool until it reaches its capacity At that time, the older fuel assemblies that no longer require water cooling will be placed in air cooled concrete shielded canisters. Rese will be stored onsite until the Department of Energy facilities are ready to receive them. Dry fuel storage is already used in many countries, including Canada, and in the U.S. at nuclear plants in Colorado, Maryland, Virginia, and South Carolina.

21

Davis-Iksse Nuclear Pc;wer Stauon lW3 Annual Rahokpcil Envirunmental Opemung Repit Description of the Davis-Besse Site l

The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio. It is on the southwestem shore of bke Erie,just north of the Toussaint River. The site lies north and east of Ohio State Route 2, approximately 10 miles northwest of Port Clinton,7 miles north of Oak Harbor, and 25 miles east of Toledo, Ohio (Figure 8).

This section of Ohio is flat and marshy, with maximum elevations of only a few feet above the level of I2ke Erie. The area originally consisted of swamp forest and marshland, rich in wildlife but unsuitable for settlement and farming. During the nineteenth century, the land was cleared and drained, and has been farmed successfully since. Today, the terrain consists of farmland with marshes extending in some places for up to two miles inland from the Sandusky 12ke Shore Ridge.

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t Davis-lhw: Nm les Power Statien IW3 Annual Radioksicil Envimnmental Operating Rep rt i

Davis-Besse site is mainly comprised of marshland with a small ponion consisting of farmland. The marshes are part of a valuable ecok)gical resource, providing a breeding ground for a variety of wildlife,

and a refuge for migratory birds. The site includes a tract known as Navarre Marsh, which was acquired i from the U.S. Bureau of Sport Fisheries and Wildlife, Department of the Interior. In 1971, Toledo Edison purchased the 188-acre Toussaint River Marsh he Toussaint River Marsh is contiguous 4

with the 610-acre Navarre Marsh section of the Ottawa National Wildlife Refuge.

He immediate area near Davis-Besse is sparsely populated; Ottawa County had a population of 40,029 in ,

I the 1990 census. The nearest incorporated communities are:  !

• Port Clinton - 10 miles southeast, population 7,106 i'

' Oak Harbor - 7 miles south, population 2,637 l 1 1

• Rocky Ridge - 7 miles west southwest, population 425 1

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• Toledo (the nearest major city) - 25 miles west, population 322,943 l l

here are some residences along the lake shore used mainly as summer homes. However, the major resort I i area of the county is farther east, around Port Clinton, Lakeside, and the Bass Islands. )

i l The non-marsh areas around the Davis-Besse site are utilized primarily for farming. He major crops I I

i include soybeans, corn, wheat, cats, hay, fruits and vegetables. Meat and dairy animals are not major sources of income in the area. He main industries within five miles of the site are located in Erie Industrial Park, about four miles southeast of the station.

Most of the remaining marshes in the area have been maintained by private hunting clubs, the U.S. Fish

and Wildlife Service, and the Ohio Department of Natural Resources, Division of Wildlife. The State of Ohio Department of Natural Resources operates many wildlife and recreational areas within 10 miles of the

Station. These include Magee Marsh, Turtle Creek, Crane Creek State Park, and the Ottawa National

Wildlife Refuge. Magee Marsh and Turtle Creek lie between three and six miles WNW of the Station.

] Magee Marsh is a wildlife preserve allowing public fishing, nature study, and controlled hunting season. )

! Tunie Creek, a wooded area at the southem end of Magee Marsh, offers boating and fishing. Crane Creek l 4 State Park is adjacent to Magee Marsh and is a popular picnicking , swimming, and fishing area. The Ottawa National Wildlife Refuge lies four to nine miles WNW of the Site, immediately west of Magee i Marsh.

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D.wis.L5w Nwicar Power Staien 10 % Annual lhdiological Environmenta! Operattng Repm l

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The 1993 Summary of Radioactivity Released in Liquid and Gaseous Effluents 1

1 1

Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazards of ionizing ,

radiation were recognized and efforts were made to establish radiation protection standards.%e primary l source of recommendations for radiation protection standards within the United States is the National Council on Radiation Protection and Measurement (NCRP). Many of these recommendations have been given legislative authority through publication in the Code of Federal Regulations (CFR) by the Nuclear .

I Regulatory Commission (NRC).

1 The main objective in the control of radiation is to ensure that any dose is kept as low as is reasonably achievable (ALARA). The ALARA principle applies to reducing radiation dose both to the individual working at Davis-Besse and to the general public. " Reasonably achievable" means that exposure reduction is based on sound economic decisions and operating practices. By practicing ALARA, Davis-Besse and l

Centerior Energy minimize health risk and environmental detriment and ensure that doses are maintained  ;

well below regulatory limits. l I

Limits i To protect the general public, guidelines and limits have been established goveming the release of radioactivity in liquid and gaseous Station effluents. He Code of Federal Regulations, Title 10 Part 50, 4

Appendix I(10CFR50, App.I) provides guidelines for the Technical Specifications which are part of the license authorizing nuclear reactor operation. Davis-Besse's Technical Specifications and Offsite Dose Calculation Manual restrict the release of radioactivity to the environment and the resulting dose to the i public. Table 2 presents these limits.

The Davis-Besse limits are only a small fraction of the dose limits established by the Environmental Protection Agency (EPA). In its environmental dose standard,40 CFR 190, the EPA established environmental mdiation protection standards for nuclear power operations. These standards for normal operation provide that the dose from all discharges of radioactivity should not exceed:

I *25 mrem / year to the whole body

• 75 mrem / year to the thyroid

• 25 mrem / year to any other organ 24

Davis llsse Nudcar Power Station 1993 Annual Rcdiologiat1 Environmental Operaung Rep v1 Table 2: Dose Limits to a Member of the Public Source NRC Limits for Davis-Besse Uquid Effluents Whole Bcx!y less than or equal to 3 mrem / year ,

Organ less than or equal to 10 mrem / year Gaseous Effluents l Noble Gases  !

gamma air dose less than or equal to 10 mrad / year beta air dose less than or equal to 20 mrad / year  !

Iodine-131, tritium and l particulates with half-lives j greater than 8 days less than or equal to 15 mrem / year Sources of Radioactivity Released l

During the nomial operation of a nuclear power station, 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. He three types of radioactive material released are noble gases, iodine and particulates, and tritium, i Re noble gas fission products in the primary coolant are given off as a gas when the coolant is depressunzed. These gases are then collected by a system designed for gas collection and storage for radioactive decay prior to release.

Small releases of radioactivity in liquids may occur from valves, piping or equipment associated with the primary coolant system. Dese liquids are collected through a series of floor and equipment drains and sumps. All liquids of this nature are monitored and processed, if necessary, prior to release.

Noble Gas Some of the 6ssion products released in airbome effluents are radioactive isotopes of noble gases, such as xenon and krypton. Noble gases are biologically and chemically nonreactive. Rey do not concentrate in humans or other organisms. Rey contribute to human radiation dose by being a source of extemal radiation exposure to the whole body. Xenon 133 and xenon 135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive noble gases released. Rey are readily dispersed in the atmosphere.

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this-lhe Nudcar Power Station IW3 Annual Radiologiail Envirunmental Operuting Report i

l In 1993, approximately 352 curies of noble gases were released in gaseous effluents. He calculated off l site gamma and beta air doses due to the release of this activity were 0.002 mrad and 0.008 mrad i respectively, and are less then 0.04 % of their respective Technical Specification limits. Additional dose information is provided in Table 3.

Iodine and Particulates i

i Annual releases of radioisotopes of iodine, and those particulates with half-lives greater than 8 days, in

gaseous and liquid effluents are small. Factors such as their high chemical reactivity and solubility in j water, combined with the high etliciency of gaseous and liquid processing systems, minimize their j discharge. He predominant radioiodine released is iodine-131 with a half-life of approximately eight days.

J Be main contribution of radioactive iodine to human dose is the thyroid gland, where the body j concentratesiodine, i

The principal radioactive particulates released are tission products (e.g., cesium 134 and cesium-137) and 2

activation products (e.g., cobalt-58 and cobalt-60). Radioactive cesiums and cobalts contribute to intemal i radiation exposure of tissues such as the muscle, liver, and intestines. Rese particulates are also a source of j extemal radiation exposure if deposited on the ground.

During 1993, the amount of radioactive iodine and particulates released was approximately 0.(X)93 curie in gaseous effluents and 0.09 curie in liquid effluents. Rese releases were well below all applicable j regulatory limits. Additional dose information is provided in Table 3.

1

! Tritium i

] Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in liquid effluents. It is also

present in gaseous effluents. Tritium is produced in the reactor coolant as a result of neutron interaction

with deuterium (also a hydrogen isotope) present in the water and with the boron in the primary coolant.

i When tritium is ingested or inhaled it is dispersed throughout the body until eliminated.

he amount of tritium released in 1993 was approximately 22.41 curies in gaseous effluents and 180 curies

]

in liquid effluents. The associated doses were well below all regulatory limits, and additional dose j information is provided in Table 3.

i l Processing and Monitoring i

Eftluents are strictly controlled to ensure radioactivity released to the environment is minimal and does not j exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and j environmental sampling and analyses progmms, quality assurance programs for effluent and environmental j programs, and pmcedures covering all aspects of effluent and environmental monitoring.

i j Re radioactive waste treatment systems at Davis-Besse are designed to collect and process the liquid and gaseous wastes which contain radioactivity. For example, the Waste Gas Decay Tanks are holding tanks

which allow radioactivity in gases to decay prior to release via the station vent.

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IMs llme Nude:r i ower Station tw3 Annual Radiologwal Environmental (Wmting Repo Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits. Dese instruments provide a continuous indication of the radioactivity present and are sensitive enough to measure 100 to 1000 times lower than the release limits. Each instrument is equipped with alarms and indicators in the control room. He alarm setpoints are low to ensure the limits will not be exceeded, if a monitor alarms, a release from a tank is automatically stopped. j All wastes are sampled prior to release and analyzed in a laboratory to identify the specific concentrations of radionuclides being released. Sampling and analysis provide a more sensitive and precise method of I determining effluent composition than with monitoring instruments alone. l A meteorological tower is located in the southwest sector of the Station. It is linked to computers which )

record the meteorological data. Coupled with the effluent release data, the meteorological data are used to calculate the dose to the public.

Beyond the plant, devices maintained in conjunction with the Radiological Environmental Monitoriy l Program constantly sample the air in the surrounding environment. Frequent samples of other en- I vironmental media, such as water and vegetation, are also taken to determine if buildup of deposited radioactive material has occurred in the area.

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Exposure Pathways Radiological exposure pathways defme the methods by which people may become exposed to radio-active material. He major pathways of concem are those which could cause the highest calculated radiation dose. These projected pathways are determined from the type and amount of radioactive i material released, the envimnmental tmnsport mechanism, and the use of the environment. De environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characterstics of the area. Infonnation on the water flow, wind speed, and wind direction at the time of a gaseous or liquid release is used to evaluate how the radionuclides will be distributed in an area. An important factor in evaluating the exposure pathways is the use of the environment. Many factors are considered such as dietary intake of residents, recreactional use of the area, and the locations of homes and farms in the area.

De extemal and intemal exposure pathway considered are shown in Figures 9 and 10. He release of radioactive gaseous effluents involves pathways such as extemal whole body exposure, deposition of radioactive material on plants, deposition on soil, inhalation by animals destined for human consumption, and inhalation by humans. The release of radioactive material in liquid effluents involves pathways such as drinking water, fish consumption, and direct exposure from the lake at the shoreline and while swimming.

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iknwlbw: Nuclear Power Statxxi FN3 Amual R.rdokpad Envinemenud Operutmg Rep o l

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nsu Figure 10 Intemal expmure pathways include the methoch by which radnxmty mdd reach people around the Stadornia the foods they cat, the milk they drink, and the air they breathe.

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l Davis-Ibc Nurlea Power Station tw3 Annual 16Jiokpcal Envmnmental Opemung Repn 1 Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway is the exposure pathway which will provide, for a specific radionuclide, tne greatest dose to a population, or to a specific group of the population, called the critical group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, or other cultural factors. He dose may be delivered to the whole body or to a specific organ. The organ receiving the greatest fraction of the dose is called the critical organ.

Dose Assessment Dose is the energy deposited by radiation in an exposed individual. Whole body exposure to radiation involves the exposure of all organs. Most background exposures are of this form. Both non-radioactive and radioactive elements can enter the body through inhalation or ingestion. When they do, they are usually not distnbuted evenly. For example, i(x!ine concentrates in the thyroid gland, cesium collects in muscle and liver tissue, and strontium collects in bone tissue.

He total dose to organs from a given radionuclide depends on the amount of radioactive material present in the organ and the amount of time that the radionuclide remains in the 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 body for longer periods of time.

He dose to the general public in the area surrounding Davis-Besse is calculated for each liquid or gaseous telease. He 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 weather conditions at the time of the release, the locations of exposure pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inhalation , food consumption). He dose due to radioactive material released in liquid effluents is calculated using factors such as the total volume of liquid, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption, shoreline and swimming factors). Rese calculations produce a conservative estimation of the dose.

Results he results of the effluent monitoring program are reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report. For 1993, the doses from radioactive material released in gaseous and liquid effluents were a small fraction of the Davis Besse Technical Specification limits. He offsite whole body dose due to radioactivity released in liquid effluents was approximately 3.43 percent of the annual Technical Specification limits. He offsite gamma and beta air doses due to gaseous effluents were I smaller, each was less than 0.003 percent of the annual Technical Specifications limits. Table 3 l summarizes the dose due to radioactivity released in ettluents in 1993.

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I Davis Ikvc Nuclear IWer Station _ tw3 Annual ILdiokyical Envinnmental Opemting Repxt i

Table 3: Annual Dose to the Public Due to Radioactive Material I 1

Released in Gaseous and Liquid Effluents  !

1993 Dose AnnualUmit Percent of Umit Uquid Emuents Whole Body 0.103 mrem 3 mrem 3.43 Organ 0.145 mrem 10 mrem 0.91 Gaseous Emuents i Gamma Air Dose 0.002 mmd 10 mrad 0.(n Beta Air Dose 0.008 mrad 20 mrad 0.03 Iodine-131, tritium 0.006 mrem 15 mrem 0.04 and paniculates with half-lives greater than 8 days i

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Davis-Iks.c Nelcar Power Station tW3 Annual Rmfiological Envuunmental Openiting Rep rt l

l l References

1. "A Citizen's Guide to Radon: What It Is and What to do About It," United States Environmental Protection Agency, United States Depanment of Health Services, Centers for Disease Control (August 198@.

2. " Basic Radiation Protection Criteria," Repon No. 39, National Council on Radiation Protection end Measurement, Washington, D.C (January 1971).

l 3. " Cesium-137 from the Environment to Man: Metabolism and Dose," Report No. 52, National Council l on Radiation Protection and Measurements, Washington, D.C (January 1977).

4. Deutch, R., " Nuclear Power, A Rational Approach," fourth edition, GP Courseware, Inc., Columbia, I l MD. (1987).

1

5. Eisenbud, hi, " Environmental Radioactivity," Academic Press, Inc., Orlando, FL (1987).

1 l 6. " Environmental Radiation Measurements," Report No. 50, National Council on Radiation Protection and l l

Measurements, Washington, D.C (December 1976).

l

7. " Exposure of the Population in the United States and Canada from Natural Background Radiation,"

Report No. 94, National Council on Radiation Protection and Measurements, Washington, D.C.

(December 1987).

8. " Health Effects of Exposure to 1.ow Levels ofIonizing Radiation: BEIR V," Committee on the Biological Effects of Ionizing Radiations, Board on Radiation Effects Research Commission on Life Sciences, National Research Council, National Academy Press, Washington, D.C (1990).

9. Hendee, William R., and Doege, Theodore C., " Origin and Health Risks of Indoor Radon," Seminars in Nuclear Medicine, Vol. XVIII, No.1, American Medical Association,01icago,IL (January 1987).

10. Hurley, P., "Living with Nuclear Radiation," University of Michigan Press, Ann Arbor, MI. (1982).

I1. " Indoor Air Quality Environmental Information Handbook: Radon," prepared for the United States Department of Energy, Assistant Secretary for Environment, Safety and Health, by Mueller Associated, Inc., Baltimore, MD. (January 1986).

12. Introduction to Davis-Besse Nuclear Power Station Plant Technology, July 1992, Rev. 4, Pg. 2-9.

13. " Ionizing Radiation Exposure of the Population of the United States," Repon No. 93, National Council on Radiation Protection and Measurements, Washington, D.C (September 1987).

14. " Natural Background 16diation in the United States," Report No. 45, National Council on Radiation Protection and Measurements, Washington, D.C (November 1975).

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Davis-lhw Ne;lar Power Senion IW3 Annual Ramokyict! Ennronmental Openning Repxt 1

i l 15. " Nuclear Energy Emerges from 1980's Poised for New Growth," U.S. Council for Energy Awareness, l

Wahington, D.C (1989).

16. " Nuclear Power: Answers to Your Questions," Edison Electric Institute, Washington, D.C (1987).

l

17. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report No. 92, i National Council on Radiation Protection and Measurement, Washington, D.C (December 1987).

18. " Radiation Protection Standards," Department of Environmental Sciences and Physiology and the l l

Office of Continuing Education, Harvard School Of Public Health, Boston, MA. (July 1989).

19. "1985 Radiological Environmental Monitoring Report for Three Mile Island Station," GPU Nuclear i Corporation, Middletown, PA. (1985).

20. " Sources, Effects and Risk of Ionizing Radiation," United Nations Scientific Committee on the Effects of Atomic Radiation,1988 Report to the General Assembly, United Nations, New York (1988).

21. " Standards for Protection Against Radiation," Title 10, Part 20, Code of Federal Regulation,  ;

Washington,D.C (1988).

22. " Domestic Ucensing of Production and Utilization Facilities," Title 10, Part 50, Code of Federal Regulations, Washington, D.C (1988).

23. " Environmental Radiation Protection Standard for Nuclear Power Operations," Title 40, Part 190, Code j of Federal Regulations, Washington, D.C (1988). j l 24. " Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurement, Washington, D.C (March 1979).

25.1992 Site Environmental Report, Femald Environmental Management Project, U.S. Department of Energy (June 1993).

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Davis-Iksse Nucle:r PowerStation 1993 Annual lux.tiological Emironmental Operuting Report Radiological Environmental Monitoring Program Introduction he Radiological Environmental Monitoring Program (REMP) was established at Davis-Besse for several reasons: to provide a supplementary check on the adequacy of containment and effluent controls, to assess the radiological impact, if any, that Station operation has on the surrounding area, and to determine compliance with applicable radiation protection guides and standards. Environmental surveillance at Davis-Besse has been a part of the radiological programs conducted at the Station for over 21 years. The REMP was established in 1972, five years before the Station became operational. This preoperational surveillance program was established to describe and quantify the radioactivity, and its variability, in the area prior to the operation of Davis-Besse. When Davis-Besse became operational in 1977, the REMP continued to measure mdiation and radioactivity in the surmunding areas. he operational surveillance program had been collecting environmental data for over 16 years.

A wide variety of environmental samples are collected as part of the REMP at Davis-Besse. De selection of sample types is based on the established critical 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 chameteristics, local population characteristics, and land usage in the area i of interest. he selection of 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 l environment.

A description of the REMP at Davis-Besse is provided in the following section. In addition, a brief history of analytical results for each sample type collected since 1972, and a more detailed summary of the analyses performed in 1993, are also provided.

Preoperational Surveillance Program All nuclear facilities are required by the federal govemment to conduct radiological environmental 7 monitoring prior to constructing the facility. Bis preopemtional surveillance program is aimed at collecting the data needed to identify critical pathways, including selection of the radioisotope and sample media combinations to be included in the surveillance program conducted after facility operation begins.

Radiochemical analyses performed on the environmental samples should include not only those nuclides expected to be released during facility opemtion, but should also include typical fallout mdionuclides and natural background radioactivity. All environmental media with a potential to be affected by facility 33

Davis-Besse NuclearIbwer Sution 1993 Armual Radiological Enviiutmental Operating Report operation, as well as those media directly in the critical pathways, should be sampled on at least an annual

)

basis during the preoperational phase of the environmental surveillance program.  ;

He preoperational surveillance design, including nuclide/ media combinations, sampling frequencies and locations, collection techniques, and mdioanalyses performed, should be carefully considered and l' 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 k) cation, etc.) in order to detect any radiological impact the facility has on the surrounding environment. Total data collection during the ,

preoperational phase should be planned to provide a comprehensive database for evaluating any future 1 changes in the environment surrounding the nuclear facility.  !

Davis-Besse began its preoperational environmental surveillance progmm five years before the Station .

began producing power for commercial use in 197/. Data accumulated during those early years provide an ,

extensive database from which Station personnel are able to identify trends in the radiological character-istics of the local environment. He environmental surveillance program at Davis-Besse will continue well after the Station has reached the end ofits economically useful life and decommissioning has begun. Such a rigorous, long term environmental surveillance progmm is designed to detect any radiological impact the operation of Davis-Besse has had on the surrounding environment.  ;

Operational Surveillance Program Objectives he operational phase of the environmental surveillance progmm at Davis-Besse was designed with the 1 l following objectives m mmd-l .

to fulfill the obligations of the radiological surveillance sections of the Station's Technical Specifications and Offsite Dose Calculation Manual: ,

to determine whether any significant increase occurs in the concentration of radionuclides in critical pathways; j

to identify and evaluate the buildup, if any, of radionuclides in the local environment, or any changes in normal background radiation levels; to verify the adequacy of Station controls for the release of radioactive materials.

Quality Assurance An important part of the environmental monitoring program at Davis-Besse is the Quality Assurance (QA) Program. QA consists of all the planned and tystematic actions that are necessary to provide l adequate confidence in the results of an activity such as the REMP. QA checks the adequacy and validity of the monitoring program through routine audits, strict adherence to written policies and procedures, and attention to good record-keeping practices.

He QA program at Davis-Besse is conducted in accordance with the guidelines specified in NRC Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs." The QA program is designed to identify possible deficiencies in the REMP so that corrective actions can be initiated promptly.

Davis-Besse's Quality Assumnce program also provides confidence in the results of the REMP through:

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Davbiksse Nuclearl'ower Steion 1993 Annual Itadiological Envirmmental Operating Repon performing regular audits (investigations) of the REMP, including a careful examination of sample collection techniques and record keeping:

performing audits of contractor laboratories which analyze the environmental samples; requiring analytical contractor laboratories to participate in the United States Environmental Protection Agency Cross-Check Program; requiring analytical contractor laboratories to split samples for separate analysis l followed by a comparison of results; splitting samples prior to analysis by independent laboratories, and then comparing the results for agreement, and, finally; requiring analytical contractor laboratories to perform in-ho ase p.ked sample analyses.

QA audits and inspections of the Davis-Besse REMP are performed by Cait-Desse's O A department and  ;

the NRC. In addition, the NRC and the Ohio Department of Health (ODH) also pcife:m independent l environmental monitoring in the vicinity of Davis-Besse. The types of samples ce!iected and the sampling locations used by the NRC and ODH were incorporated in Davis- Besse's REMP. Hence, the analytical results from the different programs can be compared. His practice of comparing results from identical-samples, collected and analyzed by different parties, provides a valuable tool to verify the quality of the l laboratories' analytical procedures and the data generated.

! In 1987, environmental sampling personnel at Davis-Besse incorporated their own Quality Assurance l program into the REMP. Duplicate samples, called quality control samples, were collected at several l locations. These duplicate samples were assigned different identification numbers than the numbers assigned to the routine samples. This ensured that the analytical laboratory would not know the samples were identical. De laboratory results from analysis of the quality control samples and the routine samples could then be compared for agreement. Quality control sampling has become an important part of the i REMP since 1987, providing a check on the quality of analyses performed at the contracted analytical laboratory. Quality control sampling k) cations are changed frequently in order to duplicate as many sampling locations as possible, and to ensure the contractor laboratory has no way of correctly pairing a quality control sample with its routine sample counterpart.

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Duvis Iksse Nuclear ibwerStaion 1993 Annual Raiblogical Enviruvnental Opemting Repan Program Description -

Overview The Radiological Environmental Monitoring Program at Davis Besse is conducted in accordance with Title 10, Code of Federal Regulations, Part 50; Regulatory Guide 4.8; the Davis Besse Nuclear Power Station Operating License, Appendix A (Technical Specifications); and the Davis Besse Offsite Dose Calculation Manual (ODCM). Samples are collected on a routine basis, either weekly, monthly, quarterly, semiannually, or annually, depending upon the sample type and nature of the radionuclides ofinterest.

Environmental samples collected by Davis-Besse personnel are divided into four general types:

a atmospheric --including samples of airborne particulates and airbome radiciodine, terrestrial -- including samples of milk, groundwater, broad leaf vegetation, fruits,.

animal / wildlife feed, soil, eggs, and wild and domestic meat, aquatic -- including samples of treated and untreated surface water, fish, and shoreline and bottom sediments, l -

direct radiation -- measured by thermoluminescent dosimeters.

All environmental samples are labeled using a sampling code. Table 4 provides the sample codes and collection frequency for each sample type.

REMP samples are collected onsite and offsite up to 25 miles away from the Station. Sampling locations may be divided 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 Davis-Besse. Generally, they are located within five miles of the station. Control locations are those which should be unaffected by Station operations. Typically, these are more than five miles away from the Station. Data obtained from the indicator locations are compared with data from the controllocations. This comparison allows REMP personnel to take into account naturally occurring background radiation, or fallout from weapons testing, in -

evaluating any radiological impact Davis Besse has on the surrounding environment. Data from indicator and control kx ations are also compared with preoperational data to determine whether significant variations or trends exist.

Since 1987, the REMP has been modified to develop a more comprehensive sampling program. The modifications included additions of sampling kx:ations above the minimum amount reguired in the ODCM and increasing the number of analyses performed on each sample. Besides adding new locations, dup i

l or Quality Control (OC) samples were collected in order to verify the accuracy of the lab analyzing the environmental samples. These additional samples are referred to as the REMP Enhancement Samples.

a result of REMP Enhancement effons, over 2100 samples were collected and over 2900 analyses were performed during 1993. In addition, of the 142 sampling locations utilized in 1993,15.5 % were quality control locations. Table 5 shows the number of sampling locations and number collected for each type !

sample.

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Davis Iksse Nuclex PowerStation 1993 Annual Radiological Envirturnental Operating Repcrt Table 4: Sample Codes and Collection Frequencies Sample Type Sample Collection Code Frequency l

Airbome Paniculate AP Weekly Airbome Iodine Al Weekly .

Thermoluminescent TLD Quarterly, Annually Dosimeter Milk MIL Monthly (semi-monthly during l grazingseason)

Groundwater WW Quarterly Broad Leaf Vegetation BLV/ Monthly (when available) and Fmits FRU l

Surface Water-Treated SWT Weekly Surface Water - Untreated SWU Weekly Fish FIS Semiannually Shoreline / Bottom SED Semiannually Sediment Soil SOI Semiannually Animal / Wildlife Feed AF/WFE Annually l

Meat-Domestic Me(D) Annually Meat-Wild Me(W) Annually Egg Egg Annually l

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l Davis lhse Nuclew IbwerSution 1993 Annual Radiological Envimnmental Opemting Repxt Table 5: Sample Collection Summary Sample Collection Number of Number of Number of l Type Type */ Locations Samples Samples Missed  !

(Remarks) Frequency ** Collected ADIOSPIIERIC Arbome Particulates CW 10 530 0 l Anbame Radioiodine CW 10 530 0 HRRENTRIAL 1 Milk (May- Oct.) G/M 2 24 0 (Nov. Apr.) GM 2 12 0 Gmundwatcr GO 5 20 0 Edible Meat wiki G/A i 1 0 domstic G/A 2 2 0 .

Eggs G/A 2 2 0 ihud traf Vegetation / Ruit GM 5 16 0.

Soil GS 11 22 0 Animal / Wildlife Fced G'A 5 5 0 AQUAllC Treated CompWM 3 152 4 Surfax: Water GWM 4 208 0 Un:n:ated G/WM 3 156 0 Suface Water GM 10 10 3)

CompWM 4 208 0 f%(3 species) GSA 2 9 3 Sixxtline Sediments GSA 7 16 0 '

DIRECTRADIAllON Thermoluminescent CQ 111 436 8 Dosimeters C/A 111 106 5

• Type orColleaian: C = Continuous; G = Grab; Comp = Qrnposite

" Requency of Collection: WM = Weekly composited Monthly; W = Weekly; SM = Semimonthly; M = Mcxithly; O = Quarterly; SA = Semiannually; A = Annually i l

1

, 38 l l- i

Davis-Iksse Nuclear Puwer Susion 1993 Annual Ramologra! Environmenta10perating Reput Sample Analysis When environmental samples are analyzed, several types of measurements may be perfomied to provide infonnation about the radionuclides present. The major analyses that are perfonned on environmental samples collected for the Davis-Besse 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 mdionuclides. Gross beta analysis merely acts as a tool to identify samples that may require further analysis.

Gamma spectral analysis provides more specific information than does gross beta analysis. Gamma spectral analysis identities each gamma emitting radionuclide present in the sample, and the amount of each nuclide present. Each radionuclide 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 of iodine 131 in a sample. Iodine 131 is a man-made radioactive isotope of iodine that may be present in the environment as a result of fallout from nuclear weapons testing, routine medical uses in diagnostic tests,'

and routine releases from nuclear power stations.

Tritium analysis indicates whether a sample contains the radionuclide tritium (H 3) and the amount present. As discussed in Giapter One, 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 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 incor[x) rated in bone tissue. The principal strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition from airbome releases.

l Gamma Doses measured by thermoluminescent dosimeters while in the field are determined by a special laboratory procedure that is more thoroughly discussed on page 74.

Table 6 provides a listing of the types of analyses perfonned on environmental samples collected for the Davis-Besse REMP.

l Often samples will contain little radioactivity, and may be below the lower limit of detection. 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 less l than LLD (<LLD), it means that the radioactivity is so low that it cannot be accurately measured with any degree of confidence by that panicular method for an individual analysis.

I 1

1 39

l Dwis4ksse Nucksr PowerSution 1993 Annual Radiologim! Environmental Openning Regrt  !

i i

Table 6: Radiochemical Analyses Performed on REMP Samples Samole Tvoe Analyses Performed ATMOSPHERIC MONTIDRING Airbome Particulate Gross Beta Gamma Spectral Strontium-89 l Strontium-90 l

Alibome Radioiodine Iodine-131 TERRESTRIALMONITORING Milk Gamma Spectral '

lodine-131 -

Strontium-89 Strontium 90 Stable Calcium Stable Potassium

Groundwater Gross Beta l' Gamma Spectral Tritium Strontium-89 Strontium 90 Broad Leaf Vegetation Gamma Spectral and Fruits lodine 131

, Strontium-89 t l Strontium 90 l l Animal / Wildlife Feed Gamma Spectml l

l Soil Gamma Spectral-Wild and Domestic Meat Gamma Spectral Egg Gamma Spectral I

9 40

_ , - . _ . . . . . , _ . . _ . -- - ._. . . . - . _ . _ _ . . , . . _. . .. _ ~_ ;

1 Davis Iksse NuclearIbwer Station 1993 Annual Ra@bgiell Emiruvnental Operating Repo l Table 6: Radiochemical Analyses Performed on REMP Samples Samole Tyne Analyses Performed AQUATIC MONITORING Untreated Surface Water Gross Beta Gamma Spectml Tritium Strontium-89 Strontium 90 Treated Surface Water Gross Beta Gamma Spectml Tritium Strontium 89 -

Strontium 90 lodine 131 Fish Gross Beta Gamma Spectral Shoreline Sediment Gamma Spectral DIRECT RADIATION MONITORING Thermoluminescent Dosimeters Gamma Dose Sample History Comparison The concentration of radioactive materials present in the environment will vary due to factors such as weather or variations in sample collection techniques or sample analysis. His is one reason why the results .

of sample analyses are compared with results from other k3 cations and from earlier years. Generally, the results of sample analyses are compared with preoperational and operational data. Additionally, the results of indicator and control locations are also compared. His allows REMP personnel to track and trend the radionuclides present in the environment, to assess whether a buildup of radionuclides is occurring and to determine the effects, if any, the operation of Davis-Besse is having on the environment. If any unusual activity is detected, it is investigated to determine whether it is attributable to the operation of Davis-Besse, or to some other source such as nuclear weapons testing. A summary of the REMP sample analyses performed from 1972 to 1993 is provided in the following section.

41

Duvis-Iksse Nuclear IbwcrStation 1993 Annel Radiologim! Enwonmental Operming Repon Atmospheric Monitoring

• Airborne Particulates: No radioactive particulates have been detected as a result of Davis Besse's operation. Only natural and fallout radioactivity from nuclear weapons testing and the 1986 nuclear accident at Chernobyl have been detected.

Airborne Radiolodine: Radioactive iodine-131 fallout was detected in 1976,1977, i and 1978 from quclear weapons testing, and in 1986 (0.12 to 1.2 picocuries per cubic meter) from the nuclear accident at Chemobyl.

i Terrestrial Monitoring. -

Groundwater: Only naturally occurring radioactive material has been detected in l groundwater.

Milk: Iodine 131 from nuclear weapons testing fallout was detected in 1976 and 1977 at concentrations of 1.36 and 23.9 picoeuries/ liter respectively. In 1986, concentrations of 8.5 picocuries/ liter were detected from the nuclear accident at Chernobyl. No iodine-131 detected has been attributable to the operation of ,

Davis Besse.

Domestic and Wild Meat: Only naturally occurring potassium 40 and very low '

cesium-137 activity has been detected in meat samples. Potassium-40 has ranged from 1.1 to 4.6 picoeuries/ gram wet weight. Cesium-137 was detected in 1974, 1975, and 1981 due to fallout from nuclear weapons testing.

Broad Leaf Vegetation and Fruits: Only naturally occurring radioactive material l and material from nuclear weapons testing has been detected.

Soll: Only natural background and material from nuclear weapons testing and the 1986 nuclear accident at Chernobyl has been detected.

Animal / Wildlife Feed: Only natural background and material from weapons testing has been detected.

Eggs: Only natural background radioactive material has been detected.

I Aquatic Monitoring

• Surface Water (Treated and Untreated): In 1979 and 1980, the tritium concentrations at location T 7 were above normal background. Location T 7 is a beach well fed directly by Lake Erie. The fourth quarter sample in 1979 read 590 picocuries per liter, and the first quarter sample in 1980 had a concentration of 960 picoeuries per liter. A follow up sample was collected in Lake Erie between T-7 and the Davis Besse liquid discharge point. This sample contained tritium at a concentration of 2737 picoeuries per liter. These concentrations could be attributed to the operation of Davis Besse. Even so, these results at T-7 were more than 39 times lower than the annual average concentration allowed by the EPA National Interim i

1 42 I 1

I

l' Davis-Bsse Nuclev PowerStrian 1993 Annual Radiological Envirwanental Operating Report Primary Drinking Water Regulations (40CFR141), and were only 0.032% of the l 4 Maximum Permissible Concentration (MPC of 3,000,000 picoeuries per liter) for l

tritium in unrestricted areas. The follow-up sample was less than 0.1% of the MPC. ,

None of the subsequent samples indicate any significant difference between the -

l l background tritium concentration and the concentration at T-7. '

In 1991, the tritium concentration in the untreated surface water at T-130 was above .

i normal background levels. T-130 is located in Lake Erie approximately 300 yards from the mouth of the Toussaint River. The August composite read 884 picoeuries per liter. Follow up samples read less than the LLD of 330 picocuries per liter.

Although this concentration may be attributed to the operation of Davis-Besse,

it was only 0.029% of the maxium permissible concentration for tritium in an unrestricted area. This did not have any significant adverse effect on the environment  ;

or population near the station.

i The December,1992 composite for tritium at T-3 (mouth of Toussaint River) showed trace amounts of activity which may be attributed to the normal operation of the

station.The tritium concentration for the composite was 950 pCi\l. This is only 0.032 percent of the maximum permissible concentration of 3,000,000 pCi\1 for tritium in an unrestricted area, as stated in 10 CFR 20, Appendix B, Part 20, Table 2.

Subsequent samples collected during January,1993 showed that the tritium had returned to below the LLD of 330 pCi\l.

Fish: Only natural background radioactive material and material from nuclear testing ]

has been detected. i 1

Shoreline Sediments: Only natural background, material from nuclear testing and l 4

from the 1986 nuclear accident at Chernobyl has been detected.

]

Direct Radiation Monitoring-l Thermoluminescent Dosimeters (TLDs): The annual average gamma dose rates l recorded by TLDs have ranged from 42 to 87 millirem per year at control locations l

.; and between 36.8 and 86.1 millirem per year at indicator locations. No increase )

i above natural background radiation attributable to the operation of Davis-Besse has been observed.

l l

43 l

Davis Besse Nuclesr IbwerStation 1993 Annual Radiological Envimoznental Opemting Report l

l l

1993 Program Deviations  ;

1 1

Provided below is a description and explanation of 1993 environmental sample collection deviations.

A grab sample of untreated surface water at T-3 (Toussaint River) was unavailable on the following collection days 1/11/93,1/18/93 2/22/93 and 3/1/93 because the water  ;

was frozen. A water sample was collected from the Davis-Besse Water Treatment l Plant per departmental procedures. The water was then split with the Ottawa County Department of Health.

On 1/25/93, at T-28, a grab sample was obtained instead of a composite sample. The water compositor malfunctioned during that collection period. The compositor was repaired and returned to sevice for the next sampling period.

On 3/8/93, the air sampling pump at T-9 had 56.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of run time because of a blown fuse. A new fuse was installed and air sampler was returned to services.

There was no data available for first quarter TLD at T-126. TLD was lost in the field due to vandalism.

On 4/13/93, the air sampling pump at T-12 had 143 hour0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br /> of run time because of a ~

power outage caused by adverse weather conditions. The sampler was returned to service same day for the next sampling period.

The air sampling pump at T-4 had 59.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> run time for sample collected on 6/7/93 because a squirrel shorted the transformer and blew a line fuse. Power was restored to location and the pump returned to service.

No data was available for second quarter 1993 TLDs at T-51, T-113, T-126 and T-204. TLDs were lost in the field due to vandalism.

The untreated water sample collected on 9/20/93 at T-28 may not have been a representative sample of the entire sampling because of a malfuction in the compositor . A new sampler was installed and placed in service.

No data was available for third quarter 1993 TLDs at T-119 and T-150. TLDs were lost in the field due to vandalism.

A T-33 fish sample was unavailable for the second half of 1993 because of seasonal unavailablity. A sample was collected the first half of the year.

On 11/8/93, the air sampling pump at T-4 malfunctioned after 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of run time for that sampling period. A new pump was installed for the next sampling period.

The required LLD for I-131 was not reached for this sampling period.

On 12/27/93, a composite sample of untreated surface water at T-12 was unavailable from the Toledo Water Works. A grab sample was collected per the sampling procedure.

44

I i

! Davis-Besse NLclex PowerStation 1993 Annual Radiological Environmental Operating Reprt i

l i No data was available for 1993 annual TLDs at T-51, T-63, T-74, T 113, T-126 and i

T-204. TLDs were lost due to vandalism. l Lake Erie water samples were not obtained from T-131, T-132, T-133, T-134, T-135, I

T-137, T-152, T-158, T-162 and T-167 during May and October due to hazardous weather conditions.

l l

Atmospheric Monitoring Air Samples j l

Environmental air sampling is conducted to detect any increase in the concentration of airbome l

radionuclides that may be inhaled by humans or serve as an extemal radiation source. Inhaled radionuclides may be absorbed from the lungs, gastrointestinal tract, or from the skin. Air samples collected by the

)

Davis-Besse REMP include both airborne particulates and airborne radiolodine. l l J l

Samples are collected weekly with low volume vacuum pumps which draw a continuous sample through a particulate glass fiber filter and charcoal cartridge at a rate of approximately one cubic foot per minute. l Airbome particulate samples are collected on a 47 mm diameter membrane filters. Charcoal canridges are installed downstream of the particulate tilter to sample for the presence of airbome radiciodine.

The airbome samples are sent to an offsite contractor laboratory for analysis. At the laboratory, the airbome paniculate filters are stored for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before they are analyzed to allow for the decay of naturally occurring short-lived radionuclides. However, due to the shon half-life ofiodine-131 (approximately eight days), the airbome mdioiodine canridges are analyzed upon receipt by the contractor j laboratory.

Airborne Particulates l

l Davis-Besse continuously samples air for airborne radionuclides at ten locations. There are six indicator l locations including four around the site boundary (T-1, T-2, T-3, and T-4), one at Sand Beach (T 7), and another at a local fhrm (T-8). There are four control locations, Oak Harbor (T-9), Pod Clinton (T-11).

Toledo (T-12) and Magee Marsh (T-27).

Gross beta analysis is performed on each of the weekly samples. Each quaner, the filters from each k3 cation are combined (composited) and analyzed for gamma emitting radionuclides, strontium-89 and strontium 90. Beta emitting radionuclides were detected at both indicator and control location at a 3 3 concentration of 0.021 pCi/m and 0.022 pCi/m . Beryllium-7 was the only gamma emitting radionuclide detected by the gamma spectroscopic analysis of the quanerly composites. Beryllium-7 is a naturally occurring radionuclide produced in the upper atmosphere by cosmic radiation. No other radionuclides were detected above their respective LLDs. Strontium 89 was not detected above its LLD of 0.0016 pCi/m3 .

Strontium-90 was detected in one sample (T-3) above the LLD of 0.0004 pCi\m 3.The concentmtion i

i 45 1

Davis-Iksse Nuclesr PowerStation 1993 Annual Radiological Erwironmental Operating Report detected at this site was 0.0007 pCi\rn'.These results show no adverse change in radioactivity in air samples due to operation of Davis-Besse Nuclear Power Statica in 1993.

Airborne Iodine-131 Airborne iodine-131 samples are collected at the same ten locations as the airborne particulate samples. Charcoal cartridges are placed downstream of the particulate filters. These cartridges are collected weekly, sealed in separate collection bags and sent to the laboratory for gamma spectral analysis. In all of the samples collected in 1993, there was no detectable iodine-131 above the LLD of 0.07 pCi/m'. On 11/3/93 at T-4, the required LLD for I-131 could not be reached because of low sample volume for that sampling period. The low volume was a result of a blown fuse in the pump. The LLD reached for this sample was <0.10 pCi\m'.

Airborne Particulates .

Gross Beta pCI/m3 0.04 0.03 -- - - - - -

1 Nr 0.02 -- - - - - - - - -

1 0.01 -- - - - - - - -

i l

1 0 '

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1993

• Indicator + Control f'igure 11: Concx:ntmtion of beta emitting mdionuclicks in airtxrne paniculates samples were asentially identical at indicat(r and wntml kx:ations.

46

. ___ ._. - . . _ ._ . . . ._ . _ .. _ _. _ _ _ . ~. ____ _

Duve Bess: Nuclex FbwerStaion 1993 Annual Radiologim! Envuuvnental Operating Repxt 4

!- Table 7: AirMonitoring Imations Samplelocation Type of Location Description i Number Location T-1 I Site boundary,0.6 miles ENE of Station j T-2 I Site boundary,0.9 miles E of Station I T-3 I Site boundary,1.4 miles ESE of Station 1

1 j T-4 I Site boundary,0.8 miles S of Station T-7 I Sand Beach, main entrance,0.9 miles NW of

] Station i

) T-8 I Earl Moore Farm,2.7 miles WSW of Station i

T-9 C Oak Harbor Substation, 6.8 miles SW of  !

l Station e

T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station i

T-12 C Toledo WaterTreatment Plant,23.5 miles WNWofStation f

! T-27 C Crane Creek State Park,5.3 miles WNW of Station i

3 I = Indicator C = Control E

i i

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! Jm Mksse Nuclear PowerStation 1993 Annual Radiological Environmental Operating Report 1

, Terrestrial Monitoring 1

The collection and analysis of groundwater, milk, meat, fruits and broad leaf vegetation provides data to assess the buildup of radionuclides that may be ingested by humans. Animal and wildlife feed samples provide additional information on mdionuclides that may be present in the food chain. He data from soil

, sampling provides information on the deposition of radionuclides from the atmosphere.

Many radionuclides are present in the environment due to sources such as cosmic radiation and fallou+

fron, nuclear weapons testing. Some of the radionuclides present are

3 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, beryllium 7, present as a result of the interaction of cosmic radiation with the upper atmosphere, 5

l -

cesium 137, a man-made radionuclide which has been deposited in the environment, 4

(for example, in surface soils) as a result of fallout from nuclear weapons testing and j routine releases from nuclear facilities, potassium-40, a naturally occurring radionuclide normally found in humans and ^ ,

throughout the environment, 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 i in the vicinity of the Davis-Besse Station. The contribution of radionuclides from the operation of

' Davis-Besse is assessed by comparing sample results with preope ational data, operational data from j previous years, control location data, and the types and amounts of radioactivPv normally released from the Station in liquid and gaseous effluents.

4 j Milk Samples

, Milk sampling is very important in environmental surveillance because it provides a direct basis for assessing the build up of radionuclides in the environment that may be ingested by humans. Milk is  ;

particularly important because it is one of the few foods commonly consumed soon after production. The  !

milk pathway involves the deposition of radionuclides from atmospheric releases onto forage consumed by l cows. He radionuclides present in the forage eating cow become incorporated into the milk which is then I consumed by humans.

Samples of milk are collected at one farm and a commercial dairy store once a month from November through April, and twice a month from May through October. Sampling is increased in the summer when the herds are usually outside on pasture and not on stored feed. He sample locations consist of one indicator (T-8) and one control locations (T 24 ). In December, T-8, Moore Farm, was eliminated from the sampling program because they went out of the dairy business and sold the herd. T-24 will continue to be l

51

Davis.Besse Nuclear IbwerStation 1993 Annual Radiological Emironmental Opemting Repun collected in order to gather additional baseline data. If any dairy animals are discovered within five miles of the station, efforts will be made to include them in the milk sampling program.

The milk samples are analyzed for strontium-89, strontium-90, iodine 131 and other gamma emitting radionuclides, stable calcium and potassium. A total of 36 milk samples were collected in 1993.

Strontium-89 was not detected above the LLD of 1.1 pCi/l in any of the samples. Strontium-90 was detected in all 36 samples collected. Re annual average concentration of strontium-90 was 1.2 pCi/l at both indicator and control locations. For all sample sites, the annual average concentration was similar to

< those measured in the previous years (Figure 15).

A total of 36 analyses for iodine-131 in milk were performed during 1993. Iodine-131 was not detected in milk samples above the LLD of 0.5 pCi/1. De concentrations of barium-140 and cesium-137 were below their respective LLDs in all samples collected. He results for potassium-40, a naturally occurring radionuclide were similar at indicator and control locations, as to be expected.

Since the chemistries of calcium and strontium are similar, as are potassium and cesiums, organisms tend to deposit cesium radioisotopes in muscle tissue and strontium radioisotopes in bones. In order to detect the

! potential environmental accumulation of these radionuclides, the ratios of the strontium radioisotopes radioactivity (pCi/l) to the concentration of calcium (g/l), and cesium radioisotopes radioactivity (pCi/1) to the concentration of potassiurn (g/l) were monitored in milk. These ratios are compared to standard values to determine if build up is occurring. No statistically significant variations in the ratios were observed. De results of the analyses performed on the milk samples collected in 1993 indicate no effect due to the operation of Davis-Besse.

MILK CONCENTRATION OF SR-90 gm 3

e i 2 -- -

c-s k .

i ,

0 , "- "-- -

77 78 79 80 81 82 83 84 85 SS 87 88 88 90 91 92 93 YEAR Ebdicator 8oontrol Figure 15:1he 1993 avemge canantration of strontium-90 deteced. in milk samplcs, was similar at indicitor and control kcitiors, a trend exhibited in pn:viam years.

88 52

l Davis Base Nuclex Fbwer Station 1993 Annual Ibfolognt! Envimnmental Operating Repon Table 8: Milk Monitoring Locations Sample Location Type of Location Description Number location l l

l l

T-8 I Moore Farm,2.7 miles WSW of Station l l

T-24 C Toft Dairy, Sandusky,21.0 miles SE l ofStation I = indicator C = control Groundwater Samples

, It is unlikely that groundwater will accumulate radioactivity from nuclear facilities, except for those

! facilities which discharge liquid effluents to the ground via cribs, pits, or trenches. This is because the soil

! acts as a filter and an ion exchange medium for most radionuclides. However, tritium and other radionuclides such as ruthenium-106 have a potential to seep through the soil into the groundwater.

Although Davis-Besse does not discharge its liquid effluents directly to the ground, REMP personnel sample local wells on a quarterly basis to ensure the detection of any adverse impact on the k) cal groundwater supplies due to Station operation. The four wells sampled include two indicator locations (T-7, T-54), and two control locations (T-23, T-27). In addition, a quality control sample is collected at one of the four wells each quarter.

The groundwater samples are analyzed for beta emitting radionuclides in dissolved and suspended solids, tritium, strontium-89, strontium-90 and gamma emitting radionuclides. Beta emitting radionuclides in suspended solids were detected in one indicator sample (T-7) at a concentration at 0.2 pCi\l. In dissolved solids, the concentration averaged 3.7 pCi/l at indicator locations and 2.4 pCi/l at control locations (figure 16). Tritium was detected in one sample above the LLD of 330 pCi/l. The sample collected during second quarter at T-7, Sand Beach, had tritium detected at a concentration of %5*125 pCi/1. This may be attributable to normal operation of the plant. Also, strontium-89 was not detected above the LLD of 1.3pCi/1. Strontium-90 was detected in three indicator samples at an average of 0.6 pCi/l. There were no l gamma emitting mdionuclides detected above their respective LLDs in any of the samples collected. All sample analyses were within normal ranges and were similar to results of previous years with the exception of T-7, tritium which is mentioned above.

I I

53

Davis Besse Nuckx PowerStakx1 1993 Amual F*leght Envutximental Openiting Repyt i l

Groundwater 1 Gross Beta pC1/1 10 g -.

S --

4 _

g- , -N_

2 --

/\ ,

0 82 88 84 SS SS 87 SS SS 90 91 92 SS year

+ 1ndioseer ~ Contrei Figun:16: Shown above are the annual averages for gross beta in groundwater fnxn 1982 - 1993. The 1993 resultsan:well within the rangeofpn:vxus ycirs.

Table 9: Groundwater Monitoring Locations Sample location Type of Location Description Number Imtion

~

T-7 I Sand Beach,0.9 miles NW of Station T-23 C Put-in-Bay Waterworks,14.3 miles ENE of Station T-27 C Cmne Creek State Park,5.3 miles WNW of 1

Station T-54 I Weis Farm,4.8 miles SW of Station T-141 QC Roving Site I I = indicator C = control QC = quality control I i

54 l

Dmis-lhse Nuclex lbwerSuaion 1993 Amual Raliologimi Envirmnental Operuting Reprt

Broad Leaf Vegetation and Fnsit Samples Fruits and broad leaf vegetation also represent a direct pathway to humans from ingestion. Fmits and broad leaf vegetation may become contaminated from atmospheric deposition from airbome sources (nuclear 4

weapons fallout or airbome releases from nuclear facilities) or from irrigation water drawn from lake water receiving liquid effluents (from hospitals, nuclear facilities, etc.). Also, radionuclides from the soil may be l absorbed by the roots of the plants and become incorporated into the edible portions. During the growing season (July through September), edible broad leaf vegetation, such as spinach and cabbage, and fruits,

, such as apples and grapes, are collected from farms in the vicinity of Davis-Besse. l l

j In 1993, broad leaf vegetation samples were collected at two indicator locations (T-8 and T-25) and one control location (T-37). Fruit samples w re collected at two indicator locations (T-8 and T-25) and three control locations (T-23, T-37 and T-173). Broad leaf vegetation was collected once a month during the growing mn. Broad leaf vegetation colleved consisted of horseradish leaves, lettuce, cabbage and Swiss 4

chard. he fmits collected were apples, pears, pumpkins, grapes and grape juice. All samples were j analyzed for gamma emitting radionuclides, strontium-89, strontium-90, and iodine-131.

1 Iodine-131 was not detected above the LLD of 0.043pCi/g wet in any broad leaf vegetation and LLD of 0.057 pCi% wet in fmit samples. He only gamma emitting radionuclide detected in the fruit and broad leaf vegetation samples was potassiura-40, which is naturally occurring. In both fruit and broad leaf -

l vegetation, strontium-89 was not detected above LLD of 0.006 pCi/g wet. Strontium-90 was detected at a l concentration of 0.006 pCi/g wet for indicator hx:ations and 0.005pCi/g wet for control locations. In the

)

fruit samples , Sr-90 was not detected above LLD of 0.001 pCi/g at indicator locations. However, Sr-90 ,

avemged 0.003 pCi/g at control locations. All results of analyses were similar to results observed in l i previous years; it also demonstrates that the operation of Davis Besse has had no adverse effect on the e surrounding environment.

4 4

Table 10: Broad Leaf Vegetation and Fruit Locations Sample Number Type of Location Description y Location Location l

i

. T-8 I Moore Farm,2.7 miles WSW of Station i

T-23 C Heineman Winery, Put-In-Bay,14.3 miles ENE of Station. I

I l

l

)3 T-25 I Miller Farm,3.7 miles S of Station l

l l T-37 C Bench Farm,13.0 miles SW of Station '

l T-173 C Firelands Winery, Sandusky,20.0 miles SE of station. I 1

I = indicator C = control 4

55

l

Davis Iksse Nucle'r PowerStation 1993 Arswal Radblogicil Enwonmenta10perating Reput l

Animal / Wildlife Feed Samples As with broad leaf vegetation and fmit samples, samples of domestic animal feed, as well as vegetation consumed by wildlife, provide an indication of airbome radionuclides deposited in the vicinity of the Station. Analyses of animal / wildlife feed samples also provide data for determining radionuclide ,

concentration in the food chain. Domestic animal feed samples are collected at one milk location and two domestic meat sampling locations. Wildlife feed samples are collected from the Navarre Marsh onsite and from a local marsh within five miles of the Station. As in all terrestrial samples, naturally occurring potassium-40, cosmic ray produced radionuclides such as beryllium-7, and fallout radionuclides from nuclear weapons testing may be present in the feed samples.

Domestic animal feed was collected annually at dairy farms and annually at chicken sampling locations. There are two indicator locations (T-8 and T-197) and one control location (T-34). The feed collected consisted of hay, mixed feed, and chicken feed. All samples were analyzed for gamma emitting radionuclides. In December, the T-8 feed sample was eliminated from the sampling program because the dairy farm went out of business.

Wildlife feed was collected annually at two locations (T-31 and T-198). The samples consisted of the edible portion of millet and smartweed. Samples were analyzed for gamma emitting radionuclides.

In both the animal and wildlife feed, only naturally occurring Be-7 and K-40 were detected. All other radionuclides were below the respective LLDs. The operation of Davis Besse had no adverse effect on the surrounding environment.

Table 11: Animal / Wildlife Feed Locations SampieIax:ation Type of Location Description Number Location T-8 I Moore farm,2.7 miles WSW of Station l

T-31 1 Davis-Besse, onsite roving location T-34 C Bertsch farm, Sandusky,20.0 miles SE ofStation i T-197 I Preisman Farm 1.7 miles W of Station T-198 I Toussaint Creek Wildlife Area 4.0 miles WSW of Station I = indicator C = control I

56 i

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

Davi@c Nelex PowerStation 1993 Annual Radiologiad Enwonrnental Operating Re[ut Wild and Domestic Meat Samples Sampling of domestic and wild meat provides information on environmental radionuclide concentrations that humans may be exposed to through an ingestion pathway. The principle pathways for radionuclide contamination of meat animals include atmospheric deposition from airbome releases on their fcxxi, contamination of their drinking water through atmospheric deposition or contamination of their drinking water from radionuclides released in liquid effluents.

1 i

The REMP generally collects wild meat and domestic meat (chickens) and eggs on an annual basis. Wild animals commonly consumed by residents in the vicinity of Davis-Besse include waterfowl, deer and muskrats. Analyses from animals whose meat is eaten by huma'ns provides general information on radionuclide concentration in the food chain. When evaluating the results from analyses performed on meat animals, it is important to consider the age, diet and mobility of the animal before drawing conclusions on mdionuclides concentration in the local environment or in a species as a whole.

Both wild and domestic meat samples and eggs were sampled in 1993 as fellows:

Domestic Meat: Chickens were collected at one indicator location (T-197) and one control location (T-34). I Wild Meat: A Canada goose was collected from the marsh on site (T-31). The sample was analyzed for gamma emitting radionuclides.

Eggs: E'ggs were collected from one indicator location (T-197) and one control location (T-34). The eggs were analyzed for gamma emitting radionuclides.

The only gamma emitter detected in all the samples was potassium-40 which is naturally occurring. The j Canada goose sample collected at T 31 had trace amounts of cesium 137 detected at a concentration of 0.032 pCi% wet. Small amounts of Cs-137 are not uncommon in meat samples from older animals such as this one. Due to the migratory habits of the Canada goose it is difficult to determine whether the Cs-137 is i attributable to the operation of Davis-Besse or some other source.

Table 12: Wild and Domestic Meat Locations I Sample location Type of Location Description Number Location T-31 1 Onsite roving location T-34 C Bertsch Egg Farm, Sandusky,20.0 miles SE of Station T-197 I Priesman Farm,1.7 miles W of Station I = indicator C = control 57

Davis-B<sse Nuclear Power Station 1993 Annual lhxiiobgical Envirtr5nentat Opemting Reprt Soil Samples Soil samples are generally collected twice a year at all sites which are also equipped with air samplers.

Only the top layer of soil is sampled in an effon to identify possible trends in the local environmental nuclide concentration caused by atmospheric deposition of fallout and station released radionuclides.

Generally, the sites are relatively undisturbed, so that the sample will be representative of the actual deposition in the area. Ideally, there should be little or no vegetation present, because the vegetation could effect the results of analyses. Approximately five pounds of soil are taken fmm the top two inches at each site. Many naturally occurring radionuclides (eg. beryllium -7, and potassium-40) and fallout radionuclides from nuclear weapons testing are detected. Fallout radionuclides which are often detected include strontium-90, cesium-137, cerium-141 and ruthenium 106. l During 1993, soil was collected at eleven sites in April and October. The indicator locations included T-1, T-2, T-3, T-4, T-7, and T-8. The control locations were T-9, T-i l, T-12, T-23, and T-27. All soil samples were analyzed for gamma emitting radionuclides. The results show that the only gamma emitter detected in addition to naturally occurring Be-7 and K-40, was Cs-137. Cs-137 was found in both indicator and control location at a concentration of 0.25 and 0.41 pCi/g dry respectively. The concentrations were similar to that observed in previous years (Figure 17).

~

Soil Cesium 137 pCM dry 2

1.5 -

Ind!ostor I ,

Control s

0.5  : -

O I- '

73 75 77 79 81 83 85 87 88 91 93 Figure 17:'Ihc axxx:ntmtion of cxsium-137 in soil tus remained fairly aristmt over the year REMP tus been ariducted. 'lhe peak seen in 1978 was due to fallout fmm nuclear weapns testing.

58 l

l

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

Dmis-Iksse Nuclear Power Stalian 1993 Annual Radiologkul Envuonmenta10perating Report Table 13: Soit Locations Sample Location Type of Location Description i

Number Location T-1 I Site boundary,0.6 miles ENE of Station . ,

T-2 I Site boundary,0.9 miles E of Station i

T-3 I Site boundary 1.4 miles ESE of Station T-4 I Site boundary 0.8 miles S of Station T-7 I Sand Beach, main entrance,0.9 miles NW ofStation T-8 I Moore Farm,2.7 miles WSW of station  ;

T-9 C Oak Harbor Substation,6.8 miles SW of Station i

T-11 C Port Clinton Water Treatment Plant,9.5 miles  !

SE of Station l

T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station T-23 C South Bass Island,14.3 miles ENE of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station I = indicator C = control 59

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Davis IksseNuctear PowerSunion 1993 Annual Rulioksical Envimnmental Operating Report 4

i Aquatic Monitoring.

t Radionuclides may be present in Lake Erie from many sources including atmospheric deposition, run-off/ soil erosion, and releases of radioactive material in liquid effluents from hospitals or nuclear facilities. These sources provide two forms of potential exposure to i radiation, external and internal. - External exposure can occur from the surface of the water, a shoreline sediments and from immersion (swimming)in the water. Internal exposure can occur

$ from ingestion of radionuclides, either directly from drinking water, or as a results of the transfer j of radionuclides through the aquatic food chain with eventual consumption of aquatic organisms,

such as fish. To monitor these pathways, Davis-Besse samples treated surface water (drinking 1 water), untreated surface water (lake or river water), fish, and shoreline sediments.

]

Treated Surface Water 3

Treated surface water is water from Lake Erie which has been processed for human consumption.

] Radiochemical analysis of this processed water provides a direct basis for assessing the dose to humans ,

j from ingestion of drinking water, l

1 I Samples of treated surface water were collected from three indicator (T-28, T-50, and T-144) and three.

} control locations (T-11, T-12, and T-23). Rese locations include the water treatment facilities for Davis-Besse, Erie Industrial Park, Port Clinton, Toledo, Green Cove, and Put-In Bay. Samples were collected weekly and composited monthly. The monthly composites were analyzed for beta emitting radionuclides. he samples were also composited in a quarterly sample and analyzed for strontium-89, strontium-90, gamma emitting radionuclides, and tritium. One OC sample was collected from a routine location which was changed each month.

In treated water samples, beta emitting radionuclides were not detected above the LLD of 0.4 pCiA for suspended solids. He average concentration was similar in dissolved solids for indicator and control locations (2.2 and 2.1 pCiA, respectively). He annual average for beta emitting radionuclides for all indicator and control location was similar to previous years as shown in Figure 21. One quanerly treated surface water sample at T-144 (Green Cove) had tritium detected at a concentmtion of 355 pCiA. All other quarterly tritium analysis results were less than the LLD of 330 pCiA.

All cesium-137 results were less than the LLD of 10.0 pCiA. Strontium-89 and strontium 90 were not  !

4 detected in any sample above 1.5 and 1.0 pCiA, respectively. These results are similar to those of previous years and indicate no adverse impact on the environment resulting from the operation of Davis-Besse.

J 1

i e

63 ,

{

Duvs.Besse Nuclar PowerStaxx1 1993 Annual Ibdiological Enytrtunental Operating Repxt TREATED SURFACE WATER

! Gross Beta l pCN 4

l s .....j.

j 8 '.

• INDICATOR 2 - - -

+ CONTMOL l

1 i

73 75 77 7s at as as s7 se si es Year Figure 21: Over the ptst 19 yeus, the annual anuitr tions of beta emitting rationuclides in treated surftxe water sarnples colleced fmm indianor locations have been ansistent with itxme frtxn control locitions. 'Ihis shows that Dass-lhse has had i no measunble radiologiati impx2 on surf:ce water tecd to make drinking water.

l Table 14: Treated Surface Water Locations l Sample Location Type of Location Description

) Number Location T-11 C Pott Clinton Water Treatment Plant 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant 23.5 miles WNW of Station l

T-23 C Put-in-Bay Water Treatment Plant 14.3 miles ENE of Station.

T-28 i Treated Water supply from Davis-Besse site T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE of Station T-143 QC Ouality Control Site T-144 I Green Cove Condominiums,0.9 miles NNW of Station I = indicator C = control QC = quality control 64 l

l l

Davis-Ihse Nuclex PowerStation 1903 Annual lkdiokyknl Environmental Openting Repon Untreated Surface Water i Sampling and analysis of untreated surface water provides a method of assessing the dose to humans from l extemal exposure from the lake surface as well as immersion in the water. It also provides infon.. . tion on the radionuclides present which may affect drinking water, fish, and irrigated crops.

Routine Program:

The routine program is the basic sampling progmm which is performed year round. Untreated water samples are collected in the areas of the station intake and discharge and at the water intakes used by nearby water treatment plants. Routine samples are collected at Port Clinton, Toledo, Davis-Besse, Erie Industrial Park, and Put-in Bay WaterTreatment Plants. A sample is also collected from I;ike Erie at the mouth of the Toussaint River. These samples are collected weeldy and composited monthly. The monthly composite is analyzed for beta emitting radionuclides, tritium, and gamma emitting radionuclides. The samples are further composited quarterly and analyzed for strontium-89 and strontium-90. A QC sample is collected weekly at a different location each month.

Summer Program :

The summer program is designed to supplement the routine untreated water sampling program in order'to  ;

provide a more comprehensive study during the months of high lake recreational activity, such as boating.

fishing, and swimniing. These samples are obtained in areas along the shoreline of I;ike Erie.The samples are collected monthly and analyzed for beta emitting radioactivity, tritium, strontium-89, strontium-90 and l

gamma emitting mdionuclides. '

Beta emitting radionuclides in suspended solids averaged 0.5 pCi/l and 0.6 pCi/l at indicator and control locations, respectively. Beta emitting radionuclides, in dissolved solids had an average concentration of 2.8 pCi/l at indicator and 2.5 pCi/l at control k) cations.

Of the 11.* /itium analyses performed on untreated water,11I were less than the LLD of 330 pCi/l.The September sample collected at T-50 (Erie Industrial Park) had tritium detected at a concentration of  ;

622i115 pCi/1. It is presumed that the tritium was caused by something other than the operation of I Davis-Besse.The reason is T-50 is 4.5 miles from the station and no other sample k) cation between there and Davis-Besse showed any tritium detectable above the LLD. The tritium detected is only 0.062 percent of the effluent concentmtion limit of 1,000,000 pCi/l for tritium in an unrestricted area, as defined in l 10CFR20, Appendix B, Part 20, Table 2. '

Cesium-137 and strontium-89 were not detectable in samples of untreated water above their LLDs of 10 pCi/l and 1.6 pCi/1, respectively. Strontium-90 was detected at an average concentration of 0.7 pCi/l at indicator locations and 0.6 pCill at control locations. The result of untreated water show that the operation of Davis-Besse had no adverse impact on nearby residents or on the environment.

I 65 l

l i

DevbIhv NuclesrIbwerStaxn IW3 Annual Radicbgical Envirmmental Opemung Reint Untreated Surface Water i Gross Beta N

1 l g .

g -. ,

illlhill um 8 -

77 78 79 SS 8182 SS 84 SS SS 87 SS SS SS S192 SS Year Eindioneer 8contrei ,

Figure 22: The average concentration of beta anitting rationuclids in untreated water was similar between contml and indnacr kna kvs. 'Ihis demonstrate, that Davs-Iksse hal no radiologia11 impact on the sumuxling awironment.

Each month, weekly quality contml samples were collected at different locations. He results of the analyses from the quality control samples were consistent with the routine samples. The average concentrations of beta emitting radionuclides detected at the OC location was 3.1 pCi/l and 2.9 pCi/l at routine locations. Tritium and cesium 137 were below their respective LLDs. There wm good agreement between the routine and OC locations.

Table 15: Untreated Surface Water Locations Sample Location Type of Location Description Number location T-3 I Site tx)undary,1.4 miles ESE of Station T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station T 12 C Toledo Water Treatment Plant, sample taken from intake crib,11.25 miles NW of Station 66

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

l Davis-Dsse Nuclear ibwerSution 1993 Anntal Radiologim! Emm1 mental Opemting Repxt I I

l Table 15: Untreated Surface Water Locations (continued)

Sample Location Type of location Description  ;

Number Ixcation l T-23 C- Put-In-Bay WaterTreatment Plant,14.3 miles ENE ofStation i

T 28 I Davis-Besse WaterTreatment Plant T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE ofStation T-131 1 12ke Erie,0.8 miles NE of Station T-132 I 12ke Erie,1.0 miles E of Station l i

T-133 I Lake Erie,0.8 miles N of Station T-134 I Lake Erie,1.4 miles NW of Station T-135 1 Lake Erie,2.5 miles WNW of Station T-137 C 12ke Erie,5.8 miles WNW of Station

- T-138 C 12ke Erie,11.0 miles NW of Station T-145 OC Roving Quality Control Site T-152 C 12ke Erie,15.6 miles WNW of Station T-158 C Lake Erie,10.0 miles WNW of Station T-162 C Lake Erie,5.4 miles SE of Station T-167 C Lake Erie,11.5 miles E of Station I = indicator C = control r

I 67 l

.., - _. _ . . .,-, , _ . , _ _ _ _ , . - _ ~ ,.-m..,, - , . . . ..,,,.m,,...mm,~..,._..~,ww.,,~,,,

Davis Beic Nuclear ibwcrStation 1993 Annual Radological Environraenta10pemting Repon Shoreline and Bottom Sediment 1

The sampling of shoreline and bottom sediments can provide an indication of the accumulation of undissolved radionuclides which may lead to internal exposure to humans through the ingestion of fish, through resuspension into drinking water supplies, or as an external radiation  !

source from shoreline exposure to fishermen and swimmers.

)

Samples of deposited sediments in water along the shore and from the bottom, were collected at various times from four indicator sites (T 3, T-4, T-130, and T-132) and four control location (T-23, T-27, T-138, and T-164). Shoreline sediment was collected with a shovel, while bottom sediment was collected with a hand held dredge. - All samples were analyzed for gamma emitting radionuclides. Naturally occurring potassium 40 was detected at both controls and indicator locations. Cesium-137 was detected at a concentration of 0.13 pCi/g at indicator locations and 0.31 pCi/g at control locations.

I Atmospheric testing of nuclear weapons has been the principal source of cesium 137 in the environment to date. Although no atmospheric nuclear weapons tests have been reported since 1980, cesium-137 is still l present in shoreline sediment samples because of its long half life (approximately 30 yeam). No other j gamma emitting radionuclides were detected in any of the samples. The concentrations of those detected l were consistent with nomial concentrations for this area and were not attributed to plant operation. -

l Table 16: Shoreline and Bottom Sediment IAcations Sample location Type of Location Description Number location T-3 I Site boundary,1.4 miles ESE of Station T4 I Site boundary,0.8 miles S of Station T-23 C South Bass Island,14.3 miles ENE of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station T-130 I 12ke Erie,1.7 miles ESE of Station T-132 I Lake Erie,1.0 miles E of Station T-138 C 12ke Erie 11.0 miles NW of Station T-164 C Lake &ie,9.5 miles ESE of Station I = indicator C = control 68

Davis-Ikse Nuclear Ibwer Statko tw3 AnnualILiiologul Envimnmentaloperating Rejut Fish Samples Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondarily to serve as indicators of radioactivity in the aquatic ecosystem. The principal nuclides which may be detected in fish include naturally occurring potassium-40, as well as cesium 137, and strontium-90. Depending upon l the feeding habit of the species (e.g., bottom-feeder versus predator), results from sample analyses may vary.

With the aid of a local commercial fisherman, Davis-Besse routinely collects three species of fish (walleye, white perch and carp) twice a year from sampling locations near the Station's liquid discharge point and more than ten miles away from the Station where fish populations would not be expected to be impacted by the Station opemtion. Walleye are collected because they are a popular sport fish, white perch or white bass because they are an important commercial fish. Carp are collected because they are bottom feeders and thus would be more likely to be affected by mdionuclides deposited in lake sediments. De edible portion of fish were analyzed for beta and gamma emitting mdionuclides.

The average concentration of beta emitting radionuclides in tish muscle was similar for indicator and control locations (3.51 pCi/g and 2.95 pCi/g wet weight, respectively). Cesium 137 was detected in a walleye sample at T 35, a control kration. He concentration of Cs-137 was 0.019 pCi/g which is similar i to concentration of previous years.

l 1

1 FISH SAMPLES i Gross Beta Indicator vs Control t

pC4 wW 5 '

l 4

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dddd78 Ti737930818283 SdS68887 SS 3090910203 war l EINDICTATon O CONTROt.

Figure 23: Average crnrntrations of beta emitting nKlianuclkks in fhh samples were sim tlar at indicitor and amtrol katans and were within the range of results of pn:vious yern.

69

Davis-Iksse Nuclear IbwerStauan 1993 Annual Radiological Envum5nental Operating Repon Table 17: Fish Imations Sample location Type of Location Description Number Location T-33 I Lake Erie, within 5 miles radius of Station T-35 C L*e Erie, greater than 10 mile radius of Station I = indicator C= control 6

1 70

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Davis Bec Nuclear PowerStation 1993 Annual Rmiiokyim! Envimnmental Opemting Repxt DIRECT RADIATION MONITORING Thermoluminescent Dosimeters Radionuclides present in the air, and those deposited on the ground, cause dose to humans due to the immersion of the human in the atmosphere or by the human walking, standing, etc. on the ground. Direct radiation levels at and around Davis-Besse are constantly monitored by thermoluminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information. The TLDs used at Davis-Besse contain a calcium sulfate: dysprosium (CaSO,:Dy) card with four main readout areas. Multiple readout areas are used to ensure the precision of the measurements.

Thermoluminescence is a process by which ionizing mdiation interacts with the sensitive material in the TLD, the phosphor. 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 ofinteraction with radiation is released and measured by a controlled heating process in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy in the form of light. He amount of light detected is directly proportional to the amount of radiation to which the TLD was exposed. The reading process rezeros the TLD and prepares it for reuse.

TLD Collection l Davis-Besse has 94 TLD k) cations (71 indicator and 23 control) which are collected and replaced on a l quarterly and annual basis. Eighteen OC TLDs are also collected on a quarterly and annual basis. There l is a total of 224 TLDs in the environment surrounding Davis-Besse at any given time. By collecting TLDs i on a quarterly and annual basis from a single site, the two measurements serve as a quality control check on each other. )

1 In 1993, the dose equivalent for quarterly TLDs at all indicator locations was 14.4 mrem /91 days, and for I all control locations was 15.5 mrem /91 days. De average dose equivalent for annual TLDs in 1993 was l 56.1 mrem /365 days at indicator locations and 63.2 mrem /365 days for control k) cations. There was a slight increase in dose observed during the third quarter. This increase was assumed to be caused by natural ,

fluctuations in the background dose rate. These results are similar to those observed in previous years. I t

Quality ControlTLDs Duplicate RDs have been placed at 18 sites. These TLDs were placed in the field at the same time and at the same location as some of the routine TLDs, but were assigned quality control site numbers. This allows us to take several measurements at the kication without the laboratory being aware that they are the same. A comparison of the quality control and routine results provides a method to check the accumey of

the measurements. The average dose equivalent at the routine TLDs averaged 15.7 mrem /91 days while the quality control RDs yielded an average dose equivalent of 15.3 mrem /91 days. All the quality control and routine sample results were similar, demonstrating the accuracy of both the TLDs and the laboratory's measurements.

74 l

Davis-Bcsse Nuclear PowerSutix) 19r13 Annual Radiobgical Diviruimental Opemting Repit TLD 1993 Indicator vs Control Locations mromW1 days 25 20 15 * - -

~ INDICTATOR 10 8

0 73 76 77 79 81, M N 87 SS 91 M h

Figun: 27: The similarity between indicntor and contml n:sults demonstrated that the operation of Davis Bcsse has not caused any abnormalgamma(ku.

NRC TLD Monitoring The NRC has 22 TLDs located around Davis-Besse as part of their Direct Monitoring Network Program.

Davis-Besse maintains TLDs at all the NRCTLD monitoring sites. The NRC collects their TLDs on a quarterly basis, whereas Davis-Besse collects TLDs quarterly and annually at these locations. He NRC TLDs are collected and read independently of Davis-Besse's TLDs. thus providing a quality control check on both laboratories.

i The NRC uses Panasonic Model UD801 TLD, which has two elements of lithium borate: copper (Li2 B,0,:

Cu) and two elements of calcium sulfate: th'ulium (CaSO : Tm). The difference in TLD material used by the NRC and Davis-Besse will cause some minor variation in results.

The results of TLD monitoring at these 22 locations show good consistency between the NRC TLDs and the Davis-Besse TLDs. He average dose equivalent of the quarterly results are 15.912.9 mremS1 days for the Davis-Besse TLDs and 17.1 2.8 mremS1 days for the NRC TLDs (data from first, second, and third quarter). ne difference between the sets of measurements is most likely due to the differences in the TLD materials.

i 1

75 1

Davis-Besse Nucbar FowerSuaian 1993 Annual Radiological Envimnmental Opemung ReFxt I

l!

TLD Comparison NRC vs DB

mR\91 days

20 5 -

~

O 88 89 90 91 92 93 1 Year i

i Figure 28: Ornputs NRCand Davis-Besse H_D's for hst six years.

1 Table 18: Thermoluminescent Dosimeter Locations

! Sample Location Type of Location Description j Number Location T-1 1 Site boundary,0.6 miles ENE of Station l

1 T-2 i Site boundary,0.9 miles E of Station T-3 I Site boundary,1.4 miles ESE of Station

T-4 1 Site boundary,0.8 miles S of Station 2

T-5 I Site boundary,0.5 miles W of Station i

T-6 i Site boundary,0.5 miles NNE of Station

. T-7 I Sand Beach, main entrance,0.9 miles NW of j Sation i T-8 I Earl Moore Farm,2.7 miles WSW of Station 1

4 76

i Davis-Iksse Nuclear PowerSuion 1993 Annual Radiologiall Envuurnental Operating Reptut Table 18: Thennoluminescent Dosimeter Locadons continued Sample Location Type of Location DescTiption Number 12 ration T-9 C Oak Harbor Substation, 6.8 miles SW of Station T-10 I Site boundary,0.5 miles SSW of Station near warehouse T C Port Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station T-23 C South Bass Island,14.3 miles ENE of Station, nearlighthouse -

T-24 C Sandusky,21.0 miles SE of Station T-27 C Cmne Creek State Park,5.3 miles WNW of Station T-38 I Site boundary,0.6 miles ENE of Station T-39 I Site boundary 1.2 miles ENE of Station T-40 I Site boundary,0.7 miles SE of Station

' T-41 I Site boundary,0.6 miles SSE of Station T-42 I Site boundary, 0.8 miles SW of Station T-43 I Site boundary,0.5 miles SW of Station T-44 I Site boundary,0.5 miles WSW of Station T-45 I Site boundary,0.5 miles WNW of Station T-46 I Site boundary,0.5 miles NW of Station T-47 I Site boundary,0.5 miles N of Station 77

Davis-Ikse Nuclear PowerStation 1993 Annual Itxtiological Eminnmental Opemting Reixxt Table 18: Thermoluminescent Dosimeter I;> cations continued Sample Location Type of Location Description Number 12) cation T-48 I Site boundary,0.5 miles NE of Station T-49 I Site boundary,0.5 miles NE of Station T-50 I Erie Industrial Park, Pon Clinton,4.5 miles SE ofStation T-51 C Daup Farm. 5.5 miles SSE of Station T-52 1 Miller Fann,3.7 miles S of Station T-53 I Nixon Farm,4.5 miles S of Station T-54 I Weis Farm,4.8 miles SW of Station T-55 I King Fann,4.5 miles W of Station T-60 I Site boundary,0.3 miles S of Station T-61 I Site boundary,0.6 miles SE of Station T-62 I Site boundary,1.0 mile SE of Station T-63 I Site boundary,1.1 miles ESE of Station T44 1 Site boundary,0.9 miles E of Station T-65 I Site boundary,0.3 miles E of Station i

T-66 I Site boundary,0.3 miles ENE of Station T-67 I Site boundary,0.3 miles NNW of Station T-68 1 Site boundary,0.5 miles WNW of Station l

T-69 i Site boundary,0.4 miles W of Station l )

i T-70 I Site boundary,0.3 miles WNW of Station '

T-71 I Site boundary,0.1 mile NNW of Station l

l 78

f Davis-Besse NuclerIbwerSutbn 1993 Annual Radiobgical Enwonmental Operating Repat l

l t

l l

. Table 18: Thermoluminescent Dostmeter Locations continued 1 l Sample Location Type of Location Number  :

. Number Location l l

T-73 I Site boundary,0.1 mile WSW of Station

{

T-74 I Site boundary,0.1 mile SSW of Station l l

T-75 I Site boundary,0.2 mile SSE of Station T-76 I Site boundary,0.1 mile SE of Station T-77 i Site boundary,0.1 mile ENE of Station .

T-80 OC Ouality control Site T-81 OC Oulaity control Site T-82 ,

QC Quality Control Site -

T-83 QC Ouality Control Site

, T-84 QC Quality Control Site i

T-85 QC Quality Control Site T-86 QC Quality Control Site T-88 QC Quality Control Site T-89 QC Ouality Control Site T-90 I Toussaint East and Leutz Roads,2.0 miles SSW of Station l T 91 I State Route 2 and Rankie Road,2.5 miles SSE I ofStation T-92 I Locust Point Road,2.7 miles WNW of Station i T-93 I Twelfth Street, Sand Beach,0.6 miles NNE of i l Station Tot I State Route 2,1.8 miles WNW of Station 79 -1 l l

- . - - - - - - . - - ~ - - . - -

I Duvbriksse NelcarIbwerSunn 1993 AnnualIbdiobgical Envirtumental Operating Reput Table 18: Thermoluminescent Dosimeter Locations continued i Sample Location Type of Location Number Number 12 ration T-95 C State Route 579,9.3 miles W of Station T-% C State Route 2 and Howard Road,10.5 miles  ;

WNW ofStation l

T-97 1 Duff Washa and Zetzer Road,1.5 miles '

W of Station T-98 C Toussaint-Portage and Bier Road,6.0 miles SW ofStation T-99 I Behlman Road,4.7 miles SSW of Station T-100 C Ottawa County Highway Garage, Oak Harbor, 6.0 miles S of Station -

T-101 C Finke Street, Oak Harbor,6.5 miles SSW of Station T-102 C Oak Street, Oak Harbor,6.5 miles SSW of Station T-103 C Lickert-Harder Road,8.5 miles SW of Station T-lN C Salem-Carroll Road,7.3 miles SW of Station T-105 C Lake Shore Drive Port Cinton,6.0 miles SE ofStation i

T-106 C Third Street, Port Cinton,8.9 miles SE of Station i

l T-107 C Little Portage East Road,8.5 miles SSE of Station T-108 C Boysen Road,9.0 miles S of Station l T-109 C Stange Road,8.0 miles W of Station T-110 C Toussaint North and Graytown Road,10.0 miles l WSW of Station I

T-111 C Toussaint North Road,8.3 miles WSW of Station 80 I

Dwis4ksse Nuclear PowerStrian 1993 Annual Ratioksiall Enstxtnental Operating Reptxt Table 18: Thermoluminescent Dos 1 meter Locations continued Samplelocation Type of Location Number Number Location T-112 I Thompson Road,1.5 miles SSW of Station l

T-113 QC Quality Control Site T-114 QC Quality Control Site T-115 QC Quality Control Site T-116 QC Quality Control Site T-117 QC Quality Control Site T-118 QC Quality Control Site T-119 QC Quality control Site T-120 QC Quality Control Site T-121 I State Route 19,2.0 miles W of Station j T-122 I Duff Washa and Humphrey Road,1.7 miles W ofStation T 123 I Zetzer Road,1.6 miles WSW of Station T-124 C Church and Walnut Street, Oak Harbor,6.5 I miles SSWof Station T-125 I Behlman and Bier Roads,4.4 miles SSW of Station T-126 I Camp Perry Westem and Toussaint South Road,3.7 miles S of Station T-127 I Camp Perry Westem and Rymers Road,4.0 miles SSE of Station T-128 I Erie Industrial Park, Port Clinton Road, 4.0 miles SE of Station l

l 81 l

l l

l DwsDesse Nuclear PowerSt;1 ion 1993 Annual Radiological Envimomental Operating Report Table 18: Thermoluminescent Dosimeter Locations continued Samplelocation Type of Location Number Number Location T-150 i Humphrey and Hollywood Road,2.1 miles NW ofStation T-151 I State Route 2 and Humphrey Road,1.8 miles WNW of Station T-153 I 1.eutz Road,1.4 miles SSW of Station T-154 1 State Route 2,0.7 miles SW of Sation T-155 C Fourth and Madison Street, Port Clinton,9.5 miles SE of Sation T-200 QC Quality Control Site T-201 I Sand Beach,1.1 miles NNW of Station T-202 I Sand Beach 0.8 miles NNW of Station T-203 1 Sand Beach,0.7 miles N of Station T-204 I Sand Beach,0.7 miles N of Station T-205 I Sand Beach,0.5 miles NNE of Station T-206 1 Site Boundary,0.6 miles NW of Station T-207 I Site Boundary,0.5 miles N of Station i

T-208 I Site boundary,0.5 miles NNE of Station.

I I

i 82

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Davis-13em Nude r PowerStation 1W3 Annual R:siioksim! Envinx1 mental Operating Repxt Conclusion The Radiological Environmental Monitoring Program at Davis Besse is conducted to determine the radiological impact of the Station's operation on the environment. Radionuclide concentmtions measured at indicator locations were compared with concentrations measured at control locations, in previous operational studies and in the preoperational surveillance program. These comparisons indicate normal l concentrations of radioactivity in all environmental samples collected in 1993. Davis Besse's operation in 1993 had no adverse impact on the residents and environment surrounding the station. In fact, the dose associated with the operation of Davis-Besse is estimated to be 0.G43 percent of that received from natural and man-made sources. The results of the sample analyses performed during the period of January tiuough l December,1993 are summarized in Appendix D of this report.

l i

e l

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I 86

Davis-Iksse NuclerIbwerStMm 1903 Annual Radicbgical Envirmrnenta10pemting Reprt I

References l l

1." Cesium-137 from the Environment to Man: Metabolism and Dose," Report No.52, National Council on l Radiation Protection and Measurement, Washington, D.C (January 1977). l l

2. Eisenbud ,M., Environmental Radioactivity, Academic Press, Inc., Orlando, FL (1987). l 3." Environmental Radiation Measurements " Report No.50, National Council on Radiation Protection and

{

Measurement, Washington, D.C (December 1976).

1 4." Exposure of the Population in the United States and Canada from Natural Background . Radiation,"

Repon No.94, National Council on Radiation Protection and Measurement, Washington, D.C (December 1987). ,

1

5. "A Guide for Environmental Radiological Surveillance at U.S. Department of Energy Installations,"

DOE /EP-0023, Department of Energy, Washington, D.C (July 1981).

6." Ionizing Radiation Exposure of the Population of the United States," Report No.93, National Council on l Radiation Protection and Measurement, Washington, D.C (September 1987).

7. Kirk, T.J. and G.N. Midkiff, Health Physics Fundamentals, General Physics Corporation (1980).

8. " Natural Background Radiation in the United States," Report No.45, National Council on Radiation Protection and Measurement, Washington, D.C (November 1975).

9." Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the Criterion

'As low As Reasonably Achievable' for Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents," Code of Federal Regulations, Title 10 Energy, Part 50 " Domestic Licensing of Production and Utilization Facilities," Appendix I(1988).

10." Performance, Testing and Procedural Specifica: ions for Thermoluminescent Dosimetry," American National Standards Institute, Inc., ANSI-N45-1975, New York, New York (1975).

11."Public Radiation Exposure from Nuclear Power Generation in the United States," Report No.92, National Council on Radiation Protection and Measurement, Washington, D.C (December 1987).

! 12." Radiological Assessment: Predicting the Transport , Bioaccumulation and Uptake by Man of l Radionuclides Released to the Environment, " Report No.76, National Council on Radiation Protection and Measurement, Washington, D.C (March 1984).

i f ,

87

Davis-Dec NuclearIbwerStation tW3 Annual Raiblogiatl Envirmmental Operating Report

13. Regulatory Guide 4.1, " Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," US NRC(April 1975).

14. Regulatory Guide 4.13," Performance, Testing, and Procedural Specifications for Thermoluminescent i Dosimetry: Environmental Applications," US NRC(July 1977).

l

15. Regulatory Guide 4.15," Quality Assurance for Radiological Monitoring Progmms (Normal )

Operations) - Efiluent Streams and the Environment," US NRC (February 1979). l 1

16. Regulatory Guide G475, " Radiological Environmental Monitoring by NRC Licensees for Routine Opemtions of Nuclear Facilities," US NRC(September 1978).

17. Regulatory Guide 0837,"NRC TLD Direct Radiation Monitoring Network," US NRC(1993).

18." Standards for Protection Against Radiation," Code of Federal Regulations, Title 10, Energy, Pan 20 (1993).

19. Teledyne Isotopes Midwest Imbomtory, " Operational Radiological Monitoring for the Davis-Besse Nuclear Power Station Unit No.1, Oak Harbor, OH, " Annual Repon, Pans I and 11 (1977 through 1990).

20.Teledyne Isotopes Midwest Laboratory, " Final Monthly Progress Report to Toledo Edison Company",

(1991-1993).

21.Teledyne Isotopes Midwest laboratory,"Preoperational Environmental Radiological Monitoring for the Davis-Besse Power Station Unit No.1", Oak Harbor, Oh (1972-1977).

21. Toledo Edison Company, " Davis-Besse: Nuclear Energy for Northem Ohio."

22. Toledo Edison Company, " Davis-Besse Nuclear Power Station, Unit No.1, Radiological Effluent l Technical Specifications," Volume 1, Appendix A to License No. NPF-3. I l

23. Toledo Edison Company, " Final Environmental Statement -Related to the Construction of Davis-Besse l Nuclear Power Station," Docket #50-346(1987).

24. Toledo Edison Company, " Performance Specifications for Radiological Environmental Monitoring Program," S 72N, Revision 2 (1993).

25. Toledo Edison Company, "Radiokigical Environmental Monitoring Program," DP-HP-00015, Revision 0,(1990).

26. Toledo Edison Company, " Radiological Environmental Monitoring Quarterly, Semiannual, and Annual Sampling,: DB-HP-03004, Revision O. (1990).

27. Toledo Edison Company, " Radiological Monitoring Weekly, Semimonthly, and Monthly Sampling,"

DB-HP-03005, Revision 0,(1990).

88 l

Davis-Ikxse Nelear Power Staion 1993 Annual Radiological Envhximental Opemting Repxt l

28. Toledo Edison Company, "REMP Enhancement Sampling, "DB-HP-10101, Revision 1,(1992).

l

29. Toledo Edison Company, " Updated Safety Analysis for the Offsite Radiological Monitoring Program,"

USAR 11.6, Revision 14,(1992).

30. Toledo Edison Company, " Annual Radiological Environmental Operating Report Prepartion and ,

Submittal," DB-HP-00014, Revision 0,(1990).

31. Toledo Edison Company, Davis-Besse Nuclear Power Station, Offsite Dose Gilculation Manual, Revision 5.2.

l 32." Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurements, Washington, D.C. (March 1979).

l l

t 89

Davis Desse Nuclear PowerStaion IW3 Annual Radiologic 11 Envuunrnental Operating Repon Land Use Census Program Design Each year a bnd Use Census is conducted by Davis-Besse in order to update information necessary to estimate radiation dose to the general public and to determine if any modifications are necessary to the Radiological Environmental Monitoring Program. The bnd Use Census is required by Title 10 of the Code of Federal Regulations, Pan 50, Appendix I and Davis-Besse Nuclear Power Station 03ite Dose Calculation Manual, Section 5, Assessment of Land Use Census Data. He Land Use Census identifies the various pathways by which radioactive material may reach the general population around Davis-Besse.

De information gathered during the bnd Use Census for dose assessment and input into the REMP ensure these programs are as current as possible. He pathways of concem 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 l the ground '

i Plume Exposure Pathway- External exposure directly from a plume or cloud of radioactive material.

Vegetation Pathway- Internal exposure as a result of eating vegetables, fruit, etc.

which have a build up of deposited radioactive material or 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 a cow or goat grazing on a pasture contaminated l by radionuclides. l l

l Methodology The bnd Use Census consists of recording and mapping the locations of all residences, dairy cattle and goats, and broad leaf vegetable gardens (greater than 500 square feet) within a five mile radius of Davis-Besse.

90

DavirrIksse NuclearIbwerStation 1993 Annual Radiologiatl Environmental Operating Repon The surveillance portion of the 199312nd Use Census was performed during the month of July. In order to gather as much information as possible, the locations of residences, dairy cows, dairy goats, vegetable gardens, beef cattle, fowl, fruit trees, grapes, sheep, and swine were recorded. However, only the ,

residences, vegetable gardens, and milk animals are used in the dose assessment program. De vegetable I gardens must be 500 square feet in size, have at least 20% of the vegetables being green leafy plants (such 2

as lettuce, cabbage, and kale) and yield 2 kg/m .Re Ottawa County Cooperative Extension Agency confirmed the presence of dairy cattle and goats reponed within the five mile radius. I Each residence is tabulated as having an inhalation pathway, as well as ground and plume exposure pathways. Each garden is tabulated as a vegetation pathway. Each milk animal is tabulated as a milk pathway.

All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 minute series I

of the relevant quadrangles) which has been divided into 16 equal sectors corresponding to the 16 cardinal compass points (Figure 32). The closest residence, milk animal, and vegetable garden in each sector are determined by measuring the distance from each to the station vent at Davis-Besse.

ReSultS The following changes in the pathways were reconfed in the 1993 census:

W Sector -The vegetation pathway at 1750 meters was deleted in favor of a site at 1060 meters.

NW Sector - A residence at 1980 meters was replaced by a residence at 1100 meters.

NW Sector - The garden at 2460 meters was not present during the 1993 census. The new vegetation pathway is at 2660 meters.

He critical receptor for 1993 Land Use Census is an infant for the a cow / milk pathway at 4270 meters in the WSW sector. his has remained unchanged since the 1990 Land Use Census.

He detailed list in Table 19 was used to update the database of the effluent dispersion model used in dose calculations. Table 19 is divided by sectors and lists the distance (in meters)of the closest pathway in each meteorological sector.

Table 20 provided information on pathways, critical age group, atmospheric dispersion (X/0) and deposition (DC) parameters for each sector. This information is used to update the Offsite Dose Calculation Manual (ODCM). he ODCM describes the methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous etlluents and in calculating liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints.

91

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i Duv!s-Iksse Nucle:rIbwerSimion 1993 Annual Radio 6gical Envumnental Operating Repxt .

Table 19 : Closest Exposure Pathways PreSent in 1993 Sector Distance from Station (meters) Closest Pathways N 880 Inhalation Ground Exposure Plume Exposure NNE 870 Inhalation Ground Exposure Plume Exposure NE 900 Inhalation Ground Exposure Plume Exposure ENE, E, ESF, SE N/A Located over Lake Erie SSE 2010 Inhalation Ground Exposure Plume Exposure SSE 2880 Vegetation 1

S 1070 inhalation Ground Exposure i Plume Exposure - i

-l S 1440 Vegetation '

SSW 980 Inhalation Ground Exposure I Plume Exposure l

SSW 1560 Vegetation i

l 93

1 DavbIksse NuclarIbwerSution 1993 Ansual Radologiad Envimnental Opemting Reput I Table 19 : Closest Exposure Pathways Present in 1993 l (continued) 1 Sector Distance from station (meters) Cosest Pathways SW 1050 inhalation Ground Eposure Plume Eposure Vegetation WSW 1620 inhalation Ground uposure Plume &posure Vegetation WSW 4270 Cow Milk W 980 inhalation Ground uposure Plume &posure W* 1060 Vegetation W 6530 Goat Milk WNW 1730 inhalation Ground Eposure Plume Eposure WNW 1750 Vegetation NW* 1100 Inhalation Ground uposure Plume Sposure NW* 2660 Vegetation 94

l l

IXwis.lksse Nucler Ibwer Sutim IW3 Annual ihtakykul Envirtximental Op:mting Reput Table 19 : Closest Exposure Pathways Present in 1993 l

1 (continued)

I sector Distance from station (meters) Qosest Pathways NNW 1210 Inhalation Ground Exposure  ;

Plume Exposure NNW 1490 Vegetation I

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l 95 1

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Duvis.Hesse NuclearIbwerSuskri IW3 Annual Radiological Environmerual Operating Reput l

l Table 20: Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) l and Deposition (D/Q) Parameters l

SEC1DR METERS CRITICAL AGE XQ D/O PATHWAY GROUP (SEOM')

2 (hf )

l l N an INHAIABON CHILD 9.15EG 8.40Em NNE 10 0 INHAIABON CHILD 127E E 1.47E u i NE 900 INHAIABON CHILD 126E4 _1.58Em i ENE* - - - - -

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SSE 2880 VEGETABON CHILD 6.85Em 8.02610 l l

S 1440 VEGETABON CHILD 1.22LG 2.48EG l SSW 1560 VEGETABON CHILD 1.03EG 228EG SW 1050 VEGETABON CHIl.D 2.92EG 533E@

WSW 4270 COW / MILK INFANT 5.71E4 531510 W 6530 GOAT / MILK INFANT 4.54E4 2.79610 l

WNW 1750 VEGETABON CHILD 1.46EG 1.72E G NW" 2660 VEGETABON CHILD 53)E3 4.41510 i

NNW 1490 VEGETABON CHILD 1.64E G 126EG

' Since these secors are locaed ever marsh an:as and take Erie, no ingesticrt puhways are pn:sent.

" Omngtssince IW2.

96

_ghm _ m--.- _ mei- .e Dmis-r acNucicarherStation 1993 Annual Ra60 logical Emironmental Opemting Rqun Meteorological Monitoring Introduction Meteorological observations at Davis Besse began in October,1968. The Meteorological Monitoring Program at Davis Besse has provided data that can be used by many other programs.

The Radiological Environmental Monitoring Program uses the meteorological data to evaluate the biological effects of radioactivity released in Station effluents. The meteorological data is used to evaluate where new radiological environmental monitoring sites should be located, to monitor severe weather conditions, and to predict the development of adverse weather trends, such as flooding or high winds.

The Meteorological Monitoring Program at Davis Besse is required by the Nuclear Regulatory Commission (NRC) as part of the program for evaluating the effects of routine operation of nuclear power stations on the surrounding environment. Both NRC regulations and Davis Besse Technical Specifications provide guidelines for the Meteorological Monitoring Program. These guidelines ensure that Davis Besse has the proper equipment, in good working order, to support the plant functions.

On-site Meteorological Monitoring

System Description

At Davis Besse, two meteorological systems measuring identical sets of data are used to collect wind speed, wind direction, sigma theta (standard deviation of wind direction), ambient (outside air at 10 meters (m)) temperature, differential temperature (the air temperature at 100 m or 75 m minus air temperature 10 m), dew point temperature (the air temperature where i moisture begins to condense out of the air), and precipitation. Two towers equipped with a l variety of meteorological instruments are used to gather these data.

i 1

(

! Meteorological Instrumentation I l

l The meteorological system consists of one monitoring site located at an elevation of 577 feet {

above mean sea level. A 100 m free-standing tower located about 3,000 feet SSW of the cooling l

tower, and an auxiliary 10 m tower located 100 feet west of the 100 m tower, are used to gather the meteorological data. The 100 m tower has primary and backup instruments for wind speed and wind direction at 100 m and 75 m. The 100 m tower also measures differential temperature l

(dalta T): 10010 m and 7510 m. The 10 m tower has instruments for wind speed and wind l direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the i 10 m tower.

l 97 l

l l

Dmis-Besse Nucimr Power Station 1993 Annual Radiological Emironmental Operating Repon According to the Davis-Besse Nuclear Power Station Operating License, Appendix A, Technical Specification, a minimum of six instruments are required to be operable at the two lower levels (75 m and 10 m) to measure temperature, wind speed, and wind direction. During 1993, annual data recovery for all required instruments was 100 percent. The annual data recovery for 1993 was 100 percent for all other measured parameters except 10 meter dew point (Table 21).

Minor losses of data occurred during routine instrument maintenance, calibration, and data validation.

Personnel at Davis-Besse inspect the meteorological site and instrumentation regularly. Tower instrumentation maintenace and semiannual calibrations are performed by in-house facilities and an outside consulting firm. These instruments are wind tunnel tested to assure compliance with applicable regulations.

Meteorological Data Handling and Reduction A Campbell Scientific Datalogger 21X located in the meteorological shelters communicates 900 second averages of meteorological data to a Digital PDP 11/84. The PDP 11/84 averages this data for each hour and stores it in computer disk files, before transferring it to a VAX system.

The data is processed and analyzed by several computer programs. A computer listing of the data is generated and values are compared to specified range and rate-of-change criteria in order to identify anomalies. Data not fitting correct ranges is not used or is replaced by backup instrument readings. A climatological data base then exists to compare data on an on-going basis for the site and surrounding area. This data base exists back to the late 1960's.

Joint Frequency Distributions Summary statistics and Joint Frequency Distributions (JFDs) of wind and stability data are generated and the results are reviewed for consistency in terms of known site characteristic and regional climatology. The end result of the review process is a validated final database suitable for use by atmospheric dispersion models and for site meteorological characterizations.

98

l l Table 21 Summary of Meteorological Data Recovery For The Davis-Besse Nuclear Power Station January 1,1993 Through December 31,1993*

100m WniSpcal JeK .1H MAR Al'R .hMX .IEi EL AEG. _SIZ -Q 2 EQY IIIE AMi 100.00 100fX) 100.00 10a00 1(OIX) 1001D 10)m 100m 10a00 100m Im00 100fX) 100.00 fE 100m Wind Dutcuan 100.00 1001D 100I10 100.00 1001X) 100.00 IMOD 100 m 100110 100.00 100 m 100.00 100 m 75m Wind Spcxx1 100.00 100.00 E 10010 100fn 1(0.00 100.00 100.00 100m 10010 1001D 100110 10011) 1001X) 75m Wmd Dmxuon 100.00 10010 100.00 100I0 100fX) Im00 100m 100.00 1001D Im00 100.00 Im00 100m 8 y

10m WindSpeed 10010 100 m 10010 100fX) 100m 100.00 100.00 1001D 1001D i m 00 100m 100110 100.00 k 10100 100I0 1001D 1001D 100.00 100.00 100m 100I0 10010 1001D 100m 100fD 1001)0 10m Wind Dmxson 10m Amtnent AirTemp 10a00 10a00 100I0 100.00 100m 100.00 10a00 100.00 1001X) 100.00 100.00 100fD 100 m f

S IQn Ikw Point Temp om 97.92 100(0 Imm fM.% 96B1 9530 1(Um 100110 100.00 90.28 100.00 88.78 g 1)ehaT(100m-10m) 100.00 100 00 100.00 "

1001X) 1(X)m 100.00 100.00 10010 100110 100.00 1Q100 100.00 100 m e Iklia TG5m.10m) 1(Um 100m 1( 0 11) c Joint 100m winds and 10011) 1(11m 100m 100m 1001D 100m 100m IMOD 100110 100m ( -

E.

Dcita T(100m-10m) 1Q100 100I10 100110 10010 100.00 100.00 100.00 10010 100.00 100 m 100u00 100.00 la)IO h Joint 75m windsand o_

f Delta T(100m-IQn) 100m 100m 100.00 1001X) 100110 100.00 100 m 100 m 1001)0 100 m IM OD 100.00 Im00 Joint 75m windsand ' h Delta Tp5m -10m) 1001X) 10a00 100I10 10000 10a00 100.00 100m 100m 100110 100 m IG100 100.00 IUOm g Joint 10m winds and is DeltaTp5m-10) 10010 100m 100.00 {

100.00 100110 100m 1(DID 100m 100m 100m 100m 100.00 100fX)

• All data for individual monthes expnssed as penznt of time instmme:a wm operable during the m(nth, divided by the maximum number of hnuts in that

{

month that the instrument mund be openble. Values for annual data nxxwenes = penrnt of time instrument was opemble dunng the year, divided by the number of hours in the5 year that the instrument was operable.

2 a

Table 22 Summary of Meteorological Data Measured at Davis-Besse Nuclear PowerStation January 1,1993 through Decernber31,1993 E

ma su a ara m .an a e se act a nzc m e 100M WIND Max Speed (mph) 42.97 35.97 44 M 37.81 41.14 33.53 30.6 23.97 35.93 3735 37.55 35.10 z 8

Date of Max Speed 31 11 13 20 12 9 11 10 14 31 11 10 Min Speed (mph) 2.40 0.70 035 2 80 1.50 2.22 1.80 1.06 1.29 2.99 139 8

2.25 g Dutc of Min Sped 19 21 22 3 10 3 22 7 22 5 30 3 h

Ave Wind Speed 18.51 15.45 16.% 1635 15.77 15.23 13.59 11.71 14G 17.56 17.86 17.07 15.90

[

75M WIND Max Speed (mph) 40.% 34.20 4160 34 51 34 05 31.90 29.02 2336 3330 35.99 36.10 34.15

_ Date of Max speed 31 11 13 20 24 9 9 3 , 14 31 11 10 o Min Speed (mph) 2.10 1.20 1.76 1.27 1.79 1.74 2.10 1.08 1.45 2.47 1.14 2.49 Date of Min Speed 19 21 22 7 to 4 2 7 22 5.

5 28 28 Ave Wind Speed 17.03 14.11 1535 14.98 14.47 13.95 12.74 10.95 13 66 1348 16.50 15.61 14 66 10M WIND d

Max Speed (mph) 31.98 24.22 31.59 25 03 29.48 22.47 20.88 18.07 23.46 25.47 27.13 24.12 Date of Max Speed 31 Ii 13 20 12 9 29 3 27 31 5 10 3.

8 Min Speed (mph) 1.28 1.59 137 1.40 1.44 1.68 131 1.23 1.57 1.84 1.76 1.54 @

Date of Min Speed 19 27 30 7 11 30 23 17 22 23 14 28 Ave Wind Speed 12.03 10.77 10.25 10 16 9.70 9.05 8.12 6.74 8.70 9.85 1032- 10.29 9 66 16M AMBIENTTEMP g

, Max (*I) 5636 48 38 59.89 74 68 82.10 86.28 92.17 9238 8533 79.80 62.54 53 02 el Datc of Max 4 5 30 15 28 18 28 27 14 7 13 10 f"

Min ("l) 13.1 2.23 7.58 28.14 44 51 44.94 59.93 53.69 39.25 8.85 25.54 5.72 Daic of Min 19 18 14 3 17 I 31 5 30 31 28 29 AveTemp 30.19 24D3 31.53 46.51 59.41 67.14 75D7 73.00 6133 5132 '

41.17 30.94 49.46 1

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Table 22 Sumnuuy of Metcomlogical Data Measured at Davis-Besse Nuclear Porver Station For January 1,1993 thmugh December 31,1993 (G====f) a 9

M Jati him AIE MAY .B2i .B5, AV.fr. E M NDY. E M F 10M DEW POINT 1EMP rican(*I) N/A 1953 28B9 33.59 45.65 57.48 6329 6139 5231 42M 33SO 2625 42.41 [

Nh (*I) N/A 3Ct5 50.59 5838 63.17 8530 75]O 75.43 72B8 65B6 59E9 52.45 8530 k Ibcofh6 N/A 10 30 25 31 9 28 30 2 21 15 10 OM E93 fa 4

Mn(T) N/A -140 .l.09 226 3130 3437 0.00 3D0 3400 2295 1793 137 -140 5 EI -

the of Mn N/A 18 14 18 13 1 9 15 30 29 20 30 02/18,93

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4 l'RECII1TA'110N Tual(indrs) 323 1BS 294 3M 193 2S1 135 037 334 1D3 239 133 26 M $

Max. in One Day 0.74 040 OB6 1.10 OBO 0.77 OB 038 095 034 OM 0.74 2 Date 4 11 4 25 28 25 11 10 25 16 14 4 -

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Dasis-Besse Nucicir her Station 1993 Annual Radiologicil Emironnental Opemting Repxt Marsh Management Navarre Marsh Navarre Marsh is located on 733 acres of wetlands on the southwestern shore of Lake Erie and surrounds the Davis-Besse Nuclear Power Station. The marsh is owned by Toledo Edison and jointly managed by the U.S. Fish and Wildlife Service and Toledo Edison. Navarre Marsh is divided into three pools (units). The pools are separated from Lake Erie and each other by a series of dikes and revetments. Toledo Edison is responsible for the maintenance and repair of the dikes and controlling the water levels in each pool.

A revetment is a retaining structure designed to hold water back for the purpose of erosion control and to encourage beach formation. Revetments are built with a gradual slope which causes waves to dissipate their energy when they strike the revetment. This encourages beach formation through passive deposition of sediment. A dike is a retaining structure designed to hold back water for the purpose of flood control and to aid in managing wetland habitat. When used as a marsh management tool, dikes aid in controlling water levels in order to obtain desired vegetation and animal species. Manipulating water levels is one of the most important marsh management tools used in Navarre Marsh. Three major types of wetland communities exist in Navarre Marsh, the freshwater marsh, swamp forest, and wet meadow. Also, there exists a narrow dry beach ridge along the lake front with a sand bar extending out into Lake Erie. All these areas provide essential food, shelter, and nesting habitat as well as a resting area for migratory birds.

In addition to water level control, several other activities occurred throughout the year such as nesting structure installation and maintenance, goose banding, songbird banding, and muskrat trapping. Toledo Edison is responsible for road and dike repairs, wood duck box installation and maintenance, marsh wildlife utilization census, assisting with bird banding and conducting tours through the marsh.

Species of wildlife commonly found in Navarre Marsh include: mallards, blackducks, woodducks, American widgeon, mergansers, Canada geese, great-blue herons, great egrets, black-crowned night herons, warblers, sparrows, thrushes, swallows, northern cardinal, great horned owls, screech owls, red-tail hawks, red foxes, mink, white-tailed deer, muskrats, woodchucks, painted turtles, Blanding turtles, snapping turtles, fox snake, and garter snake.

102

Dais-Besse Nuclear Power Station 1993 Annual Radiological Emironnental Operaung Report I

Special Projects in 1993 l In 1993, special projects included controlling undesirable plant species, songbird banding, l and Canada goose banding. A brief description of each of these projects is provided in the I following paragraphs.

Purple loosestrife (Lythrium Salicaris), a non-native plant, has been a menace to wetlands ,

I since it was introduced from Europe in the 1800's. It is more competitive than native marsh plants but provides little benefit to wildlife. In previous years, Toledo Edison personnel have controlled the spread of purple loosestrife in the Navarre Marsh by using approved I herbicides and by removing smaller individual plants. The efforts have reduced the number l of plants. I The songbird banding project was conducted in cooperation with the Ohio Department of Natural Resources (ODNR) from April through September,1993. The project involved capturing and banding songbirds migrating through the area. A total of 11,554 individual birds were banded and released. l The goose banding project, also conducted in conjunction with ODNR, captured and banded geese and fitted some with colored identification collars.

Toledo Edison is committed to protecting the Navarre Marsh and has gone to great lengths to preserve this valuable resource.

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l Davis-Desse Nuclear Fower Staion 1993 Annual Radiological Emironmental Operating Report

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Water Treatment i

1 Water Treatment Plant Operation l Description The Davis Besse Nuclear Power Station uses Lake Erie as a water source for its water i treatment plant. The lake water is treated with chlorine, lime, and other chemicals to make the water clean and safe for consumption. This water may also be further treated to produce high purity water which is used by many of the Station's cooling systems.

l Operation of the water treatment plant is monitored by the Ohio Environmental Protection j Agency (OEPA) and the Ohio Department of Health. The operation of the facility is reviewed by a Public Water Supply certified operator. Activities at the water treatment plant are conducted in compliance with the Safe Drinking Water Act and the regulations for public water supply as set forth by the OEPA.

Monthly operational reports, required by the OEPA, are completed by Toledo Edison

personnel and submitted to the agency. These reports contain sample dates and analytical results, which are compared to standards established by the OEPA. Operational data are also

, reviewed for compliance with the limits set by the OEPA. As a further means of monitoring I

water quality, drinking water is sampled annually for pesticides, herbicides, and heavy

. metals (such as chromium, arsenic, mercury, lead) and quarterly for certain organic chemicals. The health and safety of the water treatment plant operators and other site personnel is ensured through weekly housekeeping inspections of the facility, j Treatment System Raw water from Lake Erie enters an intake structure, then passes through traveling screens which remove debris and large particles. The water is then pumped to chlorine detention tanks

where sodium hypochlorite is added. The water remains in these tanks for up to twenty minutes, j j which allows contact time for disinfection and oxidation purposes. Next the water passes l through one of two clarifiers. Davis-Besse uses upflow clarifiers, or precipitators, to remove i

. sediment, organic debris, and dissolved agents from the raw water prior to filtration. Clarifiers combine the conventional treatment steps of coagulation, flocculation, and sedimentation into a j single unit. Coagulation is the process by which a chemical, called a coagulant, is added, j causing the small particles in the water to adhere to each other and form larger particles. During

. flocculation, the water is gently circulated, allowing these conglomerate particles to mass together farther. Finally, during sedimentation, large conglomerate particles settle to the bottom j

, of the clarifier. These processes normally require large separate tanks. However, the use of e

clarifiers saves both space and the manpower needed to operate the treatment plant.

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Dais-Besse Nuckur her Station 1993 Anneal Radio!Ogical Emironmental Opemting Report RAW WATER NTAKE STRUCTUfE g- -- -

s-ROW BOX i

CHLORINE A WATER ;r -

y TREATMENT DETENTION CLARIRERS -.~

FEED PUMPS TANKS -

ca -

CLEARWELL FLTERS CLE.AmVELL TRANSFER PUMPS TO DOMESTIC TO ARE (DRINKING) WATER WATER SYSTEM SYSTEM TO DEMINERAUZED WATER SYSTEM

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Figure 33 : At Davis-Besse, raw water is drawn into the water treatment plant and processed to make drinking water and water for plant systems.

After the clarifier, the water goes through a flow-splitting box which equally divides the water flow to the Automatic Valveless Gravity Filters (AVGF). These AVGFs consist of a 50:50 ratio of anthracite to filter sand. During this filtration process, suspended matter is removed from the water by the anthracite and sand media. This filtering reduces the turbidity and odor and improves the taste of the water.

1 After filtration, the water goes to a 32,000 gallon clearwell. The clearwell acts as a reservoir from which water can be drawn as needed for all systems, including fire water, demineralized water, and also drinking water.  ;

1 New Drinking Water Rules The OEPA issued several new rules which took effect in 1993 for water treatment plants using surface water sources, which includes Davis Besse. Turbidity monitoring is required every four hours instead of once per day, and the maximum allowable limits will be much more stringent, reducing limits by a factor of ten. Also, lead and copper monitoring began in July 1993, to ensure the distribution system does not contain high concentrations caused by items such as lead or copper pipes or lead solder.

105

Davis-Bcss: Nt:*ar Power Station 19D Anntsil Paliological Emironmental Operating Repon The OEPA issued additional rules concerning disinfection requirements which took effect in June,1993. Plant operations are monitored much more frequently to ensure compliance at all times, particularly during high water demand situations. Some water treatment plant modifications were required as well, including baffling of the clearwell in order to increase the amount of time water remains in the treatment system. A permanent sodium hypochlorite addition system is currently in the planning phase; it will ensure required sodium hypochlorite concentrations are supplied at all times.

Zebra Mussel Control Introduction The plant receives all of its water from an intake system from Lake Erie. The Zebra mussels can severely impact the availability of water for plant processes. Dreissena polymorpha, more commonly known as the zebra mussel, because of its striated shell, is a native European bivalve that was accidentally introduced into North American waters in 1988 and was discovered in Lake Erie in 1989. Zebra mussels are prolific breeders which rapidly colonize an area by secreting byssal threads which enable them to attach to solid surfaces and to each other. Because of their ability to attach like this, they may form layers several inches deep. This poses a problem to facilities that rely on water intakes from Lake Erie because mussels may attach to the intake structures and restrict water flow. Zebra mussels have not yet caused any significant problems at Davis-Besse, but mussels have been found attached to the intake crib (the structure that allows water to be pulled in from the lake) and the first section of the intake conduit (the pipe that connects the crib to the intake canal).

At Davis Besse, zebra mussels are monitored to estimate their population density, which will determine the severity of the problems they may cause. The life cycle of the mussel and the effects of certain variables (wind, temperature, and chemicals) on mussels and veligers, the larval stage of the mussel, are being studied to determine a means of controlling mussel population.

Monitoring The Zebra Mussel Monitoring Program has been in place since April,1990. The program involves the collection of several types of samples which are observed for the presence of adult zebra mussels or the free-swimming larval forms, veligers. The frequency of sampling is determined by lake water temperature. Samples are taken when the lake temperature is above 12 C since this is the temperature above which spawning may occur. At temperatures above 18 C, when spawning conditions are most favorable, more frequent samples are taken. Weather data and water temperatures are also recorded to determine their effects on veliger/ mussel population.

Water samples are collected in the station's intake forebay. These samples are collected using a plankton net sampler: a net support system with a straining bucket used for plankton-size (microscopic) organisms which include veligers. One milliliter from each sample is 106

Dmisacsae Nuclear Pour SuDon 1993 Annual Rwholop:al Embunnetal Operating Repon i

observed under a microscope to check for the presence of veligers to determine the average number of veligers per liter.

i The highest veliger reading for 1993 occurred on July 30th. A density of 17.2 veligers per .;

liter was detected in a plankton sample taken in the intake canal near the plant. All other  !

veliger sample results were below 10 veligers per liter. These veliger densities are significantly lower than 1992 sample results. The Zebra Mussel Program will be continued during 1994 to evaluate mussel population. l l

Wastewater Treatment Plant Operation  !

The wastewater treatment plant (WWTP) operation is supervised by a state Certified Waste- 1 water Operator. Wastewater generated by site personnel is treated at an onsite extended l aeration package treatment facility designed to accommodate a flow of 38,000 gallons per day (gpd). In the treatment process, wastewater from the various collection points around -

the site, called lift stations, enters the facility and is distributed to the surge tanks of the treatment plants. ]

l The wastewater is then pumped into the aeration tanks. Here, organic materials are digested l by microorganisms which are provided with a source of oxygen. This is accomplished through the use of blowers. The mixture of organics, microorganisms, and decomposed l wastes is called activated sludge. The treated wastewater settles in a clarifier, and the clear l

liquid passes over a welr, leaving the plant by an effluent trough. The activated sludge  ;

contains the organisms necessary for continued treatment, and is pumped back to the front of  !

the plant to digest more incoming wastewater. The effluent leaving the plant is disinfected with chlorine and is pumped to the wastewater treatment basin (NPDES Outfall 601) where I further treatment takes place. '

Summary of 1993 Wastewater Treatment Plant Operations Wastewater Treatment Plant (WWTP) Number 1 was taken out of service in July 1993 due to decreased site population and reduced flow through the facility. WWTP Number 1 was drained and cleaned. 'Ihis facility is scheluded to be painted during 1994. This side of the plant will be maintained in operating condition and utilized as a backup system for increased future needs or during periods when WWTP Number 2 is out of service for repairs.

Biochemical Oxygen Demand (BOD) is an analytical procedure designed to determine the amount of pollution in the water. The more organically active the wastewater is, the more oxygen it will consume. Hence, BOD measures the demand for this oxygen; the higher the BOD, the greater the treatment required. In 1993, water entering the treatment system had an average BOD of 151 mg/L, while water leaving the system averaged only 7 mg/L. This represents a total BOD reduction of 95E 107

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l Dmis-Besse Nuckar PownStation 1993 Annual Radiological Emironmental Operating Repon l

National Pollutant Discharge Elimination System (NPDES) Reporting The GEPA has established limits on the amount of pollutants that Davis-Besse may discharge to the environment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 21B0011

• ED.

Parameters such as chlorine, suspended solids and pH are monitored under the NPDES permit. Toledo Edison personnel prepare the NPDES Reports and submit them to the OEPA by the fifteenth day of each month.

Davis-Besse has six sampling points described in the NPDES permit. Five of these locations are discharge points, or outfalls, and one is a temperature monitoring location. Descriptions of these sampling points follow:

Outfall 001 Collection Box: At a point representative of discharge to Lake Erie.

Source of Wastes: Low volume wastes (Outfalls 601 and 602), circulation system blow down and occasional service water (sample collected at Davis-Besse Beach Sampling Station).

Outfall 002 Area Runoff: Discharge to Toussaint River Source of Wastes: Storm water runoff, circulating pump house sumps (sample collected at discharge of Training Center Pond).

Outfall 003 Screenwash Catch Basin: Outfall to Navarre Marsh. '

Source Of Wastes: Wash debris from water intake screens (sample collected at overflow of screenwash basin).

j Outfall 601 '

Wastewater Plant Tertiary Treatment Basin: Discharge from wastewater treatment system.

Sources Of Wastes: Wastewater Treatment Facility.

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Dmis&sseWdcarherstation 1993 Annual Radokgcal Emironmental Opemting Repon

Outfall 602 Low volume wastes

Discharge from settling basins. 1 3 Sources of wastes: Water treatment residues, condensate polishing resins (sample collected l 4

at overflow of number 2 basin), and condensate pit sumps. I j Sampling Point 801

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Intake Temperature: Intake water prior to cooling operation (temperature taken at the east end of the intake forebay).

2 i 1993 NPDES Summary-1

During 1993, there was one instance of the total daily suspended solids limit being exceeded.

It occurred at Outfall 601 during the month of June because of a high algae population in the l discharge basin. Although algae plays an important role in tertiary treatment, excessive algae

concentrations can adversely affect effluent quality by increasing suspended solid concentration. Also, temperature variations between intake and discharge temperatures i

ranged as high as 8.0 F and averaged 4.1 F for the year.

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, Davis-Besse Nuclear Pwer Station IW3 Annual Radiologicil Emironmental Operating Repon Chemical Waste Management Introduction The Chemical Waste Management Program for hazardous and nonhazardous chemical wastes generated at the Davis-Besse Nuclear Power Station was developed to ensure wastes are managed and disposed of in accordance with all applicable state and federal regulations.

Waste Management Resource Conservation and Recovery Act The 'Resource Conservation and Recovery Act (RCRA)is the statute which regulates solid hazardous waste. Solid waste is defined as a solid, liquid, semisolid, or contained gaseous material. The major goals of RCRA are to establish a hazardous waste regulatory program to protect human health and the environment and to encourage the establishment of solid waste management, resource recovery, and resource conservation systems. The intent of the hazardous waste management program is to control hazardous wastes from the time they are generated until they are properly disposed of, commonly referred to as " cradle to grave" management. Anyone who generates, transports, stores, treats, or disposes of hazardous waste is subject to regulation under RCRA.

Hazardous and Solid Waste Amendment This amendment promotes the recycling, recovery, or reuse of waste by sending it to waste.to-energy facilities, distillation facilities, and fuel blending facilities. These activities would result in a reduction of waste being disposed of in our nation's dwindling landfill space. An additional HSWA goal is to minimize the generation of waste through such methods as source reduction, product substitution, technology / process modification and raw material modification.

RCRA also mandates other requirements such as the use of proper storage and shipping containers, labels, manifests, reports, personnel training, spill control plan and an accident contingency plan, all of which are part of the Chemical Management Program at Davis-Besse. In 1993,1,200 gallons of hazardous waste were transported off site for disposal.This represents a 33% reduction from 1992. An additional 1,600 gallons of nonhazardous waste were disposed of in 1993, which is a 66% reduction from 1992. The following are completed as part of the hazardous waste management program to ensure compliance with the RCRA regulations.

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Dasis-Bcsse Nuclear Pouer Station 1993 Annual Radiologicil Emironmental Operaung Repon

• Inspections Chemical Waste Accumulation Areas are designated throughout the site to ensure proper handling and disposal of chemical waste. These, along with the Chemical Waste Storage Area, are routinely patrolled by security personnel and inspected weekly by Toledo Edison l personnel. All areas used for storage or accumulation of hazardous waste are posted as such l

with warning signs, and drums are color-coded for easy identifiution of waste categories by '

Davis Besse employees.

l

• Waste Inventory Forms Inventory forms are placed on waste accumulation drums or provided in the accumulation area to allow employees to record the waste type and amount as it is added to the drum. This ensures that incompatible wastes are not mixed and also identifies the drum contents for proper disposal.

• Testing of Waste Oil The majority of waste oil generated at Davis-Besse is not disposed of, but is removed to a recycling facility for energy recovery. Before removal for recycling, the oil is tested to ensure that it is nonhazardous. Waste oil that contains less than 1,000 parts per million of halogens and has a flash point above 140"F is considered to be nonhazardous waste.

Emergency Response Planning Comprehensive Environmental Response, Compensation, and Liability Act The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, sometimes referred to as Superfund) established a federal authority and source of funding for responding to spills and other releases of hazardous materials, pollutants, and contaminants into the environment. Superfund establishes " reportable quantities" for several hundred hazardous materials, and regulates the cleanup of abandoned hazardous waste disposal sites.

Superfund Amendment and Reauthorization Act (SARA)

Superfund was amended in October,1986, to establish new reporting programs dealing with

) emergency preparedness and community right-to-know laws. As part of this program, CERCLA is enhanced by ensuring that the potential for release of hazardous substances is minimized and adequate and timely responses are made to protect surrounding populations.

Davis Besse conducts site-wide inspections to identify and record all hazardous products and l

chemicals onsite as required by SARA. Determinations were made as to which products and I chemicals were present in sufficient quantities to report.

l Annual SARA reports are submitted to local fire departments, and local and state planning l commissions by March I for the preceding calendar year. No additional chemical products l l were identified for calendar year 1993.

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Davis-Besse Nucletr Power Station IW3 Anntal Radiological Emironnmal Opemting Repon Spill Kits Fifty-five gallon drums containing protective equipment and spill control equipment are maintained throughout the Station at chemical storage areas and at appropriate hazardous chemical and oil use points. Equipment in the kits includes such items as chemical resistant coveralls, gloves, absorbent cloth, goggles, and warning signs. l Other Regulating Acts i The Toxic Substance Control Act (TSCA) was enacted to provide the USEPA with the authority to require testing of new chemical substances for potential health effects before they are introduced into the environment, and to regulate them where necessary. This law would have little impact on utilities except for the fact that one family of chemicals, polychlorinated biphenyls (PCBs), has been singled out by TSCA. This has resulted in an extensive PCB management system, very similar to the hazardous waste management system established under RCRA.

In 1992, Davis-Besse completed an aggressive program that eliminated PCB transformers ,

onsite. PCB transformers were either changed out with non-PCB tluid transformers or  !

retrofilled with non-PCB liquid. <

l 1

Retrofilling PCB transformers involves flushing the PCB fluid out of a transformer, refilling it with PCB leaching solvents and allowing the solvent to circulate in the transformer during operation.The entire retrofill process takes several years and will extract almost all of the PCB. l In all, Davis-Besse retrofilled eleven PCB transformers, the majority being completed and reclassified non-PCB in 1991. The eleventh PCB transformer was declared non PCB in early 1992. The only remaining PCB containing equipment onsite are a limited number of capacitors. While the Davis-Besse Nuclear Power Station generated and disposed of over 4,000 kilograms of PCB waste in 1991 and 75 kilograms of PCB waste in 1992, only 64 kilograms of PCB waste from capacitors and associated debris were generated in 1993.

Clean Air Act l 1 l The Clean Air Act identifies substances which are considered hazardous air pollutants. l l Davis-Besse holds an OEPA permit to operate an Air Contaminant Source for the station l auxiliary boiler. This boiler is used to heat the station and provide steam to plant systems l when the reactor is not operating. A report detailing auxiliary boiler operation is submitted annually.

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Datis-Besse Nuckar her Station IW3 Annual Radiological Emironmental Opemtmg Repon Of particular significance is asbestos removal from renovation and demolition projects for which USEPA has outlined specific regulations concerning handling, removal, environmental protection, and disposal. Also the Occupational Safety and Health Protection Administration (OSHA) strictly regulates asbestos with a concern for worker protection.

Removal teams must meet medical surveillance, respirator fit tests, and training requirements prior to removing asbestos-containing material. Asbestos is not considered a hazardous waste by RCRA, but the EPA does require special handling and disposal of this waste under the Clean Air Act.

Transportation Safety Act The transportation of hazardous chemicals, including chemical waste, is regulated by the Transportation Safety Act of 1976. These regulations are enforced by the United States Department of Transportation (DOT) and cover all aspects of transporting hazardous materials, including packing, handling, labeling, marking, and placarding. Before any wastes are transported off site, Davis-Besse must ensure that the wastes are identified, labeled and marked according to DOT regulations, including verificatien that the vehicle has appropriate placards and it is in good operating condition.

Other Programs Underground Storage Tanks According to RCRA, facilities with Underground Storage Tanks (UST) are required to notify the State. This regulation was implemented in order to provided protection from tank contents leaking and causing damage to the environment. Additional standards require leak detection systems and performance standards for new tanks. At Davis Besse one 8,000 gallon diesel fuel storage tank and one 2,000 gallon waste oil tank are regulated as USTs.

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, Davis-Besse Nuclear Power Station 1993 Annual Rtdiological Environnental Opemung Repon I

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l Waste Minimization and Recycling Municipal Solid Waste (MSW) is everyday trash which is produced by individuals at home and by industries. In some communities MSW is burned in specially designed incinerators to produce power or separated into waste types (such as aluminum, glass, and paper) and i recycled. But the vast majority of MSW is sent to landfills for disposal. As the population increases and older landfills reach their capacity and close, MSW disposal becomes an important economic, health, and resource issue.

The State of Ohio has addressed the issue with the State Solid Waste Management Plan, otherwise known as Ohio House Bill 592. This legislation divides Ohio's 88 counties into 48 Solid Waste Management Districts. Each Solid Waste Management District is responsible for devising a plan to reduce MSW by 25% by 1994, as compared to base year of July 1, 1989 to June 30,1990. Each plan will be submitted to the Ohio Environmental Protection Agency (OEPA) for approval.

The intent of the bill is to extend the life of existing landfills by reducing the amount of MSW produced, by reusing waste material where possible and recycling of other waste materials. This is frequently referred to as " Reduce, Reuse, and Recycle."

l Statewide, it is prohibited to place the following items in a landfill after the dates listed below:

Lead acid batteries January 1,1993 Whole tires January 1,1993 Yard and lawn waste December 1,1993 Shredded tires January 1,1995 Beginning in 1992 and continuing through 1993 several programs were implemented to emphasize the reduce, reuse, recycle approach to MSW management, as detailed below.

Improved efficiency in collection and hauling, resulted in a reduction of disposal cost of MSW from approximately $72,000 in 1991 to $36,000 in 1992. In 1993, the approximate l l cost was $21,000. This results in a cost reduction of about 71% since 1991. '

i l Other programs include paper and cardboard recycling. A total of 68,704 pounds of paper was recycled in 1993. Also,40 bales (40,000 pounds) of cardboard have been collected that l would have otherwise been placed in a landtill.

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D:nis-Desse Nuckar Pown Station 19)3 Anntsil Radiological Emironmental C;rrating Repon Approximately 3,250 pounds of aluminum soft drink cans were collected on site for the Boy  ;

Scouts to recycle. Lead acid batteries are recycled and tires are returned to the seller for proper disposal. Although, scrap metal is not usually considered part of the MSW stream.

Davis Besse does collect and recycle scrap metals. The metals are sold at current market price to a scrap dealer for resource recovery. These program are continuously being expanded and reinforced as other components of MSW stream are targeted for reduction.

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1993 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Repon 1

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I APPENDIX A INTERLABORATORY COMPARISON PROORAM RESULTS Note: Teledyne Brown Engineering, Environmental Services, Midwest Laboratory (TBEESML)  !

participates in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. The results are reported in Appendix A. Also reported are results of in-house spikes and blanks.

I 116

1993 Davis-Besse Nuclear Power Station Annual Radiological Environmental Oprating Report Annendix A Interlaboratory Comnarison Proeram Results Teledyne Brown Engineering Environmental Services Midwest Laboratory (formerly Teledyne Isotopes and Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to the Participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water, air filters, and food samples during the period January through December 1993. This program has been conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.

The results in Table A-2 were obtained for thermoluminescent dosimeters (TLDs) during the International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Also Teledyne testing results are listed.

Table A-3 lists results of the analyses on in-house spiked samples.

Table A-4 lists results of the analyses on in-house " blank" samples.

Attachment A lists acceptance criteria for " spiked" samples.

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1993 Davis-Besse Nuclear Pouer Station Annual Radiological Ernironmental Operating Report Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Brown Engineering Environmental Services Midwest Laboratory results for milk, water, air filters, and food samples, January through December 1993'.

I Concentration in nCi/L" Lab Sample Date TBEESML EPA Result

• Control Code Type Collected Analysis Result 2 SD Limits i s,N= 1 STW-680 Water Jan 1993 Sr-89 15.0t2.0 15.0 5.0 6.3-23.7 Sr-90 10.3 1.2 10.0t5.0 1.3-18.7 STW-681 Water Jan 1993 Pu-239 17.5 1.6 20.0*2.0 16.5-23.5 STW-682 Water Jan 1993 Alpha 17. l

• l .2 34.0 9.0 18 4-49.6 Beta 46.7*3.2 44.0 5.0 35.3-52.7 STW-683 Water Feb 1993 I-131 106.0 10.0 100.0 10.0 82.7-117.3 STW-684 Water Feb 1993 Uranium 7.21.1 7.63.0 2.4-12.8 STW-68 Water Mar 1993 Ra-226 9.31.3 9. 8* l . 5 7.2-12.4 Ra-228 20.8 2.2 18.5 4.6 10.5-26.5 STW-686 Water Apr 1993 Alpha 88.3*8.1 95.0*24.0 53.4-136.6 Ra-226 25.4 1.4 24.9 3.7 18.5-31.3 Ra-228 17.4*l.2 19.0 4.8 10.7-27.3 Uranium 27.8*2.2 28.9*3.0 23.3-34.1

.STW-687 Water Apr 1993 Beta 141.7 9.0 177.0*27.0 130.2-223.8 Sr-89 28.7 9.4 41.0 5.0 32.3-49.7 Sr 90 28.0 3.5 29.0 5.0 20.3-37.7 Co-60 41.3 1.2 3 9.0+ 5.0 30 3-47.7 Cs-134 24.7*l.2 27.0 5.0 18.3-35,7 Cs-137 30.0 0.0 32.0 5.0 23.3-40.7 STW-688 Water Jun 1993 H-3 9613.3 9844t 8136.8-46.2 984.0 11551.2 118

1993 Davis-Besse Nuclear Power Station Annual Radiological Environmental Op: rating Report l

l Concentration in oCi/Lh TBEESML Lab Sample Date Results 2 EPA Results Control I Code Type Collected Analyses sigma d

i s, N= l' Limits I I

STW-689 Water Jun 1993 Co-60 17.3*4.6 15.0 5.0 6.3-23.7 Zn-65 114.0t13.2 - 103.0 10.0 85.7-120.3 Ru-106 108.0*8.0 119.0*12.0 98.2-139.8 Cs-134 5.7*l .2 5.0*5.0 0.0-13.7 Cs 137 6.0*2.0 5.0t5.0. 0.0 13.7 4

Ba-133 101.7 10.3 99.0*10.0 81.7-116.3 STW-690 Water Jul 1993 . Sr-89 28.3 2.3 .34.0 5.0 25.3-42.7 l Sr-90 25.0 1.0 25.0 5.0 16.3-33.7 STW-691 Water Jul 1993 Alpha 15.0 2.7 15.0 5.0 6.3-23.7 i

Beta 41.3*4.9 43.0 6.9 31.0-55.0 i STW-692 Water Aug 1993 Uranium 24.9 1.4 25.3 3.0 20.1-30.5 STAF-693 Air Filter Aug 1993 Alpha 17.0 1.0 19.0i5.0 10.3-27.7 Beta 47.3 0.6 47.0*5.0 38.3-55.7 Sr-90 19.3 0.6 '19.0*5.0 10.3-27.7 Cs-137 10.0 1.0 9.05.0 0.3-17.7 STW-694 Water Sep 1993 Ra-226 15.9 0.7 14.9 2.2 11.1-18.7 Ra-228 21.0*l.6 20.4t5. I 11.6-29.2 STM-695 Milk Sep 1993 I-131 125.3*4.5 120.0 12.0 99.2-140.8 Sr-89 19.3*l.5 30.0*5.0 21.3-38.7 Sr-90 22.0*0.0 25.0*5.0 16.3-33.7 Cs-137 49.0 3.0 49.0 5.0 40.3-57.7 j K 1616.7 37.9 1679.0 84.0 1533.3-1824.7 STW-696 Water Oct 1993 1-131 116.7 2.3 117.0 2.3 96.2-137.8 STW-697 Water Oct 1993 Gr. alpha 39.7 1.5 40.0 10.0 22.7-57.3 Ra-226 10.6*0.5 9.9* l .5 7.3-12.5 Ra-228 13.2*l.5 12.5*3.1 7.1-17.9 Uranium 15.3*0.6 15.1 3.0 9.9 20.3 119

1993 Davis-Besse Nuclear Power Sation Annual Radiological Environmental Operating Report Concentration in oCi/Lh TBEESML Lab Sample Date Results *2 EPA Results' Control d

Code Type Collected Analyses sigma is,N=1 Limits STW-698 Water Oct 1993 Beta 52.0*l.0 58.0 10.0 40.7-75.3 S 89 11.3 0.6 15.0 5.0 6.3-23.7 Sr-90 11.0 0.0 10.0 5.0 1.3-18.7 Co-60 10.7A0.6 10.015.0 1.3-18.7 Cs-134 10.0 1.0 12.0 5.0 3.3-20.7 Cs-137 12.3 1.2 10.0 5.0 1.3-18.7 i

STW-699 Water Oct 1993 Alpha 18.3 2.5 20.0*5.0 11.3-28.7 Beta 13.7*0.6 15.0 5.0 6.3 23.7 STW-700 Water Nov 1993 H-3 7310.0 175.2 7398.0*740.0 6114.1-8681.9 STW-701 Water Nov 1993 Ba-133 75.7 7.6 79.0*8.0 65.1-92.9 Co-60 30.7 2.1 30.0*5.0 21.3-38.7 Cs-134 51.3*5.9 59.0 5.0 50.3-67.7 Cs-137 41.7*l.2 40.0*5.0 31.3-48.7 Ru-106 163.3*3.2 201.0 20.0 166.3-235.7 l Zn-65 157.0*8.7 150.0*15.0 124.0-176.0 l

Results obtained by Teledyne Isotopes Midwest Laboatory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S. Environmental Protection Agency (EPA) Las Vegas, Nevada.

b l All results are in pCi\l, except for elemental potassium (K) data in milk, which are in mg\l, air filter samples, which are pCi\ filter; and food which is mg\kg.

• USEPA results are presented as the known values and expected laboratory precision (1s, I determination) and the control limits as defined by the EPA.

d Unless otherwise indicated, the TBEESML results are given as the mean

• 2 standard deviations for i three determinations. I t

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1993 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Reimrt Explanation of results outside EPA Control Limits i

Lab Code Analysis Explanation  :

)

STW-682 Gr Alpha Gross alpha analysis was repeated with similar results. An investigation of possible cause for the deviation from the EPA was conducted with no cause discovered. The sample was spiked with Th-230; so Alpha spec Analysis for Th 230 was performed in triplicate with results of 15.5*2.1, 13.4*l.4, and 14.8 2.0. It should be noted that 66% of all participants failed this analysis with a grand average of 17.1. This coupled with the support of the Alpha Spec results leaves TIML cause to beleive that there may have been a dilution error at the EPA. It should be noted that on the next Gross Alpha EPA check, TIML reported results that were ex-actly the known value. Since no apparent cause can be found, and TIML had outstanding results on the following samples, it is felt that no further investigation is needed. I STW-687 Sr-89 No cause for the low result for Sr-89 was found. The analyst has been observed performing this procedure with no noted discrepancies. Tele- I dyne will continue to monitor this procedure in the future. No further ac-tion is anticipated unless conditions warrant.  ;

l STM-695 Sr-89 Report was received 1/18/94; an investigation is underway as to the cause i of the low Sr-89 results. In house spikes have been prepared and the analysis is in progress (see SPM-4848 and SPM-4849 in future rerports).

There is no apparent cause of the low Sr-89 results. In-house spikes have been prepared and the analysis is in progress. The analyst has been ob-served performing this procedure with no discrepancies noted. No further action is planned unless the results of the in House spikes show a problem.

STW-701 Ru-106 The report was received on 2/14/94; the cause of the cause of the low Ru-106 is under investigation. It should be noted that the grand average of all participants in this analysis was 175.2 pCi/L, with 54% of the par-ticipants outside of limits.

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. . . - - - . . . . ~ . . - - -. - - -. - - - - - - - - - ' - - - -' ~ --~

1993 Davis Besse Nuclear Power Station Annual Radiological Environmental Operating Report t

r i TABLE A 2 CROSS CHECK PROGRAM RESULTS i

THERMOLUMINESCENT DOSIMETERS (TLD'S)  ;

i mE Lab TLD Measurement TBEESML Known value Average *2s0 Code Type Results *2 sigma (All participants)

• 2 Sigma 93-1 Te edyne Mar 1993 Lab 10.0 1.0 10.2 ND Lif-100 Chips 25.5 2.2 -25.5 ND 42.7*5.7 45.9 ND ND=No Data; Teledyne Testing was only peiformed by Teledyne isotopes.

Cards and Chips were irradiated by Teledyne Isotopes, Inc., Westwood NL on March 10,1993.

Due to a potential error of10-12% when the cards were irradiated, results of the testing on the cards will not be published. Data available upon request.

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1993 Davis.Desse Nuclear Power Station Annual Radiological Environmental Operating Reprt Table A.3. In. house " spike" samples Concentration in nCi/La Lab Sample Date Analyses TBEESML Code Type Collected Result Known Control 2s,n=1 6 Activity limits SPM.3341 Milk Jan 93 Sr.89 6.73.1 8.7 0.0 18.7 l Sr.90 20.0*l.2 19.2 9.2-29.2 I Cs.134 17.l*2.0 21.3 11.3 31.3 Cs.137 21.4 2.2 23.8 13.8-33.8 SPM.3387 Milk Feb 93 1 131 72.5*8.4 71.5 57.2 85.8 SPS.3401 Vegetation Feb 93 1131 994.5*53.2 953.7 763.0 1144.4 (Saw Dust)

SPS.3402 Charcoal Feb 93 1 131 95.2*12.8- 95.4 76.3 114.5 SPW.3434 Water Feb 93 Gr. alpha 10.4 1.8 10.4 0.4 20.4 l Gr. beta 22.0*2.0 20.6 10.6 30.6 SPW.3556 Water Apr 93 Sr-89 18.2 5.0. 22.2 12.2 32.2 Sr.90 20.I 1.8 17.0 7.0 27.0 ,

SPW.3597 Water Apr 93 H.3 5464*219 5428 4342.4-6513.6 SPW.3599 Water Apr 93 I.131 149.8 1.9 145 116.0 174.0 )

SPW.3606 Water Apr 93 Co-60 24.8 2.3 21.5 11.5 31.5 l Cs.134 26.4*l.9 26.4 16.4 36.4 Cs.137 33.9 2.6 31.7 21.7 41.7 SPM 3631 Milk Apr 93 I.131 139.8tl.6 145.0 116.0 174.0 Cs.134 48.8*2.9 52.8 42.8 62.8 Cs.137 65.2 2.9 63.4 53.4 73.4 SPS-3681 Fish May 93 Cs.137 68.2*7.7 67.6 57.6 77.6 (Jello)

SPW.3842 Water Jun 93 Th.230 4.2*0.5 4.5 2.7 6.3 SPW.4160 Water Jun 93 Alpha 8.9* l .4 12.9 7.7 18.1 Beta 22.0*l.9 31.9 19.1 44.7 SPW.4232 Water Aug 93 Fe.55 1684*415 1420 1136.0 1704.0 SPW.4246 Water Aug 93 Sr.90 32.2 2.6 30.4 24.3 36.5 123

l 1993 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Reprt l

Lab Sample Date Analyses TBEESML Code Type Collected Result Known Control 2s,n= 1 Activity Limits SPM-4247 Milk Aug 1993 Sr89 29.l*4.9 35.4 25.4-45.4 Sr-90 18.3*l.3 19.2 9.2-29.2 SPW-4248 Water Aug 1993 H-3 9910*300 10430 8344-12516 l SPW-4250 Water Aug 93 Co-60 247.0 23.1 247.7 222.9-272.5 Cs-134 141.6*15.9 141.1 127.0-155.2 Cs-137 283.5*27.8 247.2 222.5 271.9 I SPS-4251 Fish (jello) Aug 93 Cs-134 68.8*3.3 75.3 65.3-85.3 Cs 137 203.6 8.2 198.1 178.3-217.9 SPS-4262 Bottom Aug 93 Cs-134 74.1 9.9 71.0 61.0-81.0 Sediment Cs-137 212.4tl4.8 197.8 178.0-217.6 SPW-4377 Water Sep 93 1-131 39.0il 0.0 42.1 30.1-54.1 SPM-4378 Milk Sep 93 1-131 44.5 5.5 42.1 30.1-54.1 SPCH-4379 Charcoal Sep 93 1-131 90.3*13.5 84.3 67.4-101.2 SPS-4380 Vegetation Sep 93 1-131 193.2*20.0 170.2 136.2-204.2 (Sawdust)

SPW-4381 Water Sep 93 Sr-89 21.9 4.0 28.8 18.8-38.8 Sr-90 19.5*l.9 19.0 9.0-29.0 l SPW-4382 Water Sep 93 1129 18.1 1.0 18.6 6.6-30.6 SPW-4421 Water Oct 93 H-3 16900 368.0 17380 13904-20856 SPW-4428 Water Oct 93 Co-60 19.3 3.1 18.3 8 3-28.3 i Cs-134 31.5t3.3 33.5 23.5-43.5 l Cs 137 44.4 3.6 43.2 33.2-53.' 1 SPM-4426 Milk Oct 93 I-131 49.7*8.6 44.5 32.5-56.5 Cs-134 30 8*4.5 33 0 23.0-43.0 1 Cs 137 43.416.0 43.2 33.2-53.2 SPW-4427 Water Oct 93 I-131 95.2i10.6 88.9 71.1 106.7 l

All results are in pCi/l, except elemental potassium (K) data in milk, which are in mg/L: air filter j samples, which are in pCi/ filter; charcoal which are in pCi/ charcoal; and food products which are in mg'kg.

b All samples prior to January 1991 are the results of three determinations; after January 1991, all determination are single.

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1993 Davis Besse Nuclear Power Station Annual Radiological Environmental Operating Report

- Table A-4:In. house " blank" samples.

Concentration oci/L' TBEESML Results '

(4.66) sigma Lab Sample _ Date . Acceptance.  !

Code Type Collected Analysis LLD. . Activity' . Criteria (4.66) Sigma l SPM.3342 Milk Jan 1993 Sr-89 <0,7 -0.9* l .1 <5  !

. . S r.90 NA- 1.6*0.5 <1 l Cs.134 <4.1 0.92.6 <10 l

- Cs.137 <3.9 0.8*2.2 <10 l Low levels of Sr.90 concentration in milk (1 5pCi/l) is not unusual. l SPM.3386 Milk Feb 1993 I.131 <0.2 0.10.1 <1 SPW-3557 Water Mar 1993 Sr.89 <0,5 0.3*0.5 <5 l

. Sr-90 <0. 5 0.1*0.2 <1 l SPW-3598 Water Apr 1993 H.3 <180 84.7*94.2 <300 I SPW-3600 Water: Apr 1993 1131 <0.2 0. l*0.2 <1 SPW.3601 Water ~Apr 1993 Co.60. <4.2 <10 Cs.134 <4.4 <10 Cs.137 - <3.4 <10 1 131 <0.4 0.3 0.9 < l .0 i SPM.3651 Milk May 1993 I.131 <0.2 0. l *0.1 <1 l Cs.134 <4.4 <10 l Cs.137 <6. 3 <10 SPS-3680 Food May 1993 Cs-137 <6. 5 0.00.0 <10 SPS-3844 Water Jun 1993 Th.228 <0.1 0.0*0.1 <l Th.230 <0.1 0.2*0. I <1 Th-232 <0.1 0.0i0.0 <1 SPW.4234 Water Jun 1993 Gr. Alpha <0.3 0.00.2 < l .0 Gr. Beta <0. 8 0.2 0.3 <5.0 SPS.4059 Bottom Jun 1993 Cs-134 <5.0 0.0*0.0 <10 Sediment Cs.137 <7. 2 0.0 0.0 <10 SPS-4060 Wgetation Jul 1993 1-131 < l 3.5 0.00.0 <20 (sawdust) Cs-134 <4. 8 0.00.0 '<10 Cs-137 <6.4 0.0*0.0 <10 SPM.4061 Milk Jul 1993 Cs-134 <8.6 0.0 0.0 <10 Cs.137 <5.8 0.00.0 <10 125 l

__ . . - . .. - - . - - ,- - -.--.~.... = -- - - - ~ ~ --- - - - - - - - -

l 1993 Davis-Besse Nuclear Power Station Annual Radiological Environrnental Operating Report Concentration oCi/L' TBEESML Results (4.66) sigma Lab Sample Date Acceptance Code Type Collected Analysis LLD Activity

• Criteria (4.66) Sigma SPM-4062 Milk Jul 1993 Cs-134 <3.8 1.5*l.5 <10 Cs-137 <4.4 -1.63.3 <10 SPW-4063 Water Jul 1993 Co-60 <4.0 1.2*2.3 <10 Cs-134 <3.7 0.3 1.2 <10 Cs-137 <3.2 0.4*3.2 <10 SPAP-4064 Air Fliter Jul 1993 Cs-134 <2.1 0.00.0 <10 (composite) Cs-137 <2.8 0.0*0.0 <10 6

SPCH-4065 Charcoal Jul 1993 I-131 <0.06 0.0*0.0 <0.07*

SPW-4233 Water Aug 1993 Fe-55 <506 0.00.3 <1000 SPW-4235 Milk Aug 1993 1-131 <0.1 0.00.2 <1 Cs-134 <8.1 1.6 1.8 <10 Cs-137 <4.2 -1.73.4 <10 Sr-89 <0. 8 -1.01.1 <5

Sr-90 NA 1.8 0.5 <10 Low level of Sr-90 concentration in milk (1-SpCi/l) is not unusual.

SPW-4241 Water Aug 1993 H-3 <l90 72.9i99.1 <300 i SPW-4243 Water Aug 1993 Sr-89 < 1.1 -0.6*0.9 <5 l Sr-90 <0. 7 0.4i0.4 <1 l l-131 <0.5 0.0t0.1 <1 Co-60 <7.0 0.43.I <10 Cs-134 <7.6 0.8 15.6 <10 Cs-137 <5.4 -0.74.2 <10 l SPW-4244 Water Aug 1993 U-233/234 <0.1 0.1 0.1 <1 U-235 <0.1 0.00.1 <!

U-238 <0.1 0.10.1 <1 l Th-228 <0.4 -0. l *0.3 <1 Th-230 <0.1 0.00.1 <l

! Th 232 <0.1 0.00.0 <1 Pu-238 < l .0 0.4*0.7 <1 PU-239/240 <0.3 0.10.2 <1 SPW-4245 Water Aug 1993 Ra-226 <0.1 0.00.0 <!

Ra-228 <0. 8 -0.2*0.5 <1 SPW-4422 Water Oct 1993 H-3 <l80 -27.5 W 9 <300

• All results are in pCi\l, Except for air filter samples, which are in pCi/ filter 6

Prior to 1993, results were reported as LLD, the activity reported is the net activiu .esults.

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1993 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Reprt TIM L-BLIND-01 Revision 0,12-29-86 ATTACIIMENT A ACCEPTANCE CRITERIA FOR " SPIKED " SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIAITON VALUES FOR VARIOUS s

ANALYSES' i

One Standard Deviation Analysis Level for a Single Determination Gamma Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter

>100 pCi/ liter or kg 5% of known value

• ium-896 5 to 50 pCi/ liter or kg 5 pCi/ liter

>50 pCi/ liter or kg 10% of known value Strontium-906 2 to 30 pCi/ liter or kg 5.0 pCi/ liter

>30 pCi/ liter or kg 10% of known value Potassium >0.1 g/ liter or kg 5% of know value Gross alpha <20 pCi/ liter 5 pCi/ liter

>20 pCi/ liter 25% of known value Gross beta <100 pCi/ liter 5 pCi/ liter

>100 pCi/ liter 5% of known value fritium <4,000 pCi/ liter 1 s=(pCi/ liter)=

169.85 x(known)""

>4,000 pCi/ liter 10% of known value Radium-226, -228 <0.1 pCi/ liter 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value Iodine-131, <55 pCi/ liter 6 pCi/ liter Iodine-1296 >55 pCi/ liter 10% of known value Uranium-238 <35 pCi/ liter 6 pCi/ liter Nickel-646, >35 pCi/ liter 15% of known value Technetium-996 Iron-55 6 50 to 100 pCi/ liter 10pCi/ liter

>100 pCi/ liter 10% of known value

a. From EPA Publication, " Environmental Radioactivity Laboratory Intercompaison Studies Program, Fiscal Year 1981 -1982, EPA-60014-81-004,

b. TBEESML limit.

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1993 Davis.Besse Nuclear Power Station Annual Radiological Environmental Operating Report I

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APPENDLX B DATA REPORTING CONVENTIONS l

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1 1993 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Reprt

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I Data Renortine Conventions 1.0 All activities except gross alpha and gross beta are decay corrected to collection time or the j end of the collection period.

j 2.0 Sinale Measurements

Each single measurement is reported as follows

xis where x = value of the measurement; s=20 counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is found to be below the lower limit of detection L it is ' reported as

<L where L = the lower limit of detection bases on 4.660 uncertainty for a background sample.

3.0 Duolicate analyses 3,1 Individual results: x, s, 1

x is:

i Reoorted result: xs where x = (1/2)(xl x2) 2 2 s= (1/2) s, + s 3.2 Individual results: <L, '

<L:

l Reoorted remh; <L

]

where L = lower Li and L, 1

129 9

, m.-,_.,.. . _ _ _ . . , - . . _ _ . ,,- -,, , . . . .. _.i.....,, , - . _

1993 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report 3.3 Individual results: x*s l

<L Reported result: x

• s ifx 2 L;

<L otherwise 4.0 Comoutation of Averages and Standard Deviations j 4.1 Averages and standard deviaitons listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard -

deviations (s) of a set of r numbers x i , x, ..x are defined as follows:

x=Qx n

s= IR-W n-1 I i

4.2 Values be!ow the highest lower limit of detection are not included in the average I

4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated sigma error is reported.

4.5 In rounding otr, the following rules are followed:

4.5.1 If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example,11.443 is rounded ofTto 11.44.

4.5.2 If the figure following those to be retained is greater that 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.4446 is rounded ofTto 11.45, 4.5.3 If the figure following those to be retained is 5, and if there are no figures other than zeros beyond the five, the figure five is dropped, and the last-place figure retained is increased by one ifit is an odd number or it is kept unchanged if an even number. As an example,11.435 is rounded ofTto 11.44, while 11.425 is rounded o!Tto 11.42.

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1993 Das s-Besse Nuclear Power Station Annual Radiological Environmental Operating Repon i

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l APPENDIX C Emuent Concentration Limit of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas

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, . , _ , , ,, m.-. _ , y ., , . _ , .. 7,,. ,,,. ..y,

1993 Davis-Besse Nuc! car Power Station Annual Radiological Environmental Operating Repon Table C-1 Efiluent Concentration Limit of radioactivity in air and water above natural background in unrestricted areas.*

Air Water Gross alpha 3 pCi/m' Strontium-89 3,000 pCi/l Gross beta 100 pCi/m' Strontium 90 300 pCi/l b

Iodine-131 0.14 pCi/l Cesium-137 20,000 pCi/l Barium-140 20,000 pCi/l Iodine-131 300 . pCi/l Potassium-40' 3,000 pCi/l Gross alpha 30 pCi/l Gross beta 100- pCi/l Tritium 1 x 10' pCill

• Taken from Code of Federal Regulation Title 10, Pert 20, Table II and appropriate footnotes.

Concentrations may be averaged over a period not greater than one year.

b From 10 CFR 20 but adjusted by a factor of 700 ta reduce the dose resulting from the air-grass-cow-child pathway.

• A natural radionuclide.

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_e .. _,., _ .- _ ,_. , . , , _ . _y.., -,m. . , , , ,,.,,.,y..,., , ...,.,,,-4 , -,

1993 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Reprt APPENDIX D REMP Sampling Summary 133

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l Table D.1 Radiological Environmental Morutonng Program Summary.

Name of Fachty Davis-Desse Nuclear Power Station Docket No. 50-346 Location of Faabty Ottawa, Ohio Reporting Penod January December 1993 (County, State) ,

1 Indicator Location with litghest Sample Type and Locations Control Number Quanerly Mean Type Number of Locations Non-LLDb Mean (F)C (Units) Analyses a Mean (F)C Mean (F)c Routme Rangec Locationd Rangec Range Results*

Airbome CB 530 0.005 0.021 (317/318) T 11, Port Clinton parnculates 0.023 (53/53) 0.022 (212/212) O (0.007 4.049) Water Treatment (0.009-0.046)

(pCi/m3) Plant,9.5 mi SE (0.009-0.046)

Sr-89 0.0016 <LLD - -

<LLD 0

$r-90 0.0006 0.0007 (1/24) T 3, Site boundary. 0.0007 (1/1) <LLD 0 1.4 mi. ESE CS 40 Be-7 0.015 0.069 (24/24) T-11, Port Clinton 0.074 (4 /4) 0.070 (16/16) 0 (0.048 4.089) Water Treatment (0.057-0.090) (0.056-0.090)

Plant,9.5 mi SE K-40 0.063 <LLD - -

<LLD 0 Nb-95 0.0047 <LLD -

<tLD 0 Zr-95 0.0077 <LLD - 1

<LLD 0 l

Ru-103 0.0040 <LLD - -

<LLD 0

)

Ru-106 0.030 <LLD -

<tLD 0 Cs-134 0.0032 <LLD -

<LLD 0 Cs-137 0.0034 (LLD -

(LLD 0 Ce-141 0.0053 <LLD - -

<LLD 0 Ce-144 0.019 <LLD -

<LLD 0 1 Autome I-131 530 0.07f (LLD -

lodine

<LLD 0 (pCi/m3) 1 TLD Camma 370 1.0 T-52, Farm 14.4 (278/278) 20.4 (4/4) 0 (Quarterly) 15.5 (92/92)

(6.6-24.6) 3.7 mi. S (17.7246)

(mR/91 days) (9.1 21.3)

T4 Site boundary 20.4 (4/4) 0.3 mi ENE (18 2-22.6)

TLD (Annual) Camma 90 1.0 56.1 (67/67) T-8 Farm,2.7 mi (mR/365 80.7 (1/1) 63.2 (23/23) 0 (33.2-80.7) WSW days) (46.2-75.4)

Milk (pCi/L) 1-131 36 03 <LLD - -

<LLD 0 3r-89 36 1.1 <LLD - -

<LLD 0 134 4

e - , r ,

Table D-1 Radiological Enytronmental Monitonng Program Summary.

i Name of Facility Davis-Besse Nuclear Power Station Docket No. 50 346 location of Facthty Ottawa, Ohio Reporting Penod lanuary - Decernber 1993 (County, State) 1 Indicator Location with Highest Sample Type and Control Number Locations Quarterly Mean Type Locations Non-Number of LLDb Mean (F)C

)

(Units) Mean (F)C Mean (F)c Routine Analysen a Rangec Locationd  !

Rangec Range Results' l Milk (pCl/L) Sr-90 36 0.5 1.2 (18/18) Both locations had 1.2 (36/36) 1.2 (18/18) 0 (amtmued) (0.6-1.6) identical means (0.6-1.7) (0.9-1.7)

CS 36 K-40 100 1390 (18/18) T-8, Farm,2.7 mi 1390 (36/36) 1340 (18/18) 0 (1260-1510) WSW (1260-1510) (1190-1480)

Ce137 10 <LLD - -

<LLD 0 Da-La-140 10 <LLD - -

<LLD 0 (g/L) Ca 36 0.50 0.88 (18/18) Alllocations had 0.88 (36/36) 0.88 (18/18) 0 (0.69-1.02) identical means (0.69 1.02) (0.77-0.98)

(g/L) K(stable) 36 0.04 1.61 (18/18) T-8, Farm, 1.61 (18/18) 1.54 (18/18) 0 (1.46-1.75) 2.7 mi WSW (1.46-1.75) (1.38-1.71)

(pCi/g) Sr-90/Ca 36 0.36 1.34 (18/18) T-24, Sandusky, 1.36 (18/18) 1.36 (18/18) 0 (0.70 2.32) 21.0 mi SE (0.70 1.79) (0.70-1.79)

(pCi/g) Cs-137/K 36 7.25 <LLD - -

<LLD 0 Cround Water CB(SS) 16 0.8 <LLD (pCi/L)

<LLD 0 CB (DS) 16 1.8 3.7 (8/8) T-54, Farm, 3.8 (4 /4) 2.4 (4/8) 0 l (2.1-4.6) 4_8 mi SW (3.3-4.4) (1.9-2.8)

GY (TR) 16 1.8 3.7 (8/8) T-51, Farm 3.8 (4/4) 2.4 (4/8) 0 (2.1-4 8) 4.8 mi SW (3.3-4.4) (1.9-2.8)

H3 16 330 %5 (1/8) T.7, Sand Beach 965 (1/4) <LLD 0 ,

0.9 mi. NW l

3r-89 16 1.3 (LLD - -

<LLD 0 Sr-90 16 0.7 1.0(1/8) T-7, Sand Beach, 1.0(1/4) <LLD 0 0.9 mi NW CS 16 Mn-54 15 <LLD - -

<tLD 0 Fe-59 30 <LLD - -

<LLD 0 Co-58 15 <LLD - -

<LLD 0 Co-60 15 <LLD - -

<LLD 0 Zn-65 30 <LLD - -

<LLD 0 Zr-95 15 <LLD - -

<LLD 0 Cs-134 10 <LLD - -

<LLD 0 135

Table D 1 Radiological Enytronmental Morutonng Program Summary.

Name of Facihty Davis Besse Nuclear Power Station Docket No. 50-346 Wation of Facthty Ottawa, Otuo Reporting Pened January - December 1993 (County, State)

Indicator Location with liighest Sample Type and Locations Control Number Quarterly Mean Type Number of Locations Non-LLDb Mean (F)C (Uruts) Analysesa Mean (F)C Mean (F)c Routine Rangec locationd Rangee Range Results' Ground Water Cs-137 10 <LLD -

(pCi/L) <LLD 0 (conhnued) Ba La 140 15 <LLD -

<LLD 0 Edible Meat CS 3 (pCi/g wet)

K-40 0.1 2.65 (2/2) T 31, Onsite Roving 2.98 (1/1) 2.52 (1/1) 0 (2.32-2.98) location Cs 137 0.009 0.032 (1/1) T-31, Onsite Roving 0.032 (1/1) <LLD 0 Location Fruits and Sr-89 5 0.003 <LLD -

Vegetables

<LLD 0 l (pCi/g wet) Sr-90 5 0.001 0.006 (2/2) T-8, Farm, 0 009 (1/1) 0 002 (1/3) 0 2.7 mi WSW I-131 5 0.057 <tLD -

<LLD 0 GS 5 K-40 0.50 1.52 (2/2) T 173, Firelands 2.62 (1/1) 2.37 (4/4) 0 (1.15-1.88) Winery,20 mi. SE (0.74-4.09)

Nb-95 0.034 <LLD -

<LLD 0 Zr-95 0.081 <LLD -

<LLD 0 Cs-137 0.025 <LLD -

<LLD 0 Ce-141 0.030 <LLD -

<tLD 0 Ce-144 0.082 <LLD - -

<LLD 0 Broad leaf Sr-89 10 0.006 <LLD -

Vegetation

<LLD 0 (pCi/g wet) Sr-90 10 0.001 T-8, Farm, 0.006 (5/7) 0.006 (4 /4) 0 005 (3/3) 0 (0.002-0.012) 2.7 mi WSW (0.002 4 012) (0.001-0.008) 1-131 10 0.043 <LLD - -

<LLD 0 GS 10 K-40 0.1 4.78 (7/7) T-8, Farm, 5.26 (4/4) 2.61 (3/3) 0 (2.52-7.00) 2.7 mi WSW (2.52700) (2.05-3 46)

Nb-95 0.020 <LLD - J

<tLD 0 Zr-95 0.045 <LLD - -

<LLD 0 Cs-137 0.031 <LLD - -

<LLD 0 Ce-141 0.050 <LLD - -

<LLD 0 l

136 1

i l

Table D.I Radiological Environmental Monitonng Program Summary.

Name of Facility Davis.nesse Nudear Power station Docket No. 50- m Location of Facdtty Ottawa, Ohio Reporting Penod January December 1993 (County, State)

Indicator Location with Highest Control Sample Type and locations Quarterly Mean Number Locations Non- l Type Number of LLob Mean (F)C Mean (F)C Mean (F)c Routine (Umts) Analyses a Rangee Locationd Rangec Range Results' Broadleaf Ce-144 0.18 <LLD Vegetation

<lLD 0 (pCi/g wet) '

l (amtmued)

Eggs GS 2 (pCi/g wet)

K-40 0.01 1.14 (1/1) T-34, Offsite Rovmg 1.41 (1/1) 1.41 (1/1) 0 location.210 mi.

Nb-95 0.005 <LLD - -

<LLD 0 Zr-95 0.010 <LLD - -

(LLD 0 Ru 103 0.006 <LLD - -

<LLD 0 Ru-106 0.054 <LLD <LLD 0

Cs-137 0.005 <LLD -

<LLD 0 j 1

Ce-141 0.011 <LLD - -

<LLD 0 Ce-144 0.047 <LLD - -

<LLD 0 i

Arumal GS 5 Wild!tfe Feed  !

j (pCi/g wet) Be-7 0.20 0 66 (1/4) T 198, Toussaint 0.66 (1/1) <LLD 0 j Creek ,4.0 mi, WSW K-40 0.1 5.67 (4/4) T-8, Farm, 12.80 (1/1) 5.80 (1/1) 0 j (0.86-12.80) 2.7 mi WSW '

Nb-95 0.029 <LLD -

<LLD 0 Zr 95 0.050 <LLD - -

<LLD 0 Ru-103 0 025 <LLD - -

<LLD 0 Ru-106 0.22 <LLD

<LLD 0 Cs 137 0.027 <LLD -

<LLD 0 Ce-141 0.028 <LLD - -

<LLD 0 Ce-144 0.14 < LLD - -

<LLD 0 Sod CS 22 (pCi/g dry)

Be 7 1.58 <LLD - -

<LLD 0 K-40 1.0 15.35 (12/12) T-8, Farm, 24.92 (2/2) 19 % (10/10) 0 (5.93-25.70) 2.7 mi WSW (24.13-25.70) (13.65-24.40)

Nb-95 0.27 <LLD - -

<LLD 0 137

1 I

Table D 1 Radiological Environmental Monitonng Program Summary.

Name of Facility Davis Besse Nuclear Power Station Docket No. 50-346 location of Facility Ortawa, Ohio Reporting Penod January - December 1993 (County, State)

Indicator Location with Highest

. Sample Type and Control Number Locations Quarterly Mean Type Locations Non-Number of LLDb

- Mean (F)C Mean (F)C Routine (Umts) Analm a Mean (F)c Rangec Locationd Rangec Range Results' Sod Zr-95 0 30 <LLD -

(pCi/g dry) <LLD 0 (centmurd) Ru-103 0.18 <LLD - -

<LLD 0 Ru-106 0.60 <LLD - -

<LLD 0 Cs-137 0.021 0.22 (10/12) T-23, South Bass 0.67 (2/2) 0.41 (10/10) 0 (0.035 4 76) Island,14.3 mi ENE (0.58-0.76) (0.23-0.76)

Ce-141 0.50 <LLD - -

<LLD 0 Ce-144 0.68 <LLD - -

<LLD 0 Treated GB (SS) 71 0.4 <LLD -

i Surface Water

<LLD 0 (pCi/L) GB (DS) 71 1.0 2.2 (36/36) T 50, Port Clinton 2.4 (12/12) 2.1 (35 /35) 0 (1.4 3.1) 45 mi. SE (1.9 2.9) (1.3-3.2)

T-144, Green Cove 2.4 (12/12)

Cond.,0.9 mi NNW (1.7 3.1)

GB (TR) 71 1.0 2.2 (36/36) T-50, Port Chnton, 2.4 (12/12) 0 2.1 (35 /35)

(1.4-3.1) 4.5 mi. SE (1.9 2.9) (1.3-3.2)

T-144, Green Cove 2.4 (12/12)

Cond.,0.9 mi NNW (1.7 3.1)

H-3 24 "L30 355 (1/12) T-144, Green Cove 355 (1/4) <LLD 0 Cond.,0.9 mi NNW s

St-89 24 2.4 <LLD - -

<LLD 0 St90 24 1.0 <LLD - -

<tLD 0 CS 24 Mn 54 15 <LLD - -

<tLD 0 Fe-59 30 <LLD - -

<LLD 0 Co-58 15 <LLD - -

<LLD 0 Co40 15 <LLD - -

<LLD 0 Zn-45 30 <LLD -

<LLD 0

Zr-95 15 <LLD - -

<LLD 0 CelM 10 <LLD - -

<LLD 0 Ce137 10 <LLD - -

<LLD 0 Ba-La-140 15 <LLD - -

(LLD 0 138

Table D 1 Radiological Environmental Monitonng Program Summary.

Name of Facility _Davts-Besse Nuclear Power Station Docket No. 50-346 Location of Facihty _ Ottawa, Ohio Reportmg Penod January December 1993 (County, State) ~

Indicator location with Highest Sample Type and locations Control Number Quarteriv Mean Locations Type Number of LLob Non-Mean (F)C Mean (F)C Routme (Units) Analysesa Mean (F)c Rangec Locationd Rangec Range Results' Untreated CB (SS) 112 0.8 0.8 (3/56) T-12, Intake . 1 Surface Water 1.0 (1/12) 1.0 (1/56) 0 l (0.84).9) 11.25 mi NW (pCi/L)

GB (DS) 112 1.0 2.8 (56/56) T-152, Maumee Bay 3.5 (4/4) 2.5 (56/56) 0 (1.5-5.1) State Park.15.6 (3.0-4 0)

)

(1.6-4 0)  !

mi WNW l

CB (TR) 112 1.0 2.9 (56/56) T-3, Site Boundary, 3.6 (12/12) 2.5 (56/56) 0 (1.5-5.4) 1.4 mi ESE (1.9 5.4)

(1.642) '

H3 112 330 622 (1/56) T-50, Port Clinton,  !

622 (1/12) <LLD 0 4.5 mi SE Sr-89 24 16 <LLD - -

<LLD 0 St-90 24 0.7 0.7(1/12) T-3, Site Boundary, 0.7 (1/4) <LLD 0 1.4 mi ESE CS 150 l Mn 54 15 <LLD - -

<tLD 0 j Fe-59 30 <LLD - -

<LLD 0 Co-58 15 <LLD - -

(LLD 0 Co-60 15 <tLD - -

<LLD 0 Zn45 30 <LLD - -

<LLD 0 Zr-95 15 (LLD - -

<LLD 0 Cs-134 10 <LLD - -

<LLD 0 Cs 137 10 (LLD - -

<LLD 0 Ba La 140 15 <LLD - -

(LLD 0 Fish CB 9 0.1 3 51 (3/3) T-33, Lake Erie,1.5 3.51 (3/3)

(pCi/g wet) (265475) 2.95 (6/6) 0 miNE (2.65-4.75) (1.96425)

CS 9 K-40 0.1 2.35(3/3) T-35,1.ake Ene, >10 2.83 (6/6) 2.83 (6/6) 0 (1.95-2.60) mi radius (1.92 3.94) (1.92 3.94)

Mn 54 0.017 <LLD - -

<LLD 0 Fe-59 0.064 <LLD - -

<LLD 0 Co-58 0.019 (LLD - -

<LLD 0 Co-60 0.014 <LLD - -

<LLD 0 Zn-65 0.036 <LLD - -

<LLD 0 139

i 1

l I

a Table D I Radiological Environmental Morutonng Program Summary Name of Fac6ty Davts Besse Nuclear Power Station Docket No. 50-346 location of FacWty Ottawa, Ohio .

Reporting Penod Januari - December tw3 (County, State)

Indicator Location with Highest a

Sample Type and Control Number Locahora Quarterly Mean Type Locatiosu Non-Number of LLDb Mean (F)C Mean (F)C Routine 1 (Units) Amiga Mean (F)c r

Rangec Locationd Rangec Range Results' Fish Cs-134 0.016 <LLD -

(pCi/g wet)

<LLD 0 (continued) Cs-137 0.020 <LLD - -

<LLD 0 Shoreline CS 16 Sediments (pCi/g dry) K-40 0.1 15.33 (8/8) T 138, take Erie, 28.39 (2/2) 18 45 (8/8) 0 (11.80-20 67) 11.0 mi NW (25.51-31.27) (13.59-31.27)

Mn-54 0.063 <LLD - -

<LLD 0 Co-58 0.074 <LLD - -

<LLD 0 Co-60 0.059 <LLD - -

<LLD 0 Cs-134 0.13 <LLD - -

<LLD 0 Cs-137 0.042 0.16 (3/8) T 138, Lake Erie, 0.68 (2/2) 0.31(6/8 0 (0046028) 11.0 mi NW (0.49486) (00484 86) d GB = gross beta, GS = gamma scan, SS = suspended solids, DS = dissolved solids, IR = total residue.

b LLD = nominal lower Itmit of detection based on 4 C sigma counting error for background sample.

c Mean based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated parentheses (F).

d Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site.

• I Non-routtne results are 3 those which exceed ten times the control station value.

One result (<0.10 pC1/m ) exceeded required LLD. The LLD was not reached due to low volume.

140 v

i 4

Attachment 1 i

to the i

ANNUAL RADIOLOGICAL ENVIRONAIENTAL OPERATING i REPORT 1 l

Radiological Environmental Monitoring Program Sample Analysis Results i

i for I

l

, Davis-Besse Nuclear Power Station l January 1,1993 to December 31,1993 Prepared by:

l!

2 Radiation Protection Section Davis-Besse Nuclear Power Station j Toledo Edison Company

. Toledo, Ohio

April 1994 3

h l

i a

, r- -. - - - , . , _ , ,. ..

i i

l i

Table of Contents I

l Description Pace No.

List of Tables 11 Introduction 1 t

Data Tables 2 l l Appendix A-1 I

l l

I i

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

l l

4 List of Tables

)

1 Table No. Descriotion Pace No.

1 Airborne particulates and iodine 2 I collected at Location T-1, analyses i for gross beta and iodine-131.

2 Airborne particulates and iodine .

3 collected at Location T-2, analyses.

for gross beta and iodine-131.

3 Airborne particulates and' iodine 4 collected at Location T-3, analyses for gross beta and iodine-131.

4 Airborne particulates and iodine 5 collected at Location T-4, analyses for gross beta.and iodine-131.

5 Airborne particulates and iodine 6 collected at Location T-7, analyses for gross beta and iodine-131.

6 Airborne particulates and iodine 7 .

collected at Location T-8,. analyses-for gross beta and iodine-131.

7 Airborne particulates and iodine 8 collected at Location T-9, analyses for gross beta and iodine-131.

8 Airborne particulates and iodine 9 collected at Location T-11, analyses ,

for gross beta and iodine-131.

9 Airborne particulates and iodine 10 collected at Location T-12, analyses for gross beta and iodine-131.

)

10 Airborne particulates and iodine 11 collected at Location T-27, analyses i for gross beta and iodine-131. l l

11 l i

l

l' l

l List of Tables (continued)

Table No. Descrintion Pace No.

I 1

11 Airborne particulates, gross beta 12 analyses, monthly averages, minima, and maxima, 1993.

12 Airborne particulates, of all indicator 18 and all control locations, analyses for strontium and gamma-emitting isotopes, 1993.

1 1 13 Area monitors (TLD), 22 l l Collection: Quarterly. 1993.  !

I l 13 Area monitors (TLD), 1993.

Collection: Annually.

14 Milk samples, analyses for strontium-89, 30 i strontium-90, iodine-131, and I gamma-emitting isotopes. l Collection: Semimonthly, May through October, monthly otherwise. l l

15 Milk samples, analyses for calcium, 32 l stable potassium, and ratios of l pCi strontium-90/g calicum and l l pCi cesium-137/g potassium, l Collection: Semimonthly, May-through l October, monthly otherwise. l 16 Groundwater samples, analyses for 34 I I

gross beta, strontium-89, strontium-90 and gamma-emitting isotopes.

Collection: Quarterly.1993.

17 Domestic meat samples, analysis for 37 gamma-emitting isotopes.

Collection: Annually.

18 Wildlife meat samples, analysis for 38 gamma-emitting isotopes.

Collection: Annually when available.

19 Broad leaf vegetation, analyses for 39 strontium-89, strontium-90 iodine-131, and other gamma-emitting isotopes.

Collection: Monthly in season.

iii isa .. - . , + - ,ea 3-

List of Tables (continued)

Table No. Descriotion Pace No.

20 Fruit samples, analyses for strontium-89, 40 ,

strontium-90, iodine-131, gamma-emitting isotopes.

Collection: Monthly in season.

21 Animal-wildlife feed samples, analysis 41 for gamma-emitting isotopes.

Collection: Annually.

22 soil samples, analysis for gamma- 42 emitting isotopes, collection: Semiannually.

23 Treated surface water samples, 44 analysis for gross beta.

Collection: Monthly composites of weekly samples. 1993.

24 Treated surface water samples, 51 analyses for tritium, strontium and gamma-emitting isotopes.

Collection: Quarterly composites of weekly samples. 1993.

25 Untreated surface water samples, 53 analysis for gross beta, tritium, and gamma-emitting isotopes.

Collection: Monthly composites of weekly samples. 1993.

26 Untreated surface water samples, 60 analysis for strontium, collection: Quarterly composites of weekly samples. 1993 I

iv

f List of' Tables (continued)

Table No. Descriotion Pace No.

27 ' Untreated, surface lake water samples, 62 analysis for gross beta, tritium, and gamma-emitting isotopes, collected-Collection: Monthly grap samples, May through October.1993.

28 Fish samples, analyses for gross beta 66 )

and gamma-emitting isotopes. i Collection: Semiannually. I 29 Shoreline sediment samples, analysis 67 for gamma-emitting isotopes.

Collection: Semiannually.

30 Egg samples, analysis for gamma-emitting 69 isotopes.

Collection: Annually.

]

A-1 Elevated LLDs in Airborne Iodine Samples A-1 1

v

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

Introduction Attachment 1 to the Davis-Besse Nuclear Power Station 1993 Annual Radiological Environmental Operating Report (AREOR) includes the  !

results of analysis of.all radiological environmental radiation measurements taken as part of the 1993 Radiological Environmental Monitoring Program (REMP) . The summaries provided in Appendix E and thoughout the text of the 1993 AREOR are based on the data presented in the following table.

Data tabulation and sample analyses results were provided by Teledyne Brown Engineering Environmental Services Midwest Laboratory (TBEESML) in the TBEESML Final Progress Report to Toledo Edison (Feb'1994).  :

i t

l 1

I

i l

IOLFDO Table 1. Airborne particulates and charcoal canister .

I Analyses: Cross beta and iodine-131 a Location: T-1 Units: pCi/m 3 Collection: Weekly Exchange Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross Beta Reauired LLQ 03.1 00.1 1

01 04-93 191 0.022 0.004 07-05-93 283 0.017 ! 0.003 01-11-93 180 0.022 0.004 07-12-93 283 0.020 0.003 01-18-93 241 0.038 t 0.004 07-19 93 284 0.015 0.003 01-25-93 191 0.022 1 0.004 07-26-93 288 0.020 0.003 l

02-01-93 190 0.026 0.004 08-02-93 283 0.021 t 0.003 02-08-93 232 0.022 0.004 08-09-93 285 0.017 1 0.003 02-15-93 228 0.020 t 0.004 08 16-93 283 0.044 0.004 02-22-93 192 0.027 0.005 08 23 281 0.024 0.004

! 03-01-93 200 0.027 0.005 08-30-93 277 0.030 0.004 l 03-08-93 304 0.016 0.003 09-06-93 281 0.020 0.003 03-15-93 202 0.012 t 0.004 09-13-93 285 0.016 t 0.003 03-22-93 200 0.019 0.004 09 20-93 284 0.018 0.003 03-29 93 201 0.007 0.004 09 27-93 281 0.023 0.003 l 1st Qtr. Mean s.d. 0.022 0.007 3rd Qtr, Meanis.d. 0.022 0.007 04-05-93 231 0.010 0.003 10-04-93 284 0.015 0.003

04-12-93 231 0.013 t 0.004 10 11-93 286 0.022 1 0.003 l 04-19-93 232 0.014 1 0.004 10-18-93 282 0.024 0.003 1 04-26-93 231 0.018 i 0.003 10-25-93 286 0.022 0.003 05-03-93 232 0.018 i 0.004 11-01 93 283 0.018 t 0.003 05-10-93 232 0.016 i 0.004 11-08 93 285 0.016 0.003 i 05-17-93 232 0.015 0.004 11 15-93 278 0.031 t 0.004 l 05-24-93 243 0.014 1 0.003 11-22-93 284 0.026 t 0.003 l 05-31-93 230 0.011 0.004 11-29 93 284 0.031 1 0.004 06-07-93 232 0.013 1 0.003 12-06-93 283 0.033 0.004 06-14-93 233 0.014 0.004 12-13 93 266 0.022 0.003 06-21-93 231 0.016 0.004 12 20-93 284 0.015 0.003 06-28 93 280 0.013 t 0.003 12-27-93 283 0.024 1 0.003 01-03-94 284 0.018 0.003 2nd Qtr. Mean s.d. 0.014 0.002 4th Qtr Meants.d. 0.023 1 0.006 Cumulative Average

0.020 Previous Annual Average: 0.019

^ Iodine-131 concentrations are <0.07 pCi/m$ unless otherwise noted in Appendix C.

I 2

l TOLEDO Table 2. Airborne particulates and charcoal canisters . I Analyses: Gross beta and iodine 131 d Location: T2 Units: pCi/m 3 Collection: Weekly Exchange f

Date Volume Date Volume

. Collected (m 3) Gross Beta Collected (m3) Gross Beta Required LLD DA1 021 01 04-93 260 0.017 1 0.003 07-05-93 286 0.019 0.003 01-11-93 283 0.032 0.004 07-12 93 271 0.027 t 0.004 01 18-93 289 0.029 0.004 07-19-93 279 0.015 0.003 01-25-93 289 0.019 1 0.003 07-26-93 278 0.020 t 0.003 02-01-93 287 0.021 0.003 08-02-93 278 0.022 t 0.004 02-08-93 284 0.020 0.003 08 09-93 279 0.016 t 0.003 02 15-93 280 0.024 0.004 08-16-93 278 0.044 1 0.004 02-22-93 290 0.030 1 0.004 08-23-93 280 0.024 0.004 03-01-93 290 0.025 t 0.004 08-30 93 275 0.038 0.004 03-08-93 27'4 0.036 0.004 09-06 93 278 0.021 t 0.003 03-15 93 310 0.017 0.003 09-13-93 276 0.020 0.003 03-22-93 277 0.018 0.003 09-20-93 278 0.020 1 0.003 03-29-93 288 0.010 0.003 09 27-93 278 0.023 t 0.003 1st Qtr. Mean s.d. 0.023 t 0.007 3rd Qtr. Mean s.d. 0.024 1 0.008 04-05-93 285 0.013 1 0.003 10-04-93 279 0.020 0.003 04-12-93 285 0.013 1 0.001 10-11-93 278 0.024 0.004 04-19-93 292 0.015 0.003 10-18-93 277 0.021 0.003 04-26-93 285 0.021 0.003 10-25-93 280 0.021 0.003 05-03-93 287 0.018 t 0.003 11-01-93 280 0.019 1 0.003 05 10-93 293 0.015 0.003 11-08-93 280 0.021 0.003 05-17-93 288 0.015 0.003 11-15-93 274 0.031 0.004 05-24-93 293 0.015 0.003 11-22-93 278 0.025 t 0.003 05-31 93 230 0.011 1 0.004 11-29 93 279 0.033 2 0.004 06-07 93 293 0.013 0.003 12-06-93 278 0.033 0.004 06-14-93 291 0.017 i 0.003 12-13-93 278 0.025 t 0.003 06 21-93 288 0.017 0.003 12-20-93 290 0.016 0.003 06-28-93 291 0.017 0.003 12-27-93 301 0.018 t 0.003 01-03-94 299 0.019 0.003 2nd Qtr. Mean s.d. 0.015 0.003 4th Qtr. Mean s.d. 0.023 0.005 Cumulative Average: 0.021 Previous Annual Average: 0.019 Iodine-131 concentrations are <0.07 pCi/m' unless otherwise noted in Appendix C.

3

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

IOLEDO Table 3. Airborne particulates and charcoal canisters.

Analyses: Gross beta and iodine 131 a Location: T3 Units: pCi/m 3 Collection: Weeldy Exchange Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross Beta Reauired LLD E g 01-04 93 277 0.021 0.003 07-05 93 284 0.016 t 0.003 01-11-93 279 0.029 1 0.004 07 12 93 284 0.018 0.003 01 18 93 278 0.033 1 0.004 07 19-93 295 0.016 t 0.003 01-25 93 279 0.019 t 0.003 07 26 93 288 0.019 t 0.003 02-01-93 268 0.019 1 0.003 08-02-93 366 0.019 i 0.003 02-08-93 275 0.021 1 0.003 08-09 93 289 0.017 i 0.003 02-15-93 272 0.022 0.004 08 16 93 293 0.045 0.004 02-22-93 273 0.029 t 0.004 08 23-93 284 0.023 1 0.004 03 01-93 279 0.028 i 0.004 08 30 93 283 0.031 t 0.004 03-08-93 273 0.033 t 0.004 09 06 93 288 0.019 i 0.003 03 15-93 282 0.020 1 0.003 09-13-93 285 0.020 0.003 03 22 93 266 0.024 t 0.004 09 20 93 288 0.016 0.003 03-29-93 278 0.010 t 0.003 09 27-93 294 0.024 1 0.003 1st Qtr. Mean s.d. 0.024 1 0.006 3rd Qtr. Meants.d. 0.022 1 0.008 04-05 93 274 0.014 0.003 10-04 93 288 0.017 i 0.003 04-12 93 270 0.012 0.003 10 11-93 288 0.023 0.003 04 19-93 276 0.018 t 0.003 10 18 93 286 0.027 i 0.004 04 26-93 276 0.021 0.003 10 25 93 270 0.024 0.004 05-03 93 276 0.019 1 0.003 11 01-93 279 0.018 t 0.003 05-10 93 279 0.020 0.003 11 08-93 283 0.015 t 0.003 05-17 93 279 0.015 t 0.003 11 15 93 273 0.029 0.004 05 24-93 278 0.019 t 0.003 11 22 93 282 0.024 i 0.003 05 31-93 272 0.009 0.003 11 29-93 282 0.024 1 0.003 06-07 93 279 0.012 0.003 12-06 93 277 0.034 0.004 06-14-93 286 0.016 2 0.003 12-13-93 282 0.027 0.004 06-21-93 282 0.017 0.003 12 20-93 282 0.022 1 0.003 06-28 93 285 0.017 1 0.003 12 27-93 282 0.024 1 0.003 01-03 94 279 0.020 t 0.003 2nd Qtr. Meants.d. 0.016 1 0.003 - 4th Qtr, Meanis.d. 0.023 1 0.005 Cumulative Average: 0.021 Previous Annual Average: 0.018

^ lodine-131 concentrations are <0.07 pCi/m' unless otherwise noted in Appendix C.

4

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

TOLEDO l

Table 4. Airborne particulates and charcoal carusters.

Analyses: Gross beta and iodine-131 8 Location: T4 Units: pCi/m 3 Collection: Weekly Exchange Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross Beta Required LLD 02 DE 01 04-93 282 0.022 t 0.003 07 05 93 278- 0.018 0.003 01-11 93 286 0.029 i 0.004 07 12 93 283 0.022 t 0.003 01-18 93 298 0.031 1 0.004 07-19-93 284 0.018 1 0.003 01-25 93 279 0.016 t 0.003 07-26 93 261 0.018 0.003-02-01 93 295 0.022 t 0.003 08-02 93 '279 0.021 t 0.003 02-08 93 284 0.021 1 0.003 08 09 93 283 0.017 1 0.003 02-15 93 279 0.024 t 0.003. 08 16 93 280 0.049 0.004 02 22 93 288 0.028 t 0.004 08 23-93 278 0.024 1 0.004 ',

03-01 93 302 0.023 1 0.003 08 30 93 291 0.030 0.003 03-08 93 255 0.030 t 0.004 09 06 93 265 0.018 t 0.003 03-15 93 300 0.019 1 0.003 09-13-93 272 0.016 1 0.003 03 22 93 288 0.023 t 0.004 09 20 93 282 0.018 t 0.003 03 29 93 266 0.008 t 0.003 09-27-93 264 0.022 0.004 4

1st Qtr. Meants.d. 0.023 0.006 3rd Qtr. Meants.d. 0.022 0.008 l 04 05 93 274 0.010 1 0.003 10-04-93 297 0.015 t 0.003 I 04 12 93 279 0.015 t 0.003 10 11 93 294 0.013 t 0.003 04 19 93 293 0.015 0.003 10 18 93 274 0.023 t 0.004 04 26 93 273 0.021 1 0.003 10 25-93 284 0.022 0.003 )

05-03 93 284 0.018 1 0.003 11-01 93 290 0.016 1 0.003 1 C  !

05 10 93 286 0.015 t 0.003 11-08 93 33 < 0.030 05-17 93 304 0.013 0.003 11-15-93 275 0.031 1 0.004 05 24 93 283 0.016 1 0.003 11-22 93 324 0.025 t 0.003 05 31-93 284 0.009 1 0.003 11 29 93 242 0.027 0.004.

06-07-93 101 b 0.012 0.006 12-06 93 282 0.032 t 0.004 06-14-93 274 0.01'/ t 0.003 12-13 93 283 0.028 0.004 06-21 93 276 0.014 1 0.003 12 20 93 283 0.024 1 0.004 06-28-93 290 0.018 i 0.003 .12-27 93 286 0,025 t 0,003 01 03 94 284 0.022 t 0.003 2nd Qtr. Meants.d. 0.015 t 0.003 4th Qtr. Meants.d. 0.023 t 0.006 Cumulative Average: 0.021 Previous Annual Average: 0.019 d

lodine 131 concentrations are <0.07 pCi/m2 unless otherwise noted in Appendix C.

b Low volume due to pump found off.

C Pump found not t'mning; replaced pump.

5

T_QLERQ Table 5. Airborne particulates and charcoal canisters .

Analyses: Gross beta and iodine 131 d.

Location: T7 Units: pCi/m3 Collection: Weekly Exchange Date Volume Date Volume Collected -(m 3) Gross Beta Collected (m3) Gross Beta Required LLD 02 g 01 04 93 279 0.020 0.003 07-05 93 282 0.016 t 0.003 01 11 93 290 0.030 1 0.004 07 12 93 288 0.023 1 0.003 01-18 93 284 0.029 t 0.004 07 19 93 282 0.018 t 0.003 01-25 93 298 0.016 i 0.003 07-26 93 282 0.020 i 0.003 02 01-93 271 0.023 i 0.003 08 02-93 283 0.023 t 0.004 02 08 93 291 0.018 1 0.003 08 09 93 278 0.017 t 0.003 02-15-93 267 0.021 1 0.004 08 16-93 282 0.042 1 0.004 02 22 93 284 0.024 t 0.004 08 23 93 284 0.026 0.004 03 01-93 282 0.026 t 0.004 08-30 93 279 0.032 1 0.004 03-08 93 281 0.034 t 0.004 09-06 93 279 0.021 t 0.003 03 15 93 295 0.016 t 0.003 09 13 93 279 0.023 0.003 03 22 93 269 0.016 1 0.003 09 20 93 280 0.018 0.003 03-29 93 283 0.010 t 0.003 09-27-93 278 0.023 0.003 1st Qtr. Meants.d. 0.022 1 0.007 3rd Qtr. Meants.d. 0.023 t 0.007 04 05-93 278 0.012 0.003 10-04-93 281 0.017 t 0.003 04-12-93 296 0.013 1 0.003 10 11-93 281 0.021 0.003 04 19 93 286 0.013 i 0.003 10 18-93 277 0.024 1 0.004 04-26-93 267 0.019 t 0.003 10 25 93 287 0.021 1 0.003 05-03 93 283 0.016 t 0.003 11-01 93 278 0.018 t 0.003 05 10 93 286 0.015 t 0.003 11-08 93 281 0.018 t 0.003 05-17 93 318 0.016 1 0.003 11-15-93 276 0.031 1 0.004 05 24-93 337 0.017 i 0.003 11-22 93 279 0.025 1 0.003 05 31-93 281 0.009 i 0.003 11 29-93 280 0.027 t 0.004 06 07 93 320 0.015 t 0.003 12-06 93 279 0.033 t 0.004 06-14-93 283 0.017 0.003 12 13 93 280 0.024 t 0.003 I 06-21-93 282 0.017 1 0.003 12 20 93 281 0.021 t 0.003 06-28 93 283 0.015 t 0.003 12 27 93 279 0.024 t 0.003 01 03 94 298 0.021 0.003 2nd Qtr. Meants.d. 0.015 1 0.003 4th Qtr. Meanis.d. 0.023 1 0.005 Cumulative Average: 0.021 Previous Annual Average: 0.020 l d

lodine 131 concentrations are <0.07 pCi/m unless otherwise noted in Appendix C.

3 6

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

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

l TOLEDO j Table 6. Airborne particulates and charcoal canisters . l l Analyses: Gross beta and iodine 131 d i Location: T8 Units: pCi/m 3 Collection: Weekly Exchange Date Volume .

Date Volume Collected (m 3) Cross Beta Collected (m3) Gross Beta Required LLQ 02 02 01 04 93 279 0.019 0.003 07 05-93 286 0.016 t 0.003 l 01 11 93 280 0.029 1 0.004 07-12-93 283 0.022 0.003 01 18 93 263 0.027 t 0.004 07-19-93 281 0.014 t 0.003 01 25 93 278 0.016 0.003 07 26 93 280 0.020 0.003

'02 01-93 298 0.022 t 0.003 08-02 93 289 0.019 t 0.003 02-08-93 294 0.020 0.003 08-09 93 288 0.020 0.003 02 15 93 300 0.021 0.003 08-16 93 292 0.044 0.004 02 22 93 283 0.025 0.004 08 23-93 286 0.024 0.004 03 01 93 286 0.023 t 0.004 08 30 93 285 0.036 t 0.004 03 08-93 275 0.031 t 0.004 09-06-93 283 0.018 0.003 03-15 93 284 0.016 0.003 09 13 93 291 0.022 1 0.003 03-22-93 269 0.021 0.004 09 20-93 295 0.019 0.003 f 03 29 93 282 0.009 t 0.002 09-27-93 285 0.023 1 0.003 l

1st Qtr. Mean s.d. 0.021 0.006 3rd Qtr. Meants.d. 0.023 2 0.008 04-05 93 286 0.011 0.003 10 04 93 294 0.016 1 0.003 04-12-93 283 0.013 0.003 10 11-93' 291 0.024 0.004 04-19-93 278 0.016 t 0.003 10 18-93 287 0.025 t 0.004

-0 3 7 0 .

-3 .

05-10 93 289 0.016 t 0.003 11-08 93 293 0.020 1 0.003 05 17 93 281 0.016 0.003 11 15 93 286 0.029 t 0.004 05-24 93 272 0.015 2 0.003 11-22 93 289 0.024 t 0.003 05 31-93 282 0.010 t 0.002 11 29 93 290 0.029 0.004 l 06-07 93 290 0.012 t 0.003 12 06 93 289 0.033 0.004 06 14 93 282 0.018 0.003 12 13 93 290 0.024 t 0.003 l

i 06-21-93 285 0.016 0.003 12 20 93 291 0.023 0.003

! 06 28 93 278 0.017 t 0.003 12-27-93 291 0.024 0.003

! 01 03 94 284 0.019 0.003 l

2nd Qtr. Mean s.d. 0.015 t 0.003 4th Qtr. Meants.d. 0.024 t 0.004 Cumulative Average: 0.021 Previous Annual Average: 0.019 8

fodine-131 concentrations are <0.07 pCi/m' unless otherwise noted in Appendix C.

7

l l

TOLEDO Table 7. Airborne particulates and charcoal canisters .

Analyses: Gross beta and iodine 131 a Location: T-9 Units: pCi/m 3 Collection: Weekly Exchange Date Volume Date Volume -

Collected (m 3) Gross Beta Collected (m3) Gross Beta Reauired LLD 0m.01 Om 01-04 93 290 0.024 0.003 07-05-93 284 0.019 0.003 01-11-93 293 0.032 0.004 07-12-93 287 0.022 0.003 01-18-93 282 0.033 1 0.004 07-19-93 285 0.020 2 0.003 01-25-93 287 0.020 t 0.003 07-26-93 284 0.021 0.003 02-01-93 287 0.022 1 0.003 08-02-93 286 0.021 t 0.003 02-08-93 274 0.023 t 0.004 08-09-93 288 0.018 i 0.003 02-15-93 271 0.023 0.004 08 16-93 285 0.043 1 0.004 02-22-93 281 0.028 0.004 08-23-93 278 0.028 t 0.004.

03-01-93 277 0.027 1 0.004 08-30-93 284 0.036 0.004 03-08-93 94 b 0.032 2 0.008 09-06-93 284 0.022 1 0.003 03-15-93 271 0.016 0.003 09-13 93 287 0.021 i 0.003 03-22-93 275 0.020 t 0.004 09-20-93 261 0.024 0.004 '

03-29-93 278 0.010 t 0.003 09-27 93 284 0.025 t 0.003 1st Qtr. Meants.d. 0.024 0.006 3rd Qtr. Meants.d. 0.025 ! 0.007 04-05-93 282 0.011 1 0.003 10-04-93 276 0.015 1 0.003  ;

04-12-93 282 0.015 1 0.003 10-11-93 289 0.024 i 0.004 04-19-93 287 0.018 0.003 10 18-93 276 0.029 0.004 04-26-93 274 0.021 1 0.003 10 25-93 280- 0.022 0,004 05-03-93 279 0.021 0.003 11-01-93 281 0.017 0.003 05-10-93 285 0.018 t 0.003 11-08 93 278 0.020 1 0.003 05-17-93 286 0.015 0.003 11-15-93 278 0.036 t 0.004 ,

05-24-93 285 0.018 t 0.003 11-22-93 277 0.028 1 0.003 1 05-31-93 282 0.011 t 0.003 11-29 93 278' O.030 1 0.004 1 06-07-93 285 0.011 1 0.003 12-06-93 276 0.032 1 0.004 l 06-14-93 286 0.015 0.003 12 13-93 282 0.026 1 0.003 '

06-21-93 285 0.019 t 0.003 12 20-93 278 0.022 0.003 06-28-93 286 0.018 i 0.003 12-27-93 282 0.026 i 0.003 1 01-03-94 276 0.020 0.003  !

2nd Qtr. Mean s.d. 0.016 1 0.003 4th Qtr. Meanis.d. 0.025 0.006 j Cumulative Average: 0.022 l Previous Annual Average: 0.020 8

Iodine-131 concentrations are <0.07 pCi/m2 unless otherwise noted in Appendix C.

b Low volume due to pump being off upon arnval.

8

TOLEDO Table 8. Airborne particulates and ci arcoal canisters. j i

Analyses: Gross beta and ic ine-131 d l Location: T-11 i Units: pCi/m 3 )

Collection: Weekly Exchange l Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross Beta Reauired LLD DE 02 01-04-93 279 0.023 t 0.003 07-05-93 283 0.020 0.003 01-11-93 290 0.025 0.003 07-12-93 292 0.025 t 0.003 01-18-93 293 0.031 0.004 07-19 93 290 0.015 0.003 01-25-93 290 0.016 0.003 07-26-93 288 0.020 0.003 02-01 93 283 0.020 t 0.003 , 08-02-93 281 0.024 0.004 02-08-93 283 0.020 0.003 08-09-93 281 0.016 1 0.003 02-15-93 264 0.024 0.004 08-16-93 272 0.046 t 0.004 02-22-93 283 0.028 0.004 08-23-93 271 0.028 0.004 03-01-93 290 0.025 0.004 08-30-93 280 0.038 t 0.004 03-08-93 267 0.034 0.004 09-06-93 281 0.022 t 0.003 03-15-93 274 0.021 0.003 09-13-93 283 0.021 0.003 03-22-93 279 0.022 1 0.004 09-20-93 261 0.024 1 0.004 03-29-93 276 0.009 1 0.003 09-27-93 282 0.030 t 0.004 1st Qtr. Mean s.d. 0.023 1 0.006 3rd Qtr. Meanis.d. 0.025 0.008 04-05 93 271 0.011 0.003 10-04-93 304 0.022 0.003 04-12-93 287 0.015 t 0.003 10-11-93 298 0.014 0.003 04-19 93 289 0.017 0.003 10-18-93 278 0.029 i 0.004 04-26-93 287 0.021 0.003 10-25-93 284 0.025 ? 0.004 05-03-93 279 0.020 0.003 11-01-93 280 0.021 0.003 l 0.018 i 0.003 05-10-93 285 11-08-93 281 0.020 t 0.003 05-17-93 286 0.015 1 0.003 11-15-93 282 0.036 0.004 l 05-24-93 285 0.018 1 0.003 11-22-93 281 0.028 i 0.003 05-31-93 282 0.011 1 0.003 11-29 93 282 0.032 0.004 06-07-93 288 0.012 1 0.003 12-06-93 281 0.030 t 0.004 06 14-93 288 0.016 0.003 12-13-93 282 0.031 t 0.004 06-21-93 289 0.016 1 0.003 12-20 93 281 0.026 2 0.004 06-28-93 286 0.017 1 0.003 12 27 93 282 0.027 0.004 01-03 94 286 0.018 0.003 2nd Qtr. Mean s.d. 0.016 0.003 4th Qtr. Meants.d. 0.026 0.006 Cumulative Average: 0.023 i Previous Annual Average: 0.019 a Iodine-131 concentrations are <0.07 pCi/m'unless otherwise noted in Appendix C.

I l

9 l I

l

TOLEDO ,

I Table 9. Airborne parnculates and charcoal canisters.

l Analyses: Gross beta and iodine-131 4 j l

Location: T-12 1 Units: pCi/m 3 Collection: Weeldy Exchange i Date Volume Date " .,iu m e I

Collected (m 3) Gross Beta Co'! cued (m3) Gross Beta l l Recuired LLD 0A1 0A1 1 l 01-04-93 276 0.020 t 0.003 07-05-93 269 0.016 0.003 l 01-11-93 287 0.026 i 0.004 07-12-93 272 0 021 2 0.003 01-18-93 278 0.028 i 0.004 07-19-93 280 0.015 t 0.003 i

01-25-93 278 0.017 i 0.003 07-26-93 293 0.019 0.003 02-01 93 287 0.023 1 0.003 08-02-93 280 0.015 t 0.003 l 02-08-93 282 0.022 1 0.003 08-09 93 282 0.015 0.003 02-15-93 283 0.023 t 0.004 08-16-93 280 0.041 0.004

02-22 93 283 0.028 1 0.004 08-23-93 268 0.021 0.004

! 03-01-93 290 0.022 0.003 08-30-93 284 0.031 0.004 03-08-93 276 0.032 0.004 09-06-93 279 0.019 0.003 03-15-93 288 0.019 0.003 09-13-93 276 0.019 0.003 03-22-93 277 0.020 t 0.004 09-20-93 275 0.020 0.003 03 29-93 333 0.012 1 0.002 09-27-93 292 0.021 0.003 1st Qtr. Mean s.d. 0.022 0.005 3rd Qtr. Mean s.d. 0.021 0.007 l 04-05-93 277 0.012 i 0.003 10-04-93 301 0.016 t 0.003

04-12-93 238 0.011 0.003 10-11-93 282 0.023 0.004

! 04-19 93 289 0.017 0.003 10-18-93 290 0.025 0.003 04-26-93 280 0.022 0.003 10-25-93 290 0.024 0.004 05-03-93 280 0.017 0.003 11-01-93 286 0.020 t &003 05-10-93 266 0.016 0.003 11-08-93 288 0.020 0.003 05-17-93 290 0.016 t 0.003 11-15-93 283 0.033 0.004 i

05-24-93 276 0.017 t 0.003 11-22-93 286 0.024 0.003 05-31-93 285 0.010 t 0.003 11-29-93 288 0.034 0.004 06-07-93 277 0.013 0.003 12-06-93 287 0.029 0.004 06 14-93 280 0.015 i 0.003 12-13-93 288 0.028 t 0.004 06-21 93 272 0.017 t 0.003 12-20-93 284 0.023 1 0.003 06-28-93 280 0.013 i 0.003 12-27-93 286 0.025 t 0.003

! 01-03-94 284 0.019 0 003

! 2nd Qtr. Meants.d. 0.015 t 0.003 4th Qtr. Meants.d. 0.025 t 0.005 Cumulative Average: 0.021 Previous Annual Average: 0.020 l d

lodine-131 concentrations are <0.07 pCi/m' unless otherwise noted in Appendix C.

10 l

1

TOLEDO Table 10. Airborne particulates and charcoal canisters. i' Analyses: Gross beta and iodine-1313

- Location: T 27 Units: pCi/m 3 Collection: Weekly Exchange

, Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross' Beta Reauired LLD QR gm 01-04-93 284 0.018 0.003 07-05-93 287 0.017 0.003 01-11-93 286 0.031 1 0.004 07-12-93 285 0.020 0.003 01-18-93 268 0.032 0.004 07-19-93 291 0.017 0.003 01-25-93 285 0.019 1 0.003 07-26-93 -293 0.019 ! 0.003 02-01-93 282 0.025 t 0.003 08-02-93 294 0.020 0.003 02-08-93 290 0.023 0.003 08-09-93 289 0.015 0.003 02-15-93 282 0.020 1 0.003 08-16-93 290 0.043 0.004.

02-22-93 287 0.032 1 0.004 08-23-93 285 0.027 0.004 03-01-93 293 0.018 0.003 08-30-93 286 0.031 0.004 03-08-93 283 0.029 t 0.004 09-06-93 286 0.021't 0.003 03-15 93 286 0.015 0.003 09 13 93 289 0.022 1 0.003 03-22 93 289 0.023 i 0.004 09-20-93 290 0.018 i 0.003 03 29-93 281 0.009 0.003 09 27-93 288 0.024 1 0.003 1st Qtr. Mean s.d. 0.023 1 0.007 3rd Qtr. Mean s.d. 0.023 1 0.007 04-05-93 284 0.012 0.003 10-04-93 287 0.015 0.003 04-12-93 284 0.013 t 0.003 10-11-93 288 0.022 0.003 >

04-19-93 490 0.016 0.003 10-18-93 284 0.025 t 0.004 04-26-93 274 0.023 0.003 10-25-93 295 0.023 0.0 05-03-93 295 0.021 0.003 11-01-93 285 0.020 0. 6 05 10-93 289 0.016 1 0.003 11 08 93 423 0.023 0.003 ,

05-17-93 290 0.014 t 0.003 11-15-93 283 0.028 0.004 05-24-93 284 0.015 t 0.003 11-22 93 287 0.023 0.003 05-31-93 285 0.010 t 0.003 11-29-93 287 0.030 t 0.004 06-07-93 304 0.013 0.003 12-06 93 282 0.030 t 0.004 ~

06-14 93 298 0.018 0.003 12 13 93 285 0.028 1 0.004 06-21-93 282 0.014 0.003 12-20-93 288 0.022 1 0.003 06-28-93 289 0.019 1 0.003 12-27-93 287 0.022 i 0.003 01-03-94 289 0.025 0.004 2nd Qtr. Meants.d. 0.016 0.004 4th Qtr. Meants.d. 0.024 t 0.004 Cumulative Average: 0.021 Previous Annual Average: 0.018 8

Iodine-131 concentrations are <0.07 pCi/m' unless otherwise noted in Appendix C.

11 i

i t

, _. ,,_.m_..--_,,m _ _ , _ _ _ _ _ _ , ~ . . _ , , , . , , , , , . . . ,. ,_ . _ ___ _____. _ _ , _ .

l

! l I

Table 11. Airborne particulate data, gross beta analysis, monthly averages, minima, and

maxima,1993.

l Cross Beta (pCi/m3)

Month location Number of Samples a Average Mirumum Max 2 mum January T-1 5 0.026 0.022 0.038 T-2 5 0.024 0.017 0.032 T-3 5 0.024 0.019 0.033 T-4 5 0.024 0.016 0.031 T-7 5 0.024 0.016 0.030 T-8 1 0 023 QS11 0 029 All Indicators 30 0.024 0.016 0.038 T-9 5 0.026 0.020 0.033 i T-11 5 0.023 0.016 0.031 l' T-12 5 0.023 0.017 0.028 T-27 i Q_Q21 0312 0 032 All Controls 20 0.024 0.016 0.033 February T-1 4 0.024 0.020 0.027 T-2 4 0.025 0.020 0.030 T-3 4 0.025 0.021 0.029 T-4 4 0.024 0.021 0.028 T-7 4 0.022 0.018 0.026 T-8 1 0,022 0 020 0.025 All Indicators 24 0.024 0.018 0.030 T-9 4 0.025 0.023 0.028 T-11 4 0.024 0.020 0.028 T-12 4 0.024 0.022 0.028 T-27 1 Q323 Q311 0 032 All Controls 16 0.024 0.018 0.032 a Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are exduded from  !

the average. i l

12 l

Table 11. Airborne particulate data, gross beta analysis, monthly averages, mimma, and manma,1993 (continued).

Cross Beta (pCi/m3)

Month Location Number of Samplesa Average Muumum Maximum Man:h T-1 4 0.014 0.007 0.019 T-2 4 0.020 0.010 0.036 T-3 4 0.022 0.010 0.033 T-4 4 0.020 0.008 0.030 T-7 4 0.019 0.010 0.034 T-8 4 Qal.9 Q_QQ2 Q.Q21 AllIndicators 24 0.019 0.008 0.036 T-9 4 0.020 0.010 0.032 T-11 4 0.022 0.009 0.034 T-12 4- 0.021 0.012 0.032 T-27 i Q312 Q_QQ2 Q Q22 All Controls 16 0.020 0.009 0.034 ~

April T-1 4 0.015 0.010 0.018 i T-2 4 0.016 0.013 0.021 T-3 4 0.017 0.012 0.021 T-4 4 0.016 0.010 0.021 T-7 4 0.015 0.012 0.019 T-8 i Qall Q_Q11 Q122 All Indicators 24 0.016 0.010 0.023 T-9 4 0.017 0.011 0.021 T-11 4 0.017 0.011 0.021 T-12 4 0.016 0.011 0.022 T-27 i Q_Q1Z Qll2 Q_Q22 All Controls 16 0.017 0.010 0.023 a Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average.

13

Table 11. Airborne particulate data, gross beta analysis, monthly averages, minima, and maxima,1993 (continued).

l 1

Cross Beta (pCi/m3)

Month location Number of Samples a Average Mmmum Mammum i May T-1 4 0.014 0.011 0.016

! T-2 4 0.014 0.011 0.015 l T-3 4 0.016 0.009 0.020

! T-4 4 0.013 0.009 0.016

! T-7 4 0.014 0.009 0.017 T-8 i Q.01A Q.&Q2 0 016 l All Indicators 24 0.014 0.009 0.020 T-9 4 0.016 0.011 0.018 T-11 4 0.016 0.011 0.018 T-12 4 0.015 0.010 0.017 T-27 i Q_Qli Qa1Q 0,016 l All Controls 16 0.015 0.010 0.018 June T-1 4 0.014 0.013 0.016 T-2 4 0.016 0.013 0.017

( T-3 4 0.015 0.012 0.017.

T-4 4 0.016 0.012 0.018 T-7 4 0.016 0.015 0.017 T-8 1 9_Q11 9 912 0 018 l

All Indicators 24 0.016 0.012 0.018 T-9 4 0.016 0.011 0.019 T-11 4 0.015 0.012 0.017 T-12 4 0.014 0.013 0.017 T-27 i 0 016 Qall Qa12 All Controls 16 0.015 0.011 0.019 a Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average.

14 i

i i

Table 11. Airborne particulate data, gross beta analysis, monthly averages, mimma, and maxima,1993 (continued).

Gross Beta (pCi/m3)

Month Location Number of Samples a Average Muumum Maxunum July T-1 5 0.019 0.015 0.020 T-2 5 0.021 0.015 0.027 T-3 5 0.018 0.016 0.019 T-4 5 0.019 0.018 0.022 T-7 5 0.020 0.016 0.023 T-8 i Q_Q11 Q311 Q.Q12 All Indicators 30 0.019 0.014 0.027 T-9 5 0.021 0.019 0.022 T-11 5 0.021 0.015 0.025 T-12 5 0.017 0.015 0.021 T-27 1 Q.Q12 Q.a.12 Q_Q2Q All Controls 20 0.020 0.015 0.025 '

August T-1 4 0.029 0.017 0.044 T-2 4 0.030 0.016 0.044 T-3 4 0.029 0.017 0.045 T-4 4 0.030 0.017 0.049 T-7 4 0.029 0.017 0.042 T-8 A Q93.1 9.Q22 Q_Q&&

AllIndicators 24 0.030 0.016 0.049 T-9 4 0.031 0.018 0.043 T-11 4 0.032 0.016 0.046 T-12 4 0.027 0.015 0.041 T-27 A Q.022 Qall QR11 All Controls 16 0.030 0.015 0.046 a Unless otherwise specified, data for samples collected on the first, second, or tnird day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average.

15

Table 11. Airborne paniculate data, gross beta analysis, monthly averages, mmima, and maxima,1993 (continued).

f i

l Gross Beta (pCi/m3)

Month Location Number of Samplesa Average Minunum Mammum September T-1 4 0.019 0.016 0.020  ;

T-2 4 0.021 0.020 0.023 '

T-3 4 0.020 0.016 0.024 T-4 4 0.018 0.016 0.022 T-7 4 0.021 0.018 0.023 T-8 1 0 020 Q111 Q12.2 All Indicators 24 0.020 0.016- 0.024 .

T-9 4 0.023 0.021 0.025 T-11 4 0.024 0.021 0.030 T-12 4 0.020 0.019 0.021 T-27 1 0 021 0 018 Q Q21 i

All Contmls 16 0.022 0.016 0.030 October T-1 5 0.020 0.015 0.024 T-2 5 0.021 0.019 0.024 T-3 5 0.022 0.017 0.027 T-4 5 0.018 0.013 0.023 l T-7 5 0.020 0.017 0.024 <

T-8 1 0A22 0 016 Q Q21 i AllIndicators 30 0.020 0.013 0.027 T-9 5 0.021 0.015 0.029 T-11 5 0.022 0.014 0.029 l T-12 5 0.022 0.016 0.025 l T-27 5 0.021 0315 Q.Q25 All Controls 20 0.021 0.014 0.029 a Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate i the number of samples with unreliable and less than value results which are excluded from  !

the average.

l 16

._m __m 4 , -- , _ , e ,_

I I

Table 11. Airborne particulate data, gross beta analysis, monthly averages, minima, and maxima,1993 (continued).

t l

Cross Beta (pC1/m3)

Month Location Number of Samples a Average Muumum Manmum November T-1 4 0.026 0.016 0.031 l

T-2 4 0.028 0.021 0.033 T-3 4 0.023 0.015 0.029 T-4 4(1) 0.028 0.025 0.031 T-7 4 0.025 0.018 0.031 l

T-8 4, 0.026 0.020 0__.Q29 All Indicators 24 0.026 0.015 0.033 T-9 4 0.028 0.020 0.036 T-11 4 0.029 0.020 0.036 T-12 4 0.028 0.020 0.034 T-27 4 Q_Q24 Q_.Q2J 0030 All Controls 16 0.028 0.020 0.036 1

December T-1 5 0.022 0.015 0.033 l T-2 5 0.022 0.016 0.033 T-3 5 0.025 0.020 0.034 l

! T-4 5 0.026 0.022 0.032 T-7 5 0.025 0.021 0.033 T-8 1 0 025 0.019 0.033 All Indicators 30 0.024 0.015 0.033 i

T-9 5 0.025 0.020 0.032  ;

T-11 5 0.026 0.018 0.031 l T-12 5 0.025 0.019 0.029 T-27 1 Q025 Q Q22 0.030 All Controls 20 0.025 0.018 0_.032 a Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average.

1 17 1 l

l l

l

Table 11. Airborne particulate data, gross beta analysis, monthly averages, muuma, and maxima,1993 (continued).

l Cross Beta (pC /m3)

Month location Number of Samples a Average Mirumum Maximum {

l September T-1 4 0.019 0.016 0.020  :

T-2 4 0.021 0.020 0.023 '

T-3 4 0.020 0.016 0.024 T-4 4 0.018 0.016 0.022 T-7 4 0.021 0.018 0.023 T-8 1 0.020 Q._QJ1 0.023 AllIndicators 24 0.020 0.016 0.024 T-9 4 0.023 0.021 0.025 T-11 4 0.024 0.021 0.030 T-12 4 0.020 0.019 0.021 T-27 1 0 021 0 018 2 Q_Q.2.3 1

All Controls 16 0.022 0.016 0.030 October T-1 5 0.020 0.015 0.024 T-2 5 0.021 0.019 0.024 T-3 5 0.022 0.017 0.027 T-4 5 0.018 0.013 0.023 T-7 5 0.020 0.017 0.024 T-8 1 0 022 0 016 0.024 AllIndicators 30 0.020 0.013 0.027 T-9 5 0.021 0.015 0.029 T-11 5 0.022 0.014 0.029 T-12 5 0.022 0.016 0.025 T-27 5 0 021 0 015 Q_Q25 All Controls 20 0.021 0.014 0.029 a Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from i the average.

l 16 l

i l

I

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

Table 11. Airborne particulate data, gross beta analysis, monthly averages, minima, and maxima,1993 (continued).

Cross Beta (pCi/m3)

Month Location Number of Samples a Average Muumum Ahmum November T-1 4 0.026 0.016 0.031 T-2 4 0.028 0.021 0.033 T-3 4 0.023 0.015 0.029

-T-4 4(1) 0.028 0.025 0.031 T-7 4 0.025 0.018 0.031 T-8 i M M .0.029 All Indicators 24 0.026 0.015 0.033 T-9 4 0.028 0.020 0.036 T-11 4 0.029 0.020 0.036 T-12 4 0.028 0.020 0.034 T-27 1 0 026 M M All Controls 16 0.028 0.020 0.036 December T1 5 0.022 0.015 0.033 T-2 5 0.022 0.016 0.033 T-3 5 0.025 0.020 0.034 T-4 5 0.026 0.022 0.032 T-7 5 0.025 0.021 0.033 T-8 1 0 025 0.019 0 033 All Indicators 30 0.024 0.015 0.033 T-9 5 0.025 0.020 0.032 T-11 5 0.026 0.018 0.031 T-12 5 0.025 0.019 0.029 T-27 1 M M M All Controls 20 0.025 0.018 0.032 a Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average.

d 17 l

i e n

Table 12. Airborne particulates, quarterly composite of all indicator and all control locations, analyses for strontium and gamma-emitting isotopes,1993.

Sample Description and Activity (pCi/m3)

January March bb Code TAP 3460 TAP 3461 TAP-3462 TAP-3463 TAP-3464 Location T-1 T-2 T-3 T-4 T-7 Volume (m3) 2572 3701 3579 3793 3674

, Sr-89 <0.0009 <0.0016 <0.0006 <0.0006 <0.0007 l Sr-90 <0.0002 <0.0006 <0.0004 <0.0003 <0.0004 i

! Be-7 0.08010.026 0.06610.020 0.05410.017 0.069t0.022 0.06810.022 K-40 <0.063 <0.038 <0.047 <0.044 <0.045 Nb-95 <0.0047 <0.0032 <0.0036 <0.0043 <0.0039 Zr 95 <0.0077 <0.0054 <0.0051 <0.0056 <0.0055 Ru-103 <0.0040 <0.0031 <0.0027 <0.0032 <0.0029 Ru-106 <0.030 <0.022 <0.022 <0.022 <0.021 Cs 134 <0.0032 <0.0019 <0.0022 <0.0023 <0.0022 Cs-137 <0.0034 <0.0022 <0.0020 <0.0023 <0.0024 Ce-141 <0.0053 <0.0034 <0.0037 <0.0047 <0.0040 1 Ce-144 <0.019 <0.013 <0.013 <0.014 <0.013 I l

l l

l bb Code TAP-3465 TAP-3466 TAP-3467 TAP-3468 TAP 3469 l Location T-8 T-9 (C) T 11 (C) T-12 (C) T-27 (C) i Volume (m3) 3671 3473 3651 3718 3696 l Sr-89 <0.0007 <0.0007 <0.0006 <0.0009 <0.0006 l Sr-90 <0.0003 <0.0004 <0.0004 <0.0005 <0.0003 l

Be 7 0.048t0.010 0.05610.012 0.07010.020 0.05610.011 0.05810.021 K-40 <0.022 <0.023 <0.057 <0.022 <0.045 Nb 95 <0.0016 <0.0016 <0.0039 <0.0016 <0.0033 Zr-95 <0.0022 <0.0026 <0.0061 <0.0020 <0.0058 Ru-103 <0.0013 <0.0013 <0.0031 <0.0011 <0.0028 Ru-106 <0.0091 <0.0099 <0.027 <0.0075 <0.022 Cs-134 <0.0010 <0.0009 <0.0025 <0.0009 <0.0022 Cs-137 <0.0010 <0.0010 <0.0022 <0.0009 <0.0022 Ce-141 <0.0013 <0.0014 <0.0040 <0.0014 <0.0038 Ce-144 <0.0040 <0.0039 <0.014 <0.0040 <0.018 l

l 18 l

Table 12. Airbome particulates, quarterly composite of all indicator and all control locations, analyses for strontium and gamma-emitting isotopes,1993 (continued).

Sample Description and Activity (pCi/m3)

April- June Lab Code TAP-3575 TAP-3576 TAP-3577 TAP-3578 TAP-3579 Location T1 T-2 T-3 T4 T-7 Volume (m3) 3070 3701 3612 3501 3800 Sr-89 <0.0008 <0.0007 <0.0008 <0.0008 <0.0006 Sr-90 <0.0004 <0.0003 0.000710.0002<0.0004 <0.0003 Be-7 0.07710.018 0.073i0.017 0.07610.019 0.08710.020 0.075 0.017 K-40 <0.039 <0.032 <0.038 <0.034 <0.032 Nb-95 <0.0006 <0.0010 <0.0012 <0.0006 <0.0006 Zr 95 <0.0012 <0.0010 <0.0014 <0.0010 <0.0007 Ru-103 <0.0005 <0.0007 <0.0007 <0.0014 <0.0010 Ru-106 <0.0035 <0.0058 <0.0034 <0.0065 <0.0035 Cs-134 <0.0007 <0.0008 <0.0004 <0.0011 <0.0003 Cs 137 <0.0004 <0.0006 <0.0009 <0.0008 <0.0004 Ce 141 <0.0022 <0.0017 <0.0013 <0.0011 <0.0016 Ce-144 <0.0036 <0.0029 <0.0065 <0.0063 <0.0044 Lab Code TAP-3580 TAP-3581 TAP 3582 TAP-3583 TAP 3584 Location T-8 T-9 (C) T-11 (C) T-12 (C) T-27 (C)

Volume (m3) 3677 3684 3702 3590 3948 Sr-89 <0.0007 <0.0008 <0.0007 <0.0008 <0.0008 Sr-90 <0.0003 <0.0003 <0.0003 <0.0004 <0.0004 Be-7 0.05810.015 0.079i0.015 0.08110.016 0.07410.17 0.06110.014 i K-40 <0.032 <0.033 <0.032 <0.038 <0.030 l Nb-95 <0.0006 <0.0013 <0.0006 <0.0008 <0.0006  !

Zr-95 <0.0008 <0.0019 <0.0010 <0.0008 <0.0009 l Ru 103 <0.0013 <0.0010 <0.0012 <0.0008 <0.0006 Ru-106 <0.0066 <0.0064 <0.0029 <0.0080 <0.0037 Cs-134 <0.0004 <0.0008 <0.0004 <0.0008 <0.0005 Cs 137 <0.0004 <0.0004 <0.0004 <0.0005 <0.0006 Ce-141 <0.0010 <0.0017 <0.0013 <0.0024 <0.0020 Ce-144 <0.0056 <0.0030 <0.0062 <0.0064 <0.0042 19

?

]

I Table 12. Altborne particulates, quarterly composite of all indicator and all control locations, analyses for strontium and gamma-emitting isotopes,1993 (continued).

Sample Description and Activity (pCi/m3)

July September ,

1 1

L.ab Code TAP-3691 TAP-3692 TAP-3693 TAP-3694 TAP 3695 Location T-1 T-2 T3 T-4 T-7 Volume (m3) 3678 3614 3821 3600 3656 Sr-89 <0.0007 <0.0006 <0.0006 <0.0006 <0.0006 Sr-90 <0.0004 <0.0003 <0.0004 <0.0004 <0.0003 Be-7 0.069i0.020 0.07410.034 0.073i0.032 0.08310.026 0.08910.021 K-40 <0.0099 <0.012 <0.010 <0.022 <0.041 Nb-95 <0.0012 <0.0010 <0.0009 <0.0008 <0.0008 Zr 95 <0.0012 <0.0022 <0.0020 <0.0019 <0.0014 Ru 103 <0.0017 <0.0020 <0.0010 <0.0009 <0.0009 Ru 106 <0.0081 <0.0068 <0.0059 <0.011 <0.0060 Cs-134 <0.0012 <0.0008 <0.0007 <0.0006 <0.0006 Cs-137 <0.0011 <0.0008 . <0.0006 <0.0005 <0.0005 Ce-141 <0.0026 <0.0026 <0.0014 <0.0029 <0.0018 Ce-144 <0.0077 <0.0059 <0.0053 <0.0067 <0.0033 ,

Lib Code TAP-3696 TAP-3697 TAP-3698 TAP-3699 TAP 3700

< Location T-8 T-9 (C) T 11 (C) T-12 (C) T-27 (C)

Volume sm3) 3724 3677 3645 3630 3753 Sr-89 <0.0006 <0.0007 <0.0005 <0.0005 <0.0007 Sr-90 <0.0003 <0.0004 <0.0003 <0.0004 <0.0004 l Be-7 0.08910.024 0.07710.022 0.090t0.025 0.07610.020 0.08210.019 K 40 <0.038 <0.040 <0.042 <0.040 <0.038 Nb-95 <0.0007 <0.0014 <0.0016 <0.0008 <0.0007 Zr 95 <0.0013 <0.0011 <0.0016 <0.0011 <0.0018 Ru 103 <0.0011 <0.0018 <0.0006 <0.0005 <0.0010 Ru 106 <0.0042 <0.0050 <0.010 <0.0047 <0.0072 Cs-134 <0.0008 <0.0012 <0.0004 <0.0004 <0.0007 l Cs 137 <0.0008 <0.0005 <0.0007 <0.0007 <0.0009 l Ce-141 <0.0017 <0.0023 <0.0025 <0.0011 <0.0012 Ce-144 <0.0054 <0.0049 <0.0042 <0.0056 <0.0084 l

l 20 l

l

1 l

Table 12. Airbome particulates, quarterly composite of all Indicator and all control locations, analyses for strontium and gamma-emitting isotopes,1993 (continued).

l l

Sample' Description and Activity (pC1/m3)

October December . ,

1 Lab Code TAP 3811 TAP-3812 TAP 3813 TAP 3814 -TAP-3815 Location T1 T-2 T-3 T-4 T7 Volume (m3) 3952 3951 3933 3731 3937 Sr-89 <0.0003 <0.0004 <0.0003 <0.0004 <0.0003 Sr 90 <0.0003 <0.0003 <0.0003 <0.0004 <0.0003 Be-7 0.063i0.014 0.04810.012 0.06810.015 0.05610.014 0.06210.014 K-40 <0.037 <0.037 <0.037 <0.039 <0.037 Nb-95 <0.0008 <0.0007 <0.0004 <0.0004 <0.0009 -

Zr 95 <0.0013 <0.0011 <0.0016 <0.0006 <0.0011 Ru-103 <0.0004 <0.0011 <0.0007 <0.0008 <0.0007 Ru-106 <0.0060 <0.0071 <0.0027 <0.0050 <0.0029 Cs-134 <0.0004 <0.0003 <0.0003 <0.0006 <0.0004 Cs-137 <0.0007 - <0.0004 <0.0008 <0.0006 <0.0003 Ce-141 <0.0008 <0.0013 <0.0014 <0.0010 <0.0014 Ce-144 <0.0049 <0.0047 <0.0049 <0.0061 <0.0048 Lab Code TAP-3816 TAP 3817 TAP 3818 TAP-3819 TAP-3820 Location T-8 T-9 (C) T 11 (C) T-12 (C) T 27 (C)

Volume (m3) 4053 3907 3982 4023- 4150 Sr 89 <0.0003 <0.0004 <0.0003 <0.0003 <0.0004 Sr-90 <0.0003 <0 0003

. <0.0003 <0.0003 40.0003 Be-7 0.05810.014 0.06610.017 0.05710.013 0.07410.014 0.06510.013 i K-40 <0.036 <0.037 <0.036 <0.036 <0.036 Nb-95 <0.0007 <0.0005 <0.0004 <0.0006 <0.0010 Zr-95 <0.0008 <0.0012 <0.0006 <0.0010 <0.0006 Ru 103 <0.0003 <0.0006 <0.0005 <0.0006 <0.0004 Ru 106 <0.0037 <0.0042 <0.0070 <0.0068 <0.0068 Cs-134 <0.0008 <0.0003 <0.0007 <0.0006 <0.0002 Cs-137 <0.0007 <0.0009 <0.0003 <0.0007 <0.0009 Ce-141 <0.0013 <0.0011 <0.0007 <0.0008 <0.0012 Ce-144 <0.0050 <0.0025 <0.0038 <0.0052 <0.0034 ,

l I

21 4

i

- - w + ~, w- - - - - - . p m e-, . ~ , - , . ,.em,- w-w-,e-.-,...w.-y ,-,--.r.e y,r ,

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

i i

Table 13 Area monitors (TLDL quanerly,1993.

mR/91 Days Location 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Indicator T-1 11.110.3 10.610.2 12.810.2 9.910.3 T 2- 11.210.3 10.410.3 13.810.2 10.210.3.

T3 11.410.3 10.910.3 13.610.4 10.310.3 T-4 14.110.2 12.510.4 16.010.3 11.910.4 T-5 13.410.6 12.410.4 15.510.2 11.010.3 T-6 10.9i0.2 9.210.4 13.010.3 10.3i0.4 T-7' 15.010.4 15.110.4 16.710.3 13.910.3 T-8 19.010.3 17.9i0.2 22.610.2 17.410.3 T-10 13.510.3 14.9i0.2 15.410.2 13.810.4 T-38 11.210.2 12.410.2 12.9i0.4 -11.510.5 T 39 12.6i0.4 13.410.2 15.710.2 12.910.3 T-40 13.0i0.4 13.310.2 15.910.2 11.610.4 T-41 11.410.3 12.010.5 12.310.3 11.410.3 .

T-42 10.6i0.2 10.910.4 12.310.3 9.810.5-T-43 14.010.3 15.410.4 18.010.2 15.510.4 T-44 14.810.2 15.210.4 18.8to.2 14.610.3 T-45 17.510.3 17.710.3 - 23.010.3 16.010.3 T-46 12.6i0.4 12.310.3 15.3 0.2 11.310.4 T 47 9.0i0.4 9.610.3 10.110.2 9.010.4 T-48 15.510.2 15.910.6 17.710.4 15.6 0.7 T-49 11.610.3 10.610.2 14.010.2- 9.510.4 T 50 17.810.3 21.8t0.3 21.110.2 20.310.5 T-51 16.210.3 NDa 20.010.2 13.8 0.4 T-52 17.710.5 20.210.5 24.6i0.3 18,910.3 T-53 16.210.4 20.410.3 21.410.3 20.310.4 T-54 17.210.3 18.210.2 20.410.2 18.310.3 ,

17.8f0.3 13.3i0.3 T-55 14.910.2 12.510.3 Mean i s.d. 13.812.7 14.li3.5 16.713.8 13.413.3 Control ,

i T9 11.510.3 10.610.3 13.710.2 10.510.3  ;

T-11 13.6i0.3 13.810.2 15.210.2 12.910.3 T 12 17.610.4 19.210.4 21.310.3 17.510.3 T 23 12.710.5 13.710.4 15.310.2 10.810.4 T-24 15.710.3 16.010.2 21.010.2 15.210.4 T 27 15.510.2 15 Sf0.5 18.810.2 15.9t0.4 Mean i s.d. 14.412.2 14.812.9 17.6t3.3 13.812.6 l l

aND = No data: TLD missing.

l l

22 1

_ _ _ . . _ , _ . ,__ _ . , _ _ _ . , . . ,_ m.. ..,_.m , __-. . . . , , . . . _ . . _ . , . , ,

Table 13. Area monitors G1.D), quarterly,1993.

I mR/91 Days Location 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter ]

i Indicator l

I T-60 11.410.4 11.210.4 11.410.3 9.910.6 T-61 11.510.3 10.210.4 11.5 0.3 9.310.3 T-62 11.510.4 11.310.3 11.110.2 9.910.4 ,

T-63 12.610.5 13.210.3 13.2 0.4 12.410.3 T-64 8.210.4 9.210.2 8.210.2 8.510.3 T-65 14.810.3 15.410.3 16.010.3 14.610.4 l T-66 19.610.4 21.010.4 22.6i0.2 18.210.9 T-67 19.110.3 19.3 0.5 21.010.3 18.110.3 T-68 15.8t0.8 17.810.3 16.9t0.4 13.710.4 T-69 18.210.7 16.910.3 20.210.3 17.010.4 T-70 11.910.6 10.010.3 11.610.3 10.310.4 T-71 15.810.3 16.610.3 16.610.4 16.9t0.4 j T-73 13.510.3 12.110.2 14.510.3 12.310.3 j T-74 12.210.5 NDa 12.210.5 9.110.3 l T-75 15.210.4 14.110.5 16.410.5 14.210.7

! T-76 11.410.3 9.610.4 11.410.2 9.610.3 T-77 10.810.2 9.410.2 11.210.6 9.510.5

( T-90 16.010.6 19.6i0.4 19.610.3 16.910.4 T-91 15.It0.5 15.210.7 16.610.2 15.8t0.7 T-92 11.7i0.4 11.410.4 12.710.2 6.610.3

T-93 11.0i0.3 10.110.3 12.210.2 8.610.4 l T-94 14.9t0.4 11.610.5 18.010.2 10.510.4 T-97 16.710.3 17.410.3 21.910.3 16,710.2 T-99 17.2 0.4 19.110.3 22.Si0.3 18.410.4 T-112 12.910.4 14.310.4 15.410.2 15.010.3 T-121 15.110.3 19.010.4 19.8t0.2 19.510.7 T-122 14.010.3 14.510.5 16.510.3 14.610.3 T-123 14.310.2 15.210.4 16.2 0.4 15.010.6 T-125 15.410.3 15.510.4 17.4t0.2 15.110.5 T-126 NDa NDa 17.410.2 13.910.4 T-127 18.010.3 19.310.5 22.210.2 17.6i0.3 T-128 16.610.5 17.510.2 20.8i0.2 16.6t0.3 T-150 14.510.3 11.610.3 NDa 10.610.2 T-151 17.010.5 17.110.4 19.710.2 10.810.2 T-153 16.710.4 19.810.5 21.6i0.2 16.810.3 T-154 16.110.4 15.210.7 17.710.2 14.910.4 T-201 13.810.4 13.210.3 15.210.2 12.510.2 T 202 13.410.2 12.810.4 14.8t0.2 12.410.2 T-203 13.8i0.3 12.810.4 15.510.3 11.610.4 l T-204 15.010.3 NDa 15.910.3 13.410.3

! T-205 15.510.3 16.610.4 17.210.3 16.410.3 T-206 11.510.3 10.5t0.4 13.210.3 10.110.4 T-207 10.710.2 10.010.3 11.910.4 9.710.4 T-208 11 310.3 S.910 3 11.5i0.3 8.9 t0. 4 Mean i s.d. 14.212.6 14.2 3.5 16.013.8 13.213.3 a ND = No data; TLD missing.

23

Table 13. Area monitors (TLD), quarterly,1993 (continued) mR/91 Days Location 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Control j I

T-95 17.li0.5 16.410.2 20.010.4 15.410.3 T-96 9.110.2 9.710.4 11.610.3 10.110.6 T-98 16.410.3 18.910.5 20.210.3 19.410.4 T 100 16.510.3 9.810.3 20.310.3 9.910.6 T-101 15.910.3 16.010.2 19.810.3 17.310.4 T-102 13.lio.4 12.910.4 15.9 0.4 13.410.4 i T-103 15.8i0.3- 16.8i0.4 17.810.3 16.810.6 i T-104 13.210.3 15.210.2 16.410.3 17.610.3 T-105 17.910.3 18.210.3 19.710.3 17.810.3 T 106 13.910.3 15.610.4 15.510.4 15.010.3 T-107 12.510.5 17.710.3 16.410.3 18.210.6 T-108 12.7i0.3 17.710.2 19.810.4 18.710.5 T-109 15.410.4 18.3 0.5 18.510.3 19.810.4 T 110 14.810.3 15.210.4 18.910.3 15.310.4 T-111 -13.1 0.3 16.4t0.3 17.710.2 16.8i0.3 T-124 12.7i0.6 11.6t0.3 13.310.2 11.210.5 i T-155 15.3t0.3 13.7t0.3 16.410.4 14.9i0.5 Mean i s.d. 14.412.2 15.112.8 17.512.5 15.713.0 l

QC T-80 10.710.2 10.610.5 11.410.3 10.210.5 T-81 19.5 0.3 21.310.3 23.810.3 21.810.4 T 82 11.810.5 12.310.2 13.0io.2 12.810.3  ;

T-83 13.010.4 12.610.2 14.0 0.2 11.410.2 T-84 13.410.4 12.610.2 14.8i0.3 12.610.4 T 85 14.610.5 15.110.3 16.510.3 14.810.5 T 86 17.210.4 18.710.6 20.0t0.3 18.610.7 T 88 18.810.4 18.310.4 20.910.3 17.010.3 T-89 16.510.6 15.810.4 19.9 0.4 15.310.4 T-113 15.510.5 NDa 16.110.4 9.310.4 T-114 13.010.3 14.810.3 13.410.2 14.610.5 T-115 15.810.5 15.410.4 16.710.2 15.110.3 T-116 16.6t0.5 15.410.3 18.510.4 17.2 0.4 T-117 13.210.4 13.910.4 15.2i0.2 16.410.8 T-118 10.510.3 13.510.3 12.610.3 14.110.4 T-119 13.9i0.3 14.910.4 NDa 14.810.5 T 120 13.110.4 15.,910.5 15.710.3 15.410.4 T-200 15.410.4 16.910.3 17.910.9 16.610.2 Mean i s.d. 14.612.5 15.112.6 16.513.3 14.912.9 a ND = No data; TLD missing.

24

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

d Table 13. Area monitors (TLD), quarterly,1993 (continued) l

' mR/91 Days )

Location 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter l 1

Shield T-87 6.610.4 4.810.2 5.910.2 4.410.5 l

i i

i 1

25

~_ . ,

I l

i Table 13. Area monitors (TLD), Annual,1993.

1 Location mR/365 days Annual Indicator l

T-1 42.810.6 i T-2 46.310.6 T-3 44.710.9 T-4 -54.110.6 T-5 51.310.7 T6 39.010.6 '

T-7 54.010.7 T-8 80.710.7 T-10 57.810.7' T-38 42.210.7 l T-39 46.310.6

! T 40 54.210.7

! T-41 45.310.6 l T-42 41.010.6 T-43 66.210.8 T-44 65.710.7 -

T-45 74.810.7 T-46 54.110.7 T-47 34.810.6 l

T-48 62.810.7 '

T-49 43.511.0  ;

T-50 72.710.8 T-51 NDa T 52 73.710.7 T-53 64.610.7 T 54 67.110.8 T-55 54.0 0.6 Mean i s.d. 55.1112.3 Control T-9 46.410.6 T-11 57.110.7 T-12 73.710.6 i T-23 56.010.6 i T-24 69.111.1 '

T-27 69.710.8 Mean i s.d. 62.0i9.6 aND = No data; TLD lost in the field.

l 26 l

l

. ~ . .- - - .-- .-. . - . . . .

Table 13. Area monitors (TLD), Annual,1993 (continued).

Location mR/365 days Annual Indicator T-60 46.210.7 T'61 42.310.8 T 62 44.310.6 T-63 NDa T-64 35.810.8 T 65 62.710.9 T-66 '79.310.8 T-67 73.010.7.

T-68 62.810.8 T-69 72.211.2 T-70 39.710.7 T-71 63.310.7 T 53.711.2 T-74 46.110.8 T-75 61.010.6 T-76 44.711.4' T-77 43.510.7

.T-90 73.111.1 ,

l T-91 66.210.7 T-92 48.810.6 T-93 46.210.7 T 94 67.010.7 T 97 72.210.8 T 99 75.311.3 l T-112 54.810.8 T-121 71.611.1 T-122 61.610.7 T-123 62.010.7 T-125 '

63.610.7 T-126 NDa l T-127 68.210.8 T-128 68.010.7 T-150 57 010.9 T-151 64.810.9 T 153 72.510.9 T-154 60.910.7 T-201 48.610.8 T-202 49.110.8 T-203 47.710.7 T-204 NDa T-205 50.910.7 T-206 35.310.8 T-207 33.210.8 T-208 37.210.7 Mean i s.d. 56.7112.6 aND = No Data: TLD lost in the fieki.

27 i

!,,.., _ , . - . - - _ - , . -. , .- , ~, , . - . . - . - . . - .

Table 13. Area monitors (TLD), Annual,1993 (continued). -

l Location mR/365 days Annual Control T-95 71.810.7 T-96 46.2 0.7 ,

T-98 75.4t0.8  !

T-100 67.310.7 i T-101 67.2 1.3 T-102 56.210.6 T-103 67 910.7 T-104 63.410.8 T-105 72.410.9 T-106 59.111.0 T-107 63.910.7 T-108 68.110.8 T-109 68.0 0.6 T-110 59.310.9 T-111 63.410.9 T-124 52.210.7 T-155 59.510.9 Mean i s.d. 63.617.3 Q_C T 80 38.910.6 T-81 78.510.6 T-82 48.410.6 T-83 46.010.8 T-84 50.410.7 T-85 57.2 0.8 T-86 78.310.7 T-88 74.311.1 T-89 68.110.7 T-113 NDa T-114 50.510.9 T-115 57.410.6 T-116 74.7t0.7 T-117 56.3 0.6 T-118 45.2 0.8 T-119 56.410.6 T-120 54.811.2 T-200 17.4t0.9 l Mean i s.d. 58.4111.8 aND = No Data; TLD lost in the field. j 28

{

i l

Tablel 3. Area monitors (TLD), Annual,1993 (continued).

Location mR/365 days Annual Shteld T-87 22.410.6 i

l 29

Table 14. Milk samples, analyses for Sr-89, Sr 90,1 131 and gamma-emitting isotopes.

Collection: Semimonthly May through October, monthly otherwise.

Date Lab Activity (oCi/D Collected Code Sr-89 Sr 90 1131 Ba l.a-140 Cs 137 K-40 T-8 Farm. 2.7 mi WSW of Station 01-11-93 TMI-8834 <0.8 1.0i0.4 <0.4 <10 <10 13901140 02-08-93 -8912 < 1.0 1.610.5 <0.3 <10- <10 14101150 03-08-93 -8969 <0.5 0.910.3 <0.4 <10 <10 13202150 04-12 93 -9066 <0. 6 0.910.4 <0.4 <10 <10 12801120 05 10 93 9145 <0.5 0.710.4 <0.5 <10 <10 1370i220 05-24-93 -9222 < 0. 6 1.310.4 <0.3 <10 <10 1450180 06-14-93 -9327 < 0. 6 1.6i0.4 <0.3 <10. <10 1470150 06-28-93 -9376 <0.7 1.410.4 <0.3 <10 <10 14801170 07-12-93 -9461 <0. 6 1.210.4 <0.4 <10 <10 12601160 07-26-93 -9525 <0.5 0.6i0.3 <0.5 <10 <10. 1480 170 08-09-93 -9597 < 1.0 1.310.4 <0.2 <10 <10 14401180 08-23-93 -9671 < 1.0 1.210.5 <0.5 <10 <10 13901170 09-13-93 -9773 <0.8 1.010.4 <0.5 <10 <10 13601130 09-27-93 -9849 <1.1 1.410.5 <0.5 <10 <10 14101160 10-12-93 -9920 <0.9 1.210.5 <0.5 <10 <10 13201150 10-25-93 -9988 <0.6 1.110.4 <0.5 <10 <10 14401170 11-08-93 -0066 < 0.6 1.410.4 <0.4 <10 <10 15101140 12 08-93 0138 <0.7 1.310.5 <0.4 <10 <10 12701160 l

l l

I l

l l

i l

30 l

4

l l

Table 14.

Milk samples, analyses for Sr-89, Sr-90,1 131 and gamma-emitting isotopes (continued)

Date Lab Activity (oCl/L)

Collected Code Sr-89 Sr 90 I131 BaiLa-140 Cs-137 K 40 T-24 (C) Sandusky 21.0 mi SE of Station 01-11-93 TMI-8835 <0.8 0.910.4 <0. 4 <10 <10 1410il50 02-08 93 -8913 , 4 <0.6 1.4i0.3 <0.3 <10 <10 13801110 03 09-93 -8970 < 0. 8 1.510.5 <0.4 <10 <10 1420t140 04-13-93 -9067 <0. 6 0.910.4 <0.5 <10 <10 1350i130 05-10 93 -9146 <0.6 1.310.4 <0.4 <10 <10 11901140 05-24 93 -9223 <0.5 1.210.4 <0. 4 <10 <10 12501140 06-14-93 -9328 <0.9 1.310.4 <0.3 <10 <10 1340160 06-28-93 -9377 <0.5 1.410.4 <0.5 <10 <10 13901170 07-12-93 -9462 <0.5 4.210.7a <0.3 <10 <10 1260i150 07-27-93 9526 <0. 6 1.110.4 <0. 4 <10 <10 1250i160 08 10-93 -9598 <0.7 1.110.4 <0.2 <10 <10 12301170 08-23-93 -9672 <0.9 1.510.5 <0.5 <10. <10 1310.1170 09-14-93 -9774 <0.8 1.010.4 <0.5 <10 <10 13101150 09-28-93 -9850 ,1 <0.6 1.010.4 <0.5 <10 <10 1480t130 10-12-93 -9921 <0.7 1.110.4 <0.5 <10 <10 1390il70 10-25 93 9989 <0.6 1.310.4 <0.5 <10 <10 1340i190 11-08-93 -0067 <0.7 1.0i0.5 <0.5 <10 <10 13701160 12-09-93 -0139 <0.5 1.3i0.4 <0.4 <10 <10 13601140 aSample was reanalyzed; result of reanalysis is 1.710.5 pCi/L 1

31 1

l Table 15. Milk samples, analyses for calcium, stable potassium, and ratios of St 90 (pCl)  !

per gram of calcium and Cs 137 (pCi) per gram of potassium.

Collection: Semimonthly May through October; monthly othenvise.

Sr-90 (pCi) Cs 137 (pCi)

Date Lab Calcium Potassium per gram per gram Collected Code (g/L) (g/L) of Calcium of Potassium T 8 Farm. 2.7 mi WSW of Station 01 11-93 TMI-8834 0.69 1.6110.16 1.45 <6.25 02-08 93 8912 0.69 1.6310.17 2.32 <6.25

, 03-08-93 -8969 1.00 1.5310.17 0.90 <6.54 l 04-12-93 -9066 0.82 1.5010.14 1.10 <6.67 l

05-10-93 9145 0.89 0.7410.16 0.79 <6.33 05 24 93 -9222 0.84 1.6810.09 1.55 <5.9 5 06-14 93 -9327 0.90 1.7010.06 1.78 <5.88 l 06 28-93 -9376 0.88 1.7110.20 1.59 < 5.8 5 07-12 93

-9461 0.87 1.4610.18 1.38 <6.85 07-26 93 9525 0.86 1.7110.20 0.70 <5.85 08 09-93 9597 0.92 1.6610.21 1.41 <6.02 08 23-93 9671 0.93 1.6110.20 1.29 < 6.21 09-13 93 9773 0.93 1.5710.15 1.08 <6.37 -

09-27-93 -9849 0.91 1.6310.18 1.54 < 6.14 -

10-12 93 -9920 0.84 1.5310.17 1.43 <6.54 10-25-93 -9988 1.02 1.6610.20 1.08- < 6.02 11-08-93 -0066 0.99 1.7510.16 1.41 <5.71 12-08 93 -0138 0.95 1.4710.18 1.37 < 6. 80 l

i l

[

]

32 1

l' l

Table 15, Milk samples, analyses for calcium, stable potassium, and ratios of Sr 90 (pCi) per l- gram of calcium and Cs 137 (pCl) per gram of potassium (continued)

Sr 90 (pCi) Cs 137 (pCi)

Date Lab Calcium Potassium pergram per gram Collected Code (g/L) (g/L) of Calcium of Potassium i

l T-24 (C) Sandusky. 21.0 mi SE of Station 01 11 93 TMI-8835 0.78 1.6310.17 0.70 <6.14 -

02 08-93 -8913,4 0.78 1.5910.13 1.79 <6.29

03 09-93 8970 0.92 1.6410.16 1.63 <6.10 i 04 13-93 -9067 0.77 1.5610.15 1.17 < 6.41 l 05 10-93 -9146 0.80 1.3810.16 1.62 <7.25 l 05-24-93 -9223 0.83 1.4510.16 1.45 <6.90 l 06-14-93 9328 0.89 1.55i0.07 1.46. <6.45 l 06-28-93 -9377 0.87 1.6110.20 1.61 <6.21 07-12-93 -9462 0.95 1.4610.17 4.42 <6.85 07-27-93 -9526 0.83 1.4510.18 1.33 <6.90 l

08-10-93 -9598 0.81 1.4210.20 1.25 <7.04 08-23 93 -9672 0.97 1.5110.20 1.55 < 6.62 09 14-93 -9774 0.83 1.5110.17 1.20 < 6.62 09 28-93 -9850, 1 0.90 1.7110.15 1.11 <5.85.

10-12-93 -9921 0.98 1.6110.20 1.12 < 6.21 l- 10-25-93 -9989 0.96 1.5510.22 1.35 <6.45 l 11-08-93 -0067 0.92 1.5810.18 1.09 < 6.33 l

12-09-93 -0139 0.97 1.57i0.16 1.34 < 6.37 I

l l

l 33 r

, ,,._ , _ . .- , _ , _ . . - . - , , . . . .#-,...,. . . . ,.w_ _ ,

1 Table 16 Cround water samples, analyses for gross beta, tritium, Sr-89, Sr-90 and gamma-emitting isotopes. Collection: Quarterly,1993.

Sample Description and Activity (pCi/L) Annual Meant s.d.

TZ 12b Code TWW-8977a TWW-1455 TWW-2539 TWW-3661

~

Collection Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Cross Beta Suspended Solids 0.210.1 <0.2 <0.3 <0.3 Dissolved Solids 4.610.3 4.60.4 2.li0.7 3.0i0.6 Total Residue 4.810.3 4.6i0.4 2.110.7 3.0t0.6 H-3 <330 965i120b <330 <330 Sr-89 <0.7 <0.7 < 1.0 <1.1 Sr-90 0.6i0.3 1.0i0.4 <0. 6 <0.6 Cs-137 <10 <10 <10 <10 Id4 lab Code TWW-8979 TWW-1457 TWW-2541 TWW-3663 Collection Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Cross Beta l Suspended Solids <0.2 <0. 8 <0.3 <0.3 Dissolved Solids 3.3i1.6 3.310.7 4.212.4 4.412.6 Total Residue 3.3i1.6 3.310.7 4.2 2.4 4.412.6

, H3 <330 <330 <330 <330 Sr-89 <0.7 <0.6 <0.7 < 1.0 Sr-90 0.410.3 < 0. 4 <0.5 <0.5 Cs-137 <10 <10 <10 <10 a Sample labeled location 7B.

b Sample was reanalyzed twice; results of reanalyses are 783i119 pCi/L and 8671121 pCi/L 34

N l

4 1

Table 16. Ground water samples, analyses for gross beta, tritium, Sr-89, Sr-90 and gamma-emitting isotopes,1993 (continued).

Sample Description and Activity (pCi/L) Annual Meant s.d.

l 1

T-23 (C) i Lab Code TWW-1406 TWW-2498 TWW-3698 TWW-4040a  ;

CoUection Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Cross Beta Suspended Solids <0.2 <0.2 <0.2 <0.4 t Dissolved Solids 1.9t0.6 2.710.7 2.210.6 2.8.11.3 Total Residue 1.90.6 2.710.7 2.210.6 2.811.3 H-3 <330 <330 <330 <330 Sr-89 <0.8 <0.6 <1.3 < 1.1 Sr-90 <0.5 <0.4 <0.6 <0.7 Cs-137 <10 <10 <10 <10 1

T-27 (C) lab Code TWW-8978 TWW 1456 TWW-2540 TWW-3662 Couection Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Cross Beta Suspended Solids <0.2 <0.8 <0.3 <0.3 DLssolved Solids < 1.8 <1.0 <0.6 <0.9 Total Residue <1.8 < 1.0 <0.6 <0.9 -

H-3 <330 <330 <330 <330 Sr-89 < 1.2 <0.7 <1.1 < 1.3 -l Sr-90 <0. 6 < 0. 6 <0.7 < 0. 6 I Cs-137 <10 <10 <10 <10 alast collection this year, sample will be analyzed as if it were a composite.

35 l l

l Table 16. Ground water samples, analyses for gross beta, tritium, Sr 89, St-90 and gamma-emittmg tsotopes,1993 (continued).

! l l

Sample Description and Activity (pCi/L) Annual Meant s.d.

l T-141 (OC) lab Code TWW-8980 TWW-1458 TWW-2542 TWW 3664 l

Collection Period 1st Qtr. . 2nd Qtr. 3rd Qtr. 4th Qtr.

Cross Beta Suspended Solids <0.1 <0.2 <0.3 <0.3 Dissolved Solids <2.4 <3.7 - 4.112.6 <7.4 a Total Residue < 2. 4 <3.7 4.112.6 < 7. 4 H-3 <330 <330 <330 <330 Sr-89 <0.7 < 0. 6 <0.9 <0.9 Sr-90 <0.5 <0.4 <0.6 0.810.4 Cs-137 <10 <10 <10 <10 aSample reanalyzed; result of reanalysis is 2.610.6 pCi/L l

l 36

f l

l l

Table 17. Domestic meat samples, analysis for gamma-emitting isotopes.

l l

1 l l Date Lab Sample Activity (oCi/g wet) l Location Collected Code Type K-40 Cs-137 '

l T-34 07-13-93 TME-170 Chicken 2.5210.19 <0.007 T 197 07-15-93 TME-171 Chicken 2.3210.22 <0.009 l l

i t

I I

37

I I

i I

Table 18. Wild meat samples analysis for gamma-emitting isotopes.

Date Lab Sample Activity (DCif e wet)

Location Collected Code Type K-40 Cs 137 T 31 12-28 93 TME-176 Canada 2.98 0.32 0.03210.016 Goose l

i 1

I l

l 38 I

Table 19. Creen leafy vegetables, analyses for strontium 89, strontium-90, iodine-131, and other gamma-emitting isotopes. Collection: Monthly in season.

Sample Description and Activity Location T-8 T-25 T-37 Lab Code TVE 1549 TVE 1551 TVE-1550 Collection Date 07-15-93 07-15-93 07-15-93 Type Horseradish Cabbage Cabbage l

Sr-89 <0.003 <0.004 <0.002 Sr-90 0.005 0.001 0.00410.001 0.00610.001 l I-131 <0.043 <0.014 <0.031 l K 40 5.92 0.58 3.3710.38 3.4610.39 Nb-95 <0.020 <0.012 <0.016 Zr-95 <0.014 <0.021 <0.010 Cs-137 <0.031 <0.012 <0.018 I Ce-141 <0.050 <0.019 <0.042 Ce-144 <0.16 <0.079 <0.14 i

Location T8 T-8 T-25 T-37 bb Code TV E-1617 TVE-1618 TVE-1619 TVE-1620  ;

Collection Date 08 17-93 08 17-93 08-17-93 08-17-93 i Type Lettuce Horseradish Swiss Chard Cabbage l I

Sr-89 <0.005 <0.006 <0.002 <0.001 St-90 0.00510.002 0.01210.003 <0.001 0.00810.004 j I-131 <0.021 <0.034 <0.017 <0.016 I K-40 5.59 0.50 7.0010.88 5.0710.55 2.32 0.37 Nb-95 <0.014 <0.016 <0.018 <0.008 Zr-95 <0.018 <0.045 <0.030 <0.022 i Cs-137 <0.024 <0.016 <0.018 <0.008 l Ce-141 <0.017 <0.042 <0.024 <0.013 Ce-144 <0.071 <0.18 <0.10 <0.063 Location T-8 T-25 T-37 bb Code TVE-1703 TV E-1705 TVE-1707 Collection Date 09-21-93 09-21-93 09 21-93 Type Cabbage Swiss Chard Cabbage Sr-89 <0.002 <0.002 <0.002 Sr-90 0.001610.0007 <0.0009 0.001010.0005 I-131 <0.036 <0.036 <0.022 K-40 2.5210.26 4.0410.36 2.0510.11 Nb-95 <0.013 <0.010 <0.006 Zr-95 <0.017 <0.021 <0.006 Cs-137 <0.008 <0.011 <0.003 Ce 141 <0.014 <0.019 <0.008 Ce-144 <0.044 <0.059 <0.019 39

I I

f Table 20. Fruit Samples, analyses for strontium 89, strontium 90, iodine-131, and other gamma-emitting isotopes.

Collection: Monthly in season.

Sample Description and Activity (pCi/g wet)

Location T8 T-25 T-37 Lab Code TVE 1702 TVE 1704 TVE 1706 Collection Date 09-21-93 09 21-93 09 21 93 Type Apples Pears Pumpkin Sr-89 <0.002 <0.002 <0.002 Sr 90 <0.0006 <0.001 0.001210.0007 I-131 <0.017 <0.036 <0.057 K-40 1.1510.09 1.8810.24 2.0310.25 Nb-95 <0.004 <0.006 <0.011 Zr-95 <0.006 <0.010 <0.012 Cs 137 <0.003 <0.007 <0.010 Ce-141 <0.007 <0.012 <0.021 Ce-144 <0.021 <0.042 <0.053 Location T-173 T-23 T-23 Lab Code TVE-1727 TVE-1738 TVE-1739 l Collection Date 10-15-93 10 29-93 10-29-93 Type Grapes Grapes Grape Juice

! Sr-89 <0.003 <0.003 <0.001 Sr-90 0.001510.0007 0.0092i0.0016 0.000710.0003 1131 <0.016 <0.044 <0.023 K-40 2.6210.24 4.0910.56 0.7410.11 Nb-95 <0.004 <0.034 <0.007 Zr-95 <0.009 <0.081 <0.010 Cs-137 <0.007 <0.025 <0.005 Ce-141 <0.013 <0.030 <0.012 ,

Ce 144 <0.030 <0.082 <0.045 1

40 ,

1 I

Table 21. Animal- wildlife feed samples, analysis for gamma-emitting isotopes. Couection: l Semiannually. l Sample Description and Activity (pCi/g wet) l Location T-8 T-34 T-197 Collection Date 01-11-93 07-13 93 07 15 93 l bb Code TCF-499,500 TCF-511 TCF 512 l Type Sileage Mixed Feed Mixed Feed -

Be-7 <0.20 <0.046 - <0.094 K-40 12.810.6 5.8010.35 5.9610.42 i

Nb 95 <0.029 <0.008 <0.020 Zr-95 <0.050 <0.020 <0.017 Ru-103 <0.025 <0.006 <0.015 Ru-106 <0.22 <0.098 <0.14 Cs 137 <0.027 <0.010 <0.016 .

Ce-141 <0.027 <0.020 <0.028 Ce-144 <0.12 <0.072 <0.14 Location T-31 T-198 Collection Date 09 08-93 09-08 93 bb Code TCF-513 TCF-514 Type Cattall Stems Millet Be-7 <0.085 0.6610.23 K-40 0.86i0.16 3.0710.47 Nb-95 <0.012 <0.028 1 Zr-95 <0.016 <0.023

, Ru 103 <0.010 <0.017  !

Ru 106 <0.073 <0.095 Cs-137 <0.011 <0.016 Ce-141 <0.019 <0.028 Ce-144 <0.075 <0.077 i

l 41

s - - -

~

I Table 2 2. Soil samples, analysis for gamma-emitting isotopes.

Sample Description and Activity (pCi/g dry)

- Location T-1 T-2 T-3 T-4 T7 i Collection Date 04-26 93 04 26-93 04-26 93 04-26-93 04 26-93 '

bb Code TSO 769 TSO 770 TSO-771 TSO-772 TSO 778 Be-7 <0.25 <0.21 0.8810.23 <0.22 0.7610.13 K-40 8.3010.67 13.1710.65 21.50io.78 22.17i0.72 10.6810.44 Nb-95 <0.04 <0.02 <0.02 <0.03 <0.01 Zr-95 <0.06 <0.02 <0.03 <0.03 <0.02 Ru-103 <0.03 <0.02 <0.03 <0.01 <0.01 Ru-106 <0.29 <0.13 <0.21 <0.20 <0.06 Cs-137 0.18i0.03 0.2110.03 0.1010.02 0.1110.03 <0.01 Ce-141 <0.05 <0.05 <0.04 <0.04 <0.03 Ce-144 <0.19 <0.08 <0.09 <0.12 <0.04 Location T-8 T-9(C) T 11(C) T-12(C) T-27(C)

Collection Date 04-26-93 04 26-93 04-26-93 04-26-93 04-26-93 Lab Code TSO-773 TSO-774 TSO-775 TSO-776 TSO 777 Be-7 <0.38 <0.29 1.00f0.26 <0.58 0.8010.20 K 40 25.7011.38 24.4011.05 13.6510.76 18.1011.33 22.1410.75 l Nb-95 <0.06 <0.04 <0.02 <0.07 <0.03 Zr 95 <0.09 <0.07 <0.03 <0.12 <0.04 Ru-103 <0.05 <0.04 <0.01 <0.07 <0.02 Ru-106 <0.43 <0.32 <0.18 <0.56 <0.08 Cs-137 0.2510.04 0.2510.03 0.2310.04 0.4210.07 0.2810.03 Ce-141 <0.05 <0.04 <0.05 . <0.10 <0.04 Ce-144 <0.20 <0.14 <0.17 <0.39 <0.15 Location T-23 Collection Date 06-10 93 .

bb Code TSO-795 Be-7 0.3810.23 K-40 14.9610.67 Nb-95 <0.04 Zr-95 <0.02 Ru-103 <0.03 Ru-106 <0.17 Cs 137 0.76 0.04 Ce-141 <0.05 Ce-144 <0.14 42

Table 2 2, Soil samples, analysis for gamma-emitting isotopes.

Sample Description and Activity (pCl/g dry) location T1 T-2 T-3 T-4 T-7 l Collection Date 10-04-93 10-04-93 10-04-93 10-04-93 10-04 93  ;

1.ab Code TSO-823 TSO-824 TSO-825 TSO-826 TSO-827, 8 Be-7 <0.40 <0.44 <0.36 <0.57 <0.26 I K-40 5.93i0.53 6.32i0.51 13.5810.62 22.5311.14 10.2210.42 l Nb-95 <0.057 <0.071 <0.027 <0.074 <0.042 l Zr-95 <0.069 <0.028 <0.071 <0.083 <0.062 Ru-103 <0.048 <0.062 <0.055 <0.061 <0.054 Ru-106 <0.11 <0.088 <0.18 <0.16 <0.068 Cs-137 0.2310.03 0.1010.02 0.035i0.017 0.1910.05 <0.021 Ce-141 <0.055 <0.013 <0.054 <0.097 <0.086 Ce-144 <0.13 <0.084 <0.085 <0.20 <0.15

~

Location T-8 T-9(C) T-11(C) T-12(C) T-27(C)

Collection Date 10-04-93 10-04-93 10-04-93 10-04-93 10-04-93 I I.ab Ccde TSO-829 TSO-830 TSO-831 TSO 832 TSO-833 l Be-7 <0.64 <0.59 <1.58 <0.59 <0.60 K-40 24.13il.20 23.6411.07 22.97it.54 21.3710.98 23.3511.07 Nb-95 <0.050 <0.057 <0.27 <0.064 <0.041 Zr-95 <0.14 <0.11 <0.30 <0.11 <0.11 Ru-103 <0.090 <0.061 <0.18 <0.070 <0.073 Ru-106 <0.30 <0.33 <0.60 <0.26 <0.36 Cs-137 0.7610.06 0.6010.05 0.2610.07 0.40 0.04 0.3510.05 Ce-141 <0.15 <0.094 <0.50 <0.13 <0.15 Ce-144 <0.31 <0.13 <0.68 <0.24 <0.19 Location T-23 Collection Date 10-04-93 lab Code TSO-835 Be-7 <0.34 K-40 15.0410.86 Nb-95 <0.036 Zr-95 <0.026 Ru-103 <0.046 Ru-106 <0.11 Cs-137 0.5810.05 Ce-141 <0.044 Ce-144 <0.14 43

l Table 2 3. Treated surface water samples, monthly composites of weeldy grab samples, i analyses for gross beta,1993.

Cross Beta Activity (oCi/D l Collection Lab Suspended Dissolved ~ Total i Period Code Solids Solids Residue l l

T-11 (C)

Jatiuary TSWT-9066 <0.3 2.710.6 2.710.6 February -9792 <0.2 2.6t0.6 2.610.6 March -1196 512 2.410 5 2.4 t0. 5 1st Qtr. mean i s.d. <0.3 2.610.2 2.610.2 Apr0 TSWT-1570 <0.4 2.510.5 2.510.5 May -1963 <0.2 2.40.5 2.4i0.5 June -2248 s13 1.9t0 5 19t0 5 2nd Qtr. mean i s.d. <0.4 2.310.3 2.310.3 July TSWT-2648 <0.3 2.110.6 2.10.6 August -3099 <0.2 2.810.5 2.810.5 September 3418 512 2.210.5 2210_5 3rd Qtr. mean i s.d. <0.3 2.410.4 2.40.4 October TSWT-3801 <0.3 1.4t0.5 1.410.5 November -4182 <0.4 2.210.5 2.210.5 December -4490 SA3 2J1QJ 2 6tQ 6 4th Qtr. mean t s.d. <0.3 2.110.6 2.110.6 I

l l

l 1

1 l

l 44 l

l

(

l i

! I l Table 2 3. Treated surface water samples, monthly composites of weekly grab samples, analyses for gross beta,1993 (continued) l Cross Beta Activity (oCi/L) -

Collection Lab Suspended- Dissolved Total Period Code Solids Solids Residue  !

T-12 (C) 1 January TSWT 9067 <0.2 2.510.5 2.510.5 February -9793 <0.2 2.010.5 2.0i0.5 March -1197 1Q3 1.710.4 1.7t0 4 1st Qtr. mean i s.d. <0.2 2.110.4 2.110.4 April TeWT-1571 <0.3 2.3i0.5 2.310.5 May_. -1964 <0.2 2.510.5 2.510.5 June -2249 sQl 2,110 5 2,110 5 2nd Qtr. mean i s.d. - <0.3 2.310.2 2.310.2 i

July TSWT-2649 <0.3 1.810.6 1.8i0.6 ,

August -3100 <0.2 1.710.5 1.710.5 September -3419 sQJ 2.010,5 191Q.5 3rd Qtr. mean i s.d. <0.3 1.810.2 1.810.2 October TSWT-3802, 3 <0.3 1.910.4 1.910.4 November -4183 <0.3 1.5t0.4 1.510.4 December -4491 sQl 2,610 5 26106 4th Qtr. mean i s.d. <0.3 2.010.6 2.010.6 l

45

l Table 2 3. Treated surface water samples, monthly composites of weekly grab samples, analyses for gross beta,1993 (continued) i C tgas Beta Activity (oCi/L)

Collection Lab Suspended Dissolved Total Period Code Solids Solids Residue T-23 (C)

January TSWT-9662 <0.2 3.210.6 3.210.6 February -1005 <0.4 1.9to.6 1.910.6 March -1398 <12 2.5t0 6 2 5t0 6 1st Qtr. mean i s.d. <0.4 2.510.7 2.510.7 l April TSWT-1682 <0.3 1.710.5 1.7i0.5 l May -1984 <0.2 2.210.5 2.2io.5 June -2391 <13 16t0 5 16t0 5 2nd Qtr. mean i s.d. <0.3 1.810.3 1.810.3 l July TSWT 2793 < 0. 4 1.610.6 1.610.6 l August -3143 <0.2 1.310.5 1.310.5 l September -3640 $13 2.li0.5 21t0 5 i 3rd Qtr. mean i s.d. <0.4 1.10.4 1.70.4 October TSWT-4038 <0.3 2.210.5 2.210.5 November -4302 <0.3 1.810.5 1.810.5 December NSa .. .. ..

4th Qtr. mean i s.d. <0.3 2.0i0.3 2.0io.3 aNo sample; sample not collected.

I l

1 1

46 l ll

,,y,, g, ~+. . y n - _..- ., - 9y

Table 2 3. Treated surface water samples, monthly composites v weekly grab samples, analyses for gross beta,1993 (continued)

Cross Heta Activity (oCi/L)

Collection Lab Suspended Dissolved ' Total Period Code Solids Solids Residue I-23 January TSWT 9068,9 <0.2 2.410.4 2.410.3

~ February -9794,5 <0.2 2.610.4 2.610.4 March -1198 10.:2 2.410.5 2.410 5 ist Qtr. mean t s.d. <0.2 2.5t0.1 2.510.1 April TSWT-1572 <0.3 1.9to.5 1.910.5 May -1965 <0.2 1.810.4 1.810.4 June 2250 sQJ 1.4t0 4 1,4 04 2nd Qtr. mean i s.d. <0.3 1.710.3 1.710.3 July TSWT-2650 <0.3 1.7i0.5 1.710.5 August -3101 <0.2 1.910.5 1.910.5 September -3420 sQJ 1.6i0.4 16t0.4 3rd Qtr. mean i s.d. <0.3 1.710.2 1.710.2 October TSWT-3804 <0.2 1.410.5 1.410.5 l November -4184 <0.4 2.410.5 2.410.5 December -4492 1QJ . 2.110.5 2 110.5 4th Qtr. mean s.d. <0.4 2.0i0.5 2.00.5 l

! +

l l

l i

l l 4 *l 1 1

I

'l

. - _ _ .- - . _, -1

l Table 2 3. Treated surface water samples, monthly composites of weekly grab samples, analyses for gross beta,1993 (continued)

Cross Beta Activity (cCi/L)

Collection Lab Suspended Dissolved ' Total Period Code Solids Solids ' Residue I:10 January TSWT-9070 <0.2 . 2.9i0.6 2.910.6 February -9796 <0.2 2.410.5 2.410.5 March -1199 $9_2 2.410.4 2.410,4 1st Qtr. mean i s.d. <0.2 2.610.3 2.610.3 April TSWT-1573 <0.3 2.110.5 2.110.5 May -1966 <0.2 1.9i0.5 1.910.5 June -2251 sQ.] 2.710.5 2.7to.5 2nd Qtr. mean i s.d. <0.3 2.2i0.4 2.210.4 ,

, July TSWT-2651 <0.3 2.310.4 2.3to.4 August -3102 <0.2 2.110.5 2.110.5 September -3421 <Q.2 2.7i0.4 2,710.4 l _

3rd Qtr. mean i s.d. <0.3 2.410.3 2.410.3 October TSWT 3805 <0.2 2.110.5 2.110.5 November -4185 <0.3 2.410.5 2.410.5 December 4493 sDJ 2.810 5 2.8t0 5 4th Qtr. mean i s.d. <0.3 2.410.4 2.410.4 l

l I

l 48

Table 2 3. Treated surface water samples, monthly composites of weekly grab samples, i

analyses for gross beta,1993 (continued) l Cross Beta Activity foCl/L) l Collection Lab Suspended Dissolved Total l Period Code Solids Solids Residue T-144 1

January TSWT-9072 <0.2 3.li0.5 3.110.5 February -9798 < 0.2 2.710.5 2.710.5 March -1201 512 2 510.5 2.514 5 1st Qtr. mean i s.d. <0.2 2.810.3 2.810.3 April TSWT-1575 <0.3 2.510.5 2.510.5 May -1968 <0.2 2.110.5 2.110.5 June -2253 513 2 3t0 5 23105 2nd Qtr. mean i s.d. <0.3 2.310.2 2.310.2 July TSWT-2652 <0.3 2.4i0.6 ' 2.410.6 August -3104 <0. 2 2.310.5 2.310.5 l September -3423 512 2.110.4 2.10.4 .

3rd Qtr. mean i s.d. <0.3 2.310.2 2.310.2 l

l October TSWT-3807 <0.2 1.710.6 1.7t0.6 i November 4187 <0.3 2.310.5 2.310.5 December -4495 $13 2.5t0.5 2.510 5 4th Qtr. mean i s.d. <0.3 2.210.4 2.210.4 1 l

l l

1 I

I' l

49 l

• I

Table 2 3. Treated surface water samples, monthly composites of weekly grab samples, analyses for gross beta,1993.

Cross Beta Activity (oCl/L)

Collection Lab Suspended Dissolved ~ Total Period Code Solids Solids Residue l T-143 (OC)

, January TSWT 9071 <0.2 2.310.5 2.310.5 February 9797 <0.2 2.510.5 2.510.5 March 1200 <A2 2 810.5 28105 1st Qtr. mean i s.d. <0.2 .2.510.3 2.5t0.3 l

, April TSWT-1574 <0.3 2.510.5 2 510.5 l May -1967 <0.2 1.910.5 1.910.5 l June 2252 10.2 1.510 5 15105 l <0.3 2.010.5 2.010.5 2nd Qtr. mean i s.d.

l l

July TSWT-2653 <0.3 1.70.6 1.710.6 August -3103 <0.2 4.010.6 4.010.6 September -3422 512 2dtQd 2 510.4 3rd Qtr. mean i s.d. <0.3 2.711.2 2.711.2 October TSWT-3806 <0.2 1.610.5 1.610.5 November -4186 <0.3 1.810.4 1.810.4 December -4494 10 2 2.510.5 2 5t0 5 4th Qtr. mean i s.d. <0.3 2.010.5 2.010.5 l

l 50 i

i i

Table 2 4. Treated surface water samples, quarterly composites of weekly grab samples, analysis for tritium, strontium-89, strontium 90 and gamma-ermtting isotopes,1993.  ;

)

i Collection Lab Activity (oCi/D l Location Period Code H-3 Sr-89 'Sr-90 Cs 137 Control I-l l 1st Quarter TSWT-1208 <330 <0.6 <0.5 <10 2nd Quarter -2491 <330 <0.8 < 0.5 . <10 3rd Quarter -3572 <330 < 1.4 <0. 6 <10 4th Quarter -4701 s31Q 50J 50J <10 Annual mean i s.d. <330 < 1.4 <0.5 <10 I:12 1st Quarter TSWT 1209 <330 <0. 6 <0.5 <10 2nd Quarter -2492 <330 <0.9 <0.5 <10 3rd Quarter -3573 <330 < 1.4 <0.7 <10 4th Quarter 4702 s32 2 502 sQd <lQ Annual mean i s.d. <330 < 1.4 <0.7 <10 i

T-23 1st Quarter TSWT-1407 <330 <0.6 <0.3 <10 2nd Quarter -2496,7 <330 <0.6 <0.4 <10 3rd Quarter -3742 <330 <2.4 <0.8 <10 4th Quarter -4749 <330 <0.4 50J <10 Annual mean i s.d. <330 <0.6 <0. 8 <10 1

)

i 51

Table 2 4. Treated surface water samples, quarterly composites of weekly grab samples, analysis for tntium, strontium-89, strontium-90 and gamma-emitting isotopes,1993 (continued).

Collection Lab Activity (oCi/U Location Period Code H-3 Sr-89 ~ Sr-90 Cs-137 Indicator I-2J5 1st Quarter TSWT 1210 <330 <0.5 <0.5 <10 2nd Quarter -2943 <330 <0.9 <0.6 <10 3rd Quarter -3574 <330 < 1.5 <0. 7 <10 4th Quarter 4703 d3.Q <0.9 sgji < tg Annual mean s.d. <330 < 1.5 < 0. 7 <10 I.-10 1st Quarter TSWT-1211 <330 <0.5 <0.4 <10 l 2nd Quarter -2494 <330 <0.7 <0.6 <10 1 3rd Quarter -3575 <330 < 1. 4 < 0. 7 <10 1 4th Quarter -4704 <33.Q sQjl 50Ji s1Q j Annual mean i s.d. <330 < 1. 4 <0.7 <10 T-14_4 1st Quarter TSWT-1212 3551100a <0.6 <0.5 <10 2nd Quarter -2495 <330 <0.7 <0.5 <10 3rd Quarter -3576 <330 < 1.3 <0.6 <10 4th Quarter -4705 d3Q < 1. 4 < 1.0 sjig Annual mean i s.d. <330 < 1.4 <1.0 <10

.I 1

a Analysis was repeated; result of reanalysis 280t100 pCi/L I

I I

l l

52

j Table 2 5. Untreated surface water samples. monthly composites of weekly samples. analyses l

for gross beta, tritium and gamma emitting isotopes,1993.

Cross Beta Activity (oCi/L)

Collection Lab Suspended Dissolved ~ Total .Acuvity (oCi/L)

Period Code Solids Solids Residue H-3 ~Cs-137 T-11 (C)

January TSWU 9060 <0.2 3.2i0.6 3.210.6 <330 <10 i February -9801 <0.2 2.410.Sa 2.410.5a <330 <10 l March -1190 593 2.7tQ 5 77t0.5 sHQ <1Q 1st Qtr. mean i s.d. < 0. 2 2.810.4 2.810.4 <330 <10 April TSWU 1578 <0.4 2.710.5 2.710.5 <330 <10 May 1957 <0.3 2.010.5 2.010.5 <330 <10 June -2258 <0.2 2.404 2 410.4 sHQ <10 2nd Qtr. mean i s.d. <0.4 2.410.4 2.410.4 <330 <10 July TSWU-2656 <0.4 1.6t0.5 1.610.5 <330 <10 August -3093 <0.3 2.810.8 2.810.8 <330 <10 September -3427 sQJ 2.6tQ.6 2.6t0 6 sHQ <10  !

3rd Qtr. mean i s.d. < 0. 4 2.310.6 2.30.6 <330 <10 October TSWU-3810 <0.2 2.20.5 2.210.5 <330 <10 November -4191 <0.4 2.410.5 2.410.5 <330 <10 l December -4499 <0.2 3 QiQ 5 3.010.6 sMQ <10 l

4th Qtr. mean i s.d. <0.4 2.510.4 2.510.4 <330 <10 l

aSample was reanalyzed; corrected data.

l l

l I

i l 53 l

Table 2 5. Untreated surface water samples, monthly composites of weekly samples, analysis for gross beta, tritium and gamma-emitting isotopes,1993 (continued).

Gross Beta Activity (oCl/L)

Collection Lab Suspended Dissolved ~ Total Activity (oCi/L)

Period Code Solids Solids Reskiue H3 . 'Cs-137 T-12 (C)

January TSWU-9061 1.0i0.1 3.210.6 4.210.3 <330 <10 February 9802 <0.2 2.710.3 2.710.3 <330 <10 t March -1191 512 3 010.5 3 Ot0 5 5320 g.]_Q 1st Qtr. mean i s.d. 1.010.1 3.0 0.3 3.310.8 <330 <10 .

April TSWU-1579 <0.3 3.510.5 3.510.5 <330 '<10 May -1958 <0. 4 2.610.5 2.610.5 <330 ~ <10-June -2259 512 2 610.4 26104 513.Q - <10 2nd Qtr. mean i s.d. <0.4 2.910.5 .2.910.5 <330 <10-

~

! July TSWU 2657 <0.4 2.210.5 2.210.5 <330 <10 August 3094 <0.2 2.7t0.7 2.710.7 <330 <10 September -3428 512  ;!.419.7 2.4t0,7 531Q $10 3rd Qtr. mean i s.d. <0.4 2.410.3 2.410.3 <330 <10 I

October TSWU-3811 <0.3 2.510.5 2.510.5 <330 <10 November -4192 <0.3 1.910.5 1.910.5 <330 <10 December -4500 512 3 0t0 6 3.0tQ 6 513Q <10 4th Qtr. mean i s.d. <0.3 2.510.6 2.510.6 <330 <10 l

l 54 I

- - . . ~ . . - . _

1 l

Table 2 5. Untreated surface water samples, monthly composites of weekly samples, analysis for gross beta, tritium and gamma-emitting isotopes,1993 (continued).

Cross Beta Activity (oCi/L)

Collection Lab Suspended Dissolved ~ Total Activity foci /L) 1 Period Code lids Solids Residue H-3 'Cs-137

]

T-23 (C)

January TSWU-9063 0.510.1 2.810.6 3.310.6 <330 <10-February -1004 0.210.1 1.910.5 2.110.5. <330 <10 March -1399 512 77105 2.7t0 5 5339 <10 1st Qtr. mean i s.d. 0.410.2- 2.510.5 2.710.6 <330 <10 April TSWT-1683 <0.3 2.5t0.5 2.510.5 <330 <10-May -1985 <0.3 2.410.5- 2.410.5 <330 <10 June -2392 512 1,910.4 1.910 4 52 10 $1Q 2nd Qtr. mean i s.d.- <0.3 2.310.3 2.310.3 <330 <10 1

July TSWU-2794 <0.4 1.910.5 1.910.5 <330 <10 August -3142 <0.3 1.710.5 1.710.5 <330 <10 September -3641 5J0 18t0.4 1.810,4 5J10 $10 ,

3rd Qtr. mean i s.d. <0.4 1.810.1 1.810.1 <330 <10 October TSWU-4039 <0.4 2.5t0.5 2.510.5 <330 ' <10 November -4301 <0.3 3.410.6 3.410.6 <330 <10 December -4644 <0. 4 2.0 06 2.0$0 6 5310 51Q 4th Qtr. mean i s.d. <0.4 2.6t0.7 2.610.7 <330 <10 e

55 i l

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

Table 2 5. Untreated surface water samples, monthly composites of weekly samples, analysis for gross beta, tritium and gamma-emitting isotopes,1993 (continued).

Cross Beta Activity (oCi/L)

Collection Lab Suspended Dissolved ~ Total Activity (oCi/ L)

Period Code Solids Solids Residue H3 ~Cs 137 L3 January TSWU-9058 0.410.1 3.910.6 4.310.6 <330 <10 February -9799 0.810.1 2.510.3 3.310.3 <330 <10 March -1188 0.310.2 5.110.7 5.410,7 s330 s1Q 1st Qtr. mean i s.d. 0.510.3 3.811.3 4.311.0 <330 <10 April TSWU 1576 <0.3 3.510.6 3.510.6 <330 <10-May -1955 0.810.3 4.010.6 4.810.7 <330 <10 June -2255, 6 <0. 3 3 3t0.3 33103 s31Q 51Q

! 2nd Qtr. mean i s.d. 0.810.3 3.610.4 3.910.8 <330 <10 i

July TSWU 2654 <0.3 3.110.6 3.110.6 <330' <10 August -3091 <0.2 3.010.5 3.010.5 <330 <10 September -3425 504 3 St0 6 35106 s31Q s1Q 3rd Qtr. mean i s.d. <0.6 3.210.3 3.210.3 <330 <10 October TSWU-3808 <0.2 1.910.6 1.910.6 <330 <10 November -4188, 9 <0.7 2.910.4 2.910.4 <330 <10 December -4497 sQl 4,110 6 4 110,6 133Q s1Q 4th Qtr. mean i s.d. <0.7 3.011.1 3.0tl.1 <330 <10 l

I 1

56 t

y . . . _ _ . , - . _ _ _

m. _ _

1 Table 2 5. Untreated surface water samples, monthly composites of weeldy samples, i analysis for gross beta, tritium and gamma-emitting isotopes,1993 (continued).

Cross Beta Activity (oCl/L) .

Collection Lab Suspended Dissolved ' Total Activity (oCi/L) l Period Code Solids Solids Residue H3 ~Cs 137 I-2.6

. TSWU-9063 <0.2 3.110.6 3.110.6 <330 <10 I January February -9804 <0.2 3.010.5 3.0io.5 <330 .<10 March -1193 512 31106 3.1t0 6 dM sg ist Qtr. mean i s.d. <0.2 3.110.1 3.110.1 <330' <10 April TSWU-1581 <0.3 2.910.5 2.9to.5 <330 <10 May -1960 0.4t0.2 '1.910.6 2.310.6 <330 <10

June -2261 512 S.1tQ 5 3 110.5 s3M sE i 2nd Qtr. mean i s.d. 0.410.2 2.6t0.6 2.8i0.4 <330 <10 July TSWU-2660 <0.4 2.410.5 2.410.5 <330 <10 August -3096 <0.2 3.110.6 3.10.6 <330

<10 September -3430 sgj 2.610.6 2.610.6 ME $_1.Q 3rd Qtr. mean i s.d. < 0. 4 2.710.4 2.710.4 <330 <10 October TSWU-3813 <0.4 2.310.5 2.310.5 <330 <10 November -4194 <0.3 2.710.8 2.710.8 <330 <10 December -4502 5A2 2.6tQ.6 2 6t0,6 s.3M <10 4th Qtr. mean i s.d. <0.4 2.510.2 2.510.2 <330 <10 l

l

' I 1

57

/

i

1 Table 2 5. Untreated surface water samples, monthly composites of weekly samples, analysis for gross beta, tntium and gamma. emitting isotopes,1993 (continued).

Gross Beta Activity (oCi/D Collection Lab Suspended Dissolved ~ Total Activity (pfJ/_L)

Period Code Solids Solids Residue H3 Cs 137 I:10 January TSWU-9064 0.510.1 3.310.5 3.810.5 <330 <10 February -9805 0.210.1 3.610.6 3.810.3 <330 <10 March -1194 0,410 1 3 210.6 3 610.6 51 10 sig ist Qtr. mean i s.d. 0.410.2 3.410.2 3.710.1 <330 <10 April TSWU-1582 <0.3 2.2 0.5 2.20.5 <330 <10 May -1961 <0.3 2.810.6 2.810.6 <330 <10 June -2262 sQl 2 210,4 12104 51 10 s1Q 2nd Qtr. mean i s.d. <0.3 2.410.3 2.410.3 <330 <10 July TSWU-2661 <0.4 2.610.6 2.610.6 <330 < 1'O August -3097 <0.2 3.110.5 3.110.5 <330 <10 September -3431 <0.2 2.210 5 2.210 5 6221115a sig 3rd Qtr. mean i s.d. < 0. 4 2.610.5 2.610.5 6221115a <jo October TSWU-3814 < 0.2 2.110.5 2.110.5 <330 <10 November -4195 <0.3 2.210.7 2.210.7 <330 <10 December -4503 <0.2 2.110.6 2.110.6 <330 sig 4th Qtr. mean i s.d. <0.3 2.lio.1 2.110.1 <330 <10 a Sample was reanalyzed; result of reanalysis is 5751112 pCi/L l

l l 58 l

l l

1 1

1 Table 25 Untreated surface water samples, monthly composites of weekly samples, analysis

( for gross beta, tritium and gamma emitting isotopes,1993.

Cross Beta Activity (oCi/L)

Collection Lab Suspended Dissolved Total Activity (oCl/L) l Period Code Solids Solids Residue H3 TCs 137 T-145 (OC)

January TSWU 9065 2.410.2 3.5t0.6 5.910.6 <330 <10 February 9806 0.410.1 3.210.5 3.610.3 <330 <10 2,6t0 5 l March -1195 0.210 1 2.410 5 131Q s1.Q 1st Qtr. mean i s.d. 1.011.2 3.010.6 4.011.7 <330 <10 April TSWU-1583,4 <0.5 2.610.4 2.610.4 <330 <10

. May -1962 <0.3 2.810.5 2.810.5 <330 <10 June -2263 10J 3 510.5 151QJi s)1Q slQ 2nd Qtr. mean i s.d. <0.5 3.010.5 3.010.5 <330 <10 l

l July TSWU-2668 <0.4 2.410.6 2.410.6 <330 <10 August -3098 <0.2 3.310.5 3.310.5 <330 <10 September 3439 sQl 2J.t0Ji 2.7tQ.6 5320 110 3rd Qtr. mean i s.d. <0.4 2.810.5 2.810.5 <330 <10 October TSWU-3815 <0. 2 3.0t0.6 3.010.6 <330 <10 ;

November -4196 <0.4 2.110.7 2.110.7 <330 <10 December 4504 sQl 2.710.4 2,7t0.4 $130 51Q 4th Qtr. mean i s.d. <0.4 2.610.5 2.610.5 <330 <10 59 l

l

i l

l l

l Table 26. Untreated surface water samples, quarterly composites of weekly grab samples, analysis for Sr-89 and Sr-90,1993.

Collection Lab Activity (oCi/L)

Location Period Code St 89 Sr-90 Control Lil 1st Quarter TSWU-1389 <0.6 <0.5 2nd Quarter -2610 <0.8 <0. 6 3rd Quaner -3740 < 1.6 <0.7 4th Quarter -4747 10.2 sQJ Annual mean i s.d. <1.6 <0.7 L12 1st Quarter TSWU-1390 <0.6 0.610.3 2nd Quarter 2611 <1.1 <0.5 3rd Quarter -3743 <1.6 <0.6 4th Quarter -4744 10J sQJ Annual mean i s.d. <1.6 0.610.3 L23 1st Quarter TSWU-1426 <0.7 <0.5 2nd Quarter -2612 <0.8 <0. 6 3rd Quarter 3744 < 1.4 <0.6 4th Quarter -4748 10.2 $0J Annual mean i s.d. < 1.4 <0.6 60

,,,m ,._...,.i ...m.,,,_m,...--,.,_.,--.,w-- , , _ _ , _ _ _ _ _ _ . _ . - _ _ _ _ _

I Table 26. Untreated surface water samples, quarterly composites of weekly grab samples, analysis for Sr 89 and St-90,1993 (continued).

Couection Lab Activity (oCl/L)

Location Period Code Sr-89 Sr.90 Indicator I .3 1st Quarter TSWU-1388 <1.1 <0.5 2nd Quarter -2609 <0.8 <0.6 l.

1 3rd Quarter -3739 <1.4 <0. 6 l 4th Quarter -4743 <0.7 0,710.3 i

Annual mean i s.d. < 1. 4 0.710.3 Tag ist Quarter TSWU-1391 <0. 6 <0.4 l 2nd Quarter -2613 < 1.2 <0.7 3rd Quarter -3741 < 1.6 <0.7 4th Quarter -4745 @ 0 6t0.1 Annual mean i s.d. < 1. 6 0.610.1 IdQ 1st Quarter TSWU-1392 <0. 8 <0.5 2nd Quarter -2614 < 1.1 <0.6 3rd Quarter -3699, 700 < 1.2 <0.5 4th Quarter -4~/ 4 6 SQJ <0. 5 Annual mean t s.d. < 1.2 <0.6 m

61 l

Table 21 Untreated surface lake water samples, weekly grab samples, analysis for gross beta, tritium and gamma-emitting isotopes, collected May through October,1993 Gross Beta Activity (oCi/L) Activity (oCi/L)

Lab Suspended Dissolved ~ Total Location Period Code Solids Solids Residue H-3 Cs-137 j

l T 131 (MAY) NDa .. .. .. .. ..

l (JUNE) TSWU-2132,3 <0.7 2.810.5 2.810.5 <330 <10 (JULY) -2662 <0.7 2.110.5 2.10.5 <330 <10 (AUGUST) -2942 <0.6 2.810.5 2.810.5 <330 <10 (SEPTEMBER) -3432,3 <0.7 1.910.4 1.910.4 <330 <10 (OCTOBER) NDa .. .. .. .. ..

l T-132 (MAY) NDa .. .. .. .. ..

t (JUNE) TSWU-2134 <0.7 2.810.5 2.8.t0.5 <330 <10 (JULY) - -2663 <0.7 2.210.5 2.210.5 <330 <10 (AUGUST) -2943 <0.7 2.9i0.5 2.9i0.5 <330 <10 (SEPTEMBER) -3434 <0.2 1.510.5 1.Si0.5 <330 <10-(OCTOBER)- NDa .. .. .. .. ..

T-133 (MAY) NDa .. .. .. .. ..

(JUNE) TSWU 2135 <0.7 3.0t0.6 3.0i0.6 <330 <10 (JULY) -2664 <0.4 2.110.6 2.110.6 <330 <10 (AUGUST) -2944 0.910.4 3.410.6 4.310.7 <330 <10 (SEI'TEMBER) -3435 <0.3 2.110.5 2.110.5 <330 <10 (OCTOBER) NDa .. .. .. .. ..

aND = No data; sample not available.

62

1 Table 2 7. Untreated surface lake water samples, weekly grab samples, analysis for gross beta, tritium and gamma-emitting isotopes, collected May through October,1993 (continued).

l 1

Cross Beta Activity foC1/L) Activity (oCi/L) l Lab Suspended Dissolved ' Total Location Period Code Solids Solids Residue H-3 Cs-137 l l

T-134 (MAY) NDa .. .. .. .. ..  ;

(JUNE) TSWU-2136 <0.7 3.110.5 3.110.5 <330 <10 (JULY) -2665 <0.8 2.010.6 2.010.6 <330 <10 (AUGUST) -2945 <0.7 3.210.5 3.210.5 <330 <10 i (SEPTEMBER) -3436 <0.2 1.910.5 1.910.5 <330 <10 (OCTOBER) NDa .. .. .. .. ..

T-135 (MAY) NDa .. .. .. .. ..

(JUNE) TSWU-2137 <0.7 3.010.5 3.010.5 <330 <10 (JULY) -2666 <0.7 2.410.6 2.410.6 <330 <10 (AUGUST) -2946 <0.7 3.210.6 3.210.6 <330 <10 (SEPTEMBER) -3437 <0.3 2.010.5 2.010.5 <330 <10 (OCTOBER) NDa .. .. .. .. ..

T-137 (C) (MAY) NDa .. .. .. .. ..

(JUNE) ISWU-2138 <0.3 3.310.4 3.3i0.4 <330 <10 (JULY) -2667 <0.7 1.810.5 1.810.5 <330 <10 (AUGUST) -2947 <0.6 2.7io.5 2.7io.5 <330 <10 (SEPTEMBER) -3438 <0.2 2.110.4 2.110.4 <330 <10 (OCTOBER) NDa .. .. .. .. ..

aND = No data; sample not available.

63

Table 27. Untreated surface lake water samples, weekly grab samples, analysis for gross beta, tritium and gamma-emitting isoto,r% collected May through October,1993 (continued).

Gross Beta Activity (oCi/L) Activity (oCi/L) i 1.ab Suspended Dissolved Total 1.ocation Period Code Solids Solids Residue H-3 Cs 137 T-152 (C) (MAY) NDa .. .. .. .. ..

(JUNE) TSWU 2139 <0.7 3.710.5 3.7i0.5 <330 <10 (JULY) -2669 <0.3 4.0t0.6 4.0i0.6 <330 <10 (AUGUST) -2948 <0.7 3.210.5 3.210.5 <330 <10 (SEPTEMBER) -3440 <0.3 3.010.7 3.010.7 <330 <10 1 (OCTOBER) NDa .. .. .. ..

l T-158 (C) (MAY) NDa _ .. .. .. ..

(JUNE) TSWU-2140 <0.7 2.110.6 2.110.6 <330 <10 (JULY) 2670 <0.3 1.910.5 1.9i0.5 <330 <10 (AUGUST) -2949 <0.3 2.110.5 2.110.5 <330 <10 (SEPTEMBER) -3441 <0.3 2.210.7 2.210.7 <330 <10 (OCTOBER) NDa .. .. .. .. ..

T-162 (C) (MAY) NDa .. .. .. .. ..

(JUNE) TSWU-2141 <0.3 1.7io.4 1.710.4 <330 <10 (JULY) -2671 <0.3 1.8t0.6 1.810.6 <330 <10 '

(AUGUST) -2950,1 <0.3 2.510.4 2.5to.4 <330 <10-2.li0.5 (E EPTEMBER) -3442 <0.2 2.110.5 <330 <10 (OCTOBER) NDa .. .. .. .. ..

aND = No dat.s; sample not available.

l l

1 l

I l'

64 1

1

i Table 27. Untreated surface take water samples, weekly grab samples, analysis for gross beta, tritium and gamma <mitting isotopes, collected May through October,1993 (continued).

1 Gross Beta Activity (oCi/L) Activity (oCi/L)

~

Lab Suspended Dissolved ~ Total Code Solids Solids Residue H-3 Cs 137 tocation Period ,

T-167 (C) (MAY) NDa .. .. ..

'ISWU-2142 <0.7 2.5i0.5 2.510.5 <330 <10-(JUNE) <330 <10

-2672 <0.7 2.410.6 2.410.6 (JULY) <330 <10 (AUGUST) -2952 <0.3 2.2i0.5 2.210.5

-3443 <0.2 2,310.4 2.3i0.4 <330 <10 (SEPTEMBER) ..

(OCTOBER) NDa .. ..

aND - No data: sample not available.

l f

4 i

4 1

0 l

' l i

4 a

I J

l

! 65 I

\

l

\

1 l 2

Table 2 8. Fish samples, analyses for gross beta and gamma-emitting isotopes.

Couection: Semiannuauy.

Sample Description and Activity (pCi/g wet)

Indicator - Control 4

Location T-33 (12ke Erie 1.5 mi NE of Station) T-35 ,

CoUection Date 05-28-93 05-28-93 05-28-93 05 26-93 05-26-93 05 26-93 Lab Code TF-2096 TF-2097 TF 2098 TF-2099 TF-2100 TF-2101 Sample Type WaUeye Bass Carp Waueye White Bass Carp Gross Beta 4.7510.17 2.65i0.10 3.1410.10 3.1410.10 2.3310.10 3.0010.09

K-40 2.5110.31 1.9510.34 2.6010.31 2.7410.35 1.9210.37 2.7710.33 C< 7 <0.018 <0.016 <0.012 0.01910.010 <0.020 <0.011 Location T-33 (12ke Erie 1.5 mi NE of Station) T-35 Collection Date NSa NSa NSa 11 10 93 11-10-93 11-10 93

, Lab Code -- -- --

TF-2293 TF-2294 TF 2295 4 Sample Type -- -- --

Carp Walleye White Perch Gross Beta -- -- -- 1.9610.06 4.2510.17 3.0410.11 K-40 -- -- -- 2.6210.35 3.94i0.48 '2.9810.28 Cs-137 -- -- --

<0.014 <0.019 <0.013 a NS = 'no sample avallable.

t i

4 J

a 66 1

J i

l Table 2 9. Shoreline sediment samples, analysis for gamma-emitting isotopes. I Collection: Semiannuauy.

Sample Description and Activity (pCi/g dry) l Location T-3 T-4 T-27 (C)

Collection Date 05-03-93 05-03 93 05-03-93 l Lab Code TSS-1281 TSS-1282 TSS-1284 K-40 16.34t0.72 12.7010.91 15.5010.76 Mn-54 <0.028 <0.043 <0.031 Co-58 <0.029 <0.047 <0.040 .

Co-60 <0.021 <0.059 <0.040 Cs-134 <0.012 <0.054 <0.073 Cs-137 <0.022 <0.036 <0.042 Location T-3 T-4 T-23 (C)

Collection Date 11-03-93 11-03-93 11-03-93 Lab Code TSS-1398 TSS-1399,1400 TSS-1402 K-40 14.67 0.86 14.9110.51 13.5910.65 Mn-54 <0.014 <0.012 <0.022 Co-58 <0.030 <0.024 <0.023 Co-60 <0.013 <0.030 <0.024 Cs-134 <0.030 <0.018 <0.013 l Cs-137 <0.025 0.046t0.017 0.06710.021 l

Location T-27 (C) l Collection Date 11-03-93 Lab Code TSS-1403 l K-40 13.7310.74 Mn-54 <0.018 ,

Co-58 <0.012 Co-60 <0.017 Cs-134 <0.049 Cs-137 <0.024 67

Table 29. Shoreline sediment samples, analysis for gamma-emitting isotopes (continued).

Sample Description and Activity (pCi/g dry)

Location T-4 T-23 (C) T-132 l Collection Date 06-10-93 06-10-93 06 10-93 Lab Code TSS-1306 TSS 1307 TSS-1308 K-40 20.67 0.89 19.3310.81 12.2310.49 Mn-54 <0.026 <0.019 <0.011 Co-58 <0.023 <0.027 <0.015

, Co-60 <0.030 <0.016 <0.005 l Cs-134 <0.010 <0.011 <0.014 Cs-137 0.1710.03 0.3510.04 0.01710.010 l

Location T-138 (C) T 164 (C) T-4

, Collection Date 06-10 93 06-10-93 09-22 93 12b Code TSS-1309 TSS-1310 TSS-1336,7 K-40 31.27il.39 14.0810.55 19.3410.91 Mn 54 <0.063 <0.007 <0.036 Co-58 <0.074 <0.013 <0.038 Co-60 <0.042 <0.011 <0.038 Cs-134 <0.13 <0.016 <0.064 Cs-137 0.8610.07 0.04810.020 0.2810.08 Location T-132 T-138 T-164 Collection Date 09-22-93 09-22-93 09-22 93 lab Code TSS-1338 TSS-1339 TSS-1340 K 40 11.8010.50 25.5111.59 14.6010.70 Mn-54 <0.016 <0.052 <0.019 Co-58 <0.016 <0.053 <0.012 Co-60 <0.021 <0.053 <0.010 Cs-134 <0.013 <0.048 <0.010 Cs-137 <0.017 0.4910.07 0.06210.023 l

68 I

4 I

Table 30. Egg samples, analysis for gamnu-emitting isotopes.

Collection: Annually.

Sample Description and Activity (pCi/g wet)-

Location T-34 T-197 ,

Date 07 13-93 07-15-93 LabCode TE-74 TE-75 l

K-40 1.4110.15 1.1410.16 I Nb-95 <0.005 <0.005 Zr-95 <0.010 <0.007  !

Ru 103 <0.006 <0.004 I Ru 106 <0.054 <0.020 Cs-137 <0.005 <0.005  ;

Ce-141 <0.011 <0.010 l Ce 144 <0.047 <0.034 69

i Appendix: 1

)

Elevated LLDs in Airborne Iodine Samples t

Date I-131 Collected Location pCi/m3 Comments 11-03-93 T-4 <0.10 Due to low volume of 33 m3, A-1