NRC-08-0031, Fermi 2- 2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report for the Period of January 1, 2007 Through December 31, 2007

Fermi 2- 2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report for the Period of January 1, 2007 Through December 31, 2007

ML081220233
Person / Time
Site:	Fermi
Issue date:	04/24/2008
From:	DTE Energy
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209, NRC-08-0031
Download: ML081220233 (200)

Text

FERMI 2. NUCLEAR POWER PLANT DETROIT EDISON COMPANY OPERATING LICENSE NO. NPF -43 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report for the period of January 1, 2007 through December 31, 2007 Prepared by: Fermi 2 Radiological Engineering Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Table of Contents Page Executive Summary 1 Introduction 2 Noble Gases 2 Iodines and Particulates 2 Tritium 3 Plant Effluent Monitoring 3 Exposure Pathways to People 4 Dose Assessment 5 Preoperational Surveillance Program 6 Operational Surveillance Program Objectives 7 Program Overview 7 Sample Analysis 8 Quality Assurance 10 Radioactive Effluent Monitoring Results 12 Radiological Environmental Monitoring Program Results .17 Direct Radiation Monitoring 17 Thermoluminescent Dosimeters 17 Atmospheric Monitoring 18 Air Sampling 19 Terrestrial Monitoring 21 Milk Sampling 21 Groundwater Sampling 22 Garden Sampling 23 Aquatic Monitoring 24 Drinking Water Sampling 24 Surface Water Sampling 26 Sediment Sampling 27 Fish Sampling 29 Land Use Census 31 2007 Land Use Census Results 32 Appendix A Sampling Locations A-]Appendix B Environmental Data Summary B-1 ii Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Table of Contents Page Appendix C Environmental Data Tables C-1 Appendix D Environmental Program Execution D-1 Direct Radiation Monitoring D-1 Atmospheric Monitoring D-1 Terrestrial Monitoring D-1 Milk Sampling D-1 Garden Sampling D-2 Groundwater Sampling D-2 Aquatic Monitoring D-2 Drinking Water Sampling D-2 Surface Water Sampling D-2 Sediment Sampling D-2 Fish Sampling D-2 Appendix E Effluent and Radwaste Data Regulatory Limits for Radioactive Effluents E-1 Gaseous Effluents E-1 Liquid Effluents E-2 Measurements and Approximations of Total Activity in Radioactive Effluents E-3 Gaseous Effluents E-3 Fission and Activation Gases E-3 Radioiodines E-3 Particulates E-4 Tritium E-4 Gross Alpha E-5 Liquid Effluents E-5 Statistical Measurement Uncertainties E-5 iii Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Table of Contents Page Gaseous Release by Individual Nuclide E-5 Particulate Radionuclides (Curies) E-6 Noble Gases (Curies) E-6 Radioiodines (Curies) E- 7 Shipments of Radwaste E-7 Class A Resin E-8 Class B Resin E-8 Class C Resin E-9 Dry compressible waste, contaminated equipment, etc. E-9 Irradiated components, control rods, etc. E-9 Other E-9 Appendix F Interlaboratory Comparison Data, Framatome ANP Environmental Laboratory's Quality Assurance Programs Interlaboratory Comparison Program for 2007 F-1 Appendix G Meteorological Data G-1 Appendix H Offsite Dose Calculation Manual for 2007 Revisions H-I iv Fermi 2 -2007Annual Radioactive Effluent Release and-Radiological Environmental Operating Report List of Figures Page Figure 1 Fermi 2 Annual Average TLD Gamma Exposure 18 Figure 2 Historical Gross Beta and Iodine-131 Activity in Air Samples 20 Figure 3 Fermi 2 Air Particulate Gross Beta for 2007 20 Figure 4 Historical Strontium-90 Activity in Local Milk Samples 22 Figure 5 Historical Gross Beta Activity in Drinking Water Samples 26 Figure 6 Historical Cesium-13 7 Activity in Sediment Samples 29 Map 1 Sampling Locations By Station Number (within 1 mile) App.-A Map 2 Sampling Locations By Station Number (1 to 5 miles) App. -A Map 3 Sampling Locations By Station Number (greater than 5 miles) App.-A V Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report List of Tables Page Table 1 Fission and Activation Gases (Noble Gases). Summary 12 Table 2 Radioiodines Summary 13 Table 3 Particulates Summary 13 Table 4 Tritium Summary 13 Table 5 2007 Gaseous Effluent Dose to Receptor with Highest Single Organ Dose 14 Table 6 Solid Waste Received at Burial Sites 15 Table 7 Solid Waste Shipments 15 Table 8 2007 Average Gross Beta Concentrations in Air Particulates 19 Table 9 Closest Residences 33 Table 10 Closest Gardens 34 Table 11 Milk Locations 35 Table 12 Closest Meat Locations 36 Table A-1 Direct Radiation Sample Locations A-I Table A-2 Air Particulate and Air Iodine Sample Locations A-7 Table A-3 Milk Sample Locations A-7 Table A-4 Garden Sample Locations A-8 Table A-5 Drinking Water Sample Locations A-8 Table A-6 Surface Water Sample Locations A-9 Table A-7 Groundwater Sample Locations A-9 Table A-8 Sediment Sample Locations A-1O Table A-9 Fish Sample Locations A-10 Table B-i Radiological Environmental Monitoring Program Summary B-i Vi Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Executive Summary This report is published to provide information regarding radioactive effluent and environmental monitoring at the Fermi 2 Nuclear Power Plant. The 2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report covers the period from January 1, 2007 through December 31, 2007.The Radioactive Effluent Release and Radiological Environmental Operating Report is produced annually, as required by the Nuclear Regulatory Commission, to present detailed results of extensive monitoring of plant releases and measuring of radiation in the environment around the plant. This report also includes details of the independent oversight incorporated into the Radiological Effluent and Environmental Monitoring Programs to ensure program accuracy.This report describes both the continual environmental radiation monitoring and effluent monitoring of plant systems. Both types of monitoring indicate that the operation of Fermi 2 does not result in significant radiation exposure of people or the environment surrounding Fermi 2 and is well below the applicable levels set by the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).There were no releases of liquid radioactive effluents from Fermi 2 in 2007. In fact, there has not been a liquid radioactive discharge from Fermi 2 since 1994.The highest potential single organ dose to a person living offsite due to iodines, particulates, and tritium released from the plant was calculated to be 0.08 mrem, which is 0.5% of the applicable limit found in 10 CFR 50, Appendix I.Also during 2007, there was no measurable direct radiation dose due to Fermi 2 beyond the site boundary as shown by offsite thermoluminescent dosimeters (TLD) readings.

The offsite dose due to effluents is an extremely small fraction of the 40 CFR 190 limits.Therefore, the combined direct radiation and effluent dose due to Fermi 2 was in compliance with 40 CFR 190 in 2007.Radiological Environmental Monitoring Program samples collected in 2007 showed no radioactivity attributable to the 6peration of Fermi 2. The results of this sampling show thatradioactivity levels have not increased from the background radioactivity detected prior to the operation of Fermi 2. The operation of Fermi 2 continues to have no measurable radiological impact upon the environment outside the Fermi 2 Protected Area.1 Fermi 2 -2007 Annual.Radioactive Effluent Release and Radiological Environmental Operating Report Introduction During the normal operation of a nuclear power plant, most of the fission products are retained within the fuel and fuel cladding.

However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces which have been activated are present in the primary coolant water. The four types of radioactive material released are noble gases, iodine, particulates, and tritium.Noble Gases Some of the fission products released in airborne effluents are radioactive radionuclides of noble gases, such as xenon and krypton. These noble gases are released continuously at low levels while the reactor is operating, and releases may be increased when the reactor is depressurized or when there are leaks in the fuel cladding.

Noble gas releases to the environment are reduced by plant systems which delay release of these gases from the plant, which allows a portion of the noble gas activity to decay within plant systems after it is released from the fuel.Noble gases are biologically and chemically nonreactive.

They do not concentrate in humans or other organisms.

They contribute to human radiation dose by being an external source of radiation exposure to the body. They are readily dispersed in the atmosphere.

Iodines and Particulates Fermi 2 is required to calculate offsite dose due to releases of iodine-131 and iodine-133, which are radioisotopes of iodine with half lives of 8 days and 1 day, respectively, and particulates with half-lives greater than 8 days in gaseous and liquid effluents, and tritium.The principal radioactive particulates released are fission products (e.g., yttrium-91 m and barium-139) and activation products (e.g., cobalt-58 and cobalt-60).

Annual releases of these radionuclides are small. Factors such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing and radwaste systems, minimize their discharge.

2 Fermi 2 -2007 Annual Radioactive.Effluent Release and.Radiological Environmental Operating Report The main contribution of radioactive iodine to human radiation dose is to the thyroid gland, where the body concentrates iodine. This exposure results from inhalation or ingestion of these iodines. Radioactive cesiums and cobalts, when ingested or inhaled, contribute to radiation exposure of tissues such as the muscle, liver, and intestines.

These iodines and particulates are also a source of external radiation exposure if deposited on the ground.Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in radioactive liquid effluents.

Fermi 2 has not conducted liquid radiological waste discharges since 1994. It is also the predominant radionuclide in gaseous effluents, and is detected at Fermi 2 in ventilation exhaust samples. Plant personnel are also alert for evidence of unmonitored tritium releases, but no such releases have been detected.

Tritium is produced in the reactor coolant as a result of neutron interaction with deuterium (also a hydrogen isotope) present in the water, and it is also a fission product.Plant Effluent Monitoring Effluents are strictly monitored to ensure that radioactivity released to the environment is as low as reasonably achievable and does not exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance programs for effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring.

The radioactive waste treatment systems at Fermi 2 are designed to collect, process, and/or delay the release of liquid and gaseous wastes which contain radioactivity.

For example, the 2.0 and 2.2 minute holdup pipes delay the release of radioactive gases so that radioactive decay can occur prior to release. The offgas system provides additional delay for such gases.Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits. These instruments provide a continuous indication of the radioactivity present at the release points. Each instrument is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure that applicable limits will not be exceeded.

In some cases, these alarms restrict the release. For example, if the liquid radwaste effluent monitor alarms, a release in progress is automatically stopped. Also, several alarms cause building ventilation systems to be shut down and/or gaseous releases to be diverted to the standby gas treatment system.3 Fermi 2 -2007 Annual.. Radioactive Effluent Release. and.Radiological Environmental Operating Report All wastes are evaluated to identify the specific concentrations of radionuclides being released.

Sampling and analysis provide a more sensitive and precise method of determining effluent composition than monitoring instruments.

A meteorological tower is located on the Fermi 2 site. It is linked to computers which record the meteorological data. This data is used in calculating dispersion and deposition factors, which are essentially dilution factors between plant release points and points offsite. Coupled with the effluent release data, these factors are used to calculate dose to the public.Beyond the plant, devices maintained in conjunction with the Radiological Environmental Monitoring Program constantly sample the air in the surrounding environment.

Frequent samples of other environmental media, such as water and vegetation, are also taken to determine if buildup of deposited radioactive material has occurred in the area.Exposure Pathways to People Radiological exposure pathways define the methods by which people may become exposed to radioactive material.

The major pathways of concern are those which could cause the highest calculated radiation dose. These projected pathways are determined from the type and amount of radioactive material released, the environmental transport mechanism, and the use of the environment.

The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area.An important factor in evaluating the exposure pathways is the use of the environment.

This is evaluated in the annual Land Use Census. Many factors are considered, such as the locations of homes, gardens, and milk or meat animals in the area.The release of radioactive gaseous effluents involves pathways such as external whole body exposure, deposition of radioactive material on plants, deposition on soil, inhalation and ingestion by animals raised for human consumption, and inhalation by humans. The release of radioactive material in liquid effluents involves pathways such as drinking water and fish consumption.

4 Fermi 2 -2007 Annual Radioactive Effluent Release. and Radiological Environmental Operating Report Although radionuclides can reach humans by many different pathways, some result in greater dose than others. The most significant pathway is the exposure pathway which will provide the greatest dose to a population, or to a specific individual.

Identification of the most significant pathway depends on the radionuclides involved, the age and diet of the individual, and the location of the individual's residence.

The doses calculated may be delivered to the whole body or to a specific organ. The organ receiving the greatest fraction of the dose is important in determining compliance with dose limits.Dose Assessment Dose is energy deposited by radiation in anexposed individual.

Whole body exposure to radiation involves the exposure of all organs. Most exposures due to external sources of radiation are of this type. Both non-radioactive and radioactive elements can enter the body through inhalation or ingestion.

When they do, they are usually not distributed evenly. For example, iodine concentrates in the thyroid gland, cesium collects in muscle and liver tissue, and strontium collects in bone tissue.The 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. Also the form of the radionuclide (soluble vs. insoluble) and the method of uptake also influence residence times in the body.The dose to the general public in the area surrounding Fermi 2 is calculated for periods of gaseous release and for each liquid release. The dose due to radioactive material released in gaseous effluents is calculated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, the locations of exposure pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inhalation and food consumption).

The 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).

These calculations produce a conservative estimation of the dose.The Radiological Environmental Monitoring Program (REMP) was established at Fermi 2 for several reasons: to provide a supplementary check on the effluent controls, to assess the radiological impact of the plant's operation on the surrounding area, and to determine compliance with applicable radiation protection guides and standards.

The REMP was established in 1978, seven years before the plant became operational.

This preoperational surveillance program was established to describe and quantify the 5 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report radioactivity, and its variability, in the area prior to the operation of Fermi 2. After Fermi 2 became operational in 1985, the operational surveillance program continued to measure radiation and radioactivity in the surrounding areas. -....A variety of environmental samples are collected as part of the REMP at Fermi 2. The selection of sample types is based on the established pathways for the transfer of radionuclides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population characteristics, and land usage in the area of interest.

The selection of sampling frequencies for the various environmental media is based on the radionuclides of interest, their respective half-lives, and their behavior in both the biological and physical environment.

Preoperational Surveillance Program The federal government requires nuclear facilities to conduct radiological environmental monitoring prior to constructing the facility.

This preoperational surveillance program is aimed at collecting the data needed to identify pathways, including selection of the radioisotope and sample media combinations to be included in the environmental surveillance program conducted after facility operation begins. Radiochemicalanalyses performed on the environmental samples should include not only those nuclides expected to be released during facility operation, but should also include typical radionuclides from nuclear weapons testing and natural background radioactivity.

All environmental media with a potential to be affected by facility operation, as well as those media directly in the major pathways, should be sampled on at least an annual basis during the preoperational phase of the environmental surveillance program.The preoperational surveillance design, including nuclide/media combinations, sampling frequencies and locations, collection techniques, and radioanalyses performed, should be carefully considered and incorporated in the design of the operational surveillance program. In this manner, data can be compared in a variety of ways (for example, from year to year, location to location, etc.) in order to detect any radiological impact the facility has on the surrounding environment.

Data collection during the preoperational phase should be planned to provide a comprehensive database for evaluating any future changes in the environment surrounding the nuclear facility.6 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Fermi 2 began its preoperational environmental surveillance program seven years before the plant began operating in 1985. Data accumulated during those early years provide an extensive database from which environmental monitoring personnel are able to identify trends in the radiological characteristics of the local environment.

The environmental surveillance program at Fermi 2 will continue after the plant has reached the end of its economically useful life and decommissioning has begun.Operational Surveillance Program Objectives The operational phase of the environmental surveillance program at Fermi 2 was designed with the following objectives in mind:* to determine whether any significant increase occurs in the concentration of radionuclides in major pathways;* 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 the plant's controls for the release of radioactive materials;

• to fulfill the obligations of the radiological surveillance sections of Fermi 2's Offsite Dose Calculation Manual.Program Overview The Radiological Environmental Monitoring Program (REMP) at Fermi 2 is conducted in accordance with Title 10, Code of Federal Regulations, Part 50; NRC Regulatory Guide 4.8; the Fermi 2 Offsite Dose Calculation Manual (ODCM); and plant operating procedures.

Samples are collected either weekly, monthly, quarterly, semiannually, or annually, depending upon the sample type and nature of the radionuclides of interest.Environmental samples collected by Fermi 2 personnel are divided into four general types: 7 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report" direct radiation

-- measured by thermoluminescent dosimeters (TLDs).* atmospheric

-- including samples of airborne particulates and airborne radioiodine.

terrestrial

-- including samples of milk, groundwater, and broad leaf vegetation.

aquatic -- including samples of drinking water, surface water, fish, and shoreline and bottom sediments.

REMP samples are collected onsite and offsite up to 20 miles away from the plant.Sampling locations are 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 Fermi 2. Generally, they are located within ten miles of the plant.Control locations are those which should be unaffected by plant operations.

Typically, these are -more than ten miles away from the plant. Data obtained from the indicator locations are compared with data from the control locations.

This comparison allows REMP personnel to take into account naturally occurring background radiation or fallout from weapons testing in evaluating any radiological impact Fermi 2 has on the surrounding environment.

Data from indicator and control locations are also compared with preoperational data to determine whether significant variations or trends exist.Sample Analysis When environmental samples are analyzed, several types of measurements may be performed to provide information about the radionuclides present. The major analyses that are performed on environmental samples collected for the Fermi 2 REMP include: Gross beta analysis measures the total amount of beta emitting radioactive material present in a sample. Beta radiation may be released by many different radionuclides.

Since beta decay gives a continuous energy spectrum rather than the discrete lines or"peaks" associated with gamma radiation, identification of specific beta emitting nuclides is much more difficult.

Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal concentrations of beta emitting radionuclides; it does not identify specific radionuclides.

Gross beta analysis merely acts as a tool to identify samples that may require further analysis.8 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Gamma spectral analysis provides more specific information than does gross beta analysis.

Gamma spectral analysis identifies 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, or routine releases from nuclear power stations.Tritium analysis indicates whether a sample contains the radionuclide tritium (H-3) and the amount present. Tritium is an isotope of hydrogen that emits low energy beta particles.

Strontium analysis identifies the presence and amount of strontium-89 and strontium-90 in a sample. These man-made radionuclides are found in the environment mainly as a result of fallout from nuclear weapons testing. Strontium is usually incorporated into the calcium pool of the biosphere.

In other words, strontium tends to replace calcium in living organisms and becomes incorporated in bone tissue. The principle strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition from airborne releases.Gamma Doses measured by thermoluminescent dosimeters while in the field are determined by a special laboratory procedure.

Often samples will contain little radioactivity, and may be below the lower limit of detection for the particular type of analysis used. The lower limit of detection (LLD) is the smallest amount of sample activity which can be detected with a reasonable degree of confidence, at a predetermined level. When a measurement of radioactivity is reported as less than LLD (<LLD), it means that the radioactivity is so low that it cannot be accurately measured with any degree of confidence by that particular method for an individual analysis.Many radionuclides are present in the environment due to sources such as cosmic radiation and fallout from nuclear weapons testing. Some of the radionuclides present are:* tritium, present as a result of the interaction of cosmic radiation with the upper atmosphere, as a result of routine release from nuclear facilities, and due to fallout from past atmospheric nuclear weapons testing.* beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere.

Q Fermi 2 -2007Annual Radioactive Effluent Release and..Radiological Environmental Operating Report" cesium-137, a man-made radionuclide which has been deposited in the environment, (for example, in surface soils) as a result of fallout from nuclear weapons testing and routine releases from nuclear facilities.

• potassium-40, a naturally occurring radionuclide normally found throughout the environment (including humans)." fallout radionuclides from nuclear weapons testing, including strontium-89, strontium-90, cesium- 137, cerium- 141, cerium-144, and ruthenium-106.

These radionuclides may also be released in minute amounts from nuclear facilities.

The radionuclides listed above are expected to be present in many of the environmental samples collected in the vicinity of the Fermi 2. The contribution of radionuclides from the operation of Fermi 2 is assessed by comparing sample results with preoperational data, operational data from previous years, control location data, and the types and amounts of radioactivity normally released from the Fermi 2 in liquid and gaseous effluents.

Qualitý Assurance An important part of the environmental monitoring program at Fermi 2 is the Quality Assurance (QA) program. It 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.

Fermi 2's Quality Assurance program also provides confidence in the results of the REMP through:* performing regular audits of the REMP, including a careful examination of sample collection techniques and record keeping;* performing audits of the vendor laboratory which analyzes the environmental samples;* requiring the analytical vendor laboratory to participate in an approved Cross-Check Program;10 Fermi 2 -2007 Annual.Radioactive Effluent Release and Radiological Environmental Operating Report* splitting samples prior to analysis by an. independent laboratory and then comparing the results for agreement, and finally;* requiring the analytical laboratory to perform in-house spiked sample analyses.11 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Radioactive Effluent Monitoring Results This section summarizes the results of effluent monitoring and offsite dose calculation for the year 2007, as well as a listing of radioactivity contained in Fermi 2 waste shipped for burial. Calculated offsite doses are compared with Nuclear Regulatory Commission limits, and these limits are summarized in Appendix E. Appendix E also contains a detailed discussion of the methods used to determine quantities of radioactivity released in effluents, the types of solid radwaste, as well as tables of individual radionuclides released in effluents and shipped as solid radwaste.There were no releases of liquid radioactive effluents from Fermi 2 in 2007. In fact, there has not been a liquid radioactive discharge from Fermi 2 since 1994. The 2007 gaseous.effluent releases are summarized in the following tables. There were no abnormal releases of radioactive material, i.e., releases not performed in accordance with the Fermi 2 license and implementing procedures, in 2007.The data in the following tables represent continuous and batch releases.

In 2007, there were 10 containment purges in which radioactivity was detected.

The total time for these purges was 6712 minutes. Based on recorded start and stop times, the shortest of these purges lasted 116 minutes, the longest lasted 1813 minutes, and the average purge length was 671 minutes.Note that some values in the following summary tables are preceded by the "less than" symbol. For noble gases, these values represent the sum of the lower limit of detection (LLD) values for 6 common noble gases isotopes listed in Appendix E in units of microcuries per cubic centimeter (pgCi/cc).

For gross alpha radioactivity releases, the "less than" value is in units of microcuries per cubic centimeter (gCilcc) and represents the LLD value for a single sample.Table 1 -Fission and Activation Gases (Noble Gases) Summary____________

Ouarteri I Quarter 21 Quarter&3

~ Quarter 4 Release (curies) <3.8E-05 <3.8E-05 <3.8E-05 <3.8E-05 Average Release NA NA NA NA Rate for Period (ýtCi/sec) 12 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Table 2 -Radioiodines Summary________________

.Quarterd I, Quarter 2 ,Quarter 3 Qua..'er 4 Total 1- 131 4.48E-04 5.26E-04 6.66E-04 1.05E-03 (curies)Average Release 5.69E-05 6.68E-05 8.46E-05 1.33E-04 Rate for Period (gCi/sec)Table 3 -Particulates Summary/ quLarter I ()Quaoter 2 Quarter 3 ~Qjarteir 4 Particulates with 2.17E-04 4.63E-05 1.51E-04 7.43E-04 half lives > 8 days (curies)Average 2.76E-05 5.88E-06 1.92E-05 9.44E-05 Release Rate for Period (gCi/sec)Gross Alpha 1.47E-07 <5.5E- 15 <5.5E- 15 <5.5E- 15 Radioactivity (curies)Table 4 -Tritium Summary___________ -ulartert I 0Q4arter 2 Quarter 3 Quarter 4 Total Release 3.5 1E+O1 3.35E+01 4.07E+01 1.53E+01 (curies)Average Release 4.46E+00 4.25E+00 5.17E+00 1.94E+00 Rate for Period (gCi/sec)

I The offsite dose impact of the above releases was evaluated by calculating organ doses to the most highly exposed individual living near the plant due to 1-131, 1-133, tritium, and particulates with half lives greater than 8 days. This exposure is assumed to be occurring via the pathways of inhalation, vegetation ingestion, and direct radiation from material deposited on the ground. The results of this calculation are shown in the following table: 13 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Table 5 2007, Gaseou Effluent Dose toi~Organ Receptor with Highest Sin~gleOrjgan B8.45E-03 mrem Liter ,,,,,,. 1.64E-02 mrem Thyroid 7.58E-02 mrem Kidney 1.64E-02 mrem Lung 1.62E-02 mrem I1.64E-02 mrem Total body 1.76E-02 mrem The highest single organ dose is 7.58E-02 mrem to the thyroid. This is 0.5% of the federal limit of 15 mrem specified in 10 CFR 50, Appendix I.Another dose calculation normally performed on the above release data is that for gamma and beta air dose at the site boundary due to noble gases. In 2007, noble gases were not detected in Fermi noble gas effluent samples.Title 40, Part 190 of the Code of Federal Regulations requires that dose to an individual in the unrestricted area from the uranium fuel cycle, including direct radiation dose, be limited to 25 mrem/year to the total body and 75 mrem/year to the thyroid. During 2007, there was no measurable direct radiation dose beyond the site boundary as shown by offsite TLD readings.

Also, offsite dose due to effluents is an extremely small fraction of the 40 CFR 190 limits. Therefore, Fermi 2 was in compliance with 40 CFR 190 in 2007.Potential dose to visitors at Fermi 2 due to all radioactive effluents, including noble gases, was also calculated.

The Offsite Dose Calculation Manual (ODCM) considers persons visiting the Fermi 2 Visitors Center (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s/year), and persons ice fishing on Lake Erie near the plant (240 hour0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />s/year), to be visitors.

Using ODCM assumptions about these categories of visitors, the maximum potential dose to a visitor to Fermi 2 in 2007 was 0.0029 mrem to the maximally exposed organ (thyroid) and 0.0020 mrem to the total body.Also, the dose to the entire population within a fifty mile radius of Fermi 2 (about 6 million people) was calculated.

This dose was estimated to be less than one person-rem for 2007. This dose is insignificant compared to the background radiation dose to this population of approximately 1.8 million person-rem (based on an annual average individual background dose of 300 mrem).14 Fermi 2 -2007 Annual Radioactive Effluent Releaseand.

Radiological Environmental Operating Report The radioactivity and volume of Fermi 2 solid waste received at the Barnwell, SC, burial facility, or at the Clive, UT, facility in 2007 is summarized in the following table: Spent resins, sludges, etc.me curies 3.60E+01 9.4 1E+/-02+/- 25 Dry compressible waste, m 3 7.28E+01 contaminated equipment, etc. curies 1.11 E+00 +/- 25 Irradiated components, control m 3 0 rods, etc. curies 0 NA Other m 3 0 curies 0 NA Radioactive solid waste shipments from Fermi 2 in 2007 (to either disposal or to intermediate processors) are summarized in the following table: Tnhip- 7 -Sqnld WA~tL ,hinnointz tractor trailer with cask, and rail_nem iNuclear, tsarnweu, st5 Duratek, Oak Ridge, TN Dry compressible waste, 22 tractor trailer Duratek, Oak Ridge, TN contaminated equipment, etc. Envirocare, Clive, UT Used oil 0 NA NA Mixed waste 0 NA NA The ODCM was revised twice in 2007. A complete copy of the current revision is included as Appendix H.The OSSF SPING gaseous effluent monitor was out of service from 9/30/07 to 11/13/07 due to its being on temporary power during a refueling outage. This SPING was otherwise functional and the alternate method of effluent sampling at the OSSF stack was in effect throughout this period. Also, the liquid radwaste effluent monitor has been out of service since March 2007. It is awaiting a preventive maintenance procedure which has been delayed due to the lack of a required radioactive source; performance of this procedure is scheduled for April 2008. There has been no impact due to this condition since there have been no liquid radioactive discharges at Fermi 2 since 1994; if such a 15 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report discharge became necessary, the ODCM provides an alternate method which does not involve this monitor.No outside temporary tank exceeded the 10 curie content limit (excluding tritium and dissolved or entrained noble gases) in 2007. Also, there were no major changes to radioactive waste systems placed in service in 2007; however a new radwaste evaporator has been installed and is currently being tested.16 Fermi 2 -2007 Annual Radioactive Effluent Release. and Radiological Environmental Operating Report Radiological Environmental Monitoring Program Results Direct Radiation Monitoring Radiation is a normal component of the environment resulting primarily from natural sources, such as cosmic radiation and naturally occurring radionuclides; and to a lesser extent, from manmade sources such as fallout from past nuclear weapons testing. The earth is constantly bombarded by cosmic radiation in the form of high energy gamma rays and particulates.

The earth's crust also contains natural radioactive material, such as uranium and potassium-40, which contributes to the background radiation.

Direct radiation monitoring primarily measures ionizing radiation from cosmic and terrestrial sources.Thermoluminescent Dosimeters Detroit Edison uses thermoluminescent dosimeters (TLDs) to measure direct gamma radiation in the environs of Fermi 2. In this process, ionizing radiation interacts with a phosphor which is the sensitive material in the TLD. Energy is trapped in the TLD material and can be stored for several months or years. This provides an excellent method to measure the dose received over long periods of time. The energy that was stored in the TLD as a result of interaction with radiation is released and measured by a controlled heating process in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy in the form of light. The amount of light detected is directly proportional to the amount of radiation to which the TLD was exposed. This reading process then rezeros the TLD and prepares it for reuse.Fermi 2 has 67 TLD locations within a fifteen mile radius of the plant. Of the 67 TLD locations, 16 are located on-site and are not used for comparison with the control locations.

These 16 TLDs are affected by Hydrogen Water Chemistry's sky shine and are not representative of off-site dose. The TLDs are thoroughly tested to comply with NRC Regulatory Guide 4.13 and American National Standards Institute's (ANSI) publication N545-1975, which assure accurate measurements under varying environmental conditions before being placed in the field. Indicator TLDs are located within a ten mile radius of the plant and control TLDs are located at a distance that is outside the influence of the plant.While in the field, TLDs are exposed to background radiation and, if measurable, gaseous effluents and direct radiation from Fermi 2. Environmental TLDs are exchanged and processed on a quarterly basis. The TLDs' data are reported in terms of milliroentgen per standard quarter (mR/std qtr), with a standard quarter being 91 days. Regardless of the duration of TLD exposure in the field, the data have been normalized to a standard quarter to allow convenient intercomparisons with the net value.17 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report In 2007, the average exposure for TLDs at all off-site indicator locations was 14.6 mR/std qtr and for all control locations was 13.7 mR/std qtr. These exposures are consistent with preoperational and past operational measurements as shown in Figure 1.Fermi 2 Annual Average TLD Gamma Exposure 25 20~15~10 E Preoperational Operational 5 0~~~' C'0 C:,( 0 '](C- -,j (0r (0 ( 0 ' )0' 0'. 0' >-~~0 -----C>. C>.. C>. C>.---- Indicator

--a--Control Figure 1 -Fermi 2 Annual Average TLD Gamma Exposure:

The similarity between indicator and control results demonstrates that the operation of Fermi 2 has not caused any abnormal gamma exposure.Atmospheric Monitoring A potential exposure pathway to people is inhalation of airborne radioactive materials.

Detroit Edison continuously samples the ambient air surrounding Fermi 2 for radioactivity.

Air sampling began in 1979 during the preoperational program. At each sampling location, a mechanical air sampler is used to draw a continuous volume of air through two filters designed to collect particulates and radioiodines.

Air samples are collected weekly and analyzed for gross beta radiation and iodine- 131 gamma radiation.

The particulate filters for each sampling location are combined on a quarterly basis to form a "composite sample" and are analyzed for gamma emitting radionuclides.

There are four indicator sampling locations which were selected based on an evaluation of the predominant wind directions.

A fifth sampling location is approximately fourteen miles west of the plant and is considered to be in a location unaffected by the operation of the plant. This is used as the control location.18 Fermi 2 -2007Annual Radioactive Effluent Release and-Radiological Environmental Operating Report Air Sampling On October 16, 1980, the People's Republic of China-conducted an atmospheric nuclear weapon test. The fallout from this test was detected in Fermi 2 preoperational environmental air samples in 1981 (see Figure 2). The average gross beta for 1981 was 1.60E-1 pCi/cubic meter for indicator samples and 2.40E-l pCi/cubic meter for control samples which was a factor often times greater than background gross beta. Gamma spectroscopic analyses of the particulate filters indicated cesium- 137, cerium-141, cerium-144, ruthenium-103, ruthenium-106, zirconium-95, niobium-95, manganese-54, and antimony-125 in the atmosphere as a result of this test. In 1986, as shown in Figure 2, there was a slight increase in gross beta activity and a 2.70E-1 pCi/cubic meter "spike" in the iodine- 131 activity.

These elevated levels in 1986 are attributed to the. nuclear accident at Chernobyl on April 26, 1986. For all other years, the iodine- 131 activity was below the lower limit of detection (LLD) of 7.OE-2 pCi/cubic meter.During 2007, two hundred and sixty (260) particulate air filters and charcoal cartridges were collected and analyzed for gross beta activity and iodine-131 respectively.

The average gross beta for indicator samples was 2.70E-2 pCi/cubic meter and 2.93E-2 pCi/cubic meter for control samples. None of the charcoal filters collected showed detectable levels of iodine- 131. The following table contains the annual average gross*beta results of all five sample locations for 2007.2007 Average Gross Beta Concentrations in Air Particulates (pCi/m 3)Table 8 S tationt Wfl csiip/ion

({sctr/distance)

Aimt age API-1 (I) Estral Beach (NE/1.4 mi.) 2.44E-2 API-2 (I) Site Boundary (NNW/0.6 mi.) 3.22E-2 API-3 (I) Site Boundary (NW/0.6 mi.) 2.82E-2 API-4 (C) North Custer Rd. (W/14 mi.) 2.93E-2 API-5 (I) Site Boundary (S/1.2 mi.) 2.31E-2 (I) = Indicator Station (C) = Control Station Twenty (20) quarterly particulate filter composites were prepared and analyzed for gamma emitting radionuclides.

Naturally occurring beryllium-7 was detected in both indicator and control samples. One indicator sample detected naturally occurring potassium-40.

19 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report In conclusion, the atmospheric monitoring data are consistent with preoperational and prior operational data and show no adverse long-term trends in the environment attributable to operation of Fermi 2 as illustrated in Figures 2 and 3.Historical Gross Beta and Iodine -131 Activty in Air Samples E.2Q C-3.E-01 3.E-01 2.E-01 2.E-01 I.E-Ol Chernobyl Event Chinese Weapon Test 1-131 O.E+O0 M) -o O r- M) M Ct) r- M) CO) C) r-P- co ) C ) C 00 00 CO M) M) M M C) CD 01--o- Indicator Gross Beta - Control Gross Beta -Iodine -131 1 Figure 2 -Historical Gross Beta and Iodine-131 Activity in Air Samples; The similarity between indicator and control gross beta results demonstrates that the operation of Fermi 2 has had no adverse long-term trends in the environment.

The lower limit of detection (LLD)for iodine-131 is 0.07 pCi/cubic meter.Fermi 2 Air Particulate Gross Beta for 2007 a)E U 0.7.E-02 6.E-02 5.E-02 4.E-02 3.E-02 2.E-02 1.E-02 0.E+00 C C ~ ~ L C;. l> , 6 C 0 DC a Collection Date I---Indicator ControlI 99 >~D C) -C-Figure 3 -Fermi 2 Air Particulate Gross Beta for 2007; the concentration of beta emitting radionuclides in airborne particulates samples was essentially identical at indicator and control locations.

Gross beta activity varies throughout the year and is primarily an effect of seasonal precipitation.

20 Fermi 2 -2007 Annual Radioactive Effluent Release and.Radiological Environmental Operating Report Terrestrial Monitoring Radionuclides released to the atmosphere may deposit on soil and vegetation, and therefore, may eventually be incorporated into the human food chain. To assess the impact of Fermi 2 operations to humans from the ingestion pathway, samples of milk, green leafy vegetables, and groundwater are collected and analyzed for radioactivity.

The following sections discuss the type and frequency of terrestrial sampling, analyses performed, and a comparison of 2007 data to previous operational and preoperational data.Milk Sampling The milk sampling portion of the REMP is perhaps one of the most important aspects of the program. This is because a major pathway in the human food chain is the consumption of milk firom grazing animals (dairy cows or goats) due to biological concentration and the short turn around time in this pathway. Milk is collected from one indicator location and one control location semimonthly when animals are in the pasture, and monthly when the animals are on stored feed. The milk is analyzed for iodine- 131, gamma emitting radionuclides, and strontium-89/90.

At times when milk samples are not available, grass samples are collected at both the control milk sample location and the location where milk is not available.

Grass samples are analyzed for iodine- 131 and other gamma emitting radionuclides.

Milk sampling began in 1979 during the preoperational program. During this time period, milk samples were analyzed for iodine-131 and other gamma emitting radionuclides.

Cesium- 137 and naturally occurring potassium-40 were the only radionuclides detected in milk samples during the preoperational program. The cesium- 137 concentration averaged 3.60E+0 pCi/liter and is due to past atmospheric nuclear weapons testing. In 1986, after the nuclear accident at Chernobyl, iodine- 131 and cesium- 137 were detected in both indicator and control milk samples. The average concentration for iodine- 131 was 3.70E+0 pCi/liter and 6.60E+0 pCi/liter for cesium-137.

The analysis for strontium-89/90 began in 1988, and strontium-90 is routinely detected in both indicator and control milk samples because of past atmospheric nuclear weapons testing.During 2007, thirty four (34) milk samples were collected and analyzed for iodine- 131, gamma emitting radionuclides, and strontium-89/90.

No iodine-131 was detected in any of the samples. Strontium-90 was detected in one indicator milk sample and is due to fallout from past atmospheric weapons testing (see Figure 4).21 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report The indicator sample had a strontium-90 concentration of 1.24E+0 pCi/liter.

Naturally occurring potassium-40 was detected in both indicator and control samples. During 2007, no grass samples were scheduled or collected for the REMP program.In 1970, the concentration of strontium-90 in Monroe County milk was 6.OOE+0 pCi/liter according to the Michigan Department of Health's "Milk Surveillance," Radiation Data and Reports, Vol. 11-15, 1970-1974.

Figure 4 shows the calculated radiological decay curve for the 1970 concentration of strontium-90 and the average concentrations since 1988. This graph illustrates that the inventory of strontium-90 in the local environment is decreasing with time and closely follows the calculated decay curve. This supports the fact that the inventory of strontium-90 in the environment is due to fallout from past atmospheric nuclear weapons testing and not the operation of Fermi 2.Historical Strontium-90 Activity in Local Milk Samples 6.0 4.0-20.0.0 oý C~j -I (0co c o C> 0~ C'D CC CD, W 00 C C.j -I* (D P- -- r- r-_ r- 00 co 00 co co M) M) M) M M 0> 0 0 C)'IIcý CýJ C' C:)EZJAverage Sr-90 Activity -Calculated Decay]Figure 4 -Historical Strontium-90 Activity in Local Milk Samples; the concentration of strontium-90 in local milk samples is decreasing with time and is below the calculated decay curve. This supports the fact that strontium-90 in local milk is due to fallout from past atmospheric nuclear weapons testing and not the operation of Fermi 2.Groundw#ater Sampling In areas not served by municipal water systems, water supplies for domestic use are generally obtained from private wells. The network of private wells presently in use forms the source of water for domestic and livestock purposes in farms and homes west and north of the site. However, with the construction of new water plants and distribution systems, the water use trend in the area is from groundwater to surface water.22 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Groundwater is collected on a quarterly basis from four wells surrounding Fermi 2. The groundwater is analyzed for gamma emitting radionuclides and tritium. Sampling location GW-4, which is located approximately 0.6 miles west northwest, is designated as the control location because it is up-gradient and is least likely to be affected by the operation of the plant. The other three sampling locations are down-gradient from Fermi 2 and designated as indicator locations.

Groundwater sampling began in 1987, during the operational period of the REMP program. From 1987 to 1996, naturally occurring potassium-40, cesium-137, and tritium were detected in both indicator and control samples. The average concentration was 7.71E+O pCi/liter for cesium-137 and 1.50E+2 pCi/liter for tritium. The presence of cesium- 137 and tritium in groundwater samples is due to fallout from past atmospheric nuclear weapons testing leaching into the soil and becoming incorporated into the groundwater.

From 1997 to 2006, no activity was detected in groundwater samples.In 2007, sixteen(16) groundwater samples were collected and analyzed for gamma emitting radionuclides and tritium. One control sample detected naturally occurring potassium-40, no other activity was detected in groundwater samples.Garden Sampling Fermi 2 collects samples of broad leaf vegetables from indicator locations identified by the annual Land Use Census. Samples are also collected at a control location that is at a distance and direction which is considered to be unaffected by plant operations.

Samples are collected once a month during the growing season (June through September) and are analyzed for iodine- 131 and other gamma emitting radionuclides.

Vegetable sampling started in 1982. During the preoperational period from 1982 to 1985, only naturally occurring potassium-40 was detected in both indicator and control vegetable samples. During the operational period from 1985 to 1990 and 1994 to 1995, only naturally occurring potassium-40 was detected in both indicator and control vegetable samples. However, in 1991, 1992, and 1993, cesium-137 was detected in one indicator sample each year and had an average concentration of 1.2E+l pCi/kilogram.

Cesium-137 may become incorporated into plants by either uptake from the soil or direct deposition on foliar surfaces.

Since cesium-137 is normally not detected in gaseous effluent samples from Fermi 2, and there have been no recent atmospheric weapons testing or nuclear accidents, the incorporation of cesium-137 by direct deposition is highly unlikely.

The most probable source of cesium-137 in vegetable samples is the uptake of previously deposited cesium-137, which has leached into the soil. This cesium activity is attributed to fallout from past atmospheric weapons testing and to the nuclear accident at Chernobyl.

23 Fermi 2 -2007 Annual Radioactive.

Effluent Release and Radiological Environmental Operating Report During 2007, twelve (12) vegetable samples were collected and analyzed for iodine-131 and other gamma emitting radionuclides.

No iodine- 131 was detected in vegetable samples during 2007. The only gamma emitting radionuclides detected were naturally occurring potassium-40 and beryllium-7 in both indicator and control samples.Terrestrial monitoring results for 2007 of milk, groundwater and leafy garden vegetable samples, showed only naturally occurring radioactivity and radioactivity associated with fallout from past atmospheric nuclear weapons testing. The radioactivity levels detected were consistent with levels measured prior to the operation of Fermi 2 and no radioactivity attributable to activities at Fermi 2 was detected in any terrestrial samples. In conclusion, the terrestrial monitoring data show no adverse long-term trends in the terrestrial environment.

Aquatic Monitoring Lake Erie, on which Fermi 2 borders, is used as a source for drinking water, as well as for recreational activities such as fishing, swimming, sunbathing, and boating. For this reason, Lake Erie and its tributaries are routinely monitored for radioactivity.

The aquatic monitoring portion of the REMP consists of sampling raw municipal drinking water, surface water, lake sediments, and fish for the presence of radioactivity.

The following sections discuss the type and frequency of aquatic sampling, analyses performed, and a comparison of 2007 data to previous operational and preoperational data.Drinking Water Sampling Detroit Edison monitors drinking water at one control location and one indicator location using automatic samplers.

The automatic samplers collect samples, known as aliquots, at time intervals that are very short (hourly) relative to the sample collection period (monthly) in order to assure that a representative sample is obtained.

Indicator water samples are obtained at the Monroe water intake located approximately 1.1 miles south of the plant. Detroit municipal water is used for the control samples and is obtained at the Allen Park water intake located approximately 18.6 miles north of the plant. Drinking water samples are collected on a monthly basis and analyzed for gross beta, strontium-89/90, and gamma emitting radionuclides.

The monthly samples for each location are combined on a quarterly basis and analyzed for tritium activity.24 Fermi 2 -2007Annual

.Radioactive Effluent Release and Radiological Environmental Operating Report In late 1980, as shown in Figure 5, an atmospheric nuclear weapon test was conducted by the People's Republic of China. As a result of this test, the average gross beta for 1981 was 9.80E+0 pCi/liter for water samples. Figure 5 also shows that, except for the Chinese weapons testing, the historic drinking water sample data are below or slightly above the lower limit of detection (4.0OE+0 pCi/liter) required by US Environmental Protection Agency (USEPA) National Interim Primary Drinking Water regulations.

Even during the Chinese weapons testing, the drinking water samples did not exceed the USEPA maximum allowable criteria of 5.00E+l pCi/liter gross beta. In 1980 and 1983, cesium-137 was detected in drinking water samples at levels ranging from 5.40E+0 pCi/liter to 1.90E+l pCi/liter.

Tritium was also detected during the preoperational program and had an average of 3.25E+2 pCi/liter.

The presence of cesium-137 and detectable levels of tritium in these water samples is due to fallout from past atmospheric nuclear weapons testing and naturally occurring tritium.From 1985 to 2006, the average annual gross beta activity for indicator samples was 3.48E+0 pCi/liter and 2.90E+0 pCi/liter for control samples. The analysis for strontium-89/90 began in 1988, and strontium-90 has been detected in both indicator and control samples. The average strontium-90 activity for indicator samples was 7.25E-1 pCi/liter and 7.56E-1 pCi/liter for control samples during this time period. Tritium was also detected in both indicator and control drinking water samples during this time period. The average tritium activity for indicator samples was 2.52E+2 pCi/liter and 2.60E+2 pCi/liter for control samples. The presence of strontium-90 and detectable levels of tritium in these water samples is due to fallout from past atmospheric nuclear weapons testing and naturally occurring tritium.In 2007, twenty-four (24) drinking water samples were collected and analyzed for gross beta, gamma emitting radionuclides, strontium-89/90, and tritium. The average gross beta for indicator samples was 5.30E+0 and 5.55E+0 pCi/liter for control samples. No gamma emitting radionuclides or strontium-89/90 activity was detected in drinking water samples during 2007. Eight (8) quarterly composite drinking water samples were prepared and analyzed for tritium. No tritium activity was detected in drinking water samples during 2007.25 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Historical Gross Beta Activity in Drinking Water Samples 12.0 -10.0 -8.0 -6.0 -Weapons Test CL C., 0)a)4.0o- --2.0 -() ) ( 1.............................

co C0 C\j ý* (.0 00 0= C11 'I C0 co ) cdi ;a to 0 o 0) 0) 0) 00 0) 0) 03) 0) 0) 0) C0 ) ý CDý2 ý ý2CC\ CCDj CCd CC\,-0-- Indicator Gross Beta -E-- Control Gross Beta -- -- ----EPA LLD]Figure 5 -Historical Gross Beta Activity in Drinking Water Samples; Since 1982, the annual concentrations of beta emitting radionuclides in drinking water samples collected from indicator locations have been consistent with those from control locations.

This shows that Fermi 2 has had no measurable radiological impact on local drinking water.Surface Water Sampling Detroit Edison monitors surface water at two locations using automatic samplers.

As with drinking water, surface water samples are collected at time intervals that are very short (hourly) relative to the sample collection period (monthly) in order to assure obtaining a representative sample. Indicator surface water samples are obtained at the Fermi 2 General Service Water building, located approximately 0.3 miles south southeast from Fermi 2. The control surface water samples are obtained from Trenton Channel Power Plant's cooling water intake on the Detroit River, which is approximately 11.7 miles north northeast of Fermi 2. Surface water samples are collected on a monthly basis and analyzed for strontium-89/90 and gamma emitting radionuclides.

The monthly samples for each location are combined on a quarterly basis to form a quarterly composite sample and are analyzed for tritium.26 Fermi 2 -2007Annual

• Radioactive Effluent Release and Radiological Environmental Operating Report Surface water sampling began in 1979, and the samples were analyzed for gamma emitting radionuclides and tritium. During this preoperational program, no gamma emitting radionuclides, except for naturally occurring potassium-40, were detected.

Tritium was detected in both indicator and control samples during this time period and had an average concentration of 3.15E+2 pCi/liter.

This tritium activity represents the background concentration due to naturally occurring tritium and tritium produced during past atmospheric nuclear weapons testing.From 1985 to 2006, as part of the operational program, surface water samples were analyzed for gamma emitting radionuclides and tritium. The analysis for strontium-89/90 did not begin until 1988, and strontium-90 was detected in both indicator and control samples. The average strontium-90 concentration for this time period was 1.13E+0 pCi/liter.

In 1990, two indicator samples showed detectable activity for cesium-137 at an average concentration of 1.20E+1 pCi/liter.

The presence of cesium-137 and strontium-90 in these water samples is due to fallout from past atmospheric nuclear weapons testing.Tritium was detected in both indicator and control surface water samples during this time period at a concentration of2.31E+2 pCi/liter.

This tritium activity is consistent with background levels measured during the preoperational program.In 2007, twenty-six (26) surface water samples were collected and analyzed for gamma emitting radionuclides and strontium-89/90.

From these samples, eight (8) quarterly composite samples were prepared and analyzed for tritium. During 2007, no gamma emitting radionuclides, strontium-89/90 or tritium was detected in surface water samples.Sediment Sampling Sediments often act as a sink (temporary or permanent) for radionuclides, but they may also become a source, as when they are resuspended during periods of increased turbulence or are dredged and deposited elsewhere.

Sediment, in the vicinity of the liquid discharge point, represents the most likely site for accumulation of radionuclides in the aquatic environment, and with long-lived radionuclides, a gradual increase in radioactivity concentration would be expected over time if discharges occur. Sediment, therefore, provides a long-term indication of change that may appear in other sample media (i.e., water and fish samples).27 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Lake Erie shoreline and bottom sediments from five locations are collected on a semiannual basis (Spring and Fall) and are analyzed for gamma emitting radionuclides and strontium-89/90.

There is one control location and four indicator locations.

The control sample is collected near the Trenton Channel Power Plant's cooling water intake. The indicator samples are collected at Estral Beach, near the Fermi 2 liquid discharge area, the shoreline at the end of Pointe Aux Peaux, and Indian Trails Community Beach.During the preoperational program, there was not a control location, and indicator samples were analyzed for gamma emitting radionuclides.

During the preoperational program, except for naturally occurring radionuclides, only cesium-137 was detected in sediment samples. For this time period, the average cesium-137 concentration was 3.27E+2 pCi/kilogram.

The presence of cesium-137 in these sediment samples is due to fallout from past atmospheric nuclear weapons testing.From 1985 to 2006, cesium-137, strontium-90, and naturally occurring radionuclides were detected in sediment samples. The average cesium-137 concentration was 1.29E+2 pCi/kilogram for all samples. The analysis for strontium-89/90 began in 1988, and strontium-90 has been routinely detected at similar concentrations in both indicator and control samples. The average strontium-90 activity for indicator samples was 1.80E+2 pCi/kilogram and 1.98E+2 pCi/kilogram for control samples. The presence ofcesium-137 and strontium-90 in these sediment samples is'due to fallout from past atmospheric nuclear weapons testing.In 1990 and 1991, the Spring samples taken at the Fermi 2 liquid discharge line (Location S-2) showed activity for plant related radionuclides (manganese-54, cobalt-58, cobalt-60, and zinc-65) and was determined to be a result of liquid effluent from Fermi 2. The sample results were well below any regulatory reporting limits and were consistent with the activity released from the plant in liquid effluents and the dose impact was negligible.

In 2007, ten (10) sediment samples were collected and analyzed for gamma emitting radionuclides and strontium 89/90. Cesium-137 was detected in one control sample with a concentration of4.1OE+l pCi/kilogram.

Cesium-137 was not detected in any indicating sediment samples. The presence of cesium-137 in sediment samples is due to fallout from past atmospheric nuclear weapons testing. Naturally occurring radionuclide potassium-40 was also detected in sediment samples for this sampling period.28 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Historical Cesium-137 Activity in Sediment Samples 7.E+02 --6.E+02 --E 5.E+02-4 .E+02 --3.E+02 CL 2.E+02-1.E+02 O.E'FO0 o 0ý CNJ ;1- (0 00 C Cli CD ( 0 0 C) CM CD Figure 6 -Historical Cesium-137 Activity in Sediment Samples; As the calculated trend shows, the concentration of cesium-137 in Lake Erie sediments is decreasing with time. This supports the fact that cesium-137 in Lake Erie sediments is due to fallout from past atmospheric nuclear weapons testing and not the operation of Fermi 2.Figure 6 shows the historical concentration of cesium- 137 in sediment samples from 1978 to 2007. Using the data from these years, and the statistical method of least squares, an exponential curve can be calculated that represents the cesium- 137 concentration in sediment.

This curve has a negative slope which indicates the overall concentration of cesium-137 in the environment is decreasing with time. This supports the fact that the inventory of cesium-137 in the environment is due to fallout from past atmospheric nuclear weapons testing and not from the operation of Fermi 2.Fish Sampling Samples of fish are collected from Lake Erie at three locations on a semiannual basis.There are two control locations and one indicator location.

The two control locations are offshore of Celeron Island and in Brest Bay. The indicator location is approximately 1200 feet offshore of the Fermi 2 liquid effluent discharge.

Edible portions of the fish are analyzed for gamma emitting radionuclides and strontium-89/90.

During the preoperational program, fish samples were analyzed for gamma emitting radionuclides.

Only cesium-137 and naturally occurring potassium-40 were detected during this time period. The average concentration of cesium-137 for indicator samples was 3.53E+1 pCi/kilogram and 4.20E+1 pCi/kilogram for control samples. The presence of cesium-137 in these fish samples is due to fallout from past atmospheric nuclear weapons testing.29 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report From 1985 to 2006, cesium-137 and naturally occurring potassium-40 were detected in fish samples. The average cesium-137 concentration for indicator samples was 3.82E+1 pCi/kilogram and 3.92E+1 pCi/kilogram for control samples. The analysis for strontium-89/90 began in 1990, and strontium-90 has been routinely detected at similar concentrations in both indicator and control samples. The average strontium-90 concentration for indicator samples was 3.84E+1 pCi/kilogram and 3.15E+1 pCi/kilogram for control samples. The presence of cesium-137 and strontium-90 in these fish samples is due to fallout from past atmospheric nuclear weapons testing.In 2007, twenty-eight (28) fish samples were collected and analyzed for gamma emitting radionuclides and strontium-89/90.

Only naturally.occurring potassium-40 was detected in both control and indicator fish samples for 2007.Aquatic monitoring results for 2007 of water, sediment, and fish showed only naturally occurring radioactivity and radioactivity associated with fallout from past atmospheric nuclear weapons testing and were consistent with levels measured prior to the operation of Fermi 2. In conclusion, no radioactivity attributable to activities at Fermi 2 was detected in any aquatic samples during 2007 and no adverse long-term trends are shown in the aquatic monitoring data.30 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Land Use Census The Land Use Census is conducted in accordance with the Fermi 2 Offsite Dose Calculation Manual (ODCM), control 3.12.2, and satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. This census identifies changes in the use of unrestricted areas to permit modifications to monitoring programs for evaluating doses to individuals from principal pathways of exposure.

The pathways of concern are listed below:* Inhalation Pathway -Internal exposure as a result of breathing radionuclides carried in the air.* Ground Exposure Pathway -External exposure from radionuclides deposited on the ground.* Plume Exposure Pathway -External exposure directly from a plume or cloud of radioactive material.* Vegetation Pathway -Internal exposure as a result of eating vegetables which have absorbed 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 dairy animals grazing on a pasture contaminated by radionuclides.

The Land Use Census is conducted during the growing season and is used to identify, within a radius of 5 miles, the location of the nearest residences, milk animals, meat animals, and gardens (greater than 50 square meters and containing broad leaf vegetation) in each of 16 meteorological sectors surrounding Fermi 2. Gardens greater than 50 square meters are the minimum size required to produce the quantity (26 kg/year) of leafy vegetables assumed in NRC Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden is used for growing broad leaf vegetation (i.e., lettuce and cabbage);

and (2) a vegetation yield of 2 kg/square meter.31 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental.

Operating Report 2007 Land Use Census Results The Land Use Census is conducted in accordance with ODCM control 3.12.2 and satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. This census identifies changes in the use of unrestricted areas to permit modifications to monitoring programs for evaluating doses to individuals from principal pathways of exposure.

The annual Land Use Census is conducted during the growing season and is used to identify, within a radius of 5 miles, the location of the closest residences, milk animals, meat animals, and gardens in each of the 11 land based meteorological sectors surrounding Fermi 2.The 2007 Land Use Census was performed during the month of August. The 2007 census data were obtained with the use of a hand-held Global Positioning System (GPS) and aerial imagery using Google Earth. These data were compared to the 2006 data to determine any significant changes in the use of the land. The results of the census are tabulated in Tables 9 -12 of this report.No significant changes in the land use between 2006 and 2007 were found that would require changing the location of the "maximum exposed individual".

There were no real changes in the category of closest residences, although satellite imagery was used to enhance the coordinates in the West North West sector. There were slight changes in three meteorological sectors in the.category of closest gardens. See Table 2 for these changes. The "maximum exposed individual" is located in the West-North-West sector and at one time participated in the REMP program. In the past few years this location did not have a garden, but in 2007 a garden was planted at this location.

In the category of closest milk locations, there was one change; the goat in the North sector was not identified.

All milk locations that were identified are not pets and not use for human consumption.

There were three changes found in the category of closest meat locations.

Beef and sheep were identified in the North sector, a new beef location was identified in North-West sector, and in West-South-West sector the past beef location was not identified.

As with past surveys, this census identified new residential housing construction that shows a continuing trend of converting agricultural land to other uses in the area surrounding Fermi 2.As stated above, there were no significant changes in the 2007 land use that would require changing the location of the "maximum exposed individual".

For that reason, the location of"maximum exposed individual" remains the same and is described as follows: Azimuth Distance Age Maximum Pathway Sector (degrees) (miles) Group Organ Ingestion WNW 300.6 0.72 Child Thyroid (vegetation) 32 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report 2007 LAND USE CENSUS Closest Residences Table 9 S ,Sctor Year Distance i milds Clirhang (e m" N 2006 I 8.9 1.11 2007 8.9 1.11 0.00 NE 2006 34.7 1.10o 2007 34.7 1.10 0.00 NNE 2006 16.6 1.08 2007 16.6 1.08 0.00 NNW 2006 334.9 1.09o I 2007 334.9 1.09 0.00 NW 2006 309.7 1.07 t 2007 309.7 1.07 0.00 S 2006 169.6 1.03 o 2007 I 169.6 1.03 0.00 SSW 2006 200o.1 1 2007 200.1 1.12 0.00 SW ~ 2006 229.3 1.26 2007 229.3 1.26 0.00 W 2006 259.2 1.19, 2007 259.2 1.19 0.00 WNW(a) 2006 301.9 0.69 _ _2007 302.3 0.71 0.02 WSW 2006 236.3 1.39_ I 2007 236.3 1.39 0.00 (a) = Location of "maximum exposed individual" 33 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report 2007 LAND USE CENSUS Closest Gardens Table 10 Sector Year Azimuth (d rees) lDistance (miles) ChIqan& (riles)'N 2006 0.6 1.64 I 2007 358.5 2.13 0.49 NE 2006 38.9 1.98 I 2007 38.9 1.98, 0.00 NNE 2006 33 1.74 I 2007 30.6 1.91 0.17 NNW 2006 326.7 1.40 2007 326.7 1.40 0.00 NW 2006 313.5 1.08 , 2007 313.5 1.08 0.00 S 2006 No Data I 2007 No Data 1 SSW 2006 195.9 1.50 0 2007 195.9 1.50 ] 0.00 SW 2006 No Data 2007 No Data W 2006 266.7 1.70 2007 266.7 1.70 0.00 WNW(a) 2006 300.3 1.78 2007 300.6 0.72 -1.06 WSW 2006 250.5 2.38 0 I2007 250.5 2.38 0.00 (a) = Location of "maximum exposed individual" 34 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report 2007 LAND USE CENSUS Milk Locations Table 11 Sector Year~ Azimuth (deore~es)

Distance (miles) CThang ( miles) Tye N 2006 1.2 1.80 Goat 2007 No Data NE ýo0 No D~ata F 7 2007 No Data NNE 26 NoIData 2007 No Data NNW 2006 329.4 F 3.02 0Goat 2007 329.4 1 3.02 0.00 Goat NW 2006 No Data F 2007 No Data S 2006 No Data F 2007 No Data SSW 2006 No Data F 2007 No Data I SW o61 NooData F 2007 No Data I SW oo Nooo DaaI W 206 No Data F 2007 No Data WNW 20297.4 2.38 I Goat 2007 297.4 2.38 Goat WSW 2 No Data 2007 No Data 35 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report 2007 LAND USE CENSUS Closest Meat Locations Table 12-Setbr 7 Year > ~Azimuith (degrees)

Distance mriles) Change (miles) Typ N 2006 No Data 2007 9.6 4.29 4.29 Beef/Sheep NE NooData :TI N 2007 No Data NEI 207I NoData I 2007 No Data NNW 20061 3No.2t 4.3 Seep 2007 338.2 4.36 0.00 Sheep NW 2006 No Data 2007 321.4 3.02 3.02 Beef S 200 No Data 2007 No Data SSW 2006 No Data 2007 No Data SW t 06 No Data I 2007 No Data W t2006 No Data I 2007 No Data WNW t2006 No Data I 2007 No Data WSW 2006 251.1 2.96 t I Beef 2007 No Data -2.96 36 Appendix A Sampling Locations Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Direct Radiation Sample Locations Table A-1 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type TI NE/38 0 1.3 mi. Estral Beach, Pole on Q I Lakeshore 23 Poles S of Lakeview. (Special Area)T2 NNE/22 0 1.2 mi. Pole at termination of Q Brancheau St.(Special Area)T3 N/9° 1.1 mi. Pole, NW corner of Swan Q Boat Club fence. (Special Area)T4 NNW/337 0 0.6 mi. Site boundary and Toll Rd. Q on Site fence by API #2.T5 NW/3130 0.6 mi. Site boundary and Toll Rd. Q on Site fence by API #3.T6 WNW/294 0 0.6 mi. On Site fence at south end Q of N. Bullet Rd.T7 W/270 0 14.0 mi. Pole, at Michigan Gas Q C substation on N. Custer Rd., 0.66 miles west of Doty Rd.T8 NW/305 0 1.9 mi. Pole on Post Rd. near NE Q corner of Dixie Hwy. and Post Rd.T9 NNW/334 0 1.5 mi. Pole, NW comer of Q Trombley and Swan View Rd.TI0 N/6 0 2.1 mi. Pole, S side of Massarant-Q 2 poles W of Chinavare.

I Indicator C = Control 0 = On-site Q = Quarterly A-1 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A-I continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type T11 NNE/23 0 6.2 mi. Pole, NE comer of Q I Milliman and Jefferson.

T12 NNE/29 0 6.3 mi. Pointe Mouille Game Area Q Field Office, Pole near tree, N area of parking lot.T13 N/356 0 4.1 mi. Labo and Dixie Hwy. Pole Q on SW comer with light.T14 NNW/337 0 4.4 mi. Labo and Brandon Pole on Q SE comer near RR..T15 NW/315 0 3.9 mi. Pole, behind building at the Q comer of Swan Creek and Mill St.T16 WNW/283 0 4.9 mi. Pole, SE corner of War and Q Post Rd.T17 W/271 0 4.9 mi. Pole, NE comer of Nadeau Q and Laprad, near mobile home park.T18 WSW/247 0 4.8 mi. Pole, NE corner of Mentel Q and Hurd Rd.T19 SW/236 0 5.2 mi. Fermi siren pole on Q Waterworks Rd. NE comer of intersection

-Sterling State Park Rd. Entrance Drive/Waterworks.

T20 WSW/257 0 2.7 mi. Pole, S side of Williams Q Rd, 9 poles W of Dixie Hwy. (Special Area)T21 WSW/239 0 2.7 mi. Pole, N side of Pearl at Q Parkview Woodland Beach. (Special Area)I = Indicator C = Control 0 On-site Q = Quarterly A-2 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A-I continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type T22 S/172 0 1.2 mi. Pole, N side of Pointe Aux Q I Peaux 2 poles W of Long -Site Boundary.T23 SSW/195 0 1.1 mi. Pole, S side of Pointe Aux Q Peaux I pole W of Huron next to Vent Pipe -Site Boundary.T24 SW/225 0 1.2 mi. Fermi Gate along Pointe Q Aux Peaux Rd. on fence wire W of gate Site Boundary.T25 WSW/252 0 1.4 mi. Pole, Toll Rd. -12 poles S Q of Fermi Drive.T26 WSW/259 0 1.1 mi. Pole, Toll Rd. -6 poles S Q of Fermi Drive.T27 SW/225 0 6.8 mi. Pole, NE comer of Q McMillan and East Front St. (Special Area)T28 SW/229 0 10.6 mi. Pole, N side of Mortar Q C Creek between Hull and LaPlaisance.

T29 WSW/237 0 10.3 mi. Pole, NE corner of S Dixie Q C and Albain.T30 WSW/247 0 7.8 mi. E side S end of foot bridge, Q St. Mary's Park corner of Elm and Monroe St.(Special Area)T31 WSW/255 0 9.6 mi. 1 st pole W of entrance Q C drive Milton "Pat" Munson Recreational Reserve on North Custer Rd.I = Indicator C Control 0 On-site Q = Quarterly A-3 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A-] continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type T32 WNW/295 0 10.3 mi. Pole, comer of Stony Creek Q and Finzel Rd.T33 NW/3170 9.2 mi. Pole, W side of Grafton Q Rd. I pole N of Ash and Grafton intersection.

T34 NNW/338 0 9.8 mi. Pole, SW comer of Port Q Creek and Will-Carleton Rd.T35 N/359 0 6.9 mi. Pole, S Side of S Huron Q River Dr. across from Race St. (Special Area)T36 N/358 0 9.1 mi. Pole, NE comer of Q Gibraltar and Cahill Rd.T37 NNE/21 0 9.8 mi. Pole, S corner of Adams Q and Gibraltar across from Humbug Marina.T38 WNW/294 0 1.7 mi. Residence

-6594 N. Dixie Q Hwy.T39* S/1760 0.3 mi. SE comer of Protected Q 0 Area Fence (PAF).T40* S/170° 0.3 mi. Midway along OBA -PAF. Q 0 T41* SSE/161 0 0.2 mi. Midway between OBA and Q 0 Shield Wall on PAF.T42* SSE/149 0 0.2 mi. Midway along Shield Wall Q 0 on PAF.T43* SE/131 0 0.1 mi. Midway between Shield Q 0 Wall and Aux Boilers on PAF.T44* ESE/109 0 0.1 mi. Opposite OSSF door on Q 0 PAF.* = Onsite TLD I =Indicator C = Control 0 = On-site Q = Quarterly A-4 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A-I continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type T45* E/86 0 0.1 mi. NE Comer of PAF. Q 0 T46* ENE/67 0 0.2 mi. NE side of barge slip on Q 0 fence.T47* S/1850 0.1 mi. South of Turbine Bldg. Q 0 rollup door on PAF.T48* SW/235 0 0.2 mi. 30 ft. from comer of AAP Q 0 on PAF.T49 WSW/251 0 1.1 mi. Comer of Site Boundary Q fence north of NOC along Critical Path Rd.T50 W/270 0 0.9 mi. Site Boundary fence near Q main gate by the south Bullet Street sign.T51 N/3 0 0.4 mi. Site Boundary fence north Q 0 of north Cooling Tower.T52 NNE/20 0 0.4 mi. Site Boundary fence at the Q 0 comer of Arson and Tower.T53* NE/55 0 0.2 mi. Site Boundary fence east of Q 0 South Cooling Tower.T54* S/1890 0.3 mi. Pole next to Fermi 2 Q 0 Visitors Center.T55 WSW/251 0 3.3 mi. Pole, north side of Nadeau Q I Rd. across from Sodt Elementary School Marquee.T56 WSW/256 0 2.9 mi. Pole, entrance to Jefferson Q I Middle School on Stony Creek Rd.* = Onsite TLD I Indicator C = Control 0 = On-site Q Quarterly A-5 Fermi 2 -200 7 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A-I continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type T57 W/260 0 2.7 mi. Pole, north side of Q I Williams Rd. across from Jefferson High School entrance.T58 WSW/249 0 4.9 mi. Pole west of Hurd Q I Elementary School Marquee.T59 NW/325 0 2.6 mi. Pole north of St. Charles Q Church entrance on Dixie Hwy.T60 NNW/341 0 2.5 mi. 1 st pole north of North Q Elementary School entrance on Dixie Hwy.T61 W/268 0 10.1 mi. Pole, SW corner of Stewart Q I and Raisinville Rd.T62 SW/232 0 9.7 mi. Pole, NE corner of Albain Q I and Hull Rd.T63 WSW/245 0 9.6 mi. Pole, NE corner of Dunbar Q I and Telegraph Rd.T64* WNW/286 0 0.2 mi. West of switchgear yard on Q 0 PAF.T65* NW/322 0 0.1 mi. PAF switchgear yard area Q 0 NW of RHR complex.T66* NE/50° 0.1 mi. Behind Bldg. 42 on PAF. Q 0 T67* NNW/338 0 0.2 mi. Site Boundary fence West Q 0 of South Cooling Tower.* = Onsite TLD I Indicator C = Control 0 = On-site Q = Quarterly A-6 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Air Particulate and Air Iodine Sample Locations Table A-2 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type API-1 NE/39 0 1.4 mi. Estral Beach Pole on W I Lakeshore, 18 Poles S of Lakeview (Nearest Community with highest X/Q).API-2 NNW/337 0 0.6 mi. Site Boundary and Toll W I Road, on Site Fence by T-4.API-3 NW/3130 0.6 mi. Site Boundary and Toll W I Road, on Site Fence by T-5.API-4 W/270 0 14.0 mi. Pole, at Michigan Gas W C substation on N. Custer Rd., 0.66 miles west of Doty Rd.API-5 S/1880 1.2 mi. Pole, N comer of Pointe W Aux Peaux and Dewey Rd.I = Indicator C = Control W = Weekly Milk Sample Locations Table A-3 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type M-2 NW/319 0 5.4 mi. Reaume Farm -2705 E M-SM I Labo.M-8 WNW/289 0 9.9 mi. Calder Dairy -9334 Finzel M-SM C Rd.I = Indicator C = Control M = Monthly SM = Semimonthly A-7 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Garden Sample Locations Table A-4 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type FP-1 NNE/21 0 3.8 mi. 9501 Turnpike Highway. M I FP-9 W/261 0 10.9 mi. 4074 North Custer Road. M C I = Indicator C = Control M = Monthly (when available)

Drinking Water Sample Locations Table A-5 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type DW-1 S/1740 1.1 mi. Monroe Water Station N M I Side of Pointe Aux Peaux 1/2 Block W of Long Rd.DW-2 N/8 0 18.5 mi. Detroit Water Station M C 14700 Moran Rd, Allen Park.I = Indicator C = Control M = Monthly A-8 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Surface Water Sample Locations Table A-6 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type SW-2 NNE/20 0 11.7 mi. DECo's Trenton Channel M C Power Plant Intake Structure (Screenhouse

1. 1).SW-3 SSE/160 0 0.2 mi. DECO's Fermi 2 General M Service Water Intake Structure.

I = Indicator C = Control M = Monthly Groundwater Sample Locations Table A-7 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type GW-1 S/175 0 0.4 mi. Approx. 100 ft W of Lake Q I Erie, EF-1 Parking lot near gas fired peakers.GW-2 SSW/208 0 1.0 mi. 4 ft S of Pointe Aux Peaux Q (PAP) Rd. Fence 427 ft W of where PAP crosses over Stoney Point's Western Dike.GW-3 SW/226 0 1.0 mi. 143 ft W of PAP Rd. Gate, Q 62 ft N of PAP Rd. Fence.GW-4 WNW/299 0 0.6 mi. 42 ft S of Langton Rd, 8 ft Q C E of Toll Rd. Fence.I = Indicator C = Control Q = Quarterly A-9 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Sediment Sample Locations Table A-8 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type S-1 SSE/165 0 0.9 mi. Pointe Aux Peaux, SA I Shoreline to 500 ft offshore sighting directly to Land Base Water Tower.S-2 E/81 0 0.2 mi. Fermi 2 Discharge, approx. SA 200 ft offshore.S-3 NE/39 0 1.1 mi. Estral Beach, approx. 200 SA ft offshore, off North shoreline where Swan Creek and Lake Erie meet.S-4 WSW/241 0 3.0 mi. Indian Trails Community SA Beach.S-5 NNE/20 0 11.7 mi. DECo's Trenton Channel SA C Power Plant intake area.I = Indicator C = Control SA = Semiannually Fish Sample Locations Table A-9 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.)

Description Frequency Type F-I NNE/31 0 9.5 mi. Near Celeron Island. SA C F-2 E/86 0 0.4 mi. Fermi 2 Discharge (approx. SA I 1200 ft offshore).

F-3 SW/227 0 3.5 mi. Brest Bay. SA C I = Indicator C = Control SA = Semiannually A-10 MAP -1 SAMPLING LOCATIONS BY STATION NUMBER WITHIN I MILE N LEGEND 6 T- DIRECT RADIATION 0 APT- AIR PARTICULATES/AIR IODINE A S- SEDIMENTS , DW/SW- DRINKING WATER/SURFACE WATER 10 GW- GROUND WATER 17M- MILK Z FP- FOOD PRODUCTS F- FISH 0 0.5 SCALE IN MILES MAP -2 SAMPLING LOCATIONS BY STATION NUMBER (1 To 5 MILES)N A LEGEND T- DIRECT RADIATION API- AIR PARTICULATES/AIR IODINE S- SEDIMENTS DW/SW- DRINKING WATER/SURFACE WATER GW- GROUND WATER M- MILK FP- FOOD PRODUCTS F- FISH 0 SCALE IN MILES MAP -3 SAMPLING LOCATIONS BY STATION NUMBER (GREATER THAN 5 MILES)N*0 AL I: V LEGEND T- DIRECT RADIATION API- AIR PARTICULATES OR AIR IODINE S- SEDIMENTS DW/SW- DRINKING WATER/SURFACE WATER GW- GROLND WATER M- MILK FP- FOOD PRODUCTS F- FTSH'N 5 0 5 10 SCALE IN MILES Appendix B Environmental Data Summary Fermi 2 -2006 Annual Radioactive Effluent.Release and Radiological Environmental Operating Report Reporting Period: January -December 2006 Table B-1 Radiological Environmental Monitoring Program Summary Name of Facility:

Enrico Fermi Unit 2 Docket No.: 50-341 Location of Facility:

30 miles southeast of Detroit, Michigan (Frenchtown Township)Direct Radiation mR/std atr (jamma (I LU)191 1.0 14. 8 (1 //12 /)10.8 to 20.3 1-49 (Inlicator) 19.J (4/4)18.2 to 20.3 J.5/ (o0/14 )12.5 to 14.9 None+ + + I-Airborne Particulates pCi/cu. m.Gross Beta 255 Gamma Spec. 20 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru- 103 Ru- 106 Cs- 134 Cs-137 Ba- 140 La- 140 Ce- 141 Ce- 144 I.OOE-2 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 5.OOE-2 6.OOE-2 N/A N/A N/A N/A 2.13E-2 (203/203)1.97E-6 to 3.96E-2 1.06E-1 (16/16)5.60E-2 to 1.64E-1<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA API-4 (Control)API-4 (Control)2.44E-2 (52/52)6.40E-3 to 5.56E-2 1.27E- 1 (4/4)9.OOE-2 to 1.50E-1 2.44E-2 (52/52)6.40E-3 to 5.56E-2 1.27E-1 (4/4)9.OOE-2 to 1.50E-1<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA None None None None None None None None None None None None None None None None None Airborne Iodine 11-131 257 7.OOE-2 <MDA <MDA None pCi/cu. m.B-I Fermi 2 -2006 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Reporting Period: January -December 2006 Table B-I Radiological Environmental Monitoring Program Summary (cont.)Name of Facility:

Enrico Fermi Unit 2 Docket No.: 50-341 Location of Facility:

30 miles southeast of Detroit, Michigan (Frenchtown Township)pCi/l I-I. 1I Sr-89 Sr-90 36 36 N/A N/A N/A N/A<MDA<MDA 1.43E+0 (1/18)<MDA<MDA 1.70E+0 (1/18)None None None M-8 (Control)1.70E+0 (1/18)Gamma Spec.Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru- 103 Ru- 106 Cs- 134 Cs-137 Ba- 140 La- 140 Ce- 141 Ce- 144 N/A N/A N/A N/A N/A N/A N/A N/A 1.50E+1 1.80E+1 1.50E+1 1.50E+1 N/A N/A<MDA 1.41E+3 (18/18)1.27E+3 to 1.50E+3<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA M-8 (Control)1.42E+3 (18/18)1.30E+3 to 1.53E+3<MDA 1.42E+3 (18/18)1.30E+3 to 1.53E+3<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA None None None None None None None None None None None None None None None None Vegetation 1- 131 14 6.00E+1 <MDA <MDA None pCi/kg wet Gamma Spec. 14 Be-7 N/A <MDA <MDA None K-40 N/A 2.85E+3 (7/7) FP-9 (Control) 3.45E+3 (7/7) 3.45E+3 (7/7) None 1.60E+3 to 4.OOE+3 1.99E+3 to 4.71E+3 1.99E+3 to 4.71E+3 B-2 Fermi 2 -2006 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Reporting Period: January -December 2006 Table B-I Radiological Environmental Monitoring Program Summary (cont.)Name of Facility:

Enrico Fermi Unit 2 Docket No.: 50-341 Location of Facility:

30 miles southeast of Detroit, Michigan (Frenchtown Township)Vegetation (cont.)pCi/kg wet Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru- 103 Ru- 106 Cs-134 Cs-137 Ba- 140 La- 140 Ce- 141 Ce- 144 N/A N/A N/A N/A N/A N/A N/A N/A 6.00E+1 8.00E+1 N/A N/A N/A N/A<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA None None None None None None None None None None None None None None+ + I I Drinking Water pCi/l Gross Beta 25 Sr-89 Sr-90 Gamma Spec.Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 25 25 4.OOE+0 N/A N/A N/A N/A N/A 1.50E+1 1.50E+1 3.00E+l 1.50E+1 3.00E+l 1.50E+l 4.72E+0 (10/13)4.1OE+0 to 6.1OE+0<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA DW-1 (Indicator) 4.72E+0 (10/13)4.1OE+0 to 6.1OE+0 4.03E+0 (6/12)2.30E+0 to 5.90E+0<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA None None None None None None None None None None None None B-3 Fermi 2 -2006 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Reporting Period: January -December 2006 Table B-I Radiological Environmental Monitoring Program Summary (cont.)Name of Facility:

Enrico Fermi Unit 2 Docket No.: 50-341 Location of Facility:

30 miles southeast of Detroit, Michigan (Frenchtown Township)Drinking Water (cont.) pCi/l Ru- 103 Ru- 106 Cs- 134 Cs- 137 Ba- 140 La- 140 Ce- 141 Ce- 144 H-3 N/A N/A 1.50E+l 1.80E+l 1.50E+l 1.50E+l N/A N/A 2.OOE+3<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA None None None None None None None None None 8 Surface Water pCi/l Sr-89 Sr-90 Gamma Spec.Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru-103 Ru- 106 Cs-134 Cs-137 Ba- 140 La- 140 Ce- 141 24 24 N/A N/A N/A N/A N/A 1.50E+I 1.50E+l 3.OOE+I 1.50E+l 3.OOE+l 1.50E+l N/A N/A 1.50E+1 1.80E+l 1.50E+l 1.50E+l N/A<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA None None None None None None None None None None None None None None None None None None B-4 Table B-1 Radiological Environmental Monitoring Program Summary (cont.)Name of Facility:

Enrico Fermi Unit 2 Docket No.: 50-341 Location of Facility:

30 miles southeast of Detroit, Michigan (Frenchtown Township)Fermi 2 -2006 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Reporting Period: January -December 2006water (cont.) pCi/l t-e- 144 H-3 IN/A 2.OOE+3<-MLVUA<MDA<-IVIUA<MDA IN one None 8 Groundwater pCi/l Gamma Spec.Be-7 K-40 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru- 103 Ru- 106 Cs-134 Cs-137 Ba- 140 La- 140 Ce- 141 Ce- 144 H-3 16 N/A N/A N/A 1.50E+I 1.50E+l 3.OOE+l 1.50E+1 3.00E+1 I.50E+1 N/A N/A 1.50E+l I.80E+1 1.50E+1 1.50E+l N/A N/A 2.OOE+3<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA None None None None None None None None None None None None None None None None None None 16 Sediment Sr-89 10 N/A <MDA <MDA pCi/kg dry Sr-90 N/A <MDA <MDA None Gamma Spec. 10 Be-7 N/A <MDA <MDA None K-40 N/A 9.62E+3 (8/8) S-1 (Indicator) 1.21E+4 (2/2) 1.16E+4 (2/2)6.64E+3 to 1.24E+4 1.1 7E+4 to 1.24E+4 1.13E+4 to 1.18E+4 None B-5 Fermi 2 -2006 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Reporting Period: January -December 2006 Table B-1 Radiological Environmental Monitoring Program Summary (cont.)Name of Facility:

Enrico Fermi Unit 2 Docket No.: 50-341 Location of Facility:

30 miles southeast of Detroit, Michigan (Frenchtown Township)Sediment (cont.)pCi/kg dry Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru- 103 Ru- 106 Cs- 134 Cs-137 Ba-140 La- 140 Ce- 141 Ce- 144 N/A N/A N/A N/A N/A N/A N/A N/A 1.50E+2 1.80E+2<MUA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MUA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA 7.20E+1 (2/2)5.1OE+I to 9.30E+1<MDA<MDA<MDA<MDA None None None None None None None None None None None None None None S-5 (Control)7.20E+1 (2/2)5.10E+I to 9.30E+1 N/A N/A N/A N/A Fish Sr-89 19 N/A <MDA <MDA None pCi/kg wet Sr-90 N/A <MDA <MDA None Gamma Spec. 19 Be-7 N/A <MDA <MDA None K-40 N/A 3.15E+3 (6/6) F-2 (Indicator) 3.15E+3 (6/6) 2.83E+3 (13/13) None 2.25E+3 to 4.25E+3 2.25E+3 to 4.25E+3 2.30E+3 to 3.59E+3 Mn-54 1.30E+2 <MDA <MDA None Co-58 1.30E+2 <MDA <MDA None Fe-59 2.60E+2 <MDA <MDA None Co-60 1.30E+2 <MDA <MDA None Zn-65 2.60E+2 <MDA <MDA None B-6 Fermi 2 -2006 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Reporting Period: January -December 2006 Table B-1 Radiological Environmental Monitoring Program Summary (cont.)Name of Facility:

Enrico Fermi Unit 2 Docket No.: 50-341 Location of Facility:

30 miles southeast of Detroit, Michigan (Frenchtown Township)(cont.)pCi/kg wet Rur-913 Ru- 103 Ru- 106 Cs- 134 Cs- 137 Ba- 140 La- 140 Ce- 141 Ce- 144 N/A N/A N/A 1.30E+2 1.50E+2 N/A N/A N/A N/A<MLJA<MDA<MDA<MDA<MDA<MDA<MDA<MDA<MDA F-3 (Control)3.80E+1 (1/8)<MUA<MDA<MDA<MDA 3.80E+1 (1/8)<MDA<MDA<MDA<MDA None None None None None None None None None Direct Radiation mean and range values are based on off-site TLDs LLD = Fermi 2 ODCM LLD: nominal lower limit of detection based on 4.66 sigma error for background sample.<MDA = Less than the lab's minimum detectable activity which is less than the LLD.Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).Locations are specified by Fermi 2 code and are described in Appendix A Sampling Locations.

Non-routine results are those which are reportable according to Fermi 2 ODCM control 3.12.1.Note: Other nuclides were considered in analysis results, but only those identifiable were reported in addition to ODCM listed nuclides.B-7 Appendix C Environmental Data Tables Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 TLD ANALYSIS (mR/Std Qtr)T-1 12.23 13.41 14.04 12.82 T-2 12.73 13.58 14.52 12.39 T-3 10.91 11.52 16.59 11.84 T-4 13.'60 14.35 17.50 13.20 T-5 14.48 14.74 15.86 14.44 T-6 13.27 15.02 15.86 14.69 T-7 12.19 12.73 14.39 13.94 T-8 14.57 15.44 16.92 15.44 T-9 13.88 14.10 15.57 12.36 T-10 14.36 15.11 16.54 13.89 T-11 13.19 13.37 14.98 13.34 T-12 13.00 12.96 14.03 12.82 T-13 14.53 14.90 16.88 14.94 T-14 15.24 15.21 17.09 16.27 T-1 13.37 13.92 13.77 13.34 T-16 15.82 16.79 18.57 18.23 T-17 11.65 11.83 15.88 12.66 T-18 13.23 13.57 15.75 13.53 T-19 14.61 14.44 17.05 14.72 T-20 14.36 15.61 19.63 15.45 T-21 13.37 12.55 15.19 12.99 T-22 14.08 13.94 16.20 14.02 T,23 12.98 14.30 15.26 14.05 T-24 13.98 12.02 14.46 12.88 T-25 17.42 16.41 18.76 16.72 T-26 16.29 16.47 19.16 17.15 T-27 12.43 11.60 12.92 11.49 T-28 12.58 12.23 13.84 12.86 T-29 16.97 12.98 13.72 12.92 T-30 14.23 13.16 14.37 14.16 T-31 14.28 (a) 15.91 14.50 T-32 14.40 14.77 (a) 15.58 T-33 12.51 14.53 14.03 12.80 T-34 13.69 13.96 16.62 14.24 T-35 13.36 12.52 14.47 13.25 T-36 13.77 14.01 14.99 14.36 T-37 14.08 14.05 14.72 74.35 T-38 14.95 14.61 15.93 15.78 T-39 60.58 59.21 53.05 44.52 T-40 50.57 40.72 46.89 37.81 T-41 97.28 98.22 84.46 67.51 T-42 95.88 94.21 90.96 69.01 T-43 105.60 98.31 94.50 75.10 T-44 91.33 87.64 90.00 64.24 T-45 57.45 53.96 55.24 41.93 T-46 43.97 42.21 42.32 31.05 T-47 96.37 77.79 90.46 64.50 (a) TLD missing, see Appendix D -Program Execution.

C-1 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 TLD ANALYSIS (CONT.)(mR/Std Qtr)SS;TATION~

F! Iii FIS

SECOND

;i iiii FITIiRD FOURI T-48 48.53 47.85 48.27 34.52 T-49 17.23 17.49 20.31 18.92 T-50 15.12 14.42 15.91 15656 T-51 11.32 10.55 12.76 11.26 T-52 15.64 15.42 16.55 14.16 T-53 27.32 28.06 29.39 22.96 T-54 18.51 17.83 18.30 14.89 T-55 15.55 15.03 16.05 16.39 T-56 13.97 14.42 15.14 14.89 T-57 17.26 17.38 18.48 17.36 T-58 12.92 12.61 13.30 12.73 T-59 13.71 12.73 14.35 12.47 T-60 14.89 14.23 16.26 14.95 T-61 14.89 1-6.21 16.83 15.10 T-62 14.34 16.11 17.00 15.27 T-63 12.80 12.76 14.75 12.90 T-64 24.44 23.66 24.95 19.87 T-65 27.42 28.31 27.80 23.33 T-66 140.26 149.98 137.50 107.30 T-67 19.54 19.46 19.52 16.77 C-2 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)API-1 FIRST QUARTER 1/3/2007, 2.95E-02u+/-

3-OOE-03 1/11/20071 1.95E-02 12.50E-03 1/17/20071 1.75E-02 +/ 2.80E-03 1/24/2007 2.62E-02 +1-2.60E-03 1/31/2007 2.74E-02 +/ 2.60E-03 2/7/2007J!

2.75E-02 +/ 2.50E-03 2/15/2007 2.58E-021

+/-/-2.60E-03 2/21/20071 2.91E-021

+.-2.80E-03 2/28/20071 2.11E-021

+/-2.30E-03 3/7/20071 1.86E-02!

+1- 2.30E-03 3/14/20071 2.14E-02 +1- 2.30E-03 3/20/2007 2.57E-02i

+-i 2.80E-03 3/28/2007 1.99E-02L

+1- L 2.OE-03 API-1 SECOND QUARTER 1 4/4/2007' 1.45E-02'

+/-[2.50E-03 S4/11/2007i 9.90E-03.

+/- .2.40E-03[4/18/2007 2.05E-02 +/-12.50E-03

.4/25/2007 1.36E-021i

+/.-....40E-03 4/25/2007 1 1.36E-021

+/- 12.30E-03 1 5/2/2007 1.53E-021

+/- 2.30E-03 5/9/2007 2.02E-02 +/ 2.30E-03[5/16/2007 2.05E-02ý

+/- 12.40E-03 5/23/20071 1.84E-021

+/- 2.40E-03 5/30/20071 2.44E-021

+/- 2.60E-03 6/5/2007 2.34E-021

+/- 2.60E-03 6/13/2007 1.88E-021

+/- 12.20E-03 6/20/2007 2.56E-02ý

+/- 12.50E-03 6/26/20071 2.37E-021 2.-50E-03 C-3 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)API-I THIRD QUARTER 7/3/20071 1.68E-02 +/- 2.40E-03 7/11/2007I 2.69E-02 +/- 2.30E-03 7/18/2007 1.85E-02 7/25/2007 3.50E-02 +/- 2.70E-03 8/1/20071 3.38E-02 +1- 2.40E-03 8/8/20071 2.97E-02 +/- 2.40E-03 8/15/20_07_i 2.09E-02 +1- 2.30E-03 F 8/21/2007j 2.06E-02 +/ 2.90E-03 8/29/2007!

1.78E-021

+1- 3.OOE-03 9/5/2007 2.98E-02 +/- 2.60E-03 9/12/2007 3.26E-02 +/- 2.70E-03 9/1/0-0-7 2.56E-02 +/- 2.40E-03 9/26/2007 3.01E-02 +-2.60&L03 API-I FOURTH QUARTER 1 1) aI e I AcliN it N 10/3/2007i 3.08E-02j

+/-10/10/2007 2.87E-021

+/-/-10/17/2007 2.07E-02 +/-10/24/2007 2.39E-021

+/-10/31/2007 1.59E-02[

+/-11/7/2007 2.19E-021

+/, 11/14/2007 3.88E-021

+/-11/21/2007 1.93E-02 1+/-2.40E-03 12.60E-03 2.90E-03 2.70E-03 2.80E-03 12.40E-03 2.80E-03 ,2.60E-03 2.60E-03 2.70E-03 2.70E-03 2.60E-03 2.60E-03 I 11/28/2007 2.83E-021

+/-12/5/2007 3.72E-02+/-

12/12/2007 2.68E-02i

+/-12/19/2007 3.69E-021

+/-12/26/2007 4.1 OE-02 +/-C-4 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)API-2 FIRST QUARTER D~atek 1 J ActiN it%1/3/20oo, 4.11 E-02 +/3.320E-03 1/11/2007_

3.1 IE-02 +/- 2.70E-03 1/17/2007 3.08E-02 1/-33.OOE-03j 24/2007 3.62E-02 2.80E-03 1/31/20071 4.18E-02 +/-2.90E-03 2/7/20071 4.83E-02 +1- + 2.80E-03__2/15/2007~

4.OOE-02, 1+/--2.50E-03 2/21/20071 2.23E-02 1- 12.70E-03 2/28/20071 2.73E-02 +1- j2.40E-03 3/7/20071 2.66E-02 +/-'2.50E-03 3/14/2007, 3.34E-021

+/- :2.70E-03 3.10E-021

+/- 2.90E-03 1 3/28/2007

+/- 2.20E-03 1 API-2 SECOND QUARTER Date 7 Acti\ itJ 4/4/2007 2.23E-02!

+/- 2.60E-03 4/11/2007, 1.95E-021

+/- 12.50E-03 4/1 8/2007 2.46E-021

+/- 12.60E-03 4/25/2007 2.19E-02 +/- 12.50E-03 5/2/2007 1.85E-02i

+/- 12.40E-03 5/9/2007 2.64E-02 +/12.40E-03 5/16/2007 2.80E-02 +/- 2.60E-03 5/23/2007 2.54E-02 +/-12.50E-03 5/30/2007 3.61E-02 1+/-i2.80E-03 6/5/2007 3.81E-02 +/- 12.80E-03 6/13/20071 2.61E-02i

+/- 2.40E-03 1 6/20/2007 3.33E-021

+/- 2.60E-03[........6/26/2007

...3..09E-0.P2

+/..- :.i.2..7.0.E-P3.......

C-5 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)API-2 THIRD QUARTER V Datec '~ Actjivitv

~7/3/20071 2.08E-02 +1- 2.50E-03 7/11/2007' 3.43E-02 "+-ý 2.40E-03 7/18/2007 2.06E-02 +/-2.50E-03 7/25/20071 2.59E-02 J+- !2.50E-03 8/1/2007 3.95E-02 +/- 2.50E-03 8/8/2007 4.30E-02 +1- 2.60E-03 8/15/2007 2.96E-02 +/ 2.50E-03 8/21/20071 2.89E-02 +/- 3.OOE-03 8/29/20071 2.31E-02 +/- 2.30E-03 9/5/20071 3.78E-02 +/- 2.70E-03 9/12/20071 4.OOE-02 +/- 2.80E-03 9/19/2007 2.36E-02 +/- 2.40E-03 9/26/2007t 4.38E-02 +/- 2.80E-03 API-2 FOURTH QUARTER L1ae I A3/4 iVt 10/3/2007 3.61E-02F

+/- 2.50E-03 10/10/20071 3.81E-021

+/-2.70E-03 10/17/20071 2.69E-021

+/-3.OOE-03 10/24/2007 4.21E-021

+/-2.90E-03 10/31/2007 2.58E-021

+/- 3.OOE-03 11/7/2007 2.99E-02 +/- 2.5003 11/14/2007 4.41E

+/-2.90E-03 11/21/2007 2.94E-021

+/- 2.70E-03 11/28/2007 3.22E-021

+/- 2.70E-03 12/5/2007' 2.93E-021

+/- 2.60E-03 12/12/2007.

3.65E-021

+/- 2.80E-03 12/19/2007 4.67E-021

+/- 2.80E-03 12/26/2007 5.64E-021

+/-I 2.80E-03 C-6 Fermi 2 -2007 Annual Radioactive Effluent Release and.Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)API-3 FIRST QUARTER 1/3/2007 3.17E-02j+/-

13.OOE-03 1/11/2007 2.35E-02 +/- '2.60E-03 1/17/2007 2.16E-021

+/-2.80E-03 1 1/24/2007]

3.80E-021

+1-2.80E-03 1/31/.200_7]

,.8202j +1- 2.90E-03 2/7/2007 3.53E-021

+/- 2.60E-03 2/15/2007 3.34E-021

/-12.40E-03 2/21/2007 3.17E-02 +/-2.80E-03 2/28/2007 2.27E--2 +/- :2.30E-03 3/7/2007 2.07E-021 12.40E-03 3/14/2007 2.95E02+/-02 2.70E-03 3/20/2007 2.75E-02 +/- 2.80E-03 3/28/2007 2.35E-02T

+- 2.1OE-03 API-3 SECOND QUARTER 4/4/2007 1.77E-02( +/- 12.50E-03 4/11/2007 1.55E-02 /- 2.40E-03 4/18/2007:

2.57E-021

+/- 2.60E-03 4/25/20071 2.28E-02 +/-2.50E-03 5/2/2007.

2.14E-021

+/- 2.50E-03 5/9/20071 2.06E-021

+ 2.30E-03 5/16/2007 2.29E-021

+/- 12.50E-03 5/23/2007 2.04E-02j

+/-12.50E-03 5/30/2007 3.30E-02i

+/- 12.70E-03 6/5/20071 3.1OE-02 +/2.70E-03 6/13/20071 2.07E-021

+/- 2.30E-03 6/20/2007 3.22E-021

+/- 12.60E-03 6/26/20071 3.1IOE-021

+/- 12.70E-03 C-7 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)API-3 THIRD QUARTER 7/3/2007]

2.06E-021

+/- 2.50E-03 7/11/2007 2.97E-02i

+/- 2.40E-03 7/18/2007 1.69E-02 +/- 2.40E-03_7/25/2007 2.56E-02 +/- 2.50E-03 8/1/2007 3.20E-02 +/- 2.40E-03 8/8/2007 3.83E-02 +/- 2.60E-03 8/15-2 0O7 2.12E-02 +/- 2.30E-03 8/21/2007, 2.40E-02 +/-/-2.90E-03 8/29/2007 1.97E-02 +/- 2.20E-03 9/5/2007 3.57E-02-1

2. 2.0E-03 9/12/20071 3.21E-021

+/- 2.70E-03!9/19/2007 2.22E-02+/-

2.30E-03 9/26/2007 3.83E-02 +/- 2.70E-03j API-3 FOURTH QUARTER 10//20> 3 10/3/2007.

3 .37E +- i2.50E-03 10/10/2007 3.53E-02 +/- 2.60E-03 10/17/2007 1.97E-021

+/-i2.80E-03 10/24/2007 2.69E-02 +/-_2.70E-03 10/31/2007 1.76E-02 +/- 2.80E-03 11/7/2007 2.84E-02 +/- 2.50E-03 11/14/2007w 3.97E-02 +/- 2.80E-03 11/21/2007 2.87E-02'

+/- 12.70E-03 11/28/2007, 2.81E-02 +/- 12.70E-03 12/5/2007 3.49E-2 +/- 2.70E-03 12/12/2007, 3.50E-021

+/- 2.80E-03 12/19/2007 3 .94E-02! +/-12.70E-03 12/26/2007, 5.21E-02 +/- 2.80E-03 C-8 Fermi 2 -2007 Annual Radioactive .Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)API-4 FIRST QUARTER 1/3/2007 2.97E-021

+13.00E-03 21E-02 2.50E-03 1/11/2007 2.21!E-021

+/- 25E0 1/17/2007 2.18E-02 +1- 2.80E-03 1/24/2007 2.40E-021

+1-2.60E-03 1/31/2007 3.05E-02 +1- 2.80E-03 2/7/2007 3.07E-02 +/- 12.50E-03 2/15/2007 3.05 E-2 +/- 12.40E-03 2/21/2007 3.68E-02I

+/- 12.90E-03 2/28/2007 2.15E-02I

+/-2.30E-03 3/7/2007 1.46E-02i

+- 2.30E-03 3/14/2007 2.98E-0 2.70E-03 3/20/2007 2.66E-021

+1- 2.80E-03 3/28/2007 1 .85E-0'2'7

+-2.00E-03 API-4 SECOND QUARTER IU Date I Actiiy 4/4/2007 2.05E-02 +/- 12.60E-03 S4/11/2007 1.45E-02 12.40E-03 , 4/18/2007 1.83E-02, +ý/-2.50E-03 4/25/20071 1.91E-02 1 +/- ]2.50E-03./2/2007 1.65E-02 +/- 12.40E-03 5/9/20071 1 .99E-021j

+/ 2.30E-03 5/16/2007:

2.52E-021

+/- 12.50E-03 5/23/2007 1 2.16E-02 +/-12.50E-03 5/30/20071 2.46E-02 +-12.60E-03 6/5/2007 2.83E-021

/- 2.70E-03_6/13/2007 1.75E-02 +/- 2.20E-03 6/20/2007 2.74E-02 +/- 12.50E-03 6/26/2007' 2.55E 0o2, +/--T -2.5OE-3 C-9 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)API-4 THIRD QUARTER 7/3/2007u 2.07E-02i+/-

2.50E-03 I 7/11/2007i 1.97E-02'

+/-2.20E-03

/18/2007~

.98E-02T +/-2.40E-63 7/25/2007 2.64E +/- 2.50E-03 8/1/20071 4.48E-02 1 -2.60&0ý3 8/8/20071 411 E-021+/- 12.60E 8/15/2007.

2.84E-02i

+/- 2 ,40E-03 28//22007 2.57E-021

+/- i3.00E-03 8/29/2007' 2.50E-021

+/- i2.30E-03 9/5/2007 4.03E-021 12.80E-03 9/ 3.55E-02 +1- 2.80E-03 2.95E-02 +- 12.50E-03I 9/26/20071 4.09E-021 2.80E-03+",:

API-4 FOURTH QUARTER Aci t 10/3/2007 10/10/2007;4 10/17/2007

.10/24/2007 10/31/2007 11/7/2007 11/14/2007 11/21/2007 11/28/2007 12/5/2007 12/12/2007 12/19/2007 12/26/2007, 4.38E-02 +/- 2.60E-03 3.98E-02 +/- 2.70E-03 3.65E-02, +/- 3.1OE-03 4.17E-02;

+/- !2.90E-03 2.53E-02 +/-13.OOE-03 2.96E-02 +/- 2.50E-03 4.33E-02 2.96E-02 3.05E-021 3.53E-021 4.02E-02i 5.40E-02]6.22E-02+ 2.90E-03 2.70E-03 2 ---2.70E-03 2.80E-03+/- 2.90E-03+/- 2.90E-03 C-10 Fermi 2 -2007 Annual...Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)API-5 FIRST QUARTER S a-te7~ 7 At, t 1/3/2007 2.39E-02 +/- 2.80E-03 1/11/2007 1.88E-02 +/- 2.50E-03..1/17/2007 1.95E-02 +1- 2.80E-03 1/24/2007 3.09E-02 +1- j2.70E-03 1/31/2007 2.85E-02 +/- :2.70E-03 2/7/2007 2.89E-02 +,- 2.50E-03 2/15/2007 2.87E-02 +/- 2.40E-03 2/21/2007 2.55E-02 +/- 2.70E-03 2/28/2007 1.96E-02 +/-2.20E-03 3/7/20071 1.41E-02 +/-12.30E-03 3/14/20071 2.19E-02 +/- 2.60E-03 i 3/20/20O ~ 1.84E-02 +/- 2.60E-03 3/28/20071 1.98E-02 +/- 2.OOE-03 API-5 SECOND QUARTER L Date I Actwi 4/4/2007 1.41E-02 +/- 2.50E-03 4/11/20071 9.1OE-03 +/- 2.30E-03 4/18/2007!

1.38E-02 +/- 2.40E-03 4/25/2007i 1.98E-021

+/- 2.50E-03 5/2/2007 1.53E-02.

+/-2.40E-03 5/9/2007 1.86E-02 +/- 2.20E-03 5/16/2007 2.36E-02 +/ 25003 5/23/2007 1.97E-02 +/ 2.50E-03 5/30/2007 2.04E-021

+/ 2.60E-03 6/5/2007F 2.74E-02 +/ 2 70E-03 6/13/20071 2.06E-021

+/ 2.20E-03 6/20/2007 2.29E-021

+/ 2 40E-03 6/26/20071 2.32E-021 1/ 2.50E-03 C-1 1 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)API-5 THIRD QUARTER Date ' A tivAct 7/3/2007 1..02E-02

+/- 2.30E-03 7/11/2007, 2.32E-02 +/-2.30E-03 7/18/20071 1.39E-02+/-

2.40E-03 7/25/2007 1.79E.02 +/- 2.40E-03 8/1/2007 3.61E-02+/-

i2.40E-03 8/8/2007 2.92E-02 +:- 2.40E-03[ 8/15/2007 1.75E-02 +/- 2.30E-03 8/21/2007 1.83E-02 +/- 3.20E-03 8/29/2007 1.77E-02 +/- 2.50E-03 9/5/2007 2.76E-02 11- 2.50E-03 9/12/2007 2.76E-02 +/- ;2.60E-03.. 9/19/2007.

2.16E-021

+/-2.30E-03 9/26/20071 3.02E-02 +/- 2.60E-03 API-5 FOURTH QUARTER L Date 'A 7> tivii~jjj 10/3/2007 3.16E-02 +10/10/2007 2.61E-0+/_-

10/17/2007 1.87E-021

+/-10/24/2007 2.79E-021

+/-10/31/2007 1.87E-021

+/-2.50E-03 12.50E-03 2.80E-03 12.70E-03 i2.90E-03 11/7/2007 1.68E-02 11/14/20071 3.16E-02 +/-11/21/2007 2.53E-021

+/-11/28/2007 3.12E-021

+/-12/5/2007 2.37E-02[

+/12/12/2007 3.09E-021

+/-12/19/2007 3.70E-021

+/-112/26/2007~

4.40E-02+-

2.30E-03 2.70E-03 2.70E-03 12.90E-03.2.50E-03 2.70E-03 2.60E-03 2.70E-03 C-12 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)API-I FIRST QUARTER 1/3/20071

<13.80E-02 1/11/20071

<14.10E-02 1/17/20071

<i4.60E-02 1/24/20071

< 13.90E-02 1/31/20071

<P4.20E-02 2/7/20071

<--4.30E-02 2/15/20071

<5I 5.40E-02 2/21/2007

<16.30E-02 2/28/2007, <I4.90E-02 3/7/2007 <14.OOE-02 3/14/2007

< I3.60E-02 3/20/20071

< i4.70E-02 1 3/28/20071

< 2.70E-02 API-I SECOND QUARTER Dat Ia, .Activity 4/4/2007 <1 3.50E-02

<-14.90E-02 4/18/20071

< I3.50E-02 4/25/20071

<14.1 OE-02 5/2/2007 < 5.OOE-02 5/9/2007 < 4.20E-02 5/16/2007

< 4.40E-02 5/23/20071

< 3.80E-02 5/30/2007

< 5.50E-02 6/5/2007_1

<4.80E-02 6/13/20071

< 2.70E-02 6/20/200771

< 3.1 OE-02.6/26/2007

.6.50OE-02 C-13 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)API-I THIRD QUARTER Date ý[ý7 7/3/20071

<14.50E-02 7/11/2007

< 40E-02 7/18/2007

<14.80E-02 7/25/2007

< 3.30E-02 8/1/2007 < 4.90E-02 8/8/2007 < 4.30E-02 8/15/2007F

< 4.10OE-02 8/21/20071

<14.30E-02 8/29/20071

-<[5.80E-02 9/5/2007t

<13.30E-02 9/12/2007[

<43.50E-02 9/19/20071

< 3.50E-02 j 9/26/20071

< 15.20E-02 j API-i FOURTH QUARTER 10/3/20071

<4.80E- 02 10/10/20071

< 5. OE-02 10/17/2007j

< 31.5 0E022 10/24/2007

< 3.50E-02 10/31/2007

<15.20E-02 11/7/20071

<14.80E-02 11/14/20071

< i5.50E-02 I 1/21/20071

< -5 20E-02 I I 28/2007 1 < 350OE-02 L 12/52ý007'

< 650E 02 12/12/20071

< 5.1OE-02 12/19/20071

<15.30E-02 12/26/2007.1

<.I 6.20E-02 C-14 Fermi 2 -2007Annual

..Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)API-2 FIRST QUARTER Date I Activi <i...3/2007. < 3.80E-02 1/11/20071

<14.O0E-02

__1/17/20071

<14.90E-02 1/24/2007

<13.30E-02 1/31/2007

< 14.10E-02 2/7/2007 <4.60E-02 2/15/2007

< 14.10E-02 2/21/2007

<i6.00E-02 2/28/20071

<14.70E-02 3/7/20071

<14.OOE-02 3/14/20071

<14.40E-02 3/20/20071

<14 OOE-02 3/28/20077

<t3.OOE-02 API-2 SECOND QUARTER atwe I: 4/4/20071 4/11/2007 4/18/20071 5/2/20071 5/9/2007 1 5/23/20071 5/30/200711 6/5/2007j 6/13/2007 6/20/20071

<2.70E-02< i4.80E-02< 4.80E-02< I3.60E-02<i 6.50E-02<14.1 OE-02<!4.40E-02

< 14.40E-02 ,<I 5.70E-02_1 5.40o-02<12.90E-02

< 3.40E-02< 14.90E-02 C-15 Fermi 2 -2007 Annual Radioactive.

Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)API-2 THIRD QUARTER 7/3/20071

<n6.OOE-02 7/11/20071

<14.00E-02 7/18/20071

<1,5.80E-02 7/25/2007

<1 3.50E-02 L 8/1/20071

< 14.20E-02 8/8/2007.

< 3.80E-02 8/15/2007

..<5.50E-02 8/21/2007

< 3.60E-02 8/29/2007, <12.50E-02 9/5/2007 < 3.30E-02 9/12/2007

< 3.80E-02 9/26/2007j

< 6.90E-02 API-2 FOURTH QUARTER 10/3/2007 10/10/20071 10ý/17/200UO7 10/24/2007 10/31/2007, 11/7/2007

{11/14/20071 11/21/20071 11/28/2007,, 1 2/12/2007 12/19/2007 1 12/26/2007,<'6.00E-02

<I 5.30E-02< 2.70E-02<i4.20E-02

.<5.70E-02

< 3.90E-02< 4.40E-02< 6.30E-02< 2.1OE-02<'4.60E-02

< 6.20E-02".6.30E-02

<5.70E-02 C-16 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)API-3 FIRST QUARTER 1,Pate dZýCtiK it 1/3/2007 1/11/2007.......1/1)7/2..00....7 1/24/2007 1/31/2007 2/7/2007 2/15/2007 2/21/2007 2/28/2007 3/7/2007 3/14/2007 3/20/2007 3/28/2007<14.OOE-02

< 5.OOE-02-'< 3.40E-02<, 3.70E-02<43.30E-02

< 4 OE-02<j6.20E-02

<36.70E-02

<'3.40E-02

<, 4.90E-02"<3.80E-02 API-3 SECOND QUARTER Date I Ctv 4/4/20071

<J4.OOE-02 1 4/11/2007

< 5.30E-02 4/18/20071

<14.1 OE-02 4/25/20071

<1 4.30E-02 5/2/2007 <15.30E-02

-5/9/20071

<14.OOE-02 5/16/20071

<i3.20E-02 5/23/20071

<14.1OE-02 5.50E-02 6/5/2007" <13.70E-02 6/13/20071

<13.50E-02 6/20/20071

< 3.50E-02I 6/26.20071.

C-17 Fermi 2 -2007Annual

.Radioactive Effluent Release and-Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)API-3 THIRD QUARTER 7/3/2007 < 6.30E-02 7 /11/2007 j4.1OE-021 7/18/2007

< 5.40E-02 7/25/20071

< 3.OOE-02 8/1/2007 < 4.90E-02 8/8/2007, <3. 50E 02 8/1 5/20 0 7 1 < 4.10E-02/21 <3.80E-02 8/29/20071

< 3.50E-02 927 < 3.8OE-02 9/12/20071

< 4.40E-02 19/19/20071

< 3.20E-02 9/26/2007 i<16.10E-02 API-3 FOURTH QUARTER Dat jiActivity~<

10/3/2007!

< 6.OOE-02 10/10/20071

< 4.30E-02.

.10/17/20071!

< 3.70E-02 10/242007 3.80E-02 10/31/20071!

<1'5.60E-021 F 11/7/20071

< 4.50E-02 1[11/14ý/200071

< 4.80E-02 1 L1:1:/2:1/20071

< 6.80E-02 11/28/20071

< 2.90E-02[ 12/5/2007:

< 3.80E-02 12/12/2007 I< 5.90E-02 12/19/2007!

< 6.I OE-021...............

12/2 6 2 0 0 7 < [........

......I..................

C-lg Fermi 2 -2007 Annual Radioactive Effluent Release and.Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)API-4 FIRST QUARTER"Date' <Ac~tiN UN 1/3/20071

<i4.ooE-02 1 1/11/20071

<r4."60E-02 1/1 7/2/007 < 14.30E-02-1/24/2007

< 3.40E-02 1/31/2007~

< 3.90E-02 S 2/7/2007 2/15/2007

< 4.80E-02[2/21/2007

< 4.50E-02 2/28/2007

< 5.80E-02 3/7/2007 < 3.20E-02 3 0 < 3.90E-02 3/20/2007

< 4.40E-02 3/28/20071

< 3.OE--02-API-4 SECOND QUARTER Da~te ~ I Activityv/

4/4/2007, <3.90E-02 4/11/2007i

< 5.70E-02 4/18/2007

< 3.60E-02 4/25/2007i

< 4.OOE-02 5/2/2007'

< 6.OOE-02 5/9/9007 < 4.20E-02 5/16/2007

<14.30E-02 5/23/20071

<13.60E-02 5/30/2007i

<15.OOE-02 6/5/2007 < 6.40E-02 6/13/2007

< 3.40E-02 6/20/2007

<.4.OOE-02

.............

6 ...........

< 6.3 E -02 C-19 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)API-4 THIRD QUARTER D~ate Aetivlit 7/3/2007 < 16.70E-02 7/11/2007

<13.50E-02 7/18/2007

<<3.70E-02 7/25/2007

<27 2.70E-02 8/1/2007 <_5.OOE-02 8/8/07 <43E0 8/15/2007

-~< 5.40E-02 8/21/2007

< 4..6E-02 8/29/2007

< 3.60E-02 9/5/2007 < 12.80E-02 9/12/2007

< 3.80E-02 9/19/2007

< 3.40E-02 API-4 FOURTH QUARTER DPale~ ;Actiivity 10/3/20071

< 5.80E-02 10/10/2007t

<,i4.1OE-02 10/17/2007, <13.50E-02 10/24/2007

<i3.80E-02

-10/31/2007

<j6.OOE-02 11/7/2007

<T5.40E02 11/14/2007

< I 6.50E-02 11/21/20071

<5.40E-02 11/28/20071

< 3.40E-02 12/5/2007

< 14.70E-02 12/12/2007j

< 5.80E-02 12/19/2007'

<1650E-02 12/26/20071

< 16.40E-02 C-20 Fermi 2 -2007Annual Radioactive .Effluent Release and.Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)API-5 FIRST QUARTER 1/3/2007 <"4.60E-02 1/11/2007

<4.3E-02 1/17/2007

<14.80E-02 1/24/2007j

<1'4.50E-02 1/31/20071

< ;3.90E-02 2/7/2007 < 4.20E-02 2/15/20071j

< 14.90E-02 2/21/2007

< 6.40E-02 2/28/2007t

< 5.30E-02 3/7/2007'

< 3.60E-02 3/14/2007

<i 3.40E-02 3/20/2007

<14.OOE-02 S<2.8E-02 API-5 SECOND QUARTER 4/4/2007, <14.00E-02 4/11/20071

< 5.00E-02 4/18/2007

< 3.OOE-02 4/25/20071

< 4.10E-02 5/2/20071

< 3.30E-02 5/9/2007 < 43. 5OE-02 F 5/16/2667~

< 4.OOE-02 -5/23/2007

<I 4.1 OE-02 5/30/2007

< 4.50E-02 6/5/2007~

< 5.70E-02 6/13/20071

<,2.90E-02 6/20/2007

<,3.60E-02

................

6/2.6/2. 007... ...............

.<...9....

.OE.. 0_2..............

C-21 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)API-5 THIRD QUARTER 7/3/2007 <16.50E-02 7/11/2007]

<_3.90E-02 7/18/2007

<,4.90E-02 7/25/2007.

<13.OOE-02 8/1/2007 -5.OE-02 8/8/2007 < 14.OOE-02 8/15/2007

<15.10E-02 8/21/2007

<'3.90E-02 8/29/292007i

< 3.90E-02 9/5/2007 < 3.30E-02 9/12/2007

ý<410E-02 9/19/20071

<13.90E-02I

9/TY26/2071

<,5.7E-02 API-5 FOURTH QUARTER Date I Activity 10/3/20071

< 5.80E-02 10/10/2007, <4.90E-02 10/17/2 0 < =T3.3o409-02 10/24/20071

<13.30E-02 10/31/200

<5.70E-02 11/7/2007

<3.50E-02 11/14/2007 3.70E-02 11/21/20071

< 6.20E-02 11/28/20071

< 3.80E-02 12/5/20071

< 5.20E-02 12/12/2007 1 <} 5.90E-02 12/19/20071

<j 6.90E-02.12/26/2007, <15. 1 OE-02 C-22 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-1 (indicator)(pCi/cubic meter)'e7 1 7.50E-02[

+1/ 1.80E-02 I 1.86E-01 4+/-/ 4.40E-02..............

.OO....< .3 0 E-02. ..........

-- { <l 5.50E-021 0~- 4 } < " 0 -3 ..................

..............................

< .9- .10 2 1 ..... .........

I ....... .. .................

SMn -54+ 2.60E-031

< 4.OOE-03ij

_Co-58 <1 4.20E-03[

< 1.20E-O21 lFe-59 < 1 9.90E-03 1 < 3.20E-021< .730E-03,.

< 4.50E-_3031 lCo i -------03[in <1 5.IO-03t ____~ 1.80E-021

____LZr-95 <1 5.50E-03 < 1: 2--02 ,ýRu-103 <1 5.10-03 .60E-lRu-106 <1 1.70E-02 <_ 3.60E-021 Cs-134 < 1.80E-03 _ <, 1.30E-03_;Cs-137 < 1.80E-03 <4 9.90E-04.rBa- 40o K7.30E-02

__ __ _ <j 3.30E-01 La- 140 < 8.40E-02 <_ I____ 3.70E-011

____Ce-141 < 6.90E-03 2.70E-02-e-1 ...................

....... Z.7._API-I (indicator)(pCi/cubic meter)Iuld h ______ IT J]4ro orhQo jBe-7 SK-40 f Mn-54 <1Co-58 <jFe-59 <1~L-o--60 7 Zn-65 <5r-9 lRu-103 <ýRu-106 <Cs-134 <ýCs-137 <[#a- 140 <!La-140ýe- 141 <~r 1.52E-01 +/- 13.60]4.0 - --z ....... ........4.20E-02 2.OOE-02 ___1.60E-03 1.80E-02 __1 ].OOE-02 I 1.I1OE-02 5 .60E-02 5.70E-03 3.80E-03 2. 110E-70.11 1.80-02 _ _E-02 7.40E-021

+/- 11.20E-02 1.,70E-026 1 .40E-031 2.60E-03 _1.1OE-02, 1.60E-03 _2.70E-03 5.OOE-03{3.30E-03I I .OOE-021 1.1OE-031 7.30E-041 6.90E-021......6..90,E,-021 5:.30E-031

_3.80Eý-03, _C-23 Fermi 2 -2007Annual

.Radioactive Effluent Release and.Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-2 (indicator)(pCi/cubic meter)1Be-7 i 1.55E-01 1-2.00E-02

_ 2.59E-01 +/- 15.00E-02 IK-40 <1 3.20E-021

< 6.20E-02 IMn-54 < 1.90E-03 < 3.20E-03 V~o:T -~~{< -6.30E-03

___-Fe-59 < 1 1OE-023 < 3.20E-02 _[Co-60 < 2.60E-03~

__ < 4.50E-031j Zn-65 < 4.90E-03 < 9.20E-03 Zr-95 <1 7.OE03 ~ <1 _1.20i-02[Ru-103 < 5.80E-03'

< 1.20E-02 Ru- 106 < I1.80E-02

____ < 4.70E-02j Cs-134 <1 2.20E-03 _ <1 3.20E-03.Cs-137 < 1.80E-03 < 4.30E-03~Ba-140 < 6.60E-02 ~ <I 3.30E-01_______

ILa- 140 < 7.60E-02 ~ < 3.80E-01 ______Ce-HI4 < ;6.3:0E031

< 2.30E-02....... ....... <.2.O E 0 2 ...........

............

Ice-144 1<1 4.90OE -0 3 j<, 2.30E-02, ____API-2 (indicator)(pCi/cubic meter)[Nj ýI id J .ý Third Quarter fýut ýBe-7 2 I.1E +/-K-4O <0 5.OOE-02'Mn-54 <ý 1.20E-03 Co-58 <1 I.00E-021[Fe-59 <1 1.90E-02i lCo-60 51 -Zn-65 .........0........

.... ............

.........'Zr-95 < 1.40E-02~ýRu-103 <~ 1.20E-0,2 lRu-106 < 4.OOE-02i rCs-134 <5.OOF-03K JCs-137 <, 4.70E-03~lBa-140 <1 1.40E-01I ICe-141 .I < 1.70E-02 -[Ce-144 d< 2.1OE-02 4.1 OE-02 _< 8.70E-02 +/- j2.80E-02 2.90E-02 .... ____< 3.00E-03<1 3.90E-03" 2.OOE-02 _< 3.20E-03 _. .....<_9.20E-031

____ I < 1.I1OE-021'

___4 <' 8.5°E-03]

j ____" 2.60E-02j" 2.60E-03" 6.30E-04<2.20E,0!]

I< 2.20E-01,.. ... .... ... .... .. ....I.. ... ... ...... ...... ............

..........................

...< 1.90E-02 ___< 9.90E-03 _______C-24 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-3 (indicator)(pCi/cubic meter)lBe-7 K-40'Mn-54 FFe-59!Co-60 li~n-65 Zr-95 ,Ru- 106 ICs- 134!Cs-137 La- 140 Ce- 141 Ce- 144 First Quai wi 1.12E-01 +1-!1.80E-02

< 2.16E-02< 1.70E-03< 3.0-T3< 1.30E-02<2. 1OE-03_< 5.OOE-03~

____< 6.OOE-03 ____< 4.20E-03 I___< 1.90E-021~

I___<2.40E-03

___<__ 1.50E-03 _< 1.20E-01< 1.4(E-0 1 ____< 6.4E-03< 6.70E-03 ____Se C': d Quia It C 4.93E-01 14.50E-02

-< 5.50E-02< 4.70E-03a--1

_<. 7.90E-03 _______I i .50E-02JI< 6.70E-03< 3.40E-03J

____< 1.20E-02 {___< 1.60E-02 __< ]4.20E-02 I____3 3.20E-03 ____< 3.70E-031

_ __<I 1.20E-01]j____

< 1.40E-01 ___7<1 2.80E-021 IH< ....... .. 6 E ..- .0 2 1..............-

...................

API-3 (indicator)(pCi/cubic meter)C-25 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-4 (control)(pCi/cubic meter)jFcl& ht uai)ter <Cl Second Quariter~Be-7 I 7.20E-02i

+/- 11.40E-02 I 1.35E-01 j+/-i 4.00E-02 K-40 <! 2.10E-02 <1 5.50E0O2L Mn-54 <~ 2.30E-03 ~ I1 .30E-03j______i <K 3.00E-03, @ __ < 7.90E-03 _Fe-59 < 6.10E-03 < 2.50E-02 _Co-60 K< 2.1OE-03 <- 5.80E-03 Zn-65 < 4.90E-03~

___ <1 1.50E-02 Zr-95 5<0E0 < ____ 1.70E-02 ___Ru-103 <j 3.70'E-03j

<____ 1.40E-02 Ru- 106 <1 .3OE-02 ~ <____ 4.20E-02 _____Cs-134 <1 2. 1OE-03? <__ 4.60E-03 j____Cs-137 <1 1.50E-03j

...... < 5.30E-03 -Ba-140 < 4.1OE-02 < 4.10E-01 La-140 < 4.70E-02~

____ < 4.70E-01 ______Ce-141 K 6.50E-03 K 2.20E-02 C ,e- -1 444 ................

< 6 .40. 3 4_0_E_ __--- 3 .8 2 ..............

API-4 (control)(pCi/cubic meter)1JTucýide

/ r Thi a~iitc5 F-Oirh, QiiiT ---Be-7 I 1.40E-01 1 +1-3.30E-02 K-40 <~ 5.70E-02 ___Mn-54 4__41IOE-03

____Co-58 < 7.70E-031

-Fe-59 < 2.40E-02 Co-60 i 5.60E-03j I____Zn-65 K <1l.40E-02 1 Zr-95 < 1 .4015O2I Ru- 103 <~ , .30E-02~ ___Ru-106 < 3.40E-02j

____Cs-134 <~ 4.50E-03j1____

CEs-137 <I 3.60E-03~

__La- 140 <1 1.70E-01I Ce-141 <,2.OOE-02

___Ce-144 < 2.40E-02 ___<F-I K 1.36E-01 3.1OE-02 4.1 OE-03 7.60E-03 2.60E-02 3.70E-03 7.20E-03 9.30E-03 7.50E-03 3.40E-02 2.80E-03 2.OOE-03+1-_12.80E-02 t......S2.80E-01< 1.00E-02< 7.50E-03 C-26 Fermi 2 -2007Annual Radioactive Effluent Release and.Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-5 (Indicator)(pCi/cubic meter)i~1i~ ~ ;~~i~s uareii ~ Second' Qui Tter~Be-7. 1.04E-0lI

+/-j 2.00E-02 1_75E_+/ 5.30E-02.................................

-- ...E :o. .................

...................

............................

...... .... ...............................................

.........Mn-54 < 2.90E-03 ..... < 5 30E-032~Co-.58 < 4.50E-03 _____ <1 2.80E-03 __F-9 < 1.30E-02 j____ < 3.80E-02 ___Co-60 < 4.E-03 <__ <- .60E-03 Zn-65 < 5.70E-03!

< 9.50E-03 Zr-95 < 1.90E-03 E-02 iRu-103 < -4.80E-03i

..........

<. 2.30E-021 Ru- 106 < 2.00- ......I_ < 3.70E-021 Cs-134 < 1.80E-03 ....... < 6.50E-03 Cs-137 < 2.1OE-03 < 4.0E-03 Ba-140 < 9.10E-021

..... < 6.20E-01 La-140 < 1.IOE-0I 7.20E-01_Ce-141 .40-03 <1 3.30E-02.......?.. -- 11 1 1 -7 .-............

.............

7 .0 E 0 ... .............

< , 2 0 E Ce-144 < 6.50E-03 <_____ _ <02 L API-5 (Indicator)(pCi/cubic meter).. .. ...e .hiirJd Quarter F .' .. ... Oua;jBe-7 tK-40 Mn-54 ICo-58 FFe-59 iCo-60 IZn-$65 Zr-95 Ru- 103 Ru-106 Cs-134 Cs- 137.Ba- 140 ,La-140 C ..... ....1 1.15E-01{

+5.1OE-021 4.80E-oo3 3.20E-021 4.50E-031 1.40E-02j 1.20E-02_9.30E-03 5.OOE-021 4.OOE-031 4.30E-031 1.70E-011........i 7 ; ..... .. ..2.OOE-01........

I .90E-02!I .90E-2--3.50E-02_Zr -6.41 E-02 1 .20E-02 1.20E-03 2.30E-03 6.20E-03 1.40E-03 2.60E-03 3 .80,E-03+/- 9.00E-03+1-3.50E-03

< 3.40E-03< 9.40E-03 1_____ < 1.OOE-03< 7.80E-04 _________ <~ 5. 50E-02 ___.< ......5.50E -02I.........................-......o..........

< 3.90E-03 773.70773_7_

ii C-27 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-2 (Indicator)(pCi/liter)

I Nucide I 18-JAN 8 I 22-FE .,$ .5-MAR. Y.1-1 1 < 7.40E-01 ___ <I 8.10E-01 <! 7.30E-01 ___Sr-89 I< 5.20E+0--

1 <- 7.40E+00 I < 6.1OE+00

£<I -iI4 E+O 2Z .........................-.

T'... ....................

<..140E+ 0...Sr-90 < 1 .40E+001 <-;1.5 OE*+OO <i 1.40E+00 Be-7 < 5.20E+- I < 8. IOE+ _...o1 01_________~~~

____j< 580E+" i, FK-40 I 1-44E+031

+/- 6.40E+01 1.28E+031

+/- 9.50E+01 1.51E+03 +/- 9.1IOE+- I 1.4E0 +/ I 6.0+<! 1 10E 0E+ 0 ...._. ........................

Mn-54 ............

-1. 'OE+0f .7 <' 8.40E+00I

.<Co-58 < 7.10E+00 < 1.OOE+01 < 7.60E+00 -i Fe-59 J .01+l < 2.IOE+01:_

___ < 2.10OE+0 I ___FCo-60 6.90E+00 ___ <ý 1.10E+01 < 9.70E+00I

___lZn-65 < I _ _ <1 2.50E+01:

< 2.30E+01_r < 1.10E+01I

_ __ < 1.70E+01 <i 1.60E+01 _FRu-103 7.00E+00, < 9.90E+00 ,< 9.50E+00 iRu-106 <I 6.30E+01 _ __ < 9.50E+01'

< 860E+/-OL I ___ýCs-134 <1 7.70E+00 ____ 9.80E+00 J _ <. 9.70E+00 ____Cs-137 < 6.20E+-00

<i 1.10E+01:

< 8.80E+00.s -.........E -6 I 1 2 ! T T I i i.. ........ ...... ... .......................

........ ..... ..........

TI ....... ..i... ...............

iBa-140 j< 8.60E+00J i < 9.70 "I0 -_____120E+011 e-"40 i< 9.90E+O0-<

1.1.E+01 _....<-I31.40E+OI--01.

[ _C-e-14 I ~ 93E0I ____ 1.30E+01 I____ 4<11E+01 Ce-144 < 3.50E+01I

-<4 _ 4.50E+01o I _1" " I 9"APR .0-MAY A Y 11-131 Sr-89 1Sr-90!Be-7 FK-40 jMn-54 Co-58 lFe-59 Co-60 2Zn-65'Zr-95-Ru-103 SRu-I106 CKs-134 Cs-137 Ba-i 140 La- 140 Ce-141 Ce- 144 J<< 9.40E-01 _< 6.90E+00 I 1.40E+001< 4.OOE+01 -5.0< 1.20E+01 +/-1< 5.30E+00 _1.40E+01 ... _<1.40E+01 1 __<1.OOE+01 I<, 5.30E+00I<1 6.30E+00 ___<1L 5.20E+00< 7.70E+00< 8.90E+001

-_

-< 2. OOE+Ob I __I<i 1<1<1<.. .......... .. ..-.....6.20E-01 _ <I 6.80Et01:

_5.40E+00 6.50E+001

_1.40E+00 I 1.24E+00 +/- 1380E-01 6.80E+01, ____ <11 5.90E+01 ___1.38E+03 +/- 7.1OE+0 I 25E+03 +/- 8.20E+01 6.50E+00, <T 71.0E+OI " 8.20E+0 <1 7.70E+00, _ ___1.60E+01 < 220E+01 1.80E+00 < 12.0E+01K 1.30 F+-0, F--<i 1.50E+01--

_--- _------7.80E+00 < 8-40E+00-" --6.40E+01 ! _ _ <1 6.70E+01 _ _7.60E+00'

____ <1 8.60E+00 ______6.60E+00 <ý 8.50E+00 _8.90E+00, ____ <1 I.OOE+01 __I____1.OOE+01 _ ___ < 1.20E+01 _ ___1-.I1OE+0h I ___ < 1.20E+01 _____3.50E+01 _ _ _ <3 3.50E+01 ____<1 <1<1 C-28 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-2 (Indicator)(pCi/liter) 1-131 -<1 7.90E-O1i

<_ 8.60E-01 _ <1 5.20E-01 FSr-89 <, 6.90E+00 _ _ <ý 8.30E+00;

_ _ 6.90E+00 _ --.... ................

.. .,< 1 .30E+00 _ _ _ <1 1.80E+00 <1 1.40E+00°Be-7 I <1 7.50E+01 _ <i 4.10E+01 j < 4.50E+01 K-40 .I 57E+03j +/- 18.80E+01 1 .40E+03 +1-l6.40E+01 1 I I.26E+03 +/- 6.60E+01 Mn-54 j<1< 9.10E+00W

<ý 5.20E+00 <M .40E+OO Co-58 I <7.70E00 <1 6.OOE+00 1< 7.30E+00 ___Fe-59 <1 2.40E+01 <-1.50E+01

< 1.70E+01 __Co-60 < 9.70E+00_

< 6.70E+00 < 6.O-E+O-..........

....... .6_ _ ._ _ .Zn-65 < 2.10E+O1 <1 1.30E+01 < 1.50E+014' i Zr-95 < 1.40E+01 <_ 1.00E+01 o--< 1.10E+O1U Ru-103 < 9.70E+00 <1 5.80E+00 <6.50E+00 Ru-106 < 7.50E+01 <! 4.60E+O1 5.40E+O1I Cs-134 < 9.20E+00 < 6.00E+O00 , 1.10E+01 Cs-137 < 9.OOE+00 < 6.30E+00i

< 6.90E+00'Ba-140 < i0E+O1 <1 1.30E+01 __ 1.20E+01O La-140 1.20E+-1 1_ 1.50E+O1 1.40E+01_Ce-141 1 <1 1.30E+011i

< 7.60E+001

<I 7.60E+00O Ce-144 <3.90E+ < 2.60E+01 "__ <, 7.60E+00 _Nuid. ..2641 .L 16- \.... 30-AUC..1-131 < 7.20E-01 _ <1 8.90E-O1 Sr-89 <i 8.00E+00 _ 7.00E+001[Sr-90 < I .40E+OO <____ K .30E+OO'jBe-7 1< 5.20E+01i

<j 3-70E+01 K-40 1.50E+031

+/- 8.20E+01 1.37E+03, Mn-54 -<_6.80E+<

<1 4.70E+00!Co-58 < 8.20E+O <i 5.0EThW Fe-59 <1.90E+01 j<! 1.30E+O1!8Co-60 9.80E+00!

<_ 5.30E+00__ _ __ -< 1.80E+O1 < 7[_ 1.IOE+ O1 S<1.E 1.40E+01 <1 8.80E+00:[Ru-103 < 6.8OE+OO1

<1 5.1 0E+/-OOi IU-106 6.50E+01 ___ < 3.70E+01: Cs-134 <1 8.4OE+OO ____ < 4.70E+OO Cs-137 < 7.20E+00{

<1 3.90E+OO Ba-140 <1.20E+O11

<1 1.20E+01t La- 140 <I1.40E+O1I

___ <I 1.40E+01 Ce-141~ <ý930Eý+OO

! < 6.--ý 50Eý+OO~Ce- 144 <j 2.60E+01I

<1 2.OOE+Oi:+1-<4i.96h-+61....--...

7.20E-01" 7.1 OE+O0_I 140E+OO1 I1.38E+03i

+/-6.40E+01-fE< 9.1OE+00 __< 8.80E+00< 1.90E+O11<1 9.20E+00!

____< 2.1IOE+O I ____<1 1.50E+01{I <1 9.00E+01 I<!I 9.OOE+O1 ____<i 9.90E+001<~ 1.OOE+O1______

< 1.40E+01< 1.50E+01 _1.30E+O1f

[-__....... ......... ...........

1...C-29 Fermi 2 -2007Annual

.... Radioactive Effluent Release and..Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-2 (Indicator)(pCi/liter)

NcI 'I, -ý44: 13-SEP I2'7-SEP I 25-OCT~1-131

!3Sr- 89 I<5.30E+00ý

'Sr90 1< 1.30E+OO0 Be-7 < 5.00E+01I K-40 I __"1.45E+03+

Mn-54 < 6.70E+00 lko-58 < 6.1OE+00 Fe-59 < 1.30E+01 Co-60 < 7.60E+00 2Zn-65 <2.50E+01 IZr-95 < i.20E+01 lRu-103 <i 7.50E+00I Ru-106 <1 6.00E+01 iCs-134 <1 7.10E+00 FCs-137 < <nL5.90E+00 lBa-140 < 1.20E+01I La-140 < 1.40E+01!Ce-141 f < i .0oE+01 lCe-144 <1 3.46E+0-6 i> 9.OOE-01.........

! .. .........

.... ....... ..8_ .69-o E + o 0 i ............

<1 8.60E+00.:

_____ <; 1.60E+001_______ Li5.70E+01

-/7.OOE+01 1 i .42E+03 +!-<i 6.50E+00_ <: 6.60E+001 I< 1.60E+01______T'8.20E+001

...........

I < 1.20E+01<i_6.80E+O0Z T< 6.10OE+01i

<I 8.70E+001___ < 6.80E+00.t.<- 1.20E+01 1.30E+01<' 1.OOE+01.<1 3.30E+01 I<4.30E-01~

________ 50E+001 ____<' 7.50E+01 7.70E+01 14EO+-88E0

______L~19.60E;00 I___<1 2.30E+01 _______I<T 9 1 40E+00 j ______SJ7~~<!.2.70E+01

___<1 9.90E+00 ___<1 9.30E+01 ______<1 1. 1OE+O1I<1 9.60E+00 _ ____________ < 1I30E+0ij-1___ _ <ý 1.40E+011

_<1 4.70E+01 _____I uc~idj, I ~I >,-N I ,13-)EC _____1 -131 <1 5.90E-01m

_'Sr-89 <8.I1OE+00I ,Sr-90 <ý 1.80E+00 iBe-7 <,5.60E+01 XK-40 i 1.53E+03~

+1-IMn-54 <S 7.1 OE+00__[&o-58 < 1 7.OE0 0E[Fe <: 1.70E+01I!Co-60 I.8E0 12n-65 <_1.70E+01 iZr-95 -<1 1.30E+01'lu11o7 <1 7.70E+001'Ru-106 <i 5.70E+01 Cs-14 <7 6.60E+00!Cs-137 i< 6.60E+00!ýBa-140 <ý 1.40E+01 -U~-140 L I .40E+01:i!Ce-I41 < 1. OOE+0 I~!Ce-144 <t 3.20E+01 I, 7.<1 7.70E-018.50E+00< --1.40E+00... 6.40E+00 60E+01 1.36E+03<1 6.90E+00-<~ 7.90E+00< 2.20E+01<~ 9.40E+00< 2.50OE+0 I< 1.40E+01_ 3.70E+00______ <1 6.90E+01___T__ 9.30E+00____ <I 7.50E+00__ _ <j 1.30E+01___ <_ 1. 3 E+0 I____1. 1.OE+0 I<I3.80E+01

...+1-....7.. ...........-I-I iJ~ -C-30 Fermi 2 -2007 Annual-Radioactive Effluent Release and..Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Control)(pCi/liter) 1111 1< 8.OOE-O 1 <___ 5.50F-011~

S~r-89 <6.20E+001

<i 7.40E00! < 6.2E+00_jSr-90 <__1.70E+0O0___

<1 1.50E+00i

<____ 1.40E+00_______

Be7 <6.20E+01I

<ý 6.OOB+O1 1 <, 4.1 OE+01 __K-40 I1.40E+03

+/- 8.40E+O1 I 1.40E+031

+/- 'ý7.0E+01

' j .34'+'03 +/- '6.OOE+01 Mn-54 1< 8.30E+00'1

<___ 7.20E+/-001

<1 6. 1OE+O0j Co-58 < 9.30E+00 K7.40E+001 1 5.60E+00~______

Fe-59 1 2. 1OE+01I < 1.60E+01~

<1_ 1.50E+01 _Co-60 <~ I .OOE+01 <'___ 7.30E+00+

~____ < 5.90E+/-00 ___Zn-65 <J 2.1IOE+01j

____ I.O+0~ ____ 17F40E+01

____Zr-95 <I 1.60E+01 K<,_1.40E+0j K1 9.90E+00I!Ru-103 <~ 8.OOE+00 <__8.OOE+OQ1

____ 5.40E+/-O+00___

iRu-106 <j 7.OOE+01 _____ .00E+01T ~ K 4,70E+0i ___Cs-134 <] 7.70E+00 1 7.90E+001

<____ 6.20E+00O

____Ba- 140 <~ 1.30E+01 < 1.20E+01j~

<___ K .I OE+O11 ___La-140 <] 1.50E+01 < 1.40E+/-01 <'I_ 1.I 20E+0I I__ ___~Ce- 141 <1 9.80E+00 _____L IiEhýt-K7 OO0E+OO0_______

Ce-144]7~<L 3.20E+Oi I K 4.10OE+01 1E+I__ __'NciU I >9-AP*R L,~ ~ 4-MvAY'1I-131 Sr-89 Sr-9O K-40[Mn-54 Co-58 Fe-59 Co-60 Z n -65§Ru-103 K Ru-I 106 Cs-134 Cs-137 Ba- 140 La- 140 Ce-141 Ce- 144<l 8.90E-01< 8.50E+00" 1.80E+00" 3.90E+O1 1.45E+03* 4.40E+00* 5.OOE+00* 1.20E+O1< 5.00E+00< 1.20E+01 K< 8.80E+00j*< 5. 1 E00*] 4.20E+01<1 5.30E+00<1 4.40E+00* 9.OOE+00* 6.40-E+00* 2.30E+OI< 6.30E-01f]

<i 8.20E-01 _ i<. 7 .0 E 0 ... ...... .................

<; 7.30E_00 8.40E+00 i <; I.50E+001 11.60E+00

_< 6.30E+01I

<1_5.OOE+01

__+/-1 5.00E+01 1.36E03 +-- 8.70E+01 -1.42E+03 +/- 670E+01___ <: 7.30E+001

<_,__ 6.20E+00 ___< 8.70E+001

< 6.40E+00 _< 2.OOE+0l]<

1.50E+0 -1_...... .................................. ...................

..... .. ...... .. ...... i ..... .......................

...i 1.80-E+001

...- <I 6.50E+00<i 1.60E+01 1---- __ <I 1.O2 E+01 j .....<_ K 8.80E+00 _ I 6 1.4 < 6.60E+/-01 <f K 5.OOE+0ýJ -l<1 9.80E+001

<161OE+001

____<__ 1 8.50E+001

-<K 5.30E+00 __.~ .. .I...< .1OE+01i __ < 1.20E+01~<1 1 ~ .30E+01 <1 1.40E+0 1 __-<1 I.0E+01 <1 7.20E+001

[ _ ]<1 3.50E+/-01_

240E+01 ....C-31 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Control)(pCi/liter)

I N -I Iý2 1 -JUNg 11-131 <18.00E-01[.

<..........................................

..............

... .7 E 0 < ..........

.....................

...... .. ...........

.. ..... ............................

..................Sr-89 < 1.70E+001 1

< 4.80E+01 __ <_11K-40 1.37E+/-03 /-1 8.80E+/-01 Mn-54 _< 8.00E+00 <Co-58 <i 8.70E+00-

___Fe-59 t < 2.3 OE+O I1 Co-60 <1 9.80E+O90l

<Zn-65 <2.20E+01

.........Zr-95 j<1 1.50E+/-01' i _____Ru-103* K 7.46E+601

<___ I Ru 2 106 < 6.2E+0 I <1 Cs-134 <8.60E+00!K Ba- 140 < 1.10E+01~

___ I <1 La- 140 <__1.30E+/-+01{

<Ce-41 <~6.80E+00I

_____Ce-<4 3.60E+OH 1_ ___ <1 7.90E-01 7.80E+00ýI .70E+00 4.60E+01: I .42E.+0..3;+1 1.90E+01~7.50E+00 1 ... ....E+.01. --7. 80E+00I I .80E+011 7 .90E+00'6.60E+01 7.10E+00t 6.10E+0W 1.IOE+01i 3.40E+01 6.90E+01.. .. ... .. ....."4.70E-01

___< O.7E+00< 6.60E+01j

____I1.41E+031

+/- 6.6013+01-<1 6 50E+00J _<I6.90E+001

____<1 1 01+01J__<6.6013+00

____<~ 1.60E+01,<7c 1.2013+01I

__<_ 8.60E+00i

____<6.30E+01~

_<~ 7.1 OE+O0 ____<6.50OE+00

<1 1.2013+01

____" 1.40E+01 ____K 1.20E+01 ____<I 3.30E+01~

__Nucid 126-R L I 0-A[G I(] L 3UGAUG 1-131 K

_ < 9.00E-01 Sr-89 < 7.90E+00' JK8.80E+00 CSr-9 <. 1.50E+001 I < .80E+00 Be-7 <K 6.20E+01 3.3 ....K-40 I 1.54E+031

+/- 94OOE+01 1.45E+030 Ru 1 3 <1 8.40E+ 0 --.0 ------------

Mn-54 1. 60E10O <4.00E+06 Co-58 Ko 7.80E+00i

___ <i 4.90E+00.....................

BFe-59 I <1.20E+01j, _ <j 1.20E+01 LCo-60 -< 1.10E+01 <1 4.70E+00 en-1 -<1 1.80E+01 t <1.OOE+01 e-145 _ <I 3.60E+01 _ K <! 8.60E+01 R-10-3 <~ 8.-30E+001

.ý=40E+00 Ru- 106 Kt 6.30E+0I 1 i < 4.0013+01~Cs- 134 <K 9.OOE+O0j

<_____ K 4.50E+00'____7 <, 8.40E+0W <, 3.70E+00 Ba- 140 <1 1.20E+01 ~ <1__ 1. 1IOE+0 I La-140 < 1.30E+01 _____ < 1.30E+01 Ce-14 K 1. OOE+0 I <!__ __ 1.OOE+01 Ce-144 3.0+~ ___ 2.'2'0E+*01

+/-4.50E+/-01 K K K K K 1.0UL+UU0 0 _7.50E+01 _1.40E+03 +/- 18.50E+01 9.30E+00 _9.30E+00 2.1OE+01 I 9.20E+00+ ' ..............

1 1 .1 -.. ............

................

... .....2.90E+01I 1.60E+01 1.OOE+O1 J 8.60E+01 _ _8.60E+00 ___8.10E+M00 1.1OE+01 11_1.30E+01 __* __1.40E+01 _ _5.20E+01 _ _7.OOE-01 8.30E+0Oj I I __________

C-32 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Control)(pCi/liter)

N uCLId 1-131 Sr-89 Sr-90 Be-7 K-40Fi!Co-58 Fe-59 Co-6-Ru-103 IRu-I 06 Cs-134 Cs-137 Ba- 140 La- 140 Ce-I 141 ,Ce-I 44 2 i~j~ 13~-SEP,<1 5.90E-01 __<1j 1.30E+00'i

____<1 4. OOE+01I 1.5]E+03~

+/- 15.80E+01--~ 5.30E+00 ____< 4.90E+001 1: ___~<1.30E+011

<, 570E+001 ____< i 1.40+1 ____<~ 8.80E+001 1~1< 5.90E+/-001 I __<i4.90E+00I

<1 7.60E+001

_____' 8.70E+O00

____<V 8 6.0E+00 ____247-SEP ~ 25-O'CT<1 5.90E-0fl<ý 5.70E+00:<~1.80E+001

<15.OOE+01 I 1.51E+031

+/<: 5 .70E+001<! 5.20E+001< 1.40E+01<i 5.20E+00!<i 9.70E+00ý<~6.i6E+C00

_______ <~3.70E-01I~____

... .......<3 7.40E+001 t<1 .50E+001-~ ______ < <6.70E+0H!__

-6.OOE+01 1.36E+03j+/-

8.30E+01<~ 7.80E+00~~____

_______ <j8.1 OE+00 1______<' 1.80E+01,_______ < jj9.60E+00

__________ {<1 2.OOE+01_______

< 1.0E+01<~ 7.30E+00 ______-~ _______ t<1 6.90E+0 1,______.< 8920E+00j.t<, 1.30E+01 ______<.~i 1.30E+O1!<~5.30E+01~

<j 5.80E+001*I 5.70E+001*f 9.90E+001*I 1.10E+011< 9.50E+001<j 1.20E+O11______ I<~ 4.40E+01J J.NuJide I 15-NO\ I I "-[-)I (-11-131 < 6.50E-01'Sr-89 < 7.40E+00 Sr-90 <I 1.70E+00 lBe-7 <1 5.10E+01, iK-40 .1.40E+031

+/-;Mn-54 <1 5.40E+00O Co-58 <I 5.60E+00 Fe-59 < 1.30E+01 ,Co-60 <i 5 30E+00 2n-65 < <' 1.30E+011 Zr-95 < 1.10E+01I Ru-103 <i 7.30E+00;Ru-106 < 4.50E+01 Cs-134 < 5.80E+00!Cs-137 <j 5.90E+001 ,Ba-140 <1 1.20E+01 La-140 < 1.20E+01ýCe-141 <1 8.80E+00 Ce-144 <1 2.80E+01i 6.00]<1 8.40E-01<1 8.90E+00 _<i 1.60E+00< 6.40E+01 _E+01 I1.30E+03

+/-/- 8.20E+01< 7.80E+00 _< 8.40E+00< 1.50E+01<l 9.40E+00< I 2.20E+01 ____,____ <1 1.40E+01I

____ <1 8.40E+00 4<~7.80E+01

____<___ _8.40E+00, I____<1 7.OOE+/-00 [ I<T_.20E+01[

__"i__I <1 1.20E+01o i___ <1 1.30E+0l1

_______I <1 4.20E+01j I ___ I C-33 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 VEGETABLE ANALYSIS FP-1 (Indicator)(pCi/kg wet)uclide 4 ~ 64L~~,ba e 2-0-JUL Lettu~ ~ Sis hr 1-131 j 4.80E+01 _ <f 4.20E+01 ,___< 4.40E+011____

.... ..... ..............

..-/ 6 ...........

..........................

........-

...... .........................

.. .... ........ -... ...................

K-40 4.30E+03j+/5.OOE+02 II6.99E+03

+-5.90E+021 4.25E+03 +/- i5.70E+02 Mn-54 < 5.I1OE+O I < 6.30E+01__

5.20E+01 Co-58 <I 4.30E+01 <_ 4.90E+01.

<...... 6.70E+01 _Fe-59 <1 1.10E+02'

< 1.20E+02 _ < 8.40E+O I__Co,-60 < 41E+.0E--1

...... -< 5.90E+0i .. 6.80E+01 Zn-6 <1 1.40E+02 1.20E+01 < 1.50E+02 ____Zr-95 <1 9.30E+01i

< 8.50E+O1 I _ < 1.30E+02-103 <- 4.1E+1 < 4.60E+1 < 6.20E+01 Ru-106 <. 3.80E+02 _ <ý 4.10E+01 <- 5.70E+02 ___Cs-134 <_ 4.60E+01 _____< 5.OOE+O1 < ____ 5.80E+01 ______Cs-137 <j6-40E 01 ___< 5.40E+01 ___ < AOE+O1 Ba- 140 < 5.80E+01 _____< 5.50E+O I ___ < 1.50E+02 __ ___..Ce -14 4 ._. ....... .9 0 E + 0 2 _ _. ........ .............

................

.......... ...< 1...-..2.6

...0.E + 10.2. ..........

.......................

..............

-..5...........

..... ...... ...._ ..,Ce-141 <j 9.30EtO01_

<ý 6.1O + 2 I t.0E+02I FP-1 (Indicator)(pCi/kg wet)~1uc ide" -T 0Aý6Bocl 777-F 3O-At( G 14tabh: e', O-AUJG Colard ,, R 1-131 < 4.30E+01 __ i <ý 4.20E+01:

_ <Be-7 << 5.00E+02 ___ <1 3 50E+02 _K-40 I 1.51E+03 +/_ 3.40E+02 2.04E+03 +/- 3.90E+021-5 .f-90E+-1 1 <1 4.30E+01O

<Co-58 <6.OOE+O1

<____ <61O+1 ___Fe-59 <~ 1.40E+02 .< 19.40E+O1 I __<Co-60 <14 9.60E+01 ___ <1 4.1 OE+O1 I ___ <Zn-65 <1.80OE+02

<____ <970+1_ __Zr-95 9.70E+01 -<I 1.20E+02 <Ru-103 < 3.90E+O I <<[ 5.80E+-011 Ru-106 < 5.90E+02 < 5.60E+i -<Cs-134 <5.60E+O I ____ < 4.80E+01I<

r i~ ~ 6....... ......................

< 6 : E + ............

..........

.... .........................

...............

-'8 6 ; 6 ..... ........................................

................

Ba-140 <j 6.50E+01 <____ 8.OOE+O1<La-140 j_< 7.50E+01 _ <; 9.20E+01;Ce-141 < 6.50E+01 _ _ < 6.40E+01 <Ce-144 < 2.20E+02 _ _ <! 2.40E+021

<5.20E+/-O1 I ____5.50E+02 +/- 1.27E+03 +- +5.30E+01 5.30E+01 _4.00E+02 5.OOE+O1 1.40E+02 _____5.80E+01, _____.......... ..+ .......................

..7.00E+01, 2.20E+021 I C-34 Fermi 2 -2007 Annual Radioactive.

Effluent Release and Radiological Environmental Operating Report FERMI 2 VEGETABLE ANALYSIS FP-9 (Control)(pCi/kg wet)Nucid ...Cl!ol-ards

=[ -JUL Re-,d Ga=bbaj;1-131 1< 3.80E+01 < 5.20E+01 <2.60E+01[

Be-7 <1 2 90E+02 I 7.70E+021

+/- 52. 1OE+02 <3.30E+02... ............

....................

.............

1 --.................

........ .............

........ ...........

7 0 + 2 ...........

.0 E 2 .............

........ ... ....... ... ..0. 0.2......

.............

....... .........

..........................................

K-40 -4.12E+03

+/-3.10E+02 4.19E+031

+/- 14.60E+02 5.73E+03 +/- 4.60E+02 Mn-54 <j 3.OOE+01E

<ý 5.90E+01 < 4.80E+01[Co-58 < 3.30E+O I < 4.70E+01i

<_ 4.20E+01__

Fe-59 < 7.60E+01;

< 1.40E+02, -<1 1.1OE+02 Co-60 [< 3.50E+01i

<_ 6.50E+01, Ký 4.80E+01 Zn-65 < 9.30E+01 <; 1.70E+021

<1 1.00E+02 Zr-95 5.70E+01 I < 8.1OE+ <_ 8.20E+01 .. .Ru-103 < 2.90E+01 6 < 6.1OE+O 1i 4.20E+01 Ru-106 ,,< 2.90E+02 <4 5.I0E+02<

4.40E+02 Cs-134- K 3-6E+ < 5.40E+01 -.5.20E+0< 3.60E_01__

<ý --,0E I4 .20E+01 Cs-137 < 3.20E+01 <_ 4.50E+01 <1 4.90E+01 Ba- 140 K 5.60E+01'

< ____ 7.80E+0B __ <1 4.20E+0 II _La-140 < 6.40E+O1 < 9.00E+01 _ <4I4.90E+01

_Ce-141 < 3.90E+01 <I 6.30E+01 5.OOE+01.e-144 [I...1.50E2..

<1 2.50E+02!

<2.40E+02 FP-9 (Control)(pCi/kg wet).Nu. .IIde ..0 .% 6 Cabbage >o. ..-A.l... N & 1.. .. .... 30-AU ... ..rse... adis. I 1-131 < 5.20E+01I Be-7 7.OOE+02 +/- 1 K-40 _ 3.79E+03 +/- 3 Mn-54 < 4.60E+01 Co-58 [ 4.80E+01i Fe-59 <. 1.20E+02t Co-60 <, 4.80E+01, Zn-65 < 1.20E+02i Zr-95 < 7.60E+0I Ru-103 <1 4.I1OE+O I Ru-106 < 3.70E+02 1 , Cs-134 i < 4.60E+I I Cs-137 < 5.20E+ Ii C§..!..3.......................

...........

<. 5...............1........

....Ba-140 6.80E+< i La- 140 -< 7.80E+01I Ce-141 < 5.90E+01 Ce-144. ._<1 2.20E+02i j 1]<1 5.O0E+01j___

.50E+02 <1 3.20E+021 1.90E+02 4.85E+03!

+/-/- ~5.0+1 < 4.60E+011<K 3.90E+01<I 1 .40E+021 _______ I<K 4.70F+01

__________ < 1.20E+021

__<___ 9.20E+011_

___<1 4.20E+01I 1 < 4.OOE+02I 1<' 5.60E+0I 1 ___K5.90E+01:I K7.OOE+OI1 I<; 8.OOE+0I<K 5.40E+01_____

1 .70E+021-_< 4.90E+01 3.20E+03 02 I4.06E+03-< 4.0E+01<: 4.70E+01<7 1. OE+02-< 5.70E+01< 1.1 OE+02<' 9.50E+01<K 4.20E+014.70E+02<K 5.50E+01<1 5.90E+01< I O.OE+02<K 1.20E+02<1 2.40E+02+/-+/-12.50E+02+1-:3. -o+2 C-35 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-I (Indicator)(pCi/liter)

~Nitch~ide 31-JAN / 8F ~ ~ A28,-MAR GR-B 4.1OE+00 +11 1 .E+00 1 6.40E+Oo0

+/- 1.30E+00 <i 3.10E+00_Sr-89 <8.OOE+/-O i < 7.70E+00.

j <1 5.50E+00O Sr-90 < 1.50E+00 ___ <K 1.80E+0 < 1.40E+O0 K-40 470E+Ol < 6.20E+01 1 Be-7 56E0 ,<ý

.0+1i n-40 < 1.00E+02 _ <K 1.00E+021 , < 9.90E+01 _Mn5 8.20E+00 <; .40E+00 < 7 OOE+COO....5. ...... i ................

.... .......T ... ...........

....... ..20 + 0 ... ..............

........6 0 + 0 .. .....Co-8 <j6.60E+OO

____ .0+O ____ <1 7.6OE+OO 0_ ____Fe-59 < 1.40E+0_ <K 1.20E+01l

< 1.40E+0_1_

Co60 < 8.80E+00 < 6.90E+00;

___ K<i 9.40E+001 Zn-65 1.50E+01 <: < 1.60E+01+/-O i I < 1.70E+,0_l

_Zr-95 < 1.40E++01" < 1.10E+011 1.30E+01l Ru-103 I<. 6.40E+00 I <i 6.60E+001

_ < 5.50E+00O Ru-106 < 6.40E+01 <_ < 5.50E+01 _ _ < 6.70E+01 Cs-134 < 8.70E+00 < 6.70E+00 __<_ 7.30E+00 Cs-137 < 7.70E+00 < < 6.70E+00!

<_ 7.20E+00 Ba-140 < 1.20E+O1 <K 1.10E+01 <, 1.20E+01 La-140 < 1.40E+01 _ <I 1.30E+01!

__ K< 1.40E+O1 Ce-141 < 9.OOE+0[ 8.l6E+001

<, 9-40E+001 Ce-144. <1 3.40E+01 K 3.OOE+01 _ < 3.40E+01 Nuld W-5T~R 3-MIAY j:.U GR-B < 3.1 OE+00 Sr-89 .. < 4.60E+00 Sr-90 < 1.40E+00 Be-7 < 3.70E+01 K-40 <j K7.50E+01 Min-54 <1 4.50E+00 Co-58 < _5_ 4.60E+00 Fe-59 < 1. 1.OE+01I Co-60 < 5.50E+0O Zn-65 <K 1.20E+01 Zr-95 < 7.60E+00 Ru-103 < 5. OOE+00 Ru-106 < 4.90E+01 Cs-134 < 4.90E+00 Cs-137 < 5.50E+OO Ba-140 <1 < 9.70E+0O La- 140 -1.1OE+01 Ce-141 <~ 6.70E+00 Ce- 144 _ tK2."IOE+01I

....................

....................

.. .... .....~~Lir 3.20E+001 IK .60E+OO!i____ r7.60E+001

___I [160OE+O001-

<1<i K1___ K<1~.. .. .. ... .. .....<i<i 4.50E+01, 4.30E+01'5.1OE+00 5 .70E.+O.O.! 5.60E+001 5.60E+001 1.30E+01i~

.... l-If -.... ...... ........5.90E+00 5.OOE+0l.-j 5.50E+001 5.50E+00i K~3.1IOE+O001 K6 20E+OOT ___________ <_ 1. I70E+00 ____2 2.80E+01 _____ <1 6.90E+01,l

_ _ ___ _ KýL 3.20E +0 ____________ < 8.30E+06 _____________ <1 4.20E+00 _ ___K7.30E+00j

_____ 1 6.60E+00 __________ <1 4.1l0E+OO

____~< 6.60E+00j

_______ <i 83.0E+00 __ _1<1 8.30E+OO0

__<1 69.0E+00 ____<1 6 90E+00I C-36 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-1 (Indicator)(pCi/liter)

NJuclidlý

., '>25-JUL *.29AG >28-SEP~i GR-B 3.30E+00 +/- 1.OOE+00 <' 2.80E+00 ___ 7.1OE+00 +/-_ l.20E+00 Sr-89 < 8.80E+OO < 8.70E+0 < 8.00E+00 _Sr-90 <1 1.40E+00 < <! 1.60E+00, _ <_ 1.70E+00 _Be-75.70E+01

_ <4 5.00E+01 4.1OE+O1 -.IK-40 < 9.90E+01 ___ < 1.20E+02 L< 7.30E+01 M n-54 " I 7-.20E+OO i "<i 5.7 -0E+O .....................

3_.... 9. 0E+ .................................

O.........

...... ...........................................

.~ii 6 + 6 ............

....................

...........

.............

.......... -i + ............................

.. .! .............

8 E 0 .Co-58 < 6.2oE+0 _ <1 6.50E+001

< 4.80E+00 Fe-59 < 4- 1.0E+01 Co-60 <- 7.50E+00 <_ 7.1OE+00 5.O0E+00 Zn-65 <I 1.70E+01 "_ < 1.20E+01 < 1.30E+01 Zr-95 < 1.30E+01 _ < 1.1OE+01 < 8.30E+00 .Ru-103 < 8.30E+00+/-

<' 5.80E+001

< 6.50E+00+/-Ru-106 < 5.80E+01 ___ < 5.80E+01 < 4.60E+O1 I Cs-134 < 7.20E+00 < 6.50E+0 < 5.20E+00 _Cs-137 < 6.60E+00 _ < 5.70E+00 _< 4.OOE+ 00 ___Ba-140 < 1.30E+01 < 1.20E+01 --< 1.1OE+O1 ____La-140 < 1.40E+01 1.4E01 < 1.30E+01 _Ce-141 < 1.20E+01 <_ 8.10E+001

< 9.80E+00.......................

ii fi ....... ....... .......................

..........

iiiil? X ii iiiiii~~i

= : s .......................

..... ..... ............... " _ -; .. .ii ..........

....."...........

[Niiclide:

~28-NOV 26-DEC GR-B 6.40E+00 Sr-89 7.20E+00 Sr-90 < 1.40E+00 Be-7 < 5.10E+01 K-40 < 1.00E+02 Mn-54 < 5.70E+00 Co-58 < 7.1OE+00 Fe-59 < 1.40E+01 Co-60 < 8.50E+00 Zn-65 < 1.60E+OI Zr-95 < 1.1OE+OI Ru-103 < 7.OOE+00..............

....................

--Ru-106 < 5. 1OE+O1I Cs-134 < 7.I1OE+OO Cs-137 < 5.90E+00 Ba-140 < 1.1OE+OI La-I40 <1 .10E+01 Ce-141 < 1.1OE+O1 eL-44 .L 3.50E+01 K 1.20OE+00 4.50E+01)

ý/- 11.10E+0< 6.1OE+00_______ <' 1.50E+OO<1 7.00E+01'< 8.1OE+00< 7.20E+00.S I 1.50E+01< 1 7.90E+00_ < 2.20E+01_ < 1.40E+01 i < 1.10E+01.< 8.20E+01I< 8.90E+00< 7.50E+001<i 1.20E+01<I I.20E+01______ I<1 1.30E+01.< 4.50E+01.0 j < 3.OOE+00< 6.70E+00--=< 1'70E+00< 5.40E+O1 f7<9.80E+01

< 6.60E+00< 5.60E+00< 1.50E+01< 6.00E+00< 2.60E+01< 1. 1IOE+OlI--F< -6.70E+00< 6.80E+01...........

---

< ---g] 6 +--< 6.90E+00< 7 1IOE+OO<1 1.30E+01 S.3O0E+Ol< I.IOE+OI<. 3.60E+01... ... .. .. ........-r-t _________

Fermi 2 -2007 Annual..Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-2 (Control)(pCi/liter)

I -.ide F 2YEB~ bk 28MA GR-B < 3.20E+00 <{ 3.OOE+00, _,,__J 9.30E+001

+1-1,.30E+00 Sr-89 < 8.40E+00 _ < 7.70E+00j

_ <I 6.70E+00I1 Sr-90 < 1.60E+00 _ <1 1.80E+001

_ <1 1.70E+00!

_Be-7 <6.0E+01 < 5.OOE+01I 6.80E+01 K-40 < 7.90E+01 < 8.70E+011 0_<i10E+02

_..4.... ...............

.. ........ ........ ... ... ....... -§0:-58 <. 6.OOE+00 ___ _ <. 6.60E+00 1< 7.2 6 E+O O 6 _____IFe-59 < 1---.... < 1.70E+01 I < 1.30E+01 ICo-60 < 6.60E+00 ___ _ <I 5.60E+00 I ~ 6 -50E+00 _____Zn-65 < 1.80E+01 ___ <1.80E+01 1.70E+03j Zr-95 < 1.10E+01 _______ < 1.20E+011

____ <1 1.30E+011

____Ru-103 < 7.1OE+00 <1 8.20E+00 1 "__ -_ < 7.20E+001 Ru-106 < 5.90E+01 <I7.OOE+01 I <___ 6.20E+01 ___Cs-134 1< 6.70E+09I

_ _ < ?.OOE+Oj <ý 7.40E+00 Cs-137 < 6.OOE+00I

____ <I 5.70E+00 <1680+0"C s--l3=i- -l < --6I6 E ...............

...........

1 < 5170E 0 < i.68 0E.-.-....

.... .... ......- ... ............

Ba-140 1< I __ --<_ I< .._0E01I <I 1.30E+01 _La-140 I + <I 1230E+01I

_ I <1 1.50E+01;Ce-141 <1 9.50E+00 <I-- <1 9.80E+001 I <1 I.1E<01 _Ce-144 < 3.60E+01 -144 3.40E+0 < 3.90E+013

.I~ucide"I 2~-AP I ~ 9-MA v ~ I 2-j~U1[GR-B[Sr-89 Sr-90 Bge-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru-103 Ru- 106 Cs- 134 Cs-137 ,Ba- 140-La-140 Ce-141 ECe-144_L7 1<1<<1 t 3.60E+0 +1- 1(.1E+00 5.1OE+00 1.70E+00 6.40E+01 _1.00E+02 _6.90E+00 8.30E+00 1.40E+01_6.4 0E+00 1.70E+01 1.40E+01 9. 1OE+00 7.80E+01I 6.90E+00 ____6.80E+00 ____1.20E+01 1.40E+01 1.OOE+01 ____<..........

<i<<<1 3401 001 720EF+001 1 .50E+00I 5.90E+01 _9.1OE+011<3.l0E+00)

_______~5.90E+00~

_I-1-5.40E+001I

,_6.50E+00-1.60E+011

______5.60E+001

__5.60E+ 00, 1.60E+01f

____9.6~f 0 E+0_.................

7 .i ~ ; 6 ~ ...........

O E 0 ......................................

...7. 1 OE+00I 6. 1 OE+0 1 ___6.OOE+001

____6.30Eo+oI

__9.80E+01 ____].I OE+01<I 1.60E+00 _"~ 2.80E+01j" 5.OOE+01 1 _<1 2.70E+001<_ 3.1OE+00 1 _< 7.40E+00!<1 2.70E+00 _<1 6.OOE+0& ____< 5ý.70E+00

____<!I 4.1IOE+00

___...... 6 6i.........

... ...... i ...... ..........

...................

<i 2.80E+00<1 2.70E+00 ..... ___8.90E+00ooo

<'I 1.OOE+01:

__<1 6.60E+00 1 _<1 1.50E+01 C-38 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMH 2 DRINKING WATER ANALYSIS DW-2 (Control)(pCi/liter)

Nuclide 25-Rt 11 4' 1 2-AUG -' ý28SEP GR-B <1 2.90E+00 <____ <3.20E+00!

<____ 3.1 OE+00I Sr-89 < 9.OOE+00 <____ K 8.40E+00 <____ 7.60E+00 Cr-90 < 1.40E+00 ____ <1 .50E+00';

<____ 1 .60E+O00 Be-7 <5.70E+0 I <___ 5.50E+01 ____ <I 3.70E+0i: K-40 4< 9.40E+0 I <~ I.OOE+02ý 6.57E+00I Mn-54 < K 5.90E+00 < 5 60OE+00< 37Ej0 Co-58 j< 5.80E+00 ~____ 6.190E+00i

<' 4___ 1< 4OE+00 1 Fe-591 1.40E+01 1____ 1 .30E+01~ 8.30E_ __00__Co-60 < .80E+00 <____ K7 .70E+01'i

< 4.40E__00 Zn-65 K 2OOE+011 < 1.40E+01 K 8.40E+00 Zr-95 K 1.OOE+01 <, 1.30E+01i

< 7.60E+00~Ru10 K620f+00 ____ 6.20E+00'j~

5.20E+00, Ru-106 K 7.70E+01 6.OO+0III

< 36EO Cs-134 < 7.80E+00 ____ <1 5.60E+001

<1___ K 3.70E+00 ___Cs-137 1< 6.30E+00 K; 7.OOE+00l

<____ 4.OE+OO _Ba-140 < .0+I6____

_<1 1.I1OE+OH I ___ < 1.20E+01~

___La- 140 < K1.40E+01~

<_____ 1.20E+01I I~ i40E+0V ___Ce- 141 < 9.50E+00 < ____K 9.60E+001T

____ 7.56E_001 Ce- 144 K[ 3.0+1 3.30E+01 < 2.20E+ 11 Nuwclde +/- <3ACV/'28ý-NOV

~<27-DEG 7 >.LGR-B Sr-89 Sr-90 Be-7 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru-1 03 Ru-106 ICs-134 JCs-137 B1a- 140 La- 140 iCe- 141 Cýe-I1 44.4.50E+00 7.60E+00< 1.50E+00< 5.40E+0I 1-,-<" 8.60E+0I< 5.80E+00< 6.1OE+00<, 1.20E+01< 6.90E+001< 2.40E+01J< 1.00E+01< 6.1OE+00< 5.70E+01 1--.........

t "< 1 60. .0.K 7.30E+00 1.20E+01.1.20E+01 K 9.OOE+00 ,__ <1 3I.I.OE1+OI..

+1- 1.OE+00 [ 4.80E+00 +/- 1. IOE+0O<__ f7.30E+001

_________

1.70E+00 K < 5.50E+01~______ < <9.50E+01

_______ ____<__ 8OOE+OO _____< 6~ .90E+00!~

__<K 8.90E+O00

_K .IO E+ 0I1 __________ K1.30OE+01, ___<___i7.90ýE+-01L

_0_< 5.90E+01!<i 9.20E+00:

_______________I

<! 8.OOE+00 _________ < I1.40E+0I1~

j< 1.40E+01I

___-_______ < 1.30E+I ___<ý 4.40E+1 ___<1 2.90E+00<. 6.00E+0O" 1 I.50E+00~<i 6.1 OE+01I<I. 20E+02 K 7.50E+005;

<~ 9.OOE+00'K" I.60E+01i" 7.40E+001"~ 1.70E+Olj1"j 1.20E+01'"1 7.90E+00i<1 5.70E+01:<1 7.60E+00,<1 5.90E+O0t K4 1.50E+01!<1 I. 5 E+01I<; 8.90E+00 K~3.40E+011

.. .. .. ... .. .C-39 Fermi 2 -2007 Annual Radioactive Effluent Release. and Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-2 (Control)(pCi/liter)

'Sr-89 <i 7.80E+00[Sr-90 < 1.40E+00'Be-7 < 4.50E+01 K-40 < 7.20E+01 Mn-54 < 5.60E+00 Co-58 <1 5.1OE+00 Fe-59 <,1.OOE+01 Co-60 _< 6.60E+00 Zn-65 < 1.50E+01 lZr-95 < 1.00E+01 Ru- 103 ___6-0_--_

13 < 5.60E+00 Ru-106 <. 5.OOE+01 Cs-134 <: 6.60E+00 Cs-137 << 5.60E+00 Ba-14P0 <1 8.70E+00 La-140 <F 1.00E+01 iCe-141 <1 8.70E+00 lCe-144 I'< 3.E+01.A I 28-FEB i 28-M!~AR $j~...........

... .................

............

<i 6.70E+00<i 1.60E+00<1 5.40E+01<1 7.30E+01<i 5.50E+00< 6.40E+00;<I 1.20E+01<1 6.1OE+00]"<[ 2.40E+01i<1 1.00E+011< 6.00E+001< 5.201Eý+0<16.OOE+00ý

<I 6.70E+00<1 1.1OE+01<I 1.30E+011<I 9.60E+00[< 3.20E+01i<t 6.60E+00 1.60E+00_ <I 4.80E+01 I <i 8.00E+01 II < 6.30E+00.< 6.70E+00< 1.20E+01< 8.OOE+00 T <i1.50E+01

_ <I 6.70E+00<- _ 6.30E+01< 6.70E+00<6.40E+00< 8.70FE+00.........1.00E+01 9.50E+00 3.70E+01 Sr-89 <i 5.OE+00. < 4.30E+0O_

7.70E+001 Sr9 __ ___ <,-_4"0E+---,,0

__ ____ 4 7.70E+00 Sr-90 <[ 1.40E+00{ -I 1.30E+00 I-<1 60E+00 Be-7 <1 4.OOE+01 j ,_ <1 5.00E+01 _ <___ý <7.20E+01 K-40 < 5.60E+0 < 9.90E+01 1.00E+02 Mn-54 < 4.60E+0i <0 5.30E+00-

< 7 IOE+00 Co-58 < 4.30E+00 < 7.1 OE+06 ___ < 8.OOE+00 Fe-59 < 8.40E+O0 <1 1.70E+01 < 2.00E+ -Co-60 < 4.20E+00 ___ <1 9.20E+00:

< 7.70E+00 Zn-65 < 9.20E+00 1 ____ < .+< 1.60E+01 tZr-95 <1 7.20E+00 <1 1.20E+0<i 1.50E+01<Pu-10 < 5.30E+00 <1_......

<I 8.30E+00 1.00E+01 Ru-106 _< 4.50E+01 1_ < 7.30E+01.

< 780E+01 Cs-134- < 5.3 0E+00 ____ _ 6.70E+00 _< 6.90E+00 ICs-137--

<* 3.60E+00 < 6.<50E+/-001<[

7.00E+0~ i O ......~ ~.........

......................

....96

..........

i..........

.....................................

< [ 5 + i ... ...: .............

..................................

! ............

..... < ...........................................

13 E 0 Ba-.140 < 8.90E+00.

...1.20E+01-

<1 1.30E+01 La- 140 <1.OOE+01I 1.30E+01 <i___ 1.50E+01 LCe-141 < 7.30E+00 I< 1.10E+011

_ <-1__ 1.30E+01 FCe-144 < 2.30E+0 i <I 3.70E+01;

__ <1. 4.20E+01 (a) Grab sample, see Appendix D, Program Execution.

AY-t...........

..............

..........

---

C-40 Fermi 2 -2007Annual Radioactive Effluent Release and.....Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-2 (Control)(pCi/liter)

Nuclie 26JL< 8 29-A+JG Sr-89 <1 5.30E+00 Sr-90 <T i.40E+00O Be-7 < 2.90E+01O K-40 <1 7.40E+0OIl Mn-54 <i 3.80E+001 Fe-59 < 9.20E+00 Co-60 ! < 4.40E+00< 7.20E+00O Ru-103 <! 4.30E+00 Ru-106 <3.20E+01 Cs- 134 < 4.20E+00 Cs-137 < 3.90E+00O Ba-140 < 1.10E+01[La-140 < 1.30E+01 JCe-141 <1 5.50E+00 Ce-144 ,1 1.50E+01{<{ 8.70E+00< 9.70E+O1_< 8.50E+00... ..............................

.....................

.... ........<i 7.40E+011____ <! 6.90E+001< 7.90E+00< 1.70E+O11<i 1.30E+01____I< 8.60E+001 I<1 7.60E+01<ý 6.90E+001< 6.9OE+OO'....... .........1.20E+ 01<ý 1.40E+01,< L.7OE+01_<~ 3.70E+01j< 8.90E+00<1.60E+00 I

___ 9.80E+01 7.80E+00,.......................

1.... < 7- 50E+O .-- =~ ...... .. I; .....+...<...............

E< .. + .0..I- ......< 8.50E+00____I i90E+01< 7.00E+01< 7.40E+00< 7.3OE+OO 1. 1.OE+Ol I< 1.20E+01<__ 1.20E+/-01[Nuc~j~lt J ~ 28-SEP _____Sr-89 <i 7.20E+00 I <j 8.40E+00!Sr-90 <, 1.50E+00 1 <.70E+001 Be-7 3.50E+01 _ <1 4.OOE+01 K-40 < 7.1OE+O1 < 6.90E+01 Mn-54 < 4.50E+00 _ <_ 4.50E+OO Co-58 < 3.90E+00 T-<1 4.10_E+00 Fe-59 <I 9.O0E+00 <ý 7.60E+OO Co-60 <j 4.50E+00 _ _ < 4.90E+00 Zn-65 <i 1.80E+01 _ <I 1.80E+01 Zr-95 <i 7. 10E+00 <1 8.00E+00, Ru-103 < 4.50E+00 <j 5.10E+001 Ru-106 < 3.20E+O I < 4.40E+O1I Cs-134 < 4.50E+00 <z 4.70E+00{Cs-137 3.90E+00O<

5.60E+00 Ba-140 < 1.1OE+O1 < 9.40E+00.La-140 < 1.30E+01 < 9.40E+00: Ce-141 < 5.90E+00 <z 7.00E+OO Ce-144 < 1.660E+01_

_ -<- < 6 2.60E+01 (a) Grab sample, see Appendix D, Program Execution.

C-41 C': -I+@";_ <1 1.20E+01 S<F573o+oo

<1 7.30E+00{<'1 7.10E+01" 7.00E+00...... ... ...........................................

...... ... -......-< ...T .... ---.......t< 1.00E+01< I.OOE+01< 1.20E+01___ 4. < 1 41E+0I--- -----... ..... .

Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-2 (Control)(pCi/liter)

[Nul~idej I 28-NO\V I____ 2&DECN ('___Sr-89 <1 5.70E+00 -Sr-90 <1 1.40E+00 ,Be-7 <! 5.40E+01 -K-40 <7 1.1OE+02: Mn-54 <1 6.20E+00 Co-58 < 8.OOE+-0..

Fe-59 <1 1.70E+01j.Co-60 <, 5.70E+001 Zn-65 <I 2.40E+01i Zr-95 I. 1.40E+OI.Ru-103 <' 7.90E+00OýRu-106 <1 4.80E+OI1 Cs-134 <i 7.50E+00.. .... ...7...50.E .0.0.Cs-137 <1 7.90E+00 it Ba-140 <I 1.30E+01'La-140 <I 1.30E+01 Ce-141 <1 9.60E+001'Ce-144 < 3.1IOE+OI< 1.50E+0 0 ______.<i_

1.00E+01~

___<5 4.40E+OI {<1 9.20E+00 I_____ _ <i 5.70E+00O

...... 5.60E+OO<___ 9.90E+00 1.40E+01 2_ 71.0E+0O< 1 5. OOE+O1 I<1 6.20E+001{

<~ 5.70E+00___ 17 .40E+01J __< 1740E+OI I<, 8.50E+00 { __<! 2 10E+01 C-42 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-3 (Indicator)(pCi/liter)

NUChide ,,-JA~1j~

8FEBi ~ 28-MAR ISr-89 <1 8.40E+00ý

<{230E+W0

___~< 5.60E+00I[Sr-90 <i 150E+O0 ____ <~ 1.70E+f0 ____ I 40E+00f ____Be-7 <5.60E+01........<

4.90E+01:47E+l K-40 <I 9.90E+0f I ___ <ý 9.30E+01:

_____ <1 8.30E+011j____

Mn-54 < 8.20E+001

< 6.1 OE+00 __ < 7.70E+00______

Co-58 I <1 6.6 0 E+ 001 _____ < 6.20E+001 I___ <_ -630E+00[F_____

[Fe-59 <~1.40E+01

< 1.30E+01 ~ < I 50E+0Iý!Co-60 <7.60E+001

____ < 8.20E+00i

____< 7.80E+00 ____jZn-65 1< 1. 80E+01I ___ 1.40E__01_

_____ __ý 1.6E+01 ____Zr-95 < 1.1OE+01~

___ <! <.O+B ____ ____103. 15EO ____ 11 I OE+/-01i____

Ru-~103 <67.50E+00

_ __ _ <1 5.410E+001 6'60E+00~Ru- 106 < 6.90E+01 <6. OOE+OH 11<60+O ______________________~~

I__________

__ <1 6 60E+OQ ___Cs-137 <~ 7.30E+00j

____ < 6.OOE+00 ______ < 7.10E+00ý

____tBa- 140 <1 1.30E+0ý1

_ _ _ <' 1.00E+01 I _ _ _ _ < 1.30E+01_

__ _La- 1 4 0 < .50E+01~ __ ._ <1 1.20E+011

_____ <__ _ -1.50E_01!

e-141__ < 9.40E+0011

___ <~ 7.50E+00 <1 8.40E_00_Ce- 144 .0+II<13OE

<39 E. ,.. .. .. .... .. ... ... .... ... .... .... ............ ............' .... .... ... I .................... ...................tSr-89 I <1 4.90E+001

___[S-90 I<1 1.50E+001

__te-7 !< 4.OOE+O1 .I tK-40 < 6.80E+01 __Mn-54 < 4.80E+00M

___Co-5-8 < 4.40E+00._______

Fe-59 < 9.90E+00!

___Co-60 < 5.60E+00!

____Zn-65 <1 1. 20E+0 I ____Zr-95 < 7.50E+00 ____Ru-106 < 5.I1OE+00I Cs-134 <, 4.90E+ý00;

__Cs-137 <j 5.1OE+00,_o______

1Ba-140 j<t 8.80E+001

_ILa-140 < 1. 00E+0 I ___[Ce-141 < 6.0E+001[e144 1 <12.40E+011

____<1 8.20E+00;, I< 1.70E+010

_<. 4.60E+01oo-

<6.OOE+01l;ý

<i 5.80E+00 _<1 6.40E+00 i.<. 1.40E+O1 ___<1 6.OOE+00 ____<1 1.20E+01.!~___

< 1.20E+01 ____<1 4.70E+01:< ' 7.40E+00< 6.4E+00, -< 1 1.20E+01 __ _<1 1.30E+01, _ ___< 8.90E+00 -ý< 2.80OE+01, __I <1 5.OOE+O0t 1,____-<1 1.30E+001 I _*2 215E0ý i___*-s 5.50OEt+

I<j 3.0OE+00 ____I <1 3.20E+001

____< 6.60E+001j____

<~2.90E+001

_____I~ <152E+001I____

1 <1 2.80E+01; I____< 3.OOE+005

__< 2.90E+00, ____< 6.90E+00'

__< 7.90E+00 1 --<1 5.50E+0O1 I ____) .6E+011 C-43 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-3 (Indicator)(pCi/liter)

Nucid 2()-AU 81 SEP: : Sr-89 <; 9.20E+00 <( 9.40E+00 _ <_ 7.20E+001 Sr-90 1.40E+00 _ < 1.70E+O < 1.50E+00 Be-7 < 4.90E+01o

<1 5.20E+01 < 3.30E+o01

.....__K-40 < 8.80E+011 I < < 8.30E+01 __ _ <1 7.50E+01 Mn-54 1< 7.90E+00I

< 6.40E+00i

,1 [< 3.70E+00 Co-58 <8.10E+00

<! 6.70E+ <! 3.70E+006 Fe-59 +01 1.40E+01;

..........

Co-60 < 7.70E+00 _ -- 1 5.90E+00 _ -< 4.50E+00 Zn-65 1< 1.80E+01 ___- .1. 70E+O I i- l-- _ <1 1.50E+01 _Zr-95 <1 1.20E+01 <. -_'" <I 6.70E+00-

<Ru-I 03 < 7.50E+0.........

7.2.E+OOM

_______..

<1 4.50oE+o00 Ru- 106 < 7.20E+01 __ __ _ <i 5.5OE+O1'i

<1___ 3.70E+01 ____Cs-134 < 7.80E+00 _ <7 I <_ 3.80E+O)-_

Cs-137 <1 7.1OE+00 __<_ 5.70E+001

___ <i 4.00E+00!Ba-140 J 1.10E+0 I 9.30E+00j

<, 9.40E+00 __ _La-140 120E+01 < 1.10E+011 1.1OE+1 I Ce-141 _ _ <_ 8.10E+00 _ < 1.OE+Ol1 I <ý 9.20E+00 Ce-144 I 3.30E+01 _ <i 3.80E+01I

........ 26-DEC~ ~Sr-89 I < 7.1OE+00I Sr-90 < 1.40E+00O Be-7 < 4.40E+0 1__K-40 < 9.30E+01 Mn-54j < 7.OOE+00 i Co-58 < 5.80E+001 i Fe-59 < 1.60E+011

!Co-60 ,< 8.00E+00 I Zn-65 < 1.20E+01 I Zr-95 < 1.10E+011 Ru-103 < 5.70E+001 Ru-106 <, 6.10E+01 Cs-134 < 7.1OE+00 Cs-137 < 6.50E+00 Ba-140 < 1.40E+01 La-140 I <1 1.40E+01 Ce-141 < 8.80E+00 Ce-144 3.00E+0 11/2"'I <!. 5.70E+001-__<I 1. 1OE+021-<K1 5.80E+00j<1 5 90E+001___I<! 1.50E+01I< 6.30E+00,<q 1.70E+01'I I1 .1OE+I_1_71 -5.5-0E+001

<1 5.40E+01]__

I<i 5.90E+001<1 6.80E+001<i 8.50E+001<__ I< 2.80E+01I________ <~ 6.OOE+00 ___________ < 1.50E+001

_____<~ 5.60E+0I _ ____<7.50E+01_______

<5.30E+00,<1 5.60E+00 ____I___ <1 1.30E+01 j__I<1 7.90E+00J_

_ _ ________ <~ 1.60E+01 _____< I 120E+01 ___<1 6.60E+Oý I _________ < 6.20E+011~____

<1 6.40E+001I

______ '6 6I10E+OM--___ <1 1.5,0E+011j

< 6 2.0E+00]__

__<ý 6290E+01J C-44 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 DRINKING AND SURFACE WATER QUARTERLY COMPOSITE SAMPLES Tritium (pCi/liter)

[Itaio< [7 _______ Q"I' [et ýe&ýiic Qu rL IDW- I 4.-2OE+O02--ý

ý _____ -4.60E+02

______4 _____ _______ 40E+01 ___DW-2 A 'I _21 < 4.6 _iSW-2 .<1 4.20E+02, a____ 46E0 SW-3 E36+O2= _____-- '4.OEO -- ___[Statioii Thr Qufi; [ PoL1iL11 uarteri DW-1 <1 4.8 OE+O 2 tj*DW-2 < 4.OEO2 ISW-2 i < 4.70E+021 1SW-3 i < 4.80E+021 (a) See Appendix D, Program Execution.-i< 430E+02 1_____<j4.30E+021

__<i 4.30E+O02 1(a)<z 4.30E+021 C-45 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-I (Indicator)(pCi/liter)

Be-7:K-40;Mn-54!Co-58 Fe-59'Co-60.Zn-65.Zr-95'Ru-103!Ru-106.Cs-134 ,Cs-137 ,Ba-140 iLa- 140'Ce-141 lCe-144;H-3<ýý 1.20E+02 ______ <1 1.OOE+02{

_<: 6.90E+00_______

<1 5.80E+00j<$ 7.30E+001<

5.60E+00j

_<~ 1.60E+01__

_____ <14E+01<1V1.10E+01:

< 7.40E+00J<1 1.80E+0i 1.30E+01, iý .30E+01 < 1.i1OE+01

_<~ 7.60E+001

____ < 6.70E+00~<j 6.60E+01 4.90E+011<6.30E+0O

____ <~ 6.40E+001<1 6.80E+00 1 <~ 6.OOE+00__

1._11iOE+01 I ___ < 1.30E+01<11.30E+01

-1___ <.50E+011<~9.1 OE+00 ___ <j 8.70E+00I<1 3.20E+01 I __ <__ 2.80E+01~<+ 4.30E+02i

<____ 4.j30Ej02__

kN.,ýuicde I 'Ih tL~i dOuia~ter I Fo( Vthrih OultA!Be-7 X-40'Mn-54 Co-58 Fe-59 Co-60'Zn-65'Zr-95 Ru- 103 Ru- 106 Cs- 134 lCs-137:Ba-140 La-140 iCe-141!Ce- 144 11-3<i 3.90E+01 _<~8.60E+01

.......................

<i 4.90E+00.< 4.60E+001 I; iOE+01 ____4.60E+001

_ _<1 2.OOE+0i <1 9.I1OE+00< 4.70E+00i___

4 t .40E+01<1 5.OOE+00:

____.............

............

..... ....... .. ..... ......< 4.30E+001<1 1.20E+01 ____i<~ 1.40E+01 __<1 7.40E+00<2.00E+01 1 ___<i 4.40E+02 ___I < 3.40E+O01;

<1 6.60E+0O< 3.70E+00.< 4.10E+00< 9.30E+00< 3.80E+00 _<1 9.70E+00< 7.30E+00< 4.80E+00.<3.90E+01< 4.20E+00<3.70E+00~

<1 9.30E+00,<1 9.30E+00<1 1.1OE+0i<2.20E+01< 4.30E+02, I C-46 Fermi 2 -2007Annual Radioactive Effluent.

Release and Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-2 (Indicator)(pCi/liter)

NuldeIirsts uartciF )LX Scond Quartyi Be-7 < 5.70E+01 < 3.20E+01 IK-40 <1 8.1OE+O1I

< 6.80E+O1 1Mn-54 [< 6.30E+001

< _ < 4.OOE+00 1 Co-58 < 7.40E+OOj

__< 4.1OE+00 !Fe-591 1.70E+01 _< 8.40E+00 sCo-60 Ký 7.OOE+O K4.10E+00O

Zn-65 10 2.90E+O1.+01 i <1 9.20E+001 2ar-95 1 < 1.20E+01Oi

<1 7.20E+001 Ru-103 0 8M I0+0 ___ <1 4.30E+00 __CRu-1061 < 6.90E+0-01

---<I 3.60E+01 _"Cs-134 I 8.50E+00!

< 4.30E+00t Cs-137 < 6.90E+OO1

<__ 4.1IOE+0O'Ba- 140 < 1.OOE+O1 ~ <_ __ 8.20E+00 La- 140 < 1.20E+01 ___ <1 9.50E+001

__iCe-141 <; 1. 1 OE+O1 ~ <_____ 5. F9;E6) _____iCe-144 I< 4.70E+01i

< 2. OE+O I ,H-3 i< 4.30E+02 .. __ __<_ 4.30E+021

___~Nuclide T1jiid Quaitfer TFl'urth Ouiriter_lBe-7 < 4.40E+OII IK-40 I<1.OOE+01 i~ : 4 ............

........ ......................

IMn-54 <1 5.40E+001 lCo-58 1 < 4.40E+001 Fe-59 i .< 1.20E+011 C< { 6.30E+00;.Zn-65 <'1.50E+0I Zr-95 K< 1.10E+011 Ru- 103 <- 6.OOE+OOI lRu-106 <i 4.70E+O I K~s-134 I <15.90E+001 0C-137 <5.40E+OO 1Ba-140 K, 1.20E+01~la-140 <1 1.30E+01I'Ce-141 ... 7.50E+00O i e i i ... .... .........

...............

Ce-344 j < 2.50E+O0'H-3 -T< 4A.o-E+62 9 ______ <1 4.70DE+O0 J _____S <I 5.60E+00 ________V7 1 6.60E+/-O0 _____S < 6.40E+00 t_______ <I 2.30E+01 __<~ 7.90E+/-O+00

____________ < 6.1IOE+O1I

____6.OOE+OO1<1470F.+OOT 1 .50E+01 1 .50E+01 8.70E+00<13.20E+01

=<I4.30E+62 C-47 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-3 (Indicator)(pCi/liter)

N4uclide j 1Fifst Qtujiler K Seon truTe lBe-7 1<1 5.30E+01 __ < 2.60E+01 ___K-40 <i 8.20E+01~

< 5.1 OE+01I'Mn-54 <: 7.1IOE+00l

<12.90E+O00

______o-5 <1 6.5 0 E+'00 <1_______

2.90E_00 LTe-59 <~ 1.40E__0__

< 6.50E+00 ___lCo-60 <~6.90EOý

.______ <I .9OE++O11

.......<1 6.90E+001 I___[Zr-95 __<1 I.IOE+011I I_ <1 4.90E+00_____

lRu-103 I<,I 7.50E+00 l____ <i 3.90E+00 ____IRu-106 <1_6.20E+0I

~ <~ 2. 90b+01 I _!s147.1IOE+00l

<_ _ 3.20E_0 Cs14___<3 0+0 ___FdC737 <r 6.50E+00I

____ <1 2.70E+00 ____lBa-140 I I1OOE+011

______ < 60+0 ____!La-140 r<1 11OE+O I _ _<i 7.60E+00 ____!Ce-141 <1 9.I1OE+O0

____ < 5.40E+00-14 < 3.40E+01T

< 1.50E+01 ____1H-3 <f4.30E+02<43+2

____'Nuclide>

~ T hK1Td Qqarter < IOU~th (Uaj~te,ý!Be-7 I<1 5.10E+Olj1 IK-40 <~7.00E+0I1 4!Mn-54 [<'5.20E+001

!Co-58 1<1 6.30E+00j!Fe-59 <1I.10E+01

!Co-60 <~15.30E+00

!Zn-65 1~24E0'Zr-95 I <1 9.70E+00, _'Ru-103 I<~ 6.80E+00 iRu-106 <3 5.20E+0I1 Cs-I 34 <15.70E+00t

_C-37 <4.96E+66I iBa-140 <I 1.40E+01~'La-140 <I I.40E+0 II _jCe-141 <1 1.30E+01 jdCe'1 .j.<1 3.40E+01I IH-3 < 4.60E+02<I<1<i<i<<T 4.90E+0 II__I____.. ......8...2. 0 E + O i ...................

......4.60E+00]5.50E+06 { ___1.30E+01I 5.20E+00 1 .30E+01 ____9.50E+00I 6.20E+00~4.20E+01I

___5.80E+00j 5.1 OE+00,______

1.40E+01J

___1.40E+01 ____9.40E+001 4.30E+021 C-4R Fermi 2 -2007Annual Radioactive.Effluent Release and Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-4 (Control)(pCi/liter) 1Be-7 < 4.80E+01 ___ <ý 2.40E+01!

I_ _IK-40 <1 9.70E+01 _< 5.30E+01O i ___!Mn-54 <i 6.50E+00]

_ _ <!i 3.OOE+ _ _ I_Co-58 <1 5.70E+00[i

< 3.OOE+0 ,1 Fe-59 <' 1.50E+0, _ 1< 6.10E+00 1_ _lCo-60 <1 5.80E+00i

<ý 2.70E+00 R~.........

......10..-.----............

..........

3 ..40E+ .....CZn-65 <. 2.20E+010

<i .2.0E+00_

__"Zr-95 1. 1.OE+Ol I __ <1 5.30E+00__j____J ARu-103 I <1 6E+00. 1 _ <ý 3.40E+00__

'Ru- 106 _<1 4.90E+0OI

< 2.70E+01 aCs-134 6.40E+00 _ <ý 2.90E+00 _!Cs-137 <1 5.40E+O001

__ _ <1 2.70E+00}___

'Ba-140 <~ 8.60E+00I

____ <' 6.20E+00 __la-140 <1 9.90E+00 __ _ <ý 7. l0E+00~ __iCe-141 ' -8.20E+001

< 5.80E+00 1 FCe-144 <1 3.OOE+01, I <I 1.50E+01 I 1H-3 I <I 4.20E+021 I <1 4.20E+02 -I 11e-7 ___ <1 5.60E+0l I I_!Mn-54 <16.20E+O00 ,Co-58 <1 5.90E+00j Fe-59 <1 1.20E+01!Co-60 < 5.50ýE+00

_'Zn-65 j <I 2.40Eý+Ol'Zr-95 I_ <1 l.IOE+01__

Au-103 <6.70E+00j I Ru- 106 < 4.30E+01~ICs-134 <1 6.40E+00[iCs-137 1<1 5.60E0 I Ba140 <i 1.30E+01!'La-140 I< 1.40E+0lI_________

<! 1.__ 1__ ___ I SC e-144 <1 3.30E +01 H-3 <1 _5-AoE+OT

-_____ <~3.90E+01

______ <i4.20E+01

< 4.0E+00 1 <1 8.40E+00 7 ..i;~4.70E+00

<ý 9.90E+00__ _ <I 7.60E+00______ 4 80j~Ej00____ <1 3.80E+01__ _ <i 3.80E+00_____ 3.86Ei+00__ _ <~ 1.20E+01___ <1 1.20E+0l____ <ý 2.40E+0l___j<I!4.30E+02

--i1 I__-1--3.j___+0 C-49 Fermi 2 -2007 Annual Radioactive Effluent.

Release and Radiological Environmental Operating Report FERMI 2 SEDIMENT ANALYSIS S-I (Indicator)(pCi/kg dry)Sr-89 <i 2.1OE+021 J < 2.30E+02 [Sr-90 <i 1.80E+02h

_ _ ý 1.50E+021 iBe-7 < 2.40E+021<

4. 1_0E+021 _K-40 1.26E+04H-/-14.00E+02 1.34E+04 +/- i3.50E+02.Mn-54 ._.... 1.26- 04 + _-_.... _--- __ __ -- _--l~ : 9. .................

< 9 .............

0E + 21 ICo-56 -!<I 2.80E+01 <- 2.50E+01 .3.n-65 <1 8-5-0E+O I < 4.60E+02,!Zr ~ ~ ~ .....................

-..<".4.0E+0'

..... ..... .. I980 + 1 Fe-509 < 9.50E+01j

<1 2.00E+02!uo-60 I <1 2.90E+02 I <1 2.50E+01 2n-65 <~ 8.50E+0111

<______ I LA 10E:+::0:2 Zr-95 I< 4.40E+01 < 9.80E+0 J CRu-103 <; 2.70E+011

..1 7.40E+01T'Ru-106 i<; 1.80E ____02__ <1 2.OOE+0 _____!Cs-134 <;;2.20E+01j

____ <1 7.70E+01[

I ___!C-J37 < 112.20E+01______

<1 1. 90E+O I lBa-140 <1 3.10E+021

< 6.70E+03 T _ _FLa- 40 < 1.80E+021 3.I10EE03' ICe-141 < 4.90E+01 -- 1.60E+022 1 iCe-144 I <I 1.10E+021

_ _<<I 1.30E+02 " S-2 (Indicator)(pCi/kg dry)I~~~~~~~~

Nuld " %I 3NOV!Sr-89 <1 4.40E+021 j < 2.90E+021.. ..... ......... ..1. -.1 ,...........................

...... ...'Sr-90 <i 2.90E+02'

____ <ý 1.90E+021!Be-7 -< 2.30E+02 -<- 6.1 0E+024_'K-40 18299E+03I+/

t2.40E+02 1.03E+04 +Mn-54_- <1 1.90E+01 ___ _ <1 3.30E+0I Co-58 O< 3.O0E+01 ___ <1 5.50E+01I Te-59 <1 8.20E+01-2.30E+02-,Co-60 <1 2.20E+01 _ <_ 2.90E+01'Zn-65 -l'1OE+021

_ <1 1.60E+02 iZr-95 <i 4.40E+01 _<_ 1.00E+02 LRu-103 <! 3.30E+01 _ <'; 1.00E+02 Ru-106 <' 1.50E+02 -<j 2.90E+02 ICs-34 <1 1.40E+01 j <1 1.20E+02 Cs-137 < I.-60E+01{

I <I 1Ba-140 I <1 7.OOE+021

_ < 7.40E+031 ULa-140 <I 3.60E+021

<. 4.90E+031!C -41..........................

4 ...................

......................

......60 E + 0 1...............................50 E + 02.ICe-144 1 < 16.60E+01I

_ < 2.50E+02i<Cet4 1 .O+2 <1____ 2 2.E+02 I-13.50E+02-I -AT__C-50 Fermi 2 -2007 Annual.. Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 SEDIMENT ANALYSIS S-3 (Indicator)(pCi/kg dry)Nud~ide~ ~ PA i4 13-NOV~4~>

iSr-89 <i 2.60E+02 -- <1 2.30E+021 Sr-90 <i 2.30E+021

_ <1 1.40E+021

......._-Be-7 <I 2.90E+021

"< 5.1OE+02 K-40 ... 7.30E+031

+/- 3.80E+02 1 .23E+041 +/- 13.40E+02'Mn-54 <i 3.OOE+O1 <o 2.70E+01 I Co-58 < 4.1OE+O0 I <I 4.50E+01 i Fe-59 < 1.10E+02 i <1 1.70E+02r ,Co-60 <1 3.20E+01 <i 2.60E+01 , _1Zn-65 < 1.50E+024

< 2'Zr-95 <! 6.5OE+O1i

< 9.OOE+01 _Ru-103 < 3.00E+01 <1 7.70E+011

_lRu-106 21 2.0E+021 ____ < 2.2ý0E+02{

ICs-134 <1 2.00E+01 < 1.80E+01'Cs-137 K< 2.80E+01 __---<t 2.30E+01 Ba-140 < 3.70E+021

-<i 6.90E+03 iLa-140 < I 1.90E+02 _--<__ I<iCe-141 1 < 5.90E+01 __<_ 1.90E+02.Ce-144 .< I -OE+0_ < i70E+021 S-4 (Indicator)(pCi/kg dry)Nuclide; 5,-JWN _8-NO _iSr-89 <~ 2.20E+02~.........................

..............

' ..................................

..................

Sr-90 K 2.10E+02 Be-7 -<1 4.70E+02 iK-40 -1~.13E+041 Y7 iMn 4 <5.3OE+01i io-58 < 5.70E+01 9 e-59 <L 1.60E+02OýCo-60 <I 5.30E+O1 Zn-65 <-K 1.60E+02_Zr-95 < 1.1OE+021'Ru-103 < 5.1OE+01ýRu-106 <1 3.70E+021!Cs-134 < 8.OOE+01i iCs-137 < 5.20E+0I iBa-140 K< 5.70E+021 1La-140 T < 3.OOE+02 ICe-14i < K 9.60E+01i[Ce-_44 .2.80E+021 6.50E+02 i<1 1.80E+021 Ký 1.30E+021_

<1 1.20E+03 , 8.74E+03 +/-< 6.20E+01 J, 1.20E+02 T <1 3.20E+02 , 7.40E+01<i 2.90E+02<' 2.30E+021<i 2.10E+O21<, 7.OOE+02<1 7.1OE+O1<1 6.50E+011.20E+04:< 5.50E+03< 4.50E+02...........

...................

C-51 Fermi 2 -2007 Annual.Radioactive-Effluent Release and Radiological Environmental Operating Report FERMI 2 SEDIMENT ANALYSIS S-5 (Control)(pCi/kg dry)Nu~clide [ 8 ____>8NVA____

Sr-89 2.80E+02 __.... <j

]:Sr-90 <i 2.3 OE+02 {< .3E+02 ______.Be-7 <1 4.1 OE+/-02 <1 1. 1OE+O3j~______

-40 9.77E+031

+/- 3.50E+02 1.18E+041

+/- 7.OOE+02 Mn-54 <I 3.5OE+01 < 7.90E+01{

__--iCo-58 <~40E0~< 1.20E+02~< 1 4 0 E 0 1i -.................... .................. ... .. .. .. ....Fe-59 <j I *2E+02 1 _____< 5.OOE+02 Co-60 <1 3.50E+01 <1 6.50E+O1 I Zn-65 ,-~< 1.40E+02 < 2.60E+02_

{_ _Zr-95 1 8.10E+01I

<j 2.20E+02 Ru-103 < 5.1OE+O0i

< 2.30E+02 iRu-106 <1 2.10E+02 I < 7.1OE+02_!Cs-134 <I 2.1OE+01 -< 5.80E+01---

_ICs-137 OE+010 i +/- 1. 10OE+01I < 1.20E+02 ,, _!Ba-140 < 1.40E+03,1

__ < 2.20E+04 {____ILa-140 < 7.60E+021

] __ < ý4ý.OE+04 1 ____[Ce-141 1.00E+021 I < 5.50E+02 1!Ce-144 <, 1.40E+02i 4.90E+02i----

_C-52 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-I (Control)(pCi/kg wet)Nui.1ide, x8-MAY Kock fBatss YM~i %1iute Bass, 8-MVAN White Perch--tSr-89 <t 2.1OE+02i

__ < 2.10E+02!

_ < 1.90E+02 i <!Sr-90 j<~ 1.90E+02 I< 2. 1OE+021 < 1.80E+021[i ...................

i < i ............................................................

2..E+ 0 2...<...Be-7 < 5.20E+021

< 6.20E+02........

<1 6.60E+021 IK-40 2.37E+031

+/- 3" < 1.40E+03 __ 1.04E+03 +/ ý3.OOE+02!Mn-54 < 6.1OE+O 1 <s 4.70E+01I-l-

<1 6.50E+01 ICo-58 5.50E+01 < 7.80E+01.

.__ ._ < 6.70E+01 2Fe-59.0E+02

_ < 2.20E+02<

_ _ 2.20E+02 ___ T_ __ _______2 <6.2.20E1021 Co-60 < 3.70E+01__

< 5.20E+01i 1 6 Zn-65 <i .50E+021 < 1.70E+021i I_ < 1.30E+02'Zr-95 8.6<0E_0 1 <1.00E+02_

_ _ , 1.60E+02 Ru-103 ---<1 7.70E+01 < 5.20E 9.OOE+01 Ru-106 < 4.30E+02 < 5.E+02j <15- 5.70E+02 Cs-134 _< 4.20E+01 < 6.50E+01I

<f6.OOE+O1 Cs-137 <i 4.10E+01 <.... ..0___ < 5.90E+01, Ba-140 < 8.50E+01 " < 6.10E+021

<i 3.70E+02+

_La-140 < 9"80E+011

_ _ <I 7.00E+02t1

<1 4.30E+02 ........Ce-141 <1 9.60E+01 _<_ 1.00E+021

<I 1.20E+02 ___Ce-144 <ý 1.60E+02 ___ _ <i 1.80E+021

...... < 2.80E+02 ___JSr-89?Sr-90 1Be-7 K-40 MNn-54 lCo-58!Fe-59 K ICo-60 !=Zn-65 Zr-95 Ru-1 03 lRu- 106 7Cs-13 1Ba-140 La-140[Ce,--i 4 ..1- ....Ce -144< 2.50E+021< 2.40E+02<1 3.30E+02 4.70E+02<i 3.20E+01<1 3.70E+0I< 1.00E+02<1 3.OOE+01<1 9.1OE+01< 8-60E+01j.. .. ... I. .. .. .. .. .. ............

< 4.80E+0 1.2.60E+02l<1 3.60E+01I~

<1 2.30E+O I<1 2.20E+021<- 2-60E+02i,<, 5.30E+01 i 1 I.20E+02 4.50E+02'<! 1.00E+021<ý 5.50E+021 I S 2.90E+031

+/- 1.90E+02< 2.20E+01t

_____ <5.20E+/-01 I' ____<ý 1.90E+02j<ý 2.OOE+/-0 ___1 <1 7.1OE+01 II......................

< 9.70E+ O I<I 9.40E+01-

___<~1.90E+021

__< 2.80E+01i

__....S ~~2. 1OE+01 ___I <1 8.00E+031-1.90E+021

__________I<ý 8.90E+01I

__<1 6.OOE+02< _1-30E+02<;170E+03 3.9 5.E.+0..3.

< 7.20E+01< 5.70E+01< 2. 1 OE+02 4.10E+02 Ti I-Ii I-<1 7.70E+01<f 1.90E+02< 3.60E+02 ,~ 6.40E+02<1 8.70E+01<I 5.60E+01<I 2.70E+04<2_.70E+04

< 6.20E+02<j 2.60E+ý02.. ..........C-53 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-2 (Indicator)(pCi/kg wet)Nu7dide I I-MAY~ CaVfi,.h I/~ ]-~MAY> fiUm1 I~ 1 -MAY~ Wall~!Sr-89 <2.20E+021

____ <i 2.40E+02 _____ <1 1.70E+O2U

____tSr-90 ~ < 2.40E+02 <ý 2.50E+02 I< 1.70E+01: Be-7 <4.20E+021

<1 4.30E+02 _____ < 4.30E0 ___K-02.91 E+/-03 +/- 3.0E0 1.76E+03 +/- ~2.90E+02 2._07E+03

+13.80E+02 Mn-54 < 3.40E+01]

___ <i 4.30E+01.

____ <5IE0 ____Co-58 < 4.OOE+Ol __ _ <1 5.30E+01 j < 5.30E+O0j

____Fe-59 < I .20E+02i <! 1.50E+01 ____ < 1 .7OE+02i ___Co-60 _< 3.80E+01I

<1 5.70E+01<1{

5.80EE01~Zn-65 <~ 8.70E+01 .0E0 <1 1.20E+02ý

____Zr-95 < 7.50E+01i

_____ < 1.OOE+02'

<1____ 9.90E+O11~

Ru-103 <_5.60E+01I I 5.70E+01 <1___~ 6.70E+01I Ru- 106 <4.30E+021 I____ <! 4.20E+021

<1___ 5.OOE+021

___Cs-134 <~4.30E+01V

<1 4.40E+01 ___ <1 4.20E+01ý

__Cs-137 < 4.20E+011

____ <ý 4.90E+01 _____ < 5.50E+01z I Ba-140 < 2.20E+0211

< 2.60E+02 < 3.40E+021 La-140 < 2.60E+02&

____ < I2.90E+02'

____ < 3.90E+021

____Ce-141 _j<8.3 OE+O I i <1 7.90E+01 _ _ <1 9.70E+011

____Ce -_1" I< 2.OOE+/-021

-LfE+/-2< 2.00E+01 i I ucdid If 'I -MfAY White Bassý 11-MAY Whit~~efr hI. -A1/ Y Yelloý 11PeirchV Sr-89 Sr-90 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru-I 03 Ru-106 Cs-134 Fs13,7 Ba-140 La- 140 Ce-141 Ce-144" 1.50E+02ý" 1.70E+02." 4.20E+02 2.03E+03: "~ff 5.50E+01~<T4. IOE+01<1 1.20E+02;< 4.70E+01j< 1.20E+02< 1.30E+02,< 6.90E+01!j

<1 3.50E+02ii

<1 3.80E+01<12.90E+02,<I8.00E+O11;

< .50E+ý021 1+- 3.30E+02.. ............... ... .<1 2.OOE+02 j<, 2.OOE+02j L<1 4.00E+02 2.44E+03 +/- i2.80E+02<1 3.70E+01~i

_ _-<1 4.40E+01 _}_<1 9.80E+021-

!< 4.30E+01<1 I .OOE+02<~ 8.20E+01j<1 6.40E+01 ____i 13.90E+02<1L 3.90E+021

_3 50E+01< 1.80E+02.

___<1 2.1 OE+02 __........<i_7.70E+01, _ _ _ _<I1.80E+02

___<1 1 .50E+02~ __5.41.0E+02

__.32E+31 +/- 3.60E+02<I 5.90E+O1I

____I<~ 1.70E+021

____<I 7.60E+01 I _<~ 1.30E+02~<7 1.30E+02 ......<6.80E+01F__.

____I<4.60E+021______

<6.OOE+0!

__~<450E+01i

-.<1 2.70E+021

_____<1 3.I1OE+02; I____<17.60E+01.

I ____<1 1 .60E+/-01~I_____

C-54 Fermi 2 -2007Annual

.Radioactive Effluent Release and.Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-2 (Indicator)(pCi/kg wet)Nucii&, 24-OiCT Ca' Tt-OC Catfish 24-(KT1 Large~Mouth~Bass Sr-89 <1 5.OOE+02 _ <1 5.30E+02 j _ < 5.50E+02i Sr--90 < 1. 1OE+01 < 1.40E+02 j<1 1.20E+02 Be-7 < 5.IOE+02 __ <1 3.80E+02 j ___ <ý 5.80E+02J

__K-40 3 2.33E+031

+/- 1.60E+02 I 2.52E+03, +/-1.00E+02 1253E+0 +/- 2.1 OE+02 Mn-54 <I 2.20E+01 ___ <, 1.70E+01 !___ 2.70E+01 _Co-58 <_4.1OE+01 i 3.60E+01 <L 540E+1 I Fe-59 .I 50E+02 ' < < .40E+02 2.60E+02 _Co-60 + < 2.30E+01:

_F ------ <1 1.50E+01 < 2.80E+01 Zn-65 <1 4.30E+o0 I_ _ <1 6.50E+01 jE+O _Zr-95 <1 9.70E+0 I <1 7.20E+ 01 j_ I 1. 10 _+0 Ru-103 < 8.50Et01 <1 8.50E+01 -1.1OE+02 _Ru-106 "--I 80E-+0-2, _ < 1.50E+02ý

.__ , < 2.20E+O2jý 2,_Cs-134 < 2 +Ob .... __ < 1.90E+01 2.5 ..... < 2.80E+O_, __Cs-137 < 1. ... 5 <I 1.30E+01i

< 2.20E01 Ba-140 < 5.20E+03 _< 6.10E+03i

< 7.20E+031 La-140 .< 5.20E+03 _ < 6.10E+03 j < 7.20E+Ce-141 < .70E+02! < 2.OOE+021, < 2.1OE+02 Ce-144 i<j 7.50E+01 _ < 7.50E+01 < 9.60E+01I

.... ....I~~~uc~~ide\V-I I 1,CQ~aij 24-QGT Fhl-____ 2-~ Whltý: PerL ISr-89 ISr-90 lBe-7 K-40 IMn-54 Co-58 Fe-59 ICo-60 IZn -65 Zr-95 Ru- 103 Ru- 106 Cs-134 LCs-137 Ba- 140 La- 140 Ce- 141 Ce- 144< 6.OOE+02-'

6.OOE+021 3 .40E+03<2.50E+01I

<7 5.20E+OiI< .40E+ýOAl 2.40E+01< 7.50E+01<1. 1OE+02 1< 1. 10E+021<ý 2.50E+01< 2.20E+01t<8.90E+03ý

< 8.90E+03~2.20E+021< 1.E+2+/- 2.20E+02... ...... ................

....... -..............

..... 5.80E+o02<I 1.20E+02< 6.70E+02 2.58E+03<! 3.1OE+01I<I 5.70E+01'< 2.40E+02<1 3.70E+01< 8.....

<i 1.40E+02!<i 1.20E+02Z<1 2.40E+02ýt~ 3.20E+01<! 2.50E+01,<1 8.20E+0C3<1 8.20E+03 I< 2.1IOE+021

<1 I .OOE+021+/-i2.20E+02

..........

..i ...........

............

.. ..............

.-I7.30E+0 W __< 4.80E+021<~ 4.90C+;6......

2.37E+03 +/ 1.70E+02< 2.20E+014< 4.70E+01 _<1 2.30E+02< 6.90E+01I<1 8.80E+011<1 .10OE+02 _< 2.10E+021

___200OEt01 __-<i 2.1IOE+0iI__

<3 6.70E+03i

____<6.70E+03, ___<~ 1.80E+02 ____j~< 1.I1QEtO2__

C-55 Fermi 2 -2007 Annual.Radioactive Effluent.

Release and Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-2 (Indicator)(pCi/kg wet)Nuwide' : K --- i4-OCT Yellow Perch. >1'Sr-89 <1 6.30E+021 ,Be-7 <1 5.80E+021

___-40 2.81E+031

+/- 2.IOE+02 Mn-54 <1 2.40E+01 1 _lCo-5_ i< 6.30E+01_lFe-59 <t2.20E+021 Co-60 i <1 3.1OE+O1I ,Zn-65 I <I 7.S0E+01 I Zr-95 1.10E+021

___,Ru-103 <I 1.1OE+02 _lRu-106 <1 2.50E+02 _Cs-134 <1 2.40E+01 l Cs-137 <j 2.70E+01 Ba-140 <[ 8.1OE+03t f ,La-140 <I 8.1OE031 __Ce-141 < < 2.OOE+02 ..... .Ce:144 < I Ij20E+021 C-56 Fermi 2 -2007 Annual Radioactive Effluent Release and, Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-3 (Control)(pCi/kg wet)Nu9i: )MAY~ Dr 2 ~ 9-MIAY'V Walleye \hitBs_,]Sr-89 < 2.1OE+02 ___ < 2.50E+02 I <1 2.20E+02 1 Sr-90 < 2.1 OE+02 <i 2.1OE+02 I < 2.20E+021....... .... ..........

7........

+........

...........

.... .i. ..... ...........

.... ...................

(. I-. ...... ... ... ..........

..............

.+ 8' ............

Be-7 < 7.40E+02 < 4._0E+021___

__,_ , K-40 2.6E+03 +1 4.3 OE02 ____K_4 64E_61 T_430_ 0 2.99E+031+/-_3.40;E+/-

SE+/-0h W+17- 3 20E+02 Mn-5 7.70E+01 -___ <4.50E+01;

<___ 2 4.40E+01 ____,Co-58i<~

9.60E+/-01 __ _ <i 4 OOE+01 < 4.80E+01_Fe-59 2.1E+021___

<1.20E+021

_ { < 1.20E+02{

_i _]~ ~ ~ ~~~~~~~~~~~~.

......... ..........................

8...+2 Co-60 3 6.OOE+01 54.20E+01f J < 4.60E+O1 I Zn-65 < .70E+02 I < 1.20E+021

_ I.30E+0 __Zr-95 < 1.40E+02 _ __ < 7.6p0ý jqý j -...........

_____aRu-103 < I <OE+02 <, 630E- < 5.5QE+Oli, lRu-106 6.60E+02 <t3.80E+02 1 <___ 47 O0 14 ICs-134 <j8.20E+/-01 I ___ < 4_____ ____ .70E+01~ ____,Cs4137 <7.40E+01 I____ <4.60_0__7 B a- I44 0 < .OE 0 < 1 .9 0 E + 0 2 1 _ _ _ _ _ _ _ _ _ _ _ _ _ < 1 2.O O E + 02 1 _ _ _:a 140- < 5.70E+02 ___<1 2.20E+021

<1 2.30E+021______

Ce-141 < 1.30E+02 <1 9.40E+01 I <_ 9.OOE+00 1Ce-144 3.20E+02 _ <1 2.20E+021

< _ _ 2.1OE+02 _,Nu~ii 4c9-MAY, \hite 'erch -IA Yelv P' 4 c 4-OCT CaiýSr-89 ,Sr-90 Ble--7 JMn-54 LCo-58 Fe-59 Co-60 Zln-65[Zr-95 Rju-I03 JRu-106_Cs- 4 ICs-137[Ba- 140 jLa-140 lCe-141 1.70E+021

< 1.8OE+02!

_._E+0 1.60E+021

<< I.0+0i 2.40E+021 4.1IOE+02'__

< 4.70E+021

<1 6. 30E+01 2.61 E+03 +/- 14.00E+02 1.96E+031 1 2.90E+02 I 2.20E+031 6. 1OE+0 1 4~I~ .90E 1 <1 2.1iOE+01I 5.90E+01 I ___ <1 5.700I ____ -~ E+01 1.80E+02 .< 1.50E+021I____

<1 240E+02 7.70E+01 <____+0 I <, 2.20E+01j 1. 1 OE+02 ____ <i 1.40E+&2 ___ <I 6.50E+01 1.40E+02 <ý 1.IOE+02'

<~ 1.20E+02~6.80E+01, ____ 8.20E+/-01j

_____ < 1 .20E+/-02[5.OOE+02 T <1 4.30E+021

< O -2E+021 5.50E+P1jlj

<1 5.20E+01,I j___ < 2.50E+0li 6.50E+O I < 4.40E+011

<~ ] 2. OOE+O 1 2.50E+021

<I 2.90E+01 __ < 2.20E+041 2.80E+021

-1< .0+/-2 < 2.20E+04 1.0E0 <i 9.50E+0Ii

< ___ 2.70E+02!2.80E+0 I__ < 'I 2.OOE+021 T.+1- .60E+02 C-57 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-3 (Control)(pCi/kg wet)c1id [ý 4-OCT. Wallý\ 1fi .4- OCT Wiiac Bassý ___4-_C]_White______

[Sr-89 jSr-90 11e-7 K-40 Mn-54 Co-58 Fe-59 Co-60 ,Zn-65 JZr-95 jRu-I 03-Ru-I06 Cs-I 3i Cs-137 lBa- 140 ILa- 140 Lqe- 14 JCe- 144< 8.80E+02,............

................? .2 ...........

I ...........

..................

< 4.60E+021

_2.88E+031

+/- 11.30E+02<i 1.80E+011

_<4.1.0E+01

,<1 1.90E+02<l 1.50E+oL0<§ 4.60E+01 I ____< 7.80E+01]I

< 9.60E+01<1 I.50E+01~

___I 1.40E+01 I< 1.40E+04 _< I.40E+04 ____< 1.80E+02 K .OOE+01 I ____<1 8.60E+02 ____<~1.90E+02i

's5.1IOE+02, ____2.57E+03:;

+/- 1.I1OE+02<i 1.70E+0I ____<~4.50E+01-]

< 1.90E+02 ____<1 4.30E+01 ____< 8.30E+011

______<1 9.50E+01,<1 1.50E+02~

__<1 1.50E+01~

___Ki1. 60E+01 I ___<1 1.30E+04 ____<' 1 .3013+04 ____<1 2.30E+02 ____<ý 9.3E+01 ____.7.30E-+O2, 1.< 1.70E+02i

)< 6.60E+o 0 ..........2.49E+03'

+/- 1.50E+02< 2.OOE+01 ____< 5.60E+01 "< 2.5i3E+02F_

--< 2.10E+011

_< 6.30E+011__I____

<I 1.I1OE+02j

_ ___<[ I.30E+02 ___<1 2.OOE+0l ___K 1.90E+0111 K 1.90E+041 K 1.90E+042 K 2.50E+01~K I OOE+021 ____

Appendix D Environmental Program Execution Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Environmental Program Execution On occasions, samples cannot be collected.

This can be due to a variety of events, suchas equipment malfunction, loss of electrical power, severe weather conditions, or vandalism.

In 2007, missed samples were a result of missing field TLDs and loss of electrical power and sample line sediment blockage to water sampling equipment.

The following sections list all missed samples, changes and corrective actions taken during 2007. These missed and additional grab samples did not have a significant impact on the execution of the REMP.Direct Radiation Monitoring All TLDs are placed in the field in inconspicuous locations to minimize the loss of TLDs due to vandalism.

During 2007, two hundred sixty-eight (268) TLDs were placed in the field for the REMP program and all but two (2) TLDs were collected and processed.

There were no major changes to the Direct Radiation Monitoring program during 2007.* T-31 was found missing during the second quarter collection and was replaced with the next quarter's TLD." T-32 was found missing during the third quarter collection and was replaced with the next quarter's TLD.Atmospheric Monitoring During 2007, two hundred sixty (260) air samples were placed in the field, all particulate filters and charcoal filters were collected and processed.

There were no changes to the Atmospheric Monitoring program during 2007.Terrestrial Monitoring During 2007, all scheduled terrestrial monitoring samples were collected.

There were no changes to the Terrestrial Monitoring program during 2007.Milk Sampling All scheduled milk samples were collected in 2007.Garden Sampling All scheduled garden samples were collected in 2007.D-1 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Groundwater Sampling All scheduled groundwater samples were collected in 2007.Aquatic Monitoring During 2007, all scheduled aquatic monitoring samples were collected.

There were no changes to the Aquatic Monitoring program during 2007.Drinking Water Sampling All scheduled drinking water samples were collected in 2007.Surface Water Sampling All scheduled surface water samples were collected in 2007.* During weekly flow-checks on 4/18/2007, a sample line sediment blockage was found at SW-2 and a grab sample was collected.

The sample line was repaired and equipment restored to operation.

For this reason, the second quarter composite sample for this location is considered to be less than representative.

• During weekly flow-checks on 11/21/2007, sampler DW-2 was found not operating due to loss of electrical power to the equipment.

A grab sample was collected and the operating authority restored the power to the equipment.

For this reason, the fourth quarter composite sample for this location is considered to be less than representative.

Sediment Sampling All scheduled sediment samples were collected in 2007.Fish Sampling All scheduled fish samples were collected in 2007.D-2 Appendix E Effluent and Radwaste Data Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Regulatory Limits for Radioactive Effluents The Nuclear Regulatory Commission (NRC) limits on liquid and gaseous effluents are incorporated into the Fermi 2 Offsite Dose Calculation Manual. These limits prescribe the maximum doses and dose rates due to radioactive effluents resulting from normal operation of Fermi 2. These limits are described in the following sections.A. Gaseous Effluents I. Dose rate due to radioactivity released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

a) Noble gases Less than or equal to 500 mrem/year to the total body.Less than or equal to 3000 mrem/year to the skin.b) Iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half lives greater than 8 days Less than or equal to 1500 mrem/year to any organ.II. Air dose due to noble gases to areas at and beyond the site boundary shall be limited to the following:

a) Less than or equal to 5 mrad for gamma radiation Less than or equal to 10 mrad for beta radiation-During any calendar quarter b) Less than or equal to 10 mrad for gamma radiation Less than or equal to 20 mrad for beta radiation-During any calendar year III. Dose to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

E-i Fermi 2 -2007Annual

.- Radioactive Effluent Release and Radiological Environmental Operating Report a) Less than or equal to 7.5 mrem to any organ-During any calendar quarter b) Less than or equal to 15 mrem to any organ-During any calendar year Note: The calculated site boundary dose rates for Fermi 2 are based on identification of individual isotopes and on use of dose factors specific to each identified isotope or a highly conservative dose factor. Average energy values are not used in these calculations, and therefore, need not be reported.B. Liquid Effluents I. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in Title 10 of the Code of Federal Regulations (10 CFR) Part 20 (Standards for Protection Against Radiation), Appendix B, Table 2, Column 2 for radionuclides Other than dissolved or entrained noble gases, as required by the Fermi 2 Offsite Dose Calculation Manual. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 (.0002) microcuries/ml total activity.

This limit is based on the Xe-135 air submersion dose limit converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICR-P) Publication 2.II. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:

a) Less than or equal to 1.5 mrem to the total body Less than or equal to 5 mrem to any organ-During any calendar quarter b) Less than or equal to 3 mrem to the total body Less than or equal to 10 mrem to any organ-During any calendar year E-2 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Measurements and Approximations of Total Activity in Radioactive Effluents As required by NRC Regulatory Guide 1.21, this section describes the methods used to measure the total radioactivity in effluent releases and to estimate the overall errors associated with these measurements.

The effluent monitoring systems are described in Chapter 11.4 of the Fermi 2 Updated Final Safety Analysis Report (UFSAR).A. Gaseous Effluents I. Fission and Activation Gases Samples are obtained from each of the six plant radiation monitors which continuously monitor the five ventilation exhaust points. The fission and activation gases are quantified by gamma spectroscopy analysis of periodic samples.The summary values reported are the sums of all fission and activation gases quantified at all monitored release points.II. Radioiodines Samples are obtained from each of the six plant radiation monitors which continuously monitor the five ventilation exhaust points. The radioiodines are entrained on charcoal and then quantified by gamma spectroscopy analysis.For each sample, the duration of sampling and continuous flow rate through the charcoal are used in determining the concentration of radioiodines.

From the flow rate of the ventilation system, a rate of release can be determined.

The summary values reported are the sums of all radioiodines quantified at all continuously monitored release points.E-3 Fermi 2 -2007Annual Radioactive Effluent.

Release and Radiological Environmental Operating Report III. Particulates Samples are obtained from each of the six plant effluent radiation monitors which continuously monitor the five ventilation exhaust points. The particulates are collected on a filter and then quantified by gamma spectroscopy analysis.For each sample, the duration of sampling and continuous flow rate through the filter are used in determining the concentration of particulates.

From the flow rate of the ventilation system, a rate of release can be determined.

Quarterly, the filters from each ventilation release point are composited and then radiochemically separated and analyzed for strontium (Sr)-89/90 using various analytical methods.The summary values reported are the sums of all particulates quantified at all monitored release points.IV. Tritium Samples are obtained from each of the six plant effluent radiation monitors which continuously monitor the five ventilation exhaust points. The sample is passed through a bottle containing water and the tritium is "washed" out to the collecting water. Portions of the collecting water are analyzed for tritium using liquid scintillation counting techniques.

For each sample, the duration of sample and sample flow rate is used to determine the concentration.

From the flow rate of the ventilation system, a release rate can be determined.

The summary values reported are the sums of all tritium quantified at all monitored release points.E-4 Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report V. Gross Alpha The gaseous particulate filters from the six plant effluent radiation monitors are stored for one week to allow for decay of naturally occurring alpha emitters.

These fiters are then analyzed for gross alpha radioactivity by gas proportional counting, and any such radioactivity found is assumed to be plant related. The quantity of alpha emitters released can then be determined from sample flow rate, sample duration, and stack flow rate.The summary values reported are the sums of all alpha emitters quantified at all monitored release points.B. Liquid Effluents The liquid radwaste processing system and the liquid effluent monitoring system are described in the Fermi 2 UFSAR. Fermi 2 released no radioactive liquid effluents in 2007.C. Statistical Measurement Uncertainties The statistical uncertainty of the measurements in this section has been calculated and summarized in the following table: Measurement Type Sample Type One Sigma Uncertainty Fission and Activation Gaseous 30%Gases Radioiodines Gaseous 17%Particulates Gaseous 16%Tritium Gaseous 25%Gross Alpha Gaseous 16%Gaseous Releases by Individual Nuclide Values in the following tables which are preceded by the "less than" symbol represent the lower limit of detection (LLD) in units of microcuries per cubic centimeter (gCi/cc) for individual samples, and indicate that the nuclide in question was not detected in gaseous effluent samples in the indicated quarter of 2007. For quantities of gross alpha radioactivity and tritium in gaseous effluents, see Tables 3 and 4 on page 13 of this report.E-5 Fermi 2 -2007 Annual.........Radioactive Effluent Release and Radiological Environmental Operating Report A. Particulate Radionuclides (Curies)Cr-51 1.13E-04 2.35E-05 4.58E-05 4.14E-04 Mn-54 1.01E-05 3.88E-06 1.75E-05 7.58E-05 Co-58 1.05E-05 <2.5E-13 1.38E-05 4.12E-05 Co-60 2.48E-05 3.08E-06 4.22E-05 1.07E-04 Zn-65 9.1OE-06 <4.3E-13 8.58E-06 <4.3E-13 Fe-59 <4.OE-13 <4.OE-13 <4.OE-13 4.95E-05 Na-24 3.56E-05 7.25E-05 <2.6E- 13 <2.6E- 13 Zn-69m 1.86E-04 4.42E-05 <5.1E-13 1.87E-05 Tc-99m 1.25E-04 5.39E-05 6.33E-05 <6.6E- 13 Ba-139 8.27E-02 5.32E-02 5.11E-02 5.45E-02 La-140 3.84E-05 1.94E-05 8.50E-06 5.94E-05 Ba- 140 6.61E-06 <3.4E- 13 <3.4E- 13 2.43E-05 Y-91m 3.12E-03 2.65E-03 6.12E-04 5.71E-03 Sr-91 9.63E-05 <6.1E-12 <6.1E-12 <6.1E-12 Rb-89 1.65E-02 <6.1E-10 <6.1E-10 2.55E-02 Cs-138 3.87E-02 3.21E-02 3.49E-02 3.47E-02 As-76 7.03E-03 1.31E-02 5.60E-03 3.33E-03 Br-82 1.58E-05 5.01E-05 2.03E-05 2.33E-05 Ag-110m 4.38E-06 <2.2E-13 <2.2E-13 <2.2E-13 Sr-89 3.03E-05 1.43E-05 2.28E-05 3.14E-05 Sr-90 7.79E-06 1.50E-06 <5.5E-15 <5.5E-15 Cs- 134 <1.3E-13 <1.3E-13 <1.3E-13 <1.3E-13 Cs-137 <1.6E-13 <1.6E-13 <1.6E-13 <1.6E-13 Ce- 141 <1.4E-13 <1.4E-13 <1.4E-13 <1.4E-13 Ce-143 <3.6E-13 <3.6E-13 <3.6E-13 <3.6E-13 Ce-144 <2.5E-13 <2.5E-13 <2.5E-13 <2.5E-13 Total 1.49E-01 1.01E-01 9.25E-02 1.25E-01 B. Noble Gases (Curies)Kr-87 <8.7E-08 <8.7E-08 <8.7E-08 <8.7E-08 Kr-88 <l.OE-07 <l.OE-07 <l.OE-07 <1.OE-07 Xe-133 <5.7E-08 <5.7E-08 <5.7E-08 <5.7E-08 Xe-133m <1.1E-07 <1.1E-07 <1.1E-07 <1.1E-07 Xe-135 <1.5E-08 <1.5E-08 <1.5E-08 <1.5E-08 Xe-138 <3.8E-05 <3.8E-05 <3.8E-05 <3.8E-05 Total <3.8E-05 <3.8E-05 <3.8E-05 <3.8E-05 E-6 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report C. Radioiodines (Curies)1-131 4.48E-04 5.26E-04 6.66E-04 1.05E-03 1-132 2.70E-03 3.39E-03 3.39E-03 4.35E-04 1-133 2.98E-03 4.40E-03 4.30E-03 1.20E-03 1-134 1.13E-03 4.65E-03 2.16E-03 <3.3E- 11 1-135 1.55E-03 4.36E-03 2.68E-03 <8.OE- 12 Total 8.81E-03 1.73E-02 1.32E-02 2.69E-03 Shipments of Radwaste Fermi 2 complies with the extensive federal regulations which govern radioactive waste shipments.

Radioactive solid waste shipments from the Fermi 2 site consist of waste generated during water treatment, radioactive trash, irradiated components, etc. Shipment destinations are either licensed burial sites or intermediate processing facilities.

Waste shipped to intermediate processing facilities is shipped directly from these facilities to licensed burial sites after processing.

The following tables contain estimates of major nuclide composition, by class of waste, of Fermi 2 solid radwaste received at the Barnwell, SC, burial facility or at the Envirocare, UT, facility in 2007.a. Spent resins, sludges, etc. Waste in this category in 2007 was Class A or Class B waste and consisted of spent resins and sludges. It was shipped in either High Integrity Containers or Polyethylene Liners, within shielded transportation casks, directly to the Barnwell, SC, or Clive, UT, burial facilities.

Waste sent directly to a disposal facility was dewatered prior to shipment.

All quantities were determined by measurement.

E-7 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report Class A Resin: Radionuclide Activity (mCi) Percent of Total Activity Ag-110m 1.70E+01 0.01 C-14 1.25E+02 0.04 Ce-144 2.27E+00 <0.01 Co-57 2.46E-01 <0.01 Co-58 1.65E+02 0.05 Co-60 1.03E+05 33.38 Cs-134 4.92E+01 0.02 Cs-137 5.59E+02 0.18 Fe-55 1.70E+05 55.09 H-3 1.23E+02 0.04 Mn-54 1.75E+04 5.68 Ni-63 3.55E+03 1.15 Pu-241 3.46E+00 <0.01 Sr-90 9.63E+00 <0.01 Zn-65 1.34E+04 4.36 Total 3.08E+05 100.2. Class B Resin: Radionuclide Activity (mCi) Percent of Total Activity Am-241 3.98E-03 <0.01 C-14 9.02E+00 <0.01 Cm-242 7.87E-04 <0.01 Cm-243 1.60E-02 <0.01 Cm-244 1.56E-02 <0.01 Co-57 5.52E+01 0.01 Co-58 1.31E+03 0.21 Co-60 1.92E+05 30.25 Cr-51 1.56E+01 <0.01 Cs-134 4.08E+02 0.06 Cs-137 9.82E+03 1.55 Fe-55 3.43E+05 54.15 H-3 3.15E+01 <0.01 Mn-54 6.32E+04 9.98 Ni-63 7.14E+03 1.13 Pu-238 1.12E-02 <0.01 Pu-239 2.76E-03 <0.01 Pu-240 2.76E-03 <0.01 Sr-90 9.75E+00 <0.01 Zn-65 1.69E+04 2.66 Total 6.33E+05 100 E-8 Fermi 2 -2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report 3. Class C Resin: None shipped b. Dry compressible waste, contaminated equipment, etc. Waste in this category in 2007 was shipped in strong tight containers, and was classified as dry active waste (DAW). All waste in this category was Class A waste. The DAW was compacted, and sent for direct disposal or incinerated by an intermediate processor.

All quantities were determined by measurement.

Radionuclide Activity (mCi) Percent of Total Activity C-14 (LLD) 8.51 E+01 NA Co-58 6.23E+00 0.56%Co-60 2.07E+02 18.53%Cr-51 1.31 E+O1 1.18%Cs-137 2.76E-01 0.02%Fe-55 7.07E+02 63.40%Fe-59 4.59E+00 0.41%H-3 1.15E+02 10.34%1-129 (LLD) 3.50E+00 NA Mn-54 5.16E+01 4.63%Ni-63 3.93E-01 0.04%Tc-99 (LLD) 6.50E+01 NA Zn-65 9.90E+00 0.89%Total Activity 1.11 E+03 100%c. Irradiated components, control rods, etc.No waste in this category was shipped.d. Other No waste in this category was shipped to a disposal site.E-9 Appendix F Interlaboratory Comparison Data Areva NP Inc. Environmental Laboratory's Quality Assurance Programs Fermi 2 -2007Annual Radioactive Effluent.Release and Radiological Environmental Operating Report Interlaboratory Comparison Program for 2007 In an interlaboratory comparison program, participant laboratories receive from a commerce source, environmental samples of known activity concentration for analysis.After the samples have been analyzed by the laboratory, the manufacturer of the sample reports the known activity concentration of the samples to the laboratory.

The laboratory compares its results to the reported concentrations to determine any significant deviations, investigates such deviations if found, and initiates corrective action if necessary.

Participation in this program provides assurance that the contract laboratory is capable of meeting accepted criteria for radioactivity analysis.Included in this Appendix are selected tables from the Semi-Annual Status Reports covering the Areva NP Inc. Environmental Laboratory's Quality Assurance Programs for the first and second halves of 2007.For the report covering January -June 2007, the laboratory achieved:* 99.3% of 443 individual QC analyses evaluated during this semi-annual period met E-LAB acceptance criteria for bias, while* 99.7% of 305 QC analyses met the Laboratory QC acceptance criteria for precision.

For the report covering July -December 2007, the laboratory achieved: 0 96.2% of 372 individual QC analyses evaluated during this semi-annual period met E-LAB acceptance criteria for bias, while* 100% of 184 QC analyses met the Laboratory QC acceptance criteria for precision.

F-1 TABLE 2 AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIELGLER ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known E-LAB/Number Year Media Nuclide Units Value Value Analytics Evaluation E5222-162 4th/2006 Water H-3 pCi/L- 14570 14800 0.99 Agreement E5223-162 4th/2006 Water Sr-89 pCi/L 68.8 72.6 0.95 Agreement E5223-162 4th/2006 Water Sr-90 pCi/L 5.56 5.9 0.94 Agreement E5224-162 4th/2006 Filter Gross Alpha Pci 63.3 67.2 0.94 Agreement E5224-162 4th/2006 Filter Gross Beta pCi 209.6 203 1.03 Agreement E5225-162 4th/2006 Filter Ce-141 pCi 179.0 185 0.97 Agreement E5225-162 4th/2006 Filter Cr-51 Pci 277.9 273 1.02 Agreement E5225-162 4th/2006 Filter Cs-134 pCi 89.1 92.7 0.96 Agreement E5225-162 4th/2006 Filter Cs-137 pCi 158.8 149 1.06 Agreement E5225-162 4th/2006 Filter Co-58 Pci 54.0 52.8 1.02 Agreement E5225-162 4th/2006 Filter Mn-54 Pci 71.2 69.8 1.02 Agreement E5225-162 4th/2006 Filter Fe-59 pCi 51.0 50.2 1.02 Agreement E5225-162 4th/2006 Filter Zn-65 Pci 104.3 103 1.01 Agreement E5225-162 4th/2006 Filter Co-60 pci 166.7 177 0.94 Agreement E5226-162 4th/2006 Filter Sr-89 pCi 69.5 74.2 0.94 Agreement E5226-162 4th/2006 Filter Sr-90 pCi 6.46 6.06 1.07 Agreement E5227-162 4th/2006 Milk 1-131LL pCi/L 71.0 70.8 1.00 Agreement E5227-162 4th/2006 Milk 1-131 pCi/L 64.8 70.8 0.91 Agreement E5227-162 4th/2006 Milk Ce-141 pCi/L 277.7 294 0.94 Agreement E5227-162 4th/2006 Milk Cr-51 pCi/L 430.7 433 0.99 Agreement E5227-162 4th/2006 Milk Cs-134 pCi/L 141.4 147 0.96 Agreement E5227-162 4th/2006 Milk Cs-137 pCi/L 233.9 237 0.99 Agreement E5227-162 4th/2006 Milk Co-58 pCi/L 83.1 83.8 0.99 Agreement E5227-162 4th/2006 Milk Mn-54 pCi/L 110.6 111 1.00 Agreement E5227-162 4th/2006 Milk Fe-59 pCi/L 82.3 79.7 1.03 Agreement E5227-162 4th/2006 Milk Zn-65 pCi/L 171.4 164 1.05 Agreement E5227-162 4th/2006 Milk Co-60 pCi/L 273.1 281 0.97 Agreement E5228-162 4th/2006 Charcoal 1-131 pCi 84.2 87.1 0.97 Agreement F:ADMIN\CORRES\EL 081-07-A3-TABLE 2 (continued)

AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIELGLER ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known E-LAB/Number Year Media Nuclide Units Value Value Analytics Evaluation E5238-162 1 st/2007 Water Gross Alpha pCi/L 117 112 1.05 Agreement E5238-162 1 st/2007 Water Gross Beta pCi/L 104 100 1.04 Agreement E5239-162 1 st/2007 Water I-131LL pCi/L 88.3 89.8 0.98 Agreement E5239-162 1 st/2007 Water 1-131 pCi/L 74.3 89.8 0.83 Agreement E5239-162 1st/2007 Water Ce-141 pCi/L 257 258 1.00 Agreement E5239-162 1st/2007 Water Cr-51 pCi/L 218 213 1.02 Agreement E5239-162 lst/2007 Water Cs-134 pCi/L 93.6 97.1 0.96 Agreement E5239-162 1 st/2007 Water Cs-137 pCi/L 197 204 0.97 Agreement E5239-162 1st/2007 Water Co-58 pCi/L 86.2 85.8 1.00 Agreement E5239-162 1st/2007 Water Mn-54 pCi/L 155 158 0.98 Agreement E5239-162 1st/2007 Water Fe-59 pCi/L 87.1 91.7 0.95 Agreement E5239-162 1st/2007 Water Zn-65 pCi/L 886 869 1.02 Agreement E5239-162 1 st/2007 Water Co-60 pCi/L 131 132 0.99 Agreement E5240-162 1st/2007 Water Sr-89 pCi/L 127 137 0.92 Agreement E5240-162 lst/2007 Water Sr-90 pCi/L 9.39 9.99 0.94 Agreement E5241-162 1st/2007 Charcoal 1-131 pCi 67.6 70.2 0.96 Agreement E5242-162 1st/2007 Filter Gross Alpha pCi 67.2 69.1 0.97 Agreement E5242-162 lst/2007 Filter Gross Beta pCi 69.4 61.9 1.12 Agreement E5243-162 1st/2007 Milk 1-131LL pCi/L 85.1 85.2 1.00 Agreement E5243-162 lst/2007 Milk 1-131 pCi/L 75.4 85.2 0.88 Agreement E5243-162 lst/2007 Milk Ce-141 pCi/L 294 297 0.99 Agreement E5243-162 1st/2007 Milk Cr-51 pCi/L 226 245 0.92 Agreement E5243-162 1st/2007 Milk Cs-1 34 pCi/L 104 112 0.93 Agreement E5243-162 lst/2007 Milk Cs-137 pCi/L 228 234 0.97 Agreement E5243-162 1st/2007 Milk Co-58 pCi/L 98.1 98.8 0.99 Agreement E5243-162 lst/2007 Milk Mn-54 pCi/L 184 182 1.01 Agreement E5243-162 1st/2007 Milk Fe-59 pCi/L 109 106 1.03 Agreement E5243-162 lst/2007 Milk Zn-65 pCi/L 1041 1000 1.04 Agreement E5243-162 lst/2007 Milk Co-60 pCi/L 148 152 0.98 Agreement E5244-162 1st/2007 Milk Sr-89 pCi/L 126 137 0.92 Agreement E5244-162 1st/2007 Milk Sr-90 pCi/L 8.85 10 0.88 Agreement F:\ADMIN\CORRES\EL 081-07-A4 -

TABLE 2 (continued)

AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIELGLER ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known E-LAB/Number Year Media Nuclide Units Value Value Analytics Evaluation E5334-162 2nd/2007 Water H-3 pCi/L 8520 (1)E5335-162 2nd/2007 Filter Gross Alpha pCi 122.7 (1)E5335-162 2nd/2007 Filter Gross Beta pCi 137.9 (1)E5335-162 2nd/2007 Filter Ce-141 pCi/L 94.1 (1)E5335-162 2nd/2007 Filter Cr-51 pCi/L 230 (1)E5335-162 2nd/2007 Filter Cs-134 pCi/L 114.3 (1)E5335-162 2nd/2007 Filter Cs-137 pCi/L 86.3 (1)E5335-162 2nd/2007 Filter Co-58 pCi/L 98.4 (1)E5335-162 2nd/2007 Filter Mn-54 pCi/L 83.8 (1)E5335-162 2nd/2007 Filter Fe-59 pCi/L 79 (1)E5335-162 2nd/2007 Filter Zn-65 pCi/L 166.5 (1)E5335-162 2nd/2007 Filter Co-60 pCi/L 112.4 (1)E5337-162 2nd/2007 Filter Sr-89 pCi/L 71.4 (1)E5337-162 2nd/2007 Filter Sr-90 pCi/L 10.1 (1)E5338-162 2nd/2007 Milk 1-131LL pCi/L 73.5 (1)E5338-162 2nd/2007 Milk 1-131 pCi/L 75 (1)E5338-162 2nd/2007 Milk Ce-141 pCi/L 167.5 (1)E5338-162 2nd/2007 Milk Cr-51 pCi/L 446.7 (1)E5338-162 2nd/2007 Milk Cs-134 pCi/L 222.5 (1)E5338-162 2nd/2007 Milk Cs-137 pCi/L 164.8 (1)E5338-162 2nd/2007 Milk Co-58 pCi/L 203.4 (1)E5338-162 2nd/2007 Milk Mn-54 pCi/L 177.9 1 (1) 1 1 E5338-162 2nd/2007 Milk Fe-59 pCi/L 170 (1)E5338-162 2nd/2007 Milk Zn-65 pCi/L 342.9 j1_E5338-162 2nd/2007 Milk Co-60 pCi/L 237.5 (1)(1) -Results have been submitted for evaluation.

F:\ADMIN\CORRES\EL 081-07-A5-TABLE 4 DEPARTMENT OF ENERGY MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM REPORTED MAPEP SAMPLE MATRIX/ REFERENCE RADIO- MEAN VALUE VALUE ID UNITS DATE NUCLIDE Bq/Units Bq/Units % Bias EVALUATION MAPEP-07-RdF17 Filter (Bg/filter) 1-Jan-07 Cs-1 34 3.59 4.196 -14.4 Agreement MAPEP-07-RdF17 Filter (Bq/filter) 1-Jan-07 Cs-137 2.53 2.5693 -1.5 Agreement MAPEP-07-RdF17 Filter (Bq/filter) 1-Jan-07 Co-57 3.31 2.8876 14.6 Agreement MAPEP-07-RdF17 Filter (Bq/filter) 1-Jan-07 Co-60 2.83 2.9054 -2.6 Agreement MAPEP-07-RdF17 Filter (Bq/filter) 1-Jan-07 Mn-54 3.54 3.5185 0.6 Agreement MAPEP-07-RdF17 Filter (Bq/filter) 1-Jan-07 Sr-90 0.565 0.6074 -7.0 Agreement MAPEP-07-RdF17 Filter (Bq/filter) 1-Jan-07 Zn-65 2.25 2.628 -16.1 Agreement MAPEP-07-MaS17 Soil (Bg/kg) 1-Jan-07 Cs-134 358.2 327.4 9.4 Agreement MAPEP-07-MaS17 Soil (Bl/kg) 1-Jan-07 Cs-137 875.9 799.7 9.5 Agreement MAPEP-07-MaS17 Soil (Bq/kg) 1-Jan-07 Co-57 518.6 471.2 10.1 Agreement MAPEP-07-MaS17 Soil (Bq/kg) 1-Jan-07 Co-60 296.9 274.7 8.1 Agreement MAPEP-07-MaS17 Soil (Bq/k,) 1-Jan-07 Mn-54 766.7 685.2 11.9 Agreement MAPEP-07-MaS17 Soil (Bq/kg) ........1-Jan-07 K-40 655 -602 8.8 Agreement MAPEP-07-MaS17 Soil (Bq/kg) 1-Jan-07 Zn-65 595.6 536.8 11.0 Agreement MAPEP-07-RdV17 Vegetation (Bg/sample) 1-Jan-07 (1)MAPEP-07-MaW17 Water (Bq/L) 1-Jan-07 Cs-1 34 82.43 83.5 -1.3 Agreement MAPEP-07-MaW17 Water (Bq/L) 1-Jan-07 Cs-137 158.6 163 -2.7 Agreement MAPEP-07-MaW17 Water (Bq/L) 1 -Jan-07 Co-57 139.17 143.7 -3.2 Agreement MAPEP-07-MaW17 Water (Bq/L) 1-Jan-07 Co-60 26.68 26.9 -0.8 Agreement MAPEP-07-MaW17 Water (Bq/L) 1-Jan-07 H-3 303 283 7.1 Agreement MAPEP-07-MaW17 Water (Bq/L) 1-Jan-07 Mn-54 122.8 123.8 -0.8 Agreement MAPEP-07-MaW17 Water (Bq/L) 1-Jan-07 Sr-90 8.55 8.87 -3.6 Agreement MAPEP-07-MaW17 Water (Bq/L) 1-Jan-07 Zn-65 116.3 114.8 1.3 Agreement (1) -Vegetation sample not analyzed this round due to difficulties encountered with provided sample.F:\ADMIN\CORRES\EL 081-07-A7-TABLE 6 INTRA-LABORATORY ENVIRONMENTAL PROCESS CONTROL RESULTS BY AREVA NP ENVIRONMENTAL LABORATORY ACCEPTANCE CRITERIA, MEDIA, AND MEASUREMENT CATEGORIES JANUARY -JUNE 2007 Bias Criteria (1) Precision Criteria (2), (3)1 2 3 4 1 2 3 4 I. Air Particulate Beta 117 13 0 0 0 0 0 0 I1. Air Charcoal Gamma-Quantitative 48 12 4 0 0 0 0 0 II1. Food (Aquatic/Terrestrial)

Gamma 0 0 0 0 11 0 9 0 IV. Milk Gamma 0 0 0 0 8 2 8 0 Iodine (LL) 0 0 0 0 0 0 0 0 V. Soil/Sed.Gamma 1 1 01 01 0 1 0 0 0 Ni-63 1 0 0 0 0 0 0 0 Sr-90 0 0 0 1 0 0 0 0 VI. Vegetation (Aquatic/Terrestrial)

Gamma 0 1 0 0 0 5 3 11 0 VII. Water Gross Alpha 3 3 1 1 3 2 2 0 Gross Beta 7 3 1 0 4 2 1 1 Gamma 8 9 1 0 0 4 22 0 Iodine (LL) 0 0 0 0 0 0 0 0 Ni-63 4 0 2 0 0 2 2 0 Sr-90 4 2 5 0 4 2 4 0 Tritium 8 6 1 1 4 5 9 0 Total Number 201 49 15 3 39 22 68 1 in Range: Percentage of 75.0 18.3 5.6 1.1 30.0 16.9 52.3 0.8 Total Processed:

Sum of Analyses:

268 130 (1) Percent Bias by Deviation Category as noted in Table 1, Footnote (1)(2) Percent Precision by Deviation Category as noted in Table 1, Footnote (2)(3) Most Precision data generated from non-positive client samples for specific contractual evaluation

• Total may not equal 100 due to rounding F:ýADMIN\CORRES\EL 081-07-A9-TABLE 7 AREVA NP ENVIRONMENTAL LABORATORY ENVIRONMENTAL INTRA-LABORATORY AND INTER-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY MEDIA JANUARY -JUNE 2007 Bias Criteria (1) Precision Criteria (2), (3)1 2 3 4 1 2 3 4 I. Air Filter Gross Alpha 4 2 0 0 6 0 0 0 Gross Beta 120 13 3 0 6 0 0 0 Gamma 20 7 0 0 27 0 0 0 Sr-89 1 0 1 0 0 2 0 0 Sr-90 1 0 1 0 0 2 0 0 II. Charcoal Gamma-Quantitative 52 13 5 0 3 3 0 0 Ill. Food (Aquatic/Terrestrial)

Gamma 0 0 0 0 11 0 9 0 IV. Milk Gamma 42 13 5 0 '60 9 9 0 Iodine (LL) 4 1 1 0 4 1 1 0 Sr-89 1 2 0 0 3 0 0 0 Sr-90 1 0 2 0 1 1 1 0 V. Soil/Sediment Gamma 1 1 0 0 0 0 0 0 Ni-63 1 0 0 0 0 0 0 0 Sr-90 0 0 0 1 0 0 0 0 VI. Vegetation (Aquatic/Terrestrial)

Gamma 0 0 0 0 5 3 11 0 VII. Water Gross Alpha 4 5 1 1 6 2 2 0 Gross Beta 9 3 2 0 6 3 1 1 Gamma 28 15 5 0 26 7 23 0 Iodine (LL) 2 1 0 0 2 1 0 0 Ni-63 4 0 2 0 0 2 2 0 Sr-89 3 2 1 0 6 0 0 0 Sr-90 5 7 5 0 10 2 4 0 Tritium 11 6 1 1 7 5 9 0 Total Number in 314 91 35 3 189 43 72 1 Range: Percentage of 70.9 20.5 7.9 0.7 62.0 14.1 23.6 0.3 Total Processed:

Sum of Analyses:

443 305 (1) Percent Bias by Deviation Category as noted in Table 1, Footnote (1)(2) Percent Precision by Deviation Category as noted in Table 1, Footnote (2)(3) Most Precision data generated from non-positive client samples for specific contractual evaluation

• Total may not equal 100 due to rounding.** Totals summarize Internal PCs and Analytics Cross Check programs F:\ADMIN\CORRES\EL 081-07-A10-TABLE 8 AREVA NP ENVIRONMENTAL LABORATORY ENVIRONMENTAL INTRA-LABORATORY AND INTER-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY ANALYSIS TYPE JANUARY -JUNE 2007 Bias Criteria (1) Precision Criteria (2), (3)12 3 12 3 4 I. Gross Alpha Air Filteri 4 1 2 1 0 1 0 1 6 0 1 0 1 0 Water 4 5 1 1 6 2 2 0 II. Gross Beta Air Filter[ 120 1 13 1 3 1 0 1 6 1 0 0 1 0 Waterl 9 3 2 0 6 3 1 1 Ill. G am m a .. ......... ... .....Air Filter 20 7 0 0 27 0 0 0 Charcoal-Quantitative 52 13 5 0 3 3 0 0 Food 0 0 0 0 11 0 9 0 Milk 42 13 5 0 60 9 9 0 Soil/Sediment 1 1 0 0 0 0 0 0 Vegetation 0 0 0 0 5 3 11 0 Water 28 15 5 0 26 7 23 0 IV. Iodine (LL)MilkI 4 1 1 0 4 1 1 0 Water 2 1 0 0 1 2 1 0 0 V. Ni-63 Soil/Sediment 1 0 0 0 0 0 0 0 Water 4 0 2 0 0 2 2 0 V. Sr-89 Air Filter 1 0 1 0 0 2 0 0 Milk 1 2 0 0 3 0 0 0 Water 3 2 1 0 _ _6 0 0 0 VI. Sr-90 Air Filter 1 0 1 0 0 2 0 0 Milk 1 0 2 0 1 1 1 0 Soil/Sediment 0 0 0 1 0 0 0 0 Water 5 7 5 0 10 2 4 0 VII. Tritium Water 11 6 1 1 7 5 9 _ _0 Total Number in 314 91 35 3 189 43 72 1 Range: Percentage of 70.9 20.5 7.9 0.7 62.0 14.1 23.6 0.3 Total Processed:

I I _ I I III Sum of Analyses:

443 305 (1) Percent Bias by Deviation Category as noted in Table 1, Footnote (1)(2) Percent Precision by Deviation Category as noted in Table 1, Footnote (2)(3) Most Precision data generated from non-positive client samples for specific contractual evaluation

• Total may not equal 100 due to rounding.** Totals summarize Internal PCs and Analytics Cross Check programs F:\ADMIN\CORRES\EL 081-07-A11-TABLE 10 ECKERT-& ZIEGLER ANALYTICS RADIOCHEMISTRY CROSSCHECK PROGRAM RESULTS BY AREVA NP ENVIRONMENTAL LABORATORY ACCEPTANCE CRITERIA, MEDIA, AND MEASUREMENT CATEGORIES JANUARY -JUNE 2007 Bias Criteria (1) Precision Criteria (2)1 2 3 4 1 2 3 4 I. Water Fe-55 3 1 2 0 3 3 0 0 Sr-89 3 2 1 0 4 2 0 0 Sr-90 2 2 2 0 2 4 0 0 Total Number in 8 5 5 0 9 9 0 0 Range: I Percentage of 44.4 27.8 27.8 0.0 50.0 50.0 0.0 0.0 Total Processed:

Sum of Analyses:

18 18 (1) Percent Bias by Deviation Category as noted in Table 12, Footnote (1)(2) Percent Precision by Deviation Category as noted in Table 12, Footnote (2)* Total may not equal 100 due to rounding 081-07-A13-TABLE 11 AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS RADIOCHEMISTRY CROSS-CHECK PERFORMANCE EVALUATION Mean Ratio Sample Quarter/ Sample Reported Known E-LAB/Number Year Media Nuclide Units Value Value Analytics Evaluation A21176-162 1 st/2007 Liquid Fe-55 uCi/cc 7.75E-04 6.97E-04 1.11 Agreement A21177-162 1st/2007 Liquid Sr-89 uCi/cc 8.21E-03 7.96E-03 1.03 Agreement A21177-162 Ist/2007 Liquid Sr-90 uCi/cc 3.96E-04 4.01E-04 0.99 Agreement A21481-162 2nd/2007 Liquid Fe-55 uCi/cc 9.24E-04 9.02E-04 1.02 Agreement A21482-162 2nd/2007 Liquid Sr-89 uCi/cc 1.96E-02 2.00E-02 0.98 Agreement A21482-162 2nd/2007 Liquid Sr-90 uCi/cc 1.82E-03 1.87E-03 0.97 Agreement F:V\.DMIN\C0RRES\EL 081-07-A4-A14-TABLE 16 CONDITION REPORT (CR) STATUS JANUARY -JUNE 2007 (OPEN) (CLOSED)INITIATION CLOSE-OUT CR # DATE DATE DESCRIPTION STATUS AS OF07/01/07 CLOSED -Sample was re-eluted from Sr column and results were Analytics environmental cross check determined to meet acceptance criteria.

Documentation was reviewed and for Sr-90 in air filter failed to meet no errors were identified.

Sr-90 3rd party QC results were reviewed with no acceptance criteria significant problems noted with Analytics samples. Backgrounds and blanks are being updated on a more frequent basis.CR 06-16 18-Oct-06 1-May-07 CLOSED -A detailed review of required reading compliance was conducted.

All missing training was completed.

A review of the impact on quality was Procedure required reading for two performed with no problems noted. A modification to the process for issuing chemists was noted to be incomplete, training was made. Instead of each supervisor sending training notices to their employees, a single training coordinator will provide the notices from a CR 06-17 19-Oct-06 2-Jan-07 master training matrix that is approved and maintained by the LQARC.CLOSED -A reviewof all contract files was completed to identify any Numerous contract review forms were identified to have not been completed missing forms. These forms have been generated and approved.

A new as required.

procedure detailing contract review is in effect that includes tracking forms CR 06-18 20-Oct-06 20-Jun-07 for all new and revised contracts.

CLOSED -Problems with non-homogeneity of the MAPEP vegetation MAPEP vegetation gamma gamma sample. A backup sample has been obtained.

Per MAPEP spectroscopy results were evaluated Coordinator, non-homogeneity of sample prohibits use as calibration as "Wamning." standard.

Future vegetation samples to be analyzed in elevated geometry.CR 06-19 13-Nov-06 1-May-07 MAPEP soil gamma spectroscopy OPEN -A backup sample has obtained from MAPEP and will be recounted results were evaluated as "Not for extended count to evaluate previous failure.CR 06-20 13-Nov-06 Acceptable." MAPEP air particulate Sr-90 results OPEN -A backup sample has been obtained to permit reprocessing.

Filter were evaluated as "Warning." dissolution testing as well as instrument background and analytical blank CR 06-21 13-Nov-06 testing is being conducted.

IAEA gamma spectroscopy sample results for soil, grass, and water had OPEN -Reprocessing of the 3 matrices is being conducted to detemine the radionuclides evaluated as "Warning" source of any errors.CR 06-22 15-Nov-06 and "Not Acceptable." Problems were encountered during CLOSED -1) gross beta failed PT limits due to insufficient time for radon the processing of ERA Proficiency daughter decay. Results from recount the next day indicated successful Thpestsig oRAD-67 Prfcec L1509):1) results. All chemists have been reminded of the need to utilize the LIMS Test set RAD-67 (LSN Li1509): 1) processing work lists. Management has been reminded to more closely gross alpha/beta sample prep not track PT samples with hard due dates. 2) LIMS V&V to add "Methods" to completed until report due date, 2) 2 reports found to be incorrectly completed.

LIMS reports have been modified reports listed incorrect "Method," 3) no to include" methods".

V+V of change in process. 3) Chemists have been CRanalytical blank for gross alpha/beta, reminded of the need to perform blanks as required by QA Manual.CLOSED -The 1-129 precipitate was noted to have an unusual color/consistency but exhibited a stable weight. When recovery values are Part 61 Process Check sample for I- removed, the activity values are extremely consistent.

The stability of the 129 failed precision limits but had chemicals, reagents, standards used in processing failed to identify a 129epiled psreisiuliits.

d problem. The heating block was noted to have some edge positions that do not heat to same degree as internal positions.

Insufficient distillation time determined to be cause of failure. Analyst counseled, procedure already CR 06-24 5-Dec-06 1-May-07 contains sufficient details.F:\ADMIN\CORRES\EL 081-07-A20-TABLE 16 CONDITION REPORT (CR) STATUS JANUARY -JUNE 2007 (OPEN) (CLOSED)INITIATION CLOSE-OUT CR # DATE DATE DESCRIPTION STATUS AS OF 12/31106 LO-CAR- A gamma spectroscopy unit was not 2006-00135 tagged out of service with the CLOSED -The unit has been properly tagged, personnel have been re-NUPIC Audit procedurally required "Do Not Use" trained to the procedure, and the improper tags have been destroyed.

Finding 16-Nov-06 23-Mar-07 tag.2006-00136 A vendor audit finding was issued CLOSED -Condition Report Manual 180 has been revised to include the NUPIC Audit using a form not in an approved form for vendor findings.Finding 16-Nov-06 23-Mar-07 procedure/manual.

The QA Manual 100 requires LO-CAR- additional controls for: 1) record L006-CAR-0aditia controls, 2 efiior: 1 d reod CLOSED -QA Manual 100 has been revised to incorporate recommended NUPIC Audit auditor qualifications, and 3) verbiage for the three areas noted to enhance existing controls.Finding 16-Nov-06 23-Mar-07 procurement controls.Environmental water sample reported CLOSED -Sample was determined to have been cross-contaminated during by E-LAB to have positive Cs-137 pre-analysis filtering by another environmental sample that contained high a ythat was not confirmed by amounts of Cs-1 37 that was not disclosed by the client. New sample receipt aciin ety lprotocol implemented to preclude cross contamination of environmental CR 07-01 4-Jan-07 15-Feb-07 independent laboratory samples.Internal QA Assessment noted 4 admin issues not addressed by QA OPEN -1) Cross reference document has been created. 2) QC schedule Plan: 1) missing cross-reference, 2) updated for 2007 to have internal NVLAP dosimeter test, 3) Procedure has biennial testing by NVLAP, 3) inconrect been updated, 4) anomaly flags have been set and verified for other company reference on forms, 4) CER/LERs.failure to set anomaly flags for CR 07-02 9-Jan-07 CER/LER.C-14 Part 61 PC had high po sitive OPEN -Results from subsequent C-14 PC had acceptable bias. Data bias (33.7%). compared with no deficiencies noted. Single C-14 spikes to be submitted CR 07-03 11-Jan-07 monthly for evaluation.

3 Gross beta in water samples noted OPEN -Data reviewers were retrained on trending mechanisms.

Gross by 2 clients that results were alpha/beta in water procedure revised to describe recount mechanism, CR 07-04 23-Jan-07 inconsistent with previous results causes of disparate results under investigation.

Four client samples indicated non- CLOSED -Samples were re-processed and results compared favorably with Fositive activity for Ni-63 while referee referee lab. Cause identified to be communication deficiency.

Sr-89/90 lab found positive activityf chemist prepared samples using Sr-89/90 only procedure vice multi-nuclide CR 07-05 31-Jan-07 7-Feb-07 sequential procedure which caused loss of Ni-63 in processing fraction.OPEN -A project manager assigned to track client sample processing to Client sample processing deadlines ensure future deadlines are met. Daily status updates provided to the client were missed for the remainder of the project. Awaiting VP approval for closure -all CR 07-06 21-Mar-07 actions completed.

Environmental water sample MDC for OPEN -Client notified.

Composite sample management controls and gamma not met due to delay in processing are now under a single point of accountability.

Modifying CR 07-07 21-Mar-07 preparing composite worksheet to clarify MDC requirement.

A set of H-3 samples (L1 2012), duplicate and matrix spike were CLOSED -Performance issues addressed, matrix spike samples regenerated and reprocessed successfully.

Chemist has been counseled apparently mis-labeled during concemning attention to detail.CR 07-08 21-Mar-07 1-May-07 processing Environmental dosimeter result OPEN -New ECF generated and result was updated using the new value.questioned by client. Evaluation of ECF generation periodicity being performed.

CR 07-09 4-Apr-07 F:kADMIN\CORRES\EL 081-07-A21 -

TABLE 1 ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL CROSSCHECK PROGRAM RESULTS BY AREVA NP ENVIRONMENTAL LABORATORY ACCEPTANCE CRITERIA, MEDIA, AND MEASUREMENT CATEGORIES JULY -DECEMBER 2007 Bias Criteria (1) Precision Criteria (2)1 2 3 4 1 2 3 4 I. Air Particulate Alpha 3 0 0 3 6 0 0 0 Beta 3 0 3 0 6 0 0 0 Gamma 6 10 6 5 20 7 0 0 Sr-89 0 0 3 0 3 0 0 0 Sr-90 1 0 0 2 0 1 2 0 11. Charcoal Gamma 6 1 6 5 20[I1. Milk Gamma 33 19 6 2 48 8 4 0 Iodine (LL) 4 1 1 0 4 2 0 0 Sr-89 2 0 1 0 2 1 0 0 Sr-90 2 1 0 0 1 2 0 0 II1. Water Alpha 2 1 0 0 3 0 0 .0 Beta 3 0 0 0 3 0 0 0 Gamma 18 7 4 1 27 3 0 0 H-3 ,1 2 0 0 3 0 0 0 1-131 (LL) 1 2 0 0 2 1 0 0 Sr-89 0 0 0 0 1 0_0 0 Sr-90 0 0 0 0 0 0 0 0 Total Number in Range: 80 .45 24 13 130 26 6 0 Percentage of Total Processed:

49.4 27.8 14.8 8.0 80.2 16.0 3.7 0.0 Sum of Analyses:

162 162 (1) Percent Bias by Deviation Category as noted in Table 1, Footnote (1)(2) Percent Precision by Deviation Category as noted in Table 1, Footnote (2)* Total may not equal 100 due to rounding F:\ADMIN\CORRES\EL 037-081 A-2 TABLE 2 AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIELGLER ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known E-LAB/Number Year Media Nuclide Units Value Value Analytics Evaluation E5334-162 2nd/2007 Water H-3 pCi/L 8520 9040 0.94 Agreement E5335-162 2nd/2007 Filter Gross Alpha Pci 122.7 125 0.98 Agreement E5335-162 2nd/2007 Filter Gross Beta pci 127 112 1.13 Agreement E5335-162 2nd/2007 Filter Ce-141 Pci 94.1 107 0.88 Agreement E5335-162 2nd/2007 Filter Cr-51 Pci 230 273 0.84 Non-Agreement (1)E5335-162 2nd/2007 Filter Cs-134 Pci 114.3 129 0.89 Agreement E5335-162 2nd/2007 Filter Cs-1 37 pCi 86.3 90.1 0.96 Agreement E5335-162 2nd/2007 Filter Co-58 Pci 98.4 106 0.93 Agreement E5335-162 2nd/2007 Filter Mn-54 Pci 83.3 88.5 0.94 Agreement E5335-162 2nd/2007 Filter Fe-59 pCi 79 89.0 0.89 Agreement E5335-162 2nd/2007 Filter Zn-65 pCi 167 178 0.94 Agreement E5335-162 2nd/2007 Filter Co-60 Pci 112 127 0.89 Agreement E5337-162 2nd/2007 Filter Sr-89 pCi 71.4 91.2 0.78 Agreement E5337-162 2nd/2007 Filter Sr-90 pCi 10.1 12.4 0.82 Agreement E5338-162 2nd/2007 Milk 1-131LL pCi/L 73.5 70.1 1.05 Agreement E5338-162 2nd/2007 Milk 1-131 pCi/L 75 70.1 1.07 Agreement E5338-162 2nd/2007 Milk Ce-141 pCi/L 168 200 0.84 Non-Agreement (2)E5338-162 2nd/2007 Milk Cr-51 pCi/L 447 512 0.87 Agreement E5338-162 2nd/2007 Milk Cs-134 pCi/L 223 242 0.92 Agreement E5338-162 2nd/2007 Milk Cs-137 pCi/L 165 169 '0.98 Agreement E5338-162 2nd/2007 Milk Co-58 pCi/L 203 198 1.02 Agreement E5338-162 2nd/2007 Milk Mn-54 pCi/L 178 166 1.07 Agreement E5338-162 2nd/2007 Milk Fe-59 pCi/L 170 167 1.02 Agreement E5338-162 2nd/2007 Milk Zn-65 pCi/L 343 334 1.03 Agreement E5338-162 2nd/2007 Milk Co-60 pCi/L 238 238 1.00 Agreement F:\ADMIN\CORRES\EL 037-08 A-4 TABLE 2 (continued)

AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIELGLER ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known E-LAB/Number Year Media Nuclide Units Value Value Analytics Evaluation E5430-162 3rd /2007 Water Gross Alpha pCi/L 112 109 1.03 Agreement E5430-162 3rd /2007 Water Gross Beta pCi/L 218 214 1.02 Agreement E5431-1.62 3rd /2007 Water I-131 LL pCi/L 83.4 80.1 1.04 Agreement E5431-162 3rd /2007 Water 1-131 pCi/L 80.2 80.1 1.00 Agreement E5431-162 3rd /2007 Water Ce-141 pCi/L 176 182 0.97 Agreement E5431-162 3rd /2007 Water Cr-51 pCi/L 228 249 0.92 Agreement E5431-162 3rd /2007 Water Cs-134 pCi/L ill 127 0.87 Agreement E5431-162 3rd /2007 Water Cs-1 37 pCi/L 112 112 1.00 Agreement E5431-162 3rd /2007 Water Co-58 pCi/L 94.3 98.1 0.96 Agreement E5431-162 3rd /2007 Water Mn-54 pCi/L 141 144 0.98 Agreement E5431-162 3rd /2007 Water Fe-59 pCi/L 94.8 95.1 1.00 Agreement E5431-162 3rd /2007 Water Zn-65 pCi/L 186 174 1.07 Agreement E5431-162 3rd /2007 Water Co-60 pCi/L 120 127 0.94 Agreement E5432-162 3rd /2007 Charcoal 1-131 pCi 66.5 69.6 0.96 Agreement E5433-162 3rd /2007 Filter Gross Alpha pCi 86.4 105 0.82 Non-Agreement (3)E5433-162 3rd /2007 Filter Gross Beta pCi 190 196 0.97 Agreement E5434-162 3rd /2007 Milk 1-131LL pCi/L 87.2 85.2 1.02 Agreement E5434-162 3rd /2007 Milk 1-131 pCi/L 82.9 85.2 0.97 Agreement E5434-162 3rd /2007 Milk Ce-141 pCi/L 196 211 0.93 Agreement E5434-162 3rd /2007 Milk' Cr-51 pCi/L 282 289 0.97 Agreement E5434-162 3rd /2007 Milk Cs-1 34 pCi/L 141 147 0.96 Agreement E5434-162 3rd /2007 Milk Cs-1 37 pCi/L 126 131 .0.96 Agreement E5434-162 3rd /2007 Milk Co-58 pCi/L 111 114 0.97 Agreement E5434-162 3rd /2007 Milk Mn-54 pCi/L 171 168 1.02 Agreement E5434-162 3rd /2007 Milk Fe-59 pCi/L 112 ill 1.01 Agreement E5434-162 3rd /2007 Milk Zn-65 pCi/L 212 202 1.05 Agreement E5434-162 3rd /2007 Milk Co-60 pCi/L 145 148 0.98 Agreement E5435-162 3rd /2007 Milk Sr-89 pCi/L 89.2 94.9 0.94 AAgreement E5435-162 3rd /2007 Milk Sr-90 pCi/L 12.9 13.1 0.98 Agreement (1) Cr-51 on filter outside of acceptance limit. CR 08-02 generated.

(2) Ce-141 in milk outside of acceptance limit. CR 08-02 generated.

(3) Gross alpha on filter outside of acceptance limit. CR 08-01generated.

F:\ADMIN\CORRES\EL 037-08 A-5 TABLE 2 (continued)

AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIELGLER ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known E-LAB/Number Year Media Nuclide Units Value Value Analytics Evaluation E5527-162 4th/2007 Water H-3 pCi/L 9003 (4)E5528-162 4th/2007 Water Sr-89 pCi/L 87.1 (4)E5528-162 4th/2007 Water Sr-90 pCi/L 14.4 (4)E5530-162 4th/2007 Filter Gross Alpha pCi 102.7 (4)E5530-162 4th/2007 Filter Gross Beta pCi 166.1 (4)E5531-162 4th/2007 Filter Ce-141 pCi 84.1 (4)E5531-162 4th/2007 Filter Cr-51 pCi 311.7 (4)E5531-162 4th/2007 Filter Cs-134 pCi 82.3 (4)E5531-162 4th/2007 Filter Cs-137 pCi 108.9 (4)E5531-162 4th/2007 Filter Co-58 pCi 107.5 (4)E5531-162 4th/2007 Filter Mn-54 pCi 117.2 (4)E5531-162 4th/2007 Filter Fe-59 pCi 86.6 (4)E5531-162 4th/2007 Filter Zn-65 pCi 135.3 (4)E5531-162 4th/2007 Filter Co-60 pci 123.1 (4)E5532-162 4th/2007 Filter Sr-89 pCi 45.9 (4)E5532-162 4th/2007 Filter Sr-90 pCi 7.2 (4)E5533-162 4th/2007 Milk 1-131LL pCi/L 59.2 (4)E5533-162 4th/2007 Milk 1-131 pCi/L 58.5 (4)E5533-162 4th/2007 Milk Ce-141 pCi/L 136.0 (4)E5533-162 4th/2007 Milk Cr-51 pCi/L 516.7 (4)E5533-162 4th/2007 Milk Cs-134 pCi/L 137.0 (4)E5533-162 4th/2007 Milk Cs-137 pCi/L 166.2 (4)E5533-162 4th/2007 Milk Co-58 pCi/L 166.5 (4)E5533-162 4th/2007 Milk Mn-54 pCi/L 200.9 (4)E5533-162 4th/2007 Milk Fe-59 pCi/L 155.0 (4)E5533-162 4th/2007 Milk Zn-65 pCi/L 222.9 (4)E5533-162 4th/2007 Milk Co-60 pCi/L 205.1 (4)E5529-162 4th/2007 Charcoal 1-131 pCi 69.8 (4)(4) -Results have been submitted for evaluation.

F:-\ADMIN\CORRES\EL 037-08 A-6 TABLE 5 ENVIRONMENTAL RESOURCE ASSOCIATES PROFICIENCY TEST RESULTS AREVA NP ENVIRONMENTAL LABORATORY ERA REPORTED ERA ERA ERA LOT #1 MATRIX/ RADIO- MEAN VALUE VALUE CONTROL WARNING REF. DATE UNITS NUCLIDE pCi/L pCi/L LIMITS LIMITS EVALUATION RAD 70/ 07-09-2007 Water pCi/L Gross Alpha 27.6 27.1 15.4-38.8 Acceptable RAD 70/ 07-09-2007 Water pCi/L Gross Beta .10.7 11.5 2.84-20.2 Acceptable RAD 70/ 07-09-2007 Water pCi/L Tritium 1540 1770 1180-2360 Acceptable RAD 70/ 07-09-2007 Water pCi/L Ba-1 33 16.9 19.4 10.7-28.1 Acceptable RAD 70/ 07-09-2007 Water pCi/L Cs-134 69 68.9 60.2-77.6 Acceptable RAID 70/ 07-09-2007 Water pCi/L Cs-137 57.5 61.3 52.6-70 Acceptable RAID 70/ 07-09-2007 Water pCi/L Co-60 33.7 33.5 24.8-42.2 Acceptable RAD 70/ 07-09-2007 Water pCi/L Zn-65 61.9 54.6 45.2-64.0 Acceptable RAD 70/ 07-09-2007 Water pCi/L 1-131 26.4 26.5 21.3-31.7 Acceptable F-\ADMIN\CORRES\EL 037-08 A-9 TABLE 6 INTRA-LABORATORY ENVIRONMENTAL PROCESS CONTROL RESULTS BY AREVA NP ENVIRONMENTAL LABORATORY ACCEPTANCE CRITERIA, MEDIA, AND MEASUREMENT CATEGORIES JULY -DECEMBER 2007 Bias Criteria (1) Precision Criteria (2), (3)1 2 3 4 1 2 3 4 I. Air Particulate Beta 112 6 1 0 0 0 0 0 Sr-90 0 0 1 0 0 0 0 0 II. Air Charcoal Gamma-Quantitative 46 15 1 0 0 0 0 0 II1. Food (Aquatic/Terrestrial)

Gamma 0 0 0 0 0 0 0 0 IV. Milk Gamma 0 0 0 0 0 0 0 0 Iodine (LL) 4 0 1 0 4 0 1 0 V. Soil/Sed.Gamma 1 4 1 0 0 0 0 0 Ni-63 0 0 0 0 0 0 0 0 Sr-90 0 0 0 0 0 0 0 0 VI. Vegetation (Aquatic/Terrestrial)

-Gamma 0 0 0 _ 0 0 0 0 VII. Water Gross Alpha 0 0 0 0 0 0 0 0 Gross Beta 0 0 0 0 0 0 0 0 Gamma 6 0 0 0 6 0 0 0 Iodine (LL) 0 0 0 0 0 0 0 0 Ni-63 0 0 0 0 0 0 0 0 Sr-90 0 0 0 0 0 0 0 0 Tritium 2 7 1 1 9 0 2 0 Total Number 171 32 6 1 19 0 3 0 in Range: Percentage of 81.4 15.2 2.9 0.5 86.4 0.0 13.6 0.0 Total Processed:

Sum of Analyses:

210 22 (1) Percent Bias by Deviation Category as noted in Table 1, Footnote (1)(2) Percent Precision by Deviation Category as noted in Table 1, Footnote (2)(3) Most Precision data generated from non-positive client samples for specific contractual evaluation

• Total may not equal 100 due to rounding F:\ADMIN\CORRES\EL 037-08 A-10 TABLE 7 AREVA NP ENVIRONMENTAL LABORATORY ENVIRONMENTAL INTRA-LABORATORY AND INTER-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY MEDIA JULY -DECEMBER 2007 Bias Criteria (1) Precision Criteria (2), (3)I 2 T 3 4 1 2 3 4 I. Air Filter Gross Alpha 3 0 0 3 6 0 0 0 Gross Beta 115 6 4 0 6 0 0 0 Gamma 6 10 6 5 20 7 0 0 Sr-89 0 0 3 0 3 0 0 0 Sr-90 1 0 1 2 0 1 2 0 II. Charcoal Gamma-Quantitative 47 J 17 1 0 2 1 0 111. Food (Aquatic/Terrestrial)

_ _Gamma 010] 010 [o0o0 IV. Milk Gamma 33 19 6 2 48 ..8 4 0 Iodine (LL) 8 1 2 0 8 2 1 0 Sr-89 2 0 1 0 2 1 0 0 Sr-90 2 1 0 0 1 2 0 0 V. Soil/Sediment Gamma 1 4 1 0 0 0 0 0 Ni-63 0 0 0 0 0 " 0 0 0 Sr-90 0 0 0 0 0 0 0 0 VI. Vegetation (Aquatic/Terrestrial)

Gamma 0 1 0 I 0 1 0 0 0 1 0 j 0 VII. Water i ___Gross Alpha 2 1 0 0 3 0 0 0 Gross Beta 3 0 0 0 3 0 0 0 Gamma 24 7 4 1 33 3 0 0 Iodine (LL) 1 2 0 0 2 1 0 0 Ni-63 0 0 0 0 0 0 0 0 Sr-89 0 0 0 0 0 0 0 0 Sr-90 0 0 0 0 0 0 0 0 Tritium 3 9 1 1 12 0 2 0 Total Number in 251 77 30 14 149 26 9 0 Range: Percentage of 67.5 20.7 8.1 3.8 81.0 14.1 4.9 0.0 Total Processed:

Sum of Analyses:

372 184 (1) Percent Bias by Deviation Category as noted in Table 1, Footnote (1)(2) Percent Precision by Deviation Category as noted in Table 1, Footnote (2)(3) Most Precision data generated from non-positive client samples for specific contractual evaluation

• Total may not equal 100 due to rounding.** Totals summarize Internal PCs and Analytics Cross Check programs F:\ADMIN\CORRES\EL 037-08 A-1 1 TABLE 8 AREVA NP ENVIRONMENTAL LABORATORY ENVIRONMENTAL INTRA-LABORATORY AND INTER-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY ANALYSIS TYPE JULY -DECEMBER 2007 Bias Criteria (1) Precision Criteria (2), (3)1 2 3 4 1 2 3 I. Gross Alpha Air Filter 3 0 0 3 6 0 0 0 Water 2 1 0 0 3 0 0 0 I1. Gross Beta Air Filter 115' 6 4 0 6 0 0 0 Water 3 0 0 0 3 0 0 0 Ill. Gamma Air Filter 6 10 6 5 20 7 0 0 Charcoal-Quantitative 47 17 1 0 2 1 0 0 Food 0 0 0 0 0 0 0 0 Milk 33 19 6 2 48 8 4 0 Soil/Sediment 1 4 1 0 0 0 0 0 Vegetation 0 0 0 0 0 0 0 0 Water 24 7 4 1 33 3 0 0 IV. Iodine (LL)Milk 8 1 2 0 8 2 1 0 Water 1 2 0 0 2 1 0 0 V. Ni-63 Soil/Sediment 0 0 0 0 0 0 0 0 Water 0 0 0 0 0 0 0 0 V. Sr-89 Air Filter 0 03 0 3 0 0 0 Milk 2 0 1 0 2 1 0 0 Water 0 0 0 0 0 0 0 0 VI. Sr-90 Air Filter 1 0 1 2 0 1 2 0 Milk 2 1 0 0 1 2 0 0 Soil/Sediment 0 0 0 0 0 0 0 0 Water 0 0 0 0 0 0 0 0 VII. Tritium Water 3 9 1 1 12 0 2 0 Total Number in 251 77 30 14 149 26 9 0 Range: Percentage of 67.5 20.7 8.1 3.8 81.0 14.1 4.9 0.0 ITotal Processed:

Sum of Analyses:

372 184 (1) Percent Bias by Deviation Category as noted in Table 1, Footnote (1)(2) Percent Precision by Deviation Category as noted in Table 1, Footnote (2)(3) Most Precision data generated from non-positive client samples for specific contractual evaluation

• Total may not equal 100 due to rounding.** Totals summarize Internal PCs and Analytics Cross Check programs 037-08 A-12 TABLE 10 ECKERT & ZIEGLER ANALYTICS RADIOCHEMISTRY CROSSCHECK PROGRAM RESULTS BY AREVA NP ENVIRONMENTAL LABORATORY ACCEPTANCE CRITERIA, MEDIA, AND MEASUREMENT CATEGORIES JULY -DECEMBER 2007 Bias Criteria (1) Precision Criteria (2)1 2 T 3 4 1 2 3 4 I. Water Fe-55 1 2 2 1 3 2 1 0 Sr-89 2 2 2 0 2 4 0 0 Sr-90 1 2 3 0 2 2 2 0 Total Number in 4 6 7 1 7 8 3 0 R ange: .... ...........

Percentage of 22.2 33.3 38.9 5.6 38.9 44.4 16.7 0.0 Total Processed:

Sum of Analyses:

18 18 (1) Percent Bias by Deviation Category as noted in Table 12, Footnote (1)(2) Percent Precision by Deviation Category as noted in Table 12, Footnote (2)* Total may not equal 100 due to rounding F:AADMIN\CORRES\EL 037-08 A-14 TABLE 11 AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS RADIOCHEMISTRY CROSS-CHECK PERFORMANCE EVALUATION Mean Ratio Sample Quarter/ Sample Reported Known E-LAB/Number Year Media Nuclide Units Value Value Analytics Evaluation A21629-162 3rd/2007 Liquid Fe-55 uCi/cc 2.76E-03 2.16E-03 1.28 Non-Agreement A21630-162 3rd/2007 Liquid Sr-89 uCi/cc 9.84E-03 9.99E-03 0.99 Agreement A21630-162 3rd/2007 Liquid Sr-90 uCi/cc 8.87E-04 9.50E-04 0.93 Agreement A21973-162 4th/2007 Liquid Fe-55 uCi/cc 1.06E-03 9.99E-04 1.06 Agreement A21974-162 4th/2007 Liquid Sr-89 uCi/cc 6.95E-03 7.04E-03 0.99 Agreement A21974-162 4th/2007 Liquid. Sr-90 uCi/cc 7.67E-04 7.89E-04 0.97 Agreement F:ADMIN\CORRES\EL 037-08 A-15 TABLE 16 CONDITION REPORT (CR) STATUS JULY -DECEMBER 2007 (OPEN) (CLOSED)INITIATION CLOSE-OUT CR # DATE DATE DESCRIPTION STATUS AS OF07101107 Entergy IP environmental water CLOSED -Results from subsequent C-14 PC had acceptable bias. Data sample was noted by client to have C ompared with no deficiencies noted. Single C-14 spikes to be submitted 137 activity that was not confirmed by monthlyforevaluation.

CR 07-03 11-Jan-07 15-Dec-07 independent laboratory 3 Gross beta in water samples noted CLOSED -Data reviewers were retrained on trending mechanisms.

Gross by 2 clients that results were alpha/beta in water procedure 320 revision 24 was issued on 08/24/07 to CR 07-04 23-Jan-07 14-Dec-07 inconsistent with previous results describe the appropriate recount mechanism.

CLOSED -A project manager was assigned to track client sample Client sample processing deadlines processing to ensure future deadlines are met. Daily status updates provided were missed to the client for the remainder of the project. All actions completed.

VP CR 07-06 21-Mar-07 28-Nov-07 approved closure on 11/26/07.Environmental water sample MDC for CLOSED -Client notified.

Composite sample management controls and gamma not met due to delay in processing are now under a single point of accountability.

Mechanisms were CR 07-07 21-Mar-07 19-Dec-07 prepadng composite put in place to assure timely preparation of composite samples.CLOSED -1) Package was immediately surveyed and sample receipt completed.

2) The empty drum, storage area was inspected to identify additional drums Part 61 sample drum found amongst not received.

None Identified.

empty drums ready for shipment back 3) The sample receipt process was counseled with E-Lab personnel.

See to clients, additional information below.4) The client was contacted and advised of the potential for a delay reporting results due to the delay in receipt of samples CR 07-10 23-May-07 13-Dec-07 CLOSED -Positive blanks were a result of overcrowding on the hot plate. 1)Batch sizes have been reduced to reduce the potential for contamination.

2)Part 61 blank sample indicated The processing chemist has been instructed to use glass covers during evaporation.

3) The processing chemist was interviewed and instructed on CR 07-11 17-Jul-07 19-Dec-07 good laboratory practices.

A prepared Matrix Spike sample was inadvertantly analyzed as a Laboratory OPEN -Awaiting the results of an investigation to identify affected sample Control Standard with a similar source sets and to evaluate impact on data quality.CR 07-13 30-Jul-07 identification number.Gamma spectroscopy MDC for La-140 CLOSED -The client was notified of the cause of the failure. Data packages are being reviewed in a more timnely manner, permitting sufficient time to CR 07-14 2-Aug-07 13-Dec-07 was not met, recount or reprocess, as required.CLOSED -An insufficient volume of LCS media was provided resulting in a H-3 Laboratory Control Standard low volume of distillate.

This resulted in steps being taken by the chemist results Laratr Coutrof Stange lothat were not in accordance with the procedure.

The chemist was instructed results were out of range low, to stop processing and notify the radiochemistry lead if the procedure can CR 07-15 2-Au,-07 19-Dec-07 not be followed precisely.

Fish samples indicated positve for Sr- CLOSED -Samples were reprocessed with an additional step to ensure that 90 due to Sr-85 tracer contamination calcium resulting from fish bones present in the field prepared samples was CR 07-16 2 5-Sep-07 13-Dec-07 in Y-90 vials, removed as part of the Sr-90 processing.

Progress Energy Part 61 gamma CLOSED -Personnel responsible for assuring required MDCs are met were results didn't meet MDC for Nb-94 and retrained, including retraining on E-Lab procedure 1102. A new Part 61 CR 07-17 5-Nov-07 17-Dec-07 Cs-1 37 Sample Information form was generated for tracking requirements.

CLOSED -An interview with the processing chemist indicated that poor 1 of 3 Tritium Process Checks for cleaning of glassware was the probable cause of the high bias. The chemist 2nd Qtr 07 out of range high was counceled on proper glassware cleaning techniques and the necessity CR07-18 6-Nov-07 19-Dec-07 Ito follow procedure.

SNAP Project Matrix Spike and LCS OPEN -The Federal Group Project Manager was provided with the QC analysis results identified as out of summary report on 12/14/07.

An investigation is ongoing to identify the CR 07-19 25-Nov-07

_range. cause of the failures and to evaluate the impact on data quality.

037-08 A-21 TABLE 16 CONDITION REPORT (CR) STATUS JULY -DECEMBER 2007 (OPEN) (CLOSED)INITIATION CLOSE-OUT CR # DATE DATE DESCRIPTION STATUS AS OF12131106 Performance and Documentation of OPEN -8 of 11 action items associated with this CR are complete.

The QA Schedule Elements is untimely.

remaining 3 items are pending.CR 07-20 28-Nov-07 OPEN -The client was notified of the data inconsistancies, and an updated QC Summary for SCE contains QC summary report was issued. An investigation into the cause of the incorrect data. inconsistancies and implementation of appropriate corrective actions are CR 07-21 28-Nov-07 pending.OPEN -A Client Purchase Order/Contract Review Form was missing for 1 Missing FORM M100.4 client. Client contracts are being reviewed to determine if this is an isolated CR 07-22 4-Dec-07 incident.Seeker gamma spec software CLOSED- Updated results were provided to the client. No additional errors incorrectly determined Nb-s 5 activity were identified by the review of several additional spectra. No problems norretly Progetermned Nb-9activity-were found from a review of the software library. Analysts were trained to CR 07-23 5-Dec-07 19-Dec-07 for Part 61 Progress Energy sample. identify similar errors when reviewing gamma spectrometry results.Low Level H-3 3rd party spike failed OPEN -Analysis of additional 3rd party low-level H-3 samples have been put r oon the QC schedule for 2008. The cause of the initial failure is still under for one chemist by micro dist investigation.

CR 07-24 14-Dec-07

____nvestigation.______

________________________________

F:ADMIN\CORRES\EL 037-08 A-22 A AREVA TABLE 1 PERCENTAGE OF INDIVIDUAL ANALYSES WHICH PASSED E-LAB INTERNAL CRITERIA January-June 2007 (1)Shallow (7 mglcm 2) Eye (300 mg/cm 2) Deep (1000 mg/cm 2)Number of % Passed % Passed % Passed % Passed % Passed % Passed Dosimeter Type Dosimeters Bias Precision Bias Precision Bias Precision Tolerance Tolerance Tolerance Tolerance Tolerance Tolerance Limit(2) Limit(3) Limit(2) Limit(3) Limit(2) Limit(3)Panasonic 808 30 100 100 100 100 100 100 Whole Body Panasonic 814 84 100 100 100 100 100 100 Whole Body Extremity 0 --N/A N/A N/A N/A Panasonic 100 100 Evrneal36 100N/ N/A N/A Environmental 36 (free in air) (free in air) N/A N/A (1) This table summarizes results of all depths for performance tests conducted by E-LAB and the Third-party tester for High Energy Photons.CONTROL LIMITS FOR E-LAB DOSIMETRY PERFORMANCE TESTS -APPLICABLE TO INDIVIDUAL TEST DOSIMETERS IRRADIATED TO HIGH ENERGY PHOTONS Dosimeter Type BTolerance Limits pBias ] Precision Panasonic Whole Body +/- 18.5% +/- 16.1%Extremity

+/- 32.6% +/- 27.2%Panasonic Environmental

+/- 20.1% +/- 12.8%(2) The percent deviation of individual results from the delivered dose is used to measure bias.(3) The percent deviation of individual results from the mean reported dose is used to measure precision.

F:\corres\EL 082-07.doc Appendix G Meteorological Data Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Wind direction frequency measured at 10 meters.Stability Class A N WNW WSW ENE SE ESE S Stability Class B N ENE SE ESE S Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Wind direction frequency measured at 10 meters.Stability Class C N WNW WSW ENE S E ESE S Stability Class D N WNW wSw ENE SE ESE S Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Wind direction frequency measured at 10 meters.Stability Class E N WNW W WSW ENE E ESE S Stability Class F N WNW wsw ENE E ESE S

.. ..Fermi 2 -2007Annual Radioactive Effluent Release and Radiological Environmental Operating Report Wind direction frequency measured at 10 meters.Stability Class G N WNW w WSW ENE SE ESE S All Stability Classes N WNW W WSW ENE E ESE S FERMI 2 2007 X/Q and D/Q Tables USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RNDT: 22-08 92 RUN DATE: 2-25-2008 9:25 PRINTOUT OF INPUT CARDS 00101 11100 00000 00000 .00000 00000 00000 00000 00000 00000 00000 00000 00000 00000 00000 00000 Fermi 2 2007 Data 9 7 1 15 10 .00 0.000 0.000 2 .000 10.000 20. 000 14.000 15.000 1.000 3.000 0.000 0.000 0.000 2.000 2 .000 3.000 5.000 2.000 1.000 0.000 0.000 0.000 4.000 5.000 3.000 3 .000 2.000 0.000 0.000 1.000 10.000 16.000 13.000 17.000 24.000 8.000 8.000 0.000 2.000 7.000 24.000 30. 000 15.000 21. 000 101.00 0.000 0.000 1.000 11.000 19.000 13 .000 6.000 4.000 4.000 0.000 0.000 0.000 0.000 2 .000 3 .000 7 .000 1.000 0.000 0.000 0.000 0.000 0.000 2 .000 0.000 1.000 1.000 0.000 0.000 0.000 5.000 26.000 24.000 11.000 13 .000 7.000 4.000 5.000 0.000 7.000 42.000 40.000 11.000 6.000 2.26 0.000 0.000 1.000 9.000 20.000 19.000 13.000 1.000 0.000 0.000 0.000 0.000 1.000 1.000 2.000 2 .000 1.000 0. 000 0.000 0.000 1.000 1.000 1'..000 7.000 4.000 1.000 0.000 0.000 0.000 4.000 16. 000 34.000 44. 000 33.000 14. 000 0.000 0.000 2.000 6.000 18.000 43.000 25.000 9.000 5-8.00 0.000 0.000 3 .000 7.000 28.000 26.000 24.000 10.000 3 .000 0.000 0.000 0.000 0.000 2.000 3.000 1.000 2.000 1.000 0.000 0.000 0.000 1.000 0.000 3 .000 9.000 2.000 1.000 0.000 0.000 3.000 6.000 18.000 22.000 42.000 31.000 12 .000 2 .000 3 .000 5.000 8.000 19.000 29.0010 15 .000 2 0 0.00 0.000 1.000 1.000 12.000 25.000 29.000 27.000 26.000 8.000 0.000 0.000 0.000 1.000 0.000 6.000 6.000 2 .000 1.000 0.000 0.000 0.000 0.000 1.000 1.000 1.000 3 .000 2 .000 0.000 0.000 0.000 3 .000 15.000 27.000 20.000 28.000 24.000 11.000 0.000 7.000 14.000 30.000 38.000 27.000 0.000 0.000 0.000 0.000*1.000 0.000 16.000 24.000 72.000 85.000 66.000117.000 34.000 3.000 3. 000 0.000 0. 000 1. 000 0. 000 3. 000 2. 000 1. 000 0. 000 0. 000 0. 000 0.000 0.000 2.000 2.000 3. 000 4. 000 2. 000 0. 000 0. 000 0. 000 0. 000 8.000 20.000 32.000 43. 000 5. 000 4.000 0.000 0.000 5.000 20.000 46.000 36.000 18.000 36.000 0.000 0.000 0.000 0.000 0.000 2 .000 2 .000 6.000 7.000 2.000 0.000 0.000 0.000 0.000 2 .000 1.000 3 .000 0.000 0.000 1.000 0.000 0.000 3 .000 7.000 17 .000 24.000 13 .000 5.000 3.000 0.000 0.000 6.-000 13 .000 33.000 33.000 21.000 0.000 2 .000 18.000 63.000 74.000 28.000 2.000 0.000 0.000 0.000 1.000 2.000 2.000 1.000 1.000 0.000 0.000 0.000 0.000 0.000 1.000 2.00.0 1.000 2.000 3.000 0.000 0.000 0.000 2.000 10.000 14.000 9.000 10.000 5.000 1.000 0.000 0.000 7.000 23.000 28.000 15 .000 9.000 0.000 1.000 22 .000 44.000 32.000 15.000 0.000 0.000 0.000 0.000 1.000 0.000 1.000 3 .000 1.000 0.000 0.000 0.000 0.000 0.000 5.000 3 .000 1.000 1.000 0.000 0.000 0.000 0.000 2 .000 13 .000 18.000 28.000 31.000 4.000 0.000 0.000 0.000 13.000 31.000 41.000 27 .000 7 .000 0.000 1.000 22.000 57.000 45.000 35.000 7.000 1.000 0.000 0.000 0.000 0.000 3.000 1.000 9.000 5.000 2.000 0.000 0.000 0.000 2.000 3.000 4.000 6.000 2.000 0.000 0.000 0.000 6.000 17.000 34.000 46.000 0 .000 3 .000 14 .000 31.000 44 .000 50 .000 16 .000 2 .000 0 .000 0 .000 0 .000 1 .000 5 .000 9 .000 15 .000 8.000 6 .000 2 .000 0 .000 0.000 2 .000 7 .000 11 .000 8.000 4.000 15 .000 1 .000 0.000 7.000 30.000 69.000 82 .000 0.000 3.000 17.000 39.000 31.000 33.000 6.000 1.000 0.000 0.000 0.000 5.000 6.000 5.000 4.000 5.000 1.000 0.000 0.000 0.000 2.000 5.000 3.000 15.000 5.000 0.000 0.000 1.000 10.000 55.000 76.000 77.000 46.000 6.000 0.000 0.000 0.000 39.000 0.000 11.000 1.000 31.000 27.000 32.000 7.000 0.000 0.000 0.000 0.000 3.000 9.000 3.000 7.000 4.000 0.000 0.000 0.000 1.000 6.000 5.000 7.000 2.000 4.000 0.000 0.000 3.000 16.000 39.000 56.000 46.000 31.000 6.000 1.000 0.000 2.000 42.000 54.000 35.000 16.000 2.000 0.000 8.000 17 .000 33 .000 32 .000 21.000 9 .000 2 .000 0.000 0.000 0.000 3 .000 4.000 7 .000 3 .000 3 .000 0.000 0.000 0 .000 0 .000 3 .000 6 .000 4.000 1.000 1.000 2 .000 0.000 0 .000 14.000 28.000 36.000 30.000 23 .000 14.000 0 .000 0 .000 2 .000 38.000 48 .000 29 .000 6.000 0 .000 0.000 4.000 44.000 39.000 27.000 9.000 6.000 1.000 0.000 0.000 0.000 2.000 8.000 5.000 2.000 0.000 1.000 0.000 0.000 1.000 4.000 3.000 5.000 4.000 0.000 1.000 0.000 0.000 8.000 32.000 26.000 29.000 20.000 3.000 1.000 0.000 2.000 26.000 57.000 31.000 12. 000 6.000 0.000 0.000 18.000 34.000 25.000 17.000 7.000 4.000 0.000 0.000 0.000 1.000 8.000 2.000 3.000 0.000 0.000 0.000 0.000 0.000 1.000 3 .000 4.000 1.000 2.000 0.000 0.000 0.000 7.000 39.000 43.000 17.000 13 .000 8.000 0.000 0.000 0.000 14.000 54.000 28.000 11.000 3 .000 79.000118.000 29.000 5- 000 0.000 0.000 9.000 39.000 71.000 78.000 86.000 39.000 15.000 5.000 0.000 23.000 78.000100.000 57.000 72.000 30.000 17.000 35.000 7.000 6 6 6 6 6 1 6 1 6 1 6 6 6 6 ,6.6 6 6 1 6 6:6 6 6 7 VRDI ST. VRCR 10 11 9.000 2.000 0.000 0.000.1.000.4.000.9.000 4.000 2.000 0.000 0.000 0.000 0.000 9.000 9.000 5.000 1.000 0.000 0. 000 0.000 0.000 ill1.0.000 0.000 0.000 0.000 5.000 12.000 1.000 4.000 3.000 0.000 0.000 0.000 0.000 5.000 1.000 0.000 0.000 0.000 0.000 0.000 0.000 0. 750*1.000 p0.000 p0.000 P1.000 P0.000 6.000 0.000 1.000 p0.000 0.000 0.000 0.000 0.000 1.000 2.000 p1.000 p0.000 p0.000 p0.000 0.000 p0.000 p2.500 918.0.2 10 4.000 1.000 2.000 1.000 2.000 1.000 2.000 3.000 3 .000 1.000 0.000 0.000 0.000 0.000 0.000 1.000 1.000 0.000 0.000 0.000 0.000 4.500 918.0.2 18.000 3.000 0.000 0.000 2.000 2.000 8.000 5.000 2 .000 4.000 6.000 0.000 0.000 0.000 1.000 1.000 3.000 1.000 2.000 0.000 1.000 6.500 918.10.2.000 0.000 0.000 0.000 2.000 13.000 15.000 9.000 0.000 0.000 0.000 0.000 0.000 0.000 4.000 2.000 3.000 2.000 0.000 1.000 0.000 8.500 918.0.2.000 0.000 0.000 1.000 4.000 5.000 6.000 7.000 4.000 1.000 0.000 0.000 0.000 1.000 7.000 6.000 2.000 11.000 2.000 0.000 0.000 11.500 918.0.3 .000 0.000 0.000 1.000 8.000 15.000 15.000 7 .000 2 .000 1.000 2 .000 0.000 0.000 2 .000 4.000 4.000 1.000 2.000 0.000 0.000 0.000 14.500 918.0.2 .000 0.000 0.000 1.000 16.000 23.000 6.000 6.000 2.000 0.000 0.000 0.000 0.000 5.000 6.000 6.000 4.000 0.000 0.000 0.000 0.000 18.500 19.000 4.000 0.000 1.000 17.000 30.000 25.000 22.000 16.000 3.000 0.000 0.000 0.000 5.000 17.000 7.000 10.000 7.000 0.000 0.000 0.000 23.500 6.000 3 .000 0.000 1.000 19.000 41.000 7 .000 3 .000 1.000 0.000 0.000 0.000 1.000 10.000 8.000 5.000 2 .000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1.000 39.000 33.000 2.000 3.000 1.000 0.000 0.000 0.000 1.000 25.000 12.000 2.000 0.000 1.000 0.000 0.000 0.000 0.000 1.000 0. 000 0.000 1.000 38. 000 36.000 3.000 0.000 0. 000 0.000 0.000 0.000 1.000 48.000 12. 000 1.000 0. 000 0.000 0.000 0.000 0.000 0.000 1.000 0.000 0.000 0.000 46.000 36.000 3.000 0.000 4.000 0.000 0.000 0.000 0.000 69.000 31.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 3.000 0.000 0.000 2.000 31.000 30.000 2.000 0.000 2.000 0.000 0.000 0.000 0.000 29.000 17.000 0.000 1.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1.000 20.000 22 .000 12 .000 0.000 1.000 0.000 0.000 0.000 0.000 19 .000 19.000 2 .000 0.000 0.000 0.000 0.000 0.000 918.0.NOT INPUTTED 918. 918.0. 0.11 11:TE BOUNDARY 918. 918.0. 0.12 1.3 SI 918. 918. 918. 918. 918.0. 0. 0. 0. 0.5 1390.0 14 11 1825.0 10 1646.0 11 579.0 1 1417.0 2 1542.0 3 1920.0 4 1798.0 6 1082.0 13 14 3 2025.0 13 14 13 14 7 915.0 8 990.0 Residences 9 1776.0 11 1773.0 10 2 1826.0 1 1640.0 MILK COW 7 5874.0 6 3672.0 VEGETABLE GARDEN 9 2633.0 10 2894.0 11 1646.0 8 1743.0 7 1700.0 6 1103.0 5 1861.0 4 2547.0 3200.0 8 4107.0 7 4435.0 2 2414.0 3 7062.0 5 5123.0 6 2936.0 4 5173.0 13 Visitor Center/Ice F 14 2 470.0 13 470.0 15 Reactor Bldg 16 11.800 2.190 51.2 17 A 0 0 0 15 Turbine Bldg 16 3.310 7.460 40.1 17 B 0 0 0 47.5 2300.0 51.2 0.00 40.1 5130.0 40.1 0.00 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RNDT: 22-08 92 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data JOINT.FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS A UMAX (M/IS)0.34 1 .12 2 .01 2 .91 3 .80 5.14 6.48 8.27 10.51 TOTAL N 0.000 0.023 0.116 0.232 0.162 0.174 0.012 0.035 0.000 0.75 NNE 0.000 0.012 0.127 0.220 0.151 0.070 0.046 0.046 0.000 0.67 NE 0.000 0.012 0.104 0.232 0.220 0 .151 0.012 0.000 0.000 0.73 ENE 0 .000 0.035 0 .081 0.324 0.301 0.278 0.116 0.035 0.000 1.17 E 0. 012 0.012 0.139 0.290 0.336 0.313 0.301 0.093 0.000 1.49 ESE 0.000 0.012 0.185 0. 834 0.765 0.394 0.035 0.035 0. 000 2.26 SE 0.000 0.000 0.278 0 .985 1.356 0.417 0.000 0.000 0.000 3 .04 SSE 0.000 0.023 0.209 0.730 0.858 0.324 0.023 0.000 0.000 2 .17 S 0.000 0 .012 0.255 0 .510 0.371 0.174 0.000 0.000 0.000 1.32 SSW 0.000 0.012 0.255 0.661 0.521 0.406 0.081 0.012 0.000 1.95 SW 0.000 0.035 0.162 0.359 0.510 0.579 0.185 0 .023 0.000 1.85 WSW 0.000 0.035 0.197 0.452 0.359 0.382 0.070 0.012 0.000 1.51 W 0.000 0.127 0.012 0.359 0.313 0.371 0.081 0.000 0.000 1.26 WNW 0.000 0.093 0 .197 0.382 0.371 0.243 0 .104 0 .023 0 .000 1.41 NW 0.000 0.046 0.510 0.452 0.313 0.104 0.070 0.012 0.000 1.51 NNW 0.000 0.000 0.209 0.394 0.290 0 .197 0.081 0.046 0.000 1.22 TOTAL 0.012 0.487 3.036 7.417 7.197 4.578 1.217 0.371 0.000 24.31 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS B UMAX (MI S)0.34 1 .12 2 .01 2 .91 3 .80 5.14 6.48 8.27 10.51 TOTAL N 0.000 0.000 0.023 0.023 0.035 0.058 0.023 0.012 0.000 0.17 NNE 0.000 0.000 0.000 0.023 0.035 0.081 0.012 0.000 0.000 0.15 NE 0.000 0.000 0.012 0.012 0 .023 0.023 0.012 0.000 0.000 0.08 ENE 0.000 0.000 0.000 0.023 0.035 0 .012 0.023 0..012 0.000 0.10 E ESE 0.000 0.000 0.000 0.012 0.012 0.000 0.000 0.035 0.070 0.023 0.070 0.012 0.023 0.000 0.012 0.000 0.000 0.000 0.19 0.08 SE 0.000 0.000 0.023 0.023 0.070 0 .081 0.023 0.000 0.000 0.22 SSE 0.000 0.012 0.023 0.023 0.012 0.012 0.000 0.000 0.000 0.08 S 0.000 0 .012 0.000 0 .012 0.035 0 .012 0 .000 0.000 0.000 0.07 SSW 0.000 0.000 0.000 0.035 0.012 0.104 0.058 0.023 0.000 0.23 SW 0.000 0.000 0.012 0.058 0.104 0.174 0.093 0.070 0.023 0.53 WSW 0.000 0.000 0.058 0.070 0.058 0.046 0.058 0. 012 0.000 0.30 W 0.000 0.000 0.035 0.104 0.035 0. 081 0. 046 0.000 0. 000 0.30 0W.00 0 .000 0.035 0.046 0.035 0.035 0.000 0.000 0.23 NW 0.000 0.000 0.023 0.093 0.058 0.023 0.000 0.012 0.000 0.21 NNW 0.000 0.000 0.012 0.093 0.023 0.035 0.000 0.000 0.000 0.16 TOTAL 0.000 0.035 0.267 0. 672 0.707 0.858 0.406 0.151 0.023 3 .12 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS C UMAX (MI S)0.34 1.12 2.01 2.91 3.80 5.14 6.48 8.27 10.51 TOTAL N 0.000 0.000 0.046 0.058 0.035 0.035 0.023 0.000 0.000 0.20 NNE 0.000 0.000 0.000 0.023 0.000 0 .012 0 .012 0.000 0.000 0.05 NE 0.000 0.012 0.012 0.012 0.081 0.046 0. 012 0.000 0.000 0 .17 ENE 0.000 0.000 0.012 0.000 0.035 0 .104 0.023 0.012 0.000 0.19 E ESE 0.000 0.000 0.000 0.000 0.000 0.023 0.012 0.023 0.012 0.035 0.012 0.046 0.035 0.023 0.023 0.000 0.000 0.000 0.09 0.15 SE 0.000 0.000 0.023 0.012 0.035 0.000 0.000 0.012 0.000 0.08 SSE 0. 000 0.000 0.012 0.023 0. 012 0.023 0.035 0.000 0. 000 0.10 5 SSW SW WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.058 0.023 0.023 0.023 0.035 0.035 0.081 0.058 0.012 0.046 0.127 0.035 0.012 0.070 0.093 0.174 0.000 0.023 0.046 0.058 0.000 0.000 0.174 0.000 0.000 0.000 0.012 0.000 0.12 0.20 0.56 0.35 W 0. 000 0. 012 0.070 0. 058 0. 081 0.023 0.046 0.000 0.000 0.29 0.00 0.000 0.035 0.070 0.046 0 .012 0 .012 0.023 0.000 0.20 NW 0.000 0.012 0.046 0.035 0.058 0.046 0.1000 0.012 0.000 0.21 NNW 0.000 0.000 0.012 0.035 0.046 0 .012 0.023 0.000 0.000 0.13 TOTAL 0. 000 0.035 0.417 0.568 0.695 0.719 0.371 0.255 0. 012 3 .07 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTIONATOPEISABLYCASU ATMOSPHERIC STABILITY CLASS D UMAX (M/IS)0 .34 1 .1:2 2 .01 2 .91 3 .80 5 .14 6.48 8.27 10.51 TOTAL N 0.012 0.116 0.185 0.151 0.197 0.278 0.093 0.093 0.000 1.12 NNE 0.000 0.058 0.301 0.278 0.127 0.151 0.081 0.046 0.058 1.10 NE ENE 0.000 0. 046 0.185 0.394 0.510 0.382 0.162 0.000 0.000 1.68 0.000 0.035 0.070 0.209 0.255 0 .487 0.359 0.139 0.023 1.58 E ESE 0.000 0.000 0.000 0.000 0.035 0.093 0.174 0.232 0.313 0.371 0.232 0.498 0.324 0.058 0.278 0.046 0.127 0.000 1.48 1.30 SE 0.000 0.035 0.081 0 .197 0.278 0.151 0.058 0.035 0.000 0.83 SSE 0. 000 0.023 0.116 0.162 0.104 0.116 0.058 0.012 0.000 0.59 S. SSW SW WSW 0.000 0.000 0.000 0.012 0.023 0.070 0.081 0.116 0.151 0.197 0.348 0.637 0.209 0.394 0.800 0.881 0.324 0.533 0.950 0.892 0.359 0.916 1.367 0.533 0.046 0.336 0.452 0.070 0.000 0.058 0.174 0.000 0.000 0.000 0.058 0.000 1.11 2.50 4.23 3.14 W 0.035 0.185 0.452 0.649 0.533 0.359 0.070 0.012 0.000 2.29 0.000 0 .162 0.324 0 .417 0.348 0.267 0 .162 0.000 0.000 1.68 NW 0.000 0.093 0.371 0.301 0.336 0.232 0.035 0.012 0.000 1.38 NNW 0.000 0.081 0 .452 0 .498 0 .197 0.151 0 .093 0.000 0.000 1.47 TOTAL 0. 058 1.124 3.998 5. 945 6.270 6.478 2 .457 0. 904 0.267 27.50 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS E UMAX (M/IS)0.34 1 .12 2 .01 2 .91 3 .80 5 .14 6.48 8.27 10.51 TOTAL N NNE NE ENE 0.023 0.081 0.278 0.348 0. 174 0.243 0.104 0.023 0.000 1.27 0.000 0.081 0.487 0.464 0.127 0.070 0.000 0.000 0.000 1.23 0.023 0.070 0.209 0.498 0.290 0.104 0.012 0.000 0.000 1.21 0.035 0.058 0.093 0.220 0.336 0.174 0.046 0 .012 0.023 1.00 E ESE 0.000 0.000 0.081 0.058 0.162 0.232 0.348 0.533 0.440 0.417 0.313 0.209 0.209 0.023 0.035 0.000 0.000 0.000 1.59 1.47 SE 0.000 0.070 0.151 0.382 0.382 0.243 0.023 0.000 0.000 1.25 SSE 0.000 0.081 0.267 0.324 0 .174 0.104 0.035 0.000 0.000 0.99.5 SSW SW WSW 0.000 0.000 0.000 0.000 0.151 0.104 0.267 0.452 0.359 0.452 0.904 1.159 0.475 0.823 0.661 0.834 0.313 0.904 0.348 0.197 0.081 0.997 0.406 0.081 0.023 0.220 0.070 0.000 0.000 0.046 0.035 0.000 0.000 0.000 0.000 0.000 1.40 3.55 2.69 2.72 W 0.023 0.487 0.626 0.406 0.185.0.023 0.012 0.000 0.000 1.76 WNW 0.023 0 .440 0.556 0.336 0.070 0.000 0 .012 0.000 0.000 1.44 NW 0. 023 0.301 0.661 0.359 0.139 0.070 0.035 0.000 0.000 1.59 NNW 0.000 0.162 0.626 0.324 0.127 0.035 0.000 0.000 0.000 1.27 TOTAL 0.151 2 .944 7.220 7.336 4.624 3 .152 0.823 0.151 0.023 26.42 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS F UMAX (MI S)0.34 1 .12 2 .01 2 .91 3 .80 5 .14 6.48 8.27 10.51 TOTAL N 0.000 0.127 0.162 0.220 0.046 0.023 0.000 0.000 0.000 0.58 NNE 0.000 0.058 0.139 0 .012 0.046 0.035 0.000 0.000 0.000 0.29 NE 0.012 0.000 0.070 0.000 0.012 0.000 0.000 0.000 0.000 0.09 ENE 0.012 0.023 0.012 0.023 0.035 0.035 0.012 0.000 0.000 0.15 E 0.000 0.023 0.023 0.093 0. 058 0.023 0.046 0.070 0.000 0.34 ESE 0.000 0.023 0.151 0.174 0.104 0.000 0.000 0.000 0.000 0.45 SE 0 .012 0.046 0.058 0.070 0.081 0.046 0.012 0.000 0.000 0.32 SSE 0.012 0.093 0 .174 0.174 0. 081 0.023 0.012 0.023 0. 000 0.59 S 0 .012 0.185 0.267 0.070 0.070 0.023 0.000 0.000 0.000 0.63 SSW 0.012 0.197 0.348 0.290 0.255 0.185 0.035 0.000 0.000 1.32 SW 0 .012 0.220 0.475 0 .081 0.035 0 .012 0.000 0.000 0.000 0.83 WSW 0.012 0.452 0.382 0.023 0.035 0.012 0.000 0.000 0.000 0.92 W 0.012 0.440 0.417 0.035 0.000 0.000 0.000 0.000 0.000 0.90 WNW 0.000 0.533 0 .417 0.035 0.000 0 .046 0.000 0.000 0.000 1.03 NW 0. 023 0.359 0.348 0.023 0.000 0.023 0.000 0.000 0.000 0.78 0 .012 0.232 0.255 0.139 0.000 0 .012 0.000 0 .000 0 .000 0.65 TOTAL 0.139 3. 013 3.697 1.460 0.858 0.498 0.116 0.093 0.000 9.87 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTIONATOPEISABLYCAS ATMOSPHERIC STABILITY CLASS G UMAX (M/IS)0.3.4 1 .12 2 .01 2 .91 3 .80 5.14 6.48 8.27 10.51 TOTAL N 0.000 0.104 0.220 0.058 0.012 0.000 0.000 0.000 0.000 0.39 NNE NE ENE 0.000 0.058 0 .012 0.000 0.000 0.000 0.000 0.000 0.000 0.07 0.000 0.012 0 .023 0.012 0.000 0.000 0.000 0.000 0.000 0 .05 0.000 0.000 0.000 0 .012 0 .012 0.000 0.000 0.000 0.000 0.02 E 0. 000 0. 000 0.012 0.012 0.035 0. 012 0.023 0.000 0. 012 0.10 ESE 0.000 0.000 0. 046 0.023 0.035 0.023 0.000 0.012 0.000 0. 14 SE 0.000 0.012 0.081 0.070 0.023 0.127 0.023 0.000 0.000 0.34 SSE 0. 000 0.023 0. 046 0. 046 0.012 0.023 0.000 0.000 0.000 0 .15 S 0.000 0.058 0.070 0.070 0.046 0.000 0.000 0 .000 0 .000 0.24 SSW 0.000 0.058 0.197 0.081 0.116 0.081 0.000 0.000 0.000 0.53 SW 0 .012 0 .116 0 .093 0 .058 0 .023 0.000 0.000 0 .000 0 .000 0.30 WSW 0. 012 0.290 0.139 0.023 0.000 0.012 0.000 0.000 0.000 0.48 W WNW NW NNW TOTAL 0.012 0.556 0.139 0.012 0.000 0.000 0.000 0.000 0.000 0.72 0.000 0.800 0.359 0.000 0.000 0.000 0.000 0.000 0.000 1.16 0.000 0.336 0.197 0.000 0.012 0.000 0.000 0.000 0.000 0.54 0.000 0.220 0.220 0.023 0 .000 0.000 0.000 0.000 0.000 0.46 0.035 2 .642 1.854 0.498 0.324 0.278 0.046 0. 012 0. 012 5.70 TOTAL HOURS CONSIDERED ARE 8629 WIND MEASURED AT 10.0 METERS.OVERALL WIND DIRECTION WIND DIRECTION:

FREQUENCY:

FREQUENCY N NNE 4.5 3.6 NE ENE 4.0 4.2 E ESE SE SSE 5.3 5.9 6.1 4.7 5 SSW SW 4.9 10.3 11.0 WSW 9.4 W WNW NW NNW TOTAL 7.5 7.2 6.2 5.4 100.0 OVERALL WIND SPEED FREQUENCY MAX WIND SPEED (MIS): 0.335 1.118 AVE WIND SPEED (MIS): 0.168 0.726 WIND SPEED FREQUENCY:

0.39 10.28 2 .012 1.565 20.49 2.906 2.459 23.90 3.800 5.141 6.482 3.353 4.470 5.812 20.67 16.56 5.44 8.270 7.376 1.94 10.505 9.388 0.34 THE CONVERSION FACTOR APPLIED TO THE WIND SPEED CLASSESS IS 0.447 DISTANCES DIRECTION DISTANCE ELEVATION AND TERRAIN S SSW 918. 918.0. 0.HEIGHTS IN METERS SW WSW W 918. 918. 918.0. 0. 0.AS FUNCTIONS WNW NW 918. 918.0. 0.OF DIRECTION FROM NNW N NNE 918. 918. 918.0. 0. 0.THE SITE: NE ENE 918. 918.0. 0.E 918.0.ESE SE 918. 918.0. 0.SSE 918.0.

USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 Fermi 2 2007 Data Reactor Bldg NO DECAY, UNDEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 0.250 0.500 0.750 RUN DATE: 2-25-2008 9:25 DISTANCE IN MILES FROM THE SITE 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 3 113E-06 1 951E-06 2 055E-06 2 475E-06 4 062E-06 3 604E-06 4 241E-06 2 922E-06 2 854E-06 8 338E-06 6. 128E-06 4 .332E-06 3 .047E-06 3 .227E-06 3 .079E-06 2 .730E-06 1. 055E-06 6. 660E-07 7 471E-07 8 549E-07 1 361E-06 1. 137E-06 1 .243E-06 8. 631E-07 9 .273E-07 2 .778E-06 2 176E-06 1. 530E-06 1. 077E-06 1. 058E-06 1. 011E-06 8. 900E-07 6. 114E-07 4. 077E-07 4 .787E-07 5 054E-07 7 695E-07 6 .448E-07 6. 500E-07 4 626E-07 5 .435E-07 1. 603E-06 1 .336E-06 9 .745E-07 6. 803E-07 6 .229E-07 5 946E-07 5 .357E-07 3. 424E-07 2 453E-07 2 880E-07 2 847E-07 4 161E-07 3 605E-07 3. 473E-07 2. 546E-07 3. 143E-07 8. 837E-07 7 .757E-07 6. 022E-07 4. 233E-07 3. 734E-07 3. 546E-07 3. 233E-07 1. 668E-07 1. 293E-07 1. 474E-07 1. 360E-07 1. 881E-07 1. 735E-07 1. 640E-07 1. 251E-07 1. 598E-07 4. 113E-07 3. 824E-07 3 .277E-07 2. 372E-07 2. 066E-07 1. 929E-07 1. 745E-07 1. 038E-07 8 .266E-08 9. 191E-08 8. 237E-08 1. 099E-07 1. 051E-07 9 914E-08 7. 799E-08 1. 011E-07 2. 463E-07 2 353E-07 2. 138E-07 1. 589E-07 1. 392E-07 1. 279E-07 1. 139E-07 7. 273E-08 5. 831E-08 6. 365E-08 5 630E-08 7 323E-08 7. 181E-08 6. 783E-08 5. 468E-08 7. 143E-08 1. 676E-07 1. 624E-07 1. 532E-07 1. 163E-07 1. 028E-07 9. 32 1E-08 8. 188E-08 5. 468E-08 4. 382E-08 4. 717E-08 4. 146E-08 5. 297E-08 5. 286E-08 5. O1OE-08 4. 117E-08 5. 400E-08 1.233E-07 1.204E-07 1. 166E-07 9. 002E-08 8. 039E-08 7.210E-08 6.256E-08 4 .313E-08 3.444E-08 3. 667E-08 3 .213E-08 4 .050E-08 4.097E-08 3. 898E-08 3 .253E-08 4 .277E-08 9. 567E-08 9 .381E-08 9 .265E-08 7 .252E-08 6. 537E-08 5. 811E-08 4.991E-08 3.523E-08 2 .798E-08 2 .954E-08 2 .585E-08 3.224E-08 3.297E-08 3.150E-08 2 .661E-08 3.505E-08 7 .712E-08 7 .579E-08 7.602E-08 6 .021E-08 5. 474E-08 4 .828E-08 4.111E-08 2.955E-08 2.333E-08 2. 445E-08 2. 139E-08 2.645E-08 2 .729E-08 2.618E-08 2 .235E-08 2.947E-08 6.399E-08 6.296E-08 6.393E-08 5. 116E-08 4. 688E-08 4. 106E-08 3. 470E-08 ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 5.000 7.500 10.000 DISTANCE IN MILES FROM THE SITE 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 SýSSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 2 .531E-08 1. 986E-08 2. 068E-08 1. 810E-08 2 .224E-08 2 .311E-08 2 .227E-08 1. 917E-08 2 .529E-08 5 .430E-08 5 .346E-08 5 .486E-08 4. 430E-08 4 088E-08 3. 558E-08 2.988E-08 1. 462E-08 1. 115E-08 1. 135E-08 9 967E-09 1 .201E-08 1. 280E-08 1. 257E-08 1. 112E-08 1. 468E-08 3 .038E-08 2 988E-08 3. 175E-08 2 656E-08 2. 518E-08 2. 138E-08 1. 756E-08 1 017E-08 7 .572E-09 7 .601E-09 6 .700E-09 7 997E-09 8 660E-09 8 632E-09 7 .748E-09 1 022E-08 2 .072E-08 2 031E-08 2 .205E-08 1. 891E-08 1. 827E-08 1. 522E-08 1 233E-08 6 370E-09 4 572E-09 4 504E-09 3. 995E-09 4 728E-09 5 224E-09 5 322E-09 4 851E-09 6. 394E-09 1. 264E-08 1. 232E-08 1. 374E-08 1. 219E-08 1. 207E-08 9. 790E-09 7. 804E-09 4. 557E-09 3. 184E-09 3 I00E-09 2 762E-09 3. 257E-09 3 646E-09 3. 772E-09 3. 466E-09 4. 563E-09 8. 888E-0.9 8. 629E-09 9. 778E-09 8. 887E-09 8. 939E-09 7 118E-09 5. 618E-09 3. 509E-09 2 .402E-09 2 .318E-09 2 .072E-09 2. 439E-09 2 .757E-09 2. 888E-09 2. 665E-09 3. 505E-09 6. 758E-09 6. 540E-09 7 .498E-09 6. 933E-09 7. 061E-09 5. 544E-09 4 346E-09 2. 831E-09 1. 907E-09 1. 826E-09 1. 637E-09 1. 927E-09 2. 195E-09 2 321E-09 2. 148E-09 2. 822E-09 5. 401E-09 5. 213E-09 6. 030E-09 5. 651E-09 5. 814E-09 4. 513E-09 3. 520E-09 2.360E-09 1. 569E-09 1. 493E-09 1. 342E-09 1. 579E-09 1. 810E-09 1. 930E-09 1. 790E-09 2 349E-09 4. 468E-09 4. 303E-09 5. 013E-09 4. 750E-09 4. 928E-09 3. 789E-09 2 .944E-09 2 .015E-09 1.324E-09 1 .254E-09 1.129E-09 1 .329E-09 1.531E-09 1.645E-09 1.527E-09 2 .003E-09 3 .791E-09 3 .644E-09 4 .271E-09 4. 083E-09 4 .268E-09 3 .255E-09 2 .521E-09 1 .753E-09 1. 141E-09 1. 075E-09 9. 696E-10 1. 142E-09 1.322E-09 1. 429E-09 1.328E-09 l.739E-09 3 .280E-09 3. 148E-09 3.707E-09 3.572E-09 3.757E-09 2 .846E-09 2 .198E-09 1. 547E-09 9. 982E-10 9. 370E-10 8. 463E-10 9.975E-10 1. 159E-09 1. 260E-09 1. 171E-09 1. 533E-09 2. 881E-09 2. 761E-09 3 .266E-09 3. 169E-09 3.352E-09 2. 523E-09 1. 945E-09 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) 51.20 DIAMETER (METERS) 2.19 EXIT VELOCITY (METERS) 11.80 AT THE RELEASE HEIGHT: VENT RELEASE MODE WIND SPEED (METERS/SEC)

REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)(METERS)(SQ.METERS)(CAL/SEC)51.2 47.5 2300.0 0.0 AT THE MEASURED WIND HEIGHT ( 10.0 METERS): VENT RELEASE MODE WIND SPEED (METERS/SEC)

STABLE CONDITIONS ELEVATED LESS THAN 1.043 MIXED BETWEEN 1.043 AND 5.215 GROUND LEVEL ABOVE 5.215 ELEVATED MIXED GROUND LEVEL LESS THAN BETWEEN ABOVE 2.360 2.360 AND 11.800 11.800 WIND SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS THAN 1.569 BETWEEN 1.569 AND 7.844 ABOVE 7.844 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data Reactor Bldg NO DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION

.5-1 FROM SITE S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE'SSE 5. 904E-07 3.929E-07 4.536E-07 4. 850E-07 7. 438E-07 6. 277E-07 6. 472E-07 4. 592E-07 5. 270E-07 1. 544E-06 1.274E-06 9. 325E-07 6. 542E-07 6. 086E-07 5. 806E-07 5. 200E-07 1-2 1. 778E-07 1 343E-07 1. 540E-07 1. 452E-07 2. 040E-07 1. 847E-07 1. 759E-07 1. 329E-07 1. 681E-07 4 .429E-07 4 045E-07 3 381E-07 2 .438E-07 2. 137E-07 1. 999E-07 1. 806E-07 2-3 7. 381E-08 5. 901E-08 6. 460E-08 5. 731E-08 7. 490E-08 7. 312E-08 6. 909E-08 5. 549E-08 7. 238E-08 1. 708E-07 1. 650E-07 1. 547E-07 1. 171E-07 1. 036E-07 9. 401E-08 8. 270E-08 3-4 4-5 5-10 10-20 4 .342E-08 3.466E-08 3. 695E-08 3.240E-08 4. 092E-08 4 .132E-08 3.930E-08 3 .274E-08 4.304E-08 9.650E-08 9.455E-08 9 .316E-08 7 .283E-08 6.561E-08 5 .836E-08 5. 017E-08 AVERAGE EFFECTIVE STACK HEIGHT IN METERS FOR EACH SEGMENT 2 966E-08 2 342E-08 2 456E-08 2 149E-08 2 661E-08 2 742E-08 2 631E-08 2 243E-08 2 957E-08 6 429E-08 6 324E-08 6. 415E-08 5. 130E-08 4. 698E-08 4. 117E-08 3 .482E-08 4-5 6 .759E+01 6. 846E+01 6. 826E+01 6. 416E+01 5. 849E+01 6. 654E+01 6. 692E+01 6. 773E+01 6. 859E+01 6. 371E+01 6. 558E+01 7 .032E+01 7 .278E+01 7 .115E+01 7 .139E+01 7. 055E+01 1.502E-08 1. 149E-08 1.176E-08 1. 032E-08 1 .250E-08 1 .325E-08 1 .297E-08 1.141E-08 1. 506E-08 3 .140E-08 3 .087E-08 3 .258E-08 2.710E-08 2.560E-08 2.180E-08 1 .797E-08 5-10 6.759E+01 6.846E+01 6. 826E+01 6.416E+01 5. 849E+01 6.654E+01 6. 692E+01 6.773E+01 6. 859E+01 6 .371E+01 6.558E+01 7.032E+01 7 .278E+01 7. 115E+01 7. 139E+01 7 .055E+01 6.409E-09 4 622E-09 4 568E-09 4. 048E-09 4. 801E-09 5 .286E-09 5 369E-09 4. 879E-09 6 .431E-09 1. 277E-08 1 .246E-08 1 .383E-08 1. 222E-08 1 .205E-08 9. 809E-09 7. 839E-09 10-20 6 .759E+01 6. 846E+01 6. 826E+01 6 .416E+01 5 .849E+01 6. 654E+01 6 692E+01 6 .773E+01 6. 859E+01 6 .371E+01 6 .558E+01 7. 032E+01 7 .278E+01 7 .115E+01 7 .139E+01 7 .055E+01 20-30 3. 517E-09 2. 412E-09 2. 330E-09 2 .082E-09 2. 452E-09 2 .769E-09 2. 897E-09 2 .672E-09 3. 514E-09 6. 783E-09 6. 566E-09 7. 519E-09 6.941E-09 7. 063E-09 5. 551E-09 4. 355E-09 20-30 6. 759E+01 6 .846E+01 6. 826E+01 6. 416E+01 5. 849E+01 6.654E+01 6.692E+01 6. 773E+01 6. 859E+01 6.371E+01 6. 558E+01 7.032E+01 7 .278E+01 7. 115E+01 7. 139E+01 7. 055E+01 30-40 2. 363E-09 1. 572E-09 1. 497E-09 1. 345E-09 1. 583E-09 1. 814E-09 1. 933E-09 1. 792E-09 2 352E-09 4. 477E-09 4. 312E-09 5. 021E-09 4. 753E-09 4. 930E-09 3. 792E-09 2.947E-09 30-40 6. 759E+01 6. 846E+01 6. 826E+01 6. 416E+01 5. 849E+01 6. 654E+01 6. 692E+01 6. 773E+01 6. 859E+01 6. 371E+01 6. 558E+01 7. 032E+01 7. 278E+01 7 115E+01 7. 139E+01 7. 055E+01 40-50 1. 755E-09 1. 142E-09 1. 077E-09 9.712E-10 1. 144E-09 1. 324E-09 1.430E-09 1. 329E-09 1.741E-09 3. 284E-09 3. 152E-09 3. 711E-09 3. 574E-09 3. 758E-09 2. 847E-09 2. 200E-09 40-50 6. 759E+01 6. 846E+01 6. 826E+01 6. 416E+01 5. 849E+01 6. 654E+01 6. 692E+01 6. 773E+01 6. 859E+01 6. 371E+01 6. 558E+01 7. 032E+01 7. 278E+01 7. 115E+01 7. 139E+01 7. 055E+01 DIRECTION

.5-1 FROM SITE S SSW SW.WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 6. 758E+01 6. 846E+01 6. 826E+01 6. 416E+01 5. 848E+01 6. 654E+01 6. 692E+01 6. 773E+01 6. 859E+01 6. 371E+01 6. 558E+01 7. 032E+01 7. 277E+01 7. 115E+01 7. 139E+01 7. 055E+01 1-2 6 759E+01 6 846E+01 6 826E+01 6 416E+01 5 849E+01 6 654E+01 6. 692E+01 6. 773E+01 6. 859E+01 6. 371E+01 6. 558E+01 7. 032E+01 7. 278E+01 7. 115E+01 7. 139E+01 7. 055E+01 2-3 6.759E+01 6. 846E+01 6. 826E+01 6.416E+01 5. 849E+01 6. 654E+01 6. 692E+01 6. 773E+01 6. 859E+01 6. 371E+01 6. 558E+01 7. 032E+01 7. 278E+01 7. 115E+01 7. 139E+01 7. 055E+01 3-4 6 .759E+01 6. 846E+01 6. 826E+01 6. 416E+01 5. 849E+01 6. 654E+01 6. 692E+01 6. 773E+01 6. 859E+01 6 .371E+01 6. 558E+01 7. 032E+01 7.278E+01 7. 115E+01 7. 139E+01 7. 055E+01 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 Fermi 2 2007 Data Reactor Bldg 2.260 DAY DECAY, UNDEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 0.250 0.500 0.750 RUN DATE: 2-25-2008 9:25 DISTANCE IN MILES FROM THE SITE 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 3.112E-06 1. 949E-06 2 .054E-06 2 .474E-06 4. 061E-06 3 .603E-06 4 .239E-06 2 921E-06 2. 852E-06 8 334E-06 6. 125E-06 4 329E-06 3. 046E-06 3 .225E-06 3 077E-06 2 .728E-06 1. 054E-06 6. 652E-07 7. 464E-07 8. 543E-07 1. 360E-06 1. 136E-06 1 .242E-06 8 622E-07 9 .263E-07 2 .775E-06 2 174E-06 1. 528E-06 1. 075E-06 1. 056E-06 1 01OE-06 8. 889E-07 6 105E-07 4 071E-07 4 780E-07 5 048E-07 7 686E-07 6 439E-07 6 491E-07 4 619E-07 5 .427E-07 1 601E-06 1 .334E-06 9 .728E-07 6 .791E-07 6 .217E-07 5. 936E-07 5 .347E-07 3. 417E-07 2. 447E-07 2. 875E-07 2. 842E-07 4. 155E-07 3. 599E-07 3. 467E-07 2. 541E-07 3. 137E-07 8. 822E-07 7 .743E-07 6. 009E-07 4. 223E-07 3 .725E-07 3 538E-07 3 225E-07 1. 663E-07 1. 289E-07 1. 470E-07 1. 357E-07 1. 876E-07 1. 730E-07 1. 636E-07 1. 247E-07 1. 593E-07 4. 103E-07 3. 814E-07 3. 267E-07 2 363E-07 2. 058E-07 1. 922E-07 1.739E-07 1. 034E-07 8. 232E-08 9. 152E-08 8. 203E-08 1. 095E-07 1. 048E-07 9. 880E-08 7. 768E-08 1. 007E-07 2 .454E-07 2 345E-07 2. 129E-07 1. 581E-07 1. 385E-07 1. 272E-07 1. 134E-07 7 .228E-08 5. 801E-08 6. 329E-08 5. 597E-08 7. 296E-08 7. 151E-08 6. 753E-08 5. 440E-08 7. 106E-08 1. 668E-07 1. 616E-07 1. 523E-07 1. 155E-07 1. 021E-07 9. 257E-08 8. 140E-08 5. 426E-08 4. 355E-08 4. 683E-08 4. 114E-08 5 273E-08 5 260E-08 4. 983E-08 4. 091E-08 5 366E-08 1 .227E-07 1. 197E-07 1. 158E-07 8. 926E-08 7.970E-08 7. 148E-08 6.211E-08 4 .274E-08 3.418E-08 3.635E-08 3. 183E-08 4. 028E-08 4. 073E-08 3.873E-08 3.229E-08 4 .245E-08 9.508E-08 9.317E-08 9. 191E-08 7 .180E-08 6. 470E-08 5. 751E-08 4.948E-08 3.485E-08 2 .774E-08 2 .923E-08 2 .555E-08 3 .204E-08 3 .274E-08 3.126E-08 2.638E-08 3.474E-08 7.657E-08 7 .519E-08 7 .531E-08 5.951E-08 5 .409E-08 4 *770E-08 4.070E-08 2 918E-08 2 311E-08 2 .416E-08 2 .lOE-08 2 627E-08 2. 709E-08 2. 596E-08 2 .213E-08 2 917E-08 6 347E-08 6 239E-08 6 326E-08 5. 048E-08 4 624E-08 4 ..050E-08 3.432E-08 ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 5.000 7.500 10.000 DISTANCE IN MILES FROM THE SITI 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 2 .496E-08 1 965E-08 2. 040E-08 1 .782E-08 2 .206E-08 2 .292E-08 2 .205E-08 1. 895E-08 2 5OOE-08 5 .381E-08 5 .292E-08 5 .420E-08 4 .364E-08 4. 026E-08 3 504E-08 2 951E-08 1. 431E-08 1. 097E-08 1. 11OE-08 9. 716E-09 1. 186E-08 1 264E-08 1 238E-08 1. 093E-08 1. 442E-08 2. 996E-08 2 941E-08 3. 116E-08 2. 593E-08 2. 460E-08 2 086E-08 1. 722E-08 9. 877E-09 7 .411E-09 7 .371E-09 6 .465E-09 7 .869E-09 8 .515E-09 8 .453E-09 7 .566E-09 9 .979E-09 2 .033E-08 1 987E-08 2 .149E-08 1. 830E-08 1 .770E-08 1 .472E-08 1 .201E-08 6. 089E-09 4 425E-09 4 292E-09 3 .776E-09 4 614E-09 5. 093E-09 5. 152E-09 4. 676E-09 6. 159E-09 1. 227E-08 1. 191E-08 1. 320E-08 1. 158E-08 1. 151E-08 9 304E-09 7. 494E-09 4. 289E-09 3 048E-09 2 903E-09 2 558E-09 3 151E-09 3 525E-09 3 611E-09 3 298E-09 4. 338E-09 8. 542E-09 8. 238E-09 9. 258E-09 8. 286E-09 8. 395E-09 6. 648E-09 5. 318E-09 3 .253E-09 2 .274E-09 2. 133E-09 1.881E-09 2.340E-09 2. 644E-09 2 .733E-09 2. 504E-09 3 .288E-09 6. 428E-09 6. 167E-09 6. 995E-09 6. 346E-09 6. 529E-09 5. 088E-09 4. 056E-09 2. 587E-09 1 .786E-09 1. 653E-09 1. 458E-09 1.833E-09 2. 087E-09 2. 172E-09 1. 993E-09 2 613E-09 5. 085E-09 4. 854E-09 5. 544E-09 5. 080E-09 5 .293E-09 4. 072E-09 3 .239E-09 2 126E-09 1. 453E-09 1. 329E-09 1. 172E-09 1. 490E-09 1. 706E-09 1. 787E-09 1. 639E-09 2. 146E-09 4. 164E-09 3 957E-09 4. 542E-09 4. 194E-09 4. 418E-09 3 362E-09 2. 672E-09 1 .790E-09 1 .213E-09 1. 098E-09 9.685E-10 1 .244E-09 1 .432E-09 1. 506E-09 1 .381E-09 1. 806E-09 3.497E-09 3.310E-09 3 .813E-09 3.543E-09 3.767E-09 2 .840E-09 2 .256E-09 1.536E-09 1.033E-09 9 .269E-10 8. 169E-10 1.060E-09 1 .226E-09 1 .294E-09 1. 186E-09 1 .549E-09 2. 995E-09 2 .823E-09 3.263E-09 3.046E-09 3 .267E-09 2 .443E-09 1.940E-09 1. 337E-09 8. 945E-10 7. 952E-10 7. 006E-10 9. 183E-10 1. 066E-09 1. 129E-09 1. 034E-09 1.348E-09 2. 605E-09 2 .446E-09 2. 833E-09 2. 656E-09 2. 870E-09 2. 131E-09 1. 693E-09 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS)DIAMETER (METERS)EXIT VELOCITY (METERS)51.20 2.19 11.80 REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)(METERS)(SQ.METERS)(CAL/SEC)51.2 47.5 2300.0 0.0 AT THE RELEASE HEIGHT: VENT RELEASE MODE WIND SPEED (METERS/SEC)

AT THE MEASURED WIND HEIGHT ( 10.0 METERS): VENT RELEASE MODE WIND SPEED (METERS/SEC)

STABLE CONDITIONS ELEVATED LESS THAN 1.043 MIXED BETWEEN 1.043 AND 5 GROUND LEVEL ABOVE 5.215 ELEVATED MIXED GROUND LEVEL LESS THAN BETWEEN ABOVE 2.360 2.360 AND 11.800 11.800 WIND SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS THAN 1.569 BETWEEN 1.569 AND 7.844 ABOVE 7.844.215 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data Reactor Bldg 2.260 DAY DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT DIRECTION

.5-1 FROM SITE S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 5. 896E-07 3.923E-07 4.53 0E-07 4. 844E-07 7.43 1E-07 6. 269E-07 6. 464E-07 4. 585E-07 5. 261E-07 1.542E-06 1.272E-06 9. 309E-07 6.530E-07 6. 075E-07 5. 796E-07 5. 191E-07 1-2 1.773E-07 1. 339E-07 1. 536E-07 1. 448E-07 2. 036E-07 1. 842E-07 1. 755E-07 1. 326E-07 1. 676E-07 4. 419E-07 4. 034E-07 3. 370E-07 2 .429E-07 2. 129E-07 1. 992E-07 1. 800E-07 2-3 7. 336E-08 5. 871E-08 6. 423E-08 5. 699E-08 7. 462E-08 7. 281E-08 6. 879E-08 5. 521E-08 7. 200E-08 1. 701E-07 1. 643E-07 1. 539E-07 1. 164E-07 1. 029E-07 9. 337E-08 8. 222E-08 SEGMENT BOUNDARIES IN MILES FROM THE SITE 3-4 4-5 5-10 10-20 4.303E-08 3.440E-08 3.663E-08 3.210E-08 4. 070E-08 4.108E-08 3. 905E-08 3.250E-08 4 .271E-08 9..591E-08 9.391E-08 9.241E-08 7.211E-08 6.494E-08 5 .777E-08 4. 975E-08 2 930E-08 2 320E-08 2 .427E-08 2. 121E-08 2 .642E-08 2 .722E-08 2 .608E-08 2 .221E-08 2. 928E-08 6 377E-08 6 .268E-08 6 347E-08 5. 062E-08 4. 635E-08 4. 061E-08 3 .443E-08 1. 470E-08 1.132E-08 1.151E-08 1. 007E-08 1 .235E-08 1 .309E-08 1. 278E-08 1.122E-08 1. 480E-08 3 .098E-08 3. 040E-08 3.199E-08 2 .648E-08 2.502E-08 2 .128E-08 1 .763E-08 6.131E-09 4 .477E-09 4 359E-09 3 .833E-09 4. 687E-09 5. 157E-09 5 .201E-09 4 .706E-09 6. 198E-09 1 .241E-08 1 .205E-08 1 329E-08 1. 161E-08 1. 150E-08 9 .327E-09 7 .530E-09 20730 3. 263E-09 2.285E709 2.147E-09 1.893E-09 2.354E-09 2.656E-09 2.743E-09 2.511E-09 3.298E-09 6.454E-09 6.194E-09 7. 018E-09 6. 357E-09 6.532E-09 5. 098E-09 4. 066E-09 30-40 2. 130E-09 1. 457E-09 1. 334E-09 1. 176E-09 1. 494E-09 1. 710E-09 1. 790E-09 1. 642E-09 2. 150E-09 4. 173E-09 3 967E-09 4. 551E-09 4. 199E-09 4. 420E-09 3 366E-09 2. 675E-09 40-50 1. 538E-09 1. 035E-09 9. 290E-10 8. 188E-10 1. 062E-09 1. 228E-09 1. 296E-09 1. 188E-09 1. 551E-09 2. 999E-09 2. 828E-09 3. 267E-09 3. 049E-09 3. 268E-09 2. 445E-09 1. 942E-09 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 Fermi 2 2007 Data Reactor Bldg 8.000 DAY DECAY, DEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 0.250 0.500 0.750 RUN DATE: 2-25-2008 9:25 DISTANCE IN MILES FROM THE SITE 1.000 1.500 2.000 2.500 -3.000 3.500 4.000 4.500 S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 2 917E-06 1 832E-06 1 930E-06 2 328E-06 3 808E-06 3 .403E-06 4. 015E-06 2 .768E-06 2 .690E-06 7 .804E-06 5. 744E-06 4. 069E-06 2 .867E-06 3. 039E-06 2 .911E-06 2. 570E-06 9. 696E-07 6. 129E-07 6. 895E-07 7. 885E-07 1 .249E-06 1. 050E-06 1. 150E-06 7. 994E-07 8. 561E-07 2 .545E-06 2. 003E-06 1. 412E-06 9. 971E-07 9 .782E-07 9 379E-07 8 .214E-07 5. 553E-07 3 .724E-07 4 .401E-07 4 616E-07 6 961E-07 5. 886E-07 5 916E-07 4 .216E-07 4 967E-07 1. 450E-06 1 .222E-06 8 963E-07 6 .277E-07 5 .715E-07 5 .462E-07 4 911E-07 3. 094E-07 2. 244E-07 2. 650E-07 2. 589E-07 3 .733E-07 3 274E-07 3 .13 6E-07 2 306E-07 2. 866E-07 7 937E-07 7. 083E-07 5 556E-07 3. 918E-07 3 431E-07 3. 260E-07 2 970E-07 1. 501E-07 1. 186E-07 1. 354E-07 1. 23 OE-07 1. 668E-07 1. 565E-07 1. 468E-07 1. 12 8E-07 1. 455E-07 3 661E-07 3. 481E-07 3. 033E-07 2. 205E-07 1. 907E-07 1. 779E-07 1. 607E-07 9. 314E-08 7 577E-08 8 406E-08 7 402E-08 9. 647E-08 9. 424E-08 8. 797E-08 7 005E-08 9. 187E-08 2 175E-07 2 132E-07 1 978E-07 1. 478E-07 1 287E-07 1 180E-07 1 048E-07 6. 499E-08 5. 329E-08 5. 791E-08 5. 029E-08 6. 374E-08 6 395E-08 5. 972E-08 4. 892E-08 6. 471E-08 1. 470E-07 1. 464E-07 1. 414E-07 1. 080E-07 9. 504E-08 8. 599E-08 7. 513E-08 4. 867E-08 3 990E-08 4. 269E-08 3 683E-08 4. 572E-08 4. 679E-08 4. 379E-08 3. 669E-08 4. 878E-08 1. 075E-07 1. 080E-07 1. 073E-07 8. 346E-08 7. 422E-08 6. 641E-08 5. 723E-08 3 825E-08 3. 123E-08 3 301E-08 2. 839E-08 3 469E-08 3 .605E-08 3 384E-08 2 888E-08 3 853E-08 8 .291E-08 8 379E-08 8. 501E-08 6 .710E-08 6. 027E-08 5 343E-08 4. 551E-08 3 .113E-08 2 .528E-08 2 .645E-08 2 .272E-08 2 .742E-08 2.885E-08 2.718E-08 2 .354E-08 3.148E-08 6 .648E-08 6 .741E-08 6 .955E-08 5.558E-08 5 .039E-08 4. 431E-08 3.737E-08 2.601E-08 2 .100E-08 2. 179E-08 1. 870E-08 2.235E-08 2.376E-08 2.246E-08 1. 970E-08 2 .639E-08 5. 488E-08 5. 576E-08 5. 833E-08 4. 713E-08 4. 309E-08 3. 761E-08 3 .145E-08 ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 5.000 7.500 10.000 DISTANCE IN MILES FROM THE SITI 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 2 220E-08 1 781E-08 1. 835E-08 1. 575E-08 1. 866E-08 2 .002E-08 1. 899E-08 1. 684E-08 2 .259E-08 4. 635E-08 4 .717E-08 4. 992E-08 4. 073E-08 3 .753E-08 3 .253E-08 2 .701E-08 1 .265E-08 9. 847E-09 9. 877E-09 8. 503E-09 9. 826E-09 1. 087E-08 1. 048E-08 9. 638E-09 1 .297E-08 2. 546E-08 2. 596E-08 2. 858E-08 2 .421E-08 2 .298E-08 1. 939E-08 1. 569E-08 8 693E-09 6 601E-09 6 .503E-09 5 614E-09 6 .398E-09 7 .224E-09 7 052E-09 6 627E-09 8 945E-09 1 709E-08 1 .742E-08 1. 966E-08 1 710E-08 1. 657E-08 1 370E-08 1. 091E-08 5 334E-09 3. 901E-09 3. 749E-09 3. 247E-09 3. 648E-09 4. 233E-09 4. 204E-09 4. 057E-09 5. 500E-09 1. 016E-08 1. 034E-08 1 206E-08 1. 088E-08 1. 085E-08 8 694E-09 6. 800E-09 3. 752E-09 2 671E-09 2 521E-09 2. 187E-09 2. 439E-09 2. 886E-09 2. 899E-09 2. 844E-09 3 .869E-09 6. 999E-09 7. 122E-09 8. 477E-09 7. 840E-09 7. 968E-09 6. 248E-09 4. 834E-09 2 847E-09 1 986E-09 1. 847E-09 1. 603E-09 1 .781E-09 2 .139E-09 2. 167E-09 2. 150E-09 2 934E-09 5. 230E-09 5. 320E-09 6. 428E-09 6. 054E-09 6. 247E-09 4. 815E-09 3. 698E-09 2. 267E-09 1. 556E-09 1. 429E-09 1. 241E-09 1. 375E-09 1. 672E-09 1. 706E-09 1. 707E-09 2 335E-09 4. 115E-09 4. 186E-09 5. 118E-09 4. 888E-09 5. 108E-09 3. 881E-09 2. 966E-09 1. 867E-09 1. 264E-09 1. 148E-09 9 951E-10 1. 103E-09 1. 353E-09 1. 387E-09 1. 399E-09 1. 921E-09 3 355E-09 3. 412E-09 4. 213E-09 4. 070E-09 4. 299E-09 3. 227E-09 2. 457E-09 1 570E-09 1 051E-09 9 .458E-10 8. 192E-10 9. 071E-10 1. 123E-09 1. 155E-09 1. 172E-09 1. 613E-09 2 .798E-09 2 846E-09 3 .542E-09 3 .454E-09 3 680E-09 2 .734E-09 2 076E-09 1 .347E-09 8.937E-10 7.968E-10 6.891E-10 7.630E-10 9.511E-10 9.821E-10 1 .002E-09 1 .382E-09 2 .384E-09 2.425E-09 3.038E-09 2 .987E-09 3 .206E-09 2 .361E-09 1 .789E-09 1. 172E-09 7. 706E-10 6. 817E-10 5. 889E-10 6. 523E-10 8. 183E-10 8. 473E-10 8. 682E-10 1. 201E-09 2. 061E-09 2 096E-09 2 641E-09 2 .615E-09 2 .827E-09 2. 065E-09 1. 562E-09 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS)DIAMETER (METERS)EXIT VELOCITY (METERS)51.20 2.19 11.80 REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)(METERS)(SQ.METERS)(CAL/SEC)51.2 47.5 2300.0 0.0 AT THE RELEASE HEIGHT: VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ AT THE MEASURED WIND HEIGHT ( 10.0 METERS):/ VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ STABLE CONDITIONS

/ ELEVATED LESS THAN 1.043/ MIXED BETWEEN 1.043 AND 5/ GROUND LEVEL ABOVE 5.215 ELEVATED MIXED GROUND LEVEL LESS THAN BETWEEN ABOVE 2.360 2.360 AND 11.800 11.800 WIND SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS THAN 1.569 BETWEEN 1.569 AND 7.844 ABOVE 7.844.215 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data Reactor Bldg 8.000 DAY DECAY, DEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT DIRECTION

.5-1 FROM SITE S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 5. 381E-07 3.601E-07 4. 177E-07 4. 441E-07 6. 754E-07 5. 751E-07 5. 921E-07 4. 207E-07 4. 832E-07 1.402E-06 1.167E-06 8. 595E-07 6. 050E-07 5..604E-07

5. 354E-07 4. 782E-07 1-2 1. 602E-07 1. 231E-07 1. 414E-07 1. 314E-07 1. 814E-07 1. 668E-07 1. 577E-07 1. 200E-07 1. 530E-07 3 951E-07 3 .682E-07 3. 125E-07 2. 262E-07 1. 970E-07 1. 842E-07 1. 661E-07 2-3 6. 597E-08 5. 393E-08 5. 879E-08 5. 124E-08 6. 526E-08 6. 516E-08 6. 088E-08 4. 966E-08 6. 558E-08 1.500E-07 1.489E-07 1. 428E-07 1. 088E-07 9. 569E-08 8. 671E-08 7. 588E-08 SEGMENT BOUNDARIES IN MILES FROM THE SITE 3-4 4-5 5-10 10-20 3. 851E-08 3. 144E-08 3.328E-08 2 .864E-08 3.507E-08 3.638E-08 3.415E-08 2.908E-08 3.877E-08 8. 367E-08 8. 448E-08 8. 549E-08 6. 738E-08 6.049E-08 5.366E-08 4. 576E-08 2 .612E-08 2 .109E-08 2. 190E-08 1. 880E-08 2 .248E-08 2.388E-08 2 .257E-08 1.978E-08 2 .649E-08 5.516E-08 5.603E-08 5. 854E-08 4 .726E-08 4.319E-08 3.771E-08 3. 156E-08 1.301E-08 1. 017E-08 1. 026E-08 8. 829E-09 1. 027E-08 1. 128E-08 1. 085E-08 9. 901E-09 1 .332E-08 2 .638E-08 2 .688E-08 2. 936E-08 2 .472E-08 2 .337E-08 1.978E-08 1. 608E-08 5 .377E-09 3 .955E-09 3 .815E-09 3 .302E-09 3 .722E-09 4 .299E-09 4 .257E-09 4.089E-09 5 .540E-09 1.030E-08 1.048E-08 1 .216E-08 1.091E-08 1. 084E-08 8. 719E-09 6. 840E-09 20-30 2. 856E-09 1. 997E-09 1.860E-09 1. 614E-09 1. 794E-09 2.151E-09 2. 178E-09 2. 158E-09 2.944E-09 5. 256E-09 5. 347E-09 6. 451E-09 6. 064E-09 6. 251E-09 4. 823E-09 3 .708E-09 30-40 1. 868E-09 1. 267E-09 1. 151E-09 9. 982E-10 1. 106E-09 1. 357E-09 1. 390E-09 1. 401E-09 1. 922E-09 3 360E-09 3 418E-09 4. 216E-09 4. 069E-09 4. 294E-09 3 226E-09 2 457E-09 40-50 1. 348E-09 8. 948E-10 7. 983E-10 6. 905E-10 7. 647E-10 9. 527E-10 9. 834E-10 1. 003E-09 1.383E-09 2.387E-09 2. 428E-09 3. 040E-09 2. 987E-09 3. 206E-09 2.362E-09 1. 790E-09 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data Reactor Bldg CORRECTED USING STANDARD**** **** **** **** ** ** *DIRECTION FROM SITE 0.25 S 3.178E-08 SSW 2.210E-08 SW 2.506E-08 WSW 3.923E-08 W 5.909E-08 WNW 4.814E-08 NW 5.748E-08 NNW 3.905E-08.N 2.945E-08 NNE 8.386E-08 NE 8.177E-08 ENE 4.668E-08 E 3.575E-08 ESE 3.370E-08 SE 3.197E-08 SSE 2.831E-08 OPEN TERRAIN FACTORS RELATIVE DEPOSITION PER UNIT AREA (M**-2) AT FIXED POINTS BY DOWNWIND SECTORS 0.50 1 .339E-08 9. 601E-09 1. 170E-08 1 .685E-08 2 362E-08 2. 165E-08 2. 578E-08 1.765E-08 1 364E-08 3 453E-08 3 572E-08 2 .204E-08 1 .701E-08 1. 577E-08 1. 526E-08 1 314E-08 7.50 4 .727E-11 3 .723E-11 4 904E-11 5. 813E-11 7. 147E-11 7. 206E-11 7 995E-11 5. 564E-11 4 993E-11 1. 147E-10 1 347E-10 9. 509E-11 7 275E-11 6 .264E-11 5 997E-11 5 336E-11 0.75 7 .481E-09 5 .470E-09 6 .988E-09 9 .447E-09 1 .279E-08 1 .191E-08 1 .378E-08 9 .465E-09 7 .764E-09 1 916E-08 2 061E-08 1 .311E-08 1. 001E-08 9. 097E-09 8 .828E-09 7 558E-09 10.00 2 .863E-11 2 .251E-11 2 .935E-11 3 .503E-11 4 326E-11 4 378E-11 4. 899E-11 3. 414E-11 3 .027E-11 6. 916E-11 8. 070E-11 5 .712E-11 4 386E-11 3 .794E-11 3 .650E-11 3 .232E-11 1.00 3. 786E-09 2 .820E-09 3. 685E-09 4. 777E-09 6. 303E-09 5. 935E-09 6. 732E-09 4 632E-09 3 951E-09 9 627E-09 1. 064E-08 6 927E-09 5 .261E-09 4 .701E-09 4. 541E-09 3 920E-09 15.00 1. 490E-11 1 .169E-11 1. 506E-11 1. 814E-11 2 .243E-11 2 .312E-11 2. 628E-11 1. 834E-11 1. 589E-11 3. 571E-11 4 .139E-11 2 950E-11 2.280E-11 1. 988E-11 1. 928E-11 1. 692E-11 DISTANCES IN MILES 1.50 2.00 1.459E-09 7.559E-10 1.110E-09 5.819E-10 1.479E-09 7.757E-10 1.843E-09 9.493E-10 2.363E-09 1.201E-09 2.258E-09 1.160E-09 2.509E-09 1.282E-09 1.728E-09 8.850E-10 1.525E-09 7.898E-10 3.684E-09 1.891E-09 4.195E-09 2.178E-09 2.793E-09 1.474E-09 2.113E-09 1.117E-09 1.848E-09 9.691E-10 1.759E-09 9.200E-10 1.553E-09 8.186E-10 2.50 4. 588E-10 3. 560E-10 4. 731E-10 5. 728E-10 7. 189E-10 7. 001E-10 7. 721E-10 5. 340E-10 4. 791E-10 1. 139E-09 1. 321E-09 9 043E-10 6. 866E-10 5 928E-10 5 622E-10 5 026E-10 30.00 5 .133E-12 4. 026E-12 5 071E-12 6. 103E-12 7. 479E-12 8. 213E-12 9.559E-12 6. 73 8E-12 5 694E-12 1. 205E-11 1. 382E-11 1. 020E-11 8. 016E-12 7. 160E-12 7. 019E-12 5. 993E-12 3.00 3. 076E-10 2 399E-10 3. 182E-10 3. 824E-10 4. 771E-10 4. 677E-10 5. 153E-10 3. 570E-10 3 .212E-10 7. 591E-10 8. 842E-10 6. 105E-10 4. 642E-10 3 997E-10 3. 790E-10 3 397E-10 35.00 4. 122E-12 3 234E-12 4. 026E-12 4. 815E-12 5. 896E-12 6. 588E-12 7. 678E-12 5. 443E-12 4. 616E-12 9. 612E-12 1. 095E-11 8. 223E-12 6. 493E-12 5. 858E-12 5. 717E-12 4. 852E-12 3.50 2 .204E-10 1 .726E-10 2 .285E-10 2.733E-10 3.395E-10 3 .347E-10 3 .687E-10 2.557E-10 2 .304E-10 5. 418E-10 6.331E-10 4 .397E-10 3 .348E-10 2 .877E-10 2.730E-10 2.449E-10 40.00 3.436E-12 2. 698E-12 3.316E-12 3 .939E-12 4 .821E-12 5 .477E-12 6.383E-12 4 .553E-12 3. 879E-12 7. 968E-12 9. 013E-12 6.886E-12 5. 464E-12 4.977E-12 4. 821E-12 4.077E-12 4.00 1. 658E-10 1. 301E-10 1.721E-10 2. 052E-10 2. 540E-10 2. 516E-10 2 .773E-10 1. 924E-10 1. 735E-10 4. 062E-10 4.758E-10 3 318E-10 2. 528E-10 2. 171E-10 2. 062E-10 1. 850E-10 45.00 2 .924E-12 2 .297E-12 2 .789E-12 3 .287E-12 4 .025E-12 4. 632E-12 5 .389E-12 3 .866E-12 3 .319E-12 6 .747E-12 7 .579E-12 5. 884E-12 4. 687E-12 4. 305E-12 4. 138E-12 3.491E-12 4.50 1 .293E-10 1 .015E-10 1. 344E-10 1. 598E-10 1. 974E-10 1. 964E-10 2. 165E-10 1. 503E-10 1. 356E-10 3. 161E-10 3. 708E-10 2. 594E-10 1. 977E-10 1. 698E-10 1. 614E-10 1.447E-10 50.00 2. 546E-12 2. 001E-12 2.397E-12 2.795E-12 3.429E-12 3. 989E-12 4. 621E-12 3.339E-12 2. 901E-12 5. 848E-12 6. 514E-12 5. 147E-12 4. 115E-12 3. 813E-12 3. 630E-12 3. 056E-12 DIRECTION FROM SITE S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 5.00 1. 037E-10 8. 150E-11 1. 079E-10 1 .282E-10 1. 580E-10 1. 577E-10 1.741E-10 1 .209E-10 1. 090E-10 2 .532E-10 2 .973E-10 2. 084E-10 1. 589E-10 1 .365E-10 1 .299E-10 1. 163E-10 DISTANCES 20.00 9. 420E-12 7. 395E-12 9. 472E-12 1. 145E-11 1. 410E-11 1. 484E-11 1. 704E-11 1. 191E-11 1. 017E-11 2 .246E-11 2. 599E-11 1. 866E-11 1. 450E-11 1. 271E-11 1. 236E-11 1. 080E-11 IN MILES 25.00 6.705E-12 5 .260E-12 6. 689E-12 8. 075E-12 9. 919E-12 1. 067E-11 1.235E-11 8. 666E-12 7. 345E-12 1. 585E-11 1. 827E-11 1 .329E-11 1. 039E-11 9. 186E-12 9. 003E-12 7. 755E-12 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data Reactor Bldg****** **** **************

RELATIVE DEPOSITION PER UNIT AREA (M**-2) BY DOWNWIND SECTORS SEGMENT BOUNDARIES IN MILES* ** ** ****** ** ** ** * * ** * * *DIRECTION

.5-1 FROM SITE S SSW SW WSW W WNW NW NN-W N NNE NE ENE E ESE SE SSE 7. 153E-09 5.210E-09 6.568E-09 9.016E-09 1 .231E-08 1. 142E-08 1.332E-08 9. 136E-09 7.374E-09 1. 834E-08 1. 954E-08 1 .234E-08 9 .453E-09 8. 626E-09 8.351E-09 7 .181E-09 1-2 1 664E-09 1 255E-09 1 657E-09 2 098E-09 2 722E-09 2 587E-09 2 .902E-09 1. 999E-09 1. 737E-09 4 .208E-09 4. 732E-09 3 .125E-09 2 .370E-09 2. 091E-09 2. 004E-09 1. 753E-09 2-3 4.776E-10 3.698E-10 4. 918E-10 5.971E-10 7 .507E-10 7 .299E-10 8. 053E-10 5 .568E-10 4. 988E-10 1.188E-09 1 .375E-09 9.388E-10 7 .125E-10 6. 159E-10 5. 843E-10 5 .217E-10 3-4 4-5 2 .245E-10 1 756E-10 2 327E-10 2 .785E-10 3. 463E-10 3. 410E-10 3. 758E-10 2 605E-10 2 347E-10 5. 522E-10 6. 449E-10 4. 474E-10 3. 405E-10 2 928E-10 2. 778E-10 2. 492E-10 1.306E-10 1.026E-10 1.358E-10 1. 615E-10 1. 996E-10 1. 984E-10 2. 188E-10 1. 519E-10 1. 370E-10 3. 195E-10 3.747E-10 2 .619E-10 1. 997E-10 1. 715E-10 1. 630E-10 1.461E-10 5-10 5. 152E-11 4. 053E-11 5. 337E-11 6. 343E-11 7.817E-11 7 .853E-11 8.711E-11 6. 059E-11 5. 432E-11 1.252E-10 1.468E-10 1. 034E-10 7.906E-11 6. 808E-11 6. 508E-11 5. 799E-11 10-20 1. 551E-I1 1. 219E-11 1. 575E-11 1. 892E-11 2 336E-11 2 403E-11 2 722E-11 1. 899E-11 1. 654E-11 3. 725E-11 4. 328E-11 3 082E-11 2 379E-11 2. 070E-11 2. 003E-11 1. 762E-11 20-30 6. 800E-12 5 .336E-12 6.784E-12 8. 186E-12 1.006E-11 1.080E-Il 1.249E-11 8 .760E-12 7 .437E-12 1.609E-11 1.855E-11 1.349E-11 1.054E-11 9.314E-12 9.105E-12 7.861E-12 30-40 4 .150E-12 3 .256E-12 4 054E-12 4. 849E-12 5. 939E-12 6. 629E-12 7 .722E-12 5 .474E-12 4 643E-12 9 .682E-12 1 .103E-11 8 .279E-12 6 .536E-12 5 .894E-12 5 .748E-12 4. 883E-12 40-50 2. 936E-12 2 .306E-12 2 .800E-12 3.298E-12 4. 040E-12 4.645E-12 5 .399E-12 3. 874E-12 3.330E-12 6 .776E-12 7.609E-12 5.908E-12 4. 705E-12 4.322E-12 4. 152E-12 3. 504E-12 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS)DIAMETER (METERS)EXIT VELOCITY (METERS)AT THE RELEASE HEIGHT: VENT RELEASE MODE WIND SPEED 51.20 2.19 11.80 REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)(METERS)(SQ.METERS)(CAL/SEC)51.2 47.5 2300.0 0.0 (METERS/SEC)

/ AT THE MEASURED WIND HEIGHT ( 10.0 METERS):/ VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ STABLE CONDITIONS

/ ELEVATED LESS THAN 1.043/ MIXED BETWEEN 1.043 AND 5.215 WIND SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS THAN 1.569 BETWEEN 1.5.69 AND 7.844 ELEVATED MIXED GROUND LEVEL LESS THAN 2.360 BETWEEN 2.360 AND 11.800 ABOVE 11.800 GROUND LEVEL ABOVE 5.215 ABOVE 7.844 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 Fermi 2 2007 Data Reactor Bldg CORRECTED USING STANDARD OPEN TERRAIN FACTORS SPECIFIC POINTS OF INTEREST RUN DATE: 2-25-2008 9:25 RELEASE TYPE OF ID LOCATION DIRECTION FROM SITE DISTANCE X/Q X/Q X/Q (MILES) (METERS) (SEC/CUB.METER) (SEC/CUB.METER) (SEC/CUB.METER)

A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY Residences Residences Residences Residences Residences Residences Residences Residences Residences Residences Residences NE NNE NE S SSW SW WSW W WNW NW NNW N NE NNE NNW NW WNW W WSW SW SSW S NW WNW N NNE NE NNW NW SSW SW W WNW WSW SSW 1.13 1.02 0.36 0.88 0.96 1.19 1.12 0.86 0.67 0.57 0.62 1.10 1.10 1.02 1.08 1.06 0.69 1.16 1.58 1.26 1.13 1.02 3.65 2.28 1.64 1.80 1.99 2 .55 2.76 1.50 4.39 3 .18 1. 82 3.21 0.29 NO DECAY UNDEPLETED 1825. 6.2E-07 1646. 8.4E-07 579. 3.4E-06 1417. 4.4E-07 1542. 2.6E-07 1920. 2.1E-07 1798. 2.3E-07 1390. 5.6E-07 1082. 7.3E-07 915. 9.8E-07 990. 6.OE-07 1776. 2.6E-07 1773. 6.5E-07 1646. 8.4E-07 1743. 2.2E-07 1700. 3.1E-07 1103. 7.1E-07 1861. 3.1E-07 2547. 1.2E-07 2025. 2.OE-07 1826. 2.OE-07 1640. 3.3E-07 5874. 3.6E-08 3672. 8.4E-08 2633. 1.4E-07 2894. 3.OE-07 3200. 2.4E-07 4107. 5.3E-08 4435. 5.7E-08 2414. 1.3E-07 7062. 2.5E-08 5123. 4.8E-08 2936. 1.2E-07 5173. 3.7E-08 470. 1.5E-06 2.260 DAY DECAY UNDEPLETED

6. 2E-07 8. 4E-07 3. 4E-06 4. 4E-07 2. 6E-07 2. 1E-07 2. 3E-07 5. 6E-07 7. 3E-07 9. 8E-07 6. OE-07 2. 6E-07 6. 5E-07 8. 4E-07 2. 2E-07 3. 1E-07 7. 1E-07 3. 1E-07 1. 2E-07 2. OE-07 2. OE-07 3. 3E-07 3 .6E-08 8. 3E-08 1. 4E-07 3.OE-07 2.4E-07 5.3E-08 5.7E-08 1.3E-07 2.5E-08 4.7E-08 1.2E-07 3. 7E-08 1.5E-06 8.000 DAY DECAY DEPLETED 5.6E-07 7 .6E-07 3.2E-06 4. OE-07 2.4E-07 2.OE-07 2 .1E-07 5. IE-07 6.7E-07 9.OE-07 5.5E-07 2 .4E-07 5.9E-07 7.6E-07 2.OE-07 2.8E-07 6.5E-07 2.8E-07 1. 1E-07 1.8E-07 1.8E-07 3.OE-07 3 .2E-08 7 .5E-08 1.3E-07 2.6E-07 2.2E-07 4.7E-08 5.OE-08 1.2E-07 2 .3E-08 4.1E-08 1.1E-07 3 .3E-08 1.4E-06 D/Q (PER SQ.METER)8.OE-09 9.1E-09 5.4E-08 5.1E-09 3.1E-09 2.5E-09 3.7E-09 9.OE-09 1 .4E-08 2.1E-08 1.3E-08 3.1E-09 8.5E-09 9.1E-09 3.8E-09 5.9E-09 1.4E-08 4.4E-09 1.6E-09 2.2E-09 2.1E-09 3.6E-09 3.4E-10 8.6E-10 1.2E-09 2.4E-09 2.2E-09 5.1E-10 6.2E-10 1.1E-09 1.4E-10 4.2E-10 1.4E-09 3.3E-10 1.9E-08 MILK COW MILK COW VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN A Visitor Center/Ice F

A Visitor Center/Ice F VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS)DIAMETER (METERS)EXIT VELOCITY (METERS)E 0.29 470.2.3E-06 2. 3E-06 2 .2E-06 3. 1E-08 51.20 2.19 11.80 REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)(METERS)(SQ.METERS)(CAL/SEC)51.2 47.5 2300.0 0.0 AT THE RELEASE HEIGHT: VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ AT THE MEASURED WIND HEIGHT ( 10.0 METERS):/ VENT RELEASE MODE WIND SPEED (METERS/SEC)

STABLE CONDITIONS ELEVATED LESS THAN 1.043 MIXED BETWEEN 1.043 AND 5.215 GROUND LEVEL ABOVE 5.215:ELEVATED MIXED GROUND LEVEL LESS THAN BETWEEN ABOVE 2.360 2.360 AND 11.800 11.800 WIND SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS THAN 1.569 BETWEEN 1.569 AND 7.844 ABOVE 7.844 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 Fermi 2 2007 Data Turbine Bldg NO DECAY, UNDEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 0.250 0.500 0.750 RUN DATE: 2-25-2008 9:25 DISTANCE IN MILES FROM THE SITE 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE 7SSE 1. 686E-05 1 .148E-05 1. 120E-05 8 .754E-06 1. 195E-05 1. 568E-05 1. 438E-05 1 .289E-05 1. 667E-05 3 .397E-05 3 .303E-05 3 .260E-05 2 641E-05 2 .876E-05 2 .227E-05 2 043E-05 5. 501E-06 4 032E-06 3. 955E-06 2 989E-06 4 087E-06 5 137E-06 4 455E-06 4 065E-06 5 525E-06 1 136E-05 1. 128E-05 1 120E-05 8 753E-06 9 163E-06 7 291E-06 6. 708E-06 2 .940E-06 2 .217E-06 2 .133E-06 1. 592E-06 2 .191E-06 2 .748E-06 2 .304E-06 2 .180E-06 2 .990E-06 6. 132E-06 6 102E-06 6. 093E-06 4 .730E-06 4. 857E-06 3 .921E-06 3 .605E-06 1 508E-06 1 130E-06 1 075E-06 7 980E-07 1 099E-06 1 384E-06 1 160E-06 1 109E-06 1 527E-06 3. 115E-06 3. 088E-06 3. 118E-06 2. 443E-06 2. 516E-06 2 021E-06 1. 853E-06 6. 267E-07 4. 592E-07 4. 312E-07 3.211E-07 4. 380E-07 5. 562E-07 4. 747E-07 4. 561E-07 6. 269E-07 1. 264E-06 1. 244E-06 1. 282E-06 1. 027E-06 1. 071E-06 8. 497E-07 7 .706E-07 3. 493E-07 2. 512E-07 2 342E-07 1. 755E-07 2 364E-07 3. 018E-07 2 .615E-07 2. 521E-07 3. 464E-07 6. 915E-07 6. 778E-07 7 097E-07 5. 785E-07 6. 085E-07 4. 784E-07 4. 294E-07 2. 266E-07 1. 605E-07 1. 489E-07 1.123E-07 1. 496E-07 1. 916E-07 1. 682E-07 1. 62 6E-07 2 .233E-07 4. 42 4E-07 4. 32 1E-07 4. 580E-07 3. 786E-07 4. O1OE-07 3 131E-07 2 .785E-07 1. 612E-07 1. 127E-07 1. 042E-07 7 900E-08 1. 043E-07 1. 340E-07 1. 189E-07 1. 152E-07 1. 581E-07 3. 113E-07 3. 031E-07 3. 244E-07 2. 713E-07 2. 891E-07 2 244E-07 1. 982E-07 1 .219E-07 8 .429E-08 7 .769E-08 5. 921E-08 7 .757E-08 9. 995E-08 8.949E-08 8. 684E-08 1.192E-07 2 .334E-07 2 .267E-07 2 .446E-07 2 .065E-07 2 .213E-07 1 .708E-07 1 .499E-07 9 .633E-08 6. 597E-08 6. 065E-08 4. 641E-08 6. 045E-08 7 .806E-08 7. 045E-08 6. 846E-08 9. 393E-08 1. 832E-07 1. 774E-07 1. 928E-07 1. 641E-07 1 .767E-07 1 .358E-07 1.186E-07 7..865E-08

5. 341E-08 4.899E-08 3 .763E-08 4. 877E-08 6. 310E-08 5. 736E-08 5. 579E-08 7 653E-08 1. 487E-07 1. 437E-07 1. 571E-07 1. 347E-07 1. 457E-07 1.115E-07 9. 687E-08 ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 5.000 7.500 10.000 DISTANCE IN MILES FROM THE SITI 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 6 587E-08 4 440E-08 4 064E-08 3 .131E-08 4. 042E-08 5 .239E-08 4 .793E-08 4. 666E-08 6 398E-08 1.239E-07 1. 195E-07 1 313E-07 1. 134E-07 1 .230E-07 9 379E-08 8. 120E-08 3. 536E-08 2 .316E-08 2. 101E-08 1. 637E-08 2. 088E-08 2. 725E-08 2. 554E-08 2. 492E-08 3. 411E-08 6. 527E-08 6 253E-08 6 999E-08 6 .201E-08 6. 824E-08 5. 123E-08 4 372E-08 2 .359E-08 1. 514E-08 1 .364E-08 1. 071E-08 1 358E-08 1 .781E-08 1. 697E-08 1. 657E-08 2 .265E-08 4 .301E-08 4. 11E-08 4. 648E-08 4 .193E-08 4 657E-08 3 .458E-08 2 .924E-08 1 407E-08 8 774E-09 7. 829E-09 6. 202E-09 7. 822E-09 1. 034E-08 1. 008E-08 9. 838E-09 1. 341E-08 2. 523E-08 2. 390E-08 2. 753E-08 2 .547E-08 2. 863E-08 2. 092E-08 1. 749E-08 9. 774E-09 5. 975E-09 5. 296E-09 4. 220E-09 5. 310E-09 7 057E-09 6. 986E-09 6. 816E-09 9 .276E-09 1. 734E-08 1. 636E-08 1. 904E-08 1. 791E-08 2. 030E-08 1. 467E-08 1. 218E-08 7. 378E-09 4. 442E-09 3. 916E-09 3. 133E-09 3. 940E-09 5. 260E-09 5 267E-09 5 134E-09 6. 976E-09 1. 298E-08 1. 221E-08 1. 432E-08 1 .364E-08 1. 556E-08 1.115E-08 9 .209E-09 5. 868E-09 3. 490E-09 3. 063E-09 2. 458E-09 3. 091E-09 4. 143E-09 4. 186E-09 4. 077E-09 5. 532E-09 1. 026E-08 9. 627E-09 1. 136E-08 1. 092E-08 1. 252E-08 8. 913E-09 7 334E-09 4. 837E-09 2. 848E-09 2. 490E-09 2. 003E-09 2. 520E-09 3 389E-09 3. 450E-09 3. 357E-09 4. 549E-09 8. 415E-09 7. 879E-09 9. 338E-09 9. 056E-09 1.043E-08 7.379E-09 6. 054E-09 4 .094E-09 2 .390E-09 2. 082E-09 1. 679E-09 2 .113E-09 2 .849E-09 2 .920E-09 2 .838E-09 3 .842E-09 7 .091E-0,9 6.628E-09 7 .885E-09 7.699E-09 8. 898E-09 6.267E-09 5. 129E-09 3.534E-09 2 .048E-09 1. 779E-09 1. 437E-09 1. 809E-09 2 .446E-09 2 .522E-09 2 .449E-09 3 .311E-09 6. 099E-09 5.692E-09 6 .795E-09 6.673E-09 7 .739E-09 5 .427E-09 4.433E-09 3 I00E-09 1. 784E-09 1. 546E-09 1. 250E-09 1. 576E-09 2 .135E-09 2 212E-09 2. 146E-09 2 899E-09 5. 332E-09 4. 969E-09 5 949E-09 5. 873E-09 6. 831E-09 4 .773E-09 3. 891E-09 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) 40.10 DIAMETER (METERS) 7.46 EXIT VELOCITY (METERS) 3.31 AT THE RELEASE HEIGHT: VENT RELEASE MODE WIND SPEED (METERS/SEC)

REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)(METERS)(SQ.METERS)(CAL/SEC)40.1 40.1 5130.0 0.0/ AT THE MEASURED WIND HEIGHT ( 10.0 METERS):/ VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ STABLE CONDITIONS

/ ELEVATED LESS THAN 0.331/ MIXED BETWEEN 0.331 AND 1.653/ GROUND LEVEL ABOVE 1.653 ELEVATED MIXED GROUND LEVEL LESS THAN BETWEEN ABOVE 0.662 0.662 AND 3.310 3.310 WIND SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS THAN 0.468 BETWEEN 0.468 AND 2.339 ABOVE 2.339 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data Turbine Bldg NO DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION

.5-1 FROM SITE S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 2. 873E-06 2 .137E-06 2 .068E-06 1. 549E-06 2 .127E-06 2. 673E-06 2. 274E-06 2. 123E-06 2. 903E-06 5. 953E-06 5. 913E-06 5. 905E-06 4. 607E-06 4. 774E-06 3.826E-06 3.516E-06 1-2 6. 993E-07 5 158E-07 4 867E-07 3 624E-07 4 953E-07 6. 271E-07 5. 322E-07 5. 105E-07 7. 021E-07 1. 421E-06 1. 402E-06 1. 436E-06 1. 142E-06 1. 187E-06 9. 451E-07 8. 595E-07 2-3 2 332E-07 1. 656E-07 1. 538E-07 1. 158E-07 1. 546E-07 1. 980E-07 1. 733E-07 1. 675E-07 2 .300E-07 4. 564E-07 4. 460E-07 4. 717E-07 3. 890E-07 4. 116E-07 3. 217E-07 2. 866E-07 3-4 4-5 '1.234E-07 8.543E-08 7. 876E-08 5.999E-08 7. 868E-08 1. 013E-07 9 .063E-08 8 .794E-08 1 .207E-07 2 .365E-07 2 .297E-07 2 .477E-07 2. 089E-07 2 .237E-07 1 .728E-07 1.518E-07 AVERAGE EFFECTIVE STACK HEIGHT IN METERS FOR EACH SEGMENT 7.915E-08 5.380E-08 4. 935E-08 3 .789E-08 4. 914E-08 6 .357E-08 5 .774E-08 5 616E-08 7 .704E-08 1 .497E-07 1 .447E-07 1 .581E-07 1 .355E-07 1 .465E-07 1. 121E-07 9 .749E-08 4-5 2. 188E+01 2 .292E+01 1 .314E+01 7. 908E+00 6. 597E+00 8. 523E+00 9. 193E+00 1. 470E+01 1. 979E+01 1. 102E+01 1. 463E+01 2. 573E+01 3. 179E+01 3 .401E+01 3 337E+01 2 .778E+01 3.691E-08 2 .432E-08 2 .210E-08 1.718E-08 2 .198E-08 2 .864E-08 2. 671E-08 2. 604E-08 3.565E-08 6. 840E-08 6.563E-08 7.317E-08 6.450E-08 7 .079E-08 5 .329E-08 4. 561E-08 5-10 2 .188E+01 2.292E+01 1. 314E+01 7. 908E+00 6. 597E+00 8. 523E+00 9. 193E+00 1. 470E+01 1. 979E+01 1.102E+01 1. 463E+01 2 .573E+01 3 .179E+01 3 .401E+01 3 .337E+01 2.778E+01 5-10 10-20 1.428E-08 8.945E-09 7 995E-09 6 .323E-09 7 985E-09'1. 054E-08 1. 024E-08 9. 991E-09 1 .363E-08 2 .568E-08 2 .435E-08 2 .797E-08 2 .577E-08 2 .891E-08 2 .118E-08 1 .774E-08 10-20 2 .188E+01 2 .292E+01 1. 314E+01 7 908E+00 6 .597E+00 8. 523E+00 9. 193E+00 1. 470E+01 1. 979E+01 1. 102E+01 1. 463E+01 2 .573E+01 3. 179E+01 3. 401E+01 3 337E+01 2 .778E+01 20-30 7. 413E-09 4. 470E-09 3. 943E-09 3. 153E-09 3. 966E-09 5. 292E-09 5. 293E-09 5. 160E-09 7. 011E-09 1. 306E-08 1. 228E-08 1. 439E-08 1.369E-08 1. 561E-08 1. 119E-08 9. 251E-09 20-30 2. 188E+01 2. 292E+01 1. 314E+01 7. 908E+00 6. 597E+00 8. 523E+00 9. 193E+00 1. 470E+01 1. 979E+01 1. 102E+01 1. 463E+01 2 .573E+01 3. 179E+01 3. 401E+01 3 .337E+01 2. 778E+01 30-40 4. 848E-09 2. 857E-09 2. 498E-09 2. 010E-09 2. 528E-09 3.399E-09 3. 459E-09 3.365E-09 4. 560E-09 8. 438E-09 7. 902E-09 9. 361E-09 9. 073E-09 1. 044E-08 7. 394E-09 6. 067E-09 30-40 2. 188E+01 2.292E+01 1. 314E+01 7. 908E+00 6. 597E+00 8. 523E+00 9. 193E+00 1. 470E+01 1. 979E+01 1. 102E+01 1. 463E+01 2. 573E+01 3. 179E+01 3. 401E+01 3. 337E+01 2 .778E+01 40-50 3.539E-09 2.052E-09 1.782E-09 1.43 9E-09 1.813E-09 2. 450E-09 2 .525E-09 2. 452E-09 3.316E-09 6. 109E-09 5. 702E-09 6. 805E-09 6. 681E-09 7. 746E-09 5. 434E-09 4. 439E-09 40-50 2. 188E+01 2.292E+01 1. 314E+01 7.908E+00 6. 597E+00 8. 523E+00 9. 193E+00 1.470E+01 1. 979E+01 1. 102E+01 1. 463E+01 2.573E+01 3. 179E+01 3. 401E+01 3.337E+01 2. 778E+01 DIRECTION

.5-1 FROM SITE S SSW* SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 2. 187E+01 2.292E+01 1.314E+01 7. 908E+00 6. 589E+00 8. 523E+00 9. 193E+00 1. 470E+01 1. 979E+01 1. 102E+01 1. 463E+01 2. 573E+01 3. 177E+01 3. 401E+01 3.337E+01 2. 778E+01 1-2 2. 188E+01 2 292E+01 1. 314E+01 7 908E+00 6. 597E+00 8. 523E+00 9. 193E+00 1. 470E+01 1. 979E+01 1. 102E+01 1. 463E+01 2. 573E+01 3. 179E+01 3. 401E+01 3. 337E+01 2. 778E+01 2-3 2. 188E+01 2. 292E+01 1. 314E+01 7 908E+00 6. 597E+00 8. 523E+00 9. 193E+00 1. 470E+01 1. 979E+01 1. 102E+01 1. 463E+01 2. 573E+01 3. 179E+01 3. 401E+01 3 337E+01 2. 778E+01 3-4 2 .188E+01 2.292E+01 1 .314E+01 7. 908E+00 6. 597E+00 8. 523E+00 9. 193E+00 1. 470E+01 1. 979E+01 1. 102E+01 1.463E+01 2 .573E+01 3 .179E+01 3 .401E+01 3 .337E+01 2 .778E+01 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 Fermi 2 2007 Data Turbine Bldg 2.260 DAY DECAY, UNDEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 0.250 0.500 0.750 RUN DATE: 2-25-2008 9:25 DISTANCE IN MILES FROM THE SITE 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S SSW SW WSW W WNW NW.NNW N NNE NE ENE E ESE SE SSE 1 685E-05 1. 148E-05 1. 119E-05 8 .750E-06 1. 195E-05 1. 567E-05 1 .437E-05 1 .288E-05 1. 666E-05 3 .395E-05 3 .300E-05 3 .257E-05 2 .638E-05 2 873E-05 2 .225E-05 2 .041E-05 5. 493E-06 4. 026E-06 3 950E-06 2 986E-06 4 082E-06 5. 131E-06 4. 449E-06 4 059E-06 5. 516E-06 1. 134E-05 1. 127E-05 1. 118E-05 8. 735E-06 9. 143E-06 7. 276E-06 6 695E-06 2 .933E-06 2 .212E-06 2 .129E-06 1 .589E-06 2 .187E-06 2 .743E-06 2 .300E-06 2 .175E-06 2 983E-06 6 .121E-06 6 .088E-06 6 .077E-06 4 .716E-06 4 .841E-06 3 .910E-06 3 .595E-06 1 503E-06 1 126E-06 1 072E-06 7 .962E-07 1. 097E-06 1. 381E-06 1. 157E-06 1 106E-06 1. 522E-06 3. 107E-06 3 079E-06 3. 107E-06 2. 433E-06 2. 505E-06 2 014E-06 1. 846E-06 6. 236E-07 4. 570E-07 4. 294E-07 3. 199E-07 4. 365E-07 5. 541E-07 4. 72 9E-07 4. 540E-07 6 .239E-07 1. 259E-06 1. 239E-06 1. 276E-06 1. 021E-06 1. 064E-06 8. 446E-07 7. 664E-07 3. 470E-07 2. 496E-07 2 329E-07 1. 746E-07 2 354E-07 3. 002E-07 2. 601E-07 2. 506E-07 3. 441E-07 6. 879E-07 6. 737E-07 7. 046E-07 5. 736E-07 6. 030E-07 4. 745E-07 4. 262E-07 2 .247E-07 1. 592E-07 1. 478E-07 1. 115E-07 1. 487E-07 1. 904E-07 1. 671E-07 1. 614E-07 2. 215E-07 4. 395E-07 4. 288E-07 4. 538E-07 3. 745E-07 3. 965E-07 3. 098E-07 2. 760E-07 1. 595E-07 1. 116E-07 1. 032E-07 7. 826E-08 1. 036E-07 1. 330E-07 1. 179E-07 1. 141E-07 1. 566E-07 3. 088E-07 3. 003E-07 3. 209E-07 2. 678E-07 2. 852E-07 2. 215E-07 1. 959E-07 1 .204E-07 8 .334E-08 7 .683E-08 5 .853E-08 7 .696E-08 9.907E-08 8.865E-08 8 .590E-08 1 .178E-07 2 .312E-07 2 .242E-07 2.414E-07 2 .034E-07 2. 178E-07 1 .683E-07 1 .480E-07 9 .496E-08 6. 512E-08 5 .986E-08 4 .578E-08 5 990E-08 7 .728E-08 6 970E-08 6 .760E-08 9 .269E-08 1 .812E-07 1 .752E-07.1 .899E-07 1 613E-07 1 .735E-07 1 .335E-07 1. 168E-07 7 .738E-08 5. 264E-08 4. 826E-08 3.703E-08 4. 827E-08 6.239E-08 5. 666E-08 5. 500E-08 7. 538E-08 1. 468E-07 1. 417E-07 1. 544E-07 1.321E-07 1. 427E-07 1. 093E-07 9.523E-08 ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 5.000 7.500 10.000 DISTANCE IN MILES FROM THE SITE 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S SSW SW.WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 6. 469E-08 4 .368E-08 3 996E-08 3 .075E-08 3 996E-08 5. 173E-08 4. 727E-08 4. 592E-08 6 .291E-08 1 .222E-07 1. 176E-07 1 .288E-07 1 109E-07 1 .202E-07 9. 176E-08 7 966E-08 3. 439E-08 2 259E-08 2 046E-08 1 591E-08 2 052E-08 2 673E-08 2 501E-08 2 431E-08 3 .324E-08 6. 390E-08 6. 102E-08 6. 801E-08 5. 993E-08 6. 592E-08 4. 955E-08 4. 247E-08 2 .272E-08 1 .465E-08 1 .315E-08 1. 029E-08 1 .327E-08 1 .736E-08 1. 650E-08 1. 603E-08 2 187E-08 4. 181E-08 3 967E-08 4 .471E-08 4. 004E-08 4 .447E-08 3 .305E-08 2 .812E-08 1.329E-08 8. 347E-09 7.396E-09 5. 825E-09 7. 553E-09 9 .944E-09 9. 646E-09 9. 353E-09 1. 272E-08 2 .417E-08 2. 272E-08 2. 595E-08 2 373E-08 2 672E-08 1. 954E-08 1. 648E-08 9. 056E-09 5. 589E-09 4. 904E-09 3 .877E-09 5. 067E-09 6. 703E-09 6. 588E-09 6. 369E-09 8. 639E-09 1. 636E-08 1. 527E-08 1. 758E-08 1. 629E-08 1. 852E-08 1. 339E-08 1. 125E-08 6. 706E-09 4. 086E-09 3. 556E-09 2. 817.E-09 3 .715E-09 4. 932E-09 4. 894E-09 4. 716E-09 6 381E-09 1 .207E-08 1.120E-08 1 .295E-08 1 .211E-08 1 .387E-08 9. 944E-09 8. 336E-09 5. 233E-09 3. 156E-09 2 727E-09 2 164E-09 2 881E-09 3. 835E-09 3. 833E-09 3. 682E-09 4. 970E-09 9. 401E-09 8. 672E-09 1. 006E-08 9. 469E-09 1. 092E-08 7. 771E-09 6. 507E-09 4. 234E-09 2 533E-09 2 175E-09 1. 728E-09 2 321E-09 3 096E-09 3. 114E-09 2.981E-09 4. 014E-09 7. 598E-09 6. 972E-09 8. 103E-09 7. 666E-09 8. 891E-09 6. 290E-09 5. 265E-09 3 .517E-09 2 .090E-09 1 .784E-09 1 .419E-09 1.924E-09 2 .570E-09 2 .597E-09 2.478E-09 3 .330E-09 6 .310E-09 5 .761E-09 6 .704E-09 6 .366E-09 7. 421E-09 5 .225E-09 4.373E-09 2 982E-09 1 .761E-09 1 .496E-09 1. 191E-09 1 628E-09 2. 179E-09 2 .211E-09 2. 103E-09 2.820E-09 5.349E-09 4. 861E-09 5. 661E-09 5 .391E-09 6 .313E-09 4 .425E-09 3 .705E-09 2.568E-09 1. 509E-09 1.276E-09 1. 017E-09 1. 402E-09 1. 877E-09 1. 913E-09 1. 813E-09 2. 426E-09 4. 609E-09 4. 169E-09 4. 857E-09 4.636E-09 5. 451E-09 3.807E-09 3.189E-09 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) 40.10 DIAMETER (METERS) 7.46 EXIT VELOCITY (METERS) 3.31 AT THE RELEASE HEIGHT: VENT RELEASE MODE WIND SPEED (METERS/SEC)

REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)(METERS)(SQ.METERS)(CAL/SEC)40.1 40.1 5130.0 0.0/ AT THE MEASURED WIND HEIGHT ( 10.0 METERS):/ VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ STABLE CONDITIONS

/ ELEVATED LESS THAN 0.331/ MIXED BETWEEN 0.331 AND 1.653/ GROUND LEVEL ABOVE 1.653 ELEVATED MIXED GROUND LEVEL LESS THAN BETWEEN ABOVE 0.662 0.662 AND 3.310 3.310 WIND SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS THAN 0.468 BETWEEN 0.468 AND 2.339 ABOVE 2.339 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data Turbine Bldg 2.260 DAY DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT DIRECTION

.5-1 FROM SITE S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 2. 866E-06 2. 133E-06 2 .064E-06 1. 547E-06 2. 124E-06 2 .668E-06 2. 270E-06 2 .118E-06 2.897E-06 5 942E-06 5 .901E-06 5. 891E-06 4. 594E-06 4. 759E-06 3. 815E-06 3. 507E-06 1-2 6 962E-07 5. 13 6E-07 4. 849E-07 3 .612E-07 4. 938E-07 6. 249E-07 5. 304E-07 5. 084E-07 6. 991E-07 1. 416E-06 1. 397E-06 1. 429E-06 1. 136E-06 1. 179E-06 9. 398E-07 8. 552E-07 2-3 2. 312E-07 1. 643E-07 1. 526E-07 1. 150E-07 1. 538E-07 1. 967E-07 1. 722E-07 1. 663E-07 2. 282E-07 4. 534E-07 4. 427E-07 4. 675E-07 3. 849E-07 4. 070E-07 3. 184E-07 2. 840E-07 SEGMENT BOUNDARIES IN MILES FROM THE SI 3-4 4-5 5-10 1 219E-07 8 447E-08 7 790E-08 5 931E-08 7 806E-08 1 005E-07 8 980E-08 8 699E-08 1. 193E-07 2 .343E-07 2 .273E-07 2 .445E-07 2 .057E-07 2 .202E-07 1 .702E-07 1 .498E-07 7 .789E-08 5.302E-08 4. 863E-08 3 .730E-08 4. 864E-08 6 .285E-08 5 .704E-08 5. 537E-08 7.589E-08 1 .479E-07 1. 427E-07 1.555E-07 1.329E-07 1. 435E-07 1. I00E-07 9.585E-08 3 .594E-08 2 .375E-08 2 154E-08 1 671E-08 2. 162E-08 2. 812E-08 2 .617E-08 2 .543E-08 3 .478E-08 6 .704E-08 6. 411E-08 7 117E-08 6 .241E-08 6 .846E-08 5. 159E-08 4. 435E-08 TE 10-20 1 .350E-08 8. 521E-09 7 .567E-09 5.951E-09 7 .718E-09 1.015E-08 9. 809E-09 9. 510E-09 1 .294E-08 2. 462E-08 2.318E-08 2. 640E-08 2 .405E-08 2 .702E-08 1.981E-08 1. 674E-08 20-30 6. 743E-09 4. 115E-09 3. 584E-09 2. 838E-09 3 .742E-09 4. 965E-09 4. 921E-09 4. 743E-09 6. 418E-09 1. 215E-08 1. 127E-08 1. 303E-08 1. 217E-08 1. 393E-08 9. 993E-09 8. 381E-09 30-40 4. 246E-09 2.542E-09 2. 184E-09 1.735E-09 2. 330E-09 3.107E-09 3.123E-09 2.989E-09 4. 027E-09 7. 623E-09 6. 996E-09 8. 129E-09 7. 686E-09 8. 910E-09 6. 307E-09 5. 280E-09 40-50 2. 987E-09 1. 765E-09 1. 500E-09 1. 194E-09 1. 632E-09 2. 183E-09 2. 215E-09 2. 107E-09 2. 825E-09 5. 360E-09 4. 871E-09 5. 672E-09 5. 400E-09 6. 322E-09 4. 433E-09 3. 712E-09 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 Fermi 2 2007 Data Turbine Bldg 8.000 DAY DECAY, DEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 0.250 0.500 0.750 RUN DATE: 2-25-2008 9:25 DISTANCE IN MILES FROM THE SITE 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE* SE SSE 1 569E-05 1 069E-05 1 043E-05 8 151E-06 1. 113E-05 1 .460E-05 1 .339E-05 1 200E-05 1. 552E-05 3 .162E-05 3 .074E-05 3 .034E-05 2 .458E-05 2 .677E-05 2 .074E-05 1. 901E-05 5 005E-06 3 668E-06 3 598E-06 2 .720E-06 3 718E-06 4 674E-06 4 054E-06 3 699E-06 5 027E-06 1 033E-05 1 026E-05 1. 019E-05 7. 963E-06 8 335E-06 6. 635E-06 6. 101E-06 2. 623E-06 1 978E-06 1 903E-06 1 420E-06 1 953E-06 2 .450E-06 2 .055E-06 1. 944E-06 2 .668E-06 5 .466E-06 5 .441E-06 5 .438E-06 4 .223E-06 4. 334E-06 3 .501E-06 3 .217E-06 1. 323E-06 9 928E-07 9 .440E-07 7 004E-07 9 632E-07 1 213E-06 1. 017E-06 9 .730E-07 1. 340E-06 2. 729E-06 2 .709E-06 2. 740E-06 2. 148E-06 2 211E-06 1. 777E-06 1. 628E-06 5. 360E-07 3. 933E-07 3. 691E-07 2 .750E-07 3 .732E-07 4. 737E-07 4. 048E-07 3 .896E-07 5. 360E-07 1. 076E-06 1. 063E-06 1 I00E-06 8. 836E-07 9. 194E-07 7 300E-07 6. 602E-07 2 927E-07 2 108E-07 1. 964E-07 1. 475E-07 1. 968E-07 2. 510E-07 2. 180E-07 2 108E-07 2 900E-07 5 756E-07 5 669E-07 5 .975E-07 4. 893E-07 5. 132E-07 4. 037E-07 3. 606E-07 1. 866E-07 1. 322E-07 1. 227E-07 9. 292E-08 1. 220E-07 1. 561E-07 1. 375E-07 1. 335E-07 1. 837E-07 3. 611E-07 3. 549E-07 3. 794E-07 3. 157E-07 3. 333E-07 2. 603E-07 2 300E-07 1. 307E-07 9. 136E-08 8. 452E-08 6. 447E-08 8. 355E-08 1. 072E-07 9. 556E-08 9. 300E-08 1. 281E-07 2. 497E-07 2. 450E-07 2. 651E-07 2 .235E-07 2. 373E-07 1. 842E-07 1. 612E-07 9.744E-08 6.735E-08 6 .216E-08 4 .772E-08 6.115E-08 7.861E-08 7 .082E-08 6 .911E-08 9.524E-08 1 .843E-07 1 .806E-07 1.974E-07 1 .683E-07 1 .797E-07 1 .387E-07 1 .203E-07 7 601E-08 5 .201E-08 4 .790E-08 3 699E-08 4 .695E-08 6 .045E-08 5 .497E-08 5 .376E-08 7 .412E-08 1. 425E-07 1 .395E-07 1. 538E-07 1 325E-07 1. 421E-07 1. 091E-07 9. 401E-08 6. 133E-08 4. 159E-08 3. 824E-08 2 967E-08 3 735E-08 4 817E-08 4. 416E-08 4 327E-08 5. 969E-08 1. 142E-07 1. 116E-07 1 .240E-07 1. 078E-07 1. 160E-07 8. 871E-08 7. 596E-08 ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)SECTOR 5.000 7.500 10 DISTANCE IN MILES FROM THE SITE.000 15.000 20.000 25.000 30.000 35.000 ' 40.000 45.000 50.000 S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 5 080E-08 3 417E-08 3 136E-08 2 445E-08 3 056E-08 3 946E-08 3 645E-08 3 577E-08 4. 936E-08 9 .395E-08 9. 178E-08 1. 027E-07 8. 996E-08 9. 719E-08 7 .399E-08 6 301E-08 2 610E-08 1 .702E-08 1. 551E-08 1. 230E-08 1 500E-08 1. 947E-08 1. 851E-08 1. 826E-08 2. 524E-08 4. 715E-08 4. 596E-08 5. 273E-08 4. 769E-08 5. 223E-08 3. 909E-08 3. 260E-08 1 677E-08 1 070E-08 9. 693E-09 7 .776E-09 9 .331E-09 1 .215E-08 1 .179E-08 1 .168E-08 1 616E-08 2 .980E-08 2 .903E-08 3 .392E-08 3 .140E-08 3 .470E-08 2 .562E-08 2 107E-08 9. 408E-09 5 823E-09 5 225E-09 4 257E-09 5 003E-09 6 546E-09 6. 539E-09 6. 513E-09 9. 032E-09 1 634E-08 1 593E-08 1. 911E-08 1. 828E-08 2. 044E-08 1.480E-08 1. 194E-08 6. 220E-09 3 769E-09 3 357E-09 2. 763E-09 3. 203E-09 4. 206E-09 4. 287E-09 4. 286E-09 5. 958E-09 1. 063E-08 1. 039E-08 1. 269E-08 1. 242E-08 1. 401E-08 9. 997E-09 7. 956E-09 4. 497E-09 2 .683E-09 2 373E-09 1. 969E-09 2 .259E-09 2 .974E-09 3. 080E-09 3. 088E-09 4 302E-09 7. 590E-09 7 .440E-09 9. 222E-09 9.188E-09 1. 043E-08 7 .355E-09 5 795E-09 3. 442E-09 2. 028E-09 1. 782E-09 1. 488E-09 1. 694E-09 2 235E-09 2 344E-09 2 356E-09 3 290E-09 5. 750E-09 5. 653E-09 7. 092E-09 7. 167E-09 8. 182E-09 5. 712E-09 4. 465E-09 2 .739E-09 1. 598E-09 1. 395E-09 1. 171E-09 1. 324E-09 1 .750E-09 1. 856E-09 1. 870E-09 2. 617E-09 4. 537E-09 4. 473E-09 5. 671E-09 5. 800E-09 6. 654E-09 4. 604E-09 3. 575E-09 2.240E-09 1 .296E-09 1.125E-09 9.474E-10 1. 067E-09 1 .413E-09 1 .512E-09 1. 526E-09 2 .139E-09 3 .685E-09 3 .641E-09 4. 656E-09 4 .808E-09 5 .540E-09 3.805E-09 2 .939E-09 1. 873E-09 1. 077E-09 9 .285E-10 7 .846E-10 8 808E-10 1 .168E-09 1 .260E-09 1 .273E-09 1 .788E-09 3 .063E-09 3 .033E-09 3 909E-09 4. 072E-09 4 .710E-09 3 .212E-09 2 .471E-09 1. 593E-09 9. 102E-10 7 .802E-10 6. 611E-10 7 404E-10 9 828E-10 1 067E-09 1 081E-09 1 520E-09 2 590E-09 2 571E-09 3 336E-09 3. 501E-09 4. 065E-09 2. 755E-09 2. 111E-09 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS)DIAMETER (METERS)EXIT VELOCITY -(METERS)40.10 7.46 3.31 REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)(METERS)(SQ.METERS)(CAL/SEC)40.1 40.1 5130.0 0.0 AT THE RELEASE HEIGHT: VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ AT THE MEASURED WIND HEIGHT ( 10.0 METERS):/ VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ STABLE CONDITIONS

/ ELEVATED LESS THAN 0.331/ MIXED BETWEEN 0.331 AND 1.653/ GROUND LEVEL ABOVE 1.653 ELEVATED MIXED GROUND LEVEL LESS THAN BETWEEN ABOVE 0.662 0.662 AND 3.310 3.310 WIND SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS THAN 0.468 BETWEEN 0.468 AND 2.339 ABOVE 2.339 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data Turbine Bldg 8.000 DAY DECAY, DEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION

.5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 2.575E-06 6.028E-07 1.925E-07 9.877E-08 6.178E-08 2.744E-08 9.627E-09 4.535E-09 2.750E-09 1.878E-09 ,SSW 1.916E-06 4.454E-07 1.368E-07 6.836E-08 4.193E-08 1.802E-08 5.994E-09 2.711E-09 1.606E-09 1.080E-09 SW 1.853E-06 4.201E-07 1.271E-07 6.312E-08 3.855E-08 1.645E-08 5.387E-09 2.399E-09 1.403E-09 9.318E-10 WSW 1.389E-06 3.129E-07 9.611E-08 4.842E-08 2.991E-08 1.299E-08 4.375E-09 1.988E-09 1.176E-09 7.871E-10 W 1.906E-06 4.259E-07 1.266E-07 6.214E-08 3.768E-08 1.594E-08 5.165E-09 2.284E-09 1.332E-09 8.841E-10 WNW 2.395E-06 5.390E-07 1.618E-07 7.985E-08 4.859E-08 2.066E-08 6.751E-09 3.007E-09 1.760E-09 1.172E-09 NW 2.038E-06 4.579E-07 1.422E-07 7.185E-08 4.451E-08 1.951E-08 6.706E-09 3.108E-09 1.864E-09 1.263E-09 NNW 1.903E-06 4.398E-07 1.379E-07 7.009E-08 4.360E-08 1.923E-08 6.672E-09 3.115E-09 1.878E-09 1.277E-09 N 2.602E-06 6.053E-07 1.898E-07 9.658E-08 6.014E-08 2.657E-08 9.250E-09 4.339E-09 2.627E-09 1.792E-09 NNE 5.331E-06 1.221E-06 3.737E-07 1.871E-07 1.151E-07 4.984E-08 1.679E-08 7.664E-09 4.559E-09 3.072E-09 NE 5.298E-06 1.208E-06 3.674E-07 1.833E-07 1.125E-07 4.862E-08 1.638E-08 7.512E-09 4.493E-09 3.042E-09 ENE 5.294E-06 1.241E-06 3.918E-07 2.001E-07 1.249E-07 5.546E-08 1.955E-08 9.296E-09 5.690E-09 3.918E-09 E 4.132E-06 9.894E-07 3.251E-07 1.705E-07 1.085E-07 4.984E-08 1.859E-08 9.242E-09 5.812E-09 4.079E-09 ESE 4.279E-06 1.026E-06 3.429E-07 1.818E-07 1.168E-07 5.443E-08 2.075E-08 1.049E-08 6.666E-09 4.717E-09 SE 3.431E-06 8.177E-07 2.681E-07 1.404E-07 8.930E-08 4.086E-08 1.507E-08 7.403E-09 4.616E-09 3.218E-09 SSE 3.152E-06 7.420E-07 2.373E-07 1.220E-07 7.651E-08 3.423E-08 1.220E-08 5.839E-09 3.587E-09 2.476E-09 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data Turbine Bldg CORRECTED USING STANDARD DIRECTION FROM SITE 0.25 S 8.812E-08 SSW 6.940E-08 SW 8.408E-08 WSW 9.119E-08 W 1.175E-07 WNW 1.291E-07 NW 1.323E-07 NNW 9.767E-08 N 9.742E-08 NNE 2.210E-07 NE 2.293E-07 ENE 1.738E-07 E 1.264E-07 ESE 1.149E-07 SE 1.061E-07 SSE 9.802E-08 OPEN TERRAIN FACTORS RELATIVE DEPOSITION PER UNIT AREA (M**-2) AT FIXED POINTS BY DOWNWIND SECTORS** ** * * *** * ** ** ** ** **0.50 3. 033E-08 2 .400E-08 2 886E-08 3 112E-08 4. 004E-08 4 .410E-08 4. 531E-08 3. 358E-08 3 361E-08 7. 539E-08 7. 826E-08 5. 992E-08 4.367E-08 3. 979E-08 3.724E-08 3 .397E-08 7.50 7.616E-11 6. 112E-11 7. 148E-11 7. 555E-11 9.606E-11 1. 064E-10 1. 097E-10 8.206E-11 8.257E-11 1. 828E-10 1. 912E-10 1. 512E-10 1. 123E-10 1. OIIE-10 9. 509E-11 8.678E-I1 0.75 1 .572E-08 1 .251E-08 1 .494E-08 1 604E-08 2 .059E-08 2 .270E-08 2 .331E-08 1 .732E-08 1. 735E-08 3 884E-08 4. 041E-08, 3 .117E-08 2 .280E-08 2 .069E-08 1. 937E-08 1 .771E-08 10.00 4. 611E-11 3 .693E-11 4 .326E-11 4. 577E-11 5. 821E-11 6 .447E-11 6.651E-11 4.973E-11 5. 004E-11 1 .107E-10 1 .157E-10 9 .143E-11 6 .790E-11 6 .118E-11 5 .760E-11 5 .243E-11 1.00 7 534E-09 6. 019E-09 7. 152E-09 7. 649E-09 9. 796E-09 1. 081E-08 1. 10E-08 8. 265E-09 8 .285E-09 1. 852E-08 1. 930E-08 1 .497E-08 1. 098E-08 9 939E-09 9 302E-09 8. 526E-09 15.00 2 .338E-11 1. 868E-11 2. 190E-11 2 .318E-11 2 950E-11 3 .267E-11 3 375E-11 2 .524E-11 2 .542E-11 5 607E-11 5. 854E-11 4 625E-11 3 .438E-11 3 .105E-11 2 934E-I1 2 653E-11 DISTANCES 1.50 2.735E-09 2. 194E-09 2 .590E-09 2. 757E-09 3. 523E-09 3. 893E-09 4. 001E-09 2. 982E-09 2. 993E-09 6. 676E-09 6.970E-09 5.446E-09 4.003E-09 3.613E-09 3.385E-09 3.110E-09 DISTANCES 20.00 1.423E-11 1.136E-11 1.331E-11 1.407E-11 1.791E-11 1.985E-11 2.053E-11 1.537E-11 1.550E-11 3.404E-11 3.552E-11 2.812E-11 2.092E-11 1.894E-11 1.798E-11 1.615E-11 IN MILES 2.00 1.365E-09 1.096E-09 1.290E-09 1.370E-09 1.748E-09 I. 933E-09 1.989E-09 1.483E-09 1.490E-09 3.319E-09 3.467E-09 2.719E-09 2. 003E-09 1.806E-09 1. 692E-09 1.555E-09 IN MILES 25.00 9.612E-12 7.663E-12 8.970E-12 9.478E-12 1.205E-11 1.337E-11 1.385E-11 1.038E-11 1.049E-11 2.291E-11 2.391E-11 1.899E-11 1.418E-11 1.287E-11 1.225E-11 1.091E-11 2.50 8. 079E-10 6. 486E-10 7. 619E-10 8. 082E-10 1. 030E-09 1. 140E-09 1. 173E-09 8. 753E-10 8. 794E-10 1. 957E-09 2. 046E-09 1. 608E-09 1. 186E-09 1. 069E-09 1. 002E-09 9. 201E-10 30.00 6. 951E-12 5. 535E-12 6. 466E-12 6. 824E-12 8. 675E-12 9 626E-12 9. 986E-12 7. 503E-12 7. 598E-12 1. 649E-11 1. 722E-11 1. 375E-11 1. 031E-11 9. 397E-12 8. 957E-12 7 905E-12 3.00 5. 309E-10 4.263E-10 5. 001E-10 5. 299E-10 6. 750E-10 7. 470E-10 7. 691E-10 5. 742E-10 5. 771E-10 1.283E-09 1. 341E-09 1. 056E-09 7. 805E-10 7. 028E-10 6. 590E-10 6. 049E-10 35.00 5. 272E-12 4. 192E-12 4. 885E-12 5. 149E-12 6. 541E-12 7. 262E-12 7. 545E-12 5. 682E-12 5. 773E-12 1. 245E-11 1. 301E-11 1. 045E-11 7. 884E-12 7. 220E-12 6. 872E-12 6. 013E-12 3.50 3 .746E-10 3. 008E-10 3.525E-10 3 .733E-10 4 .753E-10 5 .260E-10 5 .419E-10 4 .046E-10 4.068E-10 9 .039E-10 9.451E-10 7 .450E-10 5 .511E-10 4.961E-10 4. 655E-10 4 .269E-10 40.00 4. 145E-12 3.291E-12 3.823E-12 4.025E-12 5. 108E-12 5 .675E-12 5.906E-12 4. 459E-12 4.547E-12 9. 734E-12 1. 019E-11 8.244E-12 6. 258E-12 5 .764E-12 5. 472E-12 4. 745E-12 4.00 2.782E-10 2.234E-10 2.617E-10 2.769E-10 3. 524E-10 3. 901E-10 4. 020E-10 3. 003E-10 3. 019E-10 6.704EZ10 7.011E-10 5. 532E-10 4.095E-10 3.686E-10 3.460E-10 3.171E-10 45.00 3 .347E-12 2 .654E-12 3. 072E-12 3 .231E-12 4.097E-12 4 .553E-12 4. 745E-12 3.592E-12 3.677E-12 7 .819E-12 8 .194E-12 6.682E-12 5 .106E-12 4 .729E-12 4 .471E-12 3.846E-12 4.50 2. 148E-10 1. 725E-10 2.019E-10 2. 135E-10 2. 717E-10 3.008E-10 3. lOOE-10 2 .317E-10 2.330E-10 5. 170E-10 5. 407E-10 4. 270E-10 3. 162E-10 2 .846E-10 2. 673E-10 2.448E-10 DIRECTION FROM SITE S SSW SW WSW W WNW NW NNW NNE NE ENE E ESE SE SSE 5.00 1 .708E-10 1 .372E-10 1. 605E-10 1 .698E-10 2 .159E-10.2 .391E-10 2 .465E-10 1. 842E-10 1. 853E-10 4. 109E-10 4 .298E-10 3 .396E-10 2 .516E-10 2 .265E-10 2. 128E-10 1.948E-10 50.00 2. 765E-12 2 .189E-12 2 .524E-12 2 .650E-12 3. 358E-12 3. 732E-12 3. 895E-12 2 .957E-12 3. 041E-12 6. 420E-12 6. 743E-12 5. 546E-12 4. 272E-12 3.981E-12 3. 740E-12 3. 192E-12 B Visitor Center/Ice F VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS)DIAMETER (METERS)EXIT VELOCITY (METERS)E 0.29 470.2. 1E-05 2 .1E-05 i.9E-05 1. OE-07 40.10 7.46 3.31 REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)(METERS)(SQ.METERS)(CAL/SEC)40.1 40.1 5130.0 0.0 AT THE RELEASE HEIGHT: VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ AT THE MEASURED WIND HEIGHT ( 10.0 METERS):/ VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ STABLE CONDITIONS

/ ELEVATED LESS THAN 0.331/ MIXED BETWEEN 0.331 AND 1.653/ GROUND LEVEL ABOVE 1.653 ELEVATED MIXED GROUND LEVEL LESS THAN BETWEEN ABOVE 0.662 0.662 AND 3.310 3.310 WIND SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS THAN 0.468 BETWEEN 0.468 AND 2.339 ABOVE 2.339 Appendix H Offsite Dose Calculation Manual for 2007 Revisions USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0 RUN DATE: 2-25-2008 9:25 Fermi 2 2007 Data Turbine Bldg DIRECTION

.5-1 FROM SITE RELATIVE DEPOSITION PER UNIT AREA (M**-2) BY DOWNWIND SECTORS SEGMENT BOUNDARIES IN MILES S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE 1. 533E-08 1.218E-08 1.457E-08 1. 566E-08 2.012E-08 2.217E-08 2.277E-08 1. 691E-08 1. 694E-08 3.793E-08 3.944E-08 3. 036E-08 2.219E-08 2.016E-08 1. 887E-08 1 .724E-08 1-2 3. 193E-09 2 .556E-09 3 026E-09 3 228E-09 4. 128E-09 4. 560E-09 4. 685E-09 3. 490E-09 3. 501E-09 7. 815E-09 8. 153E-09 6 351E-09 4. 665E-09 4. 216E-09 3. 947E-09 3. 622E-09 2-3 8 .458E-10 6 .790E-10 7. 980E-10 8.468E-10 1. 080E-09 1. 194E-09 1 .229E-09 9.170E-10 9 .212E-10 2. 051E-09 2. 143E-09 1. 683E-09 1 .242E-09 1.119E-09 1. 049E-09 9.632E-10 3-4 4-5 3. 826E-10 3. 072E-10 3. 601E-10 3. 813E-10 4. 855E-10 5. 374E-10 5. 535E-10 4. 133E-10 4. 155E-10 9. 233E-10 9. 654E-10 7. 608E-10 5. 627E-10 5. 066E-10 4.753E-10 4..359E-10 2 .173E-10 1. 745E-10 2.043E-10 2. 161E-10 2 .750E-10 3 .044E-10 3. 137E-10 2 .344E-10 2 .358E-10 5.232E-10 5. 471E-10 4.320E-10 3.200E-10 2. 880E-10 2 .705E-10 2 .477E-10 5-10 8. 384E-11 6. 728E-11 7. 873E-11 8. 325E-11 1. 059E-10 1. 173E-10 1. 209E-10 9. 039E-11 9. 094E-11 2. 015E-10 2. 107E-10 1. 665E-10 1.235E-10 1. 112E-10 1. 046E-10 9. 552E-11 10-20 2. 436E-11 1. 948E-11 2. 283E-11 2. 415E-11 3. 073E-11 3. 404E-11 3. 516E-11 2 629E-11 2. 648E-11 5. 842E-11 6. 102E-11 4. 823E-11 3 585E-11 3. 236E-11 3. 057E-11 2. 767E-11 20-30 9 .779E-12 7 .797E-12 9. 125E-12 9. 642E-12 1 .226E-11 1.360E-11 1.409E-11 1. 056E-11 1. 067E-11 2.331E-11 2 .433E-11 1. 933E-11 1. 443E-11 1.310E-11 1 .246E-11 1. 1IIE-II 30-40 5 .323E-12 4 .233E-12 4 932E-12 5. 199E-12 6 605E-12 7 .333E-12 7 618E-12 5 .736E-12 5. 827E-12 1 .257E-11 1 .314E-11 1 .055E-I1 7 .958E-12 7 .287E-12 6 934E-12 6.070E-12 40-50 3 .368E-12 2 .671E-12 33. 091E-12 3.251E-12 4. 123E-12 4.581E-12 4. 774E-12 3.614E-12 3.699E-12 7 .869E-12 8.247E-12 6. 724E-12 5. 138E-12 4. 758E-12 4 .497E-12 3. 870E-12 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS)DIAMETER (METERS)EXIT VELOCITY (METERS)AT THE RELEASE HEIGHT: VENT RELEASE MODE WIND SPEED 40.10 7.46 3.31 REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)(METERS)(SQ.METERS)(CAL/SEC)40.1 40.1 5130.0 0.0 ELEVATED MIXED GROUND LEVEL LESS THAN BETWEEN ABOVE (METERS/SEC) 0.662 0.662 AND 3.310 3.310/ AT THE MEASURED WIND HEIGHT ( 10.0 METERS):/ VENT RELEASE MODE WIND SPEED (METERS/SEC)

/ STABLE CONDITIONS

/ ELEVATED LESS THAN 0.331/ MIXED BETWEEN 0.331 AND 1.653/ GROUND LEVEL ABOVE 1.653 WIND SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS THAN 0.468 BETWEEN 0.468 AND 2.339 ABOVE 2.339 USNRC COMPUTER CODE -XOQDOQ, VERSION 2.0.Fermi 2 2007 Data Turbine Bldg CORRECTED USING STANDARD OPEN TERRAIN FACTORS SPECIFIC POINTS OF INTEREST RUN DATE: 2-25-2008 9:25 RELEASE TYPE OF ID LOCATION DIRECTION DISTANCE X/Q FROM SITE (MILES) (METERS) (SEC/CUB.METER)

NO DECAY X/Q X/Q (SEC/CUB.METER) (SEC/CUB.METER)

D/Q (PER SQ.METER)UNDEPLETED SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY SITE BOUNDARY Residences Residences Residences Residences Residences Residences Residences Residences Residences Residences Residences NE NNE NE S SSW SW WSW W WNW NW NNW N NE NNE NNW NW WNW W WSW SW SSW S NW WNW N NNE NE NNW NW SSW SW W WNW WSW SSW 1.13 1.02 0.36 0.88 0.96 1.19 1.12 0.86 0.67 0.57 0.62 1.10 1.10 1.02 1.08 1.06 0.69 1.16 1.58 1.26 1.13 1.02 3.65 2.28 1.64 1.80 1.99 2.55 2.76 1.50 4.39 3.18 1.82 3.21 0.29 1825.1646.579.1417.1542.1920.1798.1390.1082.915.990.1776.1773.1646.1743.1700.1103.1861.2547.2025.1826.1640.5874.3672.2633.2894.3200.4107.4435.2414.7062.5123.2936.5173.470.2 .3E-06 3 .OE-06 1. 9E'05 2 .OE-06 1. 2E-06 7 2E-07 6 2E-07 1. 6E-06 3 .3E-06 3. 6E-06 3 .0E-06 1. 2E-06 2 .5E-06 3 .OE-06 9 3E-07 1. OE-06 3 .2E-06 7 .8E-07 2 9E-07 6. 4E-07 8. 5E-07 1. 4E-06 8. 3E-08 2 3E-07 5. 2E-07 8. 6E-07 6. 9E-07 1. 6E-07 1. 4E-07 4. 6E-07 5. 1E-08 9. 3E-08 3.7E-07 6. 9E-08 9. OE-06 2.260 DAY DECAY UNDEPLETED

2. 3E-06 2. 9E-06 1. 9E-05 2. OE-06 1. 2E-06 7. 1E-07 6. 2E-07 1. 6E-06 3. 2E-06 3. 6E-06 3 .OE-06 1.2E-06 2. 5E-06 2. 9E-06 9. 2E-07 1. OE-06 3. 2E-06 7. 8E-07 2. 8E-07 6. 3E-07 8. 4E-07 1. 4E-06 8. 2E-08 2 .3E-07 5. 2E-07 8. 6E-07 6. 8E-07 1. 6E-07 1. 4E-07 4. 6E-07 5. 1E-08 9. 2E-08 3 .6E-07 6. 9E-08 9. OE-06 8.000 DAY DECAY DEPLETED 2.OE-06 2.6E-06 1.7E-05 1.8E-06 1.1E-06 6.2E-07 5.4E-07 1.4E-06 2 .9E-06 3 .3E-06 2 .7E-06 1 .1E-06 2 .2E-06 2 .6E-06 8 .1E-07 8.9E-07 2 .8E-06 6.8E-07 2 .4E-07 5.5E-07 7.4E-07 1.3E-06 6.5E-08 1.9E-07 4.4E-07 7.2E-07 5.7E-07 1.3E-07 1 .1E-07 3.9E-07 4.OE-08 7.4E-08 3. 1E-07 5.6E-08 8.4E-06 1. 4E-08 1. 7E-08 1.3E-07 1. OE-08 6. 7E-09 4.6E-09 5. 8E-09 1.4E-08 2.7E-08 3.7E-08 2 .4E-08 6. 4E-09 1. 5E-08 1. 7E-08 6. 7E-09 9.6E-09 2.6E-08 6. 8E-09 2. 4E-09 4. OE-09 4. 4E-09 7 .2E-09 4. 9E-10 1. 4E-09 2. 4E-09 4.3E-09 3. 5E-09 8. 3E-10 9. 4E-10 2 .2E-09 2. 1E-10 5. 9E-10 2.4E-09 4. 5E-10 5 .5E-08 B B B B B B B B B B B MILK COW MILK COW VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE VEGETABLE GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN B Visitor Center/Ice F