Text

Annual Radioactive Effluent Release and Radiological Environmental Operating Reports
	ML041250069
Person / Time
Site:	Fermi
Issue date:	04/30/2004
From:	O'Cnnor W; DTE Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NRC-04-0024, RG-1.021, Rev. 1
	Download: ML041250069 (324)
	v • d • e

William T. O'Connor, Jr.

Vice President, Nuclear Generation Fermi 2 6400 North Dixie Hlwuy, Newvport, Michigan 48166 Tel: 734-586-5201 Fax: 734-5864172 DTE Energy-April 30, 2004 NRC-04-0024 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001

References:

1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

2) Appendix A, Facility Operating License No.

NPF-43, Technical Specifications 5.6.2 and 5.6.3

Subject:

Annual Radioactive Effluent Release and Radiological Environmental Operating Reports The 2003 Annual Radiological Effluent Release and Radiological Environmental Operating Reports for Fermi 2 are enclosed. This combined report is being transmitted in accordance with Reference 2 and Regulatory Guide 1.21, Revision 1.

The enclosed report covers the period from January 1, 2003 through December 31, 2003.

Should you have any questions regarding this report, please contact Dan Craine, General Supervisor, Radiological Engineering at (734) 586-1516.

Sincerely, t D.&

Enclosure cc: wvEnclosure D. P. Beaulieu E. R. Duncan NRC Resident Office Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission

FERMI 2 NUCLEAR POWER PLANT DETROIT EDISON COMPANY OPERATING LICENSE NO. NPF - 43 Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report for the period of January 1, 2003 through December 31, 2003 Prepared by:

Fermi 2 Radiological Engineering

Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport Table of Contents Page Executive Summary I Introduction 2 Noble Gases 2 Iodines and Particulates 2 Tritium 3 Plant Effluent Monitoring 3 Exposure Pathwaysto People 4 Dose Assessment 5 PreoperationalSurveillance Program 6 OperationalSurveillance ProgramObjectives 7 Program Overview 7 Sample Analysis 8 Quality Assurance 10 RadiologicalEffluent MonitoringResults 12 Radiological Environmental Monitoring Program Results 16 Direct Radiation Monitoring 16 ThermoluminescentDosimeters 16 Atmospheric Monitoring 17 Air Sampling 18 TerrestrialMonitoring 20 Milk Sampling 20 GroundwaterSampling 21 Garden Sampling 22 Aquatic Monitoring 23 Drinking Water Sampling 23 Surface Water Sampling 25 Sediment Sampling 26 Fish Sampling 28 Land Use Census 30 2003 Land Use Census Results 31 Appendix A Sampling Locations A-l Appendix B Environmental DataSummary B-I

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport Table of Contents Page Appendix C Environmental Data Tables C-l Appendix D Environmental ProgramExecution D-l Direct RadiationMonitoring D-l Atmospheric Monitoring D-l TerrestrialMonitoring D-2 Milk Sampling D-2 Garden Sampling D-2 GroundwaterSampling D-2 Aquatic Monitoring D-2 Drinking Water Sampling D-2 Surface Water Sampling D-3 Sediment Sampling D-3 Fish Sampling D-3 Appendix E Effluent and Radwaste Data Regulatory Limits for Radioactive Effluents E-l Gaseous Effluents E-I Liquid Effluents E-2 Measurements and Approximations of Total Activity in Radioactive Effluents E-3 GaseousEffluents E-3 Fission andActivation Gases E-3 Radioiodines E-3 Particulates E4 Tritium E4 Gross Alpha E-5 Liquid Effluents E-5 StatisticalMeasurement Uncertainties E-5

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Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport Table of Contents Page Gaseous Release by IndividualNuclide E-5 ParticulateRadionuclides E-6 Noble Gases E-6 Radioiodines E-7 Shipments of Radwaste E-7 ClassA Resin E-8 ClassB Resin E-9 Dry compressible waste, contaminated equipment, etc. E-10 Irradiatedcomponents, control rods, etc. E-10 Other E-10 Appendix F InterlaboratoryComparison Data InterlaboratoryComparisonProgramfor 2003 F-i Appendix G MeteorologicalData G-I Appendix H Fermi2 Offsite Dose CalculationManual iv

Fermi 2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperating Report List of Figures Page Figure I Fermi 2 Annual Average TLD Gamma Exposure 17 Figure 2 HistoricalGross Beta and 1-131 Activity in Air Samples 19 Figure 3 Fermi 2 Air ParticulateGross Beta 2003 19 Figure 4 HistoricalStrontium-90 Activity in Local Milk-Samples 21 Figure 5 HistoricalGross Beta Activity in Drinking Water Samples 25 Figure 6 HistoricalCesium-137Activity in Sediment Samples 28 Map I Sampling Locations By Station Number (within I mile) App.-A Map 2 Sampling Locations By Station Number (I to 5 miles) App.-A Map 3 Sampling Locations By Station Number (greaterthan 5 miles) App.-A V

Fermi 2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperating Report List of Tables Page Table I Fission and Activation Gases (Noble Gases) Summary 12 Table 2 RadioiodinesSummary 13 Table 3 ParticulatesSummary 13 Table 4 Tritium Summary 13 Table 5 2003 Gaseous Effluent Dose to Receptor withi Highest Single OrganDose 14 Table 6 Solid Waste Received at Burial Sites 15 Table 7 Solid Waste Shipments I5 Table 8 2003 Average Gross Beta Concentrations in Air Particulates 18 Table 9 Closest Residences 32 Table 10 Closest Gardens 33 Table 1I Milk Locations 34 Table 12 Closest Meat Locations 35 Table A-I Direct Radiation Sample Locations A-I Table A-2 Air Particulateand 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 GroundwaterSample Locations A-9 Table A-8 Sediment Sample Locations A-10 Table A-9 Fish Sample Locations A-10 Table B-1 RadiologicalEnvironmentalMonitoring ProgramSummary B-1 Table F-I Analytics Cross Check ComparisonProgram2003 F-2

Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmental OperatingReport Executive Summary This report is published to provide information regarding radioactive effluent and environmental monitoring at the Fermi 2 Nuclear Power Plant. The 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report covers the period from January 1, 2003 through December 31, 2003.

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 2003. In fact, there has not been a liquid radioactive discharge from Fermi 2 since 1994.

The highest potenial single organ dose to a person living offsite due to iodines and particulates released from the plant was calculated to be 0.1 mrem, which is I% of the applicable limit found in 10 CFR 50, Appendix I.

Also during 2003, there was no measurable direct radiation dose due to Fermi 2 beyond the site boundary as shown by offsite 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 2003.

Environmental samples collected in 2003 showed no radioactivity attributable to the operation of Fermi 2. The results of environmental sampling show that radioactivity 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.

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Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEn vironmentalOperatingReport 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.

ANoble 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.

Jodines 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 I 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., yittrium-91m 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.

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Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport 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 liquid effluents. It is also present in gaseous effluents, and is routinely detected at Fermi 2.

Tritium is produced in the reactor coolant as a result of neutron interaction with deuterium (also a hydrogen isotope) present in the water, and it is also a fission product.

Plant Effluent Monitoring Effluents are strictly 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.

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Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport 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.

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Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental 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 an exposed individual. Whole body exposure to radiation involves the exposure of all organs. Most exposures due to external sources of radiation are of this type. Both non-radioactive and radioactive elements can enter the 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, 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 Environmcntal Monitoring Program (REMIP) 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 - 2003 Annual Radioactive Effluent Release and RadiologicalEnv ironmentalOperatingReport 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 Ferrni 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.

PreoperationalSurveillance 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 surveillance program conducted after facility operation begins. Radiochemical analyses performed on the environmental samples should include not only those nuclides expected to be released during facility 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.

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Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Enrironmental 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.

OperationalSunreillanceProgram 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; 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:

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Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnrironmentalOperatingReport

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.

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Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmeintal OperatingReport 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-I 31 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.

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Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport

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.

Quality Assurance An important part of the environmental monitoring program at Fermi 2 is the Quality Assurance Program (QA). 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 (investigations) 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 - 2003 Annual Radioactive Effluent Release and RadiologicalEnviron mental 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.

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Fermi 2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmental OperatingReport Radioactive Effluent MonitoringResutlts This section summarizes the results of effluent monitoring and offsite dose calculation for the year 2003, as well as a listing of radioactivity contained in Fermi 2 waste shipped for burial. Calculations of 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 2003. In fact, there has not been a liquid radioactive discharge from Fermi 2 since 1994. The 2003 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 2003.

The data in the following tables represent continuous and batch releases. In 2003, there was one containment purge in which radioactivity was detected. Based on recorded start and stop times, this purge lasted 188 minutes.

Note that some values in the fission and activation gases summary table and the tritium summary table are preceded by the "less than" symbol. These values represent the lower limit of detection (LLD) in units of microcuries per cubic centimeter (liCi/cc) for individual samples, and indicate that noble gases or tritium were not detected in the quarter. (For noble gases, the value <3.OE-07 is the sum of the LLD values for 4 common noble gases isotopes listed in Appendix E.)

Table I - Fission and Activation Gases (Noble Gases) Summary

- Quarter I Quarterter uarter 3 Quarter 4 Total Release <3.OE-07 <3.OE-07 1.07E-03 <3.0E-07 (curies)

Average Release NA NA 1.35E-04 NA Rate for Period (jICi/sec) 12

Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport Table 2 - Radioiodines Summary Quarter1 Quarter 2 Quartcr 3. Quarter 4 Total 1-13 1 2.39E-03 1.07E-03 1.69E-03 9.89E-04 (curies)

Average Release 3.08E-04 1.35E-04 2.13E-04 1.25E-04 Rate for Period (pCi/sec)

Table 3 - Particulates Summary

. Quartr Oi-i-_ 1 Quarter 2 Quarter 3 Quarter 4 Particulates with 1.43E-04 2.04E-04 1.55E-04 1.47E-04 half lives > 8 days (curies)

Average 1.84E-05 2.59E-05 1.95E-05 1.85E-05 Release Rate for Period (pCi/sec)

Gross Alpha 6.48E-07 4.91 E-07 3.14E-07 9.35E-08 Radioactivity (curies)

Table 4 - Tritium Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Release 1.59E+00 <4.OE-08 1.71 E-03 2.21 E+01 (curies)

Average Release 2.05E-01 NA 2.1513-04 2.78E+00 Rate for Period (pCi/sec) . -

The offsite dose impact of the above releases wvas 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:

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Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport Table 5

-:`;2003Gaseous Effluent Dose to Organ Receptor with Highet Single Organ i ose -:.::

Bone 0.003 mrem Liver 0.004 mrem Thyroid 0.1 mrem Kidney 0.005 mrem Lung; 0.004 mrem GI-LLI. -0.004 mrem Total body 0.004 mrem The highest single organ dose is 0.1 mrem to the thyroid. This is 1% of the federal limit of 15 mrem specified in IOCFR5O, Appendix 1.

Another dose calculation performed on the above release data is that for gamma and beta air dose at the site boundary due to noble gases. In 2003, gamma air dose, based on detected noble gas activity, was 2E-8 mrad, and beta air dose was 4E-8 mrad. These calculated doses are 2E-7% of the air dose limits of 10 mrad gamma and 20 mrad beta.

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 2003, 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 2003.

Potential dose to visitors at Fermi 2 due to all radioactive effluents, including noble gases, was also calculated. The ODCM considers persons visiting the Fermi 2 Visitors Center (4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s/year), and persons ice fishing on Lake Erie near the plant (240 hour0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months s/year), to be visitors. Using ODCM assumptions about these categories of visitors, the maximum potential dose to a visitor to Fermi 2 in 2003 was 0.003 mrem to the maximally exposed organ (thyroid) and 0.0004 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 2003. 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).

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Fermi 2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport The radioactivity and volume of Fermi 2 solid waste received at the Barnwell, SC, burial facility, or at the Envirocare, UT, facility in 2003 is summarized in the following table.

Table 6 - Solid Waste Received At Burial Sites

,. '-. ' ativity Type of waste Unit period error,-%

Spent resins, sludges, etc. m3 5.OOE+OI curies 3.03E+02 +/- 25 Dry compressible waste, m 4.09E+0 I contaminated equipment, etc. curies 1.28E+01 +/- 25 Irradiated components, control m 0 rods, etc. curies 0 NA Other m3 0 curies 0 NA Radioactive solid waste shipments from Fermi 2 in 2003 (to either disposal or to intermediate processors) are summarized in the following table.

_____________________Table 7 - Solid Waste Shipments______________

Type of shipment/ Number'of .* Mode'of Destination solidification process" shipments': A....transportation Spent resin, sludges, etc. 10 tractor trailer Chem Nuclear, Barnwell, SC, with cask Duratek, Barnwell, SC Dry compressible waste, 9 tractor trailer Duratek, Oak Ridge, TN contaminated equipment, etc.

Used oil 2 tractor trailer Duratek, Oak Ridge, TN Mixed waste I tractor trailer DSSI, Oak Ridge, TN The ODCM was revised in 2003. Appendix H of this report contains a copy of the entire ODCM, with the revised pages shown.

In 2003, no liquid or gaseous effluent monitoring instrumentation was out of service longer than the time limits specified in the ODCM. Also, no outside temporary tank exceeded the 10 curie content limit, and there were no major changes to radioactive waste systems in 2003.

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Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnv iro,,nmenitalOperating Report RadiologicalEnv;ironmntalMonitoring Program Results Direct Radiation AMonitoring 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.

Thcrinolumin escent 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 wvas exposed. This reading process then rezeros the TLD and prepares it for reuse.

Fermi 2 has 67 TLD locations within a 15 mile radius of the plant. Of the 67 TLD locations 18 are located on-site and are not used for comparison with the control locations. These 18 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), 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.

16

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEntvironmentalOperatingReport In 2003, the average exposure for TLDs at all off-site indicator locations was 15.2 mR/std qtr and for all control locations was 14.7 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 -

i= 10 E Preoperational Operational 5 I 0 ,,.,

O aM CD _ N 0

'D 0 0 _ C04 M T M 0 I- 0a 0 a N M to ) C:> 0) ) a) 0) C0 0) 0) C) 0 0) 0> 0 0) 0) 0 0)M 0 0 0 0 0 0

.0, C'J04 14 Year

-*-Indicator -- 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.

Atinospheric Alonitoring 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 arc 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 14 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.

17

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnrironmenialOperatingReport 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-1 pCi/cubic meter for control samples which was a factor of ten 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- I 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 7.0E-2 pCi/cubic meter.

During 2003, two hundred and fifty-five (255) 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 2.51 E-2 pCi/cubic meter and 2.48E-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 fivee sample locations for 2003.

2003 Average Gross Beta Concentrations in Air Particulates (pCi/m 3 )

Table 8 Station Description (sector/distance) Annual Average API-I (I) Estral Beach (NE/1.4 mi.) 2.63E-2 API-2 (I) Site Boundary (NNW/0.6 mi.) 2.48E-2 API-3 (I) Site Boundary (NW/0.6 mi.) 2.4 1E-2 API-4 (C) North Custer Rd. (W/14 mi.) 2.48E-2 API-5 (1) Site Boundary (S/1.2 mi.) 2.50E-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.

18

Fermi 2 - 2003 A nnual Radioactive Effluent Release and Radiological En vironmental OperatingReport 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 3.OE Activity in Air Samples 0

Chernobyl Event E 2.OE-01 D

-2 1.OE aL 1-13t LLD C C C p O.OE+00 r T T l - TI T T T l I I~ r 1 7 1-- I 1 Q

- C) L r- QM c ) tn F_ cn O o o> 0 o> co o co 0 o M C) oC 0 0

_.1 _2 _! _ _ _ _0 _ N 1 N Year l-tIndicator Gross Beta -Control Gross Beta - Iodine -131 Figure 2 - Hlistorical Gross Beta and lodine-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 (1I- D) for iodine-131 is 0.07 pCi/cubic meter.

Fermi 2 Air Particulate Gross Beta for 2003 6.OE-02 c 5.0E-02 E 4.OE-02 U

- 3.OE-02

.0

. 2.0E-02

a. 1.OE-02 O.OE+00 a Z

( C SD 0 > ; -

CC : CD m 0 CL CL - -> > U 0 0 f .0 CL C L 0~a a 0

? 4. c-nrn . < . O. °, C z z 0 0

> }N - 0 N Urc N < D Mo 0 _ u')°>

Collection Date

- Indicator -a- Control Figure 3 - Fermi 2 Air Particulate Gross Beta for 2003; 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.

19

Fermi 2 - 2003 Annual Radioactivc Effluent Release and Radiological Environmental OperatingReport 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 2003 data to previous operational and preoperational data.

AMilkt 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 from grazing animals (dairy cows or goats) due to biological concentration and the short turn around time in this pathway. Milk is collected from one indicator location and one control location semimonthly when animals are in the pasture, 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 arc collected at both the control milk sample location and the location wherc milk is not available. Grass samples are analyzed for iodine- 13 1 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+O 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+O 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 2003, thirty six (36) milk samples were collected and analyzed for iodine-13 1, gamma emitting radionuclides, and strontium-89/90. No iodine-131 was detected in any' of the samples. Strontium-90 was detected in both indicator and control milk samples and is due to fallout from past atmospheric weapons testing (see Figure 4). The indicator 20

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnrirownental OperatingReport samples had an average strontium-90 concentration of 2.06E+O pCi/liter and the control samples had an average concentration of 5.30E-I pCi/liter. During 2003, no grass samples were scheduled or collected for the REMP program.

In 1970, the concentration of strontium-90 in Monroe Countv milk was 6.00E+0 pCi/liter according to the Michigan Department of Health's "Milk Surveillance", Radiation Data and Reports, Vol. I I-1 5, 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 I II o N C to eO o N v tO e o N v cO co 0 N

- ra

- r- Is- - co o Co Co cCo o 0) a) 0) CY 0 0 CD CY 0n 0n a) a) 0o a a) C0 0 ) a) a) C0 c0 0 0

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ N N Year Average Sr-90 Activity - Calculated Decayl 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.

Groundwater Sampling In areas not served by municipal water systems, water supplies for domestic use are generally obtained from private wells. The network of private wells presently in use forms the source of water for domestic and livestock purposes in farms and homes west and north of the site. 1-owever, with the construction of new water plants and distribution systems, the water use trend in the area is from groundwater to surface water.

21

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport 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 north west is designated as the control location because it is up-gradient and is least likely to be affected by the operation of the plant. The other three sampling locations are down-gradient from Fermi 2 and designated as indicator locations.

Groundwater sampling began in 1987, during the operational period of the REMP program. From 1987 to 1996 naturally occurring potassium-40, cesium-137, and tritium were detected in both indicator and control samples. The average concentration was 7.71 E+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 2002 no activity was detected in groundwater samples.

In 2003, sixteen (16) groundwater samples were collected and analyzed for gamma emitting radionuclides and tritium. No activity was detected in any of these groundwater samples.

Gardei Samplitig 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 arc 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+ I pCi/k-ilogram.

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.

22

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnv;ironmnentalOperatingReport During 2003, eleven (11) vegetablc samples were collected and analyzed for iodine-131 and other gamma emitting radionuclides. No iodine- 131 was detected in vegetable samples during 2003. The only gamma emitting radionuclides detected were naturally occurring potassium-40 and beryllium-7.

Terrestrial monitoring results for 2003 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 Eric, 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, a comparison of 2003 data to previous operational and preoperational data.

Drinking Water Samplintig 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 v ery 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 1I.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.

23

Fermi 2 - 2003 Annual Radioactive EIffluent Release and RadiologicalEntvironmncntalOperatingReport 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+O pCi/liter for water samples. Figure 5 also shows that, except for the Chinese weapons testing, the historic drinking water sample data are below the lower limit of detection (4.00E+0 pCi/liter) required by US Environmental Protection Agency's (USEPA) National Interim Primary Drinking Water regulations. Even during the Chinese weapons testing. the drinking water samples did not exceed the USEPA's maximum allowable criteria of 5.OOE+I pCi/liter gross beta. In 1980 and 1983, cesium-137 was detected in drinking water samples at levels ranging from 5.40E+0 pCi/litcr to 1.90E+ I 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 2002, the average annual gross beta activity for indicator samples was 3.34E+0 pCi/liter and 2.68E+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-I pCi/liter and 7.56E- I 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/litcr 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 2003, 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 3.79E+0 and 3.29E+0 pCi/liter for control samples. No gamma emitting radionuclides or strontium-89/90 activity was detected in drinking water samples during 2003. Eight (8) quarterly composite drinking water samples were prepared and analyzed for tritium. No tritium activity was detected in drinking water samples during 2003.

24

Fermi 2 - 2003 Annual Radioactive Elffluent Release and RadiologicalEnrironmental OperatingReport Historical Gross Beta Activity 12.0 - in Drinking Water Samples 10.0 - Chines Weapons Test 8.0 -

C.)

0.

c 6.0 2.0-0.0- ,ia, , .I . . . . . . . . .

CO 0 N C (0 ECD 0 CV C to co 0 N co co co co co M 02 a) 02 0l 0 0 a) 02 02 CD 0 0 a 0x 02 02 02 C O

- _ _ _ _ _ _ _ _ CM C-Year Indicator Gross Beta Control Gross Beta --- EPA L)l 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 wvater.

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 north east 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.

25

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmnental OperatingReport 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 2002, 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+O pCi/liter. In 1990, two indicator samples showed detectable activity for cesium-I 37 at an average concentration of 1.20E+I 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 of 2.31E+2 pCi/liter. This tritium activity is consistent with background levels measured during the preoperational program.

In 2003, twenty-four (24) surface water samples were collected and analyzed for gamma emitting radionuclides and strontium-89/90. From these samples, six (6) quarterly composite samples were prepared and analyzed for tritium. During 2003, no gamma emitting radionuclides, strontium-89/90, or tritium were detected.

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).

26

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport 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 2002, cesium- 137, strontium-90, and naturally occurring radionuclides were detected in sediment samples. The average cesium- 137 concentration was 1.41 E+2 pCi/lkilogram 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 of cesium-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 2003, ten (10) sediment samples were collected and analyzed for gamma emitting radionuclides and strontium 89/90. Cesium-137 was detected in two control samples with an average concentration of 6.26E+1 pCi/kilogram and two indicator samples with an average concentration of 9.20E+1 pCi/kilogram. The presence of cesium-137 in sediment samples is due to fallout from past atmospheric nuclear weapons testing.

Naturally occurring radionuclides of potassium and beryllium were also detected in sediment samples for this sampling period.

27

Ferini 2 - 2003 Annual Radioactive Effluent Release and Radiological lnvironmental Operating Report Historical Cesium-137 Activity in Sediment Samples 7.OE+02 6.OE+02 Eu5.0E+02.

4.OE+02 - -

o2.OE+02 1.OE+02 -

co C a) as to co 0o n R) to Co 0 0

_ _ _ _ _ _ - _ _ _ CJ CN l Average Activity - Calculated Trend Figure 6 - Historical Cesium-]37 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 2003. 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 wcre detected during this time period. The averace concentration of cesium- 137 for indicator samples was 3.53E+I pCi/kilogram and 4.20E+I pCi/kilogram for control samples. The presence of cesium-I 37 in these fish samples is due to fallout from past atmospheric nuclear weapons testing.

28

Fermi 2 - 20(13 Annual RadioactiveEffluent Release and RadiologicalEnvwironm ental Operating Report From 1985 to 2002, cesium-137 and naturally occurring potassium-40 were detected in fish samples. The average cesium-137 concentration for indicator samples was 3.95E+I pCi/k-ilogram 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+l pCi/k-ilogram 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 2003, twenty-nine (29) fish samples were collected and analyzed for gamma emitting radionuclides and strontium-89/90. Naturally occurring potassium-40 was detected in all fish samples. Cesium-137 was detected in one indicator sample at a concentration of 3.70E+1 pCi/lkilogram. The presence of cesium-137 is due to fallout from past atmospheric nuclear weapons testing.

Aquatic monitoring results for 2003 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 2003 and no adverse long-term trends are shown in the aquatic monitoring data.

29

Fermi 2 - 2003 A nnal Radioactive E'ffluent Release and RadiologicalEnvironmental 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:

Inlhalation 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 Pathwiay - 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 Pathwvay - 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 Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (I) 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.

30

Fertni2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport 2003 Land Use Census Results The Land Use Census is conducted in accordance with ODCM control 3.12.2 and satisfies the requirements of Section IV..B.3 of Appendix I to 10 CFR Part 50. This census identifies changes in the use of unrestricted areas to permit modifications to monitoring programs for evaluating doses to individuals from principal pathways of exposure. The annual Land Use Census is conducted during the growing season and is used to identify, within a radius of 5 miles, the location of the closest residences, milk animals, meat animals, and gardens in each of the 16 meteorological sectors surrounding Fermi 2.

The 2003 Land Use Census was performed during the month of August. The 2003 census data were obtained with the use of a hand-held Global Positioning System (GPS).

These data were compared to the 2002 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 2002 and 2003 were found that would require changing the location of the "maximum exposed individual". There were no changes in the category of closest residences. However, there were slight changes in all but three Met Sectors in the category of closest gardens. See Table 10 for these changes.

The "maximum exposed individual" is located in the West-North-West sector and no longer participates in the REMP program. However, the location still maintains a potential for a garden. In the category of closest milk locations, one new goat location was identified North sector. All milk locations identified are not used for human consumption. There were two changes in the category of closest meat locations in 2003.

See Table 12 for these changes. 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 2003 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) (meters) Group Organ Ingestion WVNW 303.5 1103 Child thyroid (vegetation) 31

Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport 2003 LAND USE CENSUS Closest Residences Table 9 l l Distance Change Year Sector I Azimuth (decrees) (meters) (meters) I 2002 NE 34.7 1773 2003 NE 34.7 1773 2002 NNE 11.2 1646 2003 NNE 11.2 1646 2002 N 7.7 1776 2003 N 7.7 1776 2002 NNW 332.8 1743 2003 NNW 332.8 1743 2002 NW 309.9 1700 2003 NW 309.9 1700 2002 (a) WNW 303.5 1103 2003 WNW 303.5 1103 2002 NNI 258.3 1861 2003 W 258.3 1861 2002 WSW 238.2 2547 2003 WSW 238.2 2547 2002 SW 230.3 2025 2003 SW 230.3 2025 2002 SSW 200.4 1826 2003 SSW 200.4 1826 2002 S 170.0 1640 2003 S 170.0 1640 ESE-SSE Lake Erie (a) = Location of "maximum exposed individual" 32

Fermi 2 - 2003 Annual Radioactiv'e Elffluent Release and RadiologicalEnrironmentalOperatingReport 2003 LAND USE CENSUS Closest Gardens Table 10 Distance Chanoe l I Year Sector l Azimuth (derees) (metrs) (meters) l 2002 NE 39.7 3200 2003 NE 39.7 3200 0 2002 NNE 30.6 2894 2003 NNE 30.6 2894 0 2002 N 0.54 2633 2003 N 0.54 2633 0 2002 NNW 327.0 2256 2003 NNW 333.2 4107 +1851 2002 NW 325.0 2179 2003 NW 323.4 4436 +2257 2002 WNW 303.5 1103 2003 WNW 300.2 2936 +1833 2002 ' 269.0 5130 2003 W 267.0 2748 -2382 2002 WSW 247.0 4740 2003 WSW 250.7 3845 -895 2002 SW 234.1 7066 2003 SW 233.9 7062 -4*

2002 SSW 194.9 2463 2003 SSW' 195.9 2414 -49*

2002 S None 2003 S None NA ESE- SSE Lake Eric

(*) = Same location better GPS data.

33

Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEn vironmental OperatingReport 2003 LAND USE CENSUS Milk Locations Table 11 Distance Type/Changc Year Sector Ya Azimuth (degrees) (meters)

Ditac Type/Change 2002 NE None 2003 NE None N/A 2002 NNE None 2003 NNE None N/A 2002 N None Goat 2003 N 1.1 2899 N/A 2002 NNW None 2003 NNW None N/A 2002 NW 310.5 5874 Cow/Goat 2003 NW 310.5 5874 0 2002 WNW 301.0 3672 Goat 2003 WNW 301.0 3672 0 2002 W None 2003 W None N/A 2002 W'SW None 2003 WN'SW None N/A 2002 SW None 2003 SW None N/A 2002 SSW None 2003 SSW None N/A 2002 S None 2003 S None N/A ESE- SSE Lake Erie N/A 34

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmenial OperatingReport 2003 LAND USE CENSUS Closest Meat Locations Table 12 Distance Type/Change I IYear Sector I Azimuth (degrees) I (meters) (meters) I 2002 NE None 2003 NE None N/A 2002 NNE None 2003 NNE None N/A 2002 N 1.1 2899 Beef 2003 N None N/A 2002 NNW None Sheep 2003 NNW 338.4 7079 N/A 2002 NW 319.5 5225 Sheep 2003 NW 319.5 5225 0 2002 WNW 285.6 2602 Beef 2003 WNW 285.6 2602 0 2002 W None 2003 W None N/A 2002 WSW None Beef 2003 WSW 248.8 4734 N/A 2003 SW None 2003 SW None N/A 2002 SSW None 2003 SSW None N/A 2002 S None 2003 S None N/A ESE- SSE Lake Erie N/A 35

Appendix A Sampling Locations

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnrironmental OperatingReport D~irect Radiation Sample Locations Table A-I Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrecs) (Approx.) Description Frequency Type TI NE/39 0 1.3 mi. Estral Beach, Polc on Q Lakeshore 23 Poles S of Lakeview (Special Area)

T2 NNI:Y220 1.2 mi. East of termination of Q Brancheau St. on post (Special Area)

T3 N/9 0 1.1 mi. Pole, NW corer of Swvan Q I Boat Club fence (Special Area)

T4 NNN\W/337 0 0.6 mi. Site boundary and Toll Rd. Q I on Site fenc hbAPI #2 T5 NW/3 130 0.6 mi. Site boundarv and Toll Rd. Q I on Site fence by API #3 T6 WNW/294 0 (1.6 mi. On Site fence at south end Q I of N. Bullit Rd..

T7 W/2700 14.0 mi. Pole, at Michigan Gas Q C substation on N. Custer Rd., 0.66 miles west of Doty Rd.

T8 NNN/305 0 1.9 mi. Pole on Post Rd. near NE Q I corner of l)ixie Hwy. and Post Rd.

T9 NNW/334 0 1.5 mi. Pole, NW cornr of Q I Tromblcy and Swan View Rd.

TIO N/60 2.1 mi. Pole, S side of Massarant- Q I 2 poles W of Chinavare.

I = Indicator C = Control 0 = On-site Q = Quarterly A-l

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironimentalOperatingReport D)irect Radiation Sample locations (Table A-] continued)

Meteoroloical Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) I)escription Frequencv Type TI I NNE/23 0 6.2 mi. Pole, NE corner of Q Milliman and Jcffcrson Tl2 NNEF29" 6.3 mi. Pointe Mouille Game Area Q F:ield Office, Pole near tree, N area of parking lot T13 N/356 0 4.1 mi. Labo and I)ixie Hwv. Pole Q on SW corner with light T14 NNW/337 0 4.4 mi. Labo and Brandon Pole on Q SE corner near RR T15 NWV/3 150 3.9 mi. Pole, behind buildinaa Qat the corner of Swan Creek and Mill St..

T16 NVNW/283 0 4.9 mi. Pole, SE corner of War and Q Post Rd.

T17 W/271° 4.9 mi. Pole, NE cornr of Nadeau Q and Laprad near mobile home park.

0 TI NNVSWN/247 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 corner of intersection - Sterling State Park Rd. Entrance Drivc/Watcrworks T20 WSWN'/257 0 2.7 mi. Pole, S side of Williams Q Rd, S poles W of l)ixie Hwy. (Special Area)

T21 XWSWV/239 0 2.7 mi. Pole, N side of Pearl at Q Parkview Woodland Beach (Special Area)

I = IndicaJor C = Control 0 = On-site Q = Quarterl A-2

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport Direct Radiation Sample Locations (Table A-I continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Dcscription }Frequency Typc T22 S/172° 1.2 mi. Pole, N side of Pointe Aux Q Pcaux 2 poles W'of L)ne -

Site BoundarN T23 SSW/195 0 1.1 mi. Pole. S side of Pointe Aux Q Peaux I pole WV of Huron next to Vent Pipe - Site Boundarv 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 orf ermi Drive T26 WSW/259 0 1.1 mi. Pole, Toll Rd. - 6 poles S Q of Fermi l)rive T27 SNN/225 0 6.8 mi. Pole, NE corner of Q McMillan and East Front St. (Special Area)

T28 SU'/229° 10.7 mi. Pole, SE corner of Mortar Q C Creek and LaPlaisance.

0 T29 W'SW/237 10.3 mi. Pole. E side of S I)ixie, I Q C pole S of Albain.

T30 WSW/2470 7.8 mi. Pole, St. Mary's Park Q I corner of lIlm and Monroe St., S side of parking lot next to river (Special Area)

T.3 I WSW/255 0 9.6 mi. Ist pole ' of entrance Q C drive Milton "'at" Munson Recreational Reserve on North Custer Rd.

I = Indicator C = Control 0 = On-site Q = Quarterly A-3

Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental Operating Report DirectRadiation Sample Locations (Table A-I continued)

Meteorological Oistance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T32 NVNW/295 0 10.3 mi. Pole, comer of Stony Creek Q I and IFinzel Rd.

T33 NW1/3170 9.2 mi. Pole, W side of Grafton Q I Rd. I pole N of Ash and Grafton intersection.

T34 NNW/338 0 9.7 mi. Pole, W side of Port Creek, Q I I pole S of Will-Carleton Rd.

T35 N/3590 6.9 mi. Pole, S Side of S lluron Q I River Dr. across from Race St. (Special Area)

T36 N/3580 9.1 mi. Pole, NE comer of Q I Gibraltar and Cahill Rd.

T37 NNEI/2 I 9.8 mi. Pole, S corner of Adams Q I and Gibraltar across from Humbug Marina.

T38 WNW/294 0 1.7 mi. Residence - 6594 N. I)ixie Q I Hwy.

T39 S/1760 0.3 mi. SE comer of Protected Q 0 Area Fence (PAP).

T40 S/1700 0.3 mi. Midway along OBA - Q 0 (PAF)

T41 SSE/161 0 0.2 mi. Midway between OBA and Q 0 Shield Wall on PAIP.

T42 SSI;/1490 0.2 mi. Midway along Shield Wall Q 0 on PAF.

T43 SE/1310 0.1 mi. Midway between Shield Q 0 Wall and Aux Boilers on PAF.

T44 ESE11(090 0.1 mi. Opposite OSSl door on Q 0 PAF.

I = Indicator C = Control 0 = On-site Q = QuarterlY A-4

Fermi 2 - 2003 Annual Radioactive E~ffluent Release and RadiologicalEinvironmental Operating Report Direct Radiation Samnple locations (Table A-l continuied)

Metcorological D)istancc Station Scctor/Azimuth from Reactor Collection Numbcr (Degrees) (Approx.) Description Frequcncy Tvpc T45 FJ86 0 0.1 mi. NE Corner of PA. Q 0 T46 FNE/67 0 0.2 mi. NE side of barge slip on Q 0 fence.

T47 S/185° 0. mi. South of Turbine Bldg. Q 0 rollup door on PAP:.

T48 SW/235 0 0.2 mi. 30 ft. from conner of AAP Q 0 on PAF.

T49 WSW/251 I] mi. Corner of Site Boundary Q I fence north of NOC along Critical Path Rd.

T50 W/270 0 0.9 mi. Site Boundary fence near Q I main gate by the south Bullit Street sign.

T51 N/3° 0.4 mi. Site Boundary fence north Q 0 of north Cooling Tower.

T52 NNFH20( 0.4 mi. Site Boundary fence at the Q 0 conner of Arson and Tower.

T53 NF550 0.2 mi. Site Boundary fence cast of Q 0 South Cooling Tower.

T54 S/f 890 0.3 mi. Pole next to Fermi 2 Q 0 Visitors Center.

T55 WSW/251 0 3.3 mi. Pole, north side of Nadcau 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.

I = Indicator C = Control O = On-site Q = Quarterly A-5

Fermi 2 - 2003 Annual Radioactire l'ffluent Release and RadiologicalEmn-ironmental OperatingReport D)irect Radiation Sample Locations (Table A-I continued)

Mcteorological Distance Station Sector/Azimuth from Reactor Collcction Number (Dcegres) (Approx.) Dcscription Frequency Type T57 W/260 0 2.7 mi. Pole, north side of Q Williams Rd. across from Jcfferson High School entrance.

T58 WSW/249 0 4.9 mi. Pole west of l-urd Q I Elementary School Marquee T59 NW/3250 2.6 mi. Pole north of St. Charles Q I Church entrance on Dixie Hlwy.

T60 NNW/34 10 2.5 mi. I st pole north of North Q I Elementary School entrance on Dixie Hwyv.

0 Q I T61 NN7/268 10(.1 mi. Pole, SW cornerof Stewart and Raisinville Rd.

T62 SW/232 0 9.7 mi. Pole, NE corner of Alhain Q I and Hull Rd.

T63 USW/245 0 9.6 mi. Pole, NE corner of )unbar Q I and Telegraph Rd.

T64 WNW/286 0 0.2 mi. West of switchaear vard on Q 0 PAI T65 NNV/322 0 0.1 mi. PAF switchgear yard area Q 0 NW of RHR complex.

T66 N-/50° 0.1 mi. Behind 131dg. 42 on PAF Q 0 T67 NNNV/338 0 0.2 mi. Site Boundary fence West Q 0 of South Cooline Tower.

I = Indicator C = Control O = On-site Q = Quarterl A-6

Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport Air Particulateand Air Iodine Sample Locations Table A-2 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type API-I 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/313 0 0.6mi. SiteBoundaryandToll W I Road, on Site Fence by T-5 API-4 W/2700 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 corner of Pointe W I 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/3190 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

Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport 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-S 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/80 18.5 mi. Detroit Water Station M C 14700 Moran Rd, Allen Park I = Indicator C = Control M = Monthly A-8

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport Surface Water Sample Locations Table A-6 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type SW-2 NNE/200 11.7 mi. DECo's Trenton Channel M C Power Plant Intake Structure (Screenhouse #1)

SW-3 SSE/1600 0.2 mi. DECO's Fermi 2 General M I Service Water Intake Structure I = Indicator C = Control M = Monthly GroundwaterSample Locations Table A-7 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type GW-I S/1750 0.4 mi. Approx. 100 ftWof Lake Q I Erie, EF-l Parking lot near gas fired peakers GW-2 SSW/208 0 1.0 mi. 4 ft S of Pointe Aux Peaux Q I (PAP) Rd. Fence 427 ft W of where PAP crosses over Stoney Point's Western Dike GW-3 SNV/226 0 1.0 mi. 143 ft W of PAP Rd. Gate, Q I 62 ft N of PAP Rd. Fence GW-4 WNW/2990 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

Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport Sediment Sample Locations Table A-8 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type S-I SSEI1650 0.9 mi. Pointe Aux Peaux, SA I Shoreline to 500 ft offshore sighting directly to Land Base Water Tower S-2 E/8 1 0.2 mi. Fermi 2 Discharge, approx. SA I 200 ft offshore S-3 NE1390 1.1 mi. Estral Beach, approx. 200 SA I ft offshore, off North shoreline where Swan Creek and Lake Erie meet S-4 WSW/2410 3.0 mi. Indian Trails Community SA I Beach S-5 NNE/200 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/310 9.5 mi. Near Celeron Island SA C F-2 E/860 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 - I SAMPLING LOCATIONS N

BY STATION NUMBER WITHIN 1 MILE LEGEND o T- DIRECT RADIATION I O API- AIR PARTICULATES/AIR IODINE A S- SEDIMENTS L DW/SW- DRINKING WATER/SURFACE WATER

] GW- GROUND WATER o 0.5 E M- MILK E FP- FOOD PRODUCTS

F- FISH SCALE IN MILES

MAP - 2 SAMPLING LOCATIONS N

BY STATION NUMBER (1 To 5 MILES)

LEGEND N

o T- DIRECT RADIATION O API- AIR PARTICULATES/AIR IODINE A. S- SEDIMENTS n DW/SW- DRINKING WATER/SURFACE WATER E GW- GROUND WATER 0 1 o M- MILK Z FP- FOOD PRODUCTS

F- FISH SCALE IN MILES

MAP - 3 SAMPLING LOCATIONS N

BY STATION NUMBER (GREATER THAN 5 MILES)

LEGEND

T- DIRECT RADIATION O API- AIR PARTICULATES OR AIR IODINE

S- SEDIMENTS

. DW/SW- DRINKING WATER/SURFACE WATER 5 0 5 10 IE]GW- GROUND WATER El M- MILK fl FP- FOOD PRODUCTS SCALE IN MILES

F- FISH

Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport Appendix B Environmental Data Summary

Fermi2 - 2003 Annual Radioactive rEffluent Release and RadiologicalEnvironmentalOperatingReport Table B-I Radiological Environmental Monitoring Program Summary Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2003 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

- -; Location t; Wit

'Highest

'SaplInType .Ty ' aal dicalory A' Mean ; *` ', Co ntrol,;.' Nbbeo (Unts) -' ffibe o' - L-ocatios: ': LcationsN outin

___r___-____1___' Anal 'itD R ean and Range ,

edis'i' a a Meand Raiie Results Direct Radiation Gamma (TLD) 1.0 15.2 (179/179) T-49 (Indicator) 19.5 (4/4) 14.7 (16/16) None mRfstd qtr 195 10.5 to 22.2 15.6 to 22.2 12.3 to 16.2 Airborne Gross Beta 255 I.OOE-2 2.51E-2 (205/205) API-I (Indicator) 2.63E-2 (52/52) 2.48E-2 (50/50) None Particulates I.IOE-2 to 5.46E-2 1.24E-2 to 5.46E-2 1.1013-3 to 5.4313-2 pCi/cu. m. Gamma Spec. 20 Be-7 N/A 9.48E-2 (12/16) API-2 (Indicator) 9.87E-2 (3/4) 9.1313-2 (4/4) None 7.5013-2 to 1.1413-1 7.5013-2 to 1.1413-1 7.20E-2 to 1.14E-I K-40 N/A <MDA <MDA None Mn-54 N/A <MDA <MDA None Co-58 N/A <MDA <MDA None Fc-59 N/A <MDA <MDA None Co-60 N/A <MDA <MDA None Zn-65 N/A <MDA <MDA None Zr-95 N/A <MDA <MDA None Ru- 103 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs- 134 5.0013-2 <MDA <MDA None Cs- 137 6.00E-2 <MDA <MDA None Ba-140 N/A <MDA <MDA None La- 140 N/A <MDA <MDA None Cc-141 N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None Airborne Iodine 1-131 255 7.00E-2 <MDA <MDA None pCi/cl. m.

B-I

Fermi2 - 2003 Annual Radioactive rEffluent Release and RadiologicalE~nvironmental OperatingReport Table 13-1 Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2003 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

.:v- .. ti; - n r --.; ;.:. ^Location with Highest Sampl Ty ; Typ and ; . - l Annua Meann' 'N t r r of (Units) -,., Number of, 'i

'ca ' "ons- ocations, No,-r.. -ne..

.Anlyss

LL Mean and Range, Lca ion MenadRnge MaiadRne .>J'sls Milk 1-131 36 I.OOE+O <MDA <MDA None pC2/1 Sr-89 36 N/A <MDA <MDA None Sr-90 N/A 2.06E+0 (2/18) M-2 (Indicator) 2.06E+0 (2/18) 5.30E-1 (1/18) None 1.89E+0 to 2.22E+0 1.89E+0 to 2.22E+O Gamma Spec. 36 Be-7 N/A <MDA <MDA None K-40 N/A 1.39E+3 (18/18) M-2 (Indicator) 1.39E+3 (18/18) 1.38E+3 (18/18) None 1.26E+3 to 1.53E+3 1.26E+3 to 1.53E+3 1.26E+3 to 1.47E+3 Mn-54 N/A <MDA <MDA None Co-58 N/A <MDA <MDA None Fe-59 N/A <MDA <MDA None Co-60 N/A <MDA <MDA None Zn-65 N/A <MDA <MDA None Zr-95 N/A <MDA <MDA None Ru-103 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 I.SOE+1 <MDA <MDA None Cs-137 1.80E+1 <MDA <MDA None Ba-140 1.SOE+I <MDA <MDA None La-140 1.SOE+l <MDA <MDA None Ce-141 N/A <MDA <MDA None Cc-144 N/A <MDA <MDA None Vegetation 1-131 11 6.00E+1 <MDA <MDA None pCi/kg ivet Gamma Spec. 11 13e-7 N/A <MDA FP-9 (Control) 6.10E+2 (1/5) 6.10E+2 (1/5) None K-40 N/A 2.58E+3 (6/6) FP-9 (Control) 3.90E1+3 (5/5) 3.90E+3 (5/5) None I.09E+3 to 3.79E+3 I _I 1.99E+3 to 5.99E+3 1.99E+3 to 5.99E+3 B-2

Fermi 2 - 2003 Annual Radioactive lffluent Release and RadiologicalEnrironmentalOperatingReport Table B-i Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2003 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township) r,, . S . i- ' Ind r ; With Highest Location

- , C l N-m-cr or

-. Saniple Type ndltdcaor'onr:Men mye (Units) . -'Number of, L. Locations'aL o N rOu irtc

__p___._:_';___ Analysis M and ange' ' ocaionMea ad ange Mean and Range' . Resits O

Vegetation Mn-54 N/A <MDA <MDA None (cont.) Co-58 N/A <MDA <MDA None pCi/kg ivet Fe-59 N/A <MDA <MDA None Co-60 N/A <MDA <MDA None Zn-65 N/A <MDA <MDA None Zr-95 N/A <MDA <MDA None Ru-103 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 6.0011+1 <MDA <MDA None Cs- 137 8.001+1 <MDA <MDA None Ba-140 N/A <MDA <MDA None La-140 N/A <MDA <MDA None Ce-141 N/A <MDA <MDA None Cc-144 N/A <MDA <MDA None Drinking Water Gross Beta 24 4.00F+0 3.79E+0 (6/12) DW-I (Indicator) 3.79E+0 (6/12) 3.29E+0 (6/12) None pCi/ 3.601E+0 to 4.201E+1 3.60E+0 to 4.20E+l 2.86E+0 to 4.37E+O Sr-89 24 N/A <MDA <MDA None Sr-90 N/A <MDA <MDA None Gamma Spec. 24 1Be-7 N/A <MDA <MDA None K-40 N/A <MDA <MDA None Cr-SI N/A <MDA <MDA None Mn-54 1.501S+1 <MDA <MDA None Co-58 1.501S+1 <MDA <MDA None Fe-59 3.0011+1 <MDA <MDA None Co-60 1.501S+1 <MDA <MDA None Zn-65 3.0011+1 <MDA <MDA None Zr-95 1.5011+1 <MDA <MDA None B-3

Fermi 2 - 2003 Annual Radioactive Fffluent Release and RadiologicalEnvironmentalOperatingReport Table B-I Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2003 Location or Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

Location with Highest

'SamplTp 'e 'iTpe'nd"' : ' Indicator ' .Anndal -¢ Mean- "'" 'Control.' N.

.: of ' LO I ' -- . ' - - *'-f '(Units)

" lNumber

'ocations ' 6-ro tit';.

__-_-a-______' Analysts: ." ~ 'LLD Mean and Range ' oca'lige Mean' and Ra'e' Man and RaRge Rsuits '-'

Drinking Water Ru-103 N/A <MDA <MDA None (cont.) pCi/i Ru-106 N/A <MDA <MDA None Cs-134 I.50E+I <MDA <MDA None Cs-137 1.80E+1 <MDA <MDA None Ba-140 I.50E+I <MDA <MDA None La-140 I.50E+1 <MDA <MDA None Ce-141 N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None H-3 8 2.OOE+3 <MDA <MDA None Surface Water Sr-89 24 N/A <MDA <MDA None pCi/l Sr-90 N/A <MDA <MDA None Gamma Spec. 24 Be-7 N/A <MDA <MDA None K40 N/A ' <MDA <MDA None Cr-51 N/A <MDA <MDA None Mn-54 I.50E+I <MDA <MDA None Co-58 I.50E+l <MDA <MDA None Fe-59 3.OOE+l <MDA <MDA None Co-60 I'.50E+I <MDA <MDA None Zn-65 3.OOE+I <MDA <MDA None Zr-95 I.50E+I <MDA <MDA None Ru-103 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 I.50E+I <MDA <MDA None Cs-137 1.80E+l <MDA <MDA None Ba-140 I.50E+I <MDA <MDA None La-140 I.50E+I <MDA <MDA None Ce-141 N/A <MDA <MDA None B-4

Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport Table B-I Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2003 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

- ' . dicaor . 'I.' ' Location with Highest Sar pe T pe" :.' Type and - t; al Mea i ': . 'A ' Control N (Units) ' -,' Number of i* Locations .- ' ' ' , ' atons 0 N

. Anai s

- ' L' Meanand kane ' '"ocatioa ' Mean and Range' Mean an(d ang 'Resbls Surface Water Ce-144 N/A <MDA <MDA None (cont.) pCi/l H-3 8 2.OOE+3 <MDA <MDA None Groundwater Gamma Spec. 16 pCi/I Be-7 N/A <MDA <MDA None K-40 N/A <MDA <MDA None Cr-51 N/A <MDA <MDA None Mn-54 1.50E+I <MDA <MDA None Co-58 I.50E+1 <MDA <MDA None Fe-59 3.00E+1 <MDA <MDA None Co-60 1.50E+l <MDA <MDA None Zn-65 3.00E+I <MDA <MDA None Zr-95 I.50E+I <MDA <MDA None Ru-103 N/A <MDA <MDA None Ru- 106 N/A <MDA <MDA None Cs-134 1.50E+I <MDA <MDA None Cs-137 1.80E+I <MDA <MDA None Ba-140 I.50+I <MDA <MDA None L~a-140 I.50E+I <MDA <MDA None Ce-141 N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None H-3 16 2.00E+3 <MDA <MDA None 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 S-5 (Control) 2.96E+2 (1/2) 2.96E+2 (1/2) None K-40 N/A 1.12E+4 (8/8) S-1 (Indicator) 1.25E+4 (2/2) 1.06E+4 (2/2) 8.10E+3 to l.50E+44 9.92E+3 to 1.50E+4 9.59E+3 to 1.16E+4 None B-5

Fermi 2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport Table B-I Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2003 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

-, -. , * , -- . icalor ' . ~fLocation With Highest: , r ,

SapeTp Tp and ,. Iniao V Annual Mean - .... w Control mbrf

-(uits) m'ber;of . . Lations- . Lot ii ns Non n-rotl

________ Aa Y~sl> LLD, Mean and angeLcaoncatndRge -MnndRne - isiI Sediment (cont.) Mn-54 N/A <MDA <MDA None pCi/kg dry Co-58 N/A <MDA <MDA None Fe-59 N/A <MDA <MDA None Co-60 N/A <MDA <MDA None Zn-65 N/A <MDA <MDA None 7r-95 N/A <MDA <MDA None Ru-103 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs- 134 I.50E+2 <MDA <MDA None Cs-137 1.80E+2 9.20E+1 (2/8) S-l (Indicator) I.05E+2 (1/2) 6.26E+l (2/2) None 7.90E+1 to 1.05E+2 4.91E+ Io 7.60E+I Ba-140 N/A <MDA <MDA None La-140 N/A <MDA <MDA None Ce-141 N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None Fish Sr-89 29 N/A <MDA <MDA None pCi/kg ivet Sr-90 N/A <MDA <MDA None Gamma Spec. 29 Be-7 N/A <MDA <MDA None K-40 N/A 2.75E+3 (12/12) F-I (Control) 2.90E+3 (10/10) 2.79E+3 (17/17) None 1.62E+3 to4.1OE+3 2.06E+3 to3.81E+3 1.96E+3 to4.71E+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 - 2003 Annual Radioactive Eiffluent Release and RadiologicalEnvironmentalOperatingReport Table B-I Radiological Environmental Monitoring Program Summary (cont.)

Name or Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2003 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

-. .-,,,Location with Highest^'

amplehType T;ype ad ndicalontrol' - N;ritaer of (Units) NUmber of, , ocd ;o ' ' Locations ; oh-rou te

-'.Analysis- D Mean and Range Locadon Mand Mean and Range esu ss Fish (cont.) Zr-95 N/A <MDA <MDA None pCi/kg Vet Ru-103 N/A <MDA <MDA None Ru- 106 N/A <MDA <MDA None Cs-134 1.3013+2 <MDA <MDA None Cs- 137 1.50E+2 3.70E+I (1/12) F-2 (Indicator) 3.70E+1 (1/12) <MDA None Ba-140 N/A <MDA <MDA None La-140 N/A <MDA <MDA None Cc-141 N/A <MDA <MDA None Cc-144 N/A <MDA <MDA 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 (D).

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

Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 TLD ANALYSIS (mR/Std Qtr)

STATION SSECOND - THRD FOURTH NUMBER -'QUARTER -.--QUARTER. QUARTER .-QUARTER T-1 12.71 13.01 14.28 16.91 T-2 15.33 15.86 17.20 18.06 T-3 10.49 11.04 12.37 12.54 T-4 13.55 14.32 15.60 16.32 T-5 14.26 15.16 16.72 16.38 T-6 13.90 14.84 16.39 16.23 T-7 12.33 13.52 15.22 14.29 T-8 15.29 16.10 17.24 17.39 T-9 13.15 15.17 16.17 16.07 T-10 13.77 14.85 16.90 17.24 T-1 1 12.93 13.17 20.50 14.31 T-12 12.12 13.02 13.79 14.34 T-13 13.88 16.54 16.57 16.70 T-14 15.30 15.62 17.11 16.53 T-15 12.74 13.51 14.29 14.18 T-16 15.98 18.02 19.41 18.71 T-17 11.64 12.80 13.36 12.55 T-18 13.16 13.62 15.37 17.24 T-19 14.45 16.36 17.26 16.78 T-20 15.40 17.47 18.58 19.06 T-21 12.01 13.56 14.36 14.72 T-22 13.13 13.52 14.28 15.96 T-23 13.12 14.52 15.36 15.11 T-24 11.94 12.33 14.26 15.08 T-25 15.94 17.26 18.17 18.50 T-26 16.91 16.76 17.72 17.56 T-27 11.29 12.13 14.09 12.44 T-28 13.66 14.43 15.62 15.87 T-29 13.67 14.75 15.53 15.76 T-30 13.94 14.50 16.00 16.45 T-31 13.22 14.65 16.23 15.99 T-32 15.04 14.42 16.71 16.12 T-33 12.47 12.61 14.00 13.83 T-34 12.93 13.75 14.65 14.51 T-35 12.87 14.03 14.45 15.21 T-36 14.35 13.83 16.43 15.90 T-37 21.01 14.47 15.94 16.09 T-38 15.07 15.99 16.61 17.33 T-39 58.74 42.79 54.63 64.55 T-40 50.31 36.81 44.64 53.30 T-41 80.27 58.41 76.29 92.64 T-42 76.26 58.75 76.61 94.16 T-43 89.59 63.50 84.90 103.05 T-44 80.65 56.50 76.12 91.18 T-45 50.55 39.33 49.42 57.69 T-46 36.21 31.57 37.13 41.16 T-47 77.64 53.33 72.04 93.76 C-l

Ferni2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 TLD ANALYSIS (CONT.)

(mRIStd Qtr)

STATION: FIRST iSECOND THIRD "FOURTH:_

NUMBER QUARTER ; QUQUARTEQUARTER QUARTER T-48 40.68 31.64 41.70 47.58 T-49 15.63 .18.77 22.15 21.31 T-50 14.09 15.36 15.43 16.60 T-51 10.24 11.17 12.40 13.53 T-52 13.63 13.72 15.45 16.93 T-53 22.27 21.47 24.80 27.91 T-54 16.88 14.84 17.52 19.33 T-55 13.97 14.93 16.08 16.91 T-56 13.13 14.19 15.39 15.00 T-57 15.90 17.14 18.96 19.07 T-58 12.03 13.55 14.30 (a)

T-59 12.26 13.25 14.45 14.26 T-60 14.06 15.24 15.93 16.89 T-61 14.52 15.86 16.73 17.29 T-62 14.22 15.82 17.30 17.34 T-63 12.45 13.81 15.03 14.86 T-64 19.53 18.15 22.37 24.46 T-65 22.64 19.73 24.62 27.30 T-66 124.09 84.47 112.61 141.44 T-67 16.55 16.47 18.36 20.18 (a) TLD missing, see Appendix D - Program Execution.

C-2

Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-1 FIRST QUARTER T;"

,nt - -- AirtMty t I1 in//2003 2.21E-02 +1- 12.10E-03 1/14/2003 2.46E-02 +1- 12.30E-03 1/21/2003 2.79E-02 + 2.40E-03 1/28/2003 2.1 0E-02 +1- 12.20E-03 2/4/2003 2.62E-02 +- 12.50E-03 2/11/2003 2.92E-02 +1- 12.50E-03 2/18/2003 1.90E-02 +1- 2.20E-03 2/25/2003 3.17E-02 +I- 2.50E-03 3/4/2003 3.1 1E-02 +1- 2.40E-03 3/11/2003 3.10E-02 +I2.50E-03 3/18/2003 2.52E-02 +/- 2.50E-03 3/25/2003 2.12E-02 +- 12.20E03 API-1 SECOND QUARTER 7DiA6e I' ~ -. Activity '"`,

4/1/2003 2.3 8E-02 +/- 2.40E-03 4/8/2003 2.25E-02 +/- 2.50E-03 4/15/2003 2.16E-02 +/- 2.30E-03 4/22/2003 1.57E-02 +/- 2.30E-03 4/29/2003 2.05E-02 +/- 2.50E-03 5/6/2003 1.26E-02 +/- 2.50E-03 5/13/2003 1.24E-02 +/- 2.40E-03 5/20/2003 1.36E-02 +/- 1.90E-03 5/27/2003 1.4 IE-02 +/- 2.30E-03 6/3/2003 1.5 1E-02 +/- 2.1OE-03 6/10/2003 1.77E-02 +/- 2.20E-03 6/17/2003 1.89E-02 +1- 2.30E-03 6/24/203 2.51E-02 +/- 2.30E-03 C-3

Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-1 THIRD QUARTER I -'<-2 -

i.-I ' --- I At-

~,.; xv-

~ ,,: - I~~-

7/1/2003 3.11E-02 +1- 12.40E-03 7/8/2003 3.66E-02 +1- 2.60E-03 7/15/2003 2.41E-02 +/- 12.20E-03 7/22/2003 2.46E-02 +1- 12.30E-03 7/29/2003 2.95E-02 +1- t2.40E-03 8/5/2003 3.59E-02 +1- l2.50E-03 8/12/2003 1.87E-02 +1- j2.20E-03 8/19/2003 2.9 8E-02 +1- 3.20E-03 8/26/2003 5.46E-02 +1- 4.90E-03 9snn03 2.69E-02 +/- 2.40E-03 9/9/2003 2.89E-02 +/- 2.30E-03 9/16/2003 3.91E-02 +/- 2.50E-03 9/23/2003 3.41E-02 +/- 2.50E-03 9/30/2003 1.89E-02 +/- 2.20E-03 API-1 FOURTH QUARTER

- 'Date - I< l .Activity:

10n72003 1 .87E-02 -2.20E-03 10/14/2003 5.22E-02 82.80E-03 10/21/2003 2.57E-02 +/- 12.40E-03 10/28/2003 2.12E-02 2.20E-03 11/4/2003 3.46E-02 2.50E-03 11/11/2003 3.32E-02 +1- 2.40E-03 11/18/2003 3.16E-02 +1- 2.40E-03 11/25/2003 2.53E-02 +1- 2.40E-03 12/2/2003 3.56E-02 +- 2.50E-03 12/9/2003 1.70E-02 +1- 12.30E-03 12/16/2003 3.26E-02 +/- l2.40E-03 12n23/2003 3.20E-02 +/- 12.40E-03 12130/2003 3.07E-02 +/- 12.50E-03 C-4

Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-2 FIRST QUARTER lDae < - - J ActiVity --

I//2003 2.73E-02 +1- 12.20E-03 1/14/20031 1.98E-02 +1- 2.30E-03 112112003 3.15E-02 +1- l2.50E-03 1/28/2003 2.29E-02 +1- 2.40E-03 2/4/2003 3.45E-02 +1- 12.70E-03 2/11/2003 2.55E-02 +1- l2.50E-03 2/1812003 2.33E-02 +1- 2.40E-03 212512003 3.12E-02 +1- 2.50E-03 3/412003 3.77E-02 +1- 2.60E-03 3/1112003 3.54E-02 +1- 2.70E-03 3/1812003 2.61E-02 +1- 2.60E-03 312512003 2.10E-02 +1- 2.40E-03 API-2 SECOND QUARTER

'Date- 0:2 1.8E---

4/112003 1.53E-02 +1- 1.80E-03 4/812003 1.43E-02 -i-- 1.80E-03 4/1512003 2.19E-02 +1- 2.50E-03 412212003 2.34E-02 +1- 2.50E-03 412912003 2.24E-02 +I- 2.50E-03 5/612003 1.37E-02 +1- 2.50E-03 5/1312003 1.49E-02 +1- 2.40E-03 512012003 1.31E-02 +1- 2.1 OE-03 512712003 1.80E-02 +/- 2.40E-03 61312003 1.54E-02 +/- 2.20E-03 6/1012003 1.94E-02 +/- 2.20E-03 6/1712003 1.61E-02 +1- 2.10E-03 6/2412003 1.98E-02 +/- 2.20E-03 C-S

Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-2 THIRD QUARTER Dat t '--Activitv. .

7/1/2003 !

3.25E-02 +1- 2.40E-03 7/8/2003 3.13E-02 +1- I2.40E-03 7/15/2003 2.21E-02 +1- I2.20E-03 712212003 2.29E-02 1I-2.30E-03 7129/2003 2.44E-02 +1- 12.30E-03 8/512003 2.62E-02 +1- 12.30E-03 8/12/2003 2.04E-02 12.30E-03 8/1912003 2.60E-02 +1- 3.20E-03 8/2612003 3.64E-02 +1- 2.50E-03 91212003 2.46E-02 +1- 12.30E-03 9/912003 2.63E-02 +1- 2.30E-03 9/1612003 3.9 1E-02 +1- 2.50E-03 912312003 2.43E-02 +/-J12.30E-03 9/30/2003 2.10E-02 12.20E-03 API-2 FOURTH QUARTER l[<,>Date . > . -"t*

7Activity I,,a 10720031 1.48E-02 +/- 12.20E-03 10/1412003 4.23E-02 +/1 12.70E-03 1012112003 2.39E-02 +/- 12.30E-03 1012812003 1.80E-02 12.10E-03 11/412003 2.61E-02 +1- 2.40E-03 11/1112003 2.88E-02 +/- l2.30E-03 11/1812003 2.82E-02 +/-l2.30E-03 11125/2003 2.53E-02 +/- 12.40E-03 121212003 3.40E-02 +1- 12.50E-03 121912003 1.21E-02 12I2E-03 12/1612003 3.03E-02 1+-

2.40E-03 1212312003 3.19E-02 +1- 2.40E-03 12/3012003 3.13E-02 +1- 12.60E-03 C-6

Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-3 FIRST QUARTER l;Date 1 4;

-. A~ctiiity:;-'

n/7o2003 2.58E-02 +1- f2.20E-03 1/14/2003 2.50E-02 +1- 12.40E-03 1/21/2003 2.36E-02 +1- 2.50E-03 1/28/2003 2.1 IE-02 +1- 2.10E-03 2/4/2003 3.06E-02 +1- 2.40E-03 2/11/2003 2.70E-02 +1- 2.30E-03 2/18/2003 2.22E-02 +1- 2.20E-03 2125/2003 3.4 1E-02 +1- 2.40E-03 3/4/2003 3.53E-02 -I- 2.50E-03 3/11/2003 3.15E-02 +1- 2.40E-03 3/18/2003 2.56E-02 +1- f2.40E-03 3/25/2003 2.15E-02 +1- 12.1OE-03 API-3 SECOND QUARTER D-.>atejr I; I7/20031 (a) 1/14/2003 2.50E-02 +/- 2.60E-03 1/2112003 2.72E-02 +/ 2.70E-03 1/28/2003 2.03E-02 +/ 2.30E-03 2/4/2003 3.18E-02 3.60E-03 2/11/2003 5.43E-02 /5.30E-03 2/18/2003 2.67E-02 /240E-03 2/25/2003 2.50E-02 2.30E-03 3/4/2003 3.42E-02 +/ 2.70E-03 3/11/2003 3.10E-02 +/- 2.80E-03 3/18/2003 2.21E-02 +/- 12.30E-03 3/25/2003 2.88E-02 +1- 3.60E-03 API-4 SECOND QUARTER l i,'Date - tivity 4/1/2003 1.59E-02 +12.20E-03 4/8/2003 1.1 OE-02 +12.20E-03 4/15/2003 2.96E-02 +1- 3.30E-03 4/22/2003 2.90E-02 +1 2.90E-03 4/29/2003 3.15E-02 +1 2.90E-03 5/6/2003 1.93E-02 +1 2.40E-03 5/13/2003 1.50E-02 +/ 2.90E-03 5/20/2003 1.70E-02 +1 2.1 OE-03 5/27/2003 1.87E-02 +1 2.30E-03 6/3/2003 1.29E-02 +/ 2.1 OE-03 6/10/2003 1.87E-02 +J 2.30E-03 6/17/2003 1.82E-02 +1 2.20E-03 6/24/2003 2.09E-02 +1 2.30E-03 (a) Sample not collected see Appendix D, Program Execution.

~~C-9~~

~~Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)~~

~~API-4 THIRD QUARTER~~

~~.-- :;Dater ,ttt8.;I 1 ;Z t -~~

~~-, :,,~,: .~~

7/1/2003 2.79E-02 + 12.30E-03 7/8/2003 2.46E-02 +/- 2.30E-03 7/15/2003 2.04E-02 +/ 2.20E-03 7/22/2003 2.04E-02 +/ 2.20E-03 7/29/2003 2.00E-02 +/ (a) 8/5/2003 2.33E-02 3.OOE-03 8/12/2003 1.47E-02 +/- 2.20E-03 8/19/2003 2.22E-02 +/ 3.OOE-03 8/26/2003 3.85E-02 +/ 2.50E-03 9/2/2003 2.28E-02 +/- 2.30E-03 9/9/2003 2.80E-02 +/- 12.30E-03 9/16/2003 3.30E-02 +1-l2.40E-03 9/23/2003 2.33E-02 +1- 2.30E-03 9/30/2003 1.51 E-02 +1- 2.1 OE-03 API-4 FOURTH QUARTER Date - Activitys WIi>

l0/72003 1.22E-02 +/- 12.1 OE-03 10/14/2003 4.68E-02 +/- 12.80E-03 10/21/2003 2.54E-02 +/- 12.30E-03 10/28/2003 1.93E-02 +/- 2.1OE-03 11/4/2003 3.07E-02 +/- 2.50E-03 11/11/2003 3.29E-02 +- 2.40E-03 11/18/2003 3.02E-02 +1- 2.40E-03 11/25/2003 2.17E-02 +/- l2.30E-03 12/2/2003 2.68E-02 +1- 2.40E-03 12/9/2003 1.55E-02 +- 2.30E-03 12/16/2003 2.84E-02 +/ 2.30E-03 12/23/2003 2.72E-02 +/ 2.30E-03 12/30/2003 2.36E-02 +/ 2.50E-03 (a) Sample not collected see Appendix D, Program Execution.

~~C-10~~

~~Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)~~

~~API-5 FIRST QUARTER~~

.Date '3 . .:-Activt 1n/72003 2.77E-02 +1- I .80E-03 1/14/2003 2.31 E-02 +1- 2.OOE-03 1/21/2003 3.43E-02 +1- 2.20E-03 1/28/2003 2.3 1E-02 +1- 2.40E-03 2/4/2003 3.63E-02 +1- [2.60E-03 2/11/2003 2.80E-02 +1- l2.50E-03 2/18/20031 (a) 2125/2003 3.40E-02 12.60E-03 3/4/2003 3.25E-02 2.50E-03 3/11/2003 3.03E-02 +1- 12.60E-03 3/18/2003 3.06E-02 +1- !2.80E-03 3/25/2003 2.54E-02 +1- 12.50E-03 API-5 SECOND QUARTER Entl

~~. n.d ae~~

~~t. , a;, i~~
.-AtmtjV- ------: ,
4/1/2003 2.17E-02 +1- 2.70E-03 4/8/2003 1.80E-02 +1- 2.40E-03 4/15/2003 2.74E-02 +1- 2.60E-03 4/22/2003 1.65E-02 +1- 2.50E-03 4/29/2003 2.27E-02 +1- 2.60E-03 5/6/2003 1.1OE-02 +1- 2.50E-03 5/13/2003 1.20E-02 +1- 2.40E-03 5/20/2003 1.67E-02 +1- 2.5OE-03 5/27/2003 2.08E-02 +1- 2.70E-03 6/3/2003 1.7 1E-02 +/- 2.60E-03 6/10/2003 1.97E-02 +/- 2.1OE-03 6/17/2003 1.79E-02 +- 2.OOE-03 6/24/2003 1.99E-02 +1- 2.10E-03 (a) Sample not collected see Appendix D, Program Execution.
C-lI
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)
API-5 THIRD QUARTER 1nd ibif p 7/00
~~1. -~~
2.9-
>A-tMtv>
2._.,E -0, I
7/1/2003 2.90E-02 +/-12.30E-03 7/8/2003 2.90E-02 +/- 2.30E-03 07/15/2003 1.86E-02 +/- 12.20E-030 7/22/2003 2.02E-02 +/ 2.20E-03 7/29/2003 2.65E-02 +/ 2.30E-03 8/5/2003 2.86E-02 +/ 2.30E-03 8/12/2003 2.03E-02 +/- 2.30E-03 8/19/2003 3.12E-02 +/ 3.20E-03 8/26/2003 3.39E-02 +/ 2.40E-03 9/2/2003 2.49E-02 +/- 2.40E-03 9/9/2003 2.46E-02 +/- l2.20E-03 9/16/2003 3.30E-02 + 2.40E-03 9/23/2003 2.68E-02 +/ 2.40E-03 9/30/2003 1.52E-02 +/ 2.1 OE-03 API-5 FOURTH QUARTER Date -.-Activity 10nn2003 1.26E-02 +1 2.1 OE-03 10/14/2003 4.53E-02 +/ 2.80E-03 10/21/2003 2.30E-02 +/ 2.20E-03 10/28/2003 1.67E-02 +/ 2.1 OE-03 11/4/2003 2.99E-02 +/ 2.50E-03 11/11/2003 2.99E-02 +/ 2.30E-03 11/18/2003 2.96E-02 +/ 2.40E-03 11/25/2003 2.69E-02 +/ 2.40E-03 12/2/2003 2.95E-02 +/ 2.40E-03 12i9/2003 1.76E-02 +/- 2.30E-03 12/16/2003 2.90E-02 +/- 2.40E-03 0
12/23/2003 3.03E-02 +/ 2.40E-03 12/30/2003 2.85E-02 +/ 2.50E-03 C-12
Ferni 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)
API-1 FIRST QUARTER lDate0 l < Acti0tyr 1/7/2003 < 4.10E-02 1/1412003 < 4.90E-02 112112003 < 5.20E-02 1/2812003 < 3.OOE-02 21412003 < 4.30E-02 2/1112003 < 6.OOE-02 2/1812003 < 3.90E-02 2/2512003 < 4.1OE-02 3/412003 < 3.20E-02 3/1112003 < 3.60E-02 3/1812003 < 3.00E-02 312512003 < 3.50E-02 API-1 SECOND QUARTER 4-Date'3 <.0Acti2it 4/112003 < 3.90E-02 4/812003 < 3.30E-02 4/1512003 < 2.70E-02 4/2212003 < 3.80E-02 412912003 < 3.20E-02 5/612003 < 4.40E-02 5/1312003 < 3.20E-02 5/20s2003 < 2.70E-02 512712003 < 3.30E-02 6/312003 < 3.20E-02 6/1 02003 < 4.00E-02 6/1712003 < 13.30E-02 612412003 < 4.30E-02 C-13
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)
API-1 THIRD QUARTER
'Date'- Activity:
7/1/2003 < 13.1OE-02 7/8/2003 < 3.20E-02 7/15/2003 < 3.OOE-02 7/22/2003 < 5.30E-02 7129/2003 < 2.50E-02 8/5/2003 < 3.OOE-02 8/12t2003 < 3.20E-02 8/19/2003 < 5.20E-02 8/26n2003 < 5.40E-02 9/2t2003 < 2.80E-02 9/9/2003 < 5.1 OE-02 9/16/2003 < 3.10E-02 9123/2003 < 4.1OE-02 9/30/2003 < 5.40E-02 API-1 FOURTH QUARTER
-Date -- 'j,-Activity - -
10712003 < 1.30E-02 10/14/2003 < 4.30E-02 10/21/2003 < 4.30E-02 10/28/2003 < 3.1 OE-02 11/4/2003 < 4.40E-02 11/11/2003 < 5.30E-02 11/18/2003 < 4.1OE-02 11/25/2003 < 4.30E-02 12/9/2003 < 4.50E-02 12/17/2003 < 4.60E-02 12/23/2003 < 5.20E-02 12/30/2003 < 4.80E-02 C-14
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 AIR IODINE - 131 (pCi/cubic meter)
API-2 FIRST QUARTER l`Date - <Activity.
no2003 < 5.IOE-02 1/14n2003 < 5.1OE-02 112112003 < 5.20E-02 112812003 < 3.60E-02 2/412003 < 4.70E-02 2/1112003 < 6.50E-02 2/1812003 < 3.80E-02 212512003 < 4.40E-02 3/412003 < 3.80E-02 3/1112003 < 4.30E-02 3/1812003 < . 3.40E-02 312512003 < 3.1OE-02 API.2 SECOND QUARTER
.4 [
3<Dat 'Actiity 4/112003 < 2.60E-02 4/812003 <_ 2.80E-02 4/1512003 < 3.40E-02 412212003 < 3.20E-02 412912003 < 3.50E-02 5/612003 < 4.OOE-02 5/1312003 < 3.90E-02 512012003 < 3.50E-02 512712003 < 3.20E-02 6/312003 < 3.80E-02 6/1012003 < 3.30E-02 6/1712003 < 3.50E-02 612412003 < 4.00E-02 C-Is
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)
API-2 THIRD QUARTER
~~.'Date .-fActivity--~~
7/1/2003 < 3.50E-02 7/8/2003 < 2.80E-02 7/15/2003 < 2.90E-02 7/22/2003 < 4.40E-02 7/29/2003 < 3.10E-02 8/5/2003 < 3.20E-02 8/1212003 < 2.80E-02 8/19/2003 < 5.70E-02 8/26/2003 < 2.80E-02 9/2roo3 < 3.1 OE-02 9/9/2003 < 3.80E-02 9/16/2003 < 3.20E-02 9/23/2003 < 3.90E-02 9/30/2003 < 5.30E-02 API-2 FOURTH QUARTER l> Dit6= l-.Adhiity -..
10/7n2003 < 4.00E-02 10/14/2003 < 4.70E-02 10/21/2003 < 3.40E-02 10/28/2003 < 3.90E-02 11/4/2003 < 4.20E-02 11/11/2003 < 4.1OE-02 11/18/2003 < 5.IOE-02 11/25/2003 < 3.60E-02 12/9/2003 < 5.20E-02 12117/2003 < 5. 1OE-02 12123/2003 < 6.20E-02 12130/2003 < 4.10E-02 C-16
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)
API.3 FIRST QUARTER I`.Date I ActiWvity -
nn/2003 < 3.50E-02 1/1412003 < 6.OOE-02 112112003 < 5.00E-02 112812003 < 2.90E-02 2/412003 < 4.1 OE-02 2/1112003 < 5.70E-02 2/1812003 < 3.OOE-02 2/2512003 < 3.80E-02 3/412003 < 3.30E-02 3/1112003 < 3.90E-02 3/1812003 < 2.80E-02 312512003 1 < 2.70E-02 API-3 SECOND QUARTER
I < 2"Activit-y:.'
4/112003 < 3.20E-02 4/812003 < 3.50E-02 4/1512003 < 2.70E-02 412212003 < 2.60E-02 412912003 < 2.20E-02 5/612003 < 3.00E-02 5/1312003 < 2.50E-02 512012003 < 3.50E-02 512712003 < 3.1 OE-02 6/312003 < 2.20E-02 6/1012003 _ (a) 6/1712003 < 3.20E-02 612412003 < 5.30E-02 (a) Sample not collected see Appendix D, Program Execution.
C-17
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 AIR IODINE - 131 (pCi/cubic meter)
API-3 THIRD QUARTER 7/1/2003 < 3.40E-02 7/8/2003 < 2.80E-02 7/15/2003 < 2.80E-02 7/22/2003 < 4.20E-02 7/29/2003 < 3.1 OE-02 8/5/2003 < 2.80E-02 8/12/2003 _ (a) 8/19/2003 < 5.30E-02 8/26/2003 < 3.20E-02 9/2003 < 3.00E-02 9/9/2003 < 4.90E-02 9/16/2003 < 3.60E-02 9/23/2003 < 3.30E-02 9/30/2003 < 5.30E-02 API.3 FOURTH QUARTER VI.Date .;;; -<Activity 10/n2003 < 4.60E-02 10/14/2003 < 4.10E-02 10/21/2003 < 3.80E-02 10/28/2003 < 3.40E-02 11/4/2003 < 3.80E-02 11/11/2003 < 4.90E-02 11/18/2003 < 4.20E-02 11/25/2003 < 4.20E-02 12/9/2003 < 4.70E-02 12/17/2003 < 5.OOE-02 12/23/2003 < 4.70E-02 12/30/2003 < 4.70E-02 (a) Sample not collected see Appendix D, Program Execution.
C-18
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)
API-4 FIRST QUARTER l'3s'DAte-. i -I`rAcfi-ity' -. ,1 I/7/2003 (a) 1/14/2003 < 6.70E-02 1/2112003 < 5.40E-02 1/28/2003 < 3.50E-02 2/4/2003 < 6.60E-02 2/1112003 < 5.50E-02 2/18/2003 < 3.80E-02 2/2512003 < 4.40E-02 3/4/2003 < 4.1OE-02 3/1112003 < 4.OOE-02 3/18/2003 < 13.90E-02 3/25/2003 < 4.30E-02 API-4 SECOND QUARTER l ;'dat's.' :~A'ctiity-l 4/l/20031 < 3.50E-02 4/8/2003 < 3.20E-02 4/15/2003 < 3.90E-02 4/2212003 < 3.60E-02 4/29/2003 < 3.soE-02 5/612003 < 3.60E-02 5/1312003 < 4.OOE-02 5/20/2003 < 2.80E-02 5/2712003 < 2.70E-02 6/3/2003 < 3.40E-02 6/10/2003 < 4.soE-02 6/1712003 < 3.40E-02 6/24/2003 < 4.1 OE-02 (a) Sample not collected see Appendix D, Program Execution.
C-l9
Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)
API-4 THIRD QUARTER lrEndDate .Activity',:
7/1/2003 < 2.40E-02 7/8/2003 < 3.OOE-02 7/15/2003 < 3.40E-02 7n22/2003 < 4.20E-02 7129/2003 (a) 8/5/2003 < 2.10E-02 8/12/2003 < 3.30E-02 8/1912003 < 4.90E-02 812612003 < 2.50E-02 912/2003 < 3.OOE-02 9/9/2003 < 5.10E-02 9/16/2003 < 2.50E-02 9/23/2003 < 3.50E-02 9/30/2003 < 4.30E-02 API-4 FOURTH QUARTER Il IDate
-Activity. - -
l0/712003 < 4.40E-02 10/14/2003 < 4.80E-02 10/21/2003 < 4.40E-02 10/28/2003 < 3.90E-02 11/4/2003 < 3.90E-02 11/11/2003 < 5.20E-02 11/18/2003 < 4.70E-02 11/25/2003 < 3.90E-02 12/2/2003 < 4.00E-02 12/9/2003 < 5.30E-02 12/17/2003 < 5.50E-02 12/23/2003 < 5.90E-02 12/30/2003 < 5.1 OE-02 (a) Sample not collected see Appendix D, Programr Execution.
C-20
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE-131 (pCi/cubic meter)
API-5 FIRST QUARTER
-.- 'Date - '-'A-ctivit-I i17/2003 < 3.50E-02 1/14/2003 < 3.60E-02 1/21/2003 < 3.10E-02 1/28/2003 < 3.1OE-02 2/4/2003 < 4.30E-02 2/11/2003 < 5.30E-02 2/18/2003 = (a) 2/25/2003 < 4.1 0E-02 3/4/2003 < 3.40E-02 3/11/2003 < 3.50E-02 3/18/2003 D< 4.1OE-02 3/25/2003 < 12.80E-02 API-S SECOND QUARTER l'5>Date'-"' -'2-Activitj'w-- J, 4/l/2003 < 3.70E-02 4/8/2003 < 2.90E-02 4/15/2003 < 3.20E-02 4/22/2003 < 3.60E-02 4/29/2003 < 3.50E-02 5/6/2003 < 3.60E-02 5/13/2003 < 3.10E-02 5/20/2003 < 3.80E-02 5/27/2003 < 3.50E-02 6/3/2003 < 3.80E-02 6/10/2003 < 2.60E-02 6/17/2003 < 2.50E-02 6/24/2003 < 4.40E-02 (a) Sample not collected see Appendix D, Program Execution.
C-21
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)
API-5 THIRD QUARTER Datl > . Activity- --.
7/112003 < 2.90E-02 7/812003 < 2.70E-02 7/1512003 < 2.90E-02 712212003 < 4.40E-02 712912003 < 2.90E-02 8/512003 < 3.1 OE-02 8/12/2003 < 3.20E-02 8/1912003 < 5.1OE-02 8/26/2003 < 3.20E-02 9/2003 < 3.1 OE-02 9/912003 < 4.10E-02 9/1612003 < 3.OOE-02 912312003 < 3.30E-02 9/3012003 < 4.60E-02 API-5 FOURTH QUARTER
^.Date :-. j -l'Activity 10n72003 < 4.50E-02 10/14n2003 < 4.20E-02 10n21/2003 < 3.60E-02 1012812003 < 3.80E-02 11/412003 < 4.30E-02 11/11n2003 < 4.20E-02 11/1812003 < 4.00E-02 1112512003 < 3.70E-02 12/22003 < 3.90E-02 12/912003 < 5.30E-02 12/1712003 < 6.60E-02 12/2312003 < 5.IOE-02 12/3012003 < 5.40E-02 C-22
Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-1 (indicator)
(pCi/cubic meter) lNuclide - FirstQuarter - - Second Quarter - ]
Be-7 8.90E-02 +1- 2.00E-02 I 7.90E-02 +1- 2.60E-02 K-40 < 5.10E-02 <1 5.OOE-02 =
Mn-54 < 3.20E-03 _ < 3.70E-03 Co-58 < 6.90E-03 < 6.OOE-03 Fe-59 < 2.30E-02 <1 2.10E-02 Co-60 < 3.80E-03 I <l 2.90E-03 =
Zn-65 < 7.60E-03 I <1 8.1OE-03 Zr-95 < 1.20E-02 < 9.70E-03 _
Ru-103 < 8.40E-03 <1 4.40E-03 Ru-106 < 2.80E-02 _< 2.30E-02 =
Cs-134 < 2.30E-03 < 1.60E-03 Cs-137 <_ 4.70E-03 < 2.60E-03 Ba-140 I< 1.40E-01 < 2.20E-01 La-140 <1 1.60E-01 =< 2.50E-OI =I Ce-141 <_ 1.30E-02 I <1 I.50E-02 I Ce-144 <1 1.20E-02 I I <1 I.50E-02 I API-1 (indicator)
(pCi/cubic meter)
[Nuclide I < Third Qarier l Fouth rer-Be-7 I.IOE-0 +1 2.40E-02 9.30E-02 1+ 2.50E-02 K-40 < 3.70E-02 < 3.80E-02 Mn-54 < 3.50E-03 < 3.70E-03 ___ ___
Co-58 < 3.70E-03 = < 5.40E-03 Fe-59 < 1.40E-02 < 1.60E-02 Co-60 < 3.60E-03 < 7.70E-04 Zn-65 < 9.30E-03 < 8.30E-03 Zr-95 I< 8.70E-03 < 9.30E-03 Ru-103 < 5.20E-03 _ < 9.40E-03 Ru-106 < 3.50E-02 l < 2.20E-02 Cs-134 < 3.90E-03 < 2.50E-03 Cs-137 < 2.60E-03 < 2.80E-03 Ba-140 < 5.60E-02 < 7.60E-02 La-140 < 6.40E-02 __ < 8.70E-02 _
Ce-141 < I.OOE-02 < 1.40E-021 I Ce-144 <l 1.20E-02 l<_ 1.30E-02l I C-23
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-2 (indicator)
(pCi/cubic meter) lNuclide ,-'FrstQter
' -a-SecondQuarters Be-7 1.14E-01l +/- 2.1OE-02 I1.07E-01 +/- 12.50E-02 K-40 < 5.1OE-02 <1 3.90E-02 =
Mn-54 < 2.80E-03 < 3.60E-03 Co-58 < 6.20E-03 <_ 5.9OE-03 Fe-59 < 2.90E-021 <1 1.90E-02 Co-60 < 4.OOE-03l <1 3.30E-03 = ____
Zn-65 < 6.40E-03 = <1 6.60E-03 = -
Zr-95 <I 9.80E-03 <<1_ 7.90E-03 Ru-103 <l 8.20E-03 <I l.lOE-02 Ru-106 < 3.1OE-02 < 3.1 OE-02 Cs-134 < 2.90E-03 <I 2.50E-03 Cs-137 < 4.70E-03 I <1 1.40E-03 Ba-140 <1 1.90E-01 l <1 1.20E-O I La-140 <1 2.10E-01 l < 1.40E-O1 Ce-141 <1 1.30E-02 < 1 40E-02 Ce-144 < 9.50E-03 <1 1.40E-02 API-2 (indicator)
(pCi/cubic meter)
[Nuclide- -Third
',lj- i.er! Fourth Quarter:
Be-7 _ 7.50E-02 +1 2.10E-02 I < 5.80E-02 K-40 < 3.80E-021 < 2.90E-02 Mn-54 < 3.40E-03 < 3.1 OE-03 Co-58 < 3.90E-03 _ < 6.OOE-03 =
Fe-59 < 1.60E-02 < 1.60E-02 Co-60 < 2.30E-03 < 4.OOE-03 Zn-65 < 7.1OE-03 < 8.30E-03 Zr-95 < 1.1 OE-02 <I 9.30E-03 Ru-103 < 6.50E-03 _ a 8.OOE-03 Ru-106 < 3.30E-02 <l 2.20E-02 Cs-134 < 3.70E-03 _ <I 2.50E-03 Cs-137 < 2.40E-03 _ <I 2.80E-03 i Ba-140 < 4.60E-02 l <I 9.70E-02 _
La-140 < 5.30E-02 _ < I.OE-O1 _____
Ce-141 < 9.70E-03 _ <i 1.20E-02 i Ce-144 < 1.40E-02 l <I 1.30E-02 i C-24
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-3 (indicator)
(pCi/cubic meter)
Nuclide' -Il l Second Quarter(a')
-'1'---:JlrstQuartd:?'--:
Be-7 I < 6.20E-021 __ 1.IOE-OI +- 12.40E-02 K-40 < 5.10E-02 Il <1 3.60E-02 l Mn-54 < 2.80E-03_= <I 2.1OE-03 Co-58 < 4.50E-03 <I 4.70E-03 Fe-59 <j 1.70E-02 <
~~l < .60E-02 Co-60 <1 3.90E-03 = < 3.30E-03~~
Zn-65 <J 8.20E-031 <I 7.20E-03 _
Zr-95 < 7.50E-03 <1 9.40E-03 Ru-103 < 9.70E-03 I_<1 9.1 OE-03 Ru-106 < 2.60E-02 = <1 2.30E-02 =
Cs- 134 < 2.80E-03 <i 3.30E-03 Cs-137 < 4.60E-03 <I 2.30E-03 Ba-140 < 1.60E-01 <l 1.50E-O1 La-140 < 1.80E-01 <I 1.70E-O1 =
Ce-141 < 1.30E-02 '! 1.70E-02 Ce-144 < 9.50E-03 <_ 1.20E-02 API-3 (indicator)
(pCi/cubic meter) lNuclide~-- 'i 'Third Quar() -" l'-:Fo'urth Quarter ':': l Be-7 7.50E-02 +1- 2.OOE-02 < 6.60E-02 I K-40 < 4.60E-02 < 2.90E-02 Mn-54 < 3.80E-03 _ < 2.70E-03 Co-58 < 2.80E-03 = < 5.40E-03 Fe-59 < 1.20E-02 < 1.50E-02 Co-60 < 2.60E-03 < 4.00E-03 Zn-65 < 9.40E-03 < 5.50E-03 Zr-95 I I<.OOE-02 =1 = <1 4.90E-03 I Ru-103 < 8.70E-03 = < 5.40E-03 Ru-106 < 2.80E-02 _ < 3.1OE-02 Cs-134 < 3.60E-03 < 6.00E-04 Cs-137 < 3.90E-03 _ < 2.90E-03 Ba-140 <1 6.00E-02 _ = < 7.70E-02 =__
La-140 < 6.90E-02 = < 8.80E-02 =
Ce-141 < 1.IOE-02 < 1.40E-02 Ce-144 <l 1.80E-02 _ < 1.30E-02 (a) See Appendix D, Program Execution.
C-25
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-4 (control)
(pCi/cubic meter)
JNuclide -- First Quaer(a) ' Secon'd Quarer Be-7 1.05E-01 +J 3.20E-02 1 1 1.14E-01 +1 2.60E-02 K-40 < 7.00E-02 l <I 3.60E-02 Mn-54 < 3.50E-03 <I 2.30E-03 Co-58 < 7.70E-03 j < 4.60E-03 Fe-59 < 2.80E-02 < L.20E-02 _
Co-60 < 5.00E-03 _ <l 3.1OE-03 Zn-65 < 1.1OE-02 l <1 6.OOE-03 Zr-95 <1 1.50E-02 = l <1 5.80E-03 =
Ru-103 < 1.1OE-02 <t 5.80E-03 _
Ru-106 <1 3.40E-02 <1 2.90E-02 Cs-134 < 3.20E-03 l <l 2.70E-03 _
Cs-137 < 6.30E-03 I <T < 3.40E-03 __ _
Ba-140 < 1.80E-01 Il <1 1.90E-01 = -
La-140 < 2.10E-01 _ <1 2.1OE-01 Ce-141 < 1.40E-02 l < 1.70E-02 Ce-144 < L.60E-02 I I <I 1.30E-02 = -
API-4 (control)
(pCi/cubic meter)
[Nuclide,- . -7 Qer---l-,i-dq , "-FourthQuarter-Be-7 I 7.40E-02 +1- 2.101E-02 I I 7.20E-02 +/- 11.70E-02 K-40 < 4.80E-02 =I_ <1 4.20E-02 Mn-54 < 4.10E-03 l <1 2.10E-03 Co-58 < 6.OOE-03 <1 6.30E-03 Fe-59 < =.80E-02 =< L.50E02_ =
Co-60 < 3.30E-03 =__ <1 7.70E-04 =__
Zn-65 < 8.60E-03 <d 5.50E-03 = -
Zr-95 < 8.60E-03 <1 7.90E-03 Ru-103 < 6.00E-03 <1 8.80E-03 Ru-106 < 3.00E-02 <1 2.OOE-02 Cs-134 < 3.10E-03 = <1 2.20E-03 Cs-137 < 2.40E-03 = <l 2.30E-03 =
Ba-140 < 6.60E-02 _< 1.40E-01 La-140 <I 7.50E-02 _ <1 1.60E-01 = -
Ce-141 < L.20E-02 = <1 1.20E-02 __ __
Ce-144 < L.60E-02 l<l <1 1.20E-02 = -
(a) See Appendix D, Program Execution.
C-26
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-5 (Indicator)
(pCi/cubic meter) lNuclide Quarter(a) l ^ -First Second Quarter- - '
Be-7 9.30E-02 +1 2.50E-02 9.80E-02 +1 2.80E-02 K-40 < 5.40E-02 < 2.80E-02 Mn-54 < 3.20E-03 _ <1 2.60E-03 Co-58 < 4.OOE-03 <I 3.1 OE-03 Fe-59 < 2.90E-02 <I l.50E-02 Co-60 < 3.80E-03 <1 2.40E-03 Zn-65 < 6.20E-03 <F 5.90E-03 Zr-95 < l.lOE-02 <1 L.30E-02 Ru-103 < 9.90E-03 < 8.10E-03 Ru-106 < 2.50E-02 <1 2.90E-02 Cs-134 < 4.10E-03 <1 2.40E-03 Cs-137 < 5.30E-03 <I 2.50E-03 Ba-140 < L.70E-O1 < L60E-OI=
La-140 < 2.OOE-01 _ < 1.80E-0_[
Ce-141 < 1.30E-02 < 1.70E-02l Ce-144 < 1.30E-02 I < 1_3_____
API-S (Indicator)
(pCi/cubic meter) lNuclide - lThirdOQ arer FourthQuarter:-
Be-7 _ 9.50E-02 +1 2.30E-02 <1 6.OOE-02 _
K-40 < 3.80E-02 < 3.80E-02 I Mn-54 < 3.1OE-03 = < 2.70E-03 =
Co-58 < 3.OOE-03 < 5.40E-03 Fe-59 < I .50E-02 < 1.50E-02 Co-60 < 3.40E-03 < 2.80E-03 _
Z-65 < 9.30E-03 < 8.30E-03 Zr-95 < 7.00E-03 = <1 8.OOE-03 =
Ru-1 03 < 5.301E-03 <1 I.OOE-02l Ru-106 < 2.70E-02 <l 3.OOE-02l Cs-134 < 3.00E-03 i <l 2.70E-03l Cs-137 < 3.10E-03 I <1 2.60E-03 I Ba-140 < 5.30E-02 = _ <l 1.70E-01 l La-140 < 6.OOE-02 _ - l <l 1.90E-01 l Ce-141 < 1.OOE-02 l <1 1.30E-02 Ce-144 E
< 1.30E-02 l_2 (a) See Appendix D, Program Execution.
C-27
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 MILK ANALYSIS M-2 (Indicator)
(pCi/liter)
Nuclide-'.-
I-131
~~' 'I 6.50E-01 1AN 20-FEB 9.OOE-O1 I_~~
-J <
5.OOE-O1 2O-MAR~ -'
I Sr-89 < 8.OOE+00 < 9.OOE+00 < 8.90E+OO Sr-90 1.89E+00 +/- 4.30E-01 < 1.70E+00 < 1.90E+OO Be-7 < 4.80E+01 < 4.70E+01 < 3.90E+01 =
K-40 = 1.29E+03 +/- 5.80E+01 1.36E+03 +/ 5.90E+01 1.39E+03 +/- 4.90E+OI Mn-54 < 6.20E+00 < 4.90E+00 < 4.50E+OO Co-58 I_< 5.60E+OO < S.90E+W < 4.80E+OO Fe-59 < 1.30E+01 < 1.40E+O I < 1.1OE+O I Co-60 < 5.70E+00 _ < 6.80E+OO < 5.OOE+OO Zn-65 < 1.40E+01 < 1.50E+O1 < 1.20E+O1 Zr-95 < I .IOE+OI < 9.80E+00 < 9.30E+OO Ru-103 < 6.50E+00 < 4.90E+O0 < 5.OOE+O0 Ru-106 < 4.70E+OI < 5.lOE+O1 < 3.70E+O I Cs-134 < 6.10E+00 < 6.OOE+00 < 5.30E+O0 I Cs-137 < 5.40E+OO < 5.90E+00 < 4.60E+O0 Ba-140 < 1.OOE+O1 < 9.50E+00 < 6.40E+OO La-140 < 1.20E+O1 <1 1.1OE+O1 < 7.30E+OO Ce-141 < 9.40E+0 <_ 7.40E+001 I < 7.20E+OO Ce-144 <1 3.50E+01 I _ <1 2.40E+01 I I < 2.30E+O1 _
l-Nuclide; l,: 24-MR . ' ' 5-MAYx '- :.- 29-MAY _____-
I-131 < 4.20E-01 I < 8.60E-01 I < 7.80E-O1 I__
Sr-89 < 8.50E+00-i < 8.30E+00 < 8.50E+OO I0I Sr-90 < 1.80E+< < 1.30E+00 _ 1.70E+00 Be-7 < 2.80E+01 < 3.10E+01 [ < 3.60E+O1 _
K-40 1.26E+03 +/- 3.70E+01 _ 1.49E+03 +/- 4.30E+01 1.43E+03 +/- 5.OOE+°1 l Mn-54 < 3.50E+00 l < 3.60E+00' < 4.60E+0o Co-58 < 3.40E+00- _ 3.80E+00 < 4.60E+00 Fe-59 < 8.OOE+00l < 9.20E+OO < 1.IOE+01 Co-60 < 3.80E+00 < 4.80E+00 < 4.40E+00 _
Zn-65 < 9.1OE+00l < 9.30E+00 < 9.80E+OO l Zr-95 < 6.00E+00 _ < 6.70E+00 < 7.40E+OO Ru-103 < 3.80E+00 _ < 4.OOE+00 < 4.50E+OO l _
Ru-106 < 3.OOE+01 _ 3.20E+O1 < 3.90E+OI l__
Cs-134 < 3.50E+001 < 3.70E+00 < 4.1OE+00_
Cs-137 < 3.40E+00 _ 4.00E+00 < 4.20E1+OO l Ba-140 < 7.30E+00l < 8.20E+00 < 7.90E+00 La-140 < 8.40E+00 < 9.40E+00 < 9.10E+00 Ce-141 __ 4.90E+00 _ I < 5.20E+OO < 9.80E+OO0 l_
Ce-144 < 1.60E+01 I <1 1.90E+O1 I < 2.00E+OI1 Ill C-28
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 MILK ANALYSIS M-2 (Indicator)
(pCi/liter)
Nuclide. : ,12-JUN - --. ;-. I 26-JUN: . .U
_ I .L0-JU 10_ c-1-131 < 8.OOE-01l < 8.40E-01 I <1 7.60E-01 I Sr-89 < 5.OOE+0Ol < 8.70E+00 <1 7.60E+00 I Sr-90 < 8.50E-01 < 1.70E+OC < 1.70E+O0 _
Be-7 < 3.80E+01 =<- 6.90E+01 _ < 4.1OE+OII K-40 1.37E+03 +/ 5.50E+01 1.33E0 +1- 8.20E+0I 1.41E+03 +/ 5.60E+01 Mn-54 < 4.90E+C00 < 9.20E+00 < 5.30E+OO Co-58 < 4.90E+00 < 7.60EEO 00 < 5.30E+O0 ___
Fe-59 < 1.20E+01 < 2.10E+01 _< 1.20E+01 =
Co-60 < 6.40E+00 < 9.90E+00 < 6.OOE+00 Zn-65 < 1.20E+01_ < 2.30E+01 < 1.50E+01 Zr-95 < 9.OOE+00 - < 1.30E+01 < 9.90E+OO Ru-103 < 4.80E+00 < 8.50E+00 I < 5.80E+O0 =
Ru-106 < 4.OOE+01 < 6.40E+01 < 4.80E+01 Cs-134 < 5.70E+00 < 9.20E+00 _ _ 5.90E+00O Cs-137 < 4.30E+00 < 7.1OE+00= < 4.80E+0O =
Ba-140 < 9.OOE+00 < 1.10E+01 _< 7.70E+OO La-140 < 1.OOE+01 < 1.20E+01 < 8.90E+00 _
Ce-141 < 6.OOE+00 < 1.10E+01 < 8.80E+00 Ce-144 < 1.80E+01 I < 3.60E+O1 < 2.80E+01 1Nuclide- 24-.L '- 7-AUG ' 1 21-AUG -
I-131 < 5.40E-01 < 6.1OE-01 < 8.1OE-01I Sr-89 < 1.40E+01 < 4.90E+00 < 8.60E+00 Sr-90 < 4.80E+00 < 1.70E+00 I 2.22E+00 +/- 14.90E-01 Be-7 < 4.30E+01i < 6.IOE+01 = ___ < 6.OOE+01 __
K-40 1.33E+03 +/- 5.90E+OI = 1.53E+03 +/- 7.70E+01 1.40E+03l +/-16.30E+01 Mn-54 < 6.30E+00 < 6.90E+00 _ < 5.80E+OO Co-58 < 5.20E+00 < 7.80E+00 < 5.50E+00 Fe-59 < 1.50E+01 < 1.80E+01 = < 1.90E+01 Co-60 < 5.OOE+O0_ < 7.40E+00 = ______ < 5.70E-i-00 Zn-65 < 1.90E+O1l < 1.90E+01 _ < 1.50E+01 T Zr-95 < 9.30E+00, < 1.20E+01 < 1.1OE+01l I Ru-103 < 5.90E+00 < 8.20E+00 < 7.OOE+O0 - _l Ru-106 < 5.30E+01l < 6.20E+01 _ < 5.40E+01 l Cs-134 < 6.OOE+00 < 7.80E+00 < 6.40E+O00 Cs-137 < 5.50E+OO < 6.80E+00 _ 5.80E+00 Ba-140 < 1.30E+01 < 1.IOE+01 _ 1.IOE+O1I La-140 < 1.40E+01 < 1.30E+01 < 1.30E+01 l Ce-141 < 8.30E+0 < 1.IOE+01 < 8.90E+O0 _ _
Ce-144 < 2.70E+OIl < 3.40E+01 _ < 3.1OE+01 1 C-29
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 MILK ANALYSIS M-2 (Indicator)
(pCilliter) lNuclide 1. -l SEP* ________
- l 25-SEP - - 1 9-OCT - -: I- l I-131 < 7.70E-01I I < 8.30E-01 I < 8.20E-OI Sr-89 < 9.OOE+00 < 6.OOE+00 < 8.30E+OO Sr-90 < 1.70E+00 < 1.60E+00 = < 1.60E+OO =
Be-7 < 3.80E+01 < 3.20E+01 < 4.I1OE+O I K-40 1.42E+03 +/- 5.30E+01 1.3 7E+ 0 3 +/ 4.80E+0 I 1.39E+03 +/- 5.20E+OI Mn-54 < 4.60E+00 < 4.80E+00 = < 5.1OE+OO =
Co-58 < 5.60E+00 < 3.80E+00 < 5.80E+OO Fe-59 < 1.70E+01 < 1.50E+01 < 1.50E+OI =
Co-60 < 6.20E+00 < 4.70E+00 < 5.60E+OO Zn-65 < 1.30E+O1 < 1.IOE+O1 < 1.30E+01 Zr-95 < 9.40E+00 < 7.50E+00 < 9.70E+OO Ru-103 < 5.20E+00 = < 4.10E+00 < 5.30E+OO =
Ru-106 < 3.90E+01I < 3.40E3+OI <1 3.90E+OI Cs-134 < 5.60E+00 < 4.70E+00 < 5.30E+OO Cs-137 < 4.50E+00 < 4.00E+001 < 4.60E+OO Ba-140 00 < 9.10E+___
<OOE-0O < 1.OOE+OI La-140 <____E_0_ <9 1..0E+O _ < 1.20E+OI =
Ce-141 < 6.60E+00 < 5.10E+OO < 1.IOE+01 I _
Ce-144 < 2.20E+O1 <1 1.60E+01 _I < 2.30E+O1=
INuclide - l 23-OCT - - j1- 3 :; l -O- .18-DEC 1-131 < 9.30E-OII <1 1.OOE+OO < 9.80E-OI Sr-89 < 8.30E+001 < 8.50E+00 < 8.70E+OO Sr-90 < 1.80E+00 < 1.70E+00 < 1.80E+OO _
Be-7 < 5.00E+01 < 4.10E+01 < 5.90E+01 K-40 = 1.43E+03 +/ 6.30E+01 - 1.47E+03 +t- 6.20E+01 1.42E+03 +/- 7.1OE+OI Mn-54 < 4.80E+00_ < 6.40E+00 < 7.OOE+OO-Co-58 < 5.60E+00, < 5.50E+00 _ < 7.20E+OO0 Fe-59 < 1.90E+01 < 1.70E+01 < 1.80E+OI l Co-60 < 5.80E+00 < 6.20E+00 < 8.30E+OO Zn-65 < 1.60E+O1 < I.50E+01 = < 1.80E+OI I Zr-95 < 1.OOE+O1 < 1.OOE+01 = < 1.30E+O1 Ru-103 < 6.30E+00l < 5.50E+00 < 8.10E+OO Ru-106 < 5.40E+O1 < 5.OOE+01 I < 5.90E+01 Cs-134 < 5.60E+00; < 5.20E+00 = < 7.90E+OO Cs-137 < 5.30E+00 < 5.60E+00 = < 6.20E+OO Ba-140 < 8.60E+OOl < 1.IOE+O1 _ < 1.20E+OI1 La-140 < 9.90E+00 I < 1.20E+01 < 1.30E+OI l Ce-141 < 8.50E+001 < 8.20E+OO < 1.10E+OI Ce-144 < 2.80E+01 Il ____ < 2.60E+01 _I < 3.40E+OI C-30
Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 MILK ANALYSIS M-8 (Control)
(pCi/liter)
Nuclide - 16-JAN - --20-FEB 2MAR:
1-131 < 7.20E-O1 I < 11.OOE+O0 < 4.90E-0 I Sr-89 < 8.20E+00 < 9.10E+00 < 7.60E+0O Sr-90 < 1.30E+00 < 1.70E+00 < 1.60E+OO _
Be-7 < 2.80E+01 < 4.20E+OI < 3.70E+01 K-40 1.37E+03 +/- 4.00E+0I 1.47E+03 +/- 5.80E+01 1.43E+03 - I 4.90E+OI Mn-54 < 3.50E+00 < 5.70E+00 < 4.50E+OO =
Co-58 < 3.40E+00 < 6.00E+00 _ < 4.80E+00 Fe-59 < 8.70E+00 < 1.20E+01 _ < 1.20E+ 01 _
Co-60 < 4.60E3+OO < 5.90E+00 < 5.00E+OO Zn-65 < 1.10E+OI <=2.40E+01 < 1.20E+O I1 Zr-95 < 6.1 OE+O0 < 9.00E+00 < 8.20E+OO Ru-103 < 3.70E+00 <1 5.40E+00 < 5.60E+O0 . -
Ru-106 < 3.OOE+01 < 5.10E+0I < 4.00E+OI Cs-134 < 3.70E+00 < 6.00E+00 < 4.80E+O0 =
Cs-137 < 3.40E+00 _ _< 5.70_+00 _ < 4.50E+00 Ba-140 < 6.00E+00 < 6.20E+00 < 8.50E+O0O La-140 < 6.90E+00 __ 7.1OE+OO < 9.80E+OO Ce141 < S.IOE+OO <= 6.3013+00 < I .I OE+01I Ce-144 < 1.90E+01 01 I____ I_ < 2.40E+01 I I I.Nuclide -1l--4APR'; 1-MAY : - l 29-MY ____i: __
1-131 < 4.50E-01l < 8.30E-01 lIl <1 9.30E-01 I Sr-89 < 7.80E+00 < 9.20E+00- < 7.90E+00 Sr-90 < 1.60E1+00= < 1.60E+00 = < 1.60E+O0 Be-7 < 3.10E+01 < 2.90E1+01 < 3.90E+O1 K-40 _ 1.37E+03 +/- 4.30E+01 1.42E+03 +/ 4.30E+01 1.44E+03 +/- 5.60E+OI1 Mn-54 < 4.103E+OO = < 4.30E+00 c< 5.20E1O3 l-Co-58 _ 4.00E+00 < 3.80E+OC <_ 5.IOE+0O l Fe-59 < 1.00E+01l < 9.60E+00 l< 1.20E+01 l Co-60 < 5.OOE+00 < 4.50E+0O < 6.40E+00-Zn-65 < 9.40E+00 < 9.10E+00 < 1.40E+01 l_
Zr-95 < 7.20E+00, < 7.20E+OO l< I.OOE+01 l_
Ru-103 < 4.00E+0O0 < 4.10E+00 < 5.lOE+00 Ru-106 _< 2.60E+01 < 3.00E+01 _ < 3.90E+01 Cs-134 < 4.20E+00 < 4.20E+00 l< 5.1OE+O0 l Cs-137 < 3.50E+OO < 3.70E+00 <1 4.20E+00 I Ba-140 < 8.20E+00 < 7.OOE+00 < 9.80E+O01 ___
La-140 < 9.50E+00 < 8.00E+OO < 1.IOE+OI lI l_ l Ce-141 < 8.30E+00 < 5.80E+0O l< 6.50E+00}
Ce-144 < 1.40E+O1 I < 1.50E+OI I_ < 1.90E1O+l l C-31
Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 MILK ANALYSIS M-8 (Control)
(pCiffiter)
INuclide -l 12-JUN; 61-UL 1-131 < 6.00E-01 _ < 8.30E-01 I < 8.80E-0 I Sr-89 < 8.OOE+00 < 5.40E+O0 < 7.70E+OO Sr-90 < 1.80E+0 1 _ < 1.70E+00 _ < 1.70E+OO _
Be-7 < 4.30E+01 < 5.90E+01 < 4.1 OE+O0I K-40 1.32E+03 +/- 5.40E+01 = 1.38E+03 +/ 6.90E+01 = 1.46E+03 +/- 5.50E+01 Mn-54 < 4.90E+O0 < 5.90E1+00 < 5.1 OE+OO Co-58 < 5.10E+00 _< 7.40E1+00 < 5.OOE+OO Fe-59 < 1.30E+01 < 1.70E+01 < 1.20E+01 Co-60 < 5.90E+00 < 5.70E+00 = < 4.60E+OO Zn-65 < 1.30E+01 < 1.80E1+01 < 1.30E+01 Zr-95 < 8.20E+00 _ 1.I 1E+01 < 8.50E+OO Ru-103 < 4.90E+00 < 7.20E+00 < 5.20E+00 Ru-106 < 4.70E+01 < 6.00E+01 < 4.90E+01 Cs-134 < 5.40E+00 < 7.20E+00 < 4.50E+00 Cs-137 < 5.50E+00 < 5.70E+00 < 5.1OE+O0 Ba-140 < 8.20E+00 < 8.40E+00 < 6.20E+O0 La-140 < 9.40E+00 < 9.60E+00= < 7.20E+O0 Ce-141 < 5.70E+00 < 1.IOE+01 < 6.20E+O0 _ _
Ce-144 < 2.10E+01 - < 3.20E+01 < 2.701i+0 I lNuclide- 24--L I' > 7-AUG
- - AUG ____
I-131 < 6.20E-01 I < 5.70E-01 I < 9.10E-01 Sr-89 < 8.50E+00 < 9.O0E+00 < 5.50E+00 Sr-90 < 1.80E+00 < 1.60E+00' 3.1I1E+00 +/- 5.30E-01 Be-7 < 5.50E1+01 < 3.50E+01 < 5.40E+01 II K-40 1.36E+03 +/- 5.90E+O1 1.36E+131 +/- 4.80E+01 1.26E+03 +/- 7.00E+01 Mn-54 < 5.20E+00 < 4.50E+O0' < 7.20E+O0 ___
Co-58 < 6.30E+0O - _ 4.50E+00j < 7.80E+OO Fe-59 < 1.30E+01l < 1.20E+01l < 2.OOE+01 Co-60 < 6.OOE+00 _ < 4.90E1+00 < 6.20E+00 Zn-65 < 1.50E+011 < 1.20E+01 < 2.00E+01 i Zr-95 < 8.90E+00 < 8.OOE+00 < 1.20E+01 Ru-103 < 7.10E+00 < 5.30E+00 < 7.70E+00 Ru-106 < 5.30E+01 < 4.10E+01 < 6.40E+01 Cs-134 < 6.OOE+00 _ < 4.90E+OO < 7.70E+00 Cs-137 < 5.40E+00 _< 4.00E+00 < 6.50E+OO Ba-140 < 1.20E+01 l<_ 8.40E+00 < 1.30E+01 La-140 < 1.30E+01 _< 9.60E+00l < 1.40E+01 Ce-141 < 9.OOE+00 < 6.90E+00 < 1.10E+01 Ce-144 < 2.70E+01 < 2.40E+01 3.40E+01I<_
C-32
Fermi 2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 MILK ANALYSIS M-8 (Control)
(pCi/liter) lNuclide : -l 11-SEP' '- - 25
'SEP- - _ _: 9-OCT .- ; - l 1-131 < 5.70E-01 < 7.40E-01 < 5.80E-OI Sr-89 < 7.60E+00 < 8.70E+00 _ < 7.40E+OO Sr-90 < 1.40E+00 < 1.70E+00 < 1.70E+OO Be-7 < 5.40E1+01 < 4.30E+01 < 3.40E+O1 _
K40 _ .31E+03' +/- 6.70E+01 _ 1.42E+03 +/- 5.80E+01 1_
.41 E+03 +/- 4.90E+OI Mn-54 < 6.60E+00 <1 4.90E+OO < 5.OOE+OO _0 Co-58 < 6.00E+00 t _ < 6.20E+00- < 4.30E3+OO Fe-59 < 2.30E+01 < 1.60E+OI . < 1.50E+O1 _
Co-60 < 7.70E+00 < 5.80E+OO =<_ 5. lOE-+OO =
Zn-65 < 1.80E+01 < 1.20E3+O1 < 1.IOE+O I Zr-95 < 1.1OE+O I < 9E9.1OOE+00 _ < 8.OOE+OO _-
Ru-103 < 7.70E1+00 <1 6._1 OE_+OO_ < 4.80E3+OO Ru-106 < 5.20E+O1I < 4.70E+01 l < 3.30E+OI Cs-134 < 6.60E+OO0 < 5.50E+OO _ < 4.60E+OO Cs-137 < 5.90E+00 < 5.40E+00 < 4.10E+OO Ba-140 < 1.20E+O1 l<_ 1.OOE+O1 _ < 7.60E+OO La-140 < 1.40E+O1 < 1.1OE+OI - < 8.70E+OO_
Ce-141 < 9.30E+00 < 7.90E+00 < 5.80E+oo Ce-144 < 3.1OE+01I < 2.70E+01 < 1.70E+0I l Nuclide 23-O;- 13-NOV. 18-DEC _ __
1-131 < 9.40E-01 l_ _ < 8.80E-O1 <1 9.90E-OIl Sr-89 < 8.40E+OO < 5.80E+00 < 7.1OE+00 Sr-90 < 1.70E+OO < I.OOE+OO < 1.50E+OO Be-7 < 4.20E+01 < 3.80E+01 < 3.60E+01 K-40 1.36E+03 +/- 6.20E+01 1.32E+03 +/- 5.60E+01 1.35E+03 +1- 5.OOE+O1 Mn-54 < 5.50E+OO = < 5.40E+00 = < 4.1OE+OO _ _
Co-58 < 6.OOE+00 < 4.50E+00 = < 4.30E+00 Fe-59 < 1.70E+01 < 1.90E+01 < 1.60E+01 Co-60 < 6.30E+00 < 5.40E+OO < 5.IOE+OO Zn-65 < 1.50E+O1 < 1.30E+O1 =<_ 1.OOE+O1 Zr-95 < 9.70E1+00 < 9.80E+00 _<_ 8.00E+00 Ru-103 < 6.90E+00 < 5.30E+00 < 4.70E+00 Ru-106 < 4.60E+01 < 3.70E+01 < 3.40E+01 Cs-134 < 6.iOE+OO < 4.70E+00 < 4.90E+00 Cs-137 < 4.90E+00 < 5.1OE+OO < 4.20E10+0 Ba-140 < 7.40E+00 < 9.40E+00 < 9.40E3+OO _
La-140 < 8.50E+OO < 1.IOE+O1I < 1.IOE+O1 I_1 Ce-141 < 8.40E+00 < 8.10E+00 < 7.9013+00_
Ce-144 < 3.00+01 _ 1 1.90E+01 = _ 1.70E+
C-33
Fermi 2 -2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 VEGETABLE ANALYSIS FP-1 (Indicator)
(pCi/kg wet) l Nuclide >' l ;24-JULM-Swiss Chard' -'.24-JUL
.J-; Lettuce : - 24-JUL Cauliflower I-131 I < 4.10E+01 I < 4.60E+01 I <1 4.50E+01 I Be-7 < 3.60E+02 < 2.70E+02 < 2.70E+02 _
K-40 2.33E+03 +/- 3.40E+02 1.09E+03 +/- 1.90E+02 3.79E+03 +/- 3.OOE+02 Mn-54 < 5.30E+01 _ 2.60E+01 < 3.80E+01 _
Co-58 < 4.10E+01 _ < 3.50E+01 < 3.20E+01 =
Fe-59 < 1.60E+02 < 9.80E+01 < 9.90E+O1 Co-60 < 6.20E+01 _ < 3.50E+01 < 4.1 OE+O I _
Zn-65 < 1.20E+02 < 8.30E+01 < 6.90E+O I Zr-95 < 9.90E+01 _ < 6.30E+01 < 5.20E+01 Ru-103 < 5.80E+01 =<_ _ 3.60E+01 < 3.80E+01 =
Ru-106 < 3.80E+02 _ < 2.30E+02 < 2.90E+02 _
Cs-134 < 4.40E+01 < 2.90E+01 < 3.30E+O1 Cs-137 < 3.80E+01 < 2.60E+01 < 3.50E+O1 Ba-140 < 1.50E+02 _ < 1.20E+02 = < 1.30E+02 =
La-140 < 1.70E+02 < 1.30E+02 < 1.50E+02 Ce-141 < 6.90E+01 < 4.30E+O1 < 5.OOE+OI Ce-144 < 1.60E+02 I <1 1.1OE+02 = < 1.50 E+02 =
FP-1 (Indicator)
(pCi/kg wet)
[Nuclide' :-l: -w27-AUG Broccoli J'
.';27-AUG:Cabbage__-* l -:27:AUG Swiss Chard- ".
1-131 < 3.60E+O1 _ < 3.30E+01 I 1 <1 3.20E+0I I Be-7 < 3.70E+02 < 3.80E+02 < 4.70E+02 K-40 3.46E+03 +/- 3.50E+02 2.06E+03 +/- 3.50E+02 2.73E+03 +/- 4.30E+02 Mn-54 < 3.40E+01 < 2.90E+01 < 6.OOE+OI l__
Co-58 < 4.50E+01 <l 4.10E+01 < 3.80E+01 l_l Fe-59 < 1.50E+02 < 1.40E+02 < 2.50E+02 l__
Co-60 < 5.IOE+O1 <l 4.90E+01 l ___ l <1 5.80E+01 l l_ l Zn-65 < 8.70E+O1 < 9.60E+o I < 1.IOE+02 1_1 Zr-95 < 7.10E+01 < 7.90E+01 '< 1.IOE+02 l j Ru-103 < 4.10E+01 < 4.40E+01 < 5.50E+01 j__
Ru-1 06 < 3.50E+02 < 3.60E+02 l_ j < 4.OOE+02 l Cs-134 < 4.30E+01 = < 4.80E+01 < 4.40E+Ol l Cs-137 < 4.OOE+01 < 4.OOE+01 < 4.70E+01 l l Ba-140 < 9.20E+01 < 1.IOE+02 <1 1.60E+02 _ _
La-140 < 1.IOE+02 < 1.30E+02 l_ l < 1.90E+02 Ce-141 < 5.IOE+OI= < 6.20E+OI l_ l < 5.90E+O1 Ce-144 < 1.80E+02 = < 1.80E+02 l_ l < 1.60E+02l 1 _
C-34
Fermi 2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 VEGETABLE ANALYSIS FP-9 (Control)
(pCi/kg wet)
Nuclide l 24-JULCabbag - J 24-JULMRedCabbage - 24-UL:SwissChard -
1-131 < 4.50E+01 _< 3.60E+O1 < S.OOE+O1 I Be-7 < 5.70E+02 < 5.40E+02 < 6.20E+02 K-40 3.22E+03 +/- 4.90E+02 _ 4.911E+03 +/- 5.OOE+02 3.38E+03 +/- 4.OOE+02 Mn-54 < 3.90OE+01 < 4.80E+01 < 5.60E+O1 I Co-58 < 7.30E+01 < 6.10E+01 < 5.50E+O1 I Fe-59 < 1.60E+02 = < 1.60E1+02 < 1.70E+02 _
Co-60 < 5.70E+01 _ 1 7.70E+01 I < 6.90E+O1 Zn-65 < 1.60E+02 < 1.40E+02 < 1.30E+02 Zr-95 < 1.20E+02 _ < 1.20E+02 < 1.20E+02 Ru-103 < 6.30E+01 < 5.90E+01 < 7.30E+OI _
Ru-106 _ 3.90E+02 = < 5.30E+02 < 5.60E+02 Cs-134 < 5.80E+01 < 5.20E+01 < 5.80E+O1 Cs-137 < 6.30E+01 < 6.OOE+01 _< 4.80E+O1 Ba-140 < 2.50E+02 < 2.30E+02 < 2.20E+02 La-140 < 2.80E+02 _ 2.70E+02 < 2.50E+02 Ce-141 < 9.50E+01 < 9.20E+01 < 9.90E+O1I Ce-144 < 2.50E+021 < 2.10E+02 < 2.80E+02 I FP-9 (Control)
(pCi/kg wet)
[Nuclide --- 27-AUG:Cabbage-"-:- AUG Horseradish 1-131 1 < 3.10E+01l __ 3.20E+O1I Be-7 < 3.30E+02 6.1OE+02 +/-j2.OE+02 K-40 1.99E+03 +/ 2.60E+02 5.99E+03 +/- 14.80E+02 Mn-54 < 3.50E+01 < 6.I OE+O I Co-58 < 4.30E+01 < 4.30E+OI1 Fe-59 < 1.20E+02 _ 2.1 OE+02 Co-60 < 5.30E+01 < 6.70E+01 Zn-65 < 9.90E+01 = < 1.30E+02 Zr-95 < 6.90E+01 < 9.OOE+OI1_
Ru-103 < 4.20E+01 < 5.80E+O1I __
Ru-106 < 3.OOE+021 < 4.40E+021 Cs-134 <1 3.1OE+0I1 < 5.70E+O1i Cs-137 < 3.70E+01 < 5.OOE+OIl Ba-140 < 9.20E+01 l < 9.70E+OIl La-140 <l 1.IOE+02l < 1.IOE+02 l Ce-141 <c6.10E+01 l < 7.90E+OI l l Ce-144 1.70E+02_ << 2.70E+02
< I C-35
Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 DRINKING WATER ANALYSIS DW-1 (Indicator)
(pCi/liter)
Nucide JAN; - .25-FEB - -_
'-25-M AR-..
GR-B 3.60E+OO +/- 1.OOE+OO < 2.90E+OOt < 3.1OE+OO I Sr-89 < 7.40E+00 < 7.30E+00 < 7.20E+00 Sr-90 < I .50E+OO < 1.40E+OO= < .50E+OO_
Be-7 < 4.40E+01 < 3.90E+01 - < 3.90E+OIl K-40 < 8.10E+01 < 8.1OE+O1 < 6.60E+OI l Mn-54 < 4.70E+00 < 5.20E+00 < 4.40E+OO0 Co-58 < 4.60E+00 < 4.30E+00 < 3.60E+OO Fe-59 < 1.1OE+O1 = < 9.90E+00 < 8.40E+OO Co-60 < 5.OOE+OO < 5.90E+00 < 5.20E+OO Zn-65 < 1.1 OE+O I < I.OOE+O I < 1.1 OE+O I Zr-95 < 8.20E+00 < 7.60E+00 < 8.1 OE+OO Ru-103 _ 5.40E+00 < 4.70E+00 = < 4.50E+OO Ru-106 < 4.40E+01 < 3.70E+01 < 4.20E+OI Cs-134 < 4.80E+OO < 5.IOE+OO < 4.40E+OO Cs-137 < 5.30E+00 < 4.60E+00 < 4.40E+OO Ba-140 < 5.80E+00 _ 1 8.40E+00 < 8.20E+OO La-140 < 6.70E+00 < 9.70E+00 < 9.40E+OO Ce-141 < 7.90E+00 < 5.40E+00 < 6.20E+OO Ce-144 < 3.OOE+01 . < 2.OOE+01 _ < 2.30E+O1 I (Nuclide ' - 29-APR'-_______ 27-MAY'- J
-5 . 24-JUN -
GR-B 3.911E+OO +/- 8.50E-01 4.20E+OO +/ 1.IOE+OO < 2.90E+OO Sr-89 . 8.1OE+OO < 9.30E+00 < 5.70E+00 Sr-90 < 1.90E+OO = < L.70E+OO < < I.50E+OO 00 Be-7 < 5.OOE+OI _< 3.90E+01 < 6.50E+O1 =
K-40 < 8.70E+01 < 7.70E+OI < 1.IOE+02 Mn-54 < 5.80E+00 < 5.70E+00 < 7.60E+00 Co-58 < 5.OOE+OOl < 4.70E+00 < 6.60E+00 Fe-59 < 1.20E+01 < 1.30E+OI < I.50E+OI _
Co-60 < 5.70E+00 < 6.50E+00 = < 9.OOE+OO =0 _
Zn-65 < 1.40E+OIl < 1.1 OE+O I < 1.90E+01 Zr-95 < 9.30E+00 < 8.60E+OO < I.50E+O I Ru-103 < 6.20E+00 < 5.60E+00 < 7.60E+00 Ru-106 < 5.30E+011 < 4.50E+OI < 5.l OE+OII Cs-134 < 6.40E+OO < 5.90E+00 1 < 7.70E+OO =
Cs-137 < 6.30E+OO < 5I OE+OOl < 6.20E+OO Ba-140 < I.IOE+OI < 8.40E+00l < 1.O0E+01 l La-140 < 1.20E+01l < 9.60E+00 < 1.20E+01 l Ce-141 < 7.30E+00 < 7.20E+O0_ < I.IOE+OI _
Ce-144 < 2.70E+O1 I <_2.0OE+01II I < 3.60E+O1 l C-36
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 DRINKING WATER ANALYSIS DW-1 (Indicator)
(pCilliter) lNuclide JL - 26-AUG - 30-'SEP -____
GR-B 3.70E+0O + I- 1.1 OE+O0 I 3.60E+O0 +1- I .OOE+0O <1 3.OOE+OO I Sr-89 < 3.20E+00 _ < 8.40E+00= < 7.20E+OO Sr-90 < 1.40E+00 < 1.80E+00_ < 1.40E+OO_
Be-7 < 4.30E+01 < 7.70E+01 < 3.30E+01 K-40 < 8.60E+01 _ 9.80E+01 < 4.90E+01 Mn-54 < 5.30E+00 _< 8.40E+00 _ < 3.70E+00 Co-58 < 4.70E+00 < 9.50E+66, < 3.90E+00 _
Fe-59 _ 1.20E+01 < 2.60E+01l < 9.40E+00, Co-60 < 5.60E+00 < 7.90E+O0 = < 5.30E+00i Zn-65 < 2.OOE+01 < 2.OOE+01 < 8.80E+00 Zr-95 < 1.OOE+OI < 1.30E+01= < 6.70E+00 =
Ru-103 < 5.20E+00 < 8.50E+00 < 5.70E+00 Ru-106 < 5.OOE+01 < 7.20E+01 < 3.90E+OI Cs-134 < 5.90E+O0 < 9.20E+00 < 4.90E+00 Cs-137 < 6.90E+O0 < 9.OOE+00 = < 4.60E+00 Ba-140 < 8.1OE+O0 < 1.20E+01 < 7.60E+OO La-140 < 9.30E+001 < 1.40E+01 _< 8.70E+OO Ce-141 < 7.20E+00J <_ 1.20E+01 < 7.40E+OO Ce-144 < 2.70E+01 I _I_ < 4.10E+01 I=I < 2.60E+01 I lNuclide 28-OC - -__-_-_25-NOV --- I- . 30-DEC,,'
GR-B 3.70E+400-I- 1.IOE+O0 <1 3.10E+OOl i l <1 3.OOE+00 lIl Sr-89 < 9.IOE+00 I _ < 8.20E+O0 1 < 7.60E+00 Sr-90 < 1.50E+00 l < 1.50E+O0 7 < 1.80E+00 _ _I Be-7 < 4.30E+01 l _l _ l_<_ 2.50E+01 l__ < 4.50E+01 K-40 < 8.20E+01l l < 4.70E+01 l__ < 7.70E+0I l Mn-54 < 4.80E+001 < 3.10E+00 l_ < 5.20E+OOl l Co-58 < 5.OOE+O0 l < 3.30E+00 l_ < 5.30E+O0 Fe-59 < 1.40E+01I 7_ _ < 8.50E+O0 T < .30E+o1 _ _ _ I Co-60 < 5.60E+00 < 3.10E+00 l < 4.50E+O0 Zn-65 < 1.40E+ l < 1.IOE+0I < 2.OOE+O1 l l _ _
Zr-95 < 8.60E+00, < 5.50E+00 __ < 8.90E+OOI _I Ru-103 < 5.20E+00 < 4.10E+00 ___ < 6.30E+O0 _ _
Ru-106 4.40E+O < 2.80E+01 l < 4.70E+OIl01 Cs-134 < 5.20E+00 < 3.20E+00 < 5.50E+00 l Cs-137 < 5.60E+00 < 2.90E+00 __ <1 5.1OE+O0 _ I Ba-140 < 8.50E+00 < 8.70E+00 < 1.20E+01 La-140 < 9.70E+00l 7 <_ .OOE+O1 < 1.40E+01 l_l Ce-141 <l 7.40E+00 < 9.OOE+00 < 9.80E+O00 Ce-144 < 2.90E+01 l _l _ l < 1.70E+01 l l_ l < 3.OOE+OI l l C-37
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 DRINKING '"ATER ANALYSIS DW-2 (Control)
(pCi/liter) lNuclide -'28-JN-'-: :25'FEB " .25-MAR GR-B < 2.80E+00 I 2.96E+00 +/- 9.70E-01 I 2.86E+00 9.40E-OlI Sr-89 < 6.90E+00 < 8.50E+00 < 8.80E+OO Sr-90 < 1.40E+00 < 1.70E+00 < 1.70E+OO Be-7 < 3.90E+0l < 4.50E+01 < 3.20E+O I K-40 < 7.30E+0l < 7.60E+01 < 6.30E+O 1 Mn-54 < 5.20E+00 < 5.90E+00 < 4.OOE+OO Co-58 < 4.30E+OO < 5.lOE+OO I < 4.OOE+OO I Fe-59 < I.OE+OI < 1.30E+01 < 8.60E+O0 Co-60 < 5.40E+00 < 6.50E+00 = < 3.60E+OO Zn-6S < I.OOE3+OI1 < 1.20E3+01 < 8.60E+00 Zr-95 < 8.50E+00 < 9.60E+oo < 6.80E+OO0 Ru-103 < 5.20E+OO _ < 5.80E+00 < 4.60E+OO0 Ru-106 < 4.10E+01l < 5.60E+01 < 3.50E+OI I Cs-134 < 4.70E+00 < 6.40E+00 = < 4.20E+OOl Cs-137 < 4.60E+00 < 5.80E+00 <1 3.30E+OO; I Ba-140 < 9.80E+oo < 9.80E+00 < 6.50E+OO La-140 < I.IOE+OI < 1.1OE+Ol I < 7.50E+OO Ce-141 < 6.80E+00 <1 9.30E+00 I < 6.40E+OO Ce-144 < 2.40E+O I I < 3.10E+01 I < 2.00E+OI l Nuclide' '29-APR -- 27-MAY .- 24-JUN "__"'___
GR-B 4.37E+00 +/- 8.50E-01I < 2.80E+00 I < 2.80E+00 I Sr-89 < 7.1OE+OO < 6.80E+00 <1 5.70E+OO Sr-90 < 1.70E+OO < I.50E+00 < I.50E+OO Be-7 < 3.60E+01 < 3.60E1+01 < 5.50E+O I K-40 < 6.30E+01 < 6.20E+01 < 9.30E1+OI Mn-54 < 3.90E+00 < 3.60E+00 < 7.OOE+OO Co-58 < 4.70E1+00 < 4.10E+00 < 5.20E1+OO_
Fe-59 < I.OOE+O I < 8.OOE+00 < 1.60E+OI Co-60 < 4.1OE+OO < 3.70E1+00l < 8.50E+OO Zn-65 < 9.40E+OO <1 1.OOE+OI l < 1.70E+OI Zr-95 < 6.50E+00 < 7.60E+OO < L.OOE+O1 Ru-103 < 4.60E+00 < 4.70E+OO < 8.OOE+OO Ru-106 < 3.90E+01Z < 3.50E+01 < 6.60E+OI Cs-134 < 4.40E+OO < 4.20E+00 < 7.50E+W0 Cs-137 < 3.80E+0O < 3.50E+0l < 5.70E+OC Ba-140 _ 6.30E+00; < 6.60E+OOl < LlOE+OI La-140 < 7.20E1+00 1 < 7.60E+00 < 1.30E+OI_
Ce-141 < 6.50E+00 < 6.20E+OOl < I.OOE+OI1 Ce-144 < 2.1OE+0 i < 2.OOE+01 _ < 3.70E+O1 C-38
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 DRINKING WATER ANALYSIS DW-2 (Control)
(pCilliter) lNuclide ; l w.29JUL _ -'__
-- 26-AUG -,30-SEP -
GR-B _< 2.70E+000_ __ 3.42E+00J +/- 19.80E-0 l 3.10E++00 +/- 1.OOE+O0 Sr-89 < 3.OOE+00 _ < 6.80E+00 = < 7.00E+O0 =
Sr-90 < 1.30E+00 < 1.60E+00 < 1.40E+O0 I Be-7 < 7.OOE+01 < 6.20E+01 < 5.OOE+OI K-40 < 1.20E+02 < 9.10E+01 < 6.50E+0O Mn-54 < 7.20E+00 < 6.70E+00 < 6.1OE+O0 Co-58 < 7.60E+00 < 8.1OE+O0 < 5.OOE+0O Fe-59 < 1.70E+01 < 1.90E-+O1 < l.50E+0I Co-60 < 5.80E_+OO < I.OOE+0 I < 5.60E+00O Zn-65 < 2.00E+01 < 3.00E13+OI _.__E+0 <
Zr-95 < 1.20E+01 < 1.30E+0 l = < 1.I1OE+O1I Ru-103 < 8.OOE+00 <_ 6.80E+00 _ < 6.50E+00 _
Ru-106 < 8.40E1+01 < 6.30E+01 < 4.50E+OlI Cs-134 < 9.40E+00 < 7.10E+00 < 6.60E+00:
Cs-137 < 8.20E+00 < 7.40E+00 = < 4.90E+00 _
Ba-140 < 1.1OE+OI < 1.0OE+0O I < 8.70E+OO:
La-140 < 1.30E+01 < 1.20E+OI= < I.OOE+OI I Ce-141 < 1.1OE+-O Il < I.1OE+OI < 7.50E+00, Ce-144 < 4.20E+01 I < 4.00E+01 = < 2.80E+OII lNuclide IC -- __ .,:28-OCT'_ -' '25-NQV :-- -','._'
GR-B I 3.01E+001 +- 9.90E-01 < 3.00E+00 _ < 2.90E+00 I Sr-89 < 8.70E+00 < 9.00E+00 < 6.80E+00 I Sr-90 < 1.40E+00 < 1.70E+00 < 1.60E+00 I Be-7 < 3.40E+01 < 2.90E+01 < 4.IOE+0O l K-40 < 7.90E+01 < 5.30E+01 < 6.80E+01 I Mn-54 < 4.30E1+001 < 2.80E+00 < 5.20E+OO_
Co-58 < 3.90E1+00 <1 3.OOE+00 = < 5.70E+OO_
Fe-59 < 1.20E+01J < 8.80E+O0 =_ _ < 1.5013E+O1 Co-60 < 4.001E+00 < 2.70E+00 = < 4.80E+O00 Zn-65 < 9.20E+00 < I.IOE+OI _ < 2.10E+OI l Zr-95 < 7.30E+00l < 5.20E+00 I < 9.90E+00l Ru-103 < 4.20E+00 _ < 3.80E+00 < 6.60E13+0 Ru-106 < 3.70E+01 <z 2.60E+01 = < 4.50E+OI l Cs-134 < 4.40E+00, < 2.90E+00 < 4.90E+OO l Cs-137 < 4.50E+00 _ < 2.70E+00 < 4.30E+O0 . -
Ba-140 < 8.60E+00 _ < 7.801E+00 < 1.30E+OI _
La-140 < 9.90E+00 8 < 9.00E+00 I_< 1.40E+OI _.
Ce-141 < 5.60E+00l _ 5.70E+00 I < 9.30E+O00 Ce-144 < 2.20E+0 I < 1.50E+0 I I < 2.90E+0 l C-39
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 SURFACE WATER ANALYSIS SW-2 (Control)
(pCi/liter) lde ' 28-lAN l - - 25-FEB ,_,-__j MAR -
Sr-89 I < 9.90E+OO I < 9.30E+00 I <1 9.30E+OO' Sr-90 < 1.70E+00 < 1.70E+00 < 1.70E+OO Be-7 < 4.70E+01 < 3.80E+01 < 3.80E+OI K-40 < 8.90E+01 < 8.50E+01 < 8.50E+O I Mn-54 < 6.70E+00 < 4.40E+00 < 4.40E+OO Co-58 < 6.1 01E3+0 < OEO S.S1OE < 5.50E+OO _
Fe-59 < 1.20E+01 l< 1.40E+01 < 1.40E+OI Co-60 < 5.40E+00, < 5.20E+00 < 5.20E+OO<__
Zn-65 < 1.30E+01 < 1.30E+01 < 1.30E+OI Zr-95 < 9.60E+00 < 8.50E+00 < 8.50E+OO Ru-103 < 5.80E+OOi < 5.90E+OO < 5.90E+OO Ru-106 < 5.20E+O I < 5.SOE3+0I < 5.50E+O I Cs-134 < 6.00E+00 < 4.70E+00 < 4.70E+OO Cs-1 37 < 5.80E+oo0 < 5.30E+00 < 5.30E+OO Ba-140 < 1.101E+01 < 9.701+001 < 9.70E+OO =0 La-140 < 1.30OE+O0I < 1.1I OE+O I < 1.1I OE+O I_
Ce-141 < I.50OE+O I < 7.40E+00 < 7.40E+OO Ce-144 < 3.40E+01 < 2.70E+01 < 2.70E+O I Nuclide ' APR - ' - '
~~fi2 - ______r' '--~~
Sr-89 < 9.00E+00' < 8.20E+00 I <1 6.40E+00 I Sr-90 < 1.80E+OO% < 1.50E+00 l <l 1.60E+OO Be-7 < 4.90E+01 - < 5.70E+01 _________ <1 7.20E+OI K-40 < 8.30E+01l < 8.OOE+014. <l .30E+02 TI Mn-54 < 5.60E+00 < 6.60E+00 <l 9.60E+OO Co-58 < 5.60E+OO < 5.90E+00 < 7.30E+OO
<1 l0 Fe-S9 < I.50E+O01 < 1.40E+01 < 1.80E+OI lIl Co-60 < 7.1OE+OO < 5.50E+OO _ <0 9.40E+OOl Zn-65 < 1.60E+01 l_ < 1.30E+01 l < 2.20E+OI1 Zr-95 < 1.20E+01 < 9.10E+00 _ < 1.40E+0l T_1 Ru-103 < 6.20E+00l < 6.40E+00 l < 7.OOE+OO l_
Ru-106 < 5.30E+OI < 5.50E+O1 l l < 7.40E+OI l__
Cs-134 < 6.30E+00l < 5.80E+00 l < 8.60E+OO Cs-137 < 5.70E+00 < 5.70E+00 _ l < 8.20E+00 Ba-140 < I.OOE+OI < 9.50E+OO '_l <l I.IOE+OI lI l La-140 < 1.20E+O I < I.IOE+O1 l < 1.30E+O l Ce-141 < 8.80E+00l I < 9.40E+00 < 1.20E+Oll Ce-144 < 3.20E+01 <1 3.20E+01 l < 4.00E+OIl O _ _
C-40
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 SURFACE WATER ANALYSIS SW-2 (Control)
(pCi/liter)
INuclide l 29-JUL- -; 26-AUG-4 --
,30-SEP i--___
Sr-89 _ 3.20E+00I < 8.70E+W0 I < 7.50E+O0 I Sr-90 < 1.40E+00= < 1.80E+W0 < 1.40E+O0 _
Be-7 < 4.30E+01 < 6.00E+01 < 3.50E+0 I K-40 < 8.20E+01 < 9.70E+01 = < 6.40E+OI =
Mn-54 < 6.OOE+00 < 6.80E1+00 < 5.80E+0O Co-58 _ 6.50E+00 _ < 7.40E+00 < 4.40E+0 =
Fe-59 < I.1OE+01 = < 1.60E+01 << 1.80E+01 =
Co-60 < 7.20E+00 < 7.50E+00 < 6.20E+O0 Zn-65 < I .50E+OI < 2.20E+01 < 1.40E+0I Zr-95 < 9.60E+00 = < 1.20E+01 = < 9.1OE+00 Ru-103 < 6.50E+00 = < 8.OOE+00 < 6.OOE+O0 =
Ru-106 < 5.40E+01 < 6.90E+01 < 4.90E+OI1 Cs-134 < 7.40E+00 < 8.50E+00 < 3.70E+00 Cs-137 < 5.OOE+00 = < 6.30EW = __ < 5.30E+00O Ba-140 < 9.40E+00 < 1.20E+01 < 6.40E+00 La-140 < I.IOE +OI+ < 1.40E+01 = _ 7.40E+OO Ce-141 < 6.80E1+O0 I < 1.OE+ 01 _ < 7.30E+OO Ce-144 < 3.1 OE+O I I <1 3.70E+01 _ < 2.40E+Ol I
-Nuclide 28-OCT l
-_____ II> 25-NOV'-'-
' l_"- 30-DEC Sr-89 < 9.10OE+00 < 8.60E+00' < 6.70E+O0 l Sr-90 < l.50E+00 < 1.60E+00_ < 1.60E+00 l Be-7 < 4.80E+01 < 3.20E+01l < 4.50E+O1 l K-40 < 7.90E1+01= < 7.20E1+01 l < 8.40E13O l__
Mn-54 < 4.80E+00 < 3.60E+O0 < 5.50E+00 l_3 Co-58 < 5.30E+00 < 4.30E+00- < 5.60E+00 l_3 Fe-59 < 1.30E+01 < 1.20E+011 < 1.30E+O1 II _ I Co-60 < 4.80E+00 < 4.70E+00l < 5.40E3O+0 l Zn-65 < 1.20E+01 < 8.20E1+00 < 2.10E+OI l_l Zr-95 < 8.80E+00 < 8.10E+00l < 8.90E1300 Ru-103 < 6.10E+00 < 3.90E1+00 < 6.80E1+00 l__
Ru-106 < 4.40E+01I < 3.OOE+01l < 4.70E+O1l I I Cs-134 < 5.40E+00_ < 3.90E+003 < 5.20E+O0 l_l Cs-137 < 4.50E+00 < 3.20E+00 < 5.OOE+-i00 Ba-140 < 8.40E+003 < I.OOE+OI < 1.30E+0O La-140 < 9.70E+001 < 1.20E+Ol _< I.50E+0I Ce-141 < 7.60E+003_
_ < 5.40E+00l _ 1.60E+0l Ce-144 < 2.70E+OIl < I.50E+OIl_ < 2.80E+O1 l C-4 1
Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 SURFACE WATER ANALYSIS SW-3 (Indicator)
(pCilliter) l Nuclide ~- <~28-JAdN>>
- 25-FEB ,'- - 25-MAR '^
Sr-89 < 8.80E+001 I < 8.70E+00 I <1 7.80E+OO I Sr-90 < 1.50E+OO < 1.70E+00 = < 1.40E+OO =
Be-7 < 3.90E+0] < 3.80E+01 < 3.10E3+-OI_
K-40 < 7.40E+01 < 6.OOE+01 < 6.OOE+O1 Mn-54 < 4.90E+00 < 4.OOE+00 < 3.60E+oo Co-58 < 4.60E+00 < 4.OOE+00 < 3.20E+OO Fe-59 < 1.30E+01 < 9.10E+00 = < 7.90E+OO0 Co-60 < 5.60E+00 < 4.40E+00 _ < 4.30E+OO Zn-65 < 1.30E+O1 < 1.IOE+OI < 9.40E+OO Zr-95 < 8.90E+00 < 6.50E+00 < 6.30E+OO Ru-103 < 6.OOE+00 < 4.40E+00 < 3.80E+OO Ru-106 < 4.70E+01 < 3.60E+01 _ < 3.60E+O1 Cs-134 < 5.50E+OO < 5.60E+00 < 4.OOE+OO Cs-137 < 4.40E+00 < 3.70E+00 < 3.90E+OO Ba-140 < 9.70E+00 _< 7.70E+OO < 5.90E+OO I La-140 < I IIOE+OIl < 8.90E+00 < 6.80E+OO Ce-141 < 6.40E+00 < 6.50E+OO < 5.50E+OO Ce-144 < 2.4 < 2.40E+01 < 2.1OE+O I lNuclidc'- j-l-'n-"29-APR i ______IL1 27-M- *. 24-JUN ______'
Sr-89 < 6.90E+00' < 7.80E+00 < 5.80E+OO I Sr-90 < 1.60E+00 < 1.70E+OO <1 1.50E+001 Be-7 K-40
< 3.70E+O01
< 8.70E+01l
[< 5.OOE+OI
< 8.60E+01
<1 6.1OE+O I
< 1.30E+02 Mn-54 < 5.50E+00 < 6.50E+00 <l 6.50E+OO Co-58 < 4.60E+00 < 5.70E+00 < 7.1OE+OO Fe-59 I 1.IOE+O01 < 1.50E+O1 <__1.40E+01 Co-60 < 5.90E+00l < 6.OOE+00 < 9.60E+OO Zn-65 < ]I.IE+0I < 1.50E+OIl _______ < 1.80E+OI1 Zr-95 < 9.40E+OO < 1.IOE+O I < 1.40E+01 Ru-103 < 5.20E+00 < 6.70E+00 < 8.30E+OO Ru-106 < 4.80E+01I < 5.30E+01_ < 7.70E+O1l Cs-134 < 5.20E+00 < 6.60E+00 < 9.OOE+OO Cs-137 < 5.30E+00 _ < 5.70E+00 < 6.90E+00
_ t _ I ,__
Ba-140 < 9.30E+00 _ < 8.20E+W1O < 1.30E+O1 La-140 __< .IOE+O I < 9.40E+OO <l 1.50E+O01 Ce-141 < 6.30E+00 < 8.50E+00I <1 9.50E+OO Ce-144 < 2.40E+01 I <1 3.30E+01lII I <1 2.90E+O1l C-42
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 SURFACE WATER ANALYSIS SW-3 (Indicator)
(pCilliter) l Nuclide I -- 29-JUL - -. ] l -. '30-SEP.
< 8.80E+00 I < 6.30E+ O I
I Sr-89 _ 3.30E+00 _
Sr-90 < 1.40E+00 < 1.80E+00 < 1.80E+00 _
Be-7 < 5.40E+01 < 6.20E+01 < 3.30E+O1 K-40 < 1.1OE+02_ _< 9.30E+01 = < 6.70E+OI =1 Mn-54 < 6.70E+00 < 5.60E+00 < 4.80E+00 =
Co-58 < 6.1OE+00 _ < 6.40E+00 = < 5.OOE+0O =
Fe-59 < 1.40E+01 < 1.80E+01 < 1.70E+OI Co-60 < 6.90E+00 < 7.70E+00 < 7.60E+OO Zn-65 < 1.80E+01 _ 1.60E+OI _< I .OOE+O I Zr-95 < 1.20E+01 < 1.30E+01 < 9.OOE+OO Ru-103 < 7.80E+00 _ < 6.80E+O0 < 5.50E+O0 Ru-106 < 5.90E+01 < 6.40E+OI < 5.00E+OI Cs-134 < 7.40E+00 < 8.30E+00 = < 5.I OE+00 I Cs-137 < 7.60E+00 _ < 8.20E+00 = < 6.1 OE+OO =
Ba-140 < 8.70E+00 < 1.20E+01 < 9.80E+O0 La-140 < I.OOE+O1 _<_ 1.40E+OI _ < IOE+OI Ce-141 < 9.30E+O0_ < I.OOE+OI < 7.30E+O0 Ce-144 < 3.20E+O I=I < 3.80E+01 = < 3.OOE+OI =
lNuclide 'l - .28-:CT l25-NOV
- _::_ - 3...
0-DEC E-::
Sr-89 < 8.70E+001 I < 8.20E+00, I < 6.80E+0 Sr-90 < 1.40E+OO < I.50E+O00 < 1.60E+0 Be-7 < 3.10E+01 _ < 2.50E+01 = < 3.60E+01 K-40 < 6.60E+01 < 4.70E+01 < 7.30E+0 _
Mn-54 < 4.60E+00 _ < 2.60E+00 < 4.1OE+00 Co-58 _ 4 70E+001 _ 3.20E+__i < 4.1__E+_
Fe-59 I_< I.IOE+Ol < 9.60E+OOj < 01 1.20E+Ol Co-60 < 3.90E+00 < 3.20E+00_ < 4.70E+O0 L Zn-65 Z - 5 < 1.20E+O-I
__ __ __ ___ _ < .90E+00 I _ _ ___ < 1.IOE+OI I Zr-95 < 7.60E+O0 < 5.50E+00_ < 6.30E+00 I Ru-103 < 5.30E+00 < 3.50E+00 < 4.60E+00 Ru-106 < 4.40E+01 < 2.60E+01 l < 3.80E+0 l Cs-134 < 4.50E+00 < 2.90E+00 < 4.OOE+00 Cs-137 _ 4.30E+00< _ 2.80E+00 < 4.40E+00 _
Ba-140 _ 7.70E+00 _ 8 .90E+00 < 9.20E+00 La-140 < 8.80E+00 < I.OOE+O1l < I.IOE+O Il l Ce-141 6.60E+00 <_ 7.50E+00l < 5.90E+00 Ce-144 2.30E+01 I_ <1 .40E+01 I < 2.10E+OI_l l C-43
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 DRINKING AND SURFACE WATER QUARTERLY COMPOSITE SAMPLES Tritium (pCilliter) l Station -* 'Frst Quaer ondQuarter I__I__II__I DW-I I <1 1.30E+031 < 1.30E+03 I_
DW-2 <1 1.30E+03l < 1.20E+03 I SW-2 <1 1.30E+031 < 1.30E+03_I SW-3 I <1 1.30E+03 <I1=.30E+031 I l'Station l - ThirdQuarter-- ' : u Fourth Quarter -
DW-I < 1.20E+03 _ < 9.50E+021 l DW-2 < 1.20E+03 < 9.40E+021 I SW-2 SW-3 I
< 1 .20E+03 1 .20E+03 =
I
< 9.40E+02
< 9.40E+02 i
[
I
___l _
C-44
Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 GROUNDWATER ANALYSIS GW-1 (Indicator)
(pCi/liter)
Nuclide - First Quier -Sec6nd Quarter-'
Be-7 I < 2.20E+O1I I <1 4.30E+OI I K-40 I< 3.40E+O1 _< 7.1OE+O I Mn-54 I< 2.40E+00 <1 5.1OE OOE Co-58 < 2.30E+00 <1 5.40E+OO Fe-59 l< 4.80E+OO <1 1.IOE+O1I _ _
Co-60 <l 3 OOE+00_ < 4I70E+OO Zn-65 < 5.70E+00 < 1.50E+O1 Zr-95 I_< 4.40E+D < 7.70E+OO Ru-103 < 2.80E+OO < 5.60E+00 Ru-106 < 2.30E+01 < 4.OOE+OI Cs-134 < 2.40E+00 < 5.50E+OO Cs-137 < 2.40E+00 < 4.80E+OO Ba-140 < 5.80E+00, < 9.80E+00 La-140 I< 6.60E+I0_ < I.IOE+O I Ce-141 < 4.70E+00 < 7.80E+oo Ce-144 < 1.50E+01 < 3.OOE+O1 H-3 < 1.40E+031 < 1.20E+03 l-Nuclide -'l ' Th'irdQuartei "Fourth Quartcr' Be-7 < 3.20E+OI _ < 1.50E+OI I K-40 < 6.80E+01 < 3.OOE+OI I Mn-54 < 4.30E+00 < 1.50E+OO I Co-58 < 4.80E+00 __< 1.90E+OO, Fe-59 < 1.30E+01 = < 6.90E+00 Co-60 < 6.20E+00 < 1.80E+00 _
Zn-65 < 1. IOE+O1 _< 3.70E+OO' Zr-95 <' 6.80E+00 < 3.20E+OO Ru-103 < 5.80E+00 < 2.30E+OO Ru-106 < 3.30E+01 =<1.40E+OII Cs-134 <1 4.50E+00_= < 1.60E+OO _
Cs-137 d 4.70E+OC _ < 1.60E+OO Ba-140 < 6.50E+00 < 8.40E+OO _
La-140 < 7.50E+OC- < 9.70E+OO, Ce-141 < 7.30E+O0 = < 3.80E+OO, Ce-144 < 2.70E+O1 I < I.OOE+OII H-3 < 1.30E+03 I< 9._OE+02 C-45
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 GROUNDWATER ANALYSIS GW-2 (Indicator)
(pCi/liter) l iNuclide' Qari
- -' irst er 'Second Quarter--
Be-7 < 2.40E+O1 < 2.80E+O1 _-
K-40 < 3.70E+01 < 4.1 OE+OI _
Mn-54 < 2.30E+00 < 2.80E+OO Co-58 < 2.80E+00 < 3.70E+O0 Fe-59 < 5.90E+00 < 6.30E+00 _
Co-60 < 2.70E+00 < 3.10E+OOE Zn-65 < 6.OOE+OO _< 1 1.OOE+O1 Zr-95 < 5.20E+00 < 5.90E+O _ _
Ru-103 < 2.8I0E+0 =_____ < 3.40E+OO _ _
Ru-106 < 2.10E+01 = < 2.90E+OI I Cs-134 < 2.90E+00 , < 3.40E+00! l Cs-137 < 2.70E+00 < 2.80E+OO l Ba-140 < 6.30E+00 < 3.50E+00, l La-140 < 7.30E+00 < 4.0OE+O: l Ce-141 < 4.70E+00 _ < 5.90E+OO 1 Ce-144 < 1.30E+O1 _ <1 2.OOE+O I Il l H-3 <_ 1.40E+031 < 1_.20E+031l I_,,,,,_ I Nuclide t '.ThirQute . - .Fourth Quarter , -
Be-7 <l 3.80E+01 < 1.90E+01 K-40 <I 6.80E+01 < 3.70E+OI Mn-54 <1 4.40E+00 < 1.80E+00 Co-58 < 4.90E+00 < 2.1OE+00 Fe-59 < 1.20E+01 l < 1.40E+O1 l Co-60 < 5.80E+00 < 1.80E+OO _
Zn-65 < 1.70E+01 < 4.60E+OO _
Zr-95 < 7.70E+00l < 4.20E+OOl _
Ru-103 < 4.60E+00 <_ 2.70E+O_00 Ru-106 <1 3.70E+01 l<_ 1.60E+0<l l Cs-134 < 4.50E+00 <l 2.1OE+OOl l Cs-137 < 5.30E+00 < 1.60E+OO ji Ba-140 < 8 0 < 9.40E+OOt _
La-140 <l 9.70E+_ <l I._IE+_1 Ce-141 < 6.60E+00 <1 4.20E+O0, l Ce-144 < 2.60E+01 <1
' 9.OOE+oo! I H-3 < 1.30E+031 I_ <1 9.1 OE+02 I C-46
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-3 (Indicator)
(pCi/fiter) lNuclide l' First Qu'arter > SecondQuarter, '--'
Be-7 < 3.OOE+O1 _ < 3.20E+O1 _
K-40 < 4.10E+01 < 5.50E+OI _
Mn-54 < 3.30E+OO < 4.40E+OO Co-58 < 3.50E+00, < 4.30E+OO _ _
Fe-59 < 6.60E+00 < 8.40E+OO-0 Co-60 <I 2.70E+00- < 4.20E+OO _ _
Zn-65 < 1.20E+O1 < 1.80E+OI Zr-95 <l 4.90E+00 < 5.90E+00 Ru-103 <c 4.40E+OO < 4.60E+OO =
Ru-106 < 2.70E+01 < 3.40E+O I Cs-134 < 4.OOE+OO < 3.90E+00 Cs-137 < 3.1OE+OO < 4.1 OE+OO Ba-140 < 7.90E+00 =__ < 7.OOE+O La-140 < 9.10E+00 _ <___ 8.I1OE+OO ____
Ce-141 < 7.1OE+OO < 7.60E+OO Ce-144 < 2.OOE+O1 c 2.70E+01 H-3 I <1 1.40E+03 Ic<1 1.20E+03 -
l 1.uclide-]' .-4'Th iidQuaer:> .' JV ." Fourth Quarte'r ',
Be-7 < 4.70E+O1 I c< 1.80E+01 I K-40 c 7.OOE+OI c< 3.20E+Ol I Mn-54 < 4.90E+OO < 2.1 OE+OO_
Co-58 < 4.60E+OO c
< 2.10E+OO T Fe-59 < 1.60E+O1 _< 7.60E+OO l Co-60 < 6.60E+OOl < I.90E+OO1 l Zn-65 < 1.40E+OI< I14.60E+OO0 l Zr-95 < ______+_ l< 3.80E+OO: T Ru-103 < 6.OOE+OO _ < 2.90E+OO T Ru-106 <l 4.30E+OIl < 1.70E+O1 I Cs-134 < 5.90E+00 _ _ < 1.70E+OO,' l Cs-]37 < 5.40E+00' cl 1.80E++OO Ba-140 < 7.80E+00' < 8.90E+OO, La-140 T<' 9.0 o c LOOE+OI
< l Ce-141 < 7.40E+00 < 5.40E+O00 l Ce-144 < 2.50E+OIl <cl l.lOE+OIl H-3 I < 1.30E+031 I< 9.20E+02j C-47
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 GROUNDWATER ANALYSIS GW-4 (Control)
(pCi/liter) ltNuclide J '.Ftier -,Second Quarter ' -`,
Be-7 I < 2.60E+01 < 4.30E+OI I K-40 < 3.90E+01 < 8.OOE+OI I Mn-54 < 3.20E+00= < 4.50E+OO I Co-58 < 3.20E+00 <1 4.1 OE+OO Fe-59 < 7.60E+00' < 1.30E+OI Co-60 < 2.70E+00' < 4.60E+OO Zn-65 < 6.90E+00 _ < 1.30E+O1 Zr-95 <c 6.20E+00 < 9.80E+OO =
Ru-103 < 4.00E+00 _ < 5.OOE+OO_
Ru-106 < 2.60_+0II < 4.10E+OlI Cs-134 < 3.00E+001 < 6.60E+OO Cs-137 < 2.70E+001 < 6.00E+OO =
Ba-140 < 6.60E+00 _ < 1.20E+OI La-140 < 7.60E+001 < 1.40E+O I Ce-141 < 6.40E+00 < 7.1 OE+OO Ce-144 <j 2.OE+01 _= < 3.IOE+O I H-3 < 1.40E+03 IlI <1 1.20E+03 I Nuclide 2 Third Quarter'., - Fourth Quarter2' --
Be-7 < 3.20E+O0 I l_ _ < 1.80E+OI K-40 < 4.30E+O1_ < 2.60E+O1 T Mn-54 <1 3.70E+00l < 1.80E+00 Co-58 < 3.50E+00 < 2.1 OE+ ___
Fe-59 <1 9.80E+00 < 5.80E+ i__
Co-60 <I 3.60E+00 < 1.80E+00 I Zn-65 < 1.60E+01 = < 5.40E+00O T Zr-95 < 7.OOE+00 < 3.80E+OOl Ru-103 < 4.50E+00 < 3.1E OOE __
Ru-106 < 3.1OE+O1 < 1.60E3+Oll Cs-134 <1 3.50E+00 < 1.80E+OO l Cs-137 < 3.80E+00 < 1.60E+OOl Ba-140 <l 5.1OE+OO < 8.80E+OO I La-140 <l 5.80E+OOl < 1.OOE+OI l Ce-141 <1 7.80E+00l < 7.80E+OO j Ce-144 <1 2.50E+01 I < 1.20E+OI j H-3 <1 1.30E+03 I < 9.OOE+02 l C-48
Fermi 2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 SEDIMENT ANALYSIS S-1 (Indicator)
(pCi/kg dry)
Nuclide JIN< S . 20-NOV Sr-89 I < 2.40E+021 _ I_ < 2.40E+021 I Sr-90 < 2.OOE+02 = < 2.40E+02i _
Be-7 < 1.20E+02 < 7.30E+02 l K-40 9.92E+03 +/- 1.80E+02 _ I.50E+04 +/- 15.40E+02 Mn-54 <i 1.30E+01 _ < 4.90E+01 Co-58 < 1.50E+01 _ __ 8.OOE+01 Fe-59 < 4.60E+01 < 3.OOE+02 I Co-60 < 1.30E+01 < 5.50E+O lI _
Zn-65 < 6.30E+01 < 1.70E+02 Zr-95 '< 2.70E+03 < E.40E+02j=
Ru-103 < 1.60E+01 < 9.40E+0 Ru-106 < 1.OOE+02 < 3.80E+02 Cs-134 < 4.10E+01 < 5.40E+0 l Cs-137 < 1.20E+0I _ I.05E+02 +/- 11.90E+0I Ba-140 < 2.30E+02 =<_ 11.60E+03 I La-140 < 1.1OE+02 <_ 1.80E+03 Ce-141 <1 3.1OE+OI <1 2.10OE+02 I Ce-144 <1 7.30E+0I < 2.40E+021l
<1 S-2 (Indicator)
(pCi/kg dry)
[Nuclide - 6-JUN l _ 20-NOV _ _-----
Sr-89 I 2.60E+021 < 2.60E+02 I Sr-90 <l 2.40E+021 < 2.90E+02 I Be-7 <I 3.1OE+02 < 5.1OE+02 K-40 11.08E+04 +/- 2.90E+02 _ I.lOE+04 +/- 14.10E+O2 Mn-54 < 2.60E+01 _ < 4.OOE+O1 Co-58 < 3.OOE+01 _____ <_ 5.90E+01 Fe-59 < 8.50E+01 =<_ 1.80E+02 Co-60 < 2.90E+01 _1 3.OOE+O I Zn-65 < 1.20E+02 < 1.70E+02 Zr-95 < I.IOE+02 _ < 2.10E+02 Ru-103 < 3.50E+01 _ < 9.90E+OI0 Ru-106 < 2.50E+02 < 3.20E+02 Cs-134 < 9.30E+01 <l 1.40E+02 Cs-137 < 2.50E+01 _ 7.90E+01 +/- l1.60E+0I Ba-140 < 4.30E+02 = _<l 2.80E+03 _
La-140 < 2.1OE+02 _ < 1.70E+03 _
Ce-141 < 5.90E+01 I.70E+02 I<
Ce-144 < I.50E+02 _<2.20E+02 <l_
C-49
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 SEDIMENT ANALYSIS S-3 (Indicator)
(pCi/kg dry)
Nu~cide, l -;" ;t'-6-JUN- -- -' <'-.- 20-NOV--:'__
Sr-89 < 2.20E+021 < 2.70E+021 Sr-90 < 1.80E+021 < 1.60E+02 Be-7 < L.IOE+021 < 3.40E+02 K-40 1.25E+04 +/- 1.70E+02 1.1 6E+04 +/- 13.40E+02 Mn-54 < I.OOE+OI l < 2.10E+OIr I Co-58 < 1.30E+01 l < 3.50E+OI lI l Fe-59 < 4.OOE+01 < 1.30E+02l I Co-60 <I 1.1OE+0OI < 2.80E+OI0 I Zn-65 < 5.20E+01 < 7.60E+0 I Zr-95 <l 2.80E+02 = < 1.30E+02 =
Ru-103 <I 1.40E+01 < 4.70E+OIl l Ru-106 <[ 7.80E+01l- < 1.70E+02 _ -
Cs-134 < 3.30E+01 < 8.60E+0I Cs-137 < 9.OOE+00 < 2.1OE+0I Ba-140 < 1.80E+02 = < 1.80E+03 =
La-140 <l 9.70E+01 < 8.90E+02 Ce-141 < 2.90E+01 < 9.60E+0I Ce-144 < I1.20E+02 I < 1.30E+02 S-4 (Indicator)
(pCi/kg dry)
[Nuclide - 10-JUL '_'_l1
______' 9-DEC Sr-89 < 2.50E+02 = <1 2.50E+02 I Sr-90 < 2.80E+02 <1 1.40E+02l Be-7 < 2.10E+02 <1 3.20E+02 I K-40 8.1OE+03 +/- 2.20E+02 1.09E+04 +/- l4.OOE+02 Mn-54 < 1.80E+01 < 3.10E+OIl l Co-58 < 2.10E+01 = < 3.80E+01ll Fe-59 < 5.70E+I01 <l I.IOE+02l Co-60 < 1.70E+01 < 2.90E+01 I Zn-65 < 8.40E+01 <_ 1.50E+02 Zr-95 < 5.10E+0I < I.IOE-1+02 _
Ru-103 < 2.70E+01 < 4.10E+0I l I Ru-106 < 1.90E+02 < 2.20E+02 l Cs-134 < 6.70E+I01 < 1. OE+02 1 Cs-137 < 1.70E+01 < 2.40E+01 Ba-140 < 2.60E+02 < 9.40E+02 _
La-140 < 1.50E+02 = <1 4.OOE+02 _
Ce-141 _<_ 5.0E+01 I< 8.80E+01 l__
Ce-144 <1 1.20E+021 <1 1.40E+02 I C-SO
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 SEDIMENT ANALYSIS S-S (Control)
(pCi/kg dry)
-Nuclide- -. '.: 14-JULc' i7aj-:l -- 20-NOV - '
Sr-89 < 2.40E+021 <1 2.20E+02l 1 Sr-90 < 2.20E+02 _ 2.20E+02 Be-7 = 2.96E+02 +/- 4.80E+01 _ 4.20E+02 = -
K-40 9.59E+03 +/- 1.60E+02 __ 1.16E+04 +t- 4.1 OE+02 Mn-54 < 1.20E+01 < 2.80E-+OI Co-58 < I.50E+O1 _ < S.1 OE+0 I Fe-59 < 4.10E+01 _ < 1.70E+02 =
Co-60 <_ _1_.20E+O T _ 3.001_+
Zn-65 < 6.00E+01 _ 1.60E+02 Zr-95 < 1.40E+021 < 1.1IOE+04 _I Ru-103 < 1.70E+01 I <_ 6.50E+O1 =
Ru-106 < 1.1OE-+02 = < 2.40E+02 Cs-134 < 4.50E1+01 < 2.40E+01 Cs-137 4.91 E+O I +/- 4.80E+00 7.60E+01 +/- II.30E+0I Ba-140 < I.50E+02 _ 2.70E+03 I La-140 < 7.70E1i3 = _ < I.50E+03 Ce-141 < 2.80E+01 < 1.40E+02 Ce-144 <L 8.003E+01 _ -- <I 1.90E+02 C-51
Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 FISH ANALYSIS F-1 (Control)
(pCi/kg wet) lNudlide 'l --3-JUN Bullhead: -.- '* 3-UN3Muskie: - l 3-JUN RockBass -;;
Sr-89 < 2.20E+02 < 2.20E+02 I < 2.20E+02 Sr-90 < 2.1 OE+02 < 2.60E+02 < 2.30E+02 Be-7 < 5.30E+02 < 4.40E+02 = < 6.20E+02 K-40 2.06E+03 +/- 2.70E+02 - 3.12E+03 +/- 3.90E+02 2.94E+03 +/ 4.OOE+02 Mn-54 < 5.20E+01 < 4.1OE+O1 < 5.00E+O I_=
Co-58 < 5.90E+01 = < 5.80E+01 _ < 7.70E+OI Fe-59 < 1.50E+02 < 1.60E+02 < 1.80E+02 Co-60 < 5.1OE+O1 < 4.90E+01 < 6.1 OE+O I Zn-65 < L.30E+02 < 1.20E+02 = < 1.40E+02 =
Zr-95 < 11.OOE+02 < 9.80E+01 < 1.40E+02 Ru-103 < 8.OOE+01 < 6.60E+01 < 9.20E+O I Ru-106 < 4.50E+02 __< 4.80E+02 < 5.OOE+02 Cs-134 < 5.20E+01 = < 5.60E+01 = < 5.1OE+O I Cs-137 < 4.80E+01 <
< 5.10E+01 = < 5.50E+OI =
Ba-140 < 3.70E+02 < 3.60E+02 < 4.60E+02 La-140 < 4.20E+02 < 4.10E+02 < 5.30E1+02 _
Ce-141 < 1.20E+02 < 9.20E+O I < 1. IOE+02 Ce-144 < 2.20E+02 = < 1.80E+02 = < 2.60E+02 Nuclide' -l, 'i',' Suker;. ' 3-JUN Walleye i-3-JUN WlBass--. -
Sr-89 I < 2.OOE+021 __ j <1 2.OOE+02 lIj <1 l.90E+02 Sr-90 < 2.10E+02 _______ < 2.20E+02_ _ < 2.OOE+02 Be-7 < 5.40E+02 < 4.OOE+02 = < 3.90E1+02 =
K-40 3.81 E+03 +/- 3.20E+02 - 3.14E+03 +/- 3.40E+02 2.14E+03 +/- 3.20E+02 Mn-54 < 4.80E1+01 < 3.80E+01 < 4.10E+O1 _I Co-58 < 6.50E+01 < 4.90E+01 < 4.30E+O1 Fe-59 < 1.60E+02 < 1.60E+02 < 1.40E+02 Co-60 < 5.20E+OI < 4.lOE+O1 < 5.90E+O _-
Zn-65 < 1.30E+02 < 1.20E+02 = < 9.60E+OI1 Zr-95 < 1.20E+02 < 7.60E+01 < 8.70E+O I Ru-103 < 8.30E+01 < 6.60E+01 < 5.20E1+O1 Ru-106 < 4.30E+02 < 2.30E1+02 < 2.80E+02 _
Cs-134 < 5.30E+01 < 3.90E+01 < 3.30E+O1 Cs-137 < 4.80E+01 < 4.80E+01 = < 3.50E+OI -
Ba-140 < 3.20E+02 < 2.70E+02 < 2.80E+02 La-140 < 3.60E+02 < 3.1OE+02 < 3.20E+02 Ce-141 < 1.IOE+02= < 9.80E+01 =_ _ < 7.70E+OI =
Ce-144 < 2.50E+02 I < 1.90E+02 I < E.30E+02 I C-52
Fermi 2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental Operating Report FERMI 2 FISH ANALYSIS F-i (Control)
(pCi/kg wet)
I Nuclide- - l¢:--:;-3-JUN WhitePerch - -- 1l .K'3-JUN YellowPerch -j NOV Bullhead Sr-89 I < 2.20E+021 < 2.00E+02 <1 2.60E+02 I Sr-90 < 2.30E+02l 2.lOEi02 < 2.OOE+02 _
Be-7 <_ 6.80E+021 < 6.IOE+02 ____ l < 4.50E+02 l__
K-40 _ 3.09E+03 +/- 3.60E+02 3.44E+03 +1 3.60E+02 2.31 E+03 +/- 1.60E+02 Mn-54 < 6.30E+01 < 5.40E+01 < 3.00E+0O Co-58 < 7.80E+01 <1 6.80E+01 < 4.50E+OI=
Fe-59 < 2.00E+02 < I.70E+02 < 1.60E+02 Co-60 < 5.80E+01 < 6.60E+01 < 2.40E+0O Zn-65 I_ 1.40E1+02 < 1.40E+02 < 1.IOE+02 __
Zr-95 < 1.30E+02 < 1.1OE-+02 = < 8.50E+O I1 Ru-103 < l.OOE+02 < 8.20E+01 < 7.50E+OI=__
Ru-106 < 5.70E+02 < 5.90E+02 < 2.50E+02 Cs-134 < 6.60E+01 < 6.30E+01 < 2.50E+OI Cs-137 < 6.30E+01 < 6.10E+01 < 2.40E+OI _
Ba-140 < 6.30E+02 < 4.40E1+02 = < 9.50E+02 =
La-140 < 7.30E+02 < 5.10E-+02 < .IOE+03 Ce-141 < 1.40E+02 _ 1.40E+02 < 1.20E+02 Ce-144 < 2.70E+02 _ < 2.50E+02 I < 1.30E+02 =
Nuclide r- :.--'20-NOVWalleye Sr-89 < 2.10E+021 Sr-90 < 1.60E+021 Be-7 < 6.40E+02 _
K-40 2.97E+03 +/- 3.20E+02 Mn-54 < 4.80E+0I Co-58 < 6.90E+OI Fe-59 < 2.20E+02 Co-60 < 3.80E+OI Zn-65 < 1.20E+02 Zr-95 < 1.30E+02 Ru-103 < 9.40E+OI Ru-106 < 4.00E-+02 Cs-134 < 3.20E+O1 Cs-137 _< 3.90E+O=1 Ba-140 _ 1.50E+03 La-140 < 1.70E+03 Ce-141 < 1.50E+02 _
Ce-144 < I.50E+021 C-53
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 FISH ANALYSIS F-2 (Indicator)
(pCi/kg wet)
J- .:.
lNuclide ' -- ' ^282'MAY -^Cajpi' '.'i28-MAY Catfish; - ;Dmr28-MAY Sr-89 < 2.60E+021 < 1.80E+02 I _ <1 2.70E+02 I Sr-90 < 2.30E+02 I < 1.80E+02 < 2.50E+02 Be-7 < 3.20E+02 < 4.60E+02 < 4.1 OE+02 K-40 = 1.81 E+03 +/- 2.30E+02 2.98E+03 +/ 3.60E+02 2.69E+03 +/ 2.70E+02 Mn-54 < 3.30E+01 < 3.60E+01 <. 3.20E+O1 _
Co-58 < 4.90E+01 < 6.1 OE+O I < 4.30E+O I Fe-59 < 9.50E+01 < 2.10E+02 < 1.20E+02 Co-60 < 3.70E+01 < 3.60E+01 < 3.40E+O I Zn-65 < 7.50E+01 < 1.20E+02 < 9.1 OE+O I_=
Zr-95 < 7.20E+O1 < 1.OOE+02 < 6.90E+O1 _
Ru-103 < 5.30E+01 < 7.70E+01 < 6.OOE+O1 Ru-106 < 3.OOE+02 < 4.1OE+02 < 3.OOE+02 _
Cs-134 < 3.50E+01 < 4.20E+01 = 3.1OE+OII Cs-137 < 3.20E+01 _ < 4.20E+01 < 3.50E+O1 Ba-140 < 3.40E+02 < 4.50E+02 < 3.70E+02 La-140 < 3.90E+02 < 5.20E+02 < 4.20E+02 =
Ce-141 < 8.00E+OI 0 1.IOE+021 < 8.80E+O1 = _
Ce-144 < 1.60E+02 I <1 2.1OE+02 = < 1.70E+02 =
Nuclide II.lMAY ~Pik' I28-MAY ( :28-MAY VWaly-z:
Sr-89 < 2.40E+021 _ I_ < 2.30E+02 I <1 2.20E+02 I__
Sr-90 < 2.30E+02 < 2.30E+02 < 3.OOE+02 I Be-7 < 4.10E+02 < 5.50E+02 < 4.90E+02 K-40 3.33E+03 +/- 2.80E+02 3.57E+03 +/ 2.90E+02 2.85E+03 +/- 2.70E+02 Mn-54 < 3.50E+01 < 4.80E+01 < 3.50E+01 Co-58 < 4.90E+01 < 6.50E+01 < 3.70E+01 Fe-59 < 1.30E+02 < 1.70E+02 < 1.40E+02 Co-60 < 3.60E+01 < 4.50E+01 < 4.20E+O1 I_
Zn-65 < 1.OOE+02 < '1.20E+02 __ < .IOE+02 Zr-95 < 9.60E+O1 < 1.OOE+02 < 7.80E+01 Ru-103 < 5.60E+01 < 8.OOE+01 < 6.80E+01 Ru-106 < 2.90E+021 < 4.10E+02 < 3.70E+02 Cs-134 < 3.50E+O1 _ < 4.30E+01 < 4.30E+01 Cs-137 < 3.30E+01 _ < 4.80E+01 < 2.90E+01 Ba-140 < 3.50E+02 < 4.50E+02 < 2.10E+02 La-140 < 4.OOE+02 < 5.20E+02 < 2.40E+02 Ce-141 < 9.40E+01 ______ <I 1.30E+02 _ _ < 9.80E+01 l _ __
Ce-144 < 1.80E+02 I < 2.30E+02 = < 1.60E+02 7 1 C-54
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport FERMI 2 FISH ANALYSIS F-2 (Indicator)
(pCi/kg wet)
Nuclide <-
l 28-MAY :White Bass ;28-MAY 28-A ' T Yellow Perch-'
Sr-89 < 2.10E+02= <1 2.OOE+02 I < 2.20E+02 I Sr-90 < 2.1OE+02 < 2.OOE+02 < 1.90E+02 Be-7 < 5.1OE+02 < 4.70E+02 < 6.80E+02 K-40 2.32E+03 +/- 3.1 OE+02 2.18E+03 +/ 3.20E+02 = 3.13E+03 +/- 3.80E+02 Mn-54 < 4.20E+01 < 5.OOE+01 ___0< 6.OOE+O1 = -
Co-58 < 4.90E+01 < 5.40E+01 < 7.90E+O1 _
Fe-59 < 1.70E+02 < 1.70E+02 < 2.20E+02 _
Co-60 < 3.90E+01 < 3.40E+01 < 7.30E+O1 Zn-65 < 1.IOE+02 < 1.IOE+02 < 1.70E+02 Zr-95 < 9.70E+0l < 9.50E+01 < 1.20E+02 Ru-103 < 8.20E1+01 < 7.90E+OI < 1.OOE+02 Ru-106 < 3.40E1+02 < 3.50E+02 < 5.80E+02 Cs-134 < 4.20E+01 < 4.80E+O1 < 5.401E+O1 _
Cs-137 < 5.OOE+01 < 3.70E+01 < 6.OOE+O1 _
Ba-140 < 6.30E+02 < 4.30E+02 . < 7.30E+02 La-140 < 7.20E+02 < 5.OOE+02 <_ 8.40E+02 _
Ce-141 < 1.20E+021 < I.OOE+02 < 1.30E+02 Ce-144 < 1.80E+02 I < 1.30E+02 _< 2.50E+02 =
Nuclide' l 1-NOV-'Steelhead -'-' 1--NOV Walleye' 1 -NOV WhitePerch Sr-89 I < 2.50E+02 I < 1.90E+02 < 2.40E+02 _
Sr-90 < L.70E+02 < 1.30E+02 < 1.60E+02 Be-7 < 5.IOE+02 < 4.30E+02 < 4.30E+02 ___________
K-40 3.08E+03 +/- 2.40E+02 2.39E+03 +/- 2.30E+02 2.69E+03 +1 1.50E+02 Mn-54 - < 2.70E+01 < 2.60E+01 < 2.80E+ _-
Co-58 < 5.OOE+01 < 6.20E+01 < 4.50E+01 Fe-59 I < 2.40E+02= < 1.80E+02 < 2.00E+02 Co-60 < 3.70E+0I1 < 3.50E+01 < 2.50E+O1 I Zn-65 < 8.70E+01 < 7.90E+01 < 7.00E+OI _
Zr-95 < 7.50E+01 < 1.20E+02 < 8.10E+1I _I Ru-103 < 8.1OE+O1 _I 8.20E+01 < 7.80E+O1 =
Ru-106 < 2.80E+02l < 2.20E+02 < 2.50E+02 Cs-134 < 2.40E+01 _ 3.20E+01 < 2.60E+01 Cs-137 3.70E+O1 +/- 1.IOE+OI < 2.70E+01 < 2.40E+01 Ba-140 < 1.50E+03 _ < 1.90E+03 < 1.30E+03 La-140 < 1.70E+03l < 2.20E+03 < 1.50E+03 =
Ce-141 < 1.20E+02 <1 1.30E1+02 < 1.40E+02 Ce-144 I < 1.40E+02 I<1_ 1.IOE+02 < L.30E+02 =
C-55
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 FISH ANALYSIS*
F-3 (Control)
(pCi/kg wet) lNuclide': 24-MAY ZCarp ' J i----;24-MAY-'Walleye l'24-MAY-White
- Bass ¢-i > .-
Sr-89 < 2.1OE+02 < 2.80E+02 < 2.30E+02 I Sr-90 < 1.80E+02 < 2.50E+02 < 2.OOE+02 Be-7 < 4.80E+02 < 5.70E+02 < 4.80E+02 K-40 1.92E+03 +/- 3.20E+02 3.51 E+03 +/ 3.60E+02 2.07E+03 +/- 3.OOE+02 Mn-54 < 4.1OE+OI _<_ 04.1OE+O1 _ _ __ < 4.00E+OI =
Co-58 < 6.50E+01 < 5.90E+01 = < 6.30E+O1 =
Fe-59 < 1.80E+02 < 1.50E+02 < 1.30E1+02 Co-60 < 4.80E+01 < 3.90E+01 < 4.30E+O1 Zn-65 < I .OOE+02 < 1.20E+02 < 1.1 OE+02 Zr-95 < 8.40E+O1 < 1.1OE+02 = < 11.OOE+02 Ru-103 < 7.70E+01 < 8.11OE+O I < 6.20E+O I Ru-106 < 3.50E+02 < 4.20E+02 < 3.1 OE-+02 Cs-134 < 3.90E+01 _ < 4.50E+01 < 4.10E+OIE_
Cs-137 < 4.50E+01 < 3.80E+01 < 3.1 OE+O1 I Ba-140 < 5.70E+02 < 4.60E+02 < 7.30E+02 La-140 < 6.60E+02 < 5.30E1+02 _ < 8.40E+02 Ce-141 1.1OE+02 < 1.20E+02 < 1.IOE+02 Ce-144 < 2.OOE+02 I < 1.70E+02 = < 1.40E+02 Nuclide' l- - -: 24-MAY White Perch'." [ .7-
+ 24-MAY.< Yellovw Perch -- l' - '3-NOV Walleye i-'!:J-Sr-89 < 2.1 OE+021 < 2.20E+02 I < 2.80E+02 I Sr-90 < 1.80E+02 < 1.90E+02 < 1.70E+02 Be-7 < 4.40E+02 < 7.40E+02 = < 5.OOE+02 K-40 2.33E+03 +/- 2.70E1+02 2.84E+03 +/- 3.OOE+02 3.18E+03 +/-- 2.OOE+02 Mn-54 < 4.00E+01 < 5.00E+01 < 2.30E+OI1 Co-58 < 4.60E+01 < 7.30E+01 < 4.40E+OI1 Fe-59 < 1.30E+02 _ < 2.1OE+02 < 2.50E+02 Co-60 < 3.40E+OI < 5.50E+O1 < 2.70E+O1 Zn-65 < 9.50E+01 < 1.30E+02 = < 7.90E+OI Zr-95 < 1.11OE+02 __< 1.40E+02 < 9.70E+O I Ru-103 < 6.30E+O1 < 1.1OE+02 < 9.1OE+O I Ru-106 < 3.30E+02 < 4.50E+02 < 2.60E+02 Cs-134 < 3.80E+01 < 5.50E+01 < 2.50E+O1 Cs-137 < 2.90E+01 < 4.90E+01 < 2.40E+O1 Ba-140 < 3.80E+02 < 7.60E+02 _ < 2.40E+03 La-140 < 4.30E+02 << 8.70E+02 . < 2.80E+03 Ce-141 < 1.1OE-+021 < 1.70E+02 < 1.50E+02 Ce-144 < 1.80E+02 =. < 2.40E+02 =_ < 1.20E+02 C-56
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport FERMI 2 FISH ANALYSIS F-3 (Control)
(pCi/kg wet) l Nuclide!!"1+ Ii .3-TNOV -WlhtePerch Sr-89 < 2.70E+02 Sr-90 < 1.70E+02 Be-7 < 6.40E+02 K-40 2.52E+03 +/- 2.70E+02 Mn-54 < 3.10E+O1 Co-58 < 6.10E+O1 Fe-59 < 2.20E+02 Co-60 < 4.30E+Ol Zn-65 < 9.30E+Ol =
Zr-95 < I.OOE+02 _
Ru- 103 < 1.IOE+02 Ru-106 < 2.90E+02 _
Cs-134 < 2.90E+O1 Cs-137 < 2.60E+O1 Ba-140 < 1.80E+03 La-140 < 2.OOE+03 Ce-141 < 2.OOE+02 I Ce-144 < I .60E+02 I C-57
Appendix D Environmental Program Execution
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmental OperatingReport EnvironmentalProgramExecution On occasions, samples cannot be collected. This can be due to a variety of events, such as equipment malfunction, loss of electrical power, severe weather conditions, or vandalism. In 2003, missed samples were a result of missing one field TLD, loss of electrical power to sampling equipment, and the result of the August 14 th blackout. The following sections list all missed samples, changes and corrective actions during 2003.
These missed 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 2003, two hundred sixty-eight (268) TLDs were placed in the field for the REMP program and all but one TLD was collected and processed. T-58 was found missing during the forth quarter collection as a result of vandalism.
Atmospheric Monitoring During 2003, two hundred sixty (260) air samples were placed in the field, all but five particulate filters and charcoal filters were processed. New sampling equipment was deployed in the second quarter of 2003. There were other changes to the Atmospheric Monitoring program in 2003.
API-3 filters collected on 6/10/2003 were not counted due to low volume caused by loss of power to the equipment. Sampling equipment power was restored. For this reason the second quarter composite sample for this location is considered to be less than representative.
API-3 filters collected on 8/12/2003 were not counted due to low volume caused by loss of power to the equipment. Sampling equipment power was restored. For this reason the third quarter composite sample for this location is considered to be less than representative.
API-4 filters collected on 1/7/2003 were not counted due to low volume caused by loss of power to the equipment. Sampling equipment power was restored. For this reason the first quarter composite sample for this location is considered to be less than representative.
API-4 filters collected on 7/29/2003 were not counted due to low volume caused by loss of power to the equipment. Sampling equipment power was restored. For this reason the third quarter composite sample for this location is considered to be less than representative.
D-1
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report
API-5 filters collected on 2/18/2003 were not counted due to low volume caused by loss of power to the equipment. Sampling equipment power was restored. For this reason the first quarter composite'sample for this location is considered to be less than representative.
On 8/14/2003 a power blackout occurred for two days and all five air samplers were effected. For this reason the weekly filters and third quarter composite sample for all locations are considered to be less than representative.
Terrestrial Monitoring During 2003, all scheduled Terrestrial Monitoring samples were collected.
Milk Sampling All scheduled milk samples were collected in 2003.
Garden Sampling All scheduled garden samples were collected in 2003.
Groundwater Sampling All scheduled groundwater samples were collected in 2003.
Aquatic Monitoring During 2003, twenty-four (24) drinking water and surface water samples were collected, and ten (10) sediment samples were collected. In addition, twenty-nine (29) fish samples were collected for the Aquatic Monitoring program. Due to the August I4th power blackout all drinking and surface water sampling equipment was not operational for approximately two days. For this reason the monthly and third quarter composite sample for all locations are considered to be less than representative. There were no changes to the Aquatic Monitoring program during 2003.
Drinking Water Sampling All scheduled drinking water samples were collected in 2003.
D-2
Fermi 2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport Surface Water Sampling All scheduled surface water samples were collected in 2003.
Sediment Sampling All scheduled sediment samples were collected in 2003.
Fish Sampling All scheduled fish samples were collected in 2003.
D-3
Appendix E Effluent and Radwaste Data
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport 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, lodine-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
m. 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-1
Fermi 2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmental OperatingReport 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 (ICRP) Publication 2.
II. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:
a) Less than or equal to 1.5 mrem to the total body Less than or equal to 5 mrem to any organ
- During any calendar quarter b) Less than or equal to 3 mrem to the total body Less than or equal to 10 mrem to any organ
- During any calendar year E-2
Fermi 2 - 2003 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
1. 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.~~
11. 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
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport Ill. 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 for 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
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport 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 filters are then analyzed for gross alpha radioactivity by gas proportional counting, and any such radioactivity found is assumed to be plant related. The quantity of alpha emitters released can then be determined from sample flow rate, sample duration, and stack flow rate.
The summary values reported are the sums of all alpha emitters quantified at all monitored release points.
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 2003.
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 30%
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 (plCi/cc) for individual samples, and indicate that the nuclide in question was not detected in gaseous effluent samples in the indicated quarter of 2003. For quantities of gross alpha radioactivity and tritium in gaseous effluents, see Tables 3 and 4 on page 13 of this report.
E-5
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport A. Particulate Radionuclides (Curies)
I-I-.I-I-
.,, *I ,l - *f**W-W .. TIIrW i.. j .n.* sq Cr-51 5.30E-05 1.06E-04 3.45E-05 <2.5E-13 Mn-54 1.1 8E-05 6.42E-06 7.68E-06 <3.7E-14 Co-58 7.19E-06 5.70E-06 4.17E-06 <1.4E-14 Co-60 1.42E-05 4.99E-05 3.06E-05 <9.5E-14 Fe-59 <3.3E-14 5.89E-06 -<3.3E-14 <3.3E-14 Zn-65 <3.5E-14 5.32E-06 <3.5E-14 _<3.5E-14 Na-24 1.57E-05 <1.7E-13 <1.7E-13 <1.7E-13 Tc-99m 2.61E-05 <3.2E-13 <3.2E-13 <3.2E-13 Ba-139 1.1 IE-OI 3.07E-02 9.96E-02 2.94E-O1 La-140 7.62E-05 3.33E-05 9.68E-05 1.90E-04 Ba-140 3.09E-05 6.48E-06 4.46E-05 7.69E-05 Y-91m 1.09E-02 4.40E-03 1.44E-02 2.35E-02 Sr-91 3.55E-04 4.49E-05 4.05E-04 1.25E-03 Rb-89 6.23E-03 7.72E-03 1.69E-02 2.65E-O1 Cs-138 8.56E-02 2.50E-02 1.14E-01 1.53E-O1 As-76 4.51E-03 1.25E-03 1.62E-03 3.55E-03 Br-82 <1.4E-13 7.63E-06 6.81E-05 4.26E-05 Sr-89 2.59E-05 1.86E-05 3.35E-05 7.00E-05 Sr-90 I.I5E-07 8.73E-08 <1.OE-14 <1.OE-14 Cs-134 <3.4E-14 <3.4E-14 <3.4E-14 <3.4E-14 Cs-137 <3.4E-14 <3.4E-14 <3.4E-14 <3.4E-14 Ce-141 <5.1E-14 <5.1E-14 <5.1E-14 <5.1E-14 Ce-143 <2.1E-13 <2.1E-13 <2.1E-13 <2.IE-13 Ce-144 <1.5E-13 <1.SE-13 <1.SE-13 <1.SE-13 Total 2.19E-01 6.92E-02 2.47E-01 7.40E-01 B. Noble Gases
[PM 6 6 Xe-133 <6.5E-08 <6.5E-08 1.07E-03 <6.5E-08 Xe-135 <2.0E-08 <2.0E-08 <2.0E-08 <2.0E-08 Xe-135m <2.7E-08 <2.7E-08 <2.7E-08 <2.7E-08 Xe-138 <1.8E-07 <1.8E-07 <1.8E-07 <1.8E-07 Total <3.OE-07 <3.0E-07 1.07E-03 <3.0E-07 E-6
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmentalOperatingReport C. Radioiodines 0M00 I-131 l 2.39E-03 I 1.07E-03 I 1.69E-03 I 9.89E-04 I -132 2.04E-02 1.70E-03 1.04E-02 6.09E-03 I-133 1.34E-02 3.73E-03 8.46E-03 7.133E-03 1-134 2.83E-02 1.69E-03 1.93E-02 8.19E-03 I-135 2.47E-02 2.47E-03 1.06E-02 9.90E-03 Total 8.92E-02 1.07E-02 5.05E-02 3.23E-02 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 2003.
a. Spent resins, sludges, etc. Waste in this category in 2003 consisted of spent resins only. All spent resin waste shipped for disposal in 2003 was shipped in High Integrity Containers or Polyethylene Liners to the Barnwell, SC, disposal facility.
All quantities were determined by measurement.
E-7
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report
~~1. Class A Resin:~~
Radionuclide Total Activity (mCi) Percent of Total Activity Ag-1 1Om 2.37E-03 0.00%
Am-241 3.29E-03 0.00%
Ba-1 33 5.19E-02 0.00%
C-14 1.87E+03 4.25%
Ce-144 1.86E-02 0.00%
Cm-242 6.11 E-05 0.00%
Cm-243 3.91 E-03 0.00%
Cm-244 3.65E-03 0.00%
Co-57 1.54E-03 0.00%
Co-58 1.15E+03 2.62%
Co-60 1.67E+04 38.02%
Cr-51 1.92E+02 0.44%
Cs-134 4.78E+01 0.11%
Cs-137 1.17E+03 2.67%
Fe-55 1.36E+04 31.00%
Fe-59 3.86E+01 0.09%
H-3 2.20E+02 0.50%
1-129 1.33E+00 0.00%
1-131 1.46E-02 0.00%
Mn-54 5.70E+03 12.98%
Nb-95 3.70E+00 0.01%
Ni-59 3.76E+00 0.01%
Ni-63 1.43E+03 3.26%
Pu-238 1.89E-02 0.00%
Pu-239 1.46E-02 0.00%
Pu-240 1.46E-02 0.00%
Pu-241 1.22E+00 0.00%
Sb-125 1.23E-01 0.00%
Sr-89 2.52E+02 0.57%
Sr-90 4.51 E+01 0.10%
Tc-99 1.61 E+02 0.37%
Zn-65 1.48E+03 3.37%
Total Activity 4.39E+04 100.00%
E-8
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report
~~2. Class B Resin:~~
Radionuclide Total Activity (mCi) Percent of Total Activity Ag-1 Om 1.89E+01 0.01%
Am-241 1.14E-01 0.00%
C-14 3.57E+01 0.01%
Cm-242 9.43E-03 0.00%
Cm-243 7.56E-02 0.00%
Cm-244 7.32E-02 0.00%
Co-57 1.38E+01 0.01%
Co-58 4.69E+00 0.00%
Co-60 1.64E+05 63.08%
Cs-1 34 5.26E+01 0.02%
Cs-137 1.76E+03 0.68%
Fe-55 7.67E+04 29.59%
H-3 2.78E+01 0.01%
1-129 2.50E-02 0.00%
Mn-54 4.12E+03 1.59%
Ni-63 4.81 E+03 1.86%
Pu-238 1.73E-01 0.00%
Pu-239 1.38E-01 0.00%
Pu-240 1.38E-01 0.00%
Pu-241 1.61 E+01 0.01%
Sn-1 13 1.44E-02 0.00%
Sr-89 9.64E-03 0.00%
Sr-90 2.27E+02 0.09%
Tc-99 8.43E+01 0.03%
Zn-65 7.59E+03 2.93%
Total Activity 2.59E+05 100.00%
E-9
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport
b. Dry compressible waste, contaminated equipment, etc. Waste in this category in 2003 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 or incinerated by an intermediate processor. After incineration some, of the residue from this waste was solidified in concrete. All quantities were determined by measurement.
Radionuclide Total Activity (mCi) Percent of Total Activity C-14 62.1021 0.49%
Co-60 3675.4738 28.80%
Cs-1 37 215.4428 1.69%
Fe-55 7814.9555 61.23%
H-3 78.2559 0.61%
1-129 5.1444 0.04%
Mn-54 466.1978 3.65%
Ni-63 235.159 1.84%
Tc-99 211.3683 1.66%
Total Activity 12764.0996 100.00%
~~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-10
Appendix F Interlaboratory Comparison Data
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmentalOperatingReport InterlaboratoryComparison Programfor2003 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.
In 2003, Framatome ANP performed one hundred-ten ( 10) analyses of environmental samples from Analytics. All results were within the acceptance criteria and are shown in the following table.
F-I
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report ANALYTICS CROSS CHECK COMPARISON PROGRAM 2003 Table F-1 Framatore ANP Analytics I Media I Nuclide I Result(a) I Result I Ratio(b)
Water H-3 5450 5987 0.91 Water Sr-89 72 79 0.91 Water Sr-90 16 16 1 Filter Gr-Alpha 52 59 0.88 Filter Gr-Beta 147 150 0.98 Filter Ce-141 59 59 1 Filter Cr-51 184 184 1 Filter Cs-1 34 51 53 0.96 Filter Cs-1 37 125 117 1.07 Filter Co-58 75 74 1.01 Filter Mn-54 83 75 1.11 Filter Fe-59 43 38 1.13 Filter Zn-65 103 95 1.08 Filter Co-60 84 87 0.97 Filter Sr-89 68 75 0.91 Filter Sr-90 61 60 1.02 Milk 1-131 89.23 86 1.04 Milk 1-131 81 86 0.94 Milk Ce-1 41 103 111 0.93 Milk Cr-51 334 346 0.97 Milk Cs-134 98 99 1 Milk Cs-137 220 220 1 Milk Co-58 134 139 0.96 Milk Mn-54 142 142 1 Milk Fe-59 74 72 1.03 Milk Zn-65 177 178 0.99 Milk Co-60 162 164 0.99 Water Gr-Alpha 55 61 0.9 Water Gr-Beta 146 186 0.78 Water 1-131 67.7 70 0.97 Water 1-131 68 70 0.97 Water Ce-1 41 163 168 0.97 Water Cr-51 243 238 1.02 Water Cs-134 83 88 0.94 Water Cs-137 185 195 0.95 Water Co-5B 44 42 1.05 Water Mn-54 61 63 0.97 Water Fe-59 48 46 1.04 Water Zn-65 88 90 0.98 Water Co-60 156 157 0.99 Filter Gr-Alpha 52 49 1.06 Filter Gr-Beta 157 148 1.06 Milk 1-131 72.53 74 0.98 F-2
Fermi 2 - 2003 Annual Radioactive Effluent Release and Radiological Environmental Operating Report ANALYTICS CROSS CHECK COMPARISON PROGRAM 2003 Table F-1 (cont.)
Franatome ANP Analytics Media I Nuclide I Result(a) Result Ratio(b)
Milk 1-131 73 74 0.99 Milk Ce-1 41 170 173 0.98 Milk Cr-51 244 246 0.99 Milk Cs-1 34 86 90 0.96 Milk Cs-1 37 196 200 0.98 Milk Co-58 44 47 0.94 Milk Mn-54 61 64 0.95 Milk Fe-59 47 47 1 Milk Zn-65 96 93 1.03 Milk Co-60 162 162 1 Milk Sr-89 121 133 0.91 Milk Sr-90 13 12 1.08 Water Sr-89 104 114 0.91 Water Sr-90 11 10 1.1 Water H-3 10643 11953 0.89 Filter Gr-Alpha 20 21 0.95 Filter Gr-Beta 116 115 1.01 Filter Ce-1 41 149 154 0.97 Filter Cr-51 134 130 1.03 Filter Cs-134 54 56 0.96 Filter Cs-137 135 125 1.08 Filter Co-58 53 50 1.06 Filter Mn-54 110 101 1.09 Filter Fe-59 60 54 1.11 Filter Zn-65 110 99 1.11 Filter Co-60 71 72 0.99 Filter Sr-89 78 87 0.9 Filter Sr-90 24 24 1 Milk 1-131 109 103 1.06 Milk 1-131 104 103 1.01 Milk Ce-141 283 283 1 Milk Cr-51 239 239 1 Milk Cs-134 98 103 0.95 Milk Cs-137 232 230 1.01 Milk Co-58 92 93 0.99 Milk Mn-54 186 186 1 Milk Fe-59 100 99 1.01 Milk Zn-65 181 181 1 F-3
Fermi2 - 2003 Annual Radioactive Effluent Release and RadiologicalEnvironmental OperatingReport ANALYTICS CROSS CHECK COMPARISON PROGRAM 2003 Table F-1 (cont.)
Framatome ANP I Analytics l Media I Nuclide I Result(a) Result Ratio(b)
Milk Co-60 134 132 1.02 Water Gr-Alpha 37 36 1.03 Water Gr-Beta 242 246 0.98 Water 1-131 69 76 0.91 Water 1-131 78 76 1.03 Water Ce-141 78 81 0.96 Water Cr-51 198 221 0.9 Water Cs-1 34 108 113 0.96 Water Cs-1 37 85 84 1.01 Water Co-58 92 94 0.98 Water Mn-54 93 88 1.06 Water Fe-59 74 75 0.99 Water Zn-65 170 166 1.02 Water Co-60 118 117 1.01 Filter Gr-Alpha 30 28 1.07 Filter Gr-Beta 197 189 1.04 Milk 1-131 66 74 0.89 Milk 1-131 74 74 1 Milk Ce-1 41 90 86 1.05 Milk Cr-51 228 233 0.98 Milk Cs-1 34 123 119 1.03 Milk Cs-1 37 94 88 1.07 Milk Co-58 99 99 1 Milk Mn-54 101 93 1.09 Milk Fe-59 84 79 1.06 Milk Zn-65 178 176 1.01 Milk Co-60 129 123 1.05 Milk Sr-89 80 100 0.8 Milk Sr-90 11 14 0.79 Footnotes:
(a) FramatomeANP Results - Units are pCi/literfor water, soil, and milk. Units are total pCifor airparticulatefilters.
(b) Ratio of FramatomeANP to Analytics Results.
F-4
Appendix G Meteorological Data
Fermi2 - 2003 Annual RadioactiveEffluent Release and RadiologicalEnvironmental OperatingReport In accordance with Section 5.9.1.8 of the Fermi 2 Offsite Dose Calculation Manual (ODCM), a summary file of 2003 required meteorological data is retained on site and available upon request.
G-1
Appendix H Fermi 2 Offsite Dose Calculation Manual
OFFSITE DOSE CALCULATION MANUAL Pages Revised in Latest Revision 0-1, 3-13, 3-32, 3-33, 3-37, 7-2, 9-3,10-5,10-6,10-13, 10-14, and 10-15 Implementation Plan These revisions go into effect upon approval.
FERMI 2 ODCM - TRM VOLUME 11 0-1 Rev. 16
FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOLUME II - LIST OF EFFECTIVE PAGES OFFSITE DOSE CALCULATION MANUAL Page Revision Page Revision 0-1 16 I 3-15 13 0-2 13 3-16 13 0-3 13 3-17 13 0-4 13 3-18 14 0-5 13 3-19 13 0-6 13 3-20 14 3-21 14 1-1 13 3-22 14 1-2 14 3-23 13 3-24 13 2-1 13 3-25 13 2-2 14 3-26 14 2-3 14 3-27 14 2-4 14 3-28 14 2-5 14 3-29 14 2-6 14 3-30 14 2-7 14 3-31 13 3-32 15 3-1 13 3-33 15 3-2 14 3-34 13 3-3 14 3-35 14 3-4 15 3-36 13 3-5 13 3-37 14 I 3-6 14 3-38 13.
3-7 14 3-39 13 3-8 14 3-40 13 3-9 13 3-41 13 3-10 14 3-42 13 3-11 13 3-43 13 3-12 13 3-44 13 3-13 14 3-45 13 I
3-14 13 3-46 13 FERMI 2 ODCM - TRM VOLUME II LEP-1 Rev.16 102103
FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOLUME II - LIST OF EFFECTIVE PAGES OFFSITE DOSE CALCULATION MANUAL Page Revision Page Revision 4-1 13 6-19 13 4-2 13 6-20 13 4-3 13 6-21 13 4-4 13 6-22 13 4-5 13 4-6 13 4-7 13 7-1 13 4-8 13 7-2 15 7-3 13 I
5-1 13 7-4 14 5-2 13 7-5 13 5-3 13 7-6 13 5-4 14 7-7 13 5-5 13 7-8 13 7-9 13 6-1 13 7-10 13 6-2 13 7-11 13 6-3 14 7-12 14 6-4 13 7-13 14 6-5 13 7-14 14 6-6 13 7-15 13 6-7 14 .7-16 13 6-8 14 7-17 13 6-9 13 7-18 13 6-10 13 7-19 13 6-11 13 7-20 13 6-12 13 7-21 13 6-13 13 7-22 13 6-14 13 7-23 13 6-15 13 7-24 13 6-16 13 7-25 13 6-17 13 7-26 13 6-18 13 FERMI 2 ODCM - TRM VOLUME II LEP-2 Rev.16 102103 R
FERMI 2 -TECHNICAL REQUIREMENTS MANUAL VOLUME II - LIST OF EFFECTIVE PAGES OFFSITE DOSE CALCULATION MANUAL Page Revision Page Revision 7-27 13 9-1 13 7-28 13 9-2 13 7-29 13 9-3 14 7-30 13 9-4 13 7-31 13 7-32 13 10-1 13 7-33 13 10-2 13 7-34 13 10-3 13 7-35 13 10-4 13 7-36 13 10-5 14 7-37 13 10-6 14 7-38 13 10-7 13 7-39 13 10-8 13 7-40 13 10-9 13 7-41 13 10-10 13 7-42 13 10-11 13 7-43 13 10-12 13 7-44 13 10-13 14 7-45 13 10-14 14 7-46 13 10-15 14 7-47 13 7-48 13 7-49 13 7-50 13 8.0-1 13 8.0-2 13 8.0-3 13 8.0-4 13 8.0-5 13 8.0-6 13 8.0-7 13 8.0-8 13 8.0-9 13 FERMI 2 ODCM - TRM VOLUME II LEP-3 Rev.16 102103
TABLE OF CONTENTS Pane Section 1-1
~~1.0 INTRODUCTION~~
PART I - RADIOLOGICAL EFFLUENT CONTROLS 2-1 2.0 DEFINITIONS 3-1 3.0 CONTROLS AND SURVEILLANCE REQUIREMENTS 3-2 3/4.0 Controls and Surveillance Requirements Applicability 3-5 3/4.3.7.11 Radioactive Liquid Effluent Monitoring Instrumentation 3-10 3/4.3.7.12 Radioactive Gaseous Effluent Monitoring Instrumentation 3-17 3/4.11.1.1 Liquid Effluents Concentration 3-21 3/4.11.1.2 Liquid Effluents Dose 3-22 3/4.11.1.3 Liquid Waste Treatment 3-23 314.11.2.1 Gaseous Effluents Dose Rate 3-27. 3/4.11.2.2 Gaseous Effluents Dose - Noble Gases 3-28 3/4.11.2.3 Gaseous Effluents Dose - Iodine-131, lodine-133, Tritium, and Radionuclides in Particulate Form 3-29 314.11.2.4 Offgas Treatment System 3-30 3/4.11.2.5 Ventilation Exhaust Treatment System 3-31 314.11.2.8 Venting or Purging 3-32 3/4;1 1.4 Radioactive Effluents Total Dose 3-33 3/4.12.1 Radiological Environmental Monitoring Program 3-44 314.12.2 Land Use Census 3-45 3/4.12.3 Interlaboratory Comparison Program 4-1 4.0 BASES 5-1 5.0 ADMINISTRATIVE CONTROLS 5-2 5.9.1.7 Annual Radiological Environmental Operating Report 5-2 5.9.1.8 Annual Radioactive Effluent Release Report
.5-4 5.15 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems FERMI 2 ODCM - TRM VOLUME II 0-2 Rev. 13 I
TABLE OF CONTENTS (continued)
Page Section PART II - CALCULATIONAL METHODS 6-1 6.0 LIQUID EFFLUENTS 6-2 6.1 Radiation Monitoring Instrumentation and Controls 6-2 6.1.1 Offsite Dose Calculation Manual (ODCM) 3.3.7.11 Requirement 6-3 6.1.2 Non-ODCM Required Monitor 6-4 6.2 Sampling and Analysis of Liquid Effluents 6-4 6.2.1 BATCH Releases 6-5 6.2.2 CONTINUOUS Releases 6-5 6.3 Liquid Effluent Monitor Setpoints 6-6 6.3.1 Liquid Radwaste Effluent Line Monitor 6-9 6.3.2 Circulating Water Reservoir Decant Line Radiation Monitor (D1 -N402) 6-10 6.3.3 Generic, Conservative Alarm Setpoint for Di I-N402 6-11 6.3.4 Alarm Setpoint for GSW and RHR System Radiation Monitors 6-11 6.3.5 Alarm Response - Evaluating Actual Release Conditions 6-12 6.3.6 Liquid Radwaste Setpoint Determination With Contaminated Circulating Water Reservoir 6-13 6.4 Contaminated GSW or RHR System - Quantifying and Controlling Releases 6-14 6.5 Liquid Effluent Dose Calculation - 10 CFR 50 6-14 6.5.1 MEMBER OF THE PUBLIC Dose - Liquid Effluents 6-16 6.5.2 Contaminated CWR System - Dose Calculation 6-17 6.6 Liquid Effluent Dose Projections 7-1 7.0 GASEOUS EFFLUENTS 7-2 7.1 Radiation Monitoring Instrumentation and Controls 7-2 7.1.1 Effluent Monitoring - Ventilation System Releases 7-2 7.1.2 Main Condenser Offgas Monitoring 7-3 7.1.3 Reactor Building Ventilation Monitors (Gulf Atomic) 7-3 7.2 Sampling and Analysis of Gaseous Effluents 7-3 7.2.1 Containment PURGE 7-4 7.2.2 Ventilation System Releases FERMI 2 ODCM - TRM VOLUME II 0-3 Rev. 13
TABLE OF CONTENTS (continued)
Page Section 7-5 7.3 Gaseous Effluent Monitor Setpoint Determination 7-5 7.3.1 Ventilation System Monitors 7-7 7.3.2 Setpoint Determination with No Nuclides Detected 7-7 7.3.3 Gaseous Effluent Alarm Response - Evaluating Actual Release Conditions 7-8 7.4 Primary Containment VENTING and PURGING 7-8 7.4.1 Release Rate Evaluation 7-9 7.4.2 Alarm Setpoint Evaluation 7-10 7.5 Quantifying Releases - Noble Gases 7-10 7.5.1 Sampling Protocol 7-11 7.6 Calculation of Activity Released 7-11 7.7 Site Boundary Dose Rate - Radioiodine and Particulates 7-13 7.8 Noble Gas Effluent Dose Calculations - 10 CFR 50 7-13 7.8.1 UNRESTRICTED AREA Dose - Noble Gases 7-14 7.9 Radioiodine and Particulate Dose Calculations - 10 CFR 50 7-14 7.9.1 UNRESTRICTED AREA Dose - Radioiodine, Particulates, and Tritium 7-16 7.10 Gaseous Effluent Dose Projection 8-1 8.0 SPECIAL DOSE ANALYSES 8-2 8.1 Doses Due to Activities inside the SITE BOUNDARY 8-2 8.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 8-3 8.2.1 Effluent Dose Calculations 8-4 8.2.2 Direct Exposure Dose Determination 8-4 8.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data 9-1 9.0 ASSESSMENT OF LAND USE CENSUS DATA 9-2 9.1 Land Use Census as Required by ODCM 3.12.2 9-4 9.2 Land Use Census to Support Realistic Dose Assessment FERMI 2 ODCM - TRM VOLUME II 0-4 Rev. 13
TABLE OF CONTENTS (continued)
Paae Section 10-1 10.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 10-2 10.1 Sampling Locations 10-2 10.2 Reporting Levels 10-3 10.3 Interlaboratory Comparison Program TABLES Paae Table 2-7 2.1 Surveillance Frequency Notation 2-8 2.2 Operational Conditions 3-6 3.3.7.11 -1 Radioactive Liquid Effluent Monitoring Instrumentation 3-8 4.3.7.11-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 3-11 3.3.7.12-1 Radioactive Gaseous Effluent Monitoring Instrumentation 3-14 4.3.7.12-1 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3-18 4.11.1.1.1-1 Radioactive Liquid Waste Sampling and Analysis Program 3-24 4.11.2.1.2-1 Radioactive Gaseous Waste Sampling and analysis-Program 3-35 3.1 2.1-1 Radiological Environmental Monitoring Program 3-40 3.1 2.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3-41 4.1 2.1 -1 Detection Capabilities for Environmental Sample Analysis 6-19 6.0-1 Fermi 2 Site Specific Liquid Ingestion Dose Commitment Factors, Aio 6-21 6.0-2 Bioaccumulation Factors (BFi)
FERMI 2 ODCM - TRM VOLUME 11 0-5 Rev. 13 l
TABLE OF CONTENTS (continued)
TABLES (continued)
Paae Table 7-17 7.0-1 Values for Evaluating Gaseous Release Rates and Alarm Setpoints 7-18 7.0-2 Dose Factors for Noble Gases 7-19 7.0-3 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations 7-20 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors 8-8 8.0-1 Assumptions for Assessing Doses Due to Activities inside SITE BOUNDARY 8-9 8.0-2 Recommended Exposure Rates in Lieu of Site Specific Data 10-4 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media FIGURES Paae Fiaure 3-46 3.0-1 Map Defining Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents 6-22 6.0-1 Liquid Radioactive Effluent Monitoring and Processing Diagram 7-50 7.0-1 Gaseous Radioactive Effluent Monitoring and Ventilation Systems Diagram END OF SECTION 0.0 FERMI 2 ODCM - TRM VOLUME II 0-6 Rev. 13 I
Nuclear Production - Fermi 2 ODCM-2.0 Offsite Dose Calculation Manual Page 2.0-1 PART I RADIOLOGICAL EFFLUENT CONTROLS
SECTION
~~1.0 INTRODUCTION~~
~~FERMI 2 ODCM - TRM VOLUME II 1-1 Rev. 13 l~~
~~1.0 INTRODUCTION~~
Part I of the Fermi 2 Offsite Dose Calculation Manual (ODCM), which includes Sections 2.0 through 5.0, contains the controls and surveillance requirements for radioactive effluents and radiological environmental monitoring. It also contains requirements for the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report.
This satisfies the requirements for Technical Specification 5.5.1, the Offsite Dose Calculation Manual (ODCM), and Technical Specification 5.5.4, Radioactive Effluent Controls Program.
Part II of the ODCM describes the methodology and parameters used in calculating radioactive liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints, and in calculating liquid and gaseous effluent dose rates and cumulative doses.
The methodology provided in Part II of this manual is acceptable for use in demonstrating compliance with the dose limits for members of the public of 10 CFR 20, the cumulative dose criteria of 10 CFR 50, Appendix I and 40 CFR 190, and the controls in Part I of this manual.
Part II, Section 6.0 of the ODCM describes equipment for monitoring and controlling liquid effluents, sampling requirements, and dose evaluation methods. Section 7.0 provides similar information on gaseous effluent controls, sampling, and dose evaluation. Section 8.0 describes special dose analyses required for compliance with Fermi 2 Offsite Dose Calculation Manual and 40 CFR 190. Section 9.0 describes the role of the annual land use census in identifying the controlling pathways and locations of exposure for assessing potential off-site doses.
Section 10.0 describes the Radiological Environmental Monitoring Program.
The ODCM will be maintained at Fermi 2 for use as a listing of radiological effluent controls and surveillance requirements, as well as a reference guide and training document for accepted methodologies and calculations. Changes to the ODCM calculational methodologies and parameters will be made as necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix I for demonstrating that radioactive effluents are "As Low As Reasonably Achievable."
NOTE: Throughout this document words appearing all capitalized denote either definitions specified in the Fermi 2 Controls or common acronyms.
END OF SECTION 1.0 FERMI 2 ODCM - TRM VOLUME II 1-2 Rev. 14
SECTION 2.0 DEFINITIONS FERMI 2 ODCM - TRM VOLUME II 2-1 Rev. 13
2.0 DEFINITIONS Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. A CHANNEL CALIBRATION shall encompass the entire channel including the required sensor, alarm, display, and trip functions, and shall include a CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detectors (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. A CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.
CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify FUNCTIONAL CAPABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. A CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.
FERMI 2 ODCM - TRM VOLUME 11 2-2 .Rev. 14
Term Definition FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 2.1.
FUNCTIONALLY CAPABLE A system, subsystem, division, component, or device shall be FUNCTIONALLY CAPABLE or have FUNCTIONAL CAPABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC means any individual except when that individual is receiving an occupational dose.
MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 2.2 with fuel in the reactor vessel.
MPC (Maximum Permissible Concentration in water) For individual nuclides, 10 times the concentration values in 10 CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2, except for noble gases which are-limited to 2E-4 uCi/mI total activity concentration. For nuclide mixtures, concentrations for which the sum of individual nuclide concentrations divided by their corresponding individual MPC values equals 1.
OCCUPATIONAL DOSE OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose received from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the general public.
FERMI 2 ODCM - TRM VOLUME II 2-3 Rev. 14
I Term Definition OFF-GAS An OFF-GAS TREATMENT SYSTEM is any system TREATMENT SYSTEM designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system offgases from the reactor coolant and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
OFFSITE DOSE The OFFSITE DOSE CALCULATION MANUAL (ODCM)
CALCULATIONAL MANUAL shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the radiological environmental monitoring program. The ODCM shall also contain (1) the Radiological Effluent Controls and Radiological Environmental Monitoring Program Controls, and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Reports required by Controls 5.9.1.7 and 5.9.1.8.
PUBLIC DOSE PUBLIC DOSE means the dose received by a member of the public from exposure to radiation and/or radioactive material released by a licensee, or to any other source of radiation under the control of a licensee. It does not include occupational dose or doses received from background radiation, as a patient from medical practices, or from voluntary participation in medical research programs.
PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 3430 MWt.
REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
FERMI 2 ODCM - TRM VOLUME II 2-4 Rev. 14
Term Definition SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled, by the licensee.
SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNRESTRICTED AREA The Fermi 2 Energy Center UNRESTRICTED AREA includes all areas outside the site boundary.
VENTILATION EXHAUST A VENTILATION EXHAUST TREATMENT SYSTEM shall TREATMENT SYSTEM be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
FERMI 2 ODCM - TRM VOLUME 11 2-5 Rev. 14
TABLE 2.1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY S .................................... At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
... At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
...................................................................... Atla to c pe 7d ys W .................................. At least once per 7 days.
M.................................. At least once per 31 days.
.At least once per 92 days.
SA .At least once per 184 days.
A. At least once per 366 days.
R.At least once per 18 months (550 days).
S/U . Prior to each reactor startup.
P.Prior to each radioactive release:
N.A ..................................... Not applicable.
FERMI 2 ODCM - TRM VOLUME II 2-6 Rev. 14
TABLE 2.2 MODES REACTOR MODE AVERAGE REACTOR MODE TITLE SWITCH POSITION COOLANT TEMPERATURE (OF) 1 Power Operation Run NA 2 Startup Refuel(') or Startup/Hot NA Standby 3 Hot Shutdown. a) Shutdown > 200 4 Cold Shutdown(') Shutdown < 200 5 Refueling~b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.
(b) One or more reactor vessel head closure bolts less than fully tensioned.
END OF SECTION 2.0 FERMI 2 ODCM - TRM VOLUME II 2-7 Rev. 14
SECTION 3.0 CONTROLS AND SURVEILLANCE REQUIREMENTS FERMI 2 ODCM - TRM VOLUME II 3-1 Rev. 13
3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 314.0 APPLICABILITY CONTROLS 3.0.1 Controls shall be met during the MODES or other specified conditions in the Applicability, except as provided in Control 3.0.2.
3.0.2 Upon discovery of a failure to meet a Control, the Actions shall be met, except as provided in Control 3.0.5.
If the Control is met or is no longer applicable prior to expiration of the specified completion time(s), completion of the Action(s) is not required, unless otherwise stated.
3.0.3 When a Control is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the Control is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:
~~1. Mode 2 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;~~
~~2. Mode 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and~~
~~3. Mode 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .~~
Exceptions to this Control are stated in the individual Controls.
Where corrective measures are completed that permit operation in accordance with the Control or ACTIONS, completion of the actions required by Control 3.0.3 is not required.
Control 3.0.3 is only applicable in MODES 1, 2, and 3.
FERMI 2 ODCM - TRM VOLUME II 3-2 Rev. 14
314.0 APPLICABILITY CONTROLS (continued) 3.0.4 When a Control is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
Exceptions to this Control are stated in the individual Controls. These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time.
Control 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3.
3.0.5 Equipment removed from service or declared not FUNCTIONALLY CAPABLE to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its FUNCTIONAL CAPABILITY or the FUNCTIONAL CAPABILITY of other equipment. This is an exception to Control 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate FUNCTIONAL CAPABILITY.
FERMI 2 ODCM - TRM VOLUME II 3-3 Rev. 14
314.0 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the MODES or other specified conditions in the Applicability for individual Controls, unless otherwise stated in the Surveillance Requirements. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the Control. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the Control except as provided in Surveillance Requirement 4.0.3. Surveillances do not have to be performed on equipment which is not FUNCTIONALLY CAPABLE or variables outside specified limits.
4.0.2 The specified Frequency is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
For Frequencies specified as "once," the above interval extension does not apply.
If a Completion Time requires periodic performance on a "once per ..." basis, the above Frequency extension applies to each performance after the initial performance.
Exceptions to this Control are stated in the individual Controls.
4.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the Control not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the Control must immediately be declared not met, and the applicable ACTIONS must be entered.
When the Surveillance is performed within the delay period and the Surveillance is not met, the Control must immediately be declared not met, and the applicable ACTIONS must be entered.
4.0.4 Entry into a MODE or other specified condition in the Applicability of a Control shall not be made unless the Control's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
4.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3.
FERMI 2 ODCM - TRM VOLUME 11 3-4 Rev. 15
INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.11 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be FUNCTIONALLY CAPABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The alarmitrip setpoints of these*
channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATIONAL MANUAL (ODCM).
APPLICABILITY: At all times.
ACTION:
a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel not FUNCTIONALLY CAPABLE, or change the setpoint so it is acceptably conservative.
b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels FUNCTIONALLY CAPABLE, take the ACTION shown in Table 3.3.7.11-1. Restore the instrumentation which is not FUNCTIONALLY CAPABLE to FUNCTIONALLY CAPABLE status within 30 days and, if unsuccessful, explain why this condition was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.
~~c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONALLY CAPABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.11-1.
FERMI 2 ODCM - TRM VOLUME II 3-5 Rev.13
TABLE 3.3.7.11-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Instrumnt
~~-- - - - Minimum-Chahnels l-Ato~~
~~. . .uent Functionally.Capable~~
~~1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE~~
~~a. Liquid Radwaste Effluent Line D11-N007 1 110~~
~~2. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE~~
~~a. Circulating Water Reservoir Decant Line Dl 1-N402 1 111~~
~~3. FLOW RATE MEASUREMENT DEVICES'~~
~~a. Liquid Radwaste Effluent Line G1I-R703 1 112 TABLE NOTATION~~
The circulating water reservoir decant line flow rate monitor has been removed. The flow rate in this decant line is now measured using certified pump performance curves for the circulating water reservoir decant pumps, together with readings from pump discharge pressure gauges and reservoir level indication.
FERMI 2 ODCM - TRM VOLUME II 3-6 Rev. 14
TABLE 3.3.7.11-1 (Continued)
TABLE NOTATIONS ACTION 110 - With the number of channels FUNCTIONALLY CAPABLE less than that required by the Minimum Channels FUNCTIONALLY CAPABLE requirement, effluent releases from this pathway may continue provided that prior to initiating a release:
~~a. At least two independent samples are analyzed in accordance with Surveillance Requirement 4.1 1.1.1. 1, and~~
b. At least two technically qualified individuals independently verify the release rate calculations and discharge line valving (one technically qualified individual can be the preparer of the calculation, the other independently reviews the release rate calculations to verify accuracy);
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 111 - With the number of channels FUNCTIONALLY CAPABLE less than the Minimum Channels FUNCTIONALLY CAPABLE requirement, radioactive effluent releases via this pathway may continue provided that grab samples are collected and analyzed at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 microcurie/ml, for Cs-1 37. Otherwise, suspend release of radioactive effluents via this pathway. If radioactive effluent releases are not in progress, i.e., if no Waste Sample Tank (or other tank containing radioactive liquid) is being released and the circulating water is not contaminated as shown by the most recent circulating water sample(s),
this sampling requirement does not apply.
ACTION 112 - With the number of channels FUNCTIONALLY CAPABLE less than required by the Minimum Channels FUNCTIONALLY CAPABLE requirement, radioactive effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Otherwise, suspend release of radioactive effluents via this pathway. If radioactive effluent releases are not in progress, i.e., if no Waste Sample Tank (or other tank containing radioactive liquid) is being released, this requirement does not apply.
FERMI 2 ODCM - TRM VOLUME II 3-7 Rev. 14
TABLE 4.3.7.11-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument' Channel Source Channel Channel
__ Check Check Calibration Functional Test
~~1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC J I .~~
~~TERMINATION OF RELEASE l~~
~~a. Liquid Radwaste Effluent Line I P P I R(3) p Q(1) (2)~~
~~2. GROSS BETA OR GAMMA RADIOACTIVITY l MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF l RELEASE~~
~~a. Circulating Water Reservoir Decant Line I M i R(3) Q(5)~~
~~D11-N402 l~~
~~3. FLOWVRATE MEASUREMENT DEVICES (4) I~~
~~a. Liquid Radwaste Effluent Line D(4) N.A. R 0 FERMI 2 ODCM - TRM VOLUME II 3-8 Rev. 14~~
TABLE 4.3.7.11-1 (Continued)
TABLE NOTATIONS (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if any of the following conditions exists:
~~1. Instrument indicates measured levels above the alarm/trip setpoint.~~
~~2. Circuit failure.~~
~~(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:~~
~~1. Instrument indicates measured levels above the alarm setpoint.~~
~~2. Circuit failure.~~
~~3. Instrument indicates a downscale failure.~~
~~4. Instrument controls not set in operate mode.~~
(3) The initial CHANNEL CALIBRATION shall be performed using National Institute of Standards and Technology traceable sources. These standards shall permit calibrating the system over the range of energy and measurement expected during normal operation and anticipated operational occurrences. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration or are National Institute of Standards and Technology traceable shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.
(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
~~1. Instrument indicates measured levels above the alarm setpoint.~~
~~2. Circuit failure.~~
~~3. Instrument indicates a downscale failure.~~
FERMI 2 ODCM - TRM VOLUME 11 3-9 Rev. 13
INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.12 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.12-1 shall be FUNCTIONALLY CAPABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The alarm/trip setpoints of these channels, with the exception of the offgas monitoring system, shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY: Actions a and b: As shown in Table 3.3.7.12-1 Actions c and d: At all times ACTION:
a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel not FUNCTIONALLY CAPABLE, or change the setpoint so it is acceptably conservative.
~~b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels FUNCTIONALLY CAPABLE, take the ACTION shown in Table 3.3.7.12-1.~~
c. Restore radioactive gaseous effluent monitoring instrumentation which is not FUNCTIONALLY CAPABLE to FUNCTIONALLY CAPABLE status within 30 days and, if unsuccessful, explain why this condition was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.
~~d. The provisions of Controls 3.0.3 and 3.0.4 are.not applicable.~~
SURVEILLANCE REQUIREMENTS 4.3.7.12 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONALLY CAPABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.12-1.
FERMI 2 ODCM - TRM VOLUME II 3-10 Rev. 14
TABLE 3.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum
. Channels Instrument -Functionally Applicability Action
._ Capable II
, 1. REACTOR BUILDING EXHAUST PLENUM EFFLUENTll MONITORING SYSTEM l l
~~a. Low Range Noble Gas Activity Monitor - Providing Alarm 1 121~~
~~b. Iodine Sampler 1 122~~
~~c. Particulate Sampler 1~~
~~122~~
~~d. Sampler Flow Rate Monitor 1 ^ j 123 l 2. OFFGAS MONITORING SYSTEM (At the 2.2 minute delay piping)~~
~~a. Noble Gas Activity Monitor- Providing Alarm 1 126 l~~
~~3. STANDBY GAS TREATMENT SYSTEM~~
~~a. Low Range Noble Gas Activity Monitor - Providing Alarm 1 # 125~~
~~b. Iodine Sampler 1 # 122~~
~~c. Particulate Sampler 1 122 d, Sampler Flow Rate Monitor 1 123~~
~~4. TURBINE BLDG. VENTILATION MONITORING SYSTEM~~
~~a. Low Range Noble Gas Activity Monitor - Providing Alarm 1 121~~
~~b. Iodine Sampler 1~~
~~122~~
~~c. Particulate Sampler 1 122~~
~~d. Sampler Flow Rate Monitor 1 123 TABLE NOTATIONS~~
~~At all times.~~
~~During operation of the main condenser air ejector.~~
During operation of the standby gas treatment system.
FERMI 2 ODCM - TRM VOLUME II 3-11 Rev. 13
TABLE 3.3.7.12-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument .Functionally Applicability Action Capable
~~15. RADWASTE BUILDING VENTILATION MONITORING SYSTEM II12~~
~~a. Low Range Noble Gas Activity Monitor- Providing Alarm~~
~~b. Iodine Sampler 1~~
1
~~l 121 122 i c. Particulate Sampler 1 122~~
~~d. Sampler Flow Rate Monitor 1 123~~
~~16. ONSITE STORAGE BUILDING VENTILATION EXHAUST RADIATION MONITOR~~
~~a. Low Range Noble Gas Activity Monitor - Providing Alarm 1~~
~~121.~~
~~b. Iodine Sampler 1 122 i c. Particulate Sampler l 122~~
~~d. Sampler Flow Rate Monitor 1 123 TABLE NOTATIONS~~
~~At all times.~~
FERMI 2 ODCM - TRM VOLUME II 3-12 Rev. 13l
TABLE 3.3.7.12-1 (Continued)
ACTION STATEMENTS ACTION 121 - With the number of channels FUNCTIONALLY CAPABLE less than required by the Minimum Channels FUNCTIONALLY CAPABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or, if valid monitor indication of noble gas concentration is available, that noble gas concentration readings are recorded at least once per 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 122- With the number of channels FUNCTIONALLY CAPABLE one less than required by the Minimum Channels FUNCTIONALLY CAPABLE requirement, effluent releases via this pathway may continue provided that within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples are continuously collected with auxiliary sampling equipment as required in Table 4.11.2.1.2-1.
ACTION 123- With the number of channels FUNCTIONALLY CAPABLE less than required by the Minimum Channels FUNCTIONALLY CAPABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 124- Not used.
ACTION 125- With the number of channels FUNCTIONALLY CAPABLE less than required by the Minimum Channels FUNCTIONALLY CAPABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or, if valid monitor indication of noble gas concentration is available, that noble gas concentration readings are recorded at least once per 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 126 - With the number of channels FUNCTIONALLY CAPABLE less than required by the Minimum Channels FUNCTIONALLY CAPABLE requirement, releases via this pathway to the environment may continue for up to 7 days provided that:
~~a. The offgas system is not bypassed, and~~
b. The reactor building exhaust plenum noble gas effluent (downstream) monitor is FUNCTIONALLY CABAPLE; Otherwise, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
FERMI 2 ODCM - TRM VOLUME II 3-13 Rev. 14
TABLE 4.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Modes In Instrument Channel -Source Channel Fctnal Surveillance
.Check Check Calibration Test Surveillance Reuie
~~1. REACTOR BUILDING EXHAUST PLENUM~~
~~a. Low Range Noble Gas Activity Monitor - D M R(2) 0(1)~~
~~Providing Alarm~~
~~b. Iodine Sampler W N.A. N.A. N.A. l~~
~~c. Particulate Sampler W N.A. N.A. N.A. l~~
~~d. Sampler Flow Rate Monitor D N.A. R 0~~
~~2. OFFGAS MONITORING SYSTEM (At the 2.2 minute delay piping)~~
~~a. Noble Gas Activity Monitor D M R(2) Q(1) 3 STANDBY GAS TREATMENT MONITORING SYSTEM~~
~~a. Low Range Noble Gas Activity Monitor D M R(2) Q()~~
~~b. Iodine Sampler W N.A. N.A. N.A.~~
~~c. Particulate Sampler W N.A. KA. N.A.~~
~~d. Sampler Flow Rate Monitor D N.A. I R Q~~
~~4. TURBINE BLDG. VENTILATION MONITORING SYSTEM~~
~~a. Low Range Noble Gas Activity Monitor ! D M R(2) Q(4)~~
~~b. Iodine Sampler W N.A. N.A. N.A.~~
~~c. Particulate Sampler I W N.A. N.A. N.A.~~
~~d. Sampler Flow Rate Monitor j D N.A. R Q~~
~~FERMI 2 ODCM - TRM VOLUME II 3-14 Rev. 13~~
TABLE 4.3.7.12-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Modes in Instrument Channel Source Channel Channel Which Check Check Calibration Tsti Surveillance Required
~~15. RADWASTE BUILDING VENTILATION MONITORING SYSTEM~~
~~a. Low Range Noble Gas Activity Monitor D M R(2) Q(4)~~
~~b. Iodine Sampler W N.A. N.A. N.A.~~
c. Particulate Sampler W N.A. N.A. N.A. j *
~~d. Sampler Flow Rate Monitor. D N.A. R l~~
~~6. ONSITE STORAGE BUILDING VENTILATION EXHAUST RADIATION MONITOR~~
~~a. Low Range Noble Gas Activity Monitor D M R(2) Q(1)~~
I
~~b. Iodine Sampler W N.A. N.A. N.A.~~
c. Particulate Sampler W N.A. N.A. N.A. *
~~d. Sampler Flow Rate Monitor D l N.A. R 0 FERMI 2 ODCM - TRM VOLUME II 3-15 Rev. 13~~
TABLE 4.3.7.12-1 (Continued)
TABLE NOTATIONS
~~At all times.~~
~~During operation of the main condenser air ejector.~~
During operation of the standby gas treatment system.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
~~1. Instrument indicates measured levels above the alarm setpoint.~~
~~2. Circuit failure.~~
~~3. Instrument indicates a downscale failure.~~
~~4. Instrument controls not set in operate mode (alarm or type).~~
(2) The initial CHANNEL CALIBRATION shall be performed using National Institute of Standards and Technology traceable sources. These standards shall permit calibrating the system over the range of energy and measurement expected during normal operation and anticipated operational occurrences. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration or are National Institute of Standards and Technology traceable shall be used.
(3) Not used.
(4) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation occurs on high level and that control room alarm annunciation occurs if any of the following conditions exists:
~~1. Instrument indicates measured levels above the alarm setpoints.~~
~~2. Circuit failure.~~
~~3. Instrument indicates a downscale failure.~~
~~4. Instrument controls not set in the operate mode (alarm or type).~~
FERMI 2 ODCM - TRM VOLUME II 3-16 Rev. 13
3/4.11 RADIOACTIVE EFFLUENTS 314.11.1 LIQUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 3.0-1) shall be limited to ten times the concentration values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 I for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/ml total activity.
APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.1 1.1.1.1-1.
4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.
FERMI 2 ODCM - TRM VOLUME II 3-17 Rev. 13 I
TABLE 4.11.1.1.1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Sampling Minimum Type of Lower Limit of Type Frequency Analysis Activity Detection Frequency Analysis (LLD)a (uCi/mi)
Principal Gamma 5 x 10- 7 EmittersC A. Batch Releaseb: P P 1-131 1 x 10-6 Waste Sample Each Batch Each Batch Tanks (3) Dissolved and 1 x 10- 5 Entrained Gases (Gamma Emitters)
P M H-3 1x10-5 Each Batch Composited Gross Alpha 1 ;'iO7 P a Sr-89, Sr-90 5 x 10- 8 Each Batch Composited Fe-55 1 x 10-6 Principal Gamma 5 x 10- 7 EmittersC B. Continuous 1-131 1 x 10-6 Releasese Circulating Wf Mf Dissolved and 1 x 10-5 Water System (if Grab Sample Composited Entrained Gases contaminated) (Gamma Emitters)
H-3 1 x 10-5 Gross Alpha 1 x 10-7 Sr-89, Sr-90 5 x 10-8 NA Q Composited Fe-55 1x 10-6 FERMI 2 ODCM - TRM VOLUME II 3-18 Rev. 14
TABLE 4.11. .1.1-1 (Continued)
TABLE NOTATION aThe LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD=4.66 - sb LLD = E *V 2.22 x 106 *Y*exp(-At)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and t for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.
Typical values of E, V, Y, and t should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
bA batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling. Batch liquid discharge may be made from only one tank at a time.
FERMI 2 ODCM - TRM VOLUME II 3-19 Rev. 13
TABLE 4.11.1.1.1-1 (Continued)
TABLE NOTATION CThe principal gamma emitters for which the LLD specification applies exclusively are:
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 5.9.1.8.
dThis type of composite sample is a sample composed of aliquots of pre-release samples or grab samples taken during releases, or of aliquots of composite samples so prepared, so as to represent releases taking place over a longer period of time. The volumes of these aliquots should be proportional to the volumes of the releases which they represent.
eA continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of a system that has an input flow during the continuous release.
fWhen the circulating water system is first discovered to be contaminated, grab samples may be taken more frequently, and may be analyzed immediately. After the source of the contamination is discovered and isolated, and contamination levels are not increasing, this grab sampling and analysis frequency may be reduced to the schedule specified in the table..
FERMI 2 ODCM - TRM VOLUME II 3-20 Rev. 14
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE CONTROLS 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 3.0-1) shall be limited:
~~a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and~~
~~b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.~~
APPLICABILITY: At all times.
ACTION:
~~a. With the calculated dose from the release of radioactive materials in liquid effluents.~~
exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 50.4, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Safe Drinking Water Act.*
~~b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
~~Applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge.~~
FERMI 2 ODCM - TRM VOLUME II 3-21 Rev. 14
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT CONTROLS 3.11.1.3 The liquid radwaste treatment system shall be FUNCTIONALLY CAPABLE and appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each reactor unit, to UNRESTRICTED AREAS (see Figure 3.0-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any 31-day period.
APPLICABILITY: At all times.
ACTION:
a. With radioactive liquid waste being discharged and in excess of the above limits and any portion of the liquid radwaste treatment system not in operation, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 50.4, a Special Report that includes the following information:
1. Explanation of why liquid radwaste was being discharged without complete treatment, identification of any equipment or subsystems which are not FUNCTIONALLY CAPABLE, and the reason for the not FUNCTIONALLY CAPABLE status.
~~2. Action(s) taken to restore the equipment which is not FUNCTIONALLY CAPABLE to FUNCTIONALLY CAPABLE status, and~~
~~3. Summary description of action(s) taken to prevent a recurrence.~~
~~b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS.
4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated FUNCTIONALLY CAPABLE by meeting Controls 3.11.1.1 and 3.11.1.2.
FERMI 2 ODCM - TRM VOLUME II 3-22 Rev. 14
RADIOACTIVE EFFLUENTS 314.11.2 GASEOUS EFFLUENTS DOSE RATE CONTROLS 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.0-1) shall be limited to the following:
~~a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and~~
~~b. F6r 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 mrems/yr to any organ.~~
APPLICABILITY: At all times.
ACTION:
With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.
4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium, and all other radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1.
FERMI 2 ODCM - TRM VOLUME II 3-23 Rev. 13 l
TABLE 4.1 1.2.1.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Sampling -Minimum Type of Activity Lower Limit of Gaseous Release Frequency -Analysis Analysis Detection (LLD)a Type Frequency (uCi/mo )
A. Containment Pi. Si Pi, Si Principal Gamma 1 x 10-4 PURGE (Pre Each PURGE Each PURGE Emittersb Treatment) Grab Sample pi H-3 1 x 10-6 B. Reactor Building Exhaust Plenum Mc,e Mc Principal Gamma 1 x 10- 4 Standby Gas Emittersb Treatment Systemh Grab Sample Mc H-3 1 x 10-6 C. Radwaste Building Principal Gamma Turbine Building M M Emittersb 1 x 10-4 On-Site Storage Grab Sample M H-3 1 x i0-6 Facility D. All Release Types W9 1-131 1 x 10-1 2 as listed in B and C Continuousf Absorbent Sample 1-133 1 x 10-10 above. 4 Wg Principal Gamma.
Continuousf Particulate Sample Emittersb 1 x 1o-11
~~(1-131, others)~~
Gross Alpha Q
Continuousf Composite Sr-89, Sr-90 1 x 10-1 Particulate Sample Continuousf Noble Gas Monitor Noble Gas Gross I x 10-6 Beta or Gamma FERMI 2 ODCM - TRM VOLUME 11 3-24 Rev. 13
TABLE 4.11.2.1.2-1 (Continued)
TABLE NOTATION aThe LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD= 4.66 sb E-V*2.22x10 6 -Y-exp (-At)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, Ais the radioactive decay constant for the particular radionuclide, and t for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.
Typical values of E, V, Y, and t should be used in the calculation.
It should be recognized that the LLD is defined as an a Driori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
bThe principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe-1 35, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,1-131, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 5.9.1.8.
FERMI 2 ODCM - TRM VOLUME II 3-25 Rev. 13
TABLE 4.11.2.1.2-1 (Continued)
TABLE NOTATION CSampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. This requirement does not apply if the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
dNot used.
eTritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
fThe ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation-made in accordance with Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.
9Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 3 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing, at any release point at which the noble gas monitor shows that effluent activity has increased more than a factor of 3.
When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. When samples collected for periods between 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 7 days are analyzed, the corresponding LLDs may be increased by a factor equal to the normal weekly sample volume divided by the volume of the sample in question.
hRequired when the SGTS is in operation.
iln MODES 1, 2, 3, and 4, the applicable portion of primary containment shall be sampled and analyzed within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the start of any PURGING.
tin MODES 1, 2, 3, and 4, when the primary containment atmosphere radiation monitoring system is declared not FUNCTIONALLY CAPABLE or is in alarm condition, the applicable portion of primary containment shall be sampled and analyzed within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the start of any VENTING or PURGING and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING through other than SGTS.
FERMI 2 ODCM - TRM VOLUME II 3-26 Rev. 14
RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE - NOBLE GASES CONTROLS 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 3.0-1) shall be limited to the following:
~~a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and,~~
~~b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.~~
APPLICABILITY: At all times.
ACTION:
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 50.4, a Special Report that identifies the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
~~b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
FERMI 2 ODCM - TRM VOLUME II 3-27 Rev. 14
RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS 3.11.2.3 The 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, from each reactor unit, to areasat and beyond the SITE BOUNDARY (see Figure 3.0-1) shall be limited to the following:
~~a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,~~
~~b. During any calendar year: Less than or equal to 15 mrems to any organ.~~
APPLICABILITY: At all times.
ACTION:
a. With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 50.4, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
~~b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
FERMI 2 ODCM - TRM VOLUME II 3-28 Rev. 14
RADIOACTIVE EFFLUENTS OFF-GAS TREATMENT SYSTEM CONTROLS 3.11.2.4 The OFF-GAS TREATMENT SYSTEM shall be FUNCTIONALLY CAPABLE and shall be in operation.
APPLICABILITY: Whenever the main condenser steam jet air ejectors are in operation.
ACTION:
With the OFF-GAS TREATMENT SYSTEM not FUNCTIONALLY CAPABLE for more than 7 days, prepare and submit to the commission within 30 days, pursuant to 10 CFR 50.4, a Special Report that includes the following information:
~~1. Identification of the equipment or subsystems which are not FUNCTIONALLY CAPABLE and the reason for the not FUNCTIONALLY CAPABLE status,~~
~~2. Action(s) taken to restore the equipment which is not FUNCTIONALLY CAPABLE to FUNCTIONALLY CAPABLE status, and~~
~~3. Summary description of action(s) taken to prevent a recurrence.~~
~~b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable:~~
~~c. The provisions of Control 4.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.11.2.4 The OFF-GAS TREATMENT SYSTEM shall be demonstrated FUNCTIONALLY CAPABLE by meeting Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.
FERMI 2 ODCM - TRM VOLUME 11 3-29 Rev. 14
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM CONTROLS 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM as described in the ODCM shall be FUNCTIONALLY CAPABLE and appropriate portions of the system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site to UNRESTRICTED AREAS (see Figure 3.0-1) would exceed 0.3 mrem to any organ in any 31-day period.
APPLICABILITY: At all times.
ACTION:
With radioactive gaseous waste being discharged in excess of the above limits and any portion of the VENTILATION EXHAUST TREATMENT SYSTEM not in operation, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 50.4, a Special Report that includes the following information:
~~1. Identification of any equipment or subsystems which are not FUNCTIONALLY CAPABLE and the reason for the not FUNCTIONALLY CAPABLE status.~~
~~2. Action(s) taken to restore the equipment which is not FUNCTIONALLY CAPABLE to FUNCTIONALLY CAPABLE status, and~~
~~3. Summary description of action(s) taken to prevent a recurrence.~~
~~b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM, when any portion of the VENTILATION EXHAUST TREATMENT SYSTEM is not in use.
4.11.2.5.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated FUNCTIONALLY CAPABLE by meeting Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.
FERMI 2 ODCM - TRM VOLUME 11 3-30 Rev. 14
RADIOACTIVE EFFLUENTS VENTING OR PURGING CONTROLS 3.11.2.8 VENTING or PURGING of the primary containment shall be through the standby gas treatment system or the reactor building ventilation system.
APPLICABILITY: MODES 1, 2, 3, and 4 ACTION:
~~a. With the requirements of the above control not satisfied, suspend all VENTING or PURGING of the primary containment.~~
~~b. The provision of Controls 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.11.2.8.1 The applicable portion of primary containment shall be sampled and analyzed per Table 4.11.2.1.2-1 of Control 3.11.2.1 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the start of any PURGING.
4.11.2.8.2 If the primary containment radiation monitoring system is not FUNCTIONALLY CAPABLE or is in alarm condition, the applicable portion of primary containment shall be sampled and analyzed per Table 4.11.2.1.2-1 of Control 3.11.2.1 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING of primary containment through other than the standby gas treatment system.
4.11.2.8.3 The primary containment shall be determined to be aligned for VENTING or PURGING through the standby gas treatment system or the reactor building ventilation system within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING of the containment.
4.11.2.8.4 Prior to use of the vent/purge system through the standby gas treatment system assure that:
~~a. Both standby gas treatment system trains are FUNCTIONALLY CAPABLE whenever the vent/purge system is in use, and~~
~~b. Whenever the vent/purge system is in use during MODE 1 or 2 or 3, only one of the standby gas treatment system trains may be used.~~
4.11.2.8.5 Prior to VENTING or PURGING, assure that at least one of the following monitors is FUNCTIONALLY CAPABLE: the primary containment atmosphere radiation monitor, the reactor building ventilation exhaust radiation monitor (at least one division), or the SPING monitor corresponding to the release path (the reactor building exhaust plenum radiation monitor or the standby gas treatment system radiation monitor, Division 1 or 2).
FERMI 2 ODCM - TRM VOLUME II 3-31 Rev. 13
RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 The annual (calendar year) dose or dose commitment to any member of the public (as defined in 40 CFR Part 190) due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times.
ACTION:
~~a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 3.11.1.2a., 3.11.1.2b.,~~
3.11.2.2a., 3.11.2.2b., 3.11.2.3a., or 3.11.2.3b., calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 50.4, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
~~b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.
4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and from outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Control 3.11.4, ACTION a.
FERMI 2 ODCM - TRM VOLUME II 3-32 Rev. 15
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.
APPLICABILITY: At all times.
ACTION:
a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Control 5.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to 10 CFR 50.4, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to A MEMBER OF THE PUBLIC is less than the calendar year limits of Controls 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) + ... >1.0 reporting level (1) reporting level (2)
b. When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Controls 3.11.1.2, 3.11.2.2, and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
~~The methodology used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.~~
FERMI 2 ODCM - TRM VOLUME II .3-33 Rev. 15
RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS (Continued)
c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12.1-1, identify specific locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Control 5.9.1.8, identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report pursuant to Control 5.9.1.8 and also include in the report a revised table for the ODCM reflecting the new location(s).
~~d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.
FERMI 2 ODCM - TRM VOLUME II 3-34 Rev. 13
TABLE 3.12.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Representative Sampling and Exposure Pathway Samples and Sample Collection Type and Frequency and/orSample Locationsa j Frequency of Analysis
~~11. DIRECT RADIATIONb 67 routine monitoring stations, Quarterly Gamma dose quarterly.~~
with two or more dosimeters placed as follows: 1) an inner ring of stations in the general area of the SITE BOUNDARY and additional rings at approximately 2, 5. and 10 miles.
with a station in at least every other meteorological sector for each ring with the exception of those sectors over Lake Erie.
I The balance of the stations, 8, should be placed in special interest areas such as population I centers, nearby residences.
schools. and in 2 or 3 areas to serve as control stations.
~~2. AIRBORNE i Samples from 5 locations. ,Continuous sampler Radioiodine Canister:~~
Radioiodine and operation with sample 1-131 analysis weekly.
Particulates a. 3 samples from close to the 'collection weekly, or 3 SITE BOUNDARY more frequently if Particulate Sampler:
locations. in different sectors, ,,required by dust Gross beta radioactivity of the highest calculated Iloading. analysis following filter annual average ground level change:d XIQ. I Gamma isotopic
~~b. 1 sample from the vicinity of a community having the analysise of composite highest calculated annual (by location) quarterly.~~
~~average ground level X/O~~
c. 1 sample from a control location, as for example 15-30 km distant and in the least prevalent wind directionc FERMI 2 ODCM - TRM VOLUME II 3-35 Rev. 14
TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Representative Sampling and Exposure Pathway Samples and Sample Collection Type and Frequency and/or Sample Locationsa Frequency of Analysis j
~~3. WATERBORNE~~
~~a. Surfacef I a. 1 sample upstream. Composite sample Gamma isotopic~~
~~b. 1 sample downstream. over 1-month periodg analysise monthly.~~
Composite for tritium analysis quarterly.
l b. Ground Samples from 1 or 2 sources only Quarterly Gamma isotopice and if likely to be affected. tritium analysis quarterly.
~~c. Drinking~~
a. 1 sample of each of 1 to 3 of Composite sample 1-131 analysis on each the nearest water supplies over 2-week periods when the that could be affected by its when 1-131 analysis is dose calculated for the discharge. performed, monthly isugeter tha l I ompoite otherwise.
composite therise water is greater than 1 I b. 1 sample from a control mrem per year.'
I location. Composite for gross beta and gamma lI isotopic analysese monthly. Composite for tritium analysis quarterly.
d. Sediment from S shoreline I1 sample from downstream area I Gamma isotopic with existing or potential recreational value.
FERMI 2 ODCM - TRM VOLUME 11 3-36 Rev. 13
TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM N rfRepresenitative rapingnd
?~ahd/Samp~~ 7~I~ ~§-V Freqency 2 b§d$Freqn~Iy-isw
~~4. INGESTION~~
a. Milk a. Samples from milking Semimonthly when Gamma isotopice and animals in 3 locations within animals are on 1-131 analysis 5 km distance having the pasture, monthly at semimonthly when highest dose potential. If other times. animals are on pasture; there are none, then, 1 monthly at other times.
~~sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yri.~~
~~b. 1 sample from milking animals at a control location 15-30 km distant and in the least prevalent wind direction.~~
~~a. 1 sample of each Sample in season, or Gamma isotopic~~
b. Fish and commercially and semiannually if they Invertebrates are not seasonal. analysise on edible recreationally important portions.
~~species in vicinity of plant discharge area.~~
~~b. 1 sample of same species in areas not influenced by plant discharge.~~
~~a. 1 sample of each principal At time of harvesti. Gamma isotopic~~
~~c. Food Products class of food products from any area that is irrigated by analysese on edible water in which liquid plant portions.~~
~~wastes have been discharged.~~
~~b. Samples of 3 different kinds Monthly when Gamma isotopice and of broad leaf vegetation available. 1-131 analysis.~~
grown nearest each of two different offsite locations of highest predicted annual average level D/O if locations are available and milk I sampling is not performed.
Monthly when Gamma isotopice and
~~c. 1 sample of each of the available. 1-131 analysis.~~
similar broad leaf vegetation grown 15-30 km distant in the least prevalent wind direction if milk sampling is not Derformed.
FERMI 2 ODCM - TRM VOLUME II 3-37 Rev. 14
TABLE 3.12.1-1 (Continued)
TABLE NOTATIONS aSpecific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12.1-1 in a table in the ODCM. Referto NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Control 5.9.1.8, identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised table for the ODCM reflecting the new location(s).
bOne or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.
CThe purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that have valid background data may be substituted.
dAirborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
eGamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
FERMI 2 ODCM - TRM VOLUME II 3-38 Rev. 13
TABLE 3.12.1-1 (Continued)
TABLE NOTATION fThe "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in an area beyond but near the mixing zone.
"Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.
gComposite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly).
hGroundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
iThe dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.
ilf harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.
FERMI 2 ODCM - TRM VOLUME II 3-39 Rev. 13
TABLE 3.12.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Water Airborne Fish Milk Food Analysis (p Ciil) Particulateor (pCi/kg, wet) (pCi/l) Products Gases (pCi/m3 ) (pCi/kg, wet)
H-3 20,000 I Mn-54 1,000 30,000 IFe-59 400 10,000 Co-58 1,000 30.000 l Co-60 300 10.000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 ICs-134 30 10 1.000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300
~~For drinking water samples. This is 40 CFR Part 141 value.~~
FERMI 2 ODCM - TRM VOLUME II 3-40 Rev. 13
TABLE 4.12.1-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS a LOWER LIMIT OF DETECTION (LLD)bC Water Airborne Fish Milk Food Sediment
{Analysis (pCO/) GParticulateor (pC(Ikg, wet) (pCill) Products (pCeIkg, dry) I A Gases (pCuam3e (t (pCo/kg, we gross beta 4 0.01 H-3 2000 IMn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 11-131 ld 0.07 1 60
! Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 FERMI 2 ODCM - TRM VOLUME II 3-41 Rev. 13 l
TABLE 4.12.1-1 (Continued)
TABLE NOTATIONS aThis list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
bRequired detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
cThe LLD is defined, for purposes of these Controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD = 4.66
~~Sb E*V-2.22 .Y exp (-At)~~
Where:
LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y, and t should be used in the calculation.
FERMI 2 ODCM - TRM VOLUME II 3-42 Rev. 13
TABLE 4.12.1-1 (Continued)
TABLE NOTATIONS It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
dLLD for drinking water samples.
FERMI 2 ODCM - TRM VOLUME II 3-43 Rev. 13
RADIOLOGICAL ENVIRONMENTAL MONITORING 314.12.2 LAND USE CENSUS CONTROLS 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation.
APPLICABILITY: At all times.
ACTION:
a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Surveillance Requirement 4.11.2.3, identify the new location(s) in the next Annual Radioactive Effluent Release Report, pursuant to Control 5.9.1.8.
b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Control 5.9.1.8, identify the new location(s) in the next Annual Radioactive Effluent Release Report and also include in the report a revised table for the ODCM reflecting the new location(s).
~~c. The provisions of Control 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Controls for broad leaf vegetation sampling in Table 3.12.1-1, Part 4.c, shall be followed, including analysis of control samples.
FERMI 2 ODCM - TRM VOLUME II 3-44 Rev. 13
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which is audited periodically by Fermi 2 Quality Assurance.
APPLICABILITY: At all times.
ACTION:
a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
~~b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.~~
SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
FERMI 2 ODCM - TRM VOLUME 11 3-45 Rev. 13
Figure 3.0-1: map Defining Unrestricted Areas and Si. oundary For Radioactive Gaseous and Liquid Effluents FERMI 2 ODCM - TRM VOLUME II 3-46 END OF SECTION 3.0 Rev. 13 I
SECTION 4.0 BASES FERMI 2 ODCM - TRM VOLUME II 4-1 Rev. 13,
INSTRUMENTATION BASES 3/4.3.7.11 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONAL CAPABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3.7.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor arid control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM utilizing the system design flow rates as specified in the ODCM. This conservative method is used because the Fermi 2 design does not include flow rate measurement devices. This will ensure the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONAL CAPABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part, 20.1301 to a MEMBER OF THE PUBLIC. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedure Manual, HASL-300 (revised annually),
Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
FERMI 2 ODCM - TRM VOLUME 11 4-2 Rev. 13 l
RADIOACTIVE EFFLUENTS BASES 314.11.1.2 DOSE This control is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The control implements the guides set forth in Section Il.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and.
parameters in the ODCM implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The FUNCTIONAL CAPABILITY of the liquid radwaste treatment system ens-ures that this system will be available for use whenever liquid effluents require treatment prior to their release to the environment. The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix 1,10 CFR Part 50, for liquid effluents.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This control is provided to ensure that the dose to individual MEMBERS OF THE PUBLIC from gaseous effluents from all units on the site will be within the limits of 10 CFR Part 20.1301.
FERMI 2 ODCM - TRM VOLUME II 4-3 Rev. 13
RADIOACTIVE EFFLUENTS BASES 3/4.11.2.1 DOSE RATE (Continued)
Although this control applies to the SITE BOUNDARY, the occupancy and exposure pathways applicable to a MEMBER OF THE PUBLIC who may at times be within the SITE BOUNDARY will usually be such that such an individual will not receive significantly greater dose due to gaseous effluents than a MEMBER OF THE PUBLIC who remains outside the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified dose rate limits restrict, at all times, the dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal tQ 500 mrems/year to the total body or to less than or equal to 3000 mrems/year to the skin. These dose rate limits also restrict, at all times, the thyroid dose rates above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually),
Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
3/4.11.2.2 DOSE - NOBLE GASES This control is provided to implement the requirements of Sections II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The control implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
FERMI 2 ODCM - TRM VOLUME 11 4-4 Rev. 13
RADIOACTIVE EFFLUENTS BASES 3/4.11.2.3 DOSE- IODINE-131, IODINE-133. TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM This control is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The controls are the guides set forth in Section Il.C of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.
These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-1 31, iodine-1 33, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
3/4.11.2.4 OFF-GAS TREATMENT SYSTEM The FUNCTIONAL CAPABILITY of the OFF-GAS TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of General Design Criteria 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section lI.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.8 and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
FERMI 2 ODCM - TRM VOLUME II 4-5 Rev. 13
RADIOACTIVE EFFLUENTS BASES 3/4.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM The requirement that the appropriate portions of this system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections Il.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents.
3/4.11.2.8 VENTING OR PURGING This control provides reasonable assurance that releases from primary containment purging operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS.
3/4.11.4 TOTAL DOSE This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a member of the public to within the 40 CFR Part 190 limits. For the purpose of the Special Report, it may be assumed that the dose commitment to the member of the public from other than uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any -member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
FERMI 2 ODCM - TRM VOLUME II 4-6 Rev. 13
RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological environmental monitoring program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measureable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12.1-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedure Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968),
and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
3/4.12.2 LAND USE CENSUS This control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey, from visual survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified
'and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2 .
FERMI 2 ODCM - TRM VOLUME II 4-7 Rev. 13
RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program which is audited periodically is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
END OF SECTION 4.0 FERMI 2 ODCM - TRM VOLUME 11 4-8 Rev. 13
SECTION 5.0 ADMINISTRATIVE CONTROLS FERMI 2 ODCM - TRM VOLUME II 5-1 Rev. 13 l
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 5.9.1.7 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The initial report shall be submitted prior to May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison as appropriate, with preoperational studies, with operational controls, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
The reports shall also include the results of land use censuses required by Control 3.12.2. The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in Table 10.0-1 in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. If possible, the missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following: a summary description of the radiological environmental monitoring program; one or more tables covering all sampling locations; the results of licensee participation in the Interlaboratory Comparison Program, required by Control 3.12.3; discussion of all deviations from the sampling schedule of Table 3.12.1-1; and discussion of all analyses in which the LLD required by Table 4.12.1-1 was not achievable.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*
5.9.1.8 Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous year of operation shall be submitted prior to May 1 of each year. The period of the first report shall begin with the date of initial criticality.
A single submittal may be made for a mutiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
FERMI 2 ODCM - TRM VOLUME II 5-2 Rev. 13
ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)
The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The Annual Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on an electronic medium of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.*** This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 3.0-1) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. The assessment of radiation doses shall be performed in accordance with methodology and parameters in the ODCM.
The Annual Radioactive Efluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:
~~a. Total volume in all containers,~~
~~b. Total curie quantity (specify whether determined by measurement or estimate),~~
In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
FERMI 2 ODCM - TRM VOLUME II 5-3 Rev. 13
ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)
~~c. Principal radionuclides (specify whether determined by measurement or estimate),~~
~~d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),~~
~~e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and~~
~~f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).~~
The Annual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Annual Radioactive Effluent Release Reports shall include any changes made during the reporting period-to the OFFSITE DOSE CALCULATION MANUAL (ODCM) as described in Technical Specification 5.5.1.3, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Control 3.12.2.
The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the not FUNCTIONALLY CAPABLE status of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Control 3.3.7.11 or 3.3.7.12, respectively; and description of the events leading to liquid holdup tanks exceeding the limits of Technical Specification 5.5.8.6.
5.15 MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS*
5.15.1 Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid):
~~a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the OSRO. The discussion of each change shall contain:~~
~~1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.~~
~~2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;~~
~~Licensees may choose to submit the information called for in this Control as part of the UFSAR revision in accordance with 10 CFR 50.71(e).~~
FERMI 2 ODCM - TRM VOLUME II 5-4 Rev. 14
ADMINISTRATIVE CONTROLS
~~3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;~~
4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;
5. An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;
6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;
~~7. An estimate of the exposure to plant operating personnel as a result of the change; and~~
~~8. Documentation of the fact that the change was reviewed and found acceptable by the OSRO.~~
~~b. Shall become effective upon review and acceptance by the OSRO.~~
END OF SECTION 5.0 FERMI 2 ODCM - TRM VOLUME II 5-5 Rev. 13
Nuclear Production - Fermi 2 ODCM-6.0 Offsite Dose Calculation Manual Page 6.0-1 PART II CALCULATIONAL METHODS
SECTION 6.0 LIQUID EFFLUENTS FERMI 2 ODCM - TRM VOLUME II 6-1 Rev. 13
6.0 LIQUID EFFLUENTS This section summarizes information on the liquid effluent radiation monitoring instrumentation and controls. More detailed information is provided in the Fermi 2 UFSAR and Fermi 2 design drawings from which this summary was derived. This section also describes the sampling and analysis required by the Offsite Dose Calculation Manual. Methods for calculating alarm setpoints for the liquid effluent monitors are presented. Also, methods for evaluating doses from liquid effluents are provided.
6.1 Radiation Monitoring Instrunientation and Controls This section summarizes the instrumentation and controls monitoring liquid effluents. This discussion focuses on the role of this equipment in assuring compliance with the Offsite Dose Calculation Manual.
6.1.1 Offsite Dose Calculation Manual (ODCM) 3.3.7.11 Requirement Fermi 2 ODCM 3.3.7.11 prescribes the monitoring required during liquid releases and the backup sampling required when monitors are not FUNCTIONALLY CAPABLE.
The liquid effluent monitoring instrumentation for controlling and monitoring radioactive effluents in accordance with the Fermi 2 ODCM 3.3.7.11 is summarized below:
~~1. Radiation Alarm - Automatic Release Termination~~
a. Liquid Radwaste Effluent Line - The D1 1-N007 Radiation Monitor on the liquid radwaste effluent line provides the alarm and automatic termination of liquid radioactive material releases prior to exceeding 1 Maximum Permissible Concentration (MPC) at the discharge to Lake Erie, as required by ODCM 3.3.7.11. The monitor is located upstream of the Isolation Valve (G11 -F733) on the liquid radwaste discharge line and monitors the concentration of liquid effluent before dilution by the circulating water reservoir (CWR) decant flow.
~~2. Radiation Alarm (only)~~
a. Circulating Water Reservoir (CWR) Decant Line - The CWR Decant Line Radiation Monitor (D1 1-N402) provides indication of the concentration of radioactive material in the diluted radioactive liquid releases just before discharge to Lake Erie. As required by ODCM 3.3.7.11, the alarm setpoint is established to alarm (only) prior to exceeding one MPC.
~~FERMI 2 ODCM - TRM VOLUME II 6-2 Rev. 13~~
~~3. Flow Rate Measuring Devices~~
~~a. Liquid Radwaste Effluent Line - In accordance with ODCM 3.3.7.11, the release rate of liquid-radwaste discharges is monitored by G11-R703.~~
~~This flow rate instrumentation is located on the radwaste discharge line prior to the junction with the CWR decant line.~~
b. Circulating Water Reservoir Decant Line - The flow rate measuring device for the CWR decant line has been removed. The flow rate of the CWR decant line is now measured using certified pump performance curves for the CWR decant pumps, together with readings from pump discharge pressure gauges and reservoir level indication.
~~6.1.2 Non-ODCM Required Monitor An additional monitor not required by Fermi 2 ODCM is provided by Detroit Edison to reduce the likelihood of an unmonitored release of radioactive liquids.~~
1. General Service Water - The General Service Water (GSW) Radiation Monitor (D1 1-N008) provides additional control of potential radioactive effluents. D1 1-N008 monitors the GSW System prior to discharge into the Main Condenser circulating water discharge line to the Circulating Water Reservoir. Although not an ODCM required monitor, D1l-N008 monitors a primary liquid stream in the plant that also discharges to the environment (Lake Erie via the Circulating Water Reservoir). Indication of radioactive material contamination in the GSW System would also indicate potential CWR contamination and the need to control all discharges from the CWR as radioactive effluents.
FERMI 2 ODCM - TRM VOLUME 11 6-3 Rev. 14
6.2 Sampling and Analysis of Liquid Effluents The program for sampling and analysis of liquid waste is prescribed in the Fermi 2 Offsite Dose Calculation Manual Table 4.11.1.1.1-1. This table distinguishes two types of liquid releases: a) BATCH releases, defined as discrete volumes, from the Waste Sample Tanks (normally after processing through the radwaste system), and b) CONTINUOUS releases, from the Circulating Water Reservoir (CWR) System, if it becomes contaminated.
Continuous releases from the CWR System are via the CWR decant line to Lake Erie.
The CWR System is not expected to become contaminated. Therefore, continuous radioactive material releases are not expected. However, the General Service Water (GSW) and the CWR systems interface with radioactive systems in the plant. Also, the GSW intake is within a few hundred feet of the CWR decant line discharge to Lake Erie.
For these reasons, it is prudent to consider the GSW and the CWR a potential source of radioactive effluents and to sample them regularly.
6.2.1 BATCH Releases Fermi 2 ODCM Table 4.11.1.1.1-1 requires that a sample representative of the tank contents be obtained before it is released. The table specifies the following program:
- Prior to sampling, the tank is isolated. The tank level is determined and this value is converted to tank volume. A pump with a known recirculation flow rate is then activated to recirculate tank contents. The pump is allowed to run for at least the time required to recirculate the tank volume twice.
Prior to each batch release, analysis for principal gamma emitters and dissolved and entrained gases (including all peaks identified by gamma spectroscopy)
Once per month, analysis of a composite sample of all releases that month for tritium (H-3) and gross alpha activity. (The composite sample is required to be representative of the liquids released and sample quantities of the composite are to be proportional to the quantities of liquid discharged).
Once per quarter, analysis of a composite sample of all releases that quarter for Strontium (Sr)-89, Sr-90, and Iron (Fe)-55.
FERMI 2 ODCM - TRM VOLUME II 6-4 Rev. 13
6.2.2 CONTINUOUS Releases Fermi 2 00CM Table 4.11.1.1.1.-1 requires that composite samples be collected from the CWR System, if contaminated. The table specifies the following sample analysis:
- Once per month, analysis of a composite sample for principal gamma emitters and for 1-131.
- Once per month, analysis of a composite sample for H-3 and gross alpha.
- Once per month, analysis of weekly grab samples (composited) for dissolved and entrained gases (gamma emitters).
- Once per quarter, analysis for Sr-89, -90 and Fe-55.
6.3 Liquid Effluent Monitor Setpoints Offsite Dose Calculation Manual 3.11.1.1 requires that the concentration of liquid radioactive effluents not exceed the unrestricted area MPC at the discharge point to Lake Erie. Dissolved or entrained noble gases in liquid effluents are limited to a concentration of 2 E-04 pCi/ml, total noble gas activity. ODCM 3.3.7.11 requires that radiation monitor setpoints be established to alarm prior to exceeding the limits of ODCM 3.1 1.1.1.
To meet this specification, the alarm setpoints for liquid effluent monitors are determined in accordance with the following equation:
5p CL(DF+ RR)
RR (6-1) where:
SP = the setpoint, in pCi/ml, of the monitor measuring the radioactivity concentration in the effluent line prior to dilution. The setpoint represents a value which, if exceeded, would result in concentrations exceeding the MPC in the unrestricted area CL = the effluent concentration limit (ODCM 3.11.1.1) corresponding to ten times the limits of 10 CFR Part 20.1302.b.2.i at the discharge point in pCi/ml, defined in Equation (6-4)
FERMI 2 ODCM - TRM VOLUME II 6-5 Rev. 13
RR = the liquid effluent release rate as measured at the radiation monitor location, in volume per unit time, but in the same units as DF, below DF = the dilution water flow as measured prior to the release point (Lake Erie) in volume per unit time At Fermi 2 the available Dilution Water Flow (DF) is essentially constant for a given release, and the waste tank Release Rate (RR) and monitor Setpoint (SP) are set to meet the condition of Equation (6-1) for a given effluent Concentration Limit, CL.
NOTE: If no dilution is provided, SP < CL. Also, when DF is large compared to RR, then (DF + RR)-DF, and DF may be used instead of (DF + RR) as a simplification, as in Equation (6-5).
6.3.1 Liquid Radwaste Effluent Line Monitor The Liquid Radwaste Effluent Line Monitor D1 1-N007 provides alarm and automatic termination of releases prior to exceeding MPC. As required by ODCM Table 4.11.1.1.1.-1 and as discussed in ODCM Section 6.2.1, a sample of the liquid radwaste to be discharged is collected and analyzed by gamma spectroscopy to identify principal gamma emitting radionuclides. From the measured individual radionuclide concentrations, the allowable release rate is determined.
The allowable release rate is inversely proportional to the ratio of the radionuclide concentrations to the MPC values. The ratio of the measured concentration to MPC values is referred to as the "MPC fraction" and is calculated by the equation:
MIPCF=E C' MPCj (6-2) where:
MPCF = fraction of the unrestricted area MPC for a mixture of gamma emitting radionuclides Ci = concentration of each gamma emitting radionuclide i measured in each tank prior to release (pCi/ml)
MPCi = unrestricted area most restrictive MPC for each radionuclide i: ten times the value from 10 CFR Part 20, Appendix B, Table 2, Column 2. For dissolved and entrained noble gases an MPC value of 2E-04 pCi/ml may be used, but noble gases need not be included in this calculation.
FERMI 2 ODCM - TRM VOLUME II 6-6 Rev. 13
Including noble gases in Equation (6-2) eliminates the need for a separate evaluation of compliance with the noble gas concentration limit of ODCM 3.1 1.1.1.
Based on the MPCF, the maximum allowable release rate can be calculated by the following equation:
An RR <DF (MPCF* (I + BF))+ H3MPCF (6-3) where:
MAX RR = maximum acceptable waste tank discharge rate (gal/min)
(Monitor #G1 1-R703)
DF = dilution flow rate from the CWR decant line, measured as described in ODCM section 6.1.1.3.b.
SF = administrative safety factor to account for variations in monitor response and flow rates. A SF value.of 0.5 is suggested because it provides for 100% variation caused by statistical fluctuation and/or errors in measurements.
BF = conservative estimate of the ratio of the MPC fraction of pure beta emitters other than tritium to the gamma MPC fraction (MPCF) (The value 0:10 may be used for BF.)
MPCF = As previously defined by equation (6-2)
H3MPCF = conservative estimate of MPC fraction due to tritium (The value 0.13 may be used for H3MPCF.)
NOTE: Equation (6-3) is valid only for MPCF >1; if the MPCF <1, the waste tank concentration meets the limits of 10 CFR Part 20 without dilution, and the tank may be discharged at the maximum rate.
If MAX RR as calculated above is greater than the maximum discharge pump capacity, the pump capacity should be used in establishing the actual Release Rate RR for the radwaste discharge. For a Waste Sample Tank, the maximum discharge rate is 50 gallons per minute. This Release Rate RR is monitored in the Radwaste Control Room by G11 -R703.
FERMI 2 ODCM - TRM VOLUME II 6-7 Rev. 14
The Concentration Limit (CL) of a liquid radwaste discharge is the same as the effective MPC for the radionuclide mixture of the discharge. Simply, the CL (or effective MPC) represents the equivalent MPC value for a mixture of radionuclides evaluated collectively. The equation for determining CL is:
CL= =C MPCF (6-4)
Based on the Release Rate RR and Dilution Flow DF and by substituting Equation (6-4) for CL in Equation (6-1) and introducing sensitivity factors and factors to account for the presence of pure beta emitters, the alarm setpoint is calculated by the equation:
SP < (Cj *SE-N)* DF*H3F*SF MPCF*(I + BF)* RR +Bkg (6-5) where:
SP = setpoint of the radiation monitor counts per second (cps) or counts per minute (cpm)
Ci = concentration of radionuclide i as measured by gamma spectroscopy (pCi/ml)
SENi monitor sensitivity for radionuclide i based on calibration curve (cps/(pCi/ml) or cpm/(pCi/ml)) or single conservative value for all radionuclides (see below)
RR = actual release rate of the liquid radwaste discharge (gal/min)
BF = pure beta factor as defined for Equation (6-3)
MPCF = MPC fraction as determined by Equation (6-2)
H3F = correction factor to account for estimated tritium concentration at the discharge point (The value 0.99 may be used.)
Bkg = background reading of monitor (cps)
DF = dilution flow rate from the CWR decant line, measured as described in ODCM section 6.1.1.3.b. Also see note preceding Section 6.3.1.
SF = 1.0 when a single conservative sensitivity value is used; 0.5 when individual nuclide sensitivity factors are used FERMI 2 ODCM - TRM VOLUME II 6-8 Rev. 14
The sensitivity of Cr-51 determined from the primary calibration sensitivity curves may be used as a single conservative value for SENi above. The Cr-51 sensitivity has been determined to be conservative based on the nuclide mixes which have been seen in actual liquid discharges from Fermi 2. For the D11-N007 monitor, a monitor sensitivity value of 1.0 E6 cps/(pCi/ml) may be used as the single conservative value of SENi.
If no radionuclides are measured by gamma spectroscopy, the alarm setpoint can be established at one half the setpoint of the most recent discharge for which radionuclides were detected by gamma spectroscopy.
Prior to conducting any batch liquid radwaste release, Equation (6-3) is used to determine the allowable release rate in accordance with ODCM 3.11.1.1.
Equation (6-5) is used to determine the alarm setpoint in accordance with ODCM 3.3.7.11.
6.3.2 Circulating Water Reservoir Decant Line Radiation Monitor (DI I-N402)
ODCM 3.3.7.11 requires that the setpoint for the CWR Decant Line Radiation Monitor D1 1-N402 be established to ensure the radioactive material concentration in the decant line prior to discharge to Lake Erie does not exceed MPC, unrestricted area (ten times 10 CFR 20, Appendix B, Table 2, Column 2 values). The approach for determining the alarm setpoint for the CWR Decant Line Radiation Monitor is the same as presented in Section 6.3.1. However, the CWR Decant Line Radiation Monitor setpoint need not be changed prior to each release. Equation (6-1) remains valid, except that, for the CWR Decant Line Monitor, the dilution flow previously assumed for diluting the BATCH liquid radwaste effluents is now the release rate; There is no additional dilution prior to discharge to Lake Erie. Thus, Equation (6-1) simplifies to:
SP < CL (6-6)
Substituting Equation (6-4) for CL and introducing a safety factor, sensitivity factors, and monitor background, the D1 1-N402 alarm setpoint can be calculated by the equation:
Sp < E(C, *SEN,)*SF Bk MPCF (6-7)
FERMI 2 ODCM - TRM VOLUME II 6-9 Rev. 13
where:
SP = setpoint in counts per minute (cpm)
C = concentration of each radionuclide i in the CWR decant line effluent (pCi/ml)
SENi = monitor sensitivity for nuclide i based on calibration curve (cpml/(PCi/ml))
MPCF MPC fraction as determined by Equation (6-2) with Ci defined as for Equation (6-7)
SF 0.5, administrative safety factor Bkg = background reading of monitor (cpm)
Normally, only during periods of batch liquid radwaste discharges will there exist any plant-related radioactive material in the CWR decant line.
6.3.3 Generic, Conservative Alarm Setpoint for Di I-N402 The D1 1-N402 setpoint could be adjusted for each BATCH release as is done for the liquid radwaste effluent line monitor. Based on the measured levels of radioactive material in a BATCH liquid release, the alarm setpoint for D1 1-N402 could be calculated using Equation (6-7). However, during these planned releases, the concentrations will almost always be so low (due to dilution) that the D1 1-N402 Monitor will not indicate measurable levels. The CWR decant line design flow is 10,000 gpm; and the maximum liquid radwaste release rate is 50 gpm, providing a 200:1 dilution. The radioactive material concentration of BATCH liquid releases is typically in the range of 10-7 to 104 pCi/ml. With a nominal 200:1 dilution (actual dilution has been greater since in actual releases the decant line flow rate has been about 18,000 gpm), the CWR decant line monitor would monitor diluted activity in the range of 5 x 10-10 to 5 x 10-7 pCilml. D1 1-N402 Monitor response at these levels would be 0.1 to 100 cpm, depending on the particular radionuclide mixture and corresponding instrument response. These response levels are less than the monitor background levels.
In lieu of routinely adjusting the D1 1-N402 setpoints, generic, conservative setpoints have been established based on an analysis of nuclides seen in actual liquid discharges and on the primary calibration sensitivity curve.
FERMI 2 ODCM - TRM VOLUME II 6-10 Rev. 13
6.3.4 Alarm Setpoint for GSW and RHR System Radiation Monitors Levels of radioactive material detectable above background at Radiation Monitor D1 1-N008 would be one of the first indicators of contamination of the General Service Water (GSW) System and the CWR. Likewise, for the Residual Heat Removal (RHR) System, the D1 1-N401 A and B Monitors would be one of the first indicators of contamination and subsequent contamination of the CWR.
Therefore, to provide early indication and assure prompt attention, the alarm setpoints for these monitors should be established as close to background as possible without incurring a spurious alarm due to background fluctuations. This level is typically around three times background.
If the GSW System or RHR System becomes contaminated, it may become necessary to raise the radiation monitor setpoints. The alarm setpoints should be re-evaluated to provide the CR operator a timely indication of further increasing activity levels in the GSW or RHR System without spurious alarms.
The method for this re-evaluation is the same as described above - the alarm setpoint established at three times its current reading. No regulatory limits apply for establishing a maximum value for these alarm setpoints since these monitors are located on plant systems and do not monitor final release points to the environment. However, as a practical matter, upper limits on the alarm setpoints can be evaluated using the methods of ODCM Section 6.3.1 based on the actual system flows, dilution and release paths in effect at the time.
6.3.5 Alarm Response - Evaluating Actual Release Conditions Normally, liquid release rates are controlled and alarm setpoints are established to ensure that the release does not exceed the concentration limits of ODCM 3.11.1.1 at the discharge to Lake Erie. However, if either Monitor D11-N007 or D1 1-N402 alarms during a liquid release, it becomes necessary to re-evaluate the release conditions to determine compliance with ODCM 3.11.1.1.
Following an alarm, the actual release conditions should be determined.
Radioactive material concentrations should be evaluated by sampling the effluent stream or resampling the waste tank. Discharge flow and dilution water flow should be redetermined.
To perform this evaluation, the following equation may be used for all nuclides, or dissolved and entrained noble gases may be evaluated separately from other nuclides using this equation:
r(Cj0 RR *(I + B
[4MPC9*DF+RR H3F]
(6-8)
FERMI 2 ODCM - TRM VOLUME II 6-11 Rev. 13
where:
Cj = measured concentration of radionuclide i in the effluent stream (pCi/ml)
MPCi = the MPC value for radionuclide i: ten times the 10 CFR 20, Appendix B, Table 2, Column 2 value (pCi/ml); 2 E-04 pCi/ml for dissolved or entrained noble gases RR = actual release rate of the liquid effluent at the time of the alarm, gpm DF = actual dilution circulating water flow at the time of the release alarm, gpm H3F,BF = as previously defined NOTE: For alarm on D1 1-N402 (CWR decant line), the Release Rate RR is the Dilution Water Flow DF and the DF term drops out of the equation.
6.3.6 Liquid Radwaste Monitor Setpoint Determination with Contaminated Circulating Water Reservoir In the event the CWR is determined to contain radioactive material, the effective dilution capacity of the CWR is reduced as a function of the MPCF. To determine the available dilution flow capacity the MPCF for the CWR is determined using equation (6-2). The MPCF of the CWR is used to determine the available dilution flow as follows:
CWR Dilution Flow = CWR Decant Flow Rate (GPM) * (1-CWR MPCF)
(6-9)
The resulting dilution flow rate is substituted in equation (6-3) to determine the maximum allowable release rate for discharges from the radwaste system.
Substituting the available CWR dilution flow from equation (6-9), the Liquid Radwaste Monitor maximum release rate can be determined using equation (6-3).
Once the available dilution flow and maximum allowable release rate have been determined the radwaste monitor setpoint can be determined using equation (6-5).
FERMI 2 ODCM - TRM VOLUME 11 6-12 Rev. 13
6.4 Contaminated GSW or RHR System - Quantifying and Controlling Releases The GSW Radiation Monitor (D1 1-N008) provides an indication of contamination of this system. The Monitors D1 1-N401 A and B perform this function for the RHR System.
Also, the CWR Decant Line Radiation Monitor monitors all liquid releases from the plant and would record any release to Lake Erie from either of these systems if contaminated.
As discussed in ODCM Section 6.2.2, sampling and analysis of the CWR System is required only if this system is contaminated, as would be indicated by D1 1-N402 or D1-N008. Nonetheless, periodic samples are collected from the CWR System to verify absence of contamination. Although not required by the ODCM, periodic sampling and analysis of the RHR System is also performed since it also is a potential source of contamination of the CWR and subsequent releases to Lake Erie. If contamination is found, further releases from the applicable system (GSW or RHR) via the CWR decant line must be evaluated and controlled to ensure that releases are maintained ALARA.
The following actions will be considered for controlling releases.
- Sampling frequency of the applicable source (GSW or RHR System) and the CWR will be increased until the source of the contamination is found and controlled. This frequency may be relaxed after the source of contamination has been identified and isolated.
- Gamma spectral analysis will be performed on each sample.
- The measured radionuclide concentrations from the gamma spectral analysis will be compared with MPC (Equation 6-2) to ensure releases are within the limits of ODCM 3.11.1.1.
- Based on the measured concentrations, the setpoint for the CWR Decant Line Radiation Monitor (D1 1-N402) will be determined as specified in Section 6.3.2. If the calculated setpoint based on the measured distribution is greater than the current setpoint (see ODCM Section 6.3.3) no adjustment to the setpoint is required.
- Samples will be composited in accordance with ODCM Table 4.11.1.1.1-1 for monthly analysis for H-3 and gross alpha and for quarterly analysis for Sr-89, 90 and Fe-55.
- Each sample will be considered representative of the releases that have occurred since the previous sample. For each sample (and corresponding release period), the volume of liquid released to the lake will be determined based on the measured CWR decant line cumulative flow. .
- From the sample analysis and the calculated volume released, the total radioactive material released will be determined and considered representative of the release period. Cumulative doses will be determined in accordance with ODCM Section 6.5.
FERMI 2 ODCM - TRM VOLUME 11 6-13 Rev. 13
6.5 Liquid Effluent Dose Calculation -10 CFR 50 The parameters of the liquid release (or estimated parameters, for a pre-release calculation) may be used to calculate the potential dose to the public from the release (or planned release). The dose calculation provides a conservative method for estimating the impact of radioactive effluents released by Fermi 2 and for comparing that impact against limits set by the NRC in the Fermi 2 ODCM. The limits in the Fermi 2 ODCM are specified as quarterly and calendar year limits. This assures that the average over the year is kept as low as reasonably achievable.
6.5.1 MEMBER OF THE PUBLIC Dose - Liquid Effluents ODCM 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from Fermi 2 to:
- during any calendar quarter;
< 1.5 mrem to total body
< 5.0 mrem to any organ
- during any calendar year;
< 3.0 mrem to total body
<10.0 mrem to any organ ODCM 4.11.1.2 requires that quarterly and annual cumulative dose due to liquid effluents be determined at least once per 31 days. The calculation of the potential doses to MEMBERS OF THE PUBLIC is a function of the radioactive material releases to the lake, the subsequent transport and dilution in the exposure pathways, and the resultant individual uptake. At Fermi 2, pre-operational evaluation of radiation exposure pathways indicated that doses from consumption of fish from Lake Erie provided the most conservative estimate of doses from releases of radioactive liquids. However, with the proximity of the water intakes for the City of Monroe and Frenchtown Township, it must be assumed that individuals will consume drinking water as well as fish that might contain radioactivity from discharges into Lake Erie.
Study of the currents in Lake Erie indicates that the current in the Lagoona Beach embayment carries liquid effluents from Fermi 2 north along the coast part of the time and south along the coast part of the time. When the current flows north, liquid effluents are carried away from the drinking water Intakes, so only the fish consumption exposure pathway must be considered.
When the current flows south, toward the drinking water Intakes, both fish consumption and drinking water consumption exposure pathways must be considered. To ensure conservatism in the dose modelinig, the combined fish and drinking water pathway is used for evaluating the maximum hypothetical dose to a MEMBER OF THE PUBLIC from liquid radioactive effluents. The following calculational methods may be used for determining the dose or dose commitment due to the liquid radioactive effluents from Fermi 2:
FERMI 2 ODCM - TRM VOLUME II 6-14 Rev. 13
D 1.67 E- 02
~~VOL , (C, *A.)~~
DF*Z (6-10) where:
Do = dose or dose commitment to organ o or total body (mrem) due to release of a single tank Aio = site-specific ingestion dose commitment factor to the total body or any organ o for radionuclide i (mrem/hr per pCi/ml)
Ci = concentration of radionuclide i in undiluted liquid effluent representative of the volume VOL (pCi/ml)
VOL = total volume of liquid effluent released (gal)
DF = average dilution water flow (CWR decant line) during tank release (gal/min)
Z = 5, near field dilution factor (Derived from Regulatory Guide 1.109, Rev 0) 1.67 E-02 = 1 hr/60 min The site-specific ingestion dose/dose commitment factors (Aio) represents a composite dose factor for the fish and drinking water pathway. The site-specific dose factor is based on the NRC's generic maximum individual consumption rates. Values of Aio are presented in Table 6-1. They were derived in accordance with guidance of NUREG-0133 from the following equation:
A,, = 1.14 E + 1R(Uf. / D,.)+(U..
~~BJ,)] DF (6-11) where:~~
UF = 21 kg/yr adult fish consumption UW = 730 liters/yr adult water consumption DW = 13.4, additional dilution from the near field to the water intake for Frenchtown Township (Net dilution factor of 67 from discharge point to a point documented in Fermi 2 UFSAR, Chapter 11, which is closer to the discharge point than this drinking water intake)
BFi = Bioaccumulation factor for radionuclide i in fish from Table 6.0-2 (pCi/kg per pCi/liter)
FERMI 2 ODCM - TRM VOLUME II 6-15 Rev. 13
DFi = dose conversion factor for nuclide i for adults in organ o from Table E-1 1 of Regulatory Guide 1.109 (mrem/pCi) 1.14 E + 05 =0(pCi /iCi)
~~103 (mi / kg) 8760 (hr I yr)~~
The radionuclides included in the periodic dose assessment required by ODCM 3.11.1.2 are those identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of ODCM Table 4.11.1.1.1-1. In keeping with the NUREG-0133 guidance, the adult age group represents the maximum exposed individual age group. Evaluation of doses for other age groups is not required for demonstrating compliance with the dose criteria of ODCM 3.11.1.2. The dose analysis for radionuclides requiring radiochemical analysis will be performed after receipt of results of the analysis of the composite samples. In keeping with the required analytical frequencies of ODCM Table 4.1 1.1.1.1 -1, tritium dose analyses will be performed at least monthly; Sr-89, Sr-90 and Fe-55 dose analyses will be performed at least quarterly.
6.5.2 Contaminated CWR System - Dose Calculation If the CWR System becomes contaminated, releases via the CWR System to Lake Erie must be included in the evaluation of the cumulative dose to a MEMBER OF THE PUBLIC as required by ODCM 3.11.1.2. ODCM Section 6.4 described the methods for quantifying and controlling releases from the CWR System.
For calculating the dose to a MEMBER OF THE PUBLIC, Equation (6-10) remains applicable for releases from the GSW System with the following assumptions:
- DF, Dilution Flow, is set equal to the average CWR decant line flow rate over the release period.
- Ci, Radionuclide Concentration, is determined as specified in ODCM Section 6.4.
- VOL, Volume Released, is set equal to the total volume of the discharges to Lake Erie via the CWR decant line as specified in Section 6.4.
FERMI 2 ODCM - TRM VOLUME II 6-16 Rev. 13
6.6 Liquid Effluent Dose Projections 10 CFR 50.36a requires licensees to maintain and operate the Radwaste System to ensure releases are maintained ALARA. This requirement is implemented through ODCM 3.11.1.3. This section requires that the Liquid Radioactive Waste Processing System be used to reduce the radioactive material levels in the liquid waste prior to release when the projected dose in any 31 day period would exceed:
- 0.06 mrem to the total body, or
- 0.2 mrem to any organ When the projected doses exceed either of the above limits, the waste must be processed by the Liquid Radwaste System prior to release. This dose criteria for processing is established at one forty eighth of the design objective rate (3 mrem/yr, total body or 10 mrem/yr any organ) in any 31 day period.
The applicable Liquid Waste Processing System for maintaining radioactive material releases ALARA is the Mixed Bed Demineralizers as delineated in Figure 6-1. Alternately, the Waste Evaporator (presented in the Fermi 2 UFSAR, Section 11.2) can be used to meet the NRC ALARA design requirements. It may be used in conjunction with or in lieu of the Mixed Bed Demineralizers to meet the waste processing requirements of ODCM 3.11.1.3.
Each BATCH release of liquid radwaste is evaluated to ensure that cumulative doses are maintained ALARA. In keeping with the requirements of ODCM 3.11.1.3, dose projections are made at least once per 31 days to evaluate the need for additional radwaste processing to ensure future releases are maintained ALARA.
The following equations may be used for the dose projection calculation:
D,,,, = D, (31 / d)
(6-14)
Dmax r = Dma, (31 / ad)
(6-15) where:
Dtbp = the total body dose projection for the next 31 day period (mrem)
NOTE: The reference calendar quarter is normally the current calendar quarter. If there have been liquid releases in the previous quarter but not in the current quarter, the previous quarter should be used as the reference calendar quarter.
Dtb = the cumulative total body dose for all releases to date in the reference calendar quarter (normally the current quarter) as determined by equation (6-10) or (6-12) (mrem)
FERMI 2 ODCM - TRM VOLUME II 6-17 Rev. 13
Dmaxp = the maximum organ dose projection for the next 31 day period (mrem)
Dmax = the cumulative maximum organ dose for all releases to date in the reference calendar quarter as determined by Equation (6-10) or (6-13) (mrem) d = the number of days from the beginning of the reference calendar quarter to the date of the dose projection evaluation.
31 = the number of days in projection FERMI 2 ODCM - TRM VOLUME 11 6-18 Rev. 13
TABLE 6.0-1 Fermi 2 Site Specific Liquid Ingestion Dose Commitment Factors Aio (mrem/hr per uCilml)
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 8.78E-1 8.78E-1 8.78E-1 8.78E-1 8.78E-1 8.78E-1 C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 Na-24 4.18E+2 4.18E+2 4.1 8E+2 4.18E+2 4.18E+2 4.18E+2 4.18E+2 P-32 1.39E+6 8.63E+4 5.36E+4 1.56E+5 Cr-51 1.29E+O 7.70E-1 2.84E-1 1.71 E+O 3.24E+2 Mn-54 4.40E+3 8.40E+2 1.31 E+3 1.35E+4 Mn-56 1.11E+2 1.97E+1 1.41 E+2 3.54E+3 Fe-55 6.75E+2 4.67E+2 1.09E+2 2.60E+2 2.68E+2 Fe-59 1.07E+3 2.51 E+3 9.60E+2 7.00E+2 8.35E+3 Co-57 2.20E+1 3.66E+1 5.59E+2 Co-58 9.38E+1 2.1 OE+2 1.90E+3 Co-60 2.69E+2 5.94E+2 5.06E+3 Ni-63 3.19E+4 2.21 E+3 1.07E+3 4.62E+2 Ni-65 1.30E+2 1.68E+1 7.69E+O 4.27E+2 Cu-64 1.05E+1 4.92E+O 2.64E+1 8.94E+2 Zn-65 2.32E+4 7.38E+4 3.34E+4 4.94E+4 4.65E+4 Zn-69 4.94E+1 9.44E+1 6.57E+O 6.14E+1 1.42E+1 Br-82 2.28E+3 2.62E+3
-83 4.07E+1 5.86E+1
.-;-84 5.27E+1 4.14E-4 Br-85 2.17E+O 1.01E-15 Rb-86 1.01 E+5 4.71 E+4 1.99E+4 Rb-88 2.90E+2 1.54E+2 4.01 E-9 Rb-89 1.92E+2 1.35E+2 1.12E-11 Sr-89 2.40E+4 6.90E+2 3.85E+3 Sr-90 5.91 E+5 1.45E+5 1.71 E+4 Sr-91 4.42E+2 1.79E+1 2.11E+3 Sr-92 1.68E+2 7.26E+O 3.32E+3 Y-90 6.36E-1 1.70E-2 6.74E+3 Y-91m 6.00E-3 2.33E-4 1.76E-2 Y-91 9.31 E+O 2.49E-1 5.13E+3 Y-92 5.58E-2 1.63E-3 9.78E+2 Y-93 1.77E-1 4.89E-3 5.62E+3 Zr-95 4.29E-1 1.38E-1 9.31 E-2 2.16E-1 5.50E+2 Zr-97 2.37E-2 4.78E-3 2.19E-3 7.22E-3 1.48E+3 Nb-95 4.47E+2 2.49E+2 1.34E+2 2.46E+2 1.51 E+6 Nb-97 3.75E+O 9.48E-1 3.46E-1 1.11E+O 3.50E+3 Mo-99 1.30E+2 2.47E+1 2.94E+2 3.01 E+2 Tc-99m 1.04E-2 2.94E-2 3.74E-1 4.46E-1 1.44E-2 1.74E+1 Tc-101 1.07E-2 1.54E-2 1.51 E-1 2.78E-1 7.88E-3 4.63E-14 FERMI 2 ODCM - TRM VOLUME II 6-19 Rev. 13
TABLE 6.0-1 Fermi 2 Site Specific Liquid Ingestion Dose Commitment Factors Aio (mrem/hr per uCilml)
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Ru-1 03 5.58E+O 2.40E+O 2.13E+1 6.512E+2 Ru-105 4.64E-1 1.83E-1 6.00E+O 2.84E+2 Ru-106 8.29E+1 1.05E+1 1.60E+2 5.37E+3 Rh-103m Rh-106 Ag- 1Om 1.87E+O 1.73E+O 1.03E+O 3.412+0 7.08E+2 Sb-1 24 2.41 E+1 4.56E-1 9.56E+O 5.84E-2 1.88E+1 6.84E+2 Sb-125 1.54E+1 1.72E-1 3.66E+O 1.57E-2 1.19E+1 1.70E+2 Te-125m 2.58E+3 9.36E+2 3.46E+2 7.77E+2 1.05E+4 1.03E+4 Te-127m 6.52E+3 2.33E+3 7.95E+2 1.67E+3 2.65E+4 2.19E+4 Te-127 1.06E+2 3.81 E+i 2.29E+1 7.86E+1 4.32E+2 8.37E+3 Te-1 29m 1.11E+4 4.13E+3 1.75E+3 3.81 E+3 4.63E+4 5.58E+4 Te-129 3.03E+1 1.14E+1 7.37E+O 2.32E+1 1.27E+2 2.28E+1 Te-131m 1.67E+3 8.15E+2 6.79E+2 1.29E+3 8.26E+3 8.10E+4 Te-131 1.90E+1 7.93E+O 5.99E+O 1.56E+1 8.32E+1 2.69E+O Te-132 2.43E+3 1.57E+3 1.47E+3 1.73E+3 1.51 E+4 7.43E+4 1-130 3.18E+1 9.39E+1 3.71 E+1 7.96E+3 1.47E+2 8.09E+1
'31 1.75E+2 2.51 E+2 1.44E+2 8.21 E+4 4.30E+2 6.61 E+1 132 8.55E+0 2.29E+ 1 8.OOE+O 8.00E+2 3.64E+1 4.30E+O I-133 5.98E+1 1.04E+2 3.17E+1 1.53E+4 1.82E+2 9.35E+1 1-134 4.46E+O 1.21E+1 4.34E+O 2.1 OE+2 1.93E+1 1.06E-2 1-135 1.87E+1 4.89E+1 1.81E+1 3.22E+3 7.83E+1 5.52E+1 Cs-134 2.98E+5 7.1 OE+5 5.80E+5 2.30E+5 7.62E+4 1.24E+4 Cs-136 3.12E+4 1.23E+5 8.87E+4 6.86E+4 9.40E+3 1.40E+4 Cs-137 3.82E+5 5.23E+5 3.42E+5 1.77E+5 5.90E+4 1.01 E+4 Cs-138 2.65E+2 5.23E+2 2.59E+2 3.84E+2 3.79E+1 2.23E-3 Ba-139 1.53E+O 1.09E-3 4.48E-2 1.02E-3 6.19E-4 2.72E+O Ba-140 3.20E+2 4.03E-1 2.10E+1 1.37E-1 2.30E-1 6.60E+2 Ba-141 7.44E-1 5.62E-4 2.51E-2 5.23E-4 3.19E-4 3.50E-10 Ba-142 3.36E-1 3.46E-4 2.12E-2 2.92E-4 1.96E-4 4.74E-19 La-140 1.65E-1 8.32E-2 2.23E-2 6.11E+3 La-142 8.46E-3 3.84E-3 9.58E-4 2.81 E+1 Ce-141 8.05E-2 5.45E-2 6.1 8E-3 2.53E-2 2.08E+2 Ce-143 1.42E-2 1.05E+1 1.16E-3 4.62E-3 3.92E+2 Ce-144 4.20E+0 1.76E+O 2.25E-1 1.04E-0 1.42E+3 Pr-143 6.08E-1 2.44E-1 3.01 E-2 1.41 E-1 2.66E+3 Pr-144 1.99E-3 8.26E-4 1.01 E-4 4.66E-4 2.86E-10 Nd-147 4.16E-1 4.80E-1 2.87E-2 2.81 E-1 2.31 E+3 W-187 2.97E+2 2.48E+2 8.67E+1 8.12E+4 Np-239 3.59E-2 3.53E-3 1.94E-3 1.10E-2 7.24E+2 FERMI 2 ODCM - TRM VOLUME 11 6-20 Rev. 13 I
TABLE 6.0-2 Bioaccumulation Factors (BFi)
(pCi/kg per pCilliter)*
Element Freshwater Fish H 9.OE-01 C 4.6E+03 Na 1.OE+02 P 3.OE+03 Cr 2.OE+02 Mn 4.OE+02 Fe 1.OE+02 Co 5.OE+01 Ni 1.OE+02 Cu 5.OE+01 Zn 2.OE+03 Br 4.2E+02 Rb 2.OE+03 Sr 3.OE+01 Y 2.5E+01 Zr 3.3E+00 Nb 3.OE+04 Mo 1.OE+01 Tc 1.5E+01 Ru 1.OE+01 Rh 1.OE+01 Ag 2.3E+00 Sb 1.OE+00 Te 4.OE+02 I 1.5E+01 Cs 2.OE+03 Ba 4.OE+00 La 2.5E+01 Ce 1.OE+00 Pr 2.5E+01 Nd 2.5E+01 W 1.2E+03
-Np 1.OE+01
~~Values in this table are taken from Regulatory Guide 1.109 except for phosphorus, which is adapted from NUREG/CR-1336, and silver and antimony, which are taken from UCRL 50564, Rev 1, October 1972.~~
FERMI 2 ODCM - TRM VOLUME II 6-21 Rev. 13
FIGURE 6.0-1 Liquid Radioactive Effluent Monitoring and Processing Diagram he olf W_
R-a^,
To.
1A.rf.i FERMI 2 ODCM - TRM VOLUME II 6-22 Rev. 13 l END OF SECTION 6.0
SECTION 7.0 GASEOUS EFFLUENTS FERMI 2 ODCM - TRM VOLUME II 7-1 Rev. 13
7.0 GASEOUS EFFLUENTS 7.1 Radiation Monitoring Instrumentation and Controls 7.1.1 Effluent Monitoring - Ventilation System Releases The gaseous effluent monitoring instrumentation required at Fermi 2 for controlling and monitoring radioactive effluents are specified in ODCM 3.3.7.12.
The monitoring of each identified gaseous effluent release point must include the following:
- Noble Gas Activity Monitor
- Iodine Sampler (sample cartridge containing charcoal or silver zeolite)
- Particulate Sampler (filter paper)
- Sampler Flow Rate Monitor Meeting these requirements, a total of six Eberline SPING Monitoring Systems are installed on the five gaseous release points (Onsite Storage Facility, Radwaste Building, Turbine Building, Reactor Building Exhaust Plenum, and Standby Gas Treatment System Division 1 and Division 2). The SPING Monitor outputs are recorded electronically in the SS-1 Control Terminal in the Main Control Room.
In general, a reading exceeding the High alarm setpoint of the SPING Monitors causes an alarm in the Control Room. Fermi 2 ODCM Table 3.3.7.12-1 identifies these alarm functions.
7.1.2 Main Condenser Offgas Monitoring ODCM Table 3.3.7.12-1 and Technical Requirements Manual Volume 1, section TR 3.3.12, specify monitoring requirements for the Offgas System at the 2.2 minute delay line. The following monitors are required:
- Hydrogen Monitor - used to ensure the hydrogen concentration in the Offgas Treatment System is maintained less than 4% by volume as required by Technical Requirements Manual Volume 1, section TRLCO 3.3.12.
- Noble Gas Activity Monitor - used to ensure the gross activity release rate is maintained within 340 millicuries per second after 30 minute decay as required by Technical Specification 3.7.5.
These two monitors perform safety functions. The Hydrogen Monitor monitors the potential explosive mixtures in the Offgas System. The Noble Gas Monitor monitors the release rate from the main condenser ensuring doses at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR 100 in the event this effluent is inadvertently discharged directly to the environment bypassing the Offgas Treatment System.
FERMI 2 ODCM - TRM VOLUME II 7-2 Rev. 15
7.1.3 Reactor Building Ventilation Monitors (Gulf Atomic)
The Gulf Atomic Monitors (D11-N408 and 410) on the Reactor Building Ventilation System provide on high radiation levels (above alarm setpoint) initiation of SGTS, isolation of drywell vent/purge, isolation of the RB and Control Center Ventilation Systems and initiation of Control Center recirculation mode ventilation. These monitors and functions are not required by Fermi 2 ODCM but are important in controlling containment venting/purging.
7.2 Sampling and Analysis of Gaseous Effluents The program for sampling and analysis of gaseous waste is prescribed in Fermi 2 ODCM Table 4.11.2.1.2-1. This table distinguishes two types of gaseous releases:
(1) containment PURGE, treated as BATCH releases, and .(2) discharges from the Reactor Building Exhaust Plenum (including Standby Gas Treatment System (SGTS) when operating), and other building ventilation exhausts, treated as CONTINUOUS releases.
7.2.1 Containment PURGE ODCM Table 4.11.2.1.2-1 requires that samples be collected and analyzed before each primary containment PURGE. Sampling and analysis is required within eight hours before starting a PURGE. ODCM Table 4.11.2.1.2-1 Footnote j and ODCM 4.11.2.8.2 also require that if the purging or venting is through the Reactor Building ventilation, rather than through SGTS, and if the primary containment radiation monitoring system is not FUNCTIONALLY CAPABLE or in alarm condition, sampling and analysis is required within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during venting or purging of the primary containment. The required analyses must include principal gamma emitters and, if a pre-vent or pre-purge sample, tritium.
For a planned containment-PURGE; the results of the samples and analyses may be used to establish the acceptable release rate and radiation monitor alarm setpoint in accordance with ODCM Sections 7.3 and 7.4. This evaluation may be necessary to ensure compliance with the dose rate limits of ODCM 3.11.2.1.
In practice, release flow rates are fairly constant and these calculations are necessary only if a threshold value of nuclide concentration in the primary containment atmosphere is reached. The alarm setpoints of the primary containment atmosphere monitor, the Reactor Building ventilation exhaust monitors, and the Reactor Building and SGTS SPING monitors are set to ensure that release routes are continuously monitored and controlled in accordance with 10 CFR 20 or limits specified in the ODCM.
FERMI 2 ODCM - TRM VOLUME II 7-3 Rev. 13
7.2.2 Ventilation System Releases ODCM Table 4.11.2.1.2-1 requires continuous samples of releases from the RB Exhaust Plenum, Standby Gas Treatment System, Radwaste Building, Turbine Building, and Onsite Storage Facility. The table specifies the following program:
- Once per week, analysis of an adsorbent sample of 1-131 and 1-133, plus analysis of a particulate sample for principal gamma emitters.
- Once per month, analysis of a composite particulate sample of all releases (by release point) that month for gross alpha activity.
- Once per quarter, analysis of a composite particulate sample of all releases that quarter for Sr-89 and Sr-90.
- Once per month, analysis of a grab sample for principal gamma emitters (noble gases and tritium).
ODCM Table 4.11.2.1.2-1 also requires continuous monitoring for noble gases.
This requirement is met by the SPING Monitors on each of the plant gaseous release points.
The ODCM requires more frequent sampling and analysis following reactor startup, shutdown, or change in thermal power exceeding 15% within one hour.
The ODCM allows an exception to this increased sampling schedule when the applicable SPING noble gas monitor has not increased more than a factor of three.
Grab samples of the Fuel Pool Ventilation Exhaust are required tritium analysis once per seven days whenever spent fuel is in the Spent Fuel Pool. Also, grab samples for tritium are required when either the reactor well or the dryer separator pool is filled. These samples are taken at the Reactor Building Exhaust Plenum and Standby Gas Treatment System (SGTS) when operating.
FERMI 2 ODCM - TRM VOLUME II 7-4 Rev. 14
7.3 Gaseous Effluent Monitor Setpoint Determination 7 3.1 Ventilation System Monitors Per the requirements of ODCM 3.3.7.12, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of ODCM 3.11.2.1. This section limits releases to a dose rate at the SITE BOUNDARY of 500 mrem/year to the total body or 3000 mrem/year to the skin. From a grab sample analysis of the applicable release (i.e., grab sample of the primary containment or Ventilation System release), the radiation monitoring alarm setpoints may be established by the following calculational method. The measured radionuclide concentrations and release rate are used to calculate the fraction of the allowable release rate, limited by ODCM 3.11.2.1, by the equation:
1.67E+01*z/Q*VF*Z(C,*K,)
FRAC =
500 (7-1)
F4C 1.67 E +01* X IQ* VF*E(cj*[Lj+'-lm,])-
FRAC= QZ'iI 3000 (7-2)
Where:
FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate X/Q= annual average meteorological dispersion to the controlling site boundary location from Table 7.0-3 (seclm 3 ) or plant procedures VF = Ventilation System flow rate for the applicable release point and monitor (liters/minute)
Ci = concentration of noble gas radionuclide i at release point as determined by gamma spectral analysis of grab sample (pCi/cc).
Ki = total body dose conversion factor for noble gas radionuclide i (mrem/yr per pCi/m3, from Table 7.0-2)
Li = beta skin dose conversion factor for noble gas radionuclide i (mrem/yr per pCi/m3 , from Table 7.0-2)
FERMI 2 ODCM - TRM VOLUME II 7-5 Rev. 13
Mi = gamma air dose conversion factor for noble gas radionuclide i (mrad/yr per pCi/M 3, from Table 7.0-2) 1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad) 500 = total body dose rate limit (mrem/yr) 3000 = skin dose rate limit (mrem/yr) 1.67 E + 01 = 1 E + 03 (cc/liter) * (1/60) (min/sec)
Based on the more limiting (i.e., higher) value of FRAC as determined above, the alarm setpoints for the applicable monitors may be calculated by the equation:
(AF* Zci)
SP < +Bkg (7-3)
Where:
SP = alarm setpoint corresponding to the maximum allowable release rate (pCi/cc)
Bkg = background of the monitor (pCi/cc)
AF = administrative allocation factor (Table 7.0-1) for the specific monitor and type release, which corresponds to the fraction of the total allowable release rate that is administratively allocated to the individual release points.
Ci = -concentration of Noble Gas Radionuclide i as determined by gamma spectral analysis of grab sample (pCi/cc). Note: If the monitor channel in question was showing a response to the effluent at the time of the grab sample, this response minus background may be used in lieu of the summed grab sample concentrations.
FERMI 2 ODCM - TRM VOLUME II 7-6 Rev. 13
The Allocation Factor (AF) is an administrative control imposed to ensure that combined releases from all release points at Fermi 2 will not exceed the regulatory limits on release rate from the site (i.e., the release rate limits of ODCM 3.11.2.1). From the Fermi 2 design evaluation of gaseous effluents presented in the UFSAR Section 11.3, representative values have been determined for AF. These values are presented in Table 7.0-1. These values may be changed in the future as warranted by operational experience, provided the site releases comply with ODCM 3.11.2.1. In addition to the allocation factor, safety factors which have the effect of lowering the calculated setpoints may be applied. When determining the Noble Gas Monitor calibration constant, the monitor sensitivity for Xe-1 33 may be used in lieu of the sensitivity values for the individual radionuclides. Because of its lower gamma energy and corresponding monitor response, the Xe-1 33 sensitivity provides a conservative value for alarm setpoint determination. Alternatively, if the monitor channel in question frequently shows a response to a mix of isotopes whose concentrations can be determined, the calibration constant may be determined from this type of data without reference to primary calibration data.
7.3.2 Setpoint Determination with No Nuclides Detected When noble gas concentrations for a release point cannot be determined from grab samples, there are two options for setpoint determination. First, the setpoint may be set slightly above monitor background (e.g. 2 to 3 times background). This approach may be used when releases are not expected from a particular release point. Second, the equations of Section 7.3.1 may be used with noble gas concentration values based either on UFSAR tables or on values from a release point for which concentrations have been determined (e.g. reactor building exhaust plenum). When this method is used, a safety factor should be used in the setpoint calculation.
7.3.3 Gaseous Effluent Alarm Response - Evaluating Actual Release Conditions The monitor alarm setpoint is'used as the primary method for ensuring and demonstrating compliance with the release rate limits of ODCM 3.11.2.1. Not exceeding alarm setpoints constitutes a demonstration that release rates have been maintained within the ODCM limits. When an'effluent Noble Gas Monitor exceeds the alarm setpoint, an evaluation of compliance with the release rate limits must be performed using actual release conditions. This evaluation requires collecting a sample of the effluent to establish actual radionuclide concentrations and permit evaluating the monitor response. The following equations may be used for evaluating compliance with the release rate limit of ODCM 3.11.2.1a:
D,, = 1.67E+O1*z/Q* VF*Z(K,*CC)
(7-4)
= 1.67E+01
~~XI Q* VF* Z([Lj+1.1Mj]* Cj)~~
(7-5)
FERMI 2 ODCM - TRM VOLUME II 7-7 Rev. 13
Where:
Dtb = total body dose rate (mrem/yr)
Ds = skin dose rate (mrem/yr)
X/ O = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m 3 )
VF = Ventilation System release rate (liters/min)
Ci = concentration of radionuclide i as measured in the grab sample or as correlated from the SPING Noble Gas Monitor reading (pCi/cc)
Kg= total body dose conversion factor for noble gas radionuclide i (mrem/yr per pCi/m 3, from Table 7.0-2)
Li = beta skin dose conversion factor for noble gas radionuclide i (mrem/yr per pCi/m 3, from Table 7.0-2)
Mi = gamma air dose conversion factor for noble gas radionuclide i (mrad/yr per pCi/m 3, from Table 7.0-2) 1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad) 1.67 E + 01 = 1 E + 03 (cc/liter) * (1/60) (min/sec)
The above equations may also be used to verify compliance with ODCM 3.11.2.1.a when noble gases are detected in periodic (e.g. monthly) effluent noble gas samples.
7.4 Primary Containment VENTING and PURGING 7.4.1 Release Rate Evaluation For primary containment VENTING or PURGING, an evaluation of acceptable release rate may be performed prior to the release. Based on the measured noble gas concentration in the grab sample collected per the requirements of ODCM Table 4.11.2.1.2-1, the allowable release rate from primary containment can be calculated by the following equation:
FERMI 2 ODCM - TRM VOLUME II 7-8 Rev. 13
500 *AF 1.67+01 */Q* (K*
~~C,)~~
~~(7-6) or 3000 *AF 1.67E +01*/Q* ( [L + L.IJ~~
~~C;)~~
(7-7)
Where:
RRtb = allowable release rate so as not to exceed a dose rate of 500 mrem/yr, total body (liters/minute)
RRs = allowable release rate so as not to exceed a dose rate of 3000 mrem/yr,,skin (liters/minute)
AF = allocation factor for the applicable release point from Table 7.0-1 (default value is 0.5 for Reactor Building Exhaust Plenum) 500 = total body dose rate limit (mrem/yr) 3000 = skin dose rate limit (mrem/yr)
The lesser value (RRtb or RRs) as calculated above may be used for establishing the allowable release rate for primary containment PURGING or VENTING, taking into account the fraction of the allocated release limit already accounted for by continuous releases from the proposed release point. As discussed in section 7.2.1, this evaluation is rarely necessary.
7.4.2 Alarm Setpoint Evaluation For a primary containment VENTING or PURGING, a re-evaluation of the alarm setpoint may be needed to ensure compliance with the requirements of ODCM 3.3.7.12. For the identified release path (RB Exhaust Plenu'm or SGTS) and associated effluent Radiation Monitor, the alarm setpoint should be calculated using Equations (7-1), (7-2) and (7-3). In Equations (7-1) and (7-2),
the value of the Ventilation Flow VF should be established at the total release flow rate, including the contribution from the PURGE or VENT. If the calculated alarm setpoint is greater than the current setpoint, no adjustments are necessary. As discussed in section 7.2.1, this setpoint evaluation is rarely necessary.
FERMI 2 ODCM - TRM VOLUME II 7-9 Rev. 13
7.5 Quantifying Releases - Noble Gases The determination of doses in the environment from releases is dependent on the mixture of the radioactive material. Also, NRC Regulatory Guide 1.21 requires reporting of individual radionuclides released in gaseous effluents. Therefore, Detroit Edison must determine the quantities of the individual radionuclides released. For noble gases, these quantities must be based on actual noble gas grab samples.
7.5.1 Sampling Protocol As required by ODCM 3.11.2.1, a gas sample is collected at least monthly from each of the five gaseous release points (Reactor Building Exhaust Plenum, Standby Gas Treatment System, Radwaste Building, Turbine Building, and Onsite Storage Facility). As discussed in ODCM Section 7.2.2, this gas sample is analyzed by gamma spectroscopy to identify individual radionuclides (noble gases). Noble gases have been detected almost exclusively in the reactor
.building effluent.
For containment purges and containment ventings when monitoring is alarming or not FUNCTIONALLY CAPABLE, samples are collected prior to the initiation of the release and, for long releases, periodically throughout the release (see ODCM Section 7.2.1). When detected activity concentrations are above a pre-determined threshold, these samples are evaluated using Equations (7-4) and (7-5), using release rates applicable to the vent/purge condition and taking continuous releases into account, to ensure that the site boundary dose rate limits of ODCM 3.11.2.1 are not exceeded. If the primary containment atmosphere has equilibrated with the reactor building atmosphere, vent/purge sampling and analysis is not required. Such equilibrium with the drywell atmosphere may be considered to be established after at least one of the drywell equipment hatches has been open for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and equilibrium with the torus atmosphere may be assumed after at least one torus hatch has been open for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .
As required by ODCM Table 4.11.2.1.2-1, special samples are required of the RB Exhaust Plenum and SGTS following shutdown, startup or a THERMAL POWER change exceeding 15% within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period. Exceptions to this special sampling are allowed as noted previously in ODCM Section 7.2.2.
FERIVII 2 ODCM - TRM VOLUME 1i 7-10 Rev. 13
7.6 Calculation of Activity Released The following equation may be used for determining the release quantities from any release point based on the sample analysis:
Qi= 1.OE+03* VF* T*Ci (7-8)
Where:
Qi = total activity released of radionuclide i (pCi)
VF = Ventilation System release rate (liters/min)
T total time of release period (min) 1.0 E + 03 = milliliters per liter C: = concentration of radionuclide i as determined by analysis of the sample (pCi/cc). For noble gas grab samples, this value may be corrected for variations during the release period by multiplying by the ratio of the average noble gas monitor reading during the release period to the reading at the time the sample was taken.
For iodine and particulate samples, this value should be corrected for decay during the sampling period, for sample line loss if adequate data are available, and for collection efficiency if a significant fraction of the material to be collected passes through the collection media. For all samples, this value should be corrected for decay between sample collection and counting and for decay during counting.
7.7 Site Boundary Dose Rate - Radioiodine and Particulates ODCM 3.11.2.1.b limits the dose rate to <1500 mrem/yrto any organ for 1-131, 1-133, tritium and particulates with half lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (nominally once per 7 days). The following equation may be used in the dose rate evaluation for 1-131, 1-133, and particulates with half lives greater than 8 days:
DR = (x/ *RI 13'VF, *16.7 ci)
(7-9)
Where:
FERMI 2 ODCM - TRM VOLUME 11 7-11 Rev. 13
DR = total maximum organ dose rate for all release points (mrem/yr)
X/ Q. = atmospheric dispersion factor for release point r to the controlling SITE BOUNDARY location (sec/m 3 ) from Table 7-3 or plant procedures R.13,= 1-131 child thyroid inhalation pathway dose factor (mrem/yr per pCi/m 3 )
from Table 7-4 VFr = Average ventilation flow for release point r during release period (liters/min)
Cir = Concentration of radionuclide i (1-131, 1-133, or particulate with half life greater than 8 days) released from release point r during the appropriate release period (pCi/cc)--usually determined by gamma spectral analysis of effluent sample and corrected as described in definition of C,in section 7.6 16.7 = 1000 cc/liter
~~0.0167 min/sec Release periods used in Equation (7-9) are the most recent periods evaluated for the different release points, and these periods may not be identical.~~
Alternatively, the site boundary dose rate may be evaluated using the highest individual isotopic dose factors for all age groups to calculate inhalation and ground plane exposure at the highest dispersion factor location at or beyond the site boundary, as well as vegetation, milk, and meat exposure at the garden, milk, and meat locations with the highest deposition factors. Dose rate due to tritium is currently evaluated by this method, and when tritium has been detected in gaseous effluents during the most recent release period, the tritium dose rate must be added to the result from Equation (7-9) to evaluate compliance with ODCM 3.11.2.1.b.
The dose rate evaluation described above may have to be performed more frequently than once per week in order to meet the requirements of ODCM Table 4.11.2.1.2-1, footnote g: Daily sampling is required f6llowing startup, shutdown, or thermal power changes exceeding 15% in one hour if the applicable noble gas effluent monitor reading has increased by a factor of 3.
FERMI 2 ODCM - TRM VOLUME II 7-12 Rev. 14
7.8 Noble Gas Effluent Dose Calculations -10 CFR 50 7.8.1 UNRESTRICTED AREA Dose - Noble Gases ODCM 4.11.2.2 requires that an assessment of releases of noble gases be performed at least once per 31 days to evaluate compliance with the quarterly dose limits of 5 mrad, gamma-air and 10 mrad, beta-air and the calendar year limits 10 mrad, gamma-air and 20 mrad, beta-air. The following equations may be used to calculate the gamma-air and beta-air doses. If noble gases are detected at multiple release points, these equations must be performed for each such release point, and the calculated air doses must be summed.
D7 = 3.17E-08*X/Q* (Mv*i Q)
(7-10) and D = 3.17E-08*I/Q (Nj *) l (7-11)
Where:
Dy = air dose due to gamma emissions for noble gas radionuclides (mrad)
D= air dose due to beta emissions for noble gas radionuclides (mrad)
X' / Q = -atmospheric dispersion to the controlling SITE BOUNDARY location (sec/M 3)
Q = cumulative release of noble gas radionuclide i over the period of interest (pCi)
M = air dose factor due to gamma emissions from noble gas radionuclide l (mrad/yr per pCi/M 3 , from Table 7.0-2)
Ni = air dose factor due to beta emissions from noble gas radionuclide i (mrad/yr per pCi/M 3, Table 7.0-2) 3.17 E - 08 = 1/3.15 E + 07 (year/sec)
FERMI 2 ODCM - TRM VOLUME II 7-13 R ev. 14
7.9 Radioiodine and Particulate Dose Calculations -10 CFR 50 7.9.1 UNRESTRICTED AREA Dose - Radioiodine, Particulates, and Tritium In accordance with requirements of ODCM 4.11.2.3, a periodic assessment (at least once per 31 days) is required to evaluate compliance with the quarterly dose limit of 7.5 mrem and the calendar year limit of 15 mrem to any organ. The following equation may be used to evaluate the maximum organ dose due to releases of 1-131, 1-133, tritium, and particulates with half-lives greater than 8 days:
D,,,=E (,
SF
~~3.17E-8~~
~~R,,,,,~~
~~QJ)~~
P.,
(7-14)
Where:
Dao dose or dose commitment to Organ o of age group a (identified in Table 7.0-3 or plant procedures)
Wr atmospheric dispersion parameter for release point r and the residence location identified in Table 7.0-3 or plant procedures.
Either:
a) X/Q, atmospheric dispersion for inhalation pathway and H-3 and C-14 dose contribution via other pathways (sec/m 3 ), or b) DIQ, atmospheric deposition for vegetation, milk and ground plane exposure pathways (m-2 )
Raipo = dose factor (mrem/yr per. pCi/m 3 ) or (m2 - mrem/yr per pCi/sec) from Table 7.0-4 for radionuclide i, age group a, pathway p, and organ o as identified in Table 7.0-3 or plant procedures. Values for Raipo were derived in accordance with the methods described in NUREG-0133 As noted in NUREG-0133 section 5.3.1.3, in the case that the milk animal is a goat, parameter values from Reg Guide 1.109 should be used. For 1-131, for example, use of the goat feed/forage consumption rate given in Table E-3 and the stable element transfer factor given in Table E-2 of Reg Guide 1.109 results in grass-goat-milk dose factors which are equivalent to the grass-cow-milk dose factors in Table 7.0-4 multiplied by 1.2.
FERMI 2 ODCM - TRM VOLUME II 7-14 Rev. 14
Qir = cumulative release from release point r over the period of interest (normally one month) for radionuclide i -- 1-131, 1-133, tritium or radioactive material in particulate form with half-life greater than 8 days (pCi).
SFp = annual seasonal correction factor to account for the fraction of the year that the applicable exposure pathway does not exist:
~~1) For milk and vegetation exposure pathways:~~
~~= 0.5 (derived from Reg Guide 1.109, Rev 1. A six month fresh vegetation and grazing season (May through October) limits exposure through this pathway to half the year.~~
~~2) For inhalation and ground plane exposure pathways:~~
= 1.0 (derived from Reg Guide 1.109, Rev 1) 3.17 E-8 = 1 /3.15 E7 (year/sec)
This equation should be used to evaluate organ doses for the individual with the highest potential offsite dose. This calculation is performed monthly and is added to previous results for the quarter and year. The highest quarterly and annual cumulative organ dose totals for this individual should be compared with the limits of ODCM 3.11.2.3.
The residence, age group, and relevant exposure pathways for this individual are listed in Table 7.0-3 and in plant procedures. Plant procedures may provide updated information which differs from Table 7.0-3. This individual is identified
~~from data obtained in the annual Land Use Census (ODCM 3.12.2).~~
FERMI 2 C)DCM - TRM VOLUME II 7-15 Rev. 13
7.10 Gaseous Effluent Dose Projection As with liquid effluents, the Fermi 2 ODCM controls on gaseous effluents require "processing" of gaseous effluents if the projected dose exceeds specified limits. These controls implement the requirements of 10 CFR 50.36a on maintaining and using the appropriate radwaste processing equipment to keep releases ALARA.
ODCM 3.11.2.5 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when the projected dose exceeds 0.3 mrem to any organ in any 31 day period (i.e., one-quarter of the design objective rate). Figure 7.0-1 presents the gaseous effluent release points and the VENTILATION EXHAUST TREATMENT SYSTEMS applicable for reducing effluents prior to release.
Dose projection is performed at least once per 31 days using the following equation:
Dmax, = Dmac * (31 / d)
(7-16)
Where:
Dmaxp = maximum organ dose projection for the next 31 day period (mrem)
NOTE: The reference calendar quarter is normally the current calendar quarter. If the dose projection is done in the first month of the quarter and is to be based on dose calculated for the previous quarter, the reference calendar quarter is the previous quarter.
Dmax = the cumulative maximum organ dose from the beginning of the reference calendar quarter (normally the current quarter) to the end of the most recently evaluated release period as determined by Equation (7-14) or (7-15) (mrem) d = number of days from the beginning of the reference calendar quarter to the end of the most recently evaluated release period.
31 = number of days in projection FERMI 2 ODCM - TRM VOLUME II 7-16 Rev. 13 I
TABLE 7.0-1 Values for Evaluating Gaseous Release Rates and Alarm Setpoints Allocation Allocated Dose Release Point Flow Rate Factor Rate Limit (literlmin) (AF) (mremlyear)
Reactor Building 2.67E6 0.50 T Body = 250 Exhaust Plenum Skin = 1500 D11-P280 Organ = 750 Standby Gas 1.07E5 0.10 T Body= 50 Treatment System Skin = 300 Div I D11-P275 Organ = 150 Standby Gas 1.12E5 0.10 T Body= 50 Treatment System Skin = 300 Div II D11 -P276 Organ = 150 Turbine Building 8.67E6 0.20 T Body = 100 Ventilation Skin = 600 D11-P279 Organ = 300 Radwaste Building 1.13E6 0.02 T Body = 10 Ventilation Skin = 60 D11-P281 Organ = 30 Onsite Storage 3.06E5 0.02 T Body= 10 Building Skin = 60 Ventilation Organ = 30 D11-P281 Reactor Building 2.57E6 0.50 T Body = 125 Ventilation' Skin =750 Gulf Atomic Organ = 375 I Monitors D11-N408, N410 D D1-N408 and N410 will start the SGTS, close the Drywell PurgeNent Valves, isolate Rx Building Ventilation System, isolate Control Center, and initiate emergency recirculation mode.
FERMI 2 ODCM - TRM VOLUME II 7-17 Rev. 13
TABLE 7.0-2 Dose Factors for Noble Gases*
Total Body Skin Gamma Air Beta Air Gamma Dose Beta Dose Dose Factor Dose Factor Nuclide Factor Ki Factor Li Mi Ni (mremlyr per (mrem/yr per (mrad/yr per (mrad/yr per PCi/m 3) PCi/m 3 ) pCi/m 3 ) IJCi/m 3 )
Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-1 33m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-1 33 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xe-1 35 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-1 37 1.42E+03 1.22E+04 1.51 E+03 1.27E+04 Xe-1 38 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 NOTE:
~~Dose factors taken from NRC Regulatory Guide 1.109 FERMI 2 ODCM - TRM VOLUME II 7-18 Rev. 13 l~~
TABLE 7.0-3 Controlling Locations, Pathways, and Atmospheric Dispersion for Dose Calculations*
ODCM Control Location Pathway(s) Controlling Age Group X/Q D/Q 2
(seclm 3 ) (1um )
3.11.2.1a site boundary noble gases N/A RB: 1.25E-6 N/A (0.57 mi, NW) direct exposure TB: 5.71 E-6 RW: 2.66E-6 3.11.2.1b site boundary inhalation child RB: 1.25E-6 N/A (0.57 mi, NW) TB: 5.71 E-6 RW: 2.66E-6 3.11.2.2 site boundary gamma-air .N/A RB, 1.25E-6 N/A (0.57 mi, NW) beta-air TB: 5.71 E-6 RW: 2.66E-6 11.2.3 residence vegetation child RB: 1.10E-6 1.59E-8 (0.67 mi, inhalation, and TB: 4.02E-6 3.06E-8 WNW) ground plane RW: 1.53E-6 1.76E-8
. NOTE: *The identified controlling locations and pathways are derived from land use census data and dispersion and deposition factor data tables. The dispersion and deposition factor values listed are conservative values; they represent the highest .
annual average values seen at that location for a period of several years.
'I FERMI 2 ODCM - TRM VOLUME II 7-19 Rev. 13
Table 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors Raipo, Inhalation Pathway Dose Factors - ADULT (mrem/yr per p Cilm 3 )
Nuclide Bone Liver Thyroid Kidney Luns Cl-LLI T.Sody H-3 - 1.26E.3 t.26E+3 1.26E+3 1.26E.3 1.26E-3 1.26E.3 C- 14 1.82E-4 3.41E+3 3.4iE43 3.4 E-3 3.41E-3 3.4tE-3 3.41E-3 Na-24 t.O2E-4 1.02E*4 1.02E#4 1.02E-4 1.02E-4 1.C2E-4 1.02E*A P-32 1.32EL6 7.71Ev4 - - - B.64Et4 S.01Ev4 Cr-51 - - 5.95E-1 2.28E+1 1.44E#. 3.32E+3 1.001E2 Hn-5, - 3.96E-4 - 9.84E-3 1.40E+6 7.74E-4 6.30E+3 Kn-56 - 1.24E10 - 1.30E+0 9.44E.3 2.02E-4 t.83E-1 Fe-SS 2.'bE-4 1.70E-4 - - 7.21E-4 6.03E-3 3.94E.3 Fe-59 1.18E,4 2.78Ev4 - - 1.02E-6 I.SSE.S 1.06Ev' Co-57 - 6.92E12 - - 3.70E+5 3.14E+4 6.71Ev2 Co-S8 - 1.58E13 - - 9.28E+S 1.06E-S 2.07L+3 Co-60 - t.ISEv4 - - 5.97E+6 2.85E-S 1.4SEv4 Ni-63 4.32E.S 3.14E.4 - - 1.78E.S 1.34Ev4 1.45E+4 Ni-65 t.54E-0 2.tOE-1 - - S.60E-3 1.23E+4 9.12E-2 Cu-64 - 1.461>0 - 4.62E#0 6.78E+3 4.90E-4 6.15E-1 Zn-65 3.24E.4 1.03E1S - 6.90E-4 8.6&E.5 5.34E-4 4.66E-4 Zn-69 3.38E-2 6.51E-2 - 4.22E-2 9.20E12 1.63E11 4.52E-3 Br-82 - - - - - 1.04E+4 1.35E+4 Br-83 - - - - - 2.32E12 2.41iE2 8r-84 - - - - - 1.64E-3 3.13E#2 Br-85 - - - - - - 1.28E51 Rb-86 - 35E-5 -
-. 1.66E44 5.90E-4 Rb-8 - 3.87E5 2 - - - 3.34E-9 1.93E-2 Rb-89 - 2.56E#2 - - - - 1.70E12 Sr-89 3.04E.5 - - - 1.0E.6 3.50E-S 8.72E-3 Sr-90 9.92E+7 - - - 9.60E+6 7.22E+S 6.101E6 Sr-91 6.19E+1 - - 1.65E-4 1.91E+S 2.50E-0 Sr-92 6.74E*0 - - - 1.65E14 4.30E-4 2.91E-1 Y-90 2.09E-3 - - - 1.70E-S 5.06E#S 5.61E+1 Y-91m 2.61E-1 - - - 1.92E-3 1.33E+0 1.02E-2 Y-91 4.62E+5 - - - 1.70E*6 3.85ES 1.24E-4 Y-92 1.03E+1 - - - 1.57E-4 7.35E.4 3.02E-1 Y-93 9.44E+1 - - - 4.85E-4 4.22E+S 2.61E'O Zr-95 1.07E+5 3.44E.4 - 5.42E+4 1.77E-6 1.50E+S 2.33E+4 Zr-97 9.68E-1 1.96E11 - 2.97E11 7.87E14 5.23E*S 9.04E.O Nb-95 1.41E.4 7.82E+3 - 7.74E+3 S.05E+S 1.04E#S *.21E-3 Nb-97 2.22E-t 5.62E-2 - 6.54E-2 2.40E-3 2.42E12 2.05E-2 Ho-99 - 1.21E*2 - 2.91E.2 9.12E-4 2.48E-5 2.30E-1 TC 1.03E-3 2.91E-3 - 4.42E-2 7.64E12 4.16E+3 3.70E-2 Tc-101 4.18E-5 6.02E-S 1.08E-3 3.99E+2 - 5.90E-4 Ru-103 1.53E-3 - - 5.83E13 S.O5E-S 1.10E1S 6.58E*2 Ru-105 7.90E-1 - - 1.02E-0 1.10E14 4.82E.4 3.11E-I Ru-106 6.91E.4 - - 1.34E5 9.36E+6 9.12E*S 8.72E13 Rh-103. - - _ _ _
Rh-tO6 - - _ _ _ _ _
Ag-110. 1.08E.4 1.00E.4 - 1.97E'4 4.63E+6 3.02E+S 5.94E&3 Sb-124 3.12t.4 5.89E12 7.SSIE1 - 2.481E6 4.06E1S 1.24E14 Sb-125 5.34E-4 5.95E+2 5.40E.1 - 1.74E.6 1.01E*S 1.26E14 Te-i25. 3.42E*3 1.58E*3 t.OSEt3 1.24E+4 3.14E.S 7.06E+4 4.67E12 Te-127a 1.26E+4 5.77E+3 3.29E13 4.58E+4 9.60E1S I.SOE50 1.57E13 Te-127 1.40E-0 6.42E-1 1.06E+0 S.IOE.O 6.5tE-3 S.74E+4 3.10E-1 Te-129a 9.76E+3 4.67E#3 3.44E.3 3.66E+4 1.16E+6 3.83E+S l.SSE#3 Te-129 4.981E-2 2.39E-2 3.90E-2 1.87E-1 1.94E13 1.57E+2 1.24E-2 7e-l3i. 6.99E*1 4.36E-t S.501E1 3.09E12 1.4CES% 5.56E5 2.90E-1 Te-131 1.11E-2 5.95E-3 9.36E-3 4.37E-2 1.39E*3 1.84E1. 3.59E-3 Te-t32 2.60E12 2.1SE.2 1.90E12 1.46E.3 2.8SE.5 5.10E*5 1.62E+2 1-130 4.58E*3 1.34E.4 1.14E5b 2.09E4 - 7.69E-3 5.28E53 I-t31 2.52E14 3.58.E#4 1.19E+7 6.13E1A - 6.28E*3 2.051E4 I-t32 i.16E13 3.26E.3 1.14E#S 5.18E53 - 4.06E+2 1.16E-3 1-133 8.64E-3 1.48E14 2.15Eo6 2.581.4 - 8.88E+3 4.52E13 FERMI 2 ODCM - TRM VOLUME II 7-20 Rev. 13
Table 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors Raipo, Inhalation Pathway Dose Factors - ADULT (cont.)
3 (mrem/yr per ,1Ci/m )
Nuclidt lgne Lbver Thyraid Kidney Luna C-L-UI .. ody 1-13& 6.44E.2 1.73E.3 2.98E+4 2.7SE.3 1.01E+0 6.15E.2 1-135 2.68E+3 6.98E.3 4.48E.S 1.IIE.4 - 5.25E-3 2.57E-3 Ca-134 3.73EeS 8.48E.5 - 2.87E+5 9.76E.4 i.04E.4 7.28Et5 Cs-136 3.90E-4 1.46E-5 - 8.56E.4 1.20E.4 1.17E.4 1.IOE.S Cr-137 4.78E.S 6.21ES5 - 2.22E.5 7.52E.4 B.40E.3 4.28Et5 Cs-138 3.31E-2 6.21E.2 - 4.80E*2 4.86E.1 1.86E-3 3.24E*2 ga-139 9.36E-1 6.66E-4 - 6.22E-4 3.76E-3 8.96E.2 2.74E-2 la-14O 3.90Et4 4.90E.1 - 1.67E#1 1.'7E+6 2.IBE+S 2.S7E.3 Ba-lU l.OOE-l 7.53E-5 - 7.00E-5 1.94E.3 1.16E-7 3.36E-3 la-142 2.63E-2 2.70E-5 - 2.29E-5 1.19E-3 - 1.66E-3 La-140 3.44E#2 1.74E.2 - - 1.36E5 A.S8E+5 4.58E+1 L-142 6.83E-1 3.10E-1 - - 6.33E.3 2.11E*3 7.72E-2 Ce-141 1.99E*4 1.3SE-4 6.26Et3 3.62Et5 1.20E#5 1.53E-3 Ce-143 1.86E.2 1.38E.2 6.08E1 7.98E.4 2.26E-S 1.53E-1 Cc-144 3.43E+6 1.43E.6 - 8.48E.5 7.78E+6 8.16E5 1.84E.5 Pr-143 9.36E.3 3.75E.3 - 2.16E+3 2.81E.S 2.OOE.5 4.64E.2 Pr-144 3.01E-2 1.25E-2 - 7.OSE-3 1.02E-3 2.1SE-8 1.53E-3 Nd-147 5.27E.3 6.10E.3 - 3.56E+3 2.21E-S 1.73E*S 3.65E12 W-187 8.48E.0 7.08E.0 - - 2.90Ee4 I.SSE.S 2.48E+O Np-239 2.30E.2 2.26E-1 - 7.00E.1 3.76E.4 1.19E+5 1.24E+1 FERMI 2 ODCM - TRM VOLUME II 7-21 Rev. 13
Table 7.0-4 Raipo Inhalation Pathway Dose Factors - TEENAGER (mrem/yr per pCi/m;)
Nuclide gone Liver Thyroid Kidney Luns CI-LLl T.Body H-3 - 1.27E+3 1.27E+3 1.27E+3 1.27E-3 1.27E+3 1.27E-3 C-14 2.60E.4 4.B71+3 4.87E+3 &.87E+3 4.B7E-3 4.87E-3 4.87E+3 Na-24 1.38E-4 1.38E.4 1.38E.4 1.38E+' 1.38E-4 1.38E-4 1.38E.4 P-32 1.89E*6 l.lOE+S - - - 9.28E-4 7.16E-4 Cr-S1 - - 7.5OE!1 3.07E+1 2.10E-4 3.OO!E3 1.35E-2 mn-S5 _ 5.11E-4' - 1.27E!. 1.98E-6 6.6!E.4 8.40E!3 Hn-56 - 1.70E-O - 1.79E.0 1.52E-4 5.74E-4 2.52E-1 Fe-SS 3.34E-4 2.38E.4 - - 1.24E*S 6.39E-3 5.54E.3 Fe-59 1.59E.4 3.70E.4 - - 1.S53E6 1.78ES 1.43E-4 Co-57 - 6.92E.2 - - S.86E-S 3.14E-4 9.20E#2 Co-58 - 2.07E-3 - - 1.34E+6 9.52E+4 2.78E-3 Co-60 - l.SlE-4 - - 8.72E!6 2.59E-S 1.98E.'
Ni-63 5.BOE#S 4.34E!4 - - 3.07E+S 1.42E.4 1.98E.4 Ni-65 2.1tE+0 2.93E-1 - - 9.36E+3 3.67E+4 1.27E-I Cu-64 - 2.03E*O - 6.41E-0 1.11E+4 6.14E-4 9.48E-1 Zn-65 3.86E.4 1.34E+S - 8.64E-4 1.24E!6 4.66E-4 6.24E!4 Zn-69 4.S3E-2 9.20E-2 - 6.02E-2 1.S8E-3 2.85E.2 6.46E-3 Br-82 _ - _ - 1.92E!4 Br-83 - 3.44E.2 Br-84 -- 4..33E#2 8r-8S - - - - 1.83E:I Rb-S6 - 1.90E#S - - - 1.77E.4 8.40E+4 Rb-88 - 5.46E+2 - - - 2.92E-5 2.72E.2 Rb-89 - 3.52E+2 - - - 3.38E-7 2.33E#2 Sr-89 *.34EES - - - 2.42E.6 3.71E+S 1.25E+!
Sr-90 1.O8E.8 - - - 1.65E-7 7.65E+S 6.68E!b Sr-91 8.BOE!1 - - - 6.07E.4 2.S9E.5 3.51E.C Sr-92 9.52E+O - - - 2.74E!4 1.19E+5 4.06E-1 Y-90 2.9SE-3 - - - 2.93E!S S.59E#S S.O0E-1 Y 3.70E-1 - - - 3.20oE3 3.02E.1 1.42E-2 Y-91 6.61E-5 - - - 2.94E+6 *..09E-S 1.77E.4 Y-92 1.47E.1 _ - - 2.68E.4 1.65E+S 4.29E-1 Y-93 1.35E2 - - - 8.32E+4 5.79E!S 3.72E.O Zr-95 1.46E+S 4.58!E+ - 6.74E!4 2.69E!6 1.49E.S 3.15E+!
7 Zr-9 1.38E+2 2.72E.1 - 4.12E.1 1.30E.S 6.30E+S 1.26E*1 Nb-95 1.86E!4 1.03E.4 - 1.00!E4 7.S1E+S 9.68E-4 S.66E.3 Nb-97 3.14E-1 7.78E-2 - 9.12E-2 3.93E.3 2.17E.3 2.84E-2
?O-99 - 1.69E.2 - 4.11E+2 1.54ESS 2.69E-S 3.22E.1 Sc 1.3SE-3 3.86E-3 - S.76E:2 1.15E+3 6.13E*3 4.99E-2 Tc-101 5.92E-S 8.'OE-S - 1.52E-3 6.67E.2 8.72E-7 J.24E-4 Ru-103 2.10E.3 - - 7.43E!3 7.B3E*S 1.09E.S S.96E!2 Ru-lOS 1.12E.0 - - 1.41E-0 1.12E-4 9.04E-4 4.34E-!
Ru-106 9.84E!4 - - 1.90E+S 1.61E.7 9.60E+S 1.24E-4 Rh-103- - -
Rb-106 - -
Ax-110m i.38E-4 1.31E.4 - 2.50E!4:'6.75E+6 2.73E+S 7.99E.3 Sb-124 *4.30E!4 7.94E.2 9.76E.1 - 3.85E+6 3.98E:S 1.68E.4 Sb-125 7.3B8E4 J.08E-2 7.04E+1 - 2.74E+6 9.92E-4 1.72E.4 Te-125. 4..8E.3 2.2&E.3 1.4OE.3 - 5.36E-S 7.50E!4 6.67E!2 Tt-127- 1.80E.4 8.16E-3 4..8EI1 6.54E-4 1.66E-6 1.S9E-S 2.18E-3 Te-127 2.01E.0 9.12E-1 1.42E.0 7.28E.0 1.12E-4 8.08E+4 *.42E-I 2
Te-1 9- 1.39E.4 6.58E.3 4.58!E3 5.19E+4 1.98E.6 A.05E. S 2.25E.3 Te-129 7.10E-2 3.38E-2 S.18E-2 2.66E-1 3.30E.3 1.62E+3 1.76E-2 Te-131m 9.84E.1 6.01E.1 7.25E1 4.39E+2 2.38E#S 6.21E.S *.02E-I Te-131 1.58E-2 8.32E-3 1.24E-2 6.18E-2 2.34E.3 1.S1E!1 5.04E-3 Te-132 3.60E.2 2.90E+2 2.46E.2 1.95E+3 4.49E!5 '.63E+5 2.19E+2 1-130 6.24E+3 1.79E+4 1.49E+6 2.75E-4 - 9.12E-3 7.17E+3 1-131 3.54E.4 4.91E!4 1.46E.7 8.40E.4 - 6.49E-3 2.64E!.
1-112 1.59E.3 4.38EL3 I.51!ES 6.92E-3 - 1.27E-3 1.58E3 1-133 1.22E-4 2.05E-. 2.92E+6 3.59E.4 - 1.03E-4 6.22E-3 FERMI 2 ODCM - TRM VOLUME II 7-22 Rev. 13
Table 7.0-4 Raipo, Inhalation Pathway Dose Factors - TEENAGER (Cont.)
(mrem/yr per UCi/m 3 )
Nuclide gone Liver Thyroid Kidney 1.u R Cl-LSU T. Body I-134 B.88E2 2.32E-3 3.95E14 3. 661.3 2.04E+1 8. 40E+2 I-135 3.70E+3 9.44E13 6.21E+S 1.49E-4 6.95E-3 3.49E+3 Cs-134 S.02E-S 1. 13E-6 3.7S1E S 1.46E*5 9.76E+3 5.49E*S Cs-136 S.1SE*4 1.94E.5 1. 10E+5 1.78E14 t.09E-' 1.37E#S Cs-137 6.70E+S 8.48E+S 3.04E-5 1.21E+S 8.48E13 3. 11E.5 Ce-138 4.66E-2 8.56E+2 - 6.62E-2 7.87E*1 2.70E-1 * .46E*2 BA-139 1.34E*O 9.44E-4 - 8.881-4 6.46E*3 6.45E-3 3.90E-2 Sik-140 S.47E-4 6.70E1 - 2.281+1 2.03E 2.29E-S 3. 52E.3 4
B -1 4 1 1.42E-I 1.06E-4 - 9.84t-S 3.29E-3 7.46E-4 4.74E-3 RA-1 2 3.70E-2 3.70E-S _ 3. 14E-S 1.91E+3 - 2.27E-3 LA-140 4.79E+2 2.36E12 2. 14.-5 4.87E.5 6. 26E1.
La-142 9.60E-1 4.25E-1 1.02E+4 1.20E14 1.06E-1 Ce-1Ut 2.84E+4 1.90E+4 - 8.88E-3 6. 14E.5 1.26E.S 2. 17E+3 Ce-143 2.66E.2 1.94E*2 - 8.64E+1 1.30E.5 2.55E#S 2. 16E1.
Ce-144 4.89E+6 2.02E+o - t.21E-6 1.34E+7 8.64E.S 2. 62E+S Pr-143 1.34E.4 S.31E13 - 3.09E*3 4.83E15 2. 14E1S 6.62E-2 Pr-144 4.30E-2 1.76E-2 - 1.01E-2 t .75E13 2.3 SE-4 2. 18E-3 Nd-147 7.86E13 8.56E.3 - 5.02E*3 3. 72E1S 1.82E15 5.13E12 W-187 1.20E 1 9.76E+O 4.74E+4 1.77E.S 3.43E+O Np-239 3.38E+2 3. 19E#I - t1.00E2 6. 49E+4 1.32E+S 1.77E+1 7-23 Rev. 13 FERMI 2 ODCM - TRM VOLUME 11 I
Table 7.0-4 Raipo, Inhalation Pathway Dose Factors - CHILD (mrem/yr per y1Ci/m 3 )
Nuclide Bone Liver Thyroid Kidney Lun CGl-EUl T.Body H-3 -. 1~2E#3 t.t12E-31. 1~2E#3 1.12E-3 1.12E*3 1.12E+3 C-'14 3.S59E.4 6.73E13 6.71E-3 6.73E-3 6.73E-3 6.73E.3 6.73E!.
Na-24 1.61E*4 1.61E-4 1.61E-4 1.61E-4 1.61E-4 t.61E-4 1.61E.4 P-32 2.60E.6 1.11E..5 - - 4.22E-4 9.88E.4 Cr-Sl - - B.55E 1 2.43E.1 1.70E+4 1.08E-3 1.54E12 Kn-54 - 4.29E.4 - 1.00E-4 1.58E.6 2.29E.' 9.51E+3 mn-56 - 1.66E-0 - 1.67E-0 1.31E-4 1.23E-S 3.12E-1 Fe-SS 4.74E+4 2.52E+4 - - 1.11E.5 2.87E-3 7.77E+3 Fe-59 2.07E-4 3.34E' 4 - - 1.27E.6 7.07E-4 1.671+4 Co-57 - 9.03E!2 - - S.07E-S 1.32E-4 1.07E!3 Co-S8 - 1.77E.3 - - 1.11E+6 3.44E-4 3.16E-3 Co-60 - 1.31E.. - - 7.07E-6 9.62E-4 2.26E.4 Hi-63 8.21E15 4.63E+! - - 2.75E#S 6.33E+3 2.80E!4 Ni-65 2.99E+0 2.96E-1 - - 8.18E.3 8.40E-4 1.64E-1 Cu-64 - 1.99E#O - 6.03E.0 9.58E.3 3.67E.4 1.07E#O Zn-65 4.26E!4 1.13E*S - 7.14E!4 9.9SE5E 1.63E!4 7.03E!4 Zn-69 6.70E-2 9.66E-2 - 5.85E-2 1.42E!3 1.02E+4 8.92E-3 Br-82 . - - - - - - 2.09E-4 Br-83 - - - - - - 4.74E'2 Br-B4 - - - - - - 5.48E-2 Br-BS - - - - - - 2.51E-1 R*-B'6 - 1.98E+S - - - 7.99E!3 1.14E-5 Rb-8B . - 5.62E.2 - - - 1.72E+1 3.66E-2 Rb-89 - 3.45E!2 - - - 1.89E.0 2.90E+2 Sr-89 5.99E-S - - - 2.16E!6 1.67E+S 1.72E+4 Sr-90 1.011E# - - - 1.48E!7 3.43E1S 6.44E!6 Sr-91 1.21E!2 - - - 5.33E!4 1.74E.S 4.59E#O Sr-92 1.31E-1 - - - 2.40E-4 2.42E-S 5.25E-1 Y-90 '.111E3 - - - 2.62E*S 2.68E-S 1.11E-2 Y 5.07E-1 - - - 2.81E.3 1.72E+3 1.84E-2 Y-91 9.14E1S - - - 2.63E.6 1.84ESS 2.44!E4 Y-92 2.04E#1 - - - 2.39E.4 2.39E+S 5.81E-1 Y-93 1.86E+2 - - - 7.44E.4 3.89E.S 5.11E+0 Zr-95 1.90E-S 4.18E!4 - 5.96E-4 2.23E!6 6.11!.4 3.70E-4 Zr-97 1.88E.2 2.72E.1 - 3.89E-1 1.13E*S 3.51E+S 1.60E+1 Nb-9S 2.35E!4 9.18E!3 - 8.62E-3 6.14E-5 3.70E-4 6.55E!?
Nb-97 4.29E-1 7.70E-2. - 8.55!E-2 .42E.3 2.78E14 3.60E-2 Mo-99 - 1.72E!2 - 3.92E!2 1.3?S5S 1.27E!S 4.261+1 Tc-99m 1.78E-3 3.48E-3 - 5.07E-2 9.51E+2 4.81E+3 5.77E-2 Tc-101 8.10E-S 8.51E-5 - 1.45E-3 5.85E+2 1.63E+1 1.081-3 Ru-103 2.79E+3 - - 7.03E+3 6.62E-S 4.4E8!4 1.07E+3 Ru-lOS 1.53E!o - - 1.34E-0 1.59E!4 9.95E4 S.SSE-1 -
Ru-106 1.36E-5 - - 1.84E+5 1.43E-7 4.29E!S 1.69E!4 Rh-103- - - - - - -
~~Rh-106 - - - - - - -~~
Aj-110m 1.69E-4 1.14E-4 - 2.12E*4 5.48E+6 1.OOE+S 9.14E-3 Sb-124 5.74E!4 7.40E!2 1.26E!2 - 3.24E-6 1.64E!5 2.00E-4 Sb-125 9.84E!' 7.59E-2 9.10E-1 - 2.32E!6 4.03E?4 2.07E-4 Te-125m 6.73E!. 2.33E-3 1.92E?3 - *.77E-S 3.38E+4 9.14E-2 Te-127m 2.49E.4 8.SSE-3 6.07E!3 6.36E!4 1.48E!6 7.1'.E! 3.02E-3 Te-127 2.77E!0 9.51E-1 1.96E!0 7.07E!0 1.00E-4 5.62E-4 6.11E-1 Te-129m 1.92E?4 6.85E!3 6.33E?3 5.03E!4 1.76E-6 1.82E!S 3.04L-3 Te-129 9.77E-2 3.50E-2 7.14E-2 2.57E-1 2.9?E-? 2.55E.4 2.38E-2 Te-131m 1.34E!2 5.92E!1 9.77E+1 4.OOE 2 2.06E+S 3.08E+S 5.07E-1 Te-131 2.17E-2 8.44E-' 1.70E-2 5.88E-2 2.05E-? 1.33E!. 6.59E-?
Te-132 4.81E!2 2.72E-2 3.17E!2 1.77E*3 3.77E1S 1.38E-S 2.61E-2 1-130 8.18E!3 1.64E' 4 1.85E.6 2.45!-' - 1.11E-3 8.44E'.
1-131 4.1.E.4 4.81E!4 1.62E.7 7.88E-4 - 2.84E-3 2.73E-?
1-132 2.12E!3 4.07E.3 1.94E.5 6.25E-3 - 3.20E!3 1.88E-3 1-133 1.66E!4 2.03E?4 3.85E+6 3.38E!4 - S.'8E.3 7.70E-3 FERMI 2 ODCM - TRM VOLUME II 7-24 Rev. 13
Table 7.0-4 Raipo, Inhalation Pathway Dose Factors - CHILD (Cont.)
(mrem/yr per U Ci/m 3 )
Nuclide to"e Liver Thyroid Xidney Luns Cl-LUI T.ody 1-134 1.17E13 2.16E13 5.07E.4 3.30E*3 - 9.55+2 9.95E12 1-135 4.92E13 8.73E+3 7.92E+5 1.34 E.4 - 4.44E13 4.14E-3 Cs-134 6.51ES 1.011E6 - 3.30E*5 1.21E15 3.85E+3 2.25E+S Ca-136 6.511E+4 1.71E-S - 9.SSE.4 1.45E.4 4.181E3 1.16E15 Cs-137 9.07E15 8.25E+S - 2.82E-5 1.04E-S 3.62E+3 1.28E-S CS-138 6.33E+2 8.40E+2 - 6.22E12 6.81 11 2.70E+2 S.SSE 2 BS-139 1.84E10 9.84E-4 - S.62E-4 5.77E13 5.77E-4 5.37E-2 Ba-l4O 7.40E*4 6.48E-1 - 2.11E+1 1.74E16 1.02£-5 4.33E-3 Ba-141 1.96E-1 1.09E-4 - 9.47E-S 2.92E-3 2.75E+2 6.36E-3 Ba-142 5.00E-2 3.60E-5 - 2.91E-S 1.64E-3 2.74E-0 2.79E-3 La-140 6.44E+2 2.25E-2 - - 1.83E+S 2.26E+S 7.55E+1 La-142 1.30E+0 A.llE-1 - - 8.70E.3 7.59E+4 1.29E-1 Cc-141 3.92E+4 1.95E-4 - 8.55E+3 5.44E+5 5.66E*4 2.90E+3 Cc-143 3.66E+2 1.99E+2 - 8.36t+1 1.1SE+5 1.27E+S 2.87E+1 CU-1.44 6.77E+6 2.12E-6 - 1.17E16 1.20E+7 3.89E+S 3.61E+5 Pr-143 1.85E-4 S.SSE*3 - 3.00E+3 4.33E-5 9.73E-4 9.14E-2 Pr-t44 5.96E-2 1.85E-2 - 9.77E-3 1.57E-3 1.97E+2 3.00E-3 Nd-1 47 1.08E14 8.73E+3 - 4.81E*3 3.28E+S 8.21E-4 6.81E12 W-187 1.63E+1 9.66E-0 - - 4.111E4 9.10E-4 4.33E-0 hp-235 4.b6F+2 3.34E*1 - 9.73E1. 5.81E14 6.40E+4 2.35E+1 FERMI 2 ODCM - TRM VOLUME II 7-25 Rev. 13
Table 7.0-4 Raipo, Inhalation Pathway Dose Factors - INFANT 3
(mremlyr per /1 Cil/m )
Huclide Bone Liver Thyroid Kidney Luns CI-LLI T.Body H-3 - 6.47E.2 6.47E-2 6.47E*2 6:47E-2 6.47E.2 6.47E12 C-14 2.65E4 5.31E13 5.31E*3 5.31E-3 5.31E*3 5.31E-3 5.31E13 Na-24 1.06E*4 1.06E-4 1.06E.4 1.06E+4 1.06E14 1.06E-4 1.06E'4 P-32 2.03E+6 1.12E*S - - - 1.61E.4 7.74E.4 cr-51 - - 5.75E11 1.32E1* 1.28E.4 3.57E-2 8.95E+1 mn-S4 - 2.53E-4 - 4.98E13 1.00E+6 7.06E+3 4.98E13 hn-56 - 1.S4E*0 - . 1.10E*0 1.251+4 7.17E+4 2.21E-1 Fe-SS 1.97E+4 1.17E-4 - - 8.69E.4 1.09E+3 3.33E13 Fe-S9 1.36E*4 2.3SE.4 - - 1.02E+6 2.48E14 9.48E13 Co-57 - 6.51E-2 - - 3.79E+S 4.86E13 6.41E+2 Co-58 - 1.22E.3 - - 7.77E+S 1.11E-4 1.82E13 Co-60 - 8.02E13 - - 4.51E+6 3.19E14 1.18E14 Ni-63 3.39E15 2.04E-4 - - 2.09E-S 2.42E*3 1.16E14 Ni-65 2.39E*0 2.84E-1 - - 8.12E+3 S.01E.4 1.23E-1 Cu-64 - 1.88E10 - 3.98E10 9.30E*3 l.SOIE4 7.74E-1 Zn-6S 1.93E14 6.26E14 - 3.25E-4 6.47E+S 5.14E14 3.11E+4 Zn-69 5.39E-2 9.67E-2 - 4.02E-2 1.47E13 .1.32E-4 7.18E-3 Br-82 - - - - - - 1.33E-4 Br-83 - - - - - - 3.81E+2 Br-84 - - - - - - 4.00E*2 Br-85 - - - - - - 2.04E-1 Rb-86 - 1.90E. -
- - 3.01E.3 8.82E-4 Rb-88 - 5.57E+2 - - - 3.39E12 2.87E*2 Rb-89 - 3.21E12 - - - 6.82E*1 2.06E-2 Sr-J9 3.98E-S - - - 2.03E16 6.40E-4 1.14E-4 Sr-90 4.09E17 - - - 1.12E-7 1.31E-5 2.59E16 Sr-91 9.56E-1 - - - 5.26E14 7.34E.4 3.46E10 Sr-92 1.0SE-1 - - - 2.38aE4 1.40E-S 3.91E-1 Y-90 3.29E-3 - - - 2.69E1* 1.04E15 8.82E-1 Y-91m 4.07E-1 - - - 2.79E-3 2.35E-3 1.39E-2 Y-91 5.88E1S - - - 2.41E16 7.03E'4 1.57E-4 Y-92 1.64E-1 - - - 2.4SE14 1.27E-S 4.61E-1 Y-93 1.501E2 - - - 7.64E14 1.67E-S 4.07E10 Zr-95 1.15E-S 2.79E-4 - 3.11E'4 1.75E16 2.17E14 2.03E-4 Zr-97 1.50*E2 2.56E-1 - 2.59E11 1.10E1* 1.40E15 1.17E-1 Nb-9S 1.57E-4 6.43E*3 - 4.72E13 4.79E15 1.27E-4 3.78E-3 Nb-97 3.42E-1 7.29E-2 - 5.70E-2 3.32E13 2.69E14 2.63E-2 1o-99 - 1.6SE+2 - 2.65E12 1.35E1S 4.87E'4 3.23E-1 Tc-99m 1.40E-3 2.88E-3 - 3.11E-2 8.11E*2 2.03E+3 3.72E-2 Tc-101 6.51E-S 8.23E-S - 9.79E-4 5.84E*2 8.44E12 8.12E-4 Ru-103 . 2.021*3 - - 4.24E13 5.52E-S 1.61E*4 6.79E12 Ru-105 -1.221.0 - - 8.99E-1 1.57E-4 4.84E4 4.10E-1I Ru-106 8.68E-4 - - 1.07E1* 1.16E-7 1.64E1* 1.09E14 Rh-103m - - - - - - -
Rb-106 - _ _ _ _ _
Ag-l10 9.98E*3 7.22E13 - 1.09E14 3.67E-6 3.30E14 S.OOE 3 Sb-124 3.79E*4 5.56E+2 1.01E*2 - 2.65E-6 5.91*E4 1.20E'4 Sb-125 5.17E*4 4.77E*2 6.23E11 - 1.64L*6 1.47E14 1.09E1' Te-125. 4.76E-3 1.991E3 1.62E-3 - 4.47E-1 1.29E-4 6.58E-2 Te-127- 1.67E14 6.90E+3 *.87E-3 3.75E-4 1.31E*6 2.73E-4 2.07E-3 Te-127 2.23E*0 9.53E-1 1.8SE10 4.86E10 1.03E14 2.44E14 4.89E-1 Te-129- 1.41E14 6.09E+3 S.47E*3 3.18E14 1.68E*6 6.90E1. 2.23E13 Te-129 7.88E-2 3.47E-2 6.75E-2 1.75E-1 3.00E13 2.63E14 1.88E-2 Te-131- 1.07E12 S.SOE1 8.93E11 2.6SE12 1.99E1S 1.19E15 3.63E-1 Te-131 1.74E-2 8.22E-3 1.58E-2 3.99E-2 2.06*E3 8.22E13 S.OOE-3 Te-132 3.72E12 2.37E12 2.79E*2 1.03E13 3.40E*S 4.41E*4 1.76E12 1-130 6.36E13 1.39E*4 1.60E-6 1.53E14 - 1.99E13 5.57E13 1-131 3.79E-4 4.44E14 1.48E-7 5.18E*4 - 1.06E*3 1.96E*4 1-132 1.69E*3 3.54E-3 1.69E1* 3.9*E-3 - 1.90E*3 1.26E-3 1-133 1.32E-4 1.92E'4 3.56E*6 2.24E14 - 2.16E-3 5.60E13 FERMI 2 ODCM - TRM VOLUME II 7-26 . Rev. 13
Table 7.0-4 Raipo, Inhalation Pathway Dose Factors - INFANT (Cont.)
(mrem/yr per y Ci/m 3 )
Muclide load Liver Thyroid Kidney Lrns Cl-LU T.So4y 1-134 9.21E+2 1.88E+3 l.4SE+A 2.09E+3 - 1.29E-3 6.65E.2 1-135 3.86E+3 7.60E.3 6.96E.5 3.47.-3 - 1.IaE.3 2.77E-3 Cs-134 3.96E*S 7.03E.S - 1.9^E^S 7.97E.4 -1.33E-3 7.45E.4 Cs-136 4.83E-4 1.3SE.S - 5.64E+4 1.¶8E+^ 1.43E-3 5.29E-4 Cs-137 S.49E.5 6.12E.S - 1.72E.5 7.13E4 1.33E*3 4.SSE+4.
Cs-138 S.OSE.2 7.81E+2 - 4.10E+2 6.54E+1 8.76E.2 3.98E*2 Ba-139 .1.48E.O 9.84E-4. - 5.921..4 S.95E.3 S.1OE.4 4.30E-2 BS-l40 5.6 S k:.1 1.34l i.60E16 3.8'E.4 2.90E.3 Sa-141 1.57t-1 I.O8E-4 - 6.SOE-S 2.97E*3 4.7SE.3 4.91E-3 la-142 3.98E-2 3.30E..5 - 1.90ES 1.S5E33 6.93E-S 1.96E-3 LA-t40 5.OSE.2 2.OOE.2 - - 1.68E+S 8.48E-4. S.ISE.1 L~A-142 1.03E.O 3.77E-1 - - 8.22E.3 S.9SE.4 9.04E-2 Ce-141 2.77E.4 1.67E#e. - S.25E.3 S.17E.S 2.16E+4 1.99Ei3 Cc-143 2.93E+2 1.93E+2 - 5.b64E1 1.16E*S 4.97E.4 2.21E+1 Ce-144 3.19E.6 1.21E.6 - S.38E.5 9.84ti'6 1.I.BE#S 1.76E'5 Pr-143 1.40E+A 5.24E.3 - 1.97E.3 4.33E#S 3.72E+4 6.99E#2 Pr-1i& A.79E-2 i.85E-2 - 6.72E-3 1.61E+3 4.28E+3 2.41E-3 14d-14.7 7.94E.3 8.13E+3 - 3.15E.3 3.22Et5 3.12E+4 S.OOE+2 W-187 1.30E.1 9.02E+O - - 3.96E+4 3.56E.4 3.12E.O 4 23 1 p- 9 3.71E.2 3.321.1 - 6.62E.1 5.~95E.4 2.49Ei1. 1.88E-1 FERMI 2 ODCM -TRM VOLUME 11 7-27 Rev. 13
Table 7.0-4 Raipo, Grass-Cow-Milk Pathway Dose Factors - ADULT (mrem/yr per jUCi/m 3 ) for H-3 and C-14 (m 2 x mrem/yr per UCi/sec) for others Nuclide Bone Liver Thyroid, Kidney Lung Gl-Lll T.Body H-3 7.63E[2 7.63E.2 7.63E*2 7.63E.2 7.63E-2 7.63E-2 C_ 14 3.63E-5 7.26E#4 7.26E#4 7.26E-4 7.26E#4 7.26E*4 7.26E-4 Ns-24 2. 54E+6 2.54E6 2.54E.6 2.54ES6 2.54E-6 2. 54E-6 2.54ES6 P-32 1.7 1[E.0 i.06E.9 1.92E-9 6. 60E-8 Cr-S I 1.71E-4 6.30E#3 3. S0E.4 7.20E-6 2.86E*4 Mn-54 8 40E#6 - 2.SOE+6 2. 57E-7 1.60E+6 Mn-56 *.23E-3 - S.3BE-3 I.35E-1 7.5 IE-4 Fe-SS 2.5 E#7 1.73E-7 9.67E#6 9.95E6 4.04E#6 Fc-59 2.98E.7 7.OOE+7 1.95E*7 2.33E#8 2.68E+7 Co-57 1.28E+6 3.25E-7 2. 13E[6 Co-SB - 4.72E#6 - 9.57E+7 1. 06E+7 Co-60 - 1.64E.7 - 3.08E#8 3.62E+7 Ni-63 6.73E-9 4.66E#8 - 9.73E+7 2.26E .
Ni-65 3.70E-1 4.61E-2 - 1.22EtO 2.19E-2 Cu-64 - 2.41E-4 - 6.08E#4 - 2.OSE+6 1.13E#4 Zn-65 1.37E#9 4.36E-9 - Z.92EM9 - 2.75E[9 1.97E 9 Zn-69 -
Sr-82 - - 3.72E+7 3.2SE[7 Br-B3 - - 1.49E-1 1.03E-1 Br-b4 -
Br-8s -
Rb-86 - 2.59E[9 - - - S.1tE+8 1.2i1E#9 Rb-88 -
Rb-89 -
Sr-89 1.45E+9 - - - - 2.33E-8 4.16E-7 Sr-90 4.68E-10 - - - - 1.35E-9 1.1SE+ 10 Sr-91 3.13E.4 - - - - 1.49E-5 1.27E[3 Sr-92 4.89E-1 - - - - 9.68E#O 2. l1E-2 Y-90 7.07E.I _ _ - - 7.SOE+S 1.90E.O Y -
Y-91 8.60E+3 - 4.73E+6 2.30E*2 Y-92 5.42E-S - 9.49E-1 1.58E-6 Y-93 2.33E-1 - 7.39E.3 6.4 3E-3 Zr-95 9.46E+2 3.03E[2 - 4.76E*2 - 9.62E+S 2.OStE2 Zr-97 4.26E-1 8.59E-2 - 1.30E-1 - 2.66E#4 3. 93E-2 Nb-95 8.25E[4 *.59E-4 - 4.54E-4 - 2.79E#6 2. 47E-4 Nb-97 _ _ 5.47E-9 Mo-99 _ 2.52E-7 - . 5.72E-7 - S.tSE-7 4.80E.6 TC-99m 3.25E*O 9. 19EtO - 1.40E+2 '.5OE+O S.44E+3 1. 17E#2 Tc-1OI _
Ru-103 1.02E[3 - 3.89E.3 - 1. 19t.s A.39E.2 Ru-lOS S.57£-4 - l.IIE-2 - S.24E-1 3.38E-4 Ru-106 2.04E.4 _3.94E+4 - 1.32E,6 2. S8E#3 Rh-103P -
Rh-106 -
As-110o 5.83E.7 5.39E-7 1.06E,8 - 2.20E- 10 3.20E#7 Sb-124 2.57E#7 4.86E[5 6.24[E4 2.CD0E.7 7.31tE# t.02E#7 Sb-125 2.04E#7 2.28E[S 2.08E.4 1.SSBE.7 2.2SE,8 4.86E-6 Te-125 1.63E.7 S.90Et6 4.90E#6 6.63;E7 - 6.50E-7 2. 18E-6 Te-127w 4.SBE[7 1.64Et7 1. 17E#7 1.86E#B - 1.54EBS S. S8tE6 Te-127 6.72E#2 2. 41 E2 4.98E62 2.74 E 3 - S.301e'. .1.45SE2 Te-129w 6.04E+7 2.2SEe7 2.08E67 2. 52Et8 - 3.04E#. 9.57E#6 Te-129 -
Te-131m 3.61E-S 1.77E S 2. SOt. 5 1.79E+6 - 1.75E#7 1.47E#S Te-131 -
Te-132 2.39E.6 l.SSE-6 1.71E[6 1. 49E+7 - 7.32E-7 1.45.E6 1-130 4.26E[S 1.26Ei6 1.07E-8 1.96E+6 - I.08E+6 4.96E-S 1-131 2.96E*8 *.24Et8 1.39Et.1 7.27E+B - 1.12Etl 2.43E#8 1-132 1.64E-1 4. 37E-1 I.S3E-I 6.97E-1 - t.22E-2 1.53E-1 1-133 3.97E.6 6.90E-6 I.01E-9 1.20E'7 - 6.20E-6 2.10Et6 FERMI 2 ODCM - TRM VOLUME 11 7-28 Rev. 13
Table 7.0-4 Raipo, Grass-Cow-Milk Pathway Dose Factors - ADULT (CONT.)
3 (mrem/yr per ,Ci/m ) for H-3 and C-14 2
(m x mrem/yr per pCi/sec) for others Nuciide looe Liver Thyroid Kidney Lunt C1-LLI T.Body I-134 I-135 1.39E+4 3.63E*4 2. 40E.6 S.83E14 - 4.10E.4 1.34E14 Cs-134 5.65E-9 1.34E+10 4.35E*9 1.44E*9 2.35E-8 1.101+10 C.-136 2.61E18 1.03E19 5. 74E-8 7.87E-7 1.17E-8 7.42E18 Cs-137 7.38E-9 1.011E10 3. 3E-9 1.14E19 1.95E.8 6.61E*9 C.-138 U--139 4.70E-8 - 8.34E-8 1.38E-9 Ba- 140 2.69E-7 3.38E+4 - 1.15E-4 S.54E+7 1.76E16 BA-141 Ba-142 La-140 A.49E1O 2.26E+O - - - 1.66E+S 5.97E-1 La-142 - 3.03E-8 Cc-I 4 4.84E.3 3.27E13 - 1.52E13 - 1.25E-7 3.711E2 Ce-143 A.19E*1 3.09E14 - 1.36E-1 - 1.16E16 3.42E1O Cc- 144 3.58E-S 1.50E#S - 8.87E14 - 1.21E+8 1.92E+4 Pr-143 1.59E+2 6.37E11 - 3.68E*1 f6.96E+S 7.881*0 Pr-144 Nd-147 9. 42E1 1 1.09E+2 - 6.37E+1 _ 5.23E+S 6.52E+O Y-187 6.56E+3 5.48E+3 - - - 1.80E16 1.92E#3 Np-239 3. 66E+O 3.60E-1 - . 1.12E1O _ 7. 39E4 1.98E-1 FERMI 2 ODCM - TRM VOLUME 11 7-29 Rev. 13 l
Table 7.0-4 Raipo, Grass-Cow-Milk Pathway Dose Factors - TEENAGER (mrem/yr per /.tCi/m 3 ) for H-3 and C-14 (m 2 x mrem/yr per ,Ci/sec) for others Nucl ide Bone Liver Thyroid Kidney Lung CI-LL1 I. Body H-3 9.94EK2 9.9'.E-2 9.94E.2 9.94E.2 9.94EK.2 9.94E.2 C-"4 6.70E- 5 1.34E#S 1.34EK.S 1.34E+S 1.3'E-S Nz-24 4.44E*K6 4.44E 6 4.4'.E.6 4.44E+6 '..44E-6 '...44E6 4..44KE6 P-32 3. ISE+10 1.95E.9 - 2.65E.9 1.22E-9 Cr-S1 2.78K.'4 1.10!.'. 7.13K.'. 8.'.OE.6 S.OOE-4 1.40E-7 - 4.17E*6 - 2.87E.7 2. 78E-6 Mtn-54
7. SIE-3 - 4.94E-I 1.33E-3 4.45E!7 3. 16E-7 - 9.50E-3 7.36E-6 Fe- 55 2.OOE.7 1.37E.7 Fe-59 5.20EK7 1.21E.8 3.82E.7 2.87E.8 4.68E-7 Co-57 2. 2SE+6 - 4.19E.7 3.76E.6 Co-58 7.95E,6 - I.10E.B 1.83E+7 Co-60 2.78E+7 - 3.62E.8 6.26E-7 Ni1-63 t. 18E. 10 8.35E8 - 1.33E+B 4.01E-8 Ni-65 6.78E-I 8.66E-2 - '.70E,0 3.94E-2 Cu-64 4.29EK4 - 1.09E+S - 3.33E.6 2.02E-4 Zn-65 2. IIKE9 7.3 IE.9 - '..68E.9 - 3.IOE#9 3.41E.9 Zn-69 Br-82 S. 64E.7 Br-83 1.91E-1 Br-84.
Br-85 Rb-86 73E.9 - - 7.00E+8 2.22E-9 Rb-88 Rb-89 Sr-89 2.67E 9 - . - - - 3.1BK.8 7.66E.7 Sr-90 6.61E 10 - - - - I.86E*9 1.63EK10 Sr-91 5.75!E.4 - - - - 2.61E.5 2.29E+3
.Sr-92 8.9SE-I - - - - 2.28E.1 3.81E-2 Y-90 1.30E02 - - - - 1.07E+6 3. SO.0 1-91.
1-91 t1.58!.'. - 6.48E.6 4.24E*2 Y-92 1 .00E-4 - 2.75E*0 2.90E-6 Y-93 *. 30E-I - .1.31E-4 1. 1tE-2 Zr-95 1.6SE-3 S.22E!2 - 7.67E.2 - 1.20E-6 3.59E-2 Zr-97 7.75E-1 1.53E-1 - 2.32E-1 - 4.15KE.4 7.06E-2 Xb-95 1.4IE+S 7.80EK4 _ 7.57E.4 - 3.34E.8 4.30E.4 Nb-97 - 6.34E-8 Mo-99 4.56.E7 - 1.04E.8 - e. 16E.7 B.69EK6 rC-99U 5.64E.0 1. 57E+1 - 2.34E.2 9.73E-o 1.03E.' 2.04EK2 IC-10I RU- 103 1.81E-3 - 6.40*E3 - I.52E-5 7.75E*2 Ru- 105 1.57E-3 - 1.97E-2 - 1.26EK0 6.08E-4 Ru- 106 3.75.E-4 - 7.23E-4 - 1.80E.6 *4.73E.3 Rh- 103.
Ah- 106 AS- I . 9.63EK7 9. 11E.7 I.74E*8 - 2.56E-10 S. 54EK7 Sb-124 '4.59EK7 2.46E.S t.04E-S 4.01E!7 9.25E.8 1.79EK7 Sb-12S 3. 65EK7 3.99EKS 3.49E-! 3.21E-7 2.B'EK8 8.54E.6 Tc-125. 3.00.E?7 1.08E.7 8.39E-6 - 8.86E!7 *.02EK6 Te-127m 8.44E.7 2.99EK7 2.01E 7 3.42EK8 - 2.10EKB 1.00E-7 Te-127 1.24E*3 4.41E.2 S. 59E.2 S.04E.3 - 9.61E.4 2.68E 2 Te-129m 4.10EK7 3.57E.7 4.62EK8 - 4.15EK8 1.75EK7 Tc- 129 1.67E-9 - 2.18E-9 Ie-13 1. 6. 57E.S 3. 15EIS 4.74E S 3:29EK6 - 2.53E!7 2. 63E*S Te-131 Te-132 4.28E-6 2.71EK6 2.86EK6 2.60E!7 - . 8.58K.? 2. SSE-6 1-130 7.49E.S 2.17EK6 1.77E.8 3.34E,6 - -1.67E-6 8.66E-S 1-13 1 S. 38KE8 7.53EK8 2.20EK11 1.3 0!9 - 1.49EK8 4.04 E-8 1-132 2.90E-I 7.59E-1 2.56EK. 1.20E,0 - 3.31E-1 2.72E-I 1-133 7.24E.6 1.23E!7 1.72E.9 2.1SE!7 - 9.30E-6 3.7 ES6 FERMI 2 ODCM - TRM VOLUME 11 7-30 Rev. 13 1
Table 7.0-4 Raipo, Grass-Cow Milk-Pathway Dose Factors - TEENAGER (Cont.)
(mrerm/yr per .UCilm 3) for H-3 and C-14 (m 2 x mrem/yr per /lCilsec) for others Nucl id. Bo&C Liver Thyroid Kicdney Luns CI-LL1 T. Mdy
______- _______ ------ _.____6 _ - ---
J -1J. - _ _ _
1-135 2.47E-4 6.35E.4 4.08E-6 1.CDOE5 - 7.03E.4 2.35E+4 Cs-134 9.JIE-9 2.31E+10 7.3 31E+Y 2.801E9 2.8.7E+8 1.07E.10 Cs-136 *.4SE-8 1.75E+9 9.5 53E.8 1.50o+8 1. 41E.-8 1. 18.E9 Cs-137 1.34E+10 1.7UE110 6.0 )6E19 2.35E+9 2.53E.8 6.20E19 Cs-138 Ba-139 8.69E-8 7.75E-7 2.53E-9 Ba-140 4. 3 51.7 S.95E14 2.0 12E1.44.0OEr+ 7.49E+7 3. 13E.6 Ba-1'1 Ba- 142 LA-140
8.06E-0 3. 96E1O - 2.27t#5 1.05E-o La-142 - 2.23E-7 Ce-141 8.87E+3 5.92E13 - 1 2.79E13 - 1.69E.7 6. 1.E+2 Ce-143 7.69E1, S.60E-4 - 2.51IE.1 - 1.68E+6 6. 25E.0 Ce-144 6.58E1S 2.721. 5 _ 1.63E#S - 1.66E18 3.54 E.4 Pr-143 2.92E*2 1. 17E.2 - 6.77E1.i - 9.61E+5 1.45E+1 Pr-'144 Nd-147 1.811.2 1. 97E+2 - 1.16E+2 - 7.IIE+S t.18E1+
I4-187 1.20E.4 9. 78E+3 - 2.65E+6 3. 431+3 Np-239 6. 99E1o 6.59E- I - 2.07E#0 - 1.06E+S 3.66E-1 FERMI 2 ODCM - TRM VOLUME II 7-31 Rev. 13 I
Table 7.0-4 Raipo, Grass-Cow-Milk Pathway Dose Factors - CHILD (mremlyr per UCi/m 3 ) for H-3 and C-14 (m 2 x mremlyr per pCi/sec) for others Nuclide 8one Liver Thyroid Xidney Lunt CI-LLI T.Body H-3 - t.S7E-3 1.57E.3 I.S7E+3 1.57E+3 1.57E.3 1.S7E.3 C-14 1.6SE+6 3.29E.S 3.29ECS 3.29E.S 3.29E+S 3.29E-S 3.29E+S Na-24 9.23E#6 9.23E*6 9.23E.6 9.23EL6 9.23E.6 9.23E-6 9.23E16 P-32 7.77E+lO 3.64E+9 - - - 2.tSE-9 3.OOE.9 Cr-St - - S.66E.4 I.SSE+4 1.03E5S S.41E-6 1.02E+S Kn-54 - 2.09E+7 - S.87E#6 - 1.76E-7 5.58E-6 hn-56 - 1.31E-2 - 1.58E-2 - 1.90E+0 2.95E-3 Fe-SS 1.12E+8 5.93E+7 - - 3.35E-7 l.1OE+7 1.84E-7 Fe-59 1.20E-8 1.95E.8 - - S.65E-7 2.03E*8 9.71E-7 Co-57 - 3.84E+6 - - - 3.i4E+7 7.77E-6 Co-St - 1.21E-7 - - - 7.08E+7 3.72E-7 Co-60 - &.32E.7 - - - 2.39E+8 1.27E+8 Ni-63 2.96E.10 1.59E-9 - - : .07E+8 1.OIE+9 Ni-65 1.66E-0 1.56E-1 - - - 1.91E-1 9.11E-2 Cu-64 - 7.SSE+4 - 1.82E+S - 3.5 4E-6 4.56E-4 Zn-65 A.13E*9 I.IOE.10 6.94E+9 - 1.93E*9 6.85E-9 Zn-69 - - - - - 2.1E-9 -
Br-82 - - - - - - l.lSE+8 Br-83 - - - - - - 4.69£-1 Br-84 _ _
Br-8s . - _ _ _ _
Rtb-86 - 8.77E#9 - - - 5.64E58 5.39E59 Rb-88 - _ _ _ _ _ _
Rb-89 _ _ _ - _
Sr-89 6.62E.9 - - - - 2.56E+S 1.89E+8 Sr-90 1.12E5ll - -- .SIE.9 2.83E.10 Sr-91 1.1E.5.- - - 3.12E5S 5.33E53 Sr-92 2.19E-O - - 4.1..E+1 8.76E-2 Y-90 3.22E+2 - - - - 9.1S5E+S 8.61E+o Y-9t-m - - - -
Y-91 3.91E.4 - - - - 5.21E-6 1.04E*3 Y-92 2.46E-4 - - - - 7:10E+0 7.03E-6 Y-93 1.06E.0 - - - - 1.571+4 2.90E-2 Zr-95 3.84E.3 8.45E+2 - 1.211.3 - B.811+S 7.52E+2 Zr-97 1.89E-0 2.72E-1 - 3.91E-1 - 4.13E+4 1.61E-t Nb-95 3.18E+S 1.24E+S - 1.16E+5S - 2.29E+S 8.81E-.
Nb-97 - - - - - 1. 5E-6 -
Mo-99 - 8.29E+7 - 1.77E*8 - 6.86E.7 2.05E.7 Tc-990 1.29E5. 2.51E,1 - 3.68E52 1.29E+. 1.44E.4 4.20E#2 Se-tOt - - - - _ , _ -
Ru-101 *.29E+3 - - 1.08E.4 - 1.115ES 1.65ME3 Ru-tOS 3.82E-3 - - 3.36E-2 - 2.49E.0 1.39E-3 Ru-106 9.24E54 - - 1.2SE+S - 1..4E-6 1.15E+4 Rh-tO3- - - - - - - -
Rh-106 - - - - - _ _
As-lion 2.09E+. 1.41E18 - 2.63E+S - 1.68E+lo 1.13E+8 Sb-12 1.09E#8 I.1t1.8 2.10E5S - 6.03E-7 6.79E+8 3.81E57 Sb-125 8.70E.7 1.AIE.6 8.06E54 - 4.85E-7 2.08EO8 1.52E57 Te-125- 7.38E57 2.00E57 2.07E#7 - - 7.12E-7 9.84E-6 Te-127I 2.08E*$ 5.60E57 4.97E*7 S.93E+B - 1.68Eg 2.i7E-7 Te-127 3.06E53 9.25E+2 2.12E-3 8.71E3* - 1.20E5S 6.56E-2 Te-129c 2.72E58 7.61L.7 8.78E57 8.00E5S - 3.3268 4.23E-7 Te-129 - - - 2.87E-9 - 6.12E-8 -
Te-t3t- 1.60E-6 S.53E5S 1.14E+6 S.35E6 - 2.24E.7 5.89E+S Te-tMt - _ _ _ _ _ _
Te-t32 1.02E.7 4.52E-6 6.585E-6 .20E+7 - 4.SSE7 5.46E56 I-1i0 1.75E56 3.54E.6 3.90E58 5.29E-6 - 1.66E+6 1.82E.6 I-131 1.30E#9 1.31E-9 4.35E+.1 2.1$E.9 - 1.17E-8 7.46E5.
1-132 6.86E-1 1.26E+0 S.85E-t 1.93E-0 - 1.48E-0 S.80E-1 1-133 1.76E.7 2.85E.7 4.04E.9 3.63E57 - 9.77E-6 8.23E*6 FERMI 2 ODCM - TRM VOLUME II 7-32 Rev. 13
Table 7.0-4 Raipo, Grass-Cow-Milk Pathway Dose Factors - CHILD (CONT.)
(mrem/yr per JlCi/m 3 ) for H-3 and C-14 (m 2 x mrem/yr per ,uCilsec) for others Niuecide &on. Liver Thyroid Kidney Luns CI-LLI T.body 1-1 34 I-135 5.81.14 1.05-5 9. 30E+6 1.61E15 8.00+1.. 4.97E14 Co-134 2.26E-10 3.711*10 1.1 SE. 10 4. 131.9 2.00E18 7.83E#9 Cs-136 1.00E-9 2.76E+9 1.47E+9 2. 19E-8 9.70E-7 1.79E*9 Cs -137 3.22E#10 3.09E-10 1.01E-10 3.62E19 1.93E-8 4.SSE+9 BA-139 2. 14E-7 1.23£-5 6.19E-9 Ba-I 40 1. 17E#8 1.03E*S _ 3.34E#4 6. 12E-4 5.94E+7 6.83.E6 Da-lid 4-a-142 LA-1 40 1.93E1+ 6.74E10 - t1.88+5 2.27E*o La-I142 - 2.51E-6 Ce-141 2. 19E+4 1.091E- - *.7SE-3 - 1.36E+7- 1.62E+3 Ce-14.3 .89E+2 1.02E+S - 4.29E+1 - 1.50E+6 1. 481*1 ce-144 1.62E+6 5.09E1S - 2.82E15 - 1.33E+8 8.66E14 Pr-143 7.23E+2 2. 17E+2 - 1.17E+2 - 7.80E+5 3.59E+1 Pr-1144 lid- 147 4.45E.2 3.60E12 - 1.98E+2 - 5.71E-5 2.79E+1 WJ-187 2.91E+4 1.72E+4 - 2.42E.6 7.73E-3 239 lip- 1.72E 1 1.23E1O - 3.57E+C - 9. 14E14 8.68E-1 FERMI 2 ODCM - TRM VOLUME II 7-33 Rev. 13 l
Table 7.0-4 Raipo, Grass-Cow-Milk Pathway Dose Factors - INFANT 3
(mrem/yr per /CCi/m ) for H-3 and C-14 2
(m x mrem/yr per JlCilsec) for others MuClide Bone Liver Thyroid Kidney Lung CI-LLI T.Body r - - - - _-----_
H-3 2.38E.3 2.38E+3 2.38E3 2.8:E+3 2:3;E#3 2.38E.3 c-.14 3.23E.6 6.89EvS 6.89E+S 6.B9E*S 6.B9E+S 6.89E-5 6.89E15 ma-24 1.61E7 1.61Ev7 1.61E17 1.61Ev7 1.61E*7 1.61E.7 1.61E.7 P-32 1.60E* 1I 9.42E.9 - 2.17E+9 6.211.9 cr-51 1.05E+S 2.30E.4 2.05rES 4.71E.6 1.61E+S mn-S4 3.89E-7 - B.63E-6 - 1.43E+7 8.83E+6 Kn-56 3.21E-2 - 2.76E-2 - 2.91E-o S. S3E-3 Fe-S5 1.35.E8 a. 72E-7 4.27E-7 1.11E-7 2.33E-7 Fe-59 2.2SE.8 3. 93 E. 1.16E-B 1.88E-. I.55E-8 Co-57 S. 95E+6 - 3.05E-7 1.46E-7 Co-S5 A.4 - 6.05E-7 6.06E-7 Co-60 8. 811E7 _ _ - 2.10EvB 2.08E-8 N1-63 3.49E.10 2.16E.9 _ - 1.07E+8 1.21E.9 Ni-65 3.5 1E-O 3.597E-1 - _ - 3.02E-1 1.JIE-l Cu-64 1.8SE.5 - 3.17E+S - 3.85JE6 8.69Ev4 Zn-65 S. SSE*9 1.9CoE+10 - 9.23E+9 - 1.61E+10 9.79E*9 Zn-69 - 7.36E-9 Br-82 1.94E.8 Br-83 9.95E-I Br-8' Br-BS Rb-86 2.22E-10 - - - S.69EB8 1.1oE010 Rb-8b Rb-89 Sr-89 1.26E-10 - - - 2.59E18 3.61E1a Sr-90 1.22E+.I - - - - 1.52E-9 3. 10E.10 Sr-91 2. 94E-5 - _ 3.48E#S 1.06E.4 Sr-92 4.65E*O _ _ - - S.OE+1 1.73E-1 Y-90 6.SOE.2 _ _ - - 9.39E*S 1.82E-1 Y-91k Y-91 7.33E14 - 5.26E.6 1.95E-3 Y-92 5.22E-4 - 9.971.0 1.47E-S Y-93 2.25E1O - 1.78E+4 6.13E-2 Zr-9S 6.83E+3 1.66E13 - 1.79E-3 - 8.28E+S I.18.E3 Zr-97 3.99E10 6.BSE-I - 6.91E-1 - 4.37E-4 3. 13E-I Nb-95 S. 93E1S 2.44E.5 _ 1.75E*S - 2.06E-8 1.411.5 Nb-97 - 3.70E-6 Mo-99 2. 12E.8 - 3.17E+8 - 6.98E-7 4.13E+7 Tc-99m 2.69E1. 5.5SE1 - 5.971+2 2.90E-1 1.611.4 7. 1512 Te-101 Ru-103 B.69E.3 - 1.811E1. - 1.061ES 2.91E.3 Ru-1OS t.06E-3 5.92E-2 - 3.21E1O 2.71E-3 Ru-106 1.90E1S - 2.25E5 - 1.44E.6 2.38E.4 Rh-103&
Rh-106 A&-11O. 3.86E-8 2.821.8 4.03E.8 1.46E+10 1.86E18 Sb-124 2.09E*8 3. 08E6 S. 56E- 5 1.31E18 6.46E.8 6.49E-7 Sb-125 1.49E-8 t.45E-6 1.87E1S 9. 38E.7 1. 99E-8 3.07E17 12 7. 18.E7 2.04E.7 Te- 5& I.SE*8 5. 04 147 5.07E#7 Te-127a 4.21E.B 1.40E18 1.22E,8 1.04E-9 1.70E-8 S. OE.7 Te-127 6. 50E.3 2. 18E-3 S.29E.3 l1.59E.4 - 1.36E*S 1.40E.3 Te-129. S. 59E.8 1.921E8 2. 15.E8 1.40E-9 - 3. 34E.8 8.62E.7 Te-129 2.05E-9 1.75E-9 S. 18E-9 - 1.66E-7 Te-lll- 3.38E.6 1.36E.6 2.76E.6 9.35E*6 - 2.29E17 1.12E#6 Te-131 Te-132 2. 10.E7 1.04E-7 1.54E17 6.S1E.7 - 3. 85E-7 9.72E.6 1-130 3.60E16 7.92E*6 8.8E*4 8.70E*6 - 1.70E6 IE6 3.18 1-131 2.72E-9 3.21E19 1.OSE012 3.7SE.9 - .1ISE8 I.41E-9 1-132 1.1*2E*O 2.89E10 1.35E#2 3.22E1o - 2.34E-O 1.03E#O 1-133 3.72E.7 5.41E7 9.84E#9 6.36E,7 - 9.16E16 1. SBEv7 FERMI 2 ODCM - TRM VOLUME 11 7-34 Rev. 13
Table 7.0-4 R aipo Grass-Cow-Milk Pathway Dose Factors - INFANT (CONT.)
(mrem/yr per .LCi/m3 ) for H-3 and C-14 (m 2 x mrem/yr per plCi/sec) for others Nuclide soot Liver Thyroid Kidney Luns CX-LLI T.Body 1-134 - - 1.01E-9 - - _
1-135 1.21E+5 2.41E-5 2.16E#7 2.69E1S - 8.74E*4 8.80E.4 Ca-114 3.65E*10 6.80E#10 - 1.75E+10 7.18E*9 1.85E-8 6.87E.9 Cs-136 1.96E+9 5.77E+9 - 2.30E:9 4.70E1* 8.76E17 2.15E+9 Cs-137 S.ISE#10 6.02E+10 - 1.62E+10 6.55E+9 1.88E*8 4.27E+9 Cs-138 Ua-139 4. SSE-7 _ 2.88E-5 1.32E-8 ZA-140 2.41E*8 2.41E+S 5.73E*4 1.48E+S 5.92E+7 1.24E+7 DA-141 8A-142 La-140 4.03E+1 1.59E11 - 1.87E+S 4.091.0 Li-142 - 5.21E-6 Ce-lid 4 .33E+4 2.64E-4 - 8.15E - 1.37E.7 3. 11E13 Ce-143 4.OOE.2 2.65E-5 - 7.72E11 - l..SSE+6 3.02E11 Ce-I44 2. 33E+6 9.52E15 _ 3.8SE#S - 1.33E+8 1.30E#S Pr-143 1.49E+3 5 59E.2 - 2.08E+2 - 7.89E+S 7.41E*1 Pr-144 Nd-1f.7 8.82E+2 9.06E12 - 3.49E.2 _ 5.74E#S S. SSE+ 1 W-187 6. 12E+4 4.26E-4 - 2.50E+6 1.47E*4 Np-239 3.64E+1 3.25E*o - . 6.49E+0 - 9.40E+4 1.84E+0 FERMI 2 ODCM - TRM VOLUME 11 7-35 Rev. 13 l
Table 7.0-4 Raipo, Grass-Cow-Meat Pathway Dose Factors - ADULT (mremtyr per CtCi/m 3 ) for H-3 and C-14 (m 2 x mremlyr per pCi/sec) for others Nucl ide Bone Liver Thyroid Kidney Luns CI-LUI T.Body H4-3 3.2SE-2 3.25E.2 3.25E.2 3.25E+2 3.25E12 3. 25E+2 C-14 3.33E1S 6.66E-4 6.66E-4 6.66E.4 6.66E14 6.66E-4 6. 66E.4 Na-24 1.84E-3 1.84E-3 1.84E-3 1.84E-3 1.84E-3 1.84E-3 1.84E-3 P-32 4.65E1.9 2.89E+8 - 5.23E+8 1.6oS c Cr-S1 4.22E#3 1.56E+3 9.38E*3 1.7BE+6 7.07E13 hn-54 9. 15E.6 - 2.72E16 - 2.80E+7 1.75E-6 Nn-56 Fe-S5 2.93E#8 2.02E.8 1.13E*8 1.16E+8 4.72E+7 Fe-59 2.67E*8 6.27E-8 1.75E*8 2.09E-9 2.40EB8 Co-57 5.64E-6 - 1.43E+8 9.37E6 Co-58 1.83E17 - 3.70E-8 4. 10E.7 Co-60 7.52E#7 - 1.41E-9 1. 66E*8 Ni-63 1.89E-10 1.31E.9 - 2.731E8 6.33E-8 Ni-65 Cu-64 2.95E-7 - 7.45E-7 - 2.52E-S 1.39E-7 Zn-6S 3.56E-8 1.13E.9 _ - 7.57_ - 7.13E+8 5. 12E#8 Zn-69 Br-82 - 1.44E13 1.26E*3 Br-83 Br-84 Br-85 Rb-86 4. 87E+$ - - - 9.60E-7 2.27E+8 Rb-88 Rb-89 Sr-89 3.01E+8 - - - - 4.84E-7 B.65E+6 Sr-90 1.24E-10 _ _ - - 3.59E-* 3.05E#9 Sr-91 - 1.38E-9 Sr-92 Y-90 1.07E+2 - - - - 1.13E-6 2.86E*0 Y-91.
Y-91 1.13E.6 - - - - 6.241+8 3.03E-4 Y-92 Y-93 - - - - 2.08E-7 Zr-95 1.88E+6 6. 04E+S - 9.48E+S - 1.91E19 4.09E+S Zr-97 1.83E-S 3. 69E-6 - 5.58E-6 - 1.14E+O 1.69E-6 Nb-9S 2.29E16 1.2 BE.6 - 1.26E*6 _ 7.75E+9 6.86E+S Nb-97 Mo-99 1.09E+S - 2.46E#S - 2.52r*s 2.07E.4 Tc-99.
Tc-101 Ru-103 1.06E#8 - 4.03E-8 - 1.23E*10 4. 5SE-7 Ru-105 Ru-106 2.BOE-9 _ 5.40E19 - 1.81E*11 3. 54.E8 Rh-103-Rh-106 AS- I10O 6.69E16 6. 19E6 1.22E-7 - 2.52E*9 3.67E+6 Sb-124 1.98E+7 3.74E+S * .80E-4 1.54E*7 5.62E*8 7.85E*6 Sb-125 1.91E-7 2.13E15 1. 94E-4 1.47E17 2.10E18 4. 54E16 Te-125S 3.59E*8 1.30E81 1 08E*8 - 1.46E19 - 1.43E+9 Te-127. 1. 12E-9 3.99E+8. 4. 53E-9 - 3.74E*9 Te-127 1.09E-9 - 2. 10E-J Te-129m 1.14E.9 4.27E*8 3.93E18 4.77E19 - 5.76E*9 Tr-129 Te-131- 4.51E+2 2.21E+2 3.SOE*2 2.24E13 2.19E*4 1.34E+2 Te-131 Te-132 1.40E.6 9.07E1 l 1.00E16 8.731E6 - 4.29E+7 8.51E1S 1-130 2.35E-6 6.94E-6 5.88E-4 1.08E-S - 5.98E-6 2.74E-6 1-131 1.08E.7 1.54E+7 !S.OSE*9 2.64E17 4.07E+6 8.83E*6 1-132 1-133 4.30E-1 7.47E-1l 1.10E*2 1.30E10 - 6.72E-1 2.28E-I FERMI 2 ODCM - TRM VOLUME II 7-36 Rev. 13 I
Table 7.0-4 Raipo, Grass-Cow-Meat Pathway Dose Factors - ADULT (CONT) 3 (mrem/yr per ,Ci/m ) for H-3 and C-14 (m 2 x mrem/yr per LCi/sec) for others Nouclide Sone Liver Thyroid Kidney Luns Cl-LLI T.Sody 1-135 X-13S Cs-134 6. S7E+8 1.56E#9 - S.06E.8 1.68Ei8 2.7AE-7 1.28E+9 Cs-136 1l18#7 A4.67E-7 - 2.60EC7 3.56E.6 5.30E-6 3.36E+7 Cs-137 8.72E+8 1. 19E+9 - A.05E+8 1.35E+8 2.31E+7 7.81E#8 Cs-138 Ba-139 Ba-l1O 2.B8E-7 3.61E+4 - 1.23E-4 2.07E-4 5.92E.7 1.89E-6 Ba- 1AI Ba-142 La-I A 3.60E-2 1.81E-2 - 1.33E-3 4.79E-3 La-142 Ce-14 1 1.OLE+4 9.48E*3 - **OtE+3 _ 3.62E-7 I.08E+3 Ce-143 2.09E-2 - 6.8OE-3 - 5.78E+2 1.71E-3 Ce-144 1.46E+6 6.09E+S _ 3 61E+S _ 4.93E-b 7.83EL4 Pr-143 2.13E+4 8.54t+3 - 4.93E*3 - 9.33EC7 1.06E#3 Pr-I44 Nd-147 7.08E-3 S.18E+3 - 4.78E+3 - 3.93E+7 A.90E+2 W-187 2. 1E-2 1.81E-2 - 5.92E+O 6.32E-3 Np-239 2.56E-1 2. SIE-2 - 7.84E-2 - S.15E+3 1. 39E-2 FERMI 2 ODCM - TRM VOLUME 11 7-37 Rev. 13 l
Table 7.0-4 Raipo, Grass-Cow-Meat Pathway Dose Factors - TEENAGER (mrem/yr per /ICi/m 3 ) for H-3 and C-14 (m 2 x mrem/yr per gICilsec) for others Nuclide 8one Liver Thyroid Kidney Lung CI-LLI T.Body H-3 - 1.94E.2 1.94E+2 1.94E*2 1.94E+2 1.94E*2 t.94E-2 C-t' 2.81E+S 5.62E#4 5.62E+4 5.62E+4 5.62E+4 5.62E+4 5.62E*4 Na-2li 1.47E-3 t.47E-3 1.47E-3 1.47E-3 1.47E-3 1.47E-3 1.47E-3 P-32 3.93E-9 2.44E*8 - - - 3.30t+8 t 52E:8 Cr-St - 3. &E+3 1.24E-3 8.07E13 9.50E+1S S65E 3 Mn-54 - 6.98E16 - 2.08E+6 - 1.43E-7 i.38E.6 Mn-56 _ _
FC-SS 2.35E18 1.69E+8 - - 1.07E+8 7.30E+7 3.93E-7 Fe-59 2.13E.8 4.98E+8 - - I.57E+8 1. 8E*9 1.92E-8 Co-57 - 4.53E*6 - - - 8.45E+7 7.59E-6 Co-58 - 1.41E*7 - 1.94E+8 3.25E7 Co-60 - S.83E+7 - - - 7.60E*8 1.3lE+8 Ni-63 1.52E-1O 1.071+9 - - - 1.71E#8 5.15E.8 Ni-65 _ _ _ _
Cu-64 - 2.41E-7 - 6.10E-7 - 1.87E-S 1.13E-7 Zn-65 2.50E8 8.69E*8 - 5.56E+8 - 3.68E.8 &.OSE+8 Zn-69 - - - - - - -
Br-82 - - - - - - 9.98E*2 8r-t3 - - - *_
Br-84 - - - - - - -
Br-85 - - - - - - -
Rb-86 - 4.06E+B - - - 6.01E*7 1.91E+8 Rb-88 - _ _ _ _
Rb-89 _ _ _ _
Sr-89 2.54E,C - - - - 3.03E-7 7.29E+6 Sr-90 8.0SE+9 - - - - 2.26E*8 1.99E*9 Sr-91 - - - - - 1.10E-9 -
Sr-92 - _ _ _ _ _
Y-90 8.98E+l - - - - 7.4OE*S 2.42E+O Y-91m _ _ _ _ _ _ _
Y-91 9.56E+S - - - - 3.92E+8 2.56E+4 Y-92 - _ _ _
Y-93 - - - - - 1.69E-7 -
Zr-9s I.5IE+6 1.76E+5 - 6.99E*S - 1.IO1E9 3.27E+S Zr-97 1.53E-S 3.02E-6 - 4.58E-6 - 8.18E-1 1.39E-6 hb-95 1.79E#6 9.9'E*S - 9.64E*S - 4.25E-9 5.47E1S Nb-97 -
Mo-99 - 8.98E.4 - 2.06E#5 - 1.61t,5 1.71E-4 IC-99. - _ _ _ _ _ _
Tc-101 - - - - _ _ _
Ru-103 8.60E#7 - - 3.03E+B - 7.18E19 3.68E*7 Ru-tOS _ _ _ _ _ _ _
Ru-106 2.36E19 - - 4.SSE+9 - 1.13E111 2.97E-8 Rh-1031 - - - - - _ _
Rh-106 - _ _ _ _
AS-110 5.06E+6 4.79E.6 - 9.14E-6 - 1.35E+9 2.91E+6 Sb-l24 1.62E+7 2.98E+5 3.67E-4 - 1.41E7 3.26X#8 6.31E*6 Sb-12S 1.S6E+7 1.71E-S 1.49E-4 - 1.37E+7 1.22E18 3.66E+6 Te-t25- 3.03E+8 1.09E-8 8.47E17 - - 8.94E+8 *.OSE-7 Te-127. 9.41E18 3.34E-8 2.24E+8 3.82E+9 - 2.35E9 1.12E18 Te-i27 - - - - - 1.75E-8 -
Te-t29- 9.S8E+B 3.56E+8 3.09E*8 4.01E19 - 3.60E+9 1.52E1t Te-129 _ _ _ _
Te-131- 3.76E*2 1.80E*2 2.711E2 1.88E+3 - 1.451E4 1.50E*2 Te-131 _ _ _ _ _ _ _
T.-132 1.1SE6 7.26E-S 7.66E1S 6.97E6- - 2.30E17 6.t4E*S 1-130 1.89E-6 5.4tE-6 4.47E-4 8.44E-6 - 4.21E-6 2.19E-6 1-131 8.95E+6 1.251+7 3.66E19 2.16E+7 - 2.48E.6 6.73E16 1-132 - - - - _ _ _
1-133 3.59E-1 b.tOE-1 S.511E1 1.07E+0 - 4.61E-1 1.t6E-1 Rev. 13 l FERMI 2 ODCM - TRM VOLUME 11 7-38
Table 7.0-4 Rajpo, Grass-Cow-Meat Pathway Dose Factors - TEENAGER (CONT.)
(mrem/yr per pCi/m3 ) for H-3 and C-14 (m 2 x mrem/yr per ,UCi/sec) for others NucI ide Moat Liver Thyroid Kidney Lun Cl-LJL1 T. Iody r-134 I-t35 Ca-134 5.23E.8 1.23E.9 - 3.91E+8 1.49E+B 1.53E+7 S.71E+8 C. -136 9.22E+6 3.63E.7 - 1.97E*7 3.11E-6 2.921*6 2.44E-7 Cs-137 7. 24E.8 9.63E+8 - 3.28E-8 1.27E+1 1.37E+7 3.36E+8 Cs-138 Bh-139 E.-140 2.38E.7 2. 911.4 - 9.88E+3 1.96E-4 3.67E+7 1. 5316 Ba-141 Bs-142 La-140 2.96E-2 1.4 SE-2 - 8.35E*2 3.87E-3 La-142 Ce-141 1. 18E-4 7.86E+3 - 3.70E,3 - 2.25E-7 9.031*2 Ce-143 1.76E-2 1.28E*1 - 5.74E-3 - 3.85E-2 1.43E-3 Ce- 14. 1. 23E+6 5.08E.S - 3.041E5 - 3.09E*8 6. 60E-4 Pr-143 1. 79+4 7. 15E13 - 4.16E+3 - 5.90E*7 a.92E-2 4
Pr-14 Nd-147 6. 24E-3 6. 79E.3 - 3.98E+3 - 2.45E+7 4.06E*2 W-187 1.81E-2 1.48E-2 _ 3.99E*o 5.17E-3 Np-239 2.23E-1 2. 11E-2 - 6.61E-2 _ 3.39E+3 1.17E-2 FERMI 2 ODCM - TRM VOLUME II 7-39 Rev. 13 l
Table 7.0-4 Raipo, Grass-Cow-Meat Pathway Dose Factors - CHILD (mrem/yr per MCi/m 3 ) for H-3 arnd C-14 (m 2 x mremlyr per ,UCi/sec) for others Nuclide Bone Liver Irhyroid Kidney Luns CI-LLI T. Body m-3 2.34E-2 ;2.34E[2 2.3.E+2 2.34E.2 2.34E*2 2.34E#2 C-14 5.29E#S 1.06E*S 11.06E*S 1.06E[S 1.06E+S 1.06E+S 1.06E[S Na-24 2.34E-3 2. 34E-3 :2.34E-3 2. 34E-3 2.34E-3 2.34E-3 2.34E-3 P-32 7.41E*9 3.47E[.8 - 2.0SE+8 2.86E-8 Cr-Sl _ Ii.89E-3 1.34E-3 8.93E[3 4.67EZS 8.8 E.3 hn-54 7.99E*6 2.24E*6 - 6.7OE.6 2.13E+6 Mn-56 Fe-55 4.57£-8 2.4;2E+ 1.37E-8 4.49E+7 7.5IE-7 FC-59 3.78E 8 6.12E+8 1.77E.8 6.37E+8 3.OSE*8 Co-57 5.92E.6 - 4.85E-7 1.20E#7 Co-58 1.65E+7 - 9.60E*7 5.04E.7 Co-60 6.93E+7 - 3.84E+8 2.04E-8 Ni-63 2.91E. 10 1.56E-9 - t.OSE+8 9.91[E8 Ni-65 Cu-64 3.2;E-7 - 7.82E-7 - 1.52E-S 1.96E-7 Zn-65 3.7SE+8 1.oaE.9 - 6.30E[t - 1.76E.8 6.22E+B 9
Zn-6 2
Br-B 1.56E.3 8r-83 4
Br-6 Br-85 Rb-86 * - 5.76E.8 - - - 3.71E*7 3.54E-8 Rb-88 Rb-89 Sr-89 4.82Er8 - - - - 1.86E*7 1. 38E+7 Sr-90 1.04E#10 - - - - 1.40E.8 2.6'E.9 Sr-91 _ - - - - 1.oE-9 Sr-92 Y-90 1.70E*2 - - - - 4.84E+S 4.55E+O Y Y-91 1.81E*6 - 2.41E+8 4.83E.4 Y-92 Y-93 2.6B_ s.89[.5 - I.SSE-7 Zr-95 2.68E-6 - .43E*S - 6.14E-8 5.24E[S Zr-97 2.84E-S '. IO[-6 - 5.89E-6 - 6.21E-1 2.42E-6 Nb-95 3.09E+6 1.20E+6 - t.13E+6 - 2.23E+9 8.61E-S Nb-97 Ho-99 1.25E+S - 2.67E+S - 1.03E+S 3.09E+4 Tc-990 Tc-t01 Ru-103 1. 56E 8 - 3.92E-8 - 4.0[E.9 5.98E+7 Ru-105 Ru- 106 4.44E.9 _ 5.99E+9 -6.90E+ 10 5.54E1.
Rh-103.
Rh-106 AS-IIOn 8.40E+6 5.67E+6 1.06E+7 6.75E*8 4.53E+6 Sb-I24 2.93E-7 3.80E.S 6.t.6[E' 1.*62E[.7 1.83E+8 1 .03E-7 Sb-125 2.8SE-7 2. 19E[S 2.64E-4 1.59E[7 6.80E+7 5.96E.6 Te-125m 5.69E.8 1.54E+8 1.60Et8 5.49E+8 7.59E+7 Te-127- 1.77E[9 4.78E-B 4.24E-8 5.06E-9 1.44E19 2. 11E[.
Te-127 1.2 1E-9 1.66E-t 9
Te-12 m 1.8lES9 5.04E-8 5.82E.8 5.30E-9 2.20E-9 2.80E[
Te-129 Te-131- 7.00E*2 2.42E[2 4. 98E.2 2. 34E[3 - 9.92E.3 2. 58E2 Te-i3l
.- 6 Te-132 2.09E-6 9.27E[S 8.60E.6 9.33E[6 1.12E[6 1-130 3.19E-6 6.8 SE-b 7.54E:-4 1.02E-S - 3.20E-6 3.53E-b 1-131 1.66E-7 1.67E*7 S.S2E.9 2.74E[7 - 1.49E16 9.49E-o 1-132 1-131 6.68E-1 t.26E-1 . SIL.2 1.38E0 - 3.33E-1 3. 12E-1 FERMI 2 ODCM - TRM VOLUME II 7-40 Rev. 13 l
Table 7.0-4 Raipo, Grass-Cow-Meat Pathway Dose Factors - CHILD (CONT.)
(mrem/yr per /UCi/m3 ) for H-3 and C-14 (m- x mrem/yr per /lCilsec) for others NuCl ide mone Liver Thyroid Kidney LYUn Cl-LLJ S.Sody I-134 I-135 CS-134 9.22E*8 l.SIE-9 - .4.69E.8 1.69E*8 8ASE#6 3.19E.8 Cs-136 t. 59EI7 * .37E#7 - 2.33E.7 3.4.7E.6 1.54E.6 2. 3E#7 Cs-137 1.33E.9 1.28E#9 - 4.16E!8 1.S0E+8 7.99E+6 1.88E+8 Cs-138 Ba-139
&*-lAO '.39E.7 3. SE+4 1.25E.4 2.29E4' 2.22E.7 2.56E*6 Ia-1'.1 5i-142 L a-40 S 41E-2 1.89E-2 - 5.27!+2 6. 3SE-3 LA-1'2 Ce-1I4 2.22E+4 1. 1.E+4 _ 4.S4E-3 - 1.38!E7 1.64E+3 Ce-143 3.30E-2 1.79E!l - 7.S1E-3 - 2.62E+2 2.59E-3 Ce-144 2.32E.6 7.26E+S - 4.02E S - 1.89E+8 1.24E+S Pr-143 3.39E*4 1.02E-4 - S.S1!E3 - 3.66E-7 1.68E#3 Pr-1A' Nd- 147 1. 17E+4 9.48E.3 - 5.20E-3 - 1.50E+7 7.34E+2 W-187 3.36E-2 1.99E-2 - 2.79E+0 8.92E-3 NP-239 4. 20E-1 3.02E-2 - 8.73E-2 - 2.23E,3 2.12E-2 FERMI 2 ODCM - TRM VOLUME 11 7-41 Rev. 13 l
Table 7.0-4 Raipo. Vegetation Pathway Dose Factors - ADULT (mremlvr per pCi/m3 ) for H-3 and C-14 (m 2 x mrem/yr per JlCi/sec) for others Nuclide Bone Liver Thyroid. Kidney Lung Cl-IL1 T.Body H-3 _ 2.26Et3 2.26E.3 2.26E.3 2.26E!3 2.26E-3 2.26E!3 C-14 8.97E-5 1.79E#S 1.79E.5 1.79E.5 1.79E.S 1.79E+S 1.79E-S Na-24 2.76E-S 2.76EtS 2.76E1S 2.76E+S 2.76E#S 2.76E+S 2.76E-S P-32 i.4aO19 8.73E!7 - - - 1.S8E18 5.42E-7 Cr-Sl - - 2.79E-'. 1.03E+4 6.19.-4 1. 71+7 4.66E-4
)in-54 - 3.11E-8 - 9.27E-7 - 9.54E+8 5.94E!7 Mn-56 - 1.61E!i - 2.04E11 - 5.13E.2 2.85E-0 Fe-SS 2.09E-8 i1.ASE+8 - 8.06E.7 8.29E17 3.37E?7 Fe-59 1.27E18 2.99E+8 - - 8.35E-7 9.96E+8 1.14E-8 Co-S7 - 1.17E-7 - - 2.97E*8 1.95E!7 Co-58 - 3.09E-7 - - - 6.26E+8 6.92E!7 Co-60 - 1.67!.E - - - 3.14E.9 3.69E+8 Ni-63 1.04E+10 7.21E+8 - - - 1.S0E18 3.49E#8 Nl-65 6.15Evi 7.99E+0 - - - 2.03E+2 3.65E-0 Cu-64 - 9.27E-3 - 2.34E+4 - 7.90E15 4.35E!3 Zn-65 3.17E+8 l.OlE-9 - 6.75E+8 - 6.36E+8 4.56E#8 Zn-69 8.75E-6 1.67E-5 - 1.09E-S - 2.51E-6 1.16E-6 Br-82 - - - - - 1.73E46 1.51!E6 Br-83 - - - - - - 4.63E.O 3.21E+O Br-84 - - - - - - -
Br-85 - - - - - - -
Rb-86 - 2.19E-8 - - - 4.32E-7 1.02E+8 Rb-8E _ _ _
Rb-89 - . _ _ _ _ _
Sr-89 9.96E.9 - - - - 1.60E-9 2.86E*8 Sr-90 6.05E#11 - - - - 1.75E+10 1.48E111 Sr-91 3.20E#5 - - - - 1.52E.6 1.29E.4 Sr-92 4.27E+2 - - - - 8.46E+3 1.85E+1 Y-90 1.33E4 - - - - 1.41E+8 3.56E+2 Y S.83E-9 - - - - 1.71E-8 -
Y-91 5.13E+6 - - - - 2.82E+9 1.37E.S Y-92 9.01E-1 - - - - 1.58E.4 2.63E-2 Y-93 1.74E!2 - - - - 5.52E-6 4..aE+O Zr-9S 1.19E-6 3.81E+S - 5.97E+S - 1.21E-9 2.58E15 Zr-97 .3.33E+2 6.73E+1 - 1.02E!2 - 2.08E!7. 3.08E*1 Nb-95 1.42E+S 7.91E+4 - 7.81E+4 - 4.80E-8 4.25E.'
Nb-97 2.90E-6 7.34E-7 - 8.56Er7 - - 2.71E-3 2.68E-7 Mo-99 - 6.25E*6 - 1.41E+7 - 1.45E?7 1.19E-6 Tc-99% 3.06E*0 8.66E*0 - 1.32E.2 4.24E-o S.12E*3 1.101E+
TC-101 - - -
Ru-101 4.80E+6. - 1.83E!7 - S.61E+8 2.07E.6 Ru-lOS 5.391+1 - - 6.96E!2 - 3.30E-4 2.13E#1 Ru-106 1.93E#8 - - 3.72E*S - 1.25L+10 2.44E17 Rh-103a - - _ _
RN-106 - - - - - - -
Ag-liO- 1.06E-7 9.76E-6 - 1.92E+7 - 3.98E+9 5.80E16 Sb-i24 1.04E.8 1.96E16 2.S2E!S - . 8.08E!7 2.95E9 4.llE-7 Sb-125 1.36E18 1.52E.6 .1.39E1S - I.DSE.8 I.SOE+9 3.25E!7 Te-125m 9.66E-7 3.50ES7 2.90E-7 3.93E-8 - 3.86E.8 1.29E!7 Te-127m 3.k9E18 1.25E8 8.92E?7 1.42E.9 - 1.17E-9 4.26E-7 Te-127 5.76E13 2.07E?3 *.27E-3 2.35E.' - 4.54E.S 1.25E-3 Te-129m 2.5SE18 9.50E!7 8.75E-7 1.06E.9 - 1.28E-9 4.03E-7 Te-129 6.65E-4 2.50E-4 S.10E-4 2.79E-3 - 5.02E-4 1.62E-4 Te-131- 9.12E1S 4.46E!S 7.06&.S 4.52E-6 - 4.43E!7 3.72E1S Te-131 - _ _ _ _ _ _
Te-132 4.29E.6 2.77E*6 3.06E.6 2.67E?7 - 1.31E-8 2.60E-6 1-130 3.96E-S 1.17E.6 9.901?7 1.82E-6 - t.01E-6 4.61E-S 1-131 8.09E!7 1.16E*8 3.79E10 1.98E+8 - 3.0SE.7 6.63E!7 1-132 5.74E11 1.54E!2 5.38E!3 2.45E!2 - 2.89E+1 5.38E*1 1-133 2.1ZEU6 3.69E!6 5.42E-9 6.44E16 - 3.31E.6 1.12E.6 FERMI 2 ODCM - TRM VOLUME II 7-42 Rev. 13
Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - ADULT (CONT.)
(mrem/yr per uCi/m3 ) for H-3 and C-14 (M 2 x rnrern/yr per UICilsec) for others ttucl ide Moe Liver Thyroid Kidney Lung Cl -LU J. tody I-134 1.06E-4 2.88 E-4 5.OOE-3 4.59E-4 2.5 1E-7 1.03E-4 1-135 4.088E.4 1.07E1S 7.04E+6 1.71E*S 1.21E1S 3.94 E-'
CS-134 4.661*9 1. 11.10 3. 59E#9 1. 19E-9 1.95E.8 9.07E.9 CS-136 *.20E17 1.66E.8 9. 24E+7 1.27E17 1.89E+7 1. 19E-8 C.-137 6.36E#9 8.70E.9 2.95E*9 9.81E,8 1.68E+8 S. 70E19 C.-138 a-1I39 2.9SE-2 2. 10E-S 1.96E-S 1. 19E-S S.23E-2 8.63E-1 Ba-140 1.29E.8 1.62E+5 - 5.1.9E14 9.25E14 2. 65E-8 8.4s3E+6 la-141 5a-t12 LA-140 1.97E+3 9.92E+2 - 7.28E17 2.62E+2 La-142 1.401-4 6.35E-S - 4.64E-1 1.58E-5 Ce-141 1.96E+S 1.33E+S - 6.17E1. - 5.08E+8 1.5 1E.4 Ce-143 I.OOE3 7.42E1S - 3.26E+2 - 2.77E+7 8.21E#1 Ce-144 3.29E.7 1.38E+7 - B.16E16 - 1.1 E+110 i.77E+6 Pr-143 6.34E+4 2.54E+. - 1.47E.4 - 2.78E+8 3. 14E13 Pr-144 Nd-147 3.34E+4 3.86E+4 - 2.25E+. - 1.85E+8 2.31E+3 U-187 3.82E14 3.19E14 - 1.05*E7 1.12E14 Np-239 1.42L+3 1.40E+2 - * .37E+2 - 2.87E-7 7.72E+1 FERMI 2 ODCM - TRM VOLUME II 7-43 Rev. 13 l
-Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - TEENAGER (mrem/yr per llCi/m 3 ) for H-3 and C-14 (m2 x mrem/yr per plCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lunr CI-LLI T.Body H-3 2.59E+3 2.59E#3 2.59Z.3 2.59E£3 2.S9E#3 2. 59E.3 C-14 1.4SE+6 2.91E#S 2.91E-S 2.91E+S 2.91E+S 2.91E.S 2.91E+S Na-24 2.45ES 2.45ES 2.4 SE. 2.45E*S 2.4 SE+5 2.45E-S 2.45E- 5 P-32 1.61E.9 9.96E£7 1.3 E#8 6.23E+7 Cr-Sl 3.44E-4 1.36£E.4 8.SE.4 1.04E.7 6.20E+4 Mn-54 4.52E+8 - 1.35E-8 9.27E[8 8.97E-7 Mn-56 1.45E+ I - 1.83E+1 9. 54E+2 2.58E+O Fe-55 3.25E+8 2.31 E-8 1 .46E-8 9.98E57 5.38E+7 Fe-S9 1.81E8S 4.22E+8 1.13E+8 9.98E*8 1.63E+8 Co-57 1.79E+7 3.34E-S 3.00E.7 l3.OOE+7 Co-S8 4.38E.7 - 6.04E+8 1.01E#8 Co-60 2.49E*B - 3.24E+9 5.60E#8 Hi-63 1.6 lEtO 1.13E.9 - I.81E*8 S.I SE.8 Ni-65 5 73E£1 7.32E.0 - 3.97E+2 3.33 E.0 Cu-64 8.40E.3 - 2.12E.4 - 6.51E+S 3.95E+3 Zn-65 4. 24 E[. 1.47E+9 - 9.4 1[.S - 6.23E+8 6.86E+8 Zn-69 S.19E-6 1.56E-S - 1.02E-S - 2.88E-S 1.09E-6 Br-82 1.33E+6 Br-83 3.01E*O Br-84 Br-85 Rb-86 2.173E+8 - - - 4.0SE*7 1.28E-8 Rb-88 Rb-S9 Sr-89 l.SlE-10 - - - - 1.80£E9 4.33E#8 Sr-90 7.51E-11 - - - - 2.11E-10 1. 5SE-l I Sr-91 2.99E.S - - - - 1.36E-6 1.19E-4 Sr-92 3.97E+2 - - - - 1.OIE.4 1.69E+1 Y-90 1.24E+4 - - - - 1.02E+8 3.3&E+2 Y 5.43E-9 - - - - 2.56E-7 Y-91 7.87E+6 - 3.23E+9 2. 11E+5 Y-992 B.47E-1 - 2.32E*4 2.45E-2 Y-93 1.63E£2 - 4.98E+6 4. 47E[0 Zr-95 1.74E.6 5.49E-S - 8.07E-S - 1.27E+9 3.7BE+S Zr-97 3.09E1+2 6.11IE1 - 9.26E*1 - 1.65E.7 2.81£+1 Nb-95 1.92E.S 1.06E.S - 1.03E.S - 4.SSE.8 S.86E.4 Nb-97 2.69E-6 6.67 E-7 - 7.80E-7 - 1.59E-2 2.44E-7 Ho-99 5.74E-6 _ 1.31E-7 - 1.03E+7 1.09E#6 Tc-99. 2.70E0 7.54E+O - 1.12E.2 4.19E+0 4.95E-3 9.77E+1 Tc-10t Ru-103 6.87E.6 - 2. 42E-7 - 5.74E*8 2.94[E6 Ru-105 5.00 E+1 - 6.31E#2 - 4.04E.4 1.94 [E1 Ru- 106 3.09E.8 - S.97E.8 - 1.48E-10 3.90E£7 Rh-103-Rh-106 A -1 10- 1.52E.7 1.44E-7 - 2.74E+7 4.04E£9 8.74E-6 Sb-124 1.SSE*8 2.8 SE-6 3.SlE+S - 3. 11E9 6.03E£7 Sb-125 2. 14Et8 2.34E-6 2.04E[5 - 1.3SE-B t .SSE.5 1.66E[9 5.OOE7 Te-125- 1.48E-8 5.34E*7 4.14E-7 - 4.37E.S 1.98E.7 TC-127. S.S1E*8 1.96E[8 1.31E.8 2.24E-9 1.37Et9 6.56E[7 Te-127 5 43E.3 1.92E.3 3.74E.3 2.20E£4 - 4.19E+5 1. 17E#3 Te-129m 3.67E.8 1. 36E.8 1. 1SE.8 1. S4E-9 - 1.38E-9 5.81E17 Te-129 6.22E-4 2.32E-4 .4 SE-4 2.61E-3 - 3. 40E-3 1.SIE-4 Te-131- 8.44E+S 4.0 SE-S 6.09E£ S 4.22E£6 - 3.25E+. 3.38E£ S Te-131 Te- 132 3.90E.6 2. 47E[6 2.60E.6 2.37E£7 - 7.82E.7 2.32E.6 1-130 3.54E#S 8.35E.7 1.58E56 - 7.87E.S 4.09E+S 2-131 7.70E.7 1.08E*B 3.14E£ 10 1.8 SE-8 - 2.13E£7 5.79E£7 2-132 5.1E£. I 1.36E[2 4.57E#3 2. 14E.2 - 5.91E.1 4.87E£1 1-133 1.97E.6 3.34E-6 4.66E*8 S.86E#6 - 2.53E[6 1.02E.6 FERMI 2 ODCM - TRM VOLUME 11 7-44 Rev. 13 l
Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - TEENAGER (CONT.)
(mremlyr per ,llCi/m 3 ) for H-3 and C-14 (m 2 x mrem/yr per ,Cilsec) for others luclide ACDC Liver Shyrold Kidney Lunt CI-Lu T.Body 1-134 9. 59E-5 2. 54E-4 4 .24E-3 4.011-4 3. 35E-6 9.13E-S 1-135 3.68E+4 9.48E+4 6. 10E.6 1.50E+S 1.05E+S 3. S2E-1 C.-134 7.09E.9 1.67E+10 5. 301.9 2.02E.9 2.08E-8 7.74E.9 CS-136 4. 29E.7 1. 69E+8 9.19E17 1.45E.7 1.36E-7 1. 13E.8 Cs-137 1.0 1E110 1.35E.10 4.59E*9 1.78E.9 1. 92£-8 4.69E-9 Cs-138 la-139 2.77E-2 1.95E-S _ 1.84E-5 1. 34E-5 2.47E-1 8.08E-4
.- 140 1.38E+8 1.69E+S _ 5.75E*4 1. 141*S 2.13E+d 8.M91.6 BS-141 Ba-142 La-140 1.80E13 8. 84E.2 - 5.08E+7 2.35E.2 La-142 1.28 E-4 5.69E-S - 1.73E+O 1.42E-S Ce-141 2. 82E1S 1.88E+S - 8.86E+4 - 5.38E-8 2.16E.4 Ce- 143 9.37E+2 6.82E1S - 3.06E+2 - 2.05t+7 7.62E+1 Ce-144 5.27E-7 2.18E+7 _ 1.30E-7 _ 1.33E+10 2. t3E-6 Pr-143 7. 12E-4 2.84E-4 - 1.65E+4 - 2.34E+8 3. 55E.3 Pr-144 Nd-147 3.63E.4 3.94 E+4 - 2.32E+4 - 1.42E+8 2.36E+3 W-187 3. 55E+4 2.90E+4 - 7.84E+6 1.02E.4 hp-239 1.38E+3 1.30E.2 - 4.09E+2 - 2.10E+7 7.24E#1 FERMI 2 ODCM - TRM VOLUME II 7-45 Rev. 13 l
Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - CHILD C(mrem/yr per pCi/m3 ) for H-3 and C-14 (m 2 x mrem/yr per p Cilsec) for others Nuclide Bone Liver Thyroid Kidney Lunx cl-ULI T.Body r-3 4.01E.3 4.01E-3 4.01E+3 '.OE13 4.01E*3 4.012E3 C-i4 3. S5E+6 7.01E2S 7.01E.5 7.01E.5 7.01E*5 7.01E2S 7.01E2S Ha-24 3.83E+5 3.83E+S 3.83E+S 3.83E+5 3.83E2S 3.83E+S 3.83E-S r-32 3. 37E*9 1.58E,8 9. 30E-7 t.30E-8 Cr-SI 6.52E-4 1.79E24 1.19E2S 6.25E-6 I .18E-S 1n-54 6.6 1E8 - 1.85E-8 - S. SSE.8 1.76E*8 mn-56 t.90E.1 - 2.292*1 - 2. 75E+3 4.28E-0 Fe-SS 8. 00E8 4. 24E.8 - - 2.40E.8 7.86E-7 1.31E.8 Fe-59 4.01E28 6.49E#8 - - 1.88E+8 6.76E*8 3.23E-8 Co-57 2. 99E-7 2. 45E+8 6.04E27 Co-58 6.1 7E-7 - 3.77E-8 1.98E*8 Co-60 3. 78E+8 - 2. 10E*9 1. 12E+9 Ni-63 3.95E.10 2. 11E+9 - 1.42E+8 1.34E+9 Ni-65 1 .052E2 9.892.0 - 1.21E*3 5.77E*0 Cu-64 1. 11.E+ - 2.68E-4 - 5.20E*S 6.69E+3 Zn-65 8. 12+8 2. 16E-9 - 1.36E+9' - 3.80Z+8 1.35E+9 Zn-69 1. 51E-5 2. 1BE-5 - 1.32E-S - 1.38E-3 2.02E-6 Br-62 - - 2.04E26 Br-83 _ - 5.55E+O Br-84 Br-85 Rb-86 4 .52E*8 - - - 2.91E*7 2.782*8 Rb-88 Rb-89 Sr-89 3.59E.10 _ _ - - 1.39E+9 1.03E-9 Sr-90 1.24E#12 _ _ - 1.67E*10 3. 15E+ II Sr-91 S.SOE+S - - - - 1.21E,6 2.08E-4 Sr-92 7.28E*2 - - - - 1.38*1. 2.92E-1 Y-90 2.30E-4 _ _ - - 6.56E+7 6.17E+2 Y-91. 9.94E-9 _ _ - - 1.95E-5 Y-91 1.87E+7 - - - - 2.49E*9 5.012ES Y-92 1. 56E+O _ _ _ _ 4.51*E4 4. 46E-2 Y-93 3,01E*2 - - - 4.48E*6 8.25E-0 Zr-95 3. 90E-6 8 .58E+S - 1.23E+6 - 8.95E*8 7.64E2S Zr-97 5. 64E+2 a .1SE#1 - 1.17E*2 - 1.23E-7 4.81E+1 Nb-95 4. 10E.S 1.59E-S - - 1.SOE2S - 2.95E-8 1. 14E2S Nb-97 4.90E-6 8.85E-7 - 9.t2E-7 - 2.73E-t 4.13E-7 Ho-99 7.83E-6 - 1.67E;7 - 6.48E*6 1.94E+6 Tc-99% 4. 65E.0 9.12E+O - 1.33E*2 4.6 3E*0 5.19E*3 1.512*2 Tc-101 Ru-103 1. 55E-7 - 3.89E27 - 3.99E-8 15.94E.6 Ru-105 9. 17E21 - 8.06E*2 - S.98E-4 3.33E-1 Ru-106 7.5AE-8 - 1.012E9 - 1.16E#40 9.30E-7 Rh-103m Rh-106 A-1 10- 3.22E2.7 2. 17E27 4.OSE07 - 2.58E+9 1.74E27 Sb-124 3. 52E+8 &.57E26 7.78EOS 1.5P6E+8 2.20E29 1.23E-8 Sb-t25 4. 99E.8 3.85E*6 4. 61E#S 2.7 78E28 1.19E29 1.OSE08 Te-125- 3. 51E-8 9. 502E7 9. 84E+7 - 3.38E28 4.67E*7 Te-127m 1.32E.9 3. 56E28 3.16E28 3.77E29 - 1.07E-9 11.57E28 Te-127 l.0E04 2. 70E*3 6. 93E*3 2.85*E4 - 3.91E25 2.15E-3
-Te-129m 8. 54E.8 2. 39E28 2.75E28 2.51E29 - 1.04E+9 1.33E-8 Te-129 1.1SE-3 3.22E-4 8.22E-4 3.37E-3 - 7.17E-2 2.74E-4 Te-131. 1.54E2. S.33E-S 1.10E26 5.16E*6 - 2.16E+7 5.68E6S Te-131 Te-132 6.98E-6 3.09E.6 4. SOE6 2.87E27 - 3.11E*7 3.73E-6 1-130 6.21E-S 1.26E-6 1. 38E*8 1. 88E-6 _ 5.87E*S 6.47E S 1-131 1.43E+8 1.44E28 4.76E*10 2.36E28 _ 1.28E27 8.182M7 1-132 9.20E21 1.69E 2 7. 84E+3 2. 59E+2 - 1.99E+2 7.77E21 1-133 3.59E26 4.44E2b 8.25E2* 7. 40E*6 - 1.79E*6 1.68E+6 FERMI 2 ODCM - TRM VOLUME II 7-46 Rev. 13
Table 7.0-4 Raipo. Vegetation Pathway Dose Factors - CHILD (CONT.)
(mrem/yr per pCi/m3 ) for H-3 and C-14
. (m 2 x mrem/yr per yCisec) for others Nuclide 1004 Liver Thyroid Kidney Lung Cl-LI. S. lody 1-135 1.70E-4 3 16E-4 7.28E-3 .. 848-4 2.10E-4 1.66E-4 I-135 6.54E*. 1.18E+5 1.04E1.7 8.98E.4 5.57E14 1.60E110 2.63E110 8.14E+9 2.92E+9 1.42E1. 5.54E-9 Cs-136 8.06E 7 2.22E+8 1. I8E-S 1.76E17 7.79E.6 1.4 3E.8 Cs-137 2.39E+10 2.29E#10 7.1.6E-9 2.68E-9 1.43E-. 3.38E-9 Cs-133 Ia-139 5. 11E-2 2.73E-S - 2.38E-S 1.61E-S 2.95E-O 1.48E-3 Ia-140 2. 77E1. 2. 43E+S - 7.90E+. 1. 4SE.S 1. 401*8 1 . 62E.7 Ba-161 la-142 La-140 3.23E.3 1. 13E+3 _ 3. SE-7 3.811.2 La-142 2.32E-4 7.40E-S - 1.471*1 2.32E-S Cc-141 1.23E S 6. 14E+4 - 2.69E*4 _ 7.66E-7 9. 12E-3 Ce-143 1.73E 3 9.36E1S - 3.931E2 - 1.37E-7 1.36E.2 ce-144 1.27.+8 3.98E*7 - 2.21E#7 - 1.04E-10 6.78E+6 It Pr-143 1.48E+S 4.46E+4 - 2.4 1E+4 - 1.60E.8 7.37E*3 Pr-144 Nd-147 7. 16E14 5.80E4 : 3.18E+4 _ 9.18E7 4.k9E+3 W-187 6.47E-4 3.33E+4 - 5.38E-6 1.72E+4 lip-239 2.55E+3 1.83E+2 - 5.30E-2 - 1.36E-7 1.29E.2 FERMI 2 ODCM - TRM VOLUME 11 +7-47 Rev. 13 l
Table 7.0-4 Raipo, Ground Plane Pathway Dose Factors (m 2 x mrem/yr per JlCi/sec)
Nuclide Any Organ H-3 -
C-U -
Na-24 1.21E-7 P-32 -
Cr-51 4.68E-6 Hn-54 1.34E-9 Hn-56 9.05E+S re-5S-Fe-59 2.75E+B Co-58 3.82E+8 Co-60 2.16E-10 Ni-63 _
Ni-65 2.97E+S Cu-64 6.09E.5 Zn-65 7.45E-8 Zn-69 -
Br-83 4.89E+3 Br-84 2.03E-S 8r-8S -
Rb-86 8.98E#6 Rb-88 3.29E-4 Rb-89 1.21E+S Sr-89 2.16E+.
Sr-90 _
Sr-91 2.19E+6 Sr-92 7.77E:S Y-90 4.48E-3 Y-91f 1.OIE+S Y-91 1.08E+6 Y-92 1.8OE+S Y-93 1.85EeS Zr-9S 2.48E+8 Zr-97 2.94E+6 Nb-95 1.36E+8 Ho-99 4.O5E#6 Tc-99m 1.83E-S Tc-101 2.04E#4 Ru-103 1.09Er8 Ru-lOS 6.36E+S Ru-106 4.21E#B Rh-103m Rh-106 -
AM-110- 3.47E.9 Te-125m I.SSE*6 Te-127- 9.17E-4 Te-127 3.OOE-3 Tc-J29m 2.oOE:7 Te-129 2.60E-4 Te-131- 8.03E-6 T -131 2.93E-4 Te-132 4.22E.6 I-130 5.53E+6 1-131 1.72E*7 1-132 1.24E'6 1-133 2.47E-6 1-13' 4.49E-5 1-135 2.56E#6 Cs-134 6.75E+9 C.-136 1.49E+8 Cs-137 1.04E.10 FERMI 2 ODCM - TRM VOLUME II 7-48 Rev. 13
Table 7.0-4 Raipo' Ground Plane Pathway Dose Factors (CONT.)
(M2 x mrem/yr per jUCi/sec) muclide Any OrgAz Cs-138 3.59E*5 Ba-139 1.06E+5S Ba-140 2.OSE#7 la-141 4. lIE.4 ha-142 4.49E+4 La-140 1.91E 7 La-142 7.36E#5 Ce-141 1.36E.7 Ce-143 2.32E+6 Ce-144
~~6.95E-7 Pr-143 Pr-144 1.83E+3 Nd-11.7 8.40E.6 W-187~~
~~2.36E+6 Np-239 1.71E*6 FERMI 2 ODCM - TRM VOLUME II 7-49 Rev..1 3 . I~~
FIGURE 7.01 GASEOUS RADIOACTIVE EFFLUENT MONITORING AND VENTILATION SYSTEMS DIAGRAM i Key ItPA Fiter 0
RCarelm-toict nn LtrU WArUw Off Gas n- r.A~nl--
I.J-V flJ^ L^Jw Irp nWIPAnr NOTE: The HEPA and charcoal filters identified on the Standby Gas Treatment System (SGTS) are engineered safety features and are not considered Ventilation Exhaust Treatment Systems (VETS). No effluent reduction was credited in the UFSAR 10CFR50 Appendix I evaluation for filters installed in plant ventilation systems. Fermi 2 conforms to 10CFR50 Appendix I without filtration installed.
FERMI 2 ODCM - TRM VOLUME II 7 50 END)OF SECTION 7.0 Rev. 13 I
SECTION 8.0 SPECIAL DOSE ANALYSIS FERMI 2 ODCM - TRM VOLUME II 8-1 Rev. 13
8.0 SPECIAL DOSE ANALYSES 8.1 Doses Due to Activities inside the SITE BOUNDARY In accordance with ODCM 5.9.1.8, the Annual Radioactive Effluent Release Report submitted prior to May 1 of each year shall include an assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.
Two locations within the Fermi 2 SITE BOUNDARY are accessible to MEMBERS OF THE PUBLIC for activities unrelated to Detroit Edison operational and support activities. One is the over-water portion of the SITE BOUNDARY due east of the plant. Ice fishermen sometimes fish here during the winter. The other is the Fermi 2 Visitor's Center, outside the protected area (but inside the Owner Controlled Area), approximately 470 meters SSW of the Reactor Building. The Visitor's Center is open to the public and is routinely visited by MEMBERS OF THE PUBLIC, including school tour groups on a frequency of once per year.
Conservative assumptions of locations, exposure times, and exposure pathways for assessing doses from gaseous and liquid effluents due to activities inside the SITE BOUNDARY are presented in Table 8.0-1. The calculational methods presented in ODCM Sections 7.6 and 7.7 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC based on the above assumptions. Alternatively, the effluent concentration values of Appendix B, Table 2, of the revised 10 CFR Part 20 may be used to assess dose since these concentrations, if continuously inhaled or ingested, produce a total effective dose equivalent of 50 mrem per year.
The potential dose from the fish pathway to a MEMBER OF THE PUBLIC engaged in ice fishing within the SITE BOUNDARY is accounted for by the modeling presented in ODCM Section 6.5. Therefore, no additional special dose analyses are required for this exposure pathway for reporting in the Annual Radioactive Effluent Release Report.
8.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 The Annual Radioactive Effluent Release Report shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (including dose contributions from effluents and direct radiation from onsite sources).. For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of the Fermi 2 site, the sources of exposure need consider only the radioactive effluents and direct exposure contribution from Fermi 2.
No other fuel cycle facilities contribute significantly to the cumulative dose to a MEMBER OF THE PUBLIC in the immediate vicinity of the site. Davis-Besse is the closest fuel cycle facility located about 20 miles to the SSE. Due to environmental dispersion, any routine releases from Davis-Besse would contribute insignificantly to the potential doses in the vicinity of Fermi 2.
As appropriate for demonstrating/evaluating compliance with the limits of ODCM 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used to provide data on actual measured levels of radioactive material in the actual pathways of exposure.
FERMI 2 ODCM - TRM VOLUME II 8-2 Rev. 13
8.2.1 Effluent Dose Calculations For purposes of implementing the surveillance requirements of ODCM 3.11.4 and the reporting requirements of ODCM 5.9.1.8, dose calculations for Fermi 2 may be performed using the calculational methods contained within this ODCM and the conservative controlling pathways and locations of Table 7.0-3. Liquid pathway doses may be calculated using Equation (6-10). Doses due to releases of radioiodines, tritium and particulates may be calculated based on Equation (7-14).
The following equations may be used for calculating the doses to MEMBERS OF THE PUBLIC from releases of noble gases. Equation (8-2) is not used for evaluating compliance with 40 CFR Part 190, since this regulation does not address skin dose. If noble gases are being released from more than one point, these equations must be used to evaluate each release point separately, and then the doses must be added to obtain the total noble gas dose.
Dtb = 3.17E-08* X/Q *E(K
Q)
~~(8-1) and Ds= 3.17E-08* X/Q *Z1(L +l.lM.)~~
Q]
(8-2) where:
Dtb = total body dose due to gamma emissions for noble gas radionuclides (mrem)
Ds = skin dose due to gamma and beta emissions for noble gas radionuclides (mrad)
X/Q = atmospheric dispersion to the offsite location (sec/m 3 )
Q- cumulative release of noble gas radionuclide i over the period of interest (pCi)--may be determined according to Equation (7-8) 1.67E + 01 - (1E + 03 ml/liter) * (1 min/60 sec)
FERMI 2 ODCM - TRM VOLUME II 8-3 Rev. 13
K= total body dose factor due to gamma emissions from noble gas radionuclide i (mrem/yr per pCi/m 3)
(from Table 7.0-2)
Li = skin dose factor due to beta emissions from noble gas radionuclide i (mrem/yr per pCi/m 3) (from Table 7.0-2)
Mi = gamma air dose factor for noble gas radionuclide i (mrad/yr per puCi/m 3 ) (from Table 7.0-2) 1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad) 3.17 E - 08 = 1/3.15 E + 07 yr/sec Average annual meterological dispersion parameters or meterological conditions concurrent with the release period under evaluation may be used (e.g., quarterly averages or year-specific annual averages).
8.2.2 Direct Exposure Dose Determination From evaluations performed in the Fermi 2 Environmental Report, Section 5.3.4, the direct exposure to the highest offsite location from the Turbine Building N-16 skyshine dose has been calculated to be approximately 3 mrem/year. The introduction of hydrogen injection at Fermi 2 in 1997 (hydrogen water chemistry) tends to increase direct exposure. Direct exposure to offsite or onsite individuals may be evaluated based on the results of environmental measurements (e.g.
area TLD and survey meter data) or by the use of a radiation transport and shielding calculational method. Only during atypical conditions will there exist any potential for significant onsite sources at Fermi 2 that would yield potentially significant offsite doses to a MEMBER OF THE PUBLIC. However, should a situation exist whereby the direct exposure contribution is potentially significant, onsite measurements, offsite measurements and calculational techniques will be used for determination of dose for assessing 40 CFR 190 compliance. The calculational techniques will be identified, reviewed, and approved at that time, and Will be included in any report on doses due to such atypical conditions.
8.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data Normally, the assessment of potential doses to MEMBERS OF THE PUBLIC must be calculated based on the measured radioactive effluents at the plant.
The resultant levels of radioactive material in the offsite environment are usually so minute as to be undetectable. The calculational methods presented in this ODCM are used for modeling the transport in the environment and the resultant exposure to offsite individuals.
FERMI 2 ODCM - TRM VOLUME II 8-4 Rev. 13
The results of the radiological environmental monitoring program can provide input into the overall assessment of impact of plant operations and radioactive effluents. With measured levels of plant related radioactive material in principal pathways of exposure, a quantitative assessment of potential exposures can be performed. With the monitoring program not identifying any measurable levels, the data provides a qualitative assessment - a confirmatory demonstration of the negligible impact.
Dose modeling can be simplified into three basic parameters that can be applied in using environmental monitoring data for dose assessment:
D = C*U*DF (8-3) where:
D = dose or dose commitment C = concentration in the exposure media, such as air concentration for the inhalation pathway, or fish, vegetation or milk concentration for the ingestion pathway U = individual exposure to the pathway, such as hr/yr for direct exposure, kg/yr for ingestion pathway DF = dose conversion factor to convert from an exposure or uptake to an individual dose or dose commitment The applicability of each of these basic modeling parameters to the use of environmental monitoring data for dose assessment is addressed below:
Concentration - C The main value of using environmental sampling data to assess potential doses to individuals is that the data represents actual measured levels of radioactive material in the exposure pathways. This eliminates one main uncertainty and the modeling has been removed - the release from the plant and the transport to the environmental exposure medium.
Environmental samples are collected on a routine frequency per the ODCM. To determine the annual average concentration in the environmental medium for use in assessing cumulative dose for the year, an average concentration should be determined based on the sampling frequency and measured levels:
= (
~~t) /365 (8-4)~~
FERMI 2 ODCM - TRM VOLUME II 8-5 Rev. 13
where:
C.
= average concentration in the sampling medium for the year Ci = concentration of each radionuclide i measured in the individual sampling medium t = period of time that the measured concentration is considered representative of the sampling medium (typically equal to the sampling frequency; e.g., 7 days for weekly samples, 30 days for monthly samples).
If the concentration in the sampling medium is below the detection capabilities (i.e., less than Lower Limits of Detection (LLD), a value of zero should be used for Ci (Ci = 0).
Exposure - U Default Exposure Values (U) as recommended in Regulatory Guide 1.109 are presented in Table 8.0-2. These values should be used only when specific data applicable to the environmental pathway being evaluated is unavailable.
Also, the routine radiological environmental monitoring program is designed to sample/monitor the environmental media that would provide early indications of any measurable levels in the environment but not necessarily levels to which any individual is exposed. For example, sediment samples are collected in the area of the liquid discharge:, typically, no individuals are directly exposed. To apply, the measured levels of radioactivity in samples that are not directly applicable to exposure to real individuals, the approach recommended is to correlate the location and measured levels to actual locations of exposure.
Hydrological or atmospheric dilution factors can be used to provide reasonable correlations of concentrations (and doses) at other locations. The other alternative is to conservatively assume a hypothetical individual at the sampling location. Doses that are calculated in this manner should be presented as hypothetical and very conservatively determined - actual exposure would be much less. Samples collected from the Monroe water supply intake should be used for estimating the potential drinking water doses. Other water samples collected, such as near field dilution area, are not applicable to this pathway.
Dose Factors - DF The dose factors are used to convert the intake of the radioactive material to an individual dose commitment. Values of the dose factors are presented in NRC Regulatory Guide 1.109. The use of the RG 1.109 values applicable to the exposure pathway and maximum exposed individual is referenced in Table 8.0-2.
FERMI 2 ODCM - TRM VOLUME 11 8-6 Rev. 13
Assessment of Direct Exposure Doses from Noble Gases Thermoluminescent Dosimeters (TLD) are routinely used to assess the direct exposure component of radiation doses in the environment. However, because routine releases of radioactive material (noble gases) are so low, the resultant direct exposure doses are also very low. A study* performed for the NRC concluded that it was generally impractical to distinguish any plant contribution to the natural background radiation levels (direct exposure) below around 10 mrem per year. Therefore, for routine releases from nuclear power plants the use of TLD is mainly confirmatory - ensuring actual exposures are within the expected natural background variation.
For releases of noble gases, environmental modeling using plant measured releases and atmospheric transport models as presented in ODCM Sections 7.6 and 8.2.1 represents the best method of assessing potential environmental doses. However, under unusual conditions, direct radiation from noble gas concentrations could be sufficient to cause significant increases in TLD readings; any observed variations in TLD measurements outside the norm should be evaluated.
~~NUREG/CR-0711, Evaluation of Methods for the Determination of X- and Gamma-Ray Exposure Attributable to a Nuclear Facility Using Environmental TLD Measurements, Gail dePlanque, June 1979, USNRC.~~
FERMI 2 ODCM - TRM VOLUME II 8-7 Rev. 13
TABLE 8-1 Assumptions for Assessing Doses Due to Activities inside SITE BOUNDARY Ice Fishing Visitor's Center 1
Distance/ 470 meters / E 470 meters / SSW Direction:
Estimated 240 hr/yr 4 hr/yr Exposure (20 hr/week over *(4 hr/visit, 1 visit Time: 3 month period) per year)
Exposure direct exposure direct exposure Pathways: from noble gases from noble gases inhalation of inhalation of tritium, iodines, tritium, iodines particulates particulates Meteorological annual average annual average Dispersion: (as determined (as determined for year being for year being evaluated) evaluated) 6.48E-6 sec/m 3
2.54E-6 sec/m 3 *
~~Annual average X/Q Values for 1991. These values are shown as examples of the range of values to be expected.~~
FERMI 2 ODCM - TRM VOLUME II 8-8 Rev. 13 I
TABLE 8-2 Recommended Exposure Rates in Lieu of Site Specific Data*
Table Reference Exposure Pathway Maximum Exposed Exposure Rates for Dose Factor Age Group from RG 1.109 Liquid Releases Fish Adult 21 kg/y E-11 Drinking Water Adult 730 I/y E-11 Bottom Sediment Teen 67 h/y E-6 Atmospheric Releases Inhalation Teen 8,000 m3 /y E-8 Direct Exposure All 6,100 h/y** N/A Leafy Vegetables Child 26 kg/y E-1 3 Fruits, Vegetables Teen 630 kg/y E-1 2 and Grain Milk Infant 330 I/y E-14
~~Adapted from Regulatory Guide 1.109, Table E-5. This table is not a complete list of exposure rates; other applicable values may be found in Regulatory Guide 1.109.~~
Net exposure of 6,100 h/y is based on the total 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months per year adjusted by a 0.7 shielding factor as recommended in Regulatory Guide 1.109.
END OF SECTION 8.0 FERMI 2 ODCM - TRM VOLUME 11 8-9 Rev. 13
SECTION 9.0 ASSESSMENT OF LAND USE CENSUS FERMI 2 ODCM - TRM VOLUME II 9-1 Rev. 13
9.0 ASSESSMENT OF LAND USE CENSUS DATA A Land Use Census (LUC) is conducted annually in the vicinity of the Fermi 2 site. This census fulfills two main purposes: 1) Meet requirements of ODCM 3.12.2 for identifying controlling location/pathway for dose assessment of ODCM 3.11.2.3; and 2) provide data on actual exposure pathways for assessing realistic doses to MEMBERS OF THE PUBLIC.
9.1 Land Use Census as Required by ODCM 3.12.2 As required by ODCM 3.12.2, a land use census shall be conducted during the growing season at least once per twelve months. The purpose of the census is to identify within a 5 mile distance the location in each of the 16 meterological sectors of all milk producing animals, all meat producing animals, all gardens larger than 500 ft2 producing broadleaf vegetation, and the closest residence to the plant. The data from the LUC is used for updating the location/pathway for dose assessment and for updating the Radiological Environmental Monitoring Program.
If the census identifies a location/pathway(s) yielding a higher potential dose to a MEMBER OF THE PUBLIC than currently being assessed as required by ODCM 3.11.2.3 (and ODCM Section 7.7 and Table 7.0-3), this new location pathway(s) shall be used for dose assessment. Table 7.0-3 shall be updated to include the currently identified controlling location/pathway(s). Also, if the census identifies a location(s) that yields a calculated potential dose (via the same exposure pathway) 20% greater than a location currently included in the Radiological Environmental Monitoring Program, the new location(s) shall be added to the program within 30 days, unless permission to take samples cannot be obtained from the affected landowner. The sampling location(s),
excluding control locations, having the lowest calculated dose may be deleted from the program after October 31 following the current census. As required by ODCM 3.12.2 and 5.9.1.8, the new location/pathway(s) shall be identified in the next Annual Radioactive Effluent Release Report. The following guideline shall be used for assessing the results from the land use census to ensure compliance with ODCM 3.12.2.
9.1.1 Data Compilation
~~1. Compile all locations and pathways of exposure as identified by the land use census.~~
2. From this compiled data, identify any changes from the previous year's census. Identify the current controlling location/pathway (critical receptor) used in ODCM Table 7.0-3. Also, identify any location currently included in the REMP (Table 10-1).
~~FERMI 2 ODCM - TRM VOLUME II 9-2 Rev. 13~~
3. Perform relative dose calculations based on actual Fermi 2 gaseous I effluent releases for a recent period of reactor operation, using the pathway dose equations of the ODCM. In identifying the critical receptor for Table 7.0-3, all age groups and all pathways relevant to ODCM 3.11.2.3 that may be present at each evaluated location are considered. The critical receptor is assumed to be a member of the age group with the highest calculated dose to the maximally exposed organ due to 1-131, 1-133, tritium, and particulates with half lives greater than 8 days. Other receptors may have higher doses to other organs than the critical receptor has to those organs.
~~4. Formulate a listing of locations of high dose significance in descending order of relative dose significance. Include the relative dose significance in the listing.~~
~~9.1.3 Program Updates~~
1. If any receptor is identified with a higher relative dose than the current critical receptor in ODCM Table 7.0-3, this receptor and its associated location and pathways should replace the previously identified critical receptor information in Table 7.0-3.
~~2. The Land Use Census data should be used to revise the REMP and Section 10.0 of the ODCM in accordance with ODCM 3.12.2, Action Item b.~~
3. Any changes in either the controlling location/pathway(s) (critical receptor) for the ODCM dose calculations (Section 7.7 and Table 7.0-3) or the REMP (ODCM Section 10.0 and Table 10-1) shall be reported to NRC in accordance with ODCM 3.12.2, Action Items a. and b. and ODCM 5.9.1.8.
NOTE: As permitted by footnote to ODCM 3.12.2, broadleaf vegetation sampling may be performed at the SITE BOUNDARY in two locations, in different sectors with highest predicted D/Qs, in lieu of the garden census.
Also, for conservatism in dose assessment for compliance with ODCM 3.11.2.3 (see also ODCM Section 7.7 and Table 7.0-3), hypothetical exposure location/pathway(s) and conservative dispersion factors may be assumed (e.g., milk cow at 5mile location or garden at SITE BOUNDARY in highest D/Q sector). By this approach, the ODCM is riot subject to frequent revision as pathways and locations change from year to year. A verification that the hypothetical pathway remains conservative and valid is still required. Also, for NRC reporting, the actual pathways and doses should be reported along with the hypothetical. The reporting of the actual pathway and doses provides a formal documentation of the more realistic dose impact.
FERMI 2 ODCM - TRM VOLUME II 9-3 Rev. 14
9.2 Land Use Census to Support Realistic Dose Assessment The LUC provides data needed to support the special dose analyses of the ODCM Section 8.0. Activities inside the SITE BOUNDARY should be periodically reviewed for dose assessment as required by ODCM 5.9.1.8 (see also ODCM Section 8.1).
Assessment of realistic doses to MEMBERS OF THE PUBLIC is required by ODCM 3.11.4 for demonstrating compliance with the EPA Environmental Dose Standard, 40 CFR 190 (ODCM Section 8.2).
To support these dose assessments, the LUC shall include use of Lake Erie water on and near the site. The LUC shall include data on Lake Erie use obtained from local and state officials. Reasonable efforts shall be made to identify individual irrigation and potable water users, and industrial and commercial water users whose source is Lake Erie. This data is used to verify the pathways of exposure used in ODCM Section 6.5.
END OF SECTION 9.0 FERMI 2 ODCM - TRM VOLUME II 9-4 Rev. 13
SECTION 10.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FERMI 2 ODCM - TRM VOLUME II 10-1 Rev. 13
10.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of ODCM 3.12.1. The sampling and analysis program described herein was developed to provide representative measurements of radiation and radioactive materials resulting from station operation in the principal pathways of exposure of MEMBERS OF THE PUBLIC. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent control program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for the development of this monitoring program is provided by the NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.
10.1 Sampling Locations Sampling locations as required by ODCM 3.12.1 are described in Table 10.0-1.
NOTE: For purposes of implementing ODCM 3.12.2, sampling locations will be modified as required to reflect the findings of the annual land use census as described in ODCM Section 9.1 and as required by other contingencies (e.g. unavailability of milk from a listed location). Such changes will be documented in plant records and reflected in the next ODCM revision, the next Annual Effluent Release Report, and the next Annual Radiological Environmental Operating Report. Also, if the circumstances of such changes involve a possible change in the maximally exposed individual evaluated for ODCM Control 3.11.2.3, the identity of this individual will be reevaluated.
10.2 Reporting Levels ODCM 3.12.1, Action b, describes criteria for a Special Report to the NRC if levels of plant-related radioactive material, when averaged over a calendar quarter, exceed the prescribed levels of ODCM Table 3.12.1-2. The reporting levels are based on the design objective doses of 10 CFR 50, Appendix I (i.e., the annual limits of ODCM 3.11.1.2, 3.11.2.2 and 3.11.2.3). In other words, levels of radioactive material in the respective sampling medium equal to the prescribed reporting levels are representative of potential annual doses of 3 mrem, total body or 10 mrem, maximum organ from liquid pathways; or 5 mrem, total body, or 15 mrem, maximum organ for the gaseous effluent pathway. These potential doses are modeled on the maximum individual exposure or consumption rates of NRC Regulatory Guide 1.109.
The evaluation of potential doses should be based solely on radioactive material resulting from plant operation. As stated in ODCM 3.12.1, Action b, the report shall also be submitted if radionuclides other than those in ODCM Table 3.12.1-2 are detected (and are a result of plant effluents) and the potential dose exceeds the above annual design objectives. The method described in ODCM Section 8.2.3 may be used for assessing the potential dose and required reporting for radionuclides other than those in ODCM Table 3.12.1-2.
FERMI 2 ODCM - TRM VOLUME II 10-2 Rev. 13
10.3 Interlaboratory Comparison Program A major objective of this program is to assist laboratories involved in environmental radiation measurements to develop and maintain both an intralaboratory and an interlaboratory quality control program. This is accomplished through a laboratory intercomparison study ("cross-check") program involving environmental media and a variety of radionuclides with activities at or near environmental levels.
Simulated environmental samples, containing known amounts of one or more radionuclides, are prepared and routinely distributed to Detroit Edison's contract environmental laboratory, which performs the required analyses. The analysis results are then compared to the known concentrations in the samples. The program thus enables the laboratory to document the precision and accuracy of its radiation data, and identify instrument and procedural problems.
The environmental laboratory is required to participate in an Interlaboratory Comparison Program and to submit QA Program Progress Summary Reports to Detroit Edison on an annual basis. These reports contain performance data summaries on blind spiked analyses, and explanations of deviations from expected results. A summary of the Interlaboratory Comparison Program results obtained is required to be included in the Annual Radiological Environmental Operating Report pursuant to ODCM 5.9.1.7.
Participation in an Interlaboratory Comparison Program ensures that an independent check on the precision and accuracy of the measurements of radioactive material in environmental sample matrices is performed as part of the QA Program for environmental monitoring in order to demonstrate that the results are valid for the purpose of Section IV.B.2 of Appendix I to 10 CFR Part 50.
FERMI 2 ODCM - TRM VOLUME II 10-3 Rev. 13
TABLE 10.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FERMI 2 SAMPLE LOCATIONS AND ASSOCIATED MEDIA KEY 1- T TLD Locations (Pg. 10-5 through 10-9) 2- S Sediments Locations (Pg. 10-10) 3- F Fish Locations (Pg. 10-10) 4- M Milk Locations (Pg. 10-11) 5- DW Drinking Water Locations (Pg. 10-12) 6- SW Surface Water Locations (Pg. 10-12) 7- GW Ground Water Locations (Pg. 10-12) 8- API Air Particulate/Iodine Locations (Pg. 10-13) 9- FP Food Products Locations (Pg. 10-14)
FERMI 2 ODCM - TRM VOLUME II 10-4 Rev. 13
TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Direct Radiation Station ?, ee rlgc li,,,,.'iDsa from -. sq " i;-, 1":-i T1 NE/380 1.3 ml Estral Beach Polo on Lakeshore, 23 Poles S of Lakoview Direct Radiation a (Special Area)
T2 NNE/22 0 1.2 ml East of termination of Brancheau St. on post Direct Radiation a (Special Area)
T3 N/90 1.1 ml Pole, NW Corner of Swan Boat Club Fence Direct Radiation 0 (Special Area)
T4 NNW/337 0 0.6 ml Site Boundary and Toll Rd. on Site Fence bV API #2 Direct Radiation Q T5 NW/3130 0.6 ml Site Boundary and Toll Rd. on Site Fence by API #3 Direct Radiation 0 T6 WNW/2940 0.6 ml Site boundary fence at south end of N. Bullit Rd. Direct Radiation 0 T7 0 W/270 14.0 ml Pole, at Michigan Gas substation on N. Custer Rd., 0.66 miles W of Direct Radiation 0 Doty Rd. (Control)
T8 NW/3050 1.9 ml Pole on Post Rd. near NE Comer of Dixie Hwy. and Post Rd. Direct Radiation 0 T9 NNW/3340 1.5 ml Pole, NW Corner of Trombley and Swan View Road Direct Radiation 0 T10 0 N/6 2.1 ml Pole, S Side of Masserant - 2 Poles W of Chinavare Direct Radiation 0 T11 NNE/230 6.2 ml Pole, NE Corner of Milliman and Jefferson Direct Radiation 0 T12 0 NNE/29 6.3 ml Pointe Mouillee Game Area - Field Office, Pole near Tree, N Area of Direct Radiation Q Parking Lot T13 N/3560 4.1 ml Labo and Dixie Hwy - Pole on SW Corner with Light Direct Radiation 0 T14 NNW/337 0 4.4 ml Labo and Brandon - Pole on SE Corner near RR Direct Radiation a FERMI 2 ODCM - TRM VOLUME II 10-5 Rev. 14
TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Direct Radiation Ti15 NW/315 0 3.9 mi Pole, behind building at the corner of Swan Creek and Miil St. Direct Radiation 0 Ti16 WNW/283 0 4.9 ml Pole, SE corner of War and Post Rds. Direct Radiation 0 T17 0 W/271 4.9 ml Pole, NE Corner-of Nadeau and LaPrad near Mobile Home Park Direct Radiation 0 0
T18 WSW/247 4.8 ml Pole, NE Corner of Mentel and Hurd Direct Radiation a Ti19 0 SW/236 5.2 ml 1st Pole N of State Park Rd on E side of Waterworks Rd Direct Radiation 0 T20 WSW/257 0 2.7 ml Pole, S Side of Williams Rd. - 8 Poles W of Dixie Hwy. (Special Area) Direct Radiation 0 T21 WSW/239 0 2.7 ml Pole, N Side of Pearl at Parkview - Woodland Beach (Special Area) Direct Radiation 0 0
T22 S/1 72 1.2 ml Pole, N Side of Pointe Aux Peaux 2 Poles W of Long - Site Boundary Direct Radiation 0 T23 SSW/1 950 1.1 ml Pole, S Side of Pointe Aux Peaux - I Pole W of Huron next to Vent Direct Radiation 0 Pipe - Site Boundary T24 SW/225 0 1.2 ml Fermi Gate along Pointe Aux Peaux Rd.- on fence wire W of Gate - Direct Radiation 0 Site Boundary T25 WSW/252 0 1.5 ml Pole, Toil Rd. - 12 Poles S of Fermi Dr. Direct Radiation 0 T26 WSW/259 0 1.1 ml Pole, Toil Rd. - 6 Poles S of Fermi Dr. Direct Radiation0 T27 SW/225 0 6.8 ml Pole, NE Corner of McMillan and East Front St. (Special Area) Direct Radiation 0 T28 0 SW/229 10.7 ml Pole, SE Corner of' Mortar Creek and LaPtaisance (Control) Direct Radiation 0 T29 WSW/237 0 10.3 mi Pole, E Side of S Dixie, 1 Pole S of Albain (Control) Direct Radiation 0 FERMI 2 ODCM - TRM VOLUME II 10-6 Rev. 14
TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Direct Radiation Station Meteorological Distance from Number Sector/Azimuth Reactor (Approx.) Description Media Frequency Direction T30 WSW/2470 7.8 mi Pole, St. Mary's Park near foot bridge (park is near corner of Elm and Direct Radiation a Monroe streets)
T31 WSW/2550 9.6 mi 1st Pole W of Entrance Drive Milton 'Pat" Munson Recreational Direct Radiation Q Reserve - N. Custer Rd. (Control)
T32 WNW/2950 10.3 mi Pole. Corner of Stony Creek and Finzel Rds. Direct Radiation a T33 NW/3170 9.2 ml Pole, W Side of Grafton Rd. 1 Pole N of Ash/Grafton Intersection Direct Radiation Q T34 NNW/3380 9.7 mi Pole, W Side of Port Creek, 1 pole S of Will Carleton Rd. Direct Radiation Q T35 N/3590 6.9 ml Pole, S Side of S. Huron River Dr. across from Race St. (Special Direct Radiation Q
- Area)
T36 N/3580 9.1 mi Pole, NE Comer of Gibraltar and Cahill Rds. Direct Radiation Q T37 NNE/210 9.8 ml Pole, S Corner of Adams and Gibraltar (across from Humbug Marina) Direct Radiation Q T38 WNW/2940 1.7 mi Residence - 6594 N. Dixie Hwy. Direct Radiation 0 T39 S/1 760 0.3 mi SE Corner of Protected Area Fence (PAF) Direct Radiation Q T40 S/i 700 0.3 mi Midway along OBA - PAF Direct Radiation Q T41 SSE/1610 0.2 ml Midw~ay between OBA and Shield Wall - PAF Direct Radiation 0 T42 SSE/1490 0.2 mi Midway along Shield Wall - PAF Direct Radiation 0 T43 SE/1310 0.1 mi Midway between Shield Wall and Aux Boilers- PAF Direct Radiation Q T44 ESE/1090 0. 1 mi Opposite OSSF Door PAF - Direct Radiation 0 FERMI 2 ODCM - TRM VOLUME II 10-7 Rev. 13 l
TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Direct Radiation Station Meteorological Distance from Number Sector/Azimuth Reactor (Approx.) Description Media Frequency Direction T45 E/860 0.1 mi NE Corner - PAF T46 ENE/670 0.2 mi NE Side Barge Slip - on Fence Direct Radiation Q T47 S/1 850 0.1 mi South of Turbine Bldg. rollup door on PAF Direct Radiation Q T48 SW/2350 0.2 mi 30 ft. from comer of AAP on PAF T49 WSW/2510 1.1 ml Corn of site boundary fence north of NOC along Critical Path Rd. Direct Radiation _ Q T50 W/2700 0.9 mi Site boundary fence near main gate by the south Bullit St. sign Direct Radiation Q T51 N/30 0.4 mi Site boundary fence north of North Cooling Tower Direct Radiation 0 T52 NNE/200 0.4 mi Site boundary fence at the corner of Arson and Tower Direct Radiation Q T53 NE/550 0.2 mi Site boundary fence east of South Cooling Tower Direct Radiation Q T54 S/1 890 0.3 mi Pole, next to Fermi 2 Visitors Center Direct Radiation Q T55 WSW/2510 3.3 mi' First pole east of Frenchtown Fire Station entrance, across from Sodt Direct Radiation 0 Elementary School T56 WSW/2550 4.9 mi Pole, entrance to Jefferson Middle School on Stony Creek Rd. Direct Radiation 0 T57 W/2600 2.7 mi Pole, north side of Williams Rd. across from Jefferson High School Direct Radiation a entrance T58 WSW/2490 4.9 ml Pole, west of Hurd Elementary School Marquee Direct Radiation 0 T59 NW/3250 2.6 mi Pole, north of St. Charles Church entrance on Dixie Hwy. Direct Radiation 0 T60 NNW/3410 2.5 mi 1st pole north of North Elementary School entrance on Dixie Hwy. Direct Radiation a FERMI 2 ODCM - TRM VOLUME II 10-8 Rev. 13
TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Direct Radiation Station Meteorological Distance from Number Sector/Azimuth Reactor (Approx.) Description Media Frequency Direction T61 W/2680 10.1 m_ Pole, SW Corner of Stewart and Raisinville Rds. Direct Radiation 0 T62 SW/232 0 9.7 mi Pole, NW Corner of Albain and Hull Rds. Direct Radiation 0 T63 WSW/245 0 9.6 m' Pole, Corner of Dunbar and Telegraph Rds. Direct Radiation 0 T64 WNW/286 0 0.2 mi W of switchgear yard on PAF Direct Radiation Q T65 NW/322 0 0.1 m! PAF switchgear yard area NW of RHR complex Direct Radiation 0 T66 0 NE/50 0.1 mi Behind Bldg. 42 on PAF Direct Radiation Q T67 NNW/338 0 0.2 m' Site boundary fence W of S cooling tower Direct Radiation 0 I
FERMI 2 ODCM - TRM VOLUME II 10-9 Rev. 13 l .
TABLE 10.0.1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Fish and Sediment Station Meteorolog, Ical Distance from Number Sector/Azim uth Reactor (Approx.) Description Media Frequency Directior SEDIMENTS S-1 SSE/165( 0.9 mi Pointe Aux Peaux, Shoreline to 500 ft. offshore sighting directly to Sediment SA Land Base Water Tower S-2 E/810 0.2 mi Fermi 2 Discharge, approx. 200 ft. offshore Sediment SA S-3 NE/39° 1.1 mi Estral Beach, approx. 200 ft. offshore, off North shoreline where Sediment SA Swan Creek and Lake Erie meet _____ _
S-4 WSW/241 0 3.0 mi Indian Trails Community Beach Sediment SA S-5 NNE/200 11.7 mi DECo's Trenton Channel Power Plant intake area (Control) Sediment_ SA FISH F-1 NNE/310 9.5 mi Celeron Island (Control) Fish SA F-2 E/860 0.4 mi Fermi 2 Discharge (Approx. 1200 ft. offshore) Fish SA F-3 SW/227C 3.5 mi Breast Bay Area (Control) Fish SA FERMI 2 ODCM - TFZM VOLUME II 10-10 Rev. 13
TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Milk/Grass Station Meteorological Distance from Number Sector/Azimuth Reactor (Approx.) Description Media Frequency Direction _ _ -
M-2 NW/3190 5.4 mi Reaume Farm -2705 E. Labo _ _ ___ Milk M-SM M-8 WNW/289 0 9.9 mi Calder -9334 Finzel Rd. Milk __ M-SM FERMI 2 ODCM - TRM VOLUME II 10-11 Rev. 13
TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Water Station Meteorolog Ical Distance from Number Sector/Azin- ruth Reactor (Approx.) Description Media Frequency Directior DRINKING WATER DW-1 S/1740 1.1 ml Monroe Water Station N Side of Pointe Aux Peaux 1/2 Block W of Drinking Water M Long Rd. _ _. _
DW-2 N180 18.5 mi Detroit Water Station, 14700 Moran Rd. Allen Park (Control) Drinking Water M SURFACE WATER SW-2 NNE/20c 11.7 ml DECo's Trenton Channel Power Plant Intake Structure (Screenhouse Surface Water M
~~1) (Control)~~
SW-3 SSE/160( 0.2 mi DECo's Fermi 2 General Service Water Intake Structure Surface Water M SITE WELLS GW-1 Sf1750 0.4 mi Approx. 100 fl. W of Lake Erie, EF-1 Parking lot Groundwater near Groundwater Q gas fired peakers ___ __ _
GW-2 SSW/208 0 1.0 mi 4 ft. S of Pointe Aux Peaux (PAP) Rd. Fence 427 ft. W of where PAP Groundwater 0 crosses over Stony Point's Western Dike GW-3 SW1226c 1.0 mi 143 ft. W of PAP Rd. Gate, 62 ft. N of PAP Rd. Fence Groundwater Q GW-4 WNW1299 30 0.6 ml 42 ft. S of Langton Rd., 8 ft. E of Toll Rd. Fence Groundwater Q FERMI 2 ODCM - TFZM VOLUME II 10-12 Rev. 13
TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Air Particulate Air Iodine iJ.on, Me dhore quency,,,,
API-1 NE/390 1.4 mi Estral Beach Pole on Lakeshore, 18 Poles S of Lakeview (Nearest Radiolodine W Community with highest Z IQ) . Particulates W API-2 NNW/337 0 0.6 ml Site Boundary and Toll Road, on Site Fence by T-4 Radiolodine W Particulates W API-3 NW/313° 0.6 ml Site Boundary and Toll Road, on Site Fence by T-5 Radioiodine W Particulates W API-4 W/2700 14.0 mi Pole, at Michigan Gas substation on N. Custer Rd., 0.66 miles W of Radioiodine W Doty Rd. (control) Particulates W API-5 S/1880 1.2 ml Pole, N comer of Pointe Aux Peaux and Dewey Rd. Radiolodine W Particulates W FERMI 2 ODCM - TRM VOLUME 11 10-13 Rev. 14
TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Food Products
,i Statlon qf.,';;,Meteorolog Ntmber:, ",! Sectoi/AzIn-FP-1 NNEI21 0 3.8 ml 9501 Turnpike Highway Food Products M (when available) 0 FP-9 w/261° Fp-q W19R1 . I-f.5 LI-f-L~ I -JUA ruu&AUUI I...U
_ .,.ov.
--- s7 ,, svv vIal
-~ rIvau rouu rrUuLcIas MVi twaen available)
FERMI 2 ODCM - TRM VOLUME II 10-14 Rev. 14
TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Land Use Census Closest Residences NE 1.1 mi NNE 1.0Omi 4w .,
N 1.1lml NNW 1.1 mi NW - 1.1 ml WNW 0.7 ml W 1.2 mi I WSW 1.6 ml SW 1.3 mi SSW 1.1 ml I S 1.0 mi ESE-SSE Lake Erie END OF SECTION 10.0 FERMI 2 ODCM - TRM VOLUME II .0-15 Rev. 14
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NRC-04-0024, Annual Radioactive Effluent Release and Radiological Environmental Operating Reports

Contents

Text

References:

Subject:

l < .60E-02 Co-60 <1 3.90E-03 = < 3.30E-03

1.0 INTRODUCTION

1.0 INTRODUCTION

1.0 INTRODUCTION

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NRC-04-0024, Annual Radioactive Effluent Release and Radiological Environmental Operating Reports

Text

References:

Subject:

l < .60E-02 Co-60 <1 3.90E-03 = < 3.30E-03

1.0 INTRODUCTION

1.0 INTRODUCTION

1.0 INTRODUCTION

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