NRC-11-0016, Annual Radiological Environmental Operating Report, Radioactive Effluent Release Report and Revised Offsite Dose Calculation Manual

Annual Radiological Environmental Operating Report, Radioactive Effluent Release Report and Revised Offsite Dose Calculation Manual

ML111220090
Person / Time
Site:	Fermi
Issue date:	04/28/2011
From:	Plona J DTE Energy
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NRC-11-0016
Download: ML111220090 (378)

Text

Joseph 1I. Plona Site Vice President 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734,586.5910 Fax: 734.586.4172 3-- Ener y DTE April 28, 2011 NRC-11-0016 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 5.5.1, 5.6.2 and 5.6.3

Subject:

Annual Radiological Environmental Operating Report, Radioactive Effluent Release Report and Revised Offsite Dose Calculation Manual The 2010 Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for Fermi 2 are enclosed. These reports are being transmitted in accordance with Reference 2 and Regulatory Guide 1.21, Revision 1. The enclosed reports cover the period from January 1 through December 31, 2010. Additionally, since the Offsite Dose Calculation Manual (ODCM) was revised in 2010, a complete copy is attached in accordance with the Technical Specifications.

Should you have any questions regarding this report, please contact Mr. Bruce Rumans, General Supervisor, Radiation Protection at (734) 586-5015.

Sincerely, Enclosures cc: NRC Project Manager [w/o Enclosure]

NRC Resident Office [w/Enclosure]

Reactor Projects Chief, Branch 4, Region III [w/o Enclosure]

Regional Administrator, Region III [w/Enclosure]

Supervisor, Electric Operators, Michigan Public Service Commission [w/Enclosure]

Fermi 2 - 2010 Annual Radioactive Effluent Release Report FERMI 2 NUCLEAR POWER PLANT DETROIT EDISON COMPANY OPERATING LICENSE NO. NPF - 43 Fermi 2 - 2010 Annual Radioactive Effluent Release Report for the period of January 1, 2010 through December 31, 2010 Prepared by:

Fermi 2 Radiological Engineering 1

Fermi 2 - 2010 Annual Radioactive Effluent Release Report Table of Contents Page Executive Summary 4 Introduction 5 Noble Gases 5 Iodines and Particulates 5 Tritium 6 Carbon-14 6 PlantEffluent Monitoring 6 Exposure Pathways to People 7 Dose Assessment 8 Radioactive Effluent Monitoring Results 9 Summary of Radioactive Waste Shipments 12 Additional Required Information 12 Appendices 12 ODCMRevisions 13 ODCMMonitors Out of Service 13 Outside Temporary Tanks 13 MeteorologicalTables 13 Major Changes to Radioactive Waste Systems 13 Abnormal RadiologicalReleases 14 Appendix A: Effluent and Radwaste Data 15 Regulatory Limitsfor Radioactive Effluents 16 Gaseous Effluents 16 Liquid Effluents 17 Measurements andApproximations of Total Activity in Radioactive Effluents 18 Gaseous Effluents 18 Fission and Activation Gases 18 Radioiodines 18 Particulates 19 Tritium 19 Gross Alpha 19 Carbon-14 20 Liquid Effluents 20 StatisticalMeasurement Uncertainties 20 GaseousRelease by Individual Nuclide 20 ParticulateRadionuclides (Curies) 21 Noble Gases (Curies) 22 Radioiodines (Curies) 22 Shipments of Radwaste 22 Spent resins, sludges, etc. 22 Dry compressible waste, contaminatedequipment, etc. 24 Irradiatedcomponents, control rods, etc. 24 2

Fermi 2 - 2010 Annual Radioactive Effluent Release Report Other 24 Appendix B: Ground Water ProtectionProgramData andAnalysis 25 Appendix C: Offsite Dose CalculationManualRevision 34 List of Tables Page Table 1 Fission andActivation Gases (Noble Gases) Summary 9 Table 2 RadioiodinesSummary 9 Table 3 ParticulatesSummary 10 Table 4 Tritium and Carbon-14 Summary 10 Table 5 2010 Gaseous Effluent Dose to Receptor with Highest Single Organ Dose 11 Table 6 Solid Waste Received at Burial Sites 12 Table 7 Solid Waste Shipments 12 3

Fermi 2 - 2010 Annual Radioactive Effluent Release Report Executive Summary This report is published to provide information regarding radioactive effluent monitoring at the Fermi 2 Nuclear Power Plant. The 2010 Annual Radioactive Effluent Release Report covers the period from January 1, 2010 through December 31, 2010.

The Radioactive Effluent Release Report is produced annually, as required by the Nuclear Regulatory Commission, to present detailed results of extensive monitoring of plant releases and offsite dose resulting from these releases. The data presented indicate that the operation of Fermi 2 results in offsite radiation exposures which are well below the applicable allowable levels set by the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).

There were no routine releases of liquid radioactive effluents from Fermi 2 in 2010.

There has not been a routine liquid radioactive discharge from Fermi 2 since 1994.

However there was one inadvertent liquid discharge on December 1, 2010. This release, which resulted in negligible dose to the public, is described under Abnormal Radiological Releases on page 14 of this report. Data on routine releases of radioactive isotopes in gaseous effluents, as well as regulatory limits and sampling methods for these releases, are contained in the body of the report and in Appendix A.

Regulatory limits for radioactive effluents pertain to allowable offsite doses rather than to quantities of radioactivity released. The highest potential single organ dose to a person living offsite due to iodines, particulates, tritium, and carbon-14 released from the plant was calculated to be 0.24 mrem, which is 1.6% of the applicable limit found in 10 CFR Part 50, Appendix I.

During 2010, no direct radiation dose to members of the public beyond the site boundary was attributed to the operation of Fermi 2, based on analysis of readings of thermoluminescent dosimeters (TLD) placed at various locations near the Fermi site.

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 2010.

Data on radioactivity contained in radwaste shipments to points offsite are contained in the body of the report and in Appendix A. The Offsite Dose Calculation Manual (ODCM) was revised in 2010 and the current revision is shown in Appendix C.

Additional sections of the report address ODCM monitors which were out of service for more than 30 days in 2010, major changes in radwaste processing, the contents of outside temporary tanks, meteorological tables, and abnormal releases (see pages 13 and 14).

Appendix B of this report describes the Fermi Integrated Ground Water Protection Program. This program was established as part of the site's commitment to conformance with an industry-wide ground water protection initiative. This appendix also contains the results of 2010 quarterly ground water sampling, from approximately 40 monitor wells 4

Fermi 2 - 2010 Annual Radioactive Effluent Release Report Other 24 Appendix B: Ground Water ProtectionProgramData and Analysis 25 Appendix C: Offsite Dose Calculation Manual Revision 34 List of Tables Page Table 1 FissionandActivation Gases (Noble Gases) Summary 9 Table 2 Radioiodines Summary 9 Table 3 ParticulatesSummary 10 Table 4 Tritium and Carbon-14 Summary 10 Table 5 2010 Gaseous Effluent Dose to Receptor with Highest Single Organ Dose 11 Table 6 Solid Waste Received at BurialSites 12 Table 7 Solid Waste Shipments 12 3

Fermi 2 - 2010 Annual Radioactive Effluent Release Report Executive Summary This report is published to provide information regarding radioactive effluent monitoring at the Fermi 2 Nuclear Power Plant. The 2010 Annual Radioactive Effluent Release Report covers the period from January 1, 2010 through December 31, 2010.

The Radioactive Effluent Release Report is produced annually, as required by the Nuclear Regulatory Commission, to present detailed results of extensive monitoring of plant releases and offsite dose resulting from these releases. The data presented indicate that the operation of Fermi 2 results in offsite radiation exposures which are well below the applicable allowable levels set by the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).

There were no routine releases of liquid radioactive effluents from Fermi 2 in 2010.

There has not been a routine liquid radioactive discharge from Fermi 2 since 1994.

However there was one inadvertent liquid discharge on December 1, 2010. This release, which resulted in negligible dose to the public, is described under Abnormal Radiological Releases on page 14 of this report. Data on routine releases of radioactive isotopes in gaseous effluents, as well as regulatory limits and sampling methods for these releases, are contained in the body of the report and in Appendix A.

Regulatory limits for radioactive effluents pertain to allowable offsite doses rather than to quantities of radioactivity released. The highest potential single organ dose to a person living offsite due to iodines, particulates, tritium, and carbon-14 released from the plant was calculated to be 0.24 mrem, which is 1.6% of the applicable limit found in 10 CFR Part 50, Appendix I.

During 2010, no direct radiation dose to members of the public beyond the site boundary was attributed to the operation of Fermi 2, based on analysis of readings of thermoluminescent dosimeters (TLD) placed at various locations near the Fermi site.

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 2010.

Data on radioactivity contained in radwaste shipments to points offsite are contained in the body of the report and in Appendix A. The Offsite Dose Calculation Manual (ODCM) was revised in 2010 and the current revision is shown in Appendix C.

Additional sections of the report address ODCM monitors which were out of service for more than 30 days in 2010, major changes in radwaste processing, the contents of outside temporary tanks, meteorological tables, and abnormal releases (see pages 13 and 14).

Appendix B of this report describes the Fermi Integrated Ground Water Protection Program. This program was established as part of the site's commitment to conformance with an industry-wide ground water protection initiative. This appendix also contains the results of 2010 quarterly ground water sampling, from approximately 40 monitor wells 4

Fermi 2 - 2010 Annual Radioactive Effluent Release Report around Fermi 2 (ground water sampling has been performed under this program since the fall of 2007). Some of these monitor wells, primarily to the east and south of Fermi 2, have yielded sporadic and variable trace quantities of tritium that have been attributed to the recapture of tritium in precipitation from the plant's gaseous effluent or to background concentrations of tritium in the environment.

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, as well as tritium and carbon-14. The five types of radioactive material released are noble gases, iodine, particulates, tritium, and carbon-14.

Noble Gases Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. These noble gases are released continuously at low levels while the reactor is operating. 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 prior to release.

Noble gases are biologically and chemically nonreactive. They do not concentrate in humans or other organisms. They contribute to human radiation dose by being an external source of radiation exposure to the body. They are readily dispersed in the atmosphere.

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

yttrium-91m and barium-139) and activation products (e.g., cobalt-58 and cobalt-60).

Annual releases of these radionuclides are well within industry norms. 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.

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.

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Fermi 2 - 2010 Annual Radioactive Effluent Release Report Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in radioactive gaseous effluents. It is detected at Fermi 2 in ventilation exhaust samples. Tritium is also the predominant radionuclide in liquid effluents; however Fermi 2 has not conducted routine liquid radioactive waste discharges since 1994. Plant personnel are alert for evidence ofunmonitored liquid tritium releases.

Carbon-14 The year 2010 is the first year for which U.S. nuclear power plants are expected to report releases of carbon-14 (C-14). The releases reported are based on calculations involving the thermal power rating of the unit and 2010 quarterly capacity factors. The Fermi 2 UFSAR estimates annual gaseous C-14 releases of 9.88 curies. The calculation performed for this report estimated a total 2010 C-14 release of 14.2 curies. Since this calculation provides a higher, more conservative estimate, its results are used in this report.

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 verify 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, 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 - 2010 Annual Radioactive Effluent Release Report All wastes are evaluated to identify the specific concentrations ofradionuclides 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 and meteorological 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 - 2010 Annual Radioactive Effluent Release 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. Doses delivered to the total body and to specific organs were calculated. The organ receiving the greatest dose is important in determining compliance with dose limits. The standard assumptions used in dose calculation result in conservative dose estimates.

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. The form of the radionuclide (soluble vs. insoluble) and the method of uptake also influence residence times in the body.

The maximum dose to the general public in the area surrounding Fermi 2 is calculated for periods of gaseous release and for each liquid release. The dose due to radioactive material released in gaseous effluents is calculated using factors such as the amount of' radioactive material released, the concentration beyond the site boundary, the locations of exposure pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inhalation and food consumption). The dose due to radioactive material released in liquid effluents is calculated using factors such as the total volume of liquid, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption). These calculations produce a conservative estimation of the dose.

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Fermi 2 - 2010 Annual Radioactive Effluent Release Report Radioactive Effluent Monitoring Results This section summarizes the results of effluent monitoring and offsite dose calculation for the year 2010. Calculated offsite doses are compared with Nuclear Regulatory Commission limits, and these limits are summarized in Appendix A. Appendix A 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 routine releases of liquid radioactive effluents from Fermi 2 in 2010.

There has not been a routine liquid radioactive discharge from Fermi 2 since 1994.

However there was one abnormal liquid release in 2010 which is described on page 14 of the Additional Required Information section and which resulted in negligible dose to the public; this section contains both estimates of radioactivity released and maximum offsite dose due to this event.

The data in the following gaseous effluent tables represent continuous and batch releases.

In 2010, there were twelve recorded containment purges in which radioactivity was detected. The total time for these purges was 8460 minutes. Based on recorded start and stop times, the shortest of these purges lasted 69 minutes, the longest lasted 2399 minutes, and the average purge length was 705 minutes. The amounts of radioactivity released in these purges is very small compared with the amounts released in continuous releases.

Table 1 - Fission and Activation Gases (Noble Gases) Summary S Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (curies) 2.89E+00 3.41E+00 2.73E+00 8.49E+00 Average Release 3.71E-01 4.34E-01 3.43E-01 1.07E+00 Rate for Period

([Ci/sec)

Table 2 - Radioiodines Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total 1-131 3.12E-04 7.60E-04 3.93E-04 2.88E-04 (curies)

Average Release 4.01E-05 9.67E-05 4.94E-05 3.62E-05 Rate for Period (UCi/sec) 9

Fermi 2 - 2010 Annual Radioactive Effluent Release Report Table 3 - Particulates Summary Quarter I Quarter 2 Quarter 3 Quarter 4 Particulates with 1.61E-04 1.18E-04 5.60E-04 8.96E-04 half lives > 8 days (curies)

Average 2.07E-05 1.50E-05 7.04E-05 1.13E-04 Release Rate for Period (jtCi/sec)

Gross Alpha <5.6E-15 4.08E-07 <5.6E-15 <5.6E-15 Radioactivity uCi/cc curies uCi/cc uCi/cc For gross alpha radioactivity releases, the "less than" value in units of microcuries per cubic centimeter (jtCi/cc) is used when no radioactivity was detected and represents the lower limit of detection (LLD) value for a single sample.

Table 3 shows that gross alpha radioactivity was detected in the second quarter of 2010.

This activity was detected in turbine building ventilation effluent samples during two consecutive weeks in June 2010. During this time period there were no indications of alpha activity in the reactor building, radwaste building or on-site storage building gross alpha radioactivity samples. Additionally during 2010 there continued to be no indications of fuel degradation. The dose calculated for this gross alpha activity release, using worst case assumptions, is a small fraction of the dose calculated for 2010 radioiodine, particulate, tritium, and carbon-14 releases, shown in Table 5 below.

Table 4 - Tritium (H-3) and Carbon-14 (C-14) Summary Quarter I Quarter 2 Quarter 3 Quarter 4 Total H-3 Release 1.66E+01 1.76E+01 5.58E+01 2.76E+01 (curies)

Average H-3 Release 2.13E+00 2.24E+00 7.02E+00 3.47E+00 Rate ([tCi/sec)

Total C-14 Release 3.97E+00 3.82E+00 4.39E+00 2.01E+00 (curies)

Average C-14 Release 5.10E-01 4.86E-01 5.52E-01 2.53E-01 Rate (iCi/sec) 10

Fermi 2 - 2010 Annual Radioactive Effluent Release Report The offsite dose impact of the above releases was evaluated by calculating organ doses to the most highly exposed individual living near the plant due to 1-131, 1-133, H-3, C-14 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:

Table 5 2010 Gaseous Effluent Dose to Organ Receptor with Highest Single Organ Dose Bone 2.35E-01 mrem Liver 7.74E-02 mrem Thyroid 1.06E-01 mrem Kidney 7.75E-02 mrem Lung 7.73E-02 mrem GI-LLI 7.77E-02 mrem Total body 7.74E-02 mrem The highest single organ dose is 2.35E-01 mrem to the bone. This is 1.6% of the federal limit of 15 mrem specified in 10 CFR 50, Appendix I.

Another dose calculation normally performed on the above release data is that for gamma and beta air dose at the site boundary due to noble gases. In 2010, gamma air dose was 3.16E-03 mrad, 0.03% of the 10 mrad annual limit; beta air dose in 2010 was 5.78E-03 mrad, 0.03% of the 20 mrad annual limit.

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 2010, there was no direct radiation dose attributed to the operation of Fermi 2 beyond the site boundary, based on analysis of offsite TLD readings. Based on Table 5 above, the offsite dose due to effluents is 0.31% and 0.14% of 40 CFR 190 limits for the total body and thyroid, respectively. Therefore, Fermi 2 was in compliance with 40 CFR 190 in 2010.

Potential dose to visitors at Fermi 2 due to all radioactive effluents, including noble gases, was also calculated. The Offsite Dose Calculation Manual (ODCM) considers persons visiting the Fermi 2 Visitors Center (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s/year), and persons ice fishing on Lake Erie near the plant (240 hour0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />s/year), to be visitors. Using ODCM assumptions about these categories of visitors, the maximum potential dose to a visitor to Fermi 2 in 2010 was 3.85E-03 mrem to the maximally exposed organ (thyroid) and 2.92E-03 mrem to the total body.

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Fermi 2 - 2010 Annual Radioactive Effluent Release Report Summary of Radioactive Waste Shipments The radioactivity and volume of Fermi 2 solid waste received at the Clive, UT, facility in 2010 is summarized in the following table:

Table 6 - Solid Waste Received At Burial Sites Est. total 12 month activity Type of waste Unit period error, %

Spent resins, sludges, etc. m 4.52E+01

__curies 7.71E+02 25 Dry compressible waste, m3 2.22E+02 contaminated equipment, etc. curies 1.90E+00 + 25 Irradiated components, control m 0 rods, etc. curies 0 N/A Other m3 0

_curies 0 N/A Radioactive solid waste shipments from Fermi 2 in 2010 (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 transportation Spent resin, sludges, etc. 23 Tractor trailer EnergySolutions, Oak Ridge, TN with cask EnergySolutions, Clive, UT Dry compressible waste, 46 Tractor trailer EnergySolutions, Oak Ridge, TN contaminated equipment, etc.

Oil 1 Tractor trailer EnergySolutions, Oak Ridge, TN Additional Required Information Appendices The contents of Appendix A, Effluent and Radwaste Data, are described on page 9.

Appendix B contains a description of the Fermi 2 Integrated Groundwater Protection Program, 2010 sampling data for this program, and a discussion of sampling results.

Appendix C contains the revised ODCM.

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Fermi 2 - 2010 Annual Radioactive Effluent Release Report ODCM Revisions The ODCM was revised once in 2010; the complete ODCM, including revisions approved in December 2010, is shown as Appendix C.

ODCM Monitors Out ofService The Offgas Radiation Monitor, Division 2, was out of service from February 15, 2010, to April 8, 2010 due to erratic monitor readings (referred to as "step changes" in readings),

and again from November 3, 2010 to December 13, 2010 due to calibration issues.

Difficulties in maintaining this offgas radiation monitor are related to equipment age.

Efforts are underway to improve monitor maintenance, upgrade monitor components, and purchase replacement equipment. The Division 1 Offgas Radiation Monitor remained in service throughout 2010 so that there was no loss of ability to monitor offgas radiation levels, and no compensatory sampling was required.

The Circulating Water Decant Line Radiation Monitor was out of service from November 4, 2010 to December 9, 2010 due to failure of the check source mechanism; the monitor itself remained functional. No compensatory sampling was required since there were no liquid radioactive discharges through the circulating water decant line during this period.

The Radwaste Building SPING monitor has been administratively removed from service since December 13, 2010. This monitor is not damaged. However, since Radwaste Building ventilation is not in service due to duct cleaning necessitated by the December 1, 2010, flooding event (see Abnormal Radiological Releases section),

required Radwaste Building SPING surveillances cannot be completed. This monitor will be returned to service after decontamination of Radwaste Building ventilation ducts is complete.

Outside Temporary Tanks In 2010 no outside temporary tank exceeded the 10 curie content limit for nuclides other than tritium and dissolved or entrained noble gases.

Meteorological Tables Meteorological tables for 2010 are not included in this report. Instead, in accordance with Section 5.9.1.8 of the Fermi 2 Offsite Dose Calculation Manual (ODCM), a summary file of required meteorological data for 2010 is retained on site and is available upon request.

Major Changes to Radioactive Waste Systems There were no major changes to radioactive waste systems in 2010.

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Fermi 2 - 2010Annual Radioactive Effluent Release Report Abnormal Radiological Releases On December 1, 2010, Fermi 2 inadvertently released radioactive water from a spill inside its radiologically restricted area (RRA) into its sanitary sewer system. Some of this water was pumped from the site septic tank into the sewer line leading to the Monroe wastewater treatment plant, from which it was discharged into Lake Erie at the Monroe Power Plant cooling water outfall. This incident began at 12:50 p.m. on December 1 and ended when the Fermi 2 sewage system was shut down at 4:01 p.m. After isolation of this sewer line, no further offsite release occurred. Prior to restoring this line to operation, it was flushed repeatedly until radioactivity was no longer detected; all waste was collected for disposal.

Two samples of the released water were obtained. Radionuclides were detected in both of these samples; the higher concentrations in the first sample were used to calculate quantities of radionuclides released. The following are conservative estimates of radionuclide activities released, dilution flows, and discharge concentrations in this event:

Cr-51: 2.33E-04 curies Mn-54: 1.57E-04 curies Co-58: 4.61E-05 curies Fe-59: 2.93E-05 curies Co-60: 1.98E-04 curies Zn-65: 3.74E-05 curies Total fission and activation product activity: 7.01E-04 curies H-3: 4.12E-03 curies Volume of discharge prior to dilution: 7.73E+04 liters Volume of dilution water used during discharge period: 7.52E+08 liters Average diluted concentration at point of discharge into Lake Erie:

Fission and activation products: 9.32E-10 uCi/ml Tritium (H-3): 5.48E-09 uCi/ml The preceding data were also used to calculate the maximum potential dose to a member of the public due to this event. This calculation showed a negligibly small offsite dose potential from the December 1 abnormal discharge: a dose of 1.3E-06 mrem to the total body and a maximum organ dose of 4.5E-06 mrem to the GI tract. These doses are much less than allowable offsite doses due to liquid effluents from Fermi 2. These allowable doses are 1.5 mrem per quarter and 3.0 mrem per year to the total body, and 5.0 mrem per quarter and 10.0 mrem per year to any organ, based on 10 CFR 50 Appendix I limits.

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Fermi2 - 2010 Annual Radioactive Effluent Release Report Appendix A Effluent and Radwaste Data 15

Fermi 2 - 2010 Annual Radioactive Effluent Release Report Regulatory Limits for Radioactive Effluents The Nuclear Regulatory Commission (NRC) limits on liquid and gaseous effluents are incorporated into the Fermi 2 Offsite Dose Calculation Manual. These limits prescribe the maximum doses and dose rates due to radioactive effluents resulting from normal operation of Fermi 2. These limits are described in the following sections.

A. Gaseous Effluents I. Dose rate due to radioactivity released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

a) Noble gases Less than or equal to 500 mrem/year to the total body.

Less than or equal to 3000 mrem/year to the skin.

b) Iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half lives greater than 8 days Less than or equal to 1500 mrem/year to any organ.

II. Air dose due to noble gases to areas at and beyond the site boundary shall be limited to the following:

a) Less than or equal to 5 mrad for gamma radiation Less than or equal to 10 mrad for beta radiation

- During any calendar quarter b) Less than or equal to 10 mrad for gamma radiation Less than or equal to 20 mrad for beta radiation

- During any calendar year III. Dose to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

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Fermi 2 - 2010 Annual Radioactive Effluent Release Report a) Less than or equal to 7.5 mrem to any organ

- During any calendar quarter b) Less than or equal to 15 mrem to any organ

- During any calendar year Note: The calculated site boundary dose rates for Fermi 2 are based on identification of individual isotopes and on use of dose factors specific to each identified isotope or a highly conservative dose factor. Average energy values are not used in these calculations, and therefore need not be reported.

B. Liquid Effluents I. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in Title 10 of the Code of Federal Regulations (10 CFR) Part 20 (Standards for Protection Against Radiation), Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases, as required by the Fermi 2 Offsite Dose Calculation Manual. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 (.0002) microcuries/ml total activity. This limit is based on the Xe-135 air submersion dose limit converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (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 17

Fermi 2 - 2010 Annual Radioactive Effluent Release 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 L Fission and Activation Gases Samples are obtained from each of the six plant radiation monitors which continuously monitor the five ventilation exhaust points. The fission and activation gases are quantified by gamma spectroscopy analysis of periodic samples.

The summary values reported are the sums of all fission and activation gases quantified at all monitored release points.

II. Radioiodines Samples are obtained from each of the six plant radiation monitors which continuously monitor the five ventilation exhaust points. The radioiodines are entrained on charcoal and then quantified by gamma spectroscopy analysis.

For each sample, the duration of sampling and continuous flow rate through the charcoal are used in determining the concentration of radioiodines. From the flow rate of the ventilation system, a rate of release can be determined.

The summary values reported are the sums of all radioiodines quantified at all continuously monitored release points.

18

Fermi 2 - 2010Annual Radioactive Effluent Release Report III.Particulates Samples are obtained from each of the six plant effluent radiation monitors which continuously monitor the five ventilation exhaust points. The particulates are collected on a filter and then quantified by gamma spectroscopy analysis.

For each sample, the duration of sampling and the 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.

The summary values reported are the sums of all particulates quantified at all monitored release points.

IV. Tritium Samples are obtained from each of the six plant effluent radiation monitors which continuously monitor the five ventilation exhaust points. The sample is passed through a bottle containing water and the gaseous tritium is collected in this 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.

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.

19

Fermi 2 - 2010 Annual Radioactive Effluent Release Report VI. Carbon-14 Carbon-14 releases are calculated using a method published by the Electric Power Research Institute in December 2010. Plant rated thermal power and quarterly capacity factors were used in the calculation of quarterly releases.

B. Liquid Effluents The liquid radwaste processing system and the liquid effluent monitoring system are described in the Fermi 2 UFSAR. Fermi 2 did not perform any routine releases of radioactive liquid effluents in 2010; however there was an inadvertent release on December 1, 2010 which is described on page 14 of this report.

C. Statistical Measurement Uncertainties The statistical uncertainty of the measurements in this section has been calculated and summarized in the following table:

Measurement Type Sample Type One Sigma Uncertainty Fission and Activation Gaseous 30%

Gases Radioiodines Gaseous 17%

Particulates Gaseous 16%

Tritium Gaseous 25%

Gross Alpha Gaseous 16%

Gaseous Releases by Individual Nuclide Values in the following tables which are preceded by the "less than" symbol represent the lower limit of detection (LLD) in units of microcuries per cubic centimeter (uiCi/cc) for individual samples, and indicate that the nuclide in question was not detected in gaseous effluent samples in the indicated quarter of 2010. For quantities of gross alpha radioactivity, tritium, and carbon-14 in gaseous effluents, see Tables 3 and 4 on page 10 of this report.

20

Fery'ni2 - 2010 Annital Radioactive Effluent Release Report A. Particulate Radionuclides (Curies)

Mn-54 <2.1-E-13--- 1.AE-.05 1.16E-04 7.12E-05 Co-58 <2.OE-13 5.86E-06 1.64E-04 7.46E-05 Co-60 7.60E-06 7.57E-06 1.20E-04 1.19E-04 Na-24 <2.7E-13 1.28E-04 2.OOE-03 4.OOE-04 Cr-51 <1.8E-13 3.79E-05 <1.8E-13 3.08E-04A Zn-65 <4.3E- 13 <4.3E- 13 6.401E-05 3.10E-05 Zn-69m <2.2E- 13 6. 1OE-05 1.78E-03 4.77E-04 Tc-99m <1.9E-13 1.41E-04 1.08E-03 4.89E-04 Ba-139 9.64E-02 9.291E-02 7.28E-02 4.22E-02 La-140 1.69E-04 9.99E-05 2.84E-05 1.51E-05 Ba-140 6.42E-05 2.84E-05 3.55E-05 <1.2E-13 Y-91M 1.24E-02 6.9 1E-03 4.441E-03 4.98E-03 Rb-89 4.61E-02 3.76E-02 <1.9E-10 1.47E-02 Cs-138 6.75E-02 1.58E-01 1.151E-02 3.26E-02 As-76 1.06E-02 1.44E-02 9.01E-03 6.21E-03 Br-82 7.67E-06 <1.9E-13 3.39E-05 <1.9E-13 Mn-56 <8.7E-12 <8.7E-12 5.35E-03 1.43,E-03 Sr-91 1.85E-04 2.35E-04 <2.7E-12 <2.7E-12 Sr-89 6.86E-05 2.39E-05 <4.5E-14 2.65E-05 Sr-90 4.96E-07 <2.9E- 15 <6.7E- 15 1.64E-06 Fe-55 2.02E-05 <1.5E-13 6.OOE-05 2.641E-04 Cs-134 <2.1E-13 <2.1E-13 <2.1E-13 <2.1E-13 Cs- 137 <2.9E- 13 <2.9E- 13 <2.9E- 13 <2.9E- 13 Ce- 141 <2.OE- 13 <2.OE-13 <2.OE-13 <2. OE- 13 Ce-143 <2.1E-13 <2.1E-13 <2.1E-13 <2.1E-13 Ce-144 <6.9E-13 <6.9E-13 <6.9E-13 <6.9E-13 Total 2.33E-01 3.10E-01 1.08E-01 1.04E-01 21

Fermi 2 - 2010Annual Radioactive Effluent Release Report B. Noble Gases (Curies)

Ar-41 8.77E-01 5.54E-01 2.48E-01 1.93E-01 Kr-87 <1.7E-07 <1.7E-07 <1.7E-07 <1.7E-07 Kr-88 <1.5E-07 <1.5E-07 <1.5E-07 <1.5E-07 Kr-85m 2.91E-01 6.87E-02 <2.1E-08 <2.1E-08 Xe-133 1.57E-01 <1.2E-07 <1.2E-07 <1.2E-07 Xe-133m <3.1E-07 <3.1E-07 <3.1E-07 <3.1E-07 Xe-135 5.36E-02 6.68E-02 <3.5E-08 <3.5E-08 Xe-135m 6.72E-01 <3.1E-07 3.24E-01 1.43E-01 Xe-137 <2.0E-05 <2.0E-05 1.27E+00 7.76E+00 Xe-138 8.43E-01 2.72E+00 8.86E-01 3.95E-01 Total 2.89E+00 3.41E+00 2.73E+00 8.49E+00 C. Radioiodines (Curies)

I-131 3.12E-04 7.60E-04 3.93E-04 2.88E-04 1-132 <7.6E-13 2.80E-04 1.80E-03 <7.6E-13 1-133 1.33E-03 2.39E-02 3.03E-03 1.74E-03 1-134 <5.1E-12 <5.1E-12 <5.1E-12 <5.1E-12 1-135 <1.4E-12 5.35E-04 1.21E-03 <1.4E-12 Total 1.64E-03 2.55E-02 6.43E-03 2.03E-03 Shipments of Radwaste Fermi 2 complies with the extensive federal regulations which govern radioactive waste shipments. Radioactive solid waste shipments from the Fermi 2 site consist of waste generated during water treatment, radioactive trash, irradiated components, etc.

Shipment destinations are either a licensed burial site or intermediate processing facilities. Waste shipped to intermediate processing facilities is shipped directly from these facilities to a licensed burial site after processing. The following tables contain estimates of major nuclide composition, by class of waste, of Fermi 2 solid radwaste received at the Clive, UT, facility in 2010.

a. Spent resins, sludges, etc. All waste in this category in 2010 was Class A waste and consisted of spent resins. It was shipped in either High Integrity Containers or Polyethylene Liners, within shielded transportation casks, directly to the Clive, UT, burial facility or to an intermediate processor. Waste sent directly to a disposal facility was dewatered prior to shipment. All quantities were determined by measurement.

22

Ferini 2 - 2010 Annual Radioactive Effluent Release Report Spent Resins (Class A)

Activity Isotope mCi Percent Ag-110m 5.24E+02 0.07%

Am-241 2.5413-02 0.00%

Ba-140 2.22E+00 0.00%

C-14 1.09E+02 0.01%

Cm-242 1.11 E-02 0.00%

Cm-243 1.46E-01 0.00%

Cm-244 1.4513-01 0.00%

Co-57 2.91E+01 0.00%

Co-58 4.66E+02 0.06%

Co-60 1,37E+/-05 17.71%

Cr-51 1.96E+02 0.03%

Cs-134 1.61E+/-02 0.02%

Cs-137 1.39E+03 0.18%

Fe-55 5.83E+05 75.67%

Fe-59 1.2213+02 0.02%

H-3 2.59E+02 0.03%

1-129 2.66E+00 0.00% LLD 1-13 1 2.60E+00 0.00%

La-140 1.69E+/-00 0.00%

Mn-54 3.1613+/-04 4.10%

Nb-95 6.OOE-01 0.00%

Ni-63 6.5013+03 0.84%

Pu-238 1.04E-01 0.00%

Pu-239 5.75E-02 0.00%

Pu-240 5.75E-02 0.00%

Pu-241 4.12E+/-00 0.00%

Sb- 124 9.851E+/-00 0.00%

Sb-125 4.93E+00 0.00%

Sr-89 2.48E+01 0.00%

Sr-90 1.46E+01 0.00%

Tc-99 2.01E+01 0.00% LLD Zn-65 9.90E+03 1.28%

Total Activity 7.71LE+05 100.00%

Volume Shipped (Mn) 4.52E+/-01_________

23

Fermi 2 - 2010 Annual Radioactive Effluent Release Report

b. Dry compressible waste, contaminated equipment, etc. Waste in this category in 2010 was shipped in strong tight containers, and was classified as Dry Active Waste (DAW). All waste in this category was Class A waste. The DAW was compacted, and sent for direct disposal or incinerated by an intermediate processor. All quantities were determined by measurement.

Dry Active Waste (Class A)

Activity Isotope mCi Percent C-14 3.22E+01 1.70% LLD Co-58 2.55E+00 0.13%

Co-60 1.38E+02 7.29%

Cr-51 1.83E+00 0.10%

Fe-55 1.54E+03 81.07%

Fe-59 1.77E+00 0.09%

H-3 4.52E+01 2.38%

1-129 1.57E+00 0.08% LLD Mn-54 1.54E+02 8.13%

Ni-63 6.93E+00 0.36%

Sb-124 2.91E-01 0.02%

Tc-99 3.47E+01 1.83% LLD Zn-65 8.83E+00 0.47%

Total Activity (mCi) 1.90E+03 100.00%

Volume Disposed (nm) 2.22E+02

c. Irradiated components, control rods, etc.: No waste in this category

d. Other: One shipment of oil was made to the Energy Solutions facility in Oak Ridge, TN. This oil is awaiting incineration. As this waste has not been processed, no activity or volume is reported.

24

Ferini2 - 2010 Annual Radioactive Effluent Release Report Appendix B Ground Water Protection Program Data and Analysis 25

Fermi 2 - 2010 Annual Radioactive Effluent Release Report EXECUTIVE

SUMMARY

Fermi personnel conclude that the occasional positive tritium sample results in ground water from the shallow and deep monitor wells is not due to a leak from plant systems.

Tritium in ground water in the shallow aquifer is the result of washout and recapture of tritium in precipitation that has passed through gaseous effluent from monitored plant systems. Low-level positive tritium results in ground water from the bedrock aquifer have been found in several different wells across the site. Due to plant design, site geology, and the depth of these wells relative to plant systems, it is highly improbable that these very low-level positive results could be attributed to a spill or leak from a plant system without tritium activities in adjacent shallow wells being several orders of magnitude higher than have been identified to date.

PROGRAM OVERVIEW Quarterly sampling and gauging of the Fermi 2 Integrated Ground Water Protection Program (IGWPP) monitor wells continued uninterrupted in 2010. 2010 Ground-water samples analyzed for tritium were distilled and analyzed using liquid scintillation technology with a 500 pCi/L Lower Limit of Detection (LLD); however, the contract laboratory regularly achieved LLDs less than 200 pCi/L.

Procedurally, each IGWPP specified monitor well is sampled for tritium and plant-related gamma-emitting radioisotopes each quarter. Furthermore, once per year water from three monitor wells most likely to be contaminated by leaked or spilled material is analyzed for hard-to-detect (HTD) radionuclides (Fe-55, Sr-89, and Sr-90).

In 2010 Fermi personnel began taking an additional sample split for tritium analysis.

These samples were analyzed for the presence of tritium by the Fermi chemistry laboratory. This change was implemented to ensure more accurate data for shipping the samples to the offsite contract laboratory, but, more importantly, to quickly determine if abnormally high levels of tritium were in site ground water.

RESULTS Samples analyzed for gamma-emitting radionuclides, as well as HTDs, are counted to environmental LLDs for each given radioisotope of interest, with the exception of La-140 and Ba-140 (due to their extremely short half-lives). For tritium there is no required limit of detection, beyond what is prescribed for ground water samples taken as part of the site's REMP. The REMP LLD is set at 2,000 pCi/L which is 1/10 th of the EPA's drinking water limit of 20,000 pCi/L. Fermi 2's contract laboratory achieved LLDs for tritium of 317 pCi/L, or less, for all ground-water samples taken during 2010.

Deep Wells (Table 1)

Tritium was not detected in samples of ground water from the Fermi 2 deep monitor wells, with the periodic exception of ground-water samples from monitor wells EF2 003D, EF2-07-004D, EF2-07-006D, EF2-07-008D, EF2-07-009D, EF2-07-020D, and EF2-07-029D. The positive results for tritium from water in these monitor wells range from 207 - 424 pCi/L.

26

Fermi 2 - 2010 Annual Radioactive Effluent Release Report Monitor well EF2-07-020D second quarter sample tritium result was initially reported as 3,460 pCi/L. This deep well is located between the Fermi 2 Primary Access Portal and the Fermi 1 Fuel Assembly and Repair Building. Reanalysis of the original sample, as well as subsequent samples all were non-detect for tritium at the 300 pCi/L level.

Plant-related gamma-emitting radioisotopes were not detected in any samples collected from deep monitor wells in 2010.

Shallow Wells (Table 2)

Most shallow monitor wells have consistently yielded results indicating that tritium is not present at the detection limit. Shallow monitor wells, where trace levels of tritium have been detected, yielded sporadic and variable tritium activities that are all less than 920 pCi/L, with exception of monitor well EF2-07-031S that produced water with a result of 1260 pCi/L in the second quarter of the year.

Monitor well EF2-07-016S first quarter sample was initially reported as 750 pCi/L. This well is located adjacent to Lake Erie east of the Fermi 2 Circulating Water Pump House.

Reanalysis of the original ground-water sample, as well as all subsequent samples, were all non-detect for tritium at the 300 pCi/L level.

Plant-related gamma-emitting radioisotopes and hard-to-detect radioisotopes were not detected in any ground-water samples collected from shallow monitor wells in 2010.

DISCUSSION This is the third annual review of results of ground-water sampling performed in compliance with the Fermi Energy Center IGWPP. Results of tritium analysis of ground water sampled in 2010 have shown that many of the site's wells have never had a positive result for that radionuclide. In 2010, positive ground water results for tritium ranged from 100 - 1260 pCi/L.

Well EF2-07-03 1S produced a sample in the second quarter of 2010 with a tritium value of 1260 pCi/L. This monitor well is located south the AIB, in an area far from any plant components containing tritiated water. Furthermore, there are several shallow monitor wells (EF2-07-005S, EF2-07-007S, EF2-07-020S, and EF2-07-021S) located between plant systems containing tritiated water and monitor well EF2-07-031S and most of the samples from these wells were either non-detect for tritium or had sporadic positive values all less than 487 pCi/L. Well EF2-07-031S is located in a gravelly area that sometimes experiences ponding after heavy rains, precipitation events of long duration, or after snow melt. The tritium value seen in the second quarter ground-water sample from monitor well EF2-07-031S is attributed to washout and recapture of tritium from monitored gaseous effluent releases in precipitation.

If the tritium found in ground water from shallow wells were attributable to a leaking plant system then one would expect the levels to steadily increase over time, especially during the winter when there is less recharge from surface water. Instead the results from 27

Fermi 2 - 2010 Annual Radioactive Effluent Release Report shallow monitor wells show periodic low-level hits for tritium in ground water with no trend. This pattern is more consistent with what one would expect to see if the tritium were attributable to recapture in precipitation. Recapture of tritium emitted from nuclear power plant stacks in precipitation is well documented and these emissions are continuously monitored and reported annually by the utility as part of an approved effluents program. A tritium rain water washout study performed at the Fermi site revealed that tritium is found in rain water collected at the site. Tritium activity in rain water samples, taken at the site over a period of two months, ranged from ca. 400 pCi/L to 5,750 pCi/L.

In 2010 tritium was found at very low levels in several deep monitor wells. The positive results were sporadic, low level, and do not show any spatial trend. The deep monitor wells are screened 40-45 feet below ground surface in bedrock. An approximately 10-foot thick inorganic clay layer between surficial aquifer and the bedrock aquifer impedes flow to such a degree that the bedrock aquifer is saturated and under pressure to the point that static pressure in deep monitor wells rises to a level several feet above the top of the clay layer. Plant components, outside of buildings, that contain large quantities of highly tritiated water are either above ground in tanks or in piping running through aggregate at or above the water table. If these components were to generate a leak the contamination would be evident by the presence of high levels of activity in nearby shallow monitor wells screened in the surficial aquifer. Under these conditions (hydrogeological and plant construction) it is highly improbable that the positive tritium values in ground water from deep monitor wells are indicative of plant-related tritium because there is no known pathway for plant-related tritium to contaminate the bedrock aquifer.

Furthermore, natural radioisotopes commonly found in bedrock, such as Pb-210, produce low-energy betas in a similar energy range as tritium and may cause spurious results.

The low-level of activity in ground water from the deep monitor wells may also be attributable to chemiluminescence due to natural compounds that occur in the hard water from the bedrock (Bass Islands Group) dolomite.

Fermi's contract laboratory is achieving detection limits that are below levels that the state of Michigan periodically finds when sampling surface water in Lake Erie. This suggests that current levels of detection used by the Fermi contract laboratory for tritium are so low that some positive values are most likely the upper levels of the range of background values for tritium in the region.

In 2010 the Fermi personnel initiated three emergent sample events: two events were in response to ground-water sample tritium results that were higher than expected and one event was in response to the excursion of plant process water and contaminated resin beads to the sanitary sewer system. In the cases where emergent sample events were initiated in response to questionable sample results, subsequent samples proved that the initial results were erroneous, due to contract laboratory error. The last emergent sample event revealed that contamination in the sanitary sewer system was not leaked to ground water.

28

Ferini2 - 2010 Annual Radioactive Effluent Release Report Table 1: Deep Monitor Well Tritium Analysis Results for Year 2010.

MONITOR LAB WELL EVENT ID QA TYPE ID PARAMETER PREFIX VALUE UNITS EF2-07-OOID P-2010-G-Q1 NORMAL GEL 11-3 <LLD PCI/L EF2-07-001D P-2010-G-Q1 DUPLICATE GEL H-3 <LLD PCI/L EF2-07-001D P-2010-G-Q2 NORMAL GEL H-3 <LLD PCI/L E172-07-0011) P-2010-G-Q3 NORMAL GEL H-3 <LLD PCI/L E172-07-0011) P-2010-G-Q4 NORMAL GEL H-3 <LLD PCI/L E172-07-003D P-2010-G-QI NORMAL GEL H-3 <LLD PCI/L EF2-07-003D P-2010-G-Q2 NORMAL GEL H-3 <LLD PCI/L E172-07-0031) P-2010-G-Q3 DUPLICATE GEL 11-3 <LLD PCI/L EF2-07-003D P-2010-G-Q3 NORMAL GEL 11-3 <LLD PCI/L EF2-07-003D P-2010-G-Q4 NORMAL GEL H-3 270 PCI/L EF2-07-004D P-2010-G-Q1 NORMAL GEL H-3 393 PCI/L EF2-07-004D P-2010-G-Q2 NORMAL GEL H-3 284 PCI/L EF2-07-004D P-2010O-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-004D P-2010O-G-Q4 NORMAL GEL H-3 <LLD PCI/L EF2-07-004D P-2010-G-Q4 DUPLICATE GEL 11-3 <LLD PCI/L EF2-07-006D P-2010-G-QI NORMAL GEL 11-3 207 PCI/L EF2-07-006D P-2010O-G-Q2 NORMAL GEL 11-3 <LLD PCI/L EF2-07-006D P-2010-G-Q3 NORMAL GEL 11-3 <LLD PCI/L EF2-07-006D P-2010-G-Q4 NORMAL GEL H-3 <LLD PCI/L EF2-07-008D P-2010-G-Ql NORMAL GEL H-3 <LLD PCI/L EF2-07-008D P-2010-G-Q2 NORMAL GEL 11-3 334 PCI/L EF2-07-008D P-2010-G-Q3 NORMAL GEL 11-3 <LLD PCI/L EF2-07-008D P-2010-G-Q4 NORMAL GEL H1-3 303 PCI/L EF2-07-009D P-2010-G-Q1 NORMAL GEL 11-3 421 PCI/L EF2-07-009D P-2010-G-Q2 NORMAL GEL 11-3 424 PCI/L EF2-07-009D P-2010-G-Q3 NORMAL GEL 11-3 <LLD PCI/L EF2-07-009D P-2010-G-Q4 NORMAL GEL 11-3 262 PCI/L EF2-07-015D P-2010-G-Q1 NORMAL GEL 11-3 <LLD PCI/L EF2-07-015D P-20t0-G-Q2 NORMAL GEL 11-3 <LLD PCI/L EF2-07-015D P-2010-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-015D P-2010-G-Q4 NORMAL GEL 11-3 <LLD PCI/L EF2-07-020D P-2010-G-Ql NORMAL GEL H-3 295 PCI/L EF2-07-020D P-2010-G-Q2 NORMAL GEL 11-3 278 PCI/L EE2-07-020D P-2010-G-Q3 NORMAL GEL 11-3 <LLD PCI/L EF2-07-020D P-2010-G-Q4 NORMAL GEL 11-3 297 PCI/L EF2-07-029D P-2010-G-Q1 NORMAL GEL 11-3 <LLD PCI/L EF2-07-029D P-2010-G-Q2 NORMAL GEL 11-3 <LLD PCI/L EF2-07-029D P-2010-G-Q3 NORMAL GEL 11-3 <LLD PCI/L EF2-07-029D P-2010O-G-Q4 NORMAL GEL H1-3 284 PCI/L 29

Fermni2 - 2010 Annual Radioactive Effluent Release Report Table 2: Shallow Monitor Well Tritium Analysis Results for Year 2010.

MONITOR LAB WELL EVENT ID QA TYPE ID PARA-METER PREFIX VALUE UNITS EF2-07-002S P-2010-G-Q1 NORMAL GEL H-3 <LLD PCI/L EF2-07-002S P-201I0-G-Q2 NORMAL GEL H-3 <LLD PCI/L EF2-07-002S P-2010O-G-Q2 DUPLICATE GEL H-3 <LLD PCI/L EF2-07-002S P-2010O-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-002S P-201I0-G-Q4 NORMAL GEL H1-3 <LLD PCI/L EF2-07-003S P-2010-G-Q1 NORMAL GEL H-3 231 PCILL EF2-07-003S P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCI/L EF2-07-003S P-2010-G-Q3 NORMAL GEL H1-3 <LLD PCI/L EF2-07-003S P-2010-G-Q4 NORMAL GEL H1-3 <LLD PCI/L E172-07.-005S P-2010-G-Q1 NORMAL GEL H1-3 376 PCI/L EF2-07-005S P-2010O-G-Q2 NORMAL GEL H-3 487 PCI/L EF2.-07-005S P-2010-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-005S P-2010O-G-Q4 NORMAL GEL H1-3 215 PCTI/

EF2-07-007S P-2010-G-QI Note 1 EF2-07-007S P-2010O-G-Q2 NORMAL GEL H-3 356 PCI/L EF2-07-007S P-2010O-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-007S P-2010O-G-Q4 NORMAL GEL H1-3 <LLD PCI/L EF2-07-008S P-2010-G-Q1 NORMAL GEL H-3 <LLD PCI/L EF2-07-008S P-2010O-G-Q2 NORMAL GEL 11-3 <LLD PCI/L EF2-07-008S P-2010O-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-008S P-2010-G-Q4 NORMAL GEL H-3 <LLD PCI/L EF2-07-012S P-2010-G-Q1 NORMAL GEL H-3 <LLD PCI/L EF2-07-012S P-2010-G-Q2 NORMAL GEL H-3 270 PCI/L EF2-07-012S P-2010O-G-Q2 DUPLICATE GEL H-3 <LLD PCI/L EF2-07-0 12S P-2010O-G-Q3 Note 2 EF2-07-012S P-2010O-G-Q4 NORMAL GEL H-3 297 PCT/L EF2-07-013S P-2010-G-Q1 NORMAL GEL 11-3 678 PCI/L EF2-07-013S P-2010-G-Q2 NORMAL GEL H-3 592 PCI/L EF2-07-013S P-2010-G-Q3 NORMAL GEL H-3 257 PCI/L EF2-07-013S P-2010O-G-Q3 DUPLICATE GEL H-3 <LLD PCI/L EF2-07-0 13S P-2010O-G-Q4 NORMAL GEL H-3 663 PCI/L EF2-07-014S P-2010-G-Q1 NORMAL GEL H-3 374 PCI/L EF2-07-014S P-2010-G-Q2 NORMAL GEL H-3 346 PCI/L EF2-07-014S P-201 O-G-Q3 NORMAL GEL H-3 331 PCI/L EF2-07-014S P-2010-G-Q4 DUPLICATE GEL H-3 521 PCI/L EF2-07-014S P-2010O-G-Q4 NORMAL GEL H-3 479 PCI/L EF2-07-015S P-2010-G-Ql NORMAL GEL H-3 <LLD PCI/L EF2-07-015S P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCI/L EF2-07-015S P-2010O-G-Q3 NORMAL GEL 11-3 <LLD PCT/L EF2-07-015S P-2010O-G-Q4 NORMAL GEL H-3 <LLD PCI/L EF2-07-016S P-2010-G-Q1 NORMAL GEL 11-3 100 PCI/L EF2-07-016S P-2010-G-Q2 NORMAL GEL H-3 <LLD PCI/L EF2-07-016S P-2010-G-Q3 NORMAL GEL 11-3 <LLD PCI/L EF2-07-016S P-2010-G-Q4 NORMAL GEL H-3 <LLD PCI/L EF2-07-017S P-2010-G-Q1 NORMAL GEL H-3 <LLD PCI/L EF2-07-017S P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCI/L EF2-07-017S P-201 O-G-Q3 NORMAL GEL 11-3 <LLD PCI/L 30

Fermi 2 - 2010 Annual Radioactive Effluent Release Report EF2-07-017S P-.2010-G-Q4 NORMAL GEL H-3 <LLD PCI/L EF2-07-018S P-2010-G-Q1 NORMAL GEL H-3 303 PCI/L EF2-07-018S P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCI/L EF2-07-018S P-2010-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-018S P-2010-G-Q4 NORMAL GEL H-3 <LLD PCI/L EF2-07-019S P-2010-G-Q1 NORMAL GEL H-3 436 PCI/L EF2-07-019S P-2010-G.-Q2 NORMAL GEL H-3 <LLD PCI/L E172-07-019S P-2010-G-Q3 NORMAL GEL H-3 278 PCI/L EF2-07-019S P-2010O-G-Q4 NORMAL GEL H-3 428 PCI/L EF2-07-.020S P-2010-G-Q1 NORMAL GEL H-3 <LLD PCI/L EF2-07-020S P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCI/L EF2-07-020S P-2010-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-020S P-2010O-G-Q4 NORMAL GEL H-3 <LLD PCI/L.

E172-07-021S P-2010-G-Q1 DUPLICATE GEL H-3 <LLD PCI/L E172-07-021 S P-2010-G-Qt NORMAL GEL H-3 <LLD PCI/L EF2-07-021 S P-201 O-G-Q2 NORMAL GEL H-3 329 PCI/L EF2-07-021 S P-2010O-G-Q3 NORMAL GEL H-3 <LLD PCI/L E172-07-021 S P-2010O-G-Q4 NORMAL GEL H-3 297 PCI/L E172-07-022S P-2010-G-Q1 NORMAL GEL H-3 <LLD PCI/L E172-07-022S P-2010-G-Q2 NORMAL GEL H-3 <LLD PCI/L EF2-07-022S P-2010-G-Q2 DUPLICATE GEL H-3 <LLD PCI/L EF2-07-022S P-2010O-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-022S P-2010O-G-Q4 NORMAL GEL H-3 <LLD PCI/L EF2-07-023S P-2010-G-Q1 NORMAL GEL H-3 254 PCI/L EF2-07-023S P-2010O-G-Q2 NORMAL GEL H-3 620 PCI/L EF2-07-023S P-2010-G-Q3 DUPLICATE GEL H-3 <LLD PCI/L EF2-07-023S P-2010-G-Q3 NORMAL GEL H1-3 <LLD PCI/L EF2-07-023S P-2010-G-Q4 NORMAL GEL H1-3 919 PCI/L EF2-07-024S P-2010-G-Q1 NORMAL GEL H-3 237 PCI/IL EF2-07-024S P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCI/L EF2-07-024S P-2010O-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-024S P-.2010O-G-Q4 NORMAL GEL H-3 <LLD PCI/L EF2-07-024S P-2010O-G-Q4 DUPLICATE GEL H1-3 <LLD PCI/L EF2-07-025S P-2010-G-Q1 NORMAL GEL H-3 361 PCI/L.

EF2-07-025S P-2010O-G-Q2 NORMAL GEL H-3 316 PCI/L EF2-07-025S P-2010O-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-025S P-2010O-G-Q4 NORMAL GEL H1-3 <LLD PCI/L.

EF2-07-026S P-2010-G-Q1 NORMAL GEL H1-3 <LLD PCI/I.

EF2-07-026S P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCI/L EF2-07-026S P-2010-G-Q3 NORMAL GEL 11-3 <LLD PCI/IL EF2-07-026S P-2010-G-Q4 NORMAL GEL H-3 281 PCI/L EF2-07-027S P-2010-G-Q1 NORMAL GEL 11-3 <LLD PCI/I.

EF2-07-027S P-2010-G-Q2 NORMAL GEL 11-3 <LLD PCI/L.

EF2-07-027S P-201 O-G-Q3 NORMAL GEL H-3 <LLD PCI/I.

EF2-07-027S P-2010O-G-Q4 NORMAL GEL H-3 <LLD PCI/I.

EF2-07-028S P-2010-G-Q1 NORMAL GEL H-3 <LLD PCI/I.

EF2-07-028S P-2010-G-Q2 NORMAL GEL H-3 <LLD PCI/I.

EF2-07-028S P-2010-G-Q3 NORMAL GEL H-3 <LLD PCI/L EF2-07-028S P-2010-G-Q4 NORMAL GEL H-3 <LLD PCI/I.

EF2-07-029S P-2010-G-Q1 NORMAL GEL H-3 <LLD PCI/I.

31

Fermni2 - 2010 Annual Radioactive Effluent Release Report EF2-07-029S P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCY/L EF2-07-029S P-201 O-G-Q3 NORMAL GEL H-3 <LLD PCF!L EF2-07-029S P-201 O-G-Q4 NORMAL GEL H-3 <LLD PCI/L EF2-07-031 S P-2010-G-Ql NORMAL GEL H-3 241 PCI/L E172-07-03 IS P-2010-G-QI DUPLICATE GEL H-3 237 PCI/L EF2-07-031IS P-2010O-G-Q2 NORMAL GEL H-3 1260 PCV/L E172-07-031 S P-201 O-G-Q3 NORMAL GEL H-3 <LLD PCI/L E172-07-031IS P-2010O-G-Q4 NORMAL GEL H-3 291 PCF'I MW-10 P-2010-G-Ql NORMAL GEL H-3 <LLD PCI/L MW-10 P-2010-G-Q2 Note 3 MW-10 P-201 O-G-Q3 NORMAL GEL H-3 <LLD PCI/L MW-10 P-2010-G-Q4 Note 2 MW-il P-2010-G-Ql NORMAL GEL H-3 <LLD PCI/L MW-il1 P-2010-G-Ql DUPLICATE GEL H-3 <LLD PCI/L MW-Il1 P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCI/L MW-il P-201 O-G-Q3 NORMAL GEL H-3 <LLD PCI/L MW-il P-2010-G-Q4 NORMAL GEL H-3 <LLD PCI/L MW-18 P-2010-G-Ql NORMAL GEL H-3 253 PCI/L MW-18 P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCI/L MW-18 P-2010-G-Q3 NORMAL GEL H-3 <LLD PCI/L MW-18 P-2010O-G-Q4 NORMAL GEL H1-3 <LLD PCV/L MW-21 P-2010-G-QI DUPLICATE GEL H-3 <LLD PCI/L MW-21 P-2010-G-Q1 NORMAL GEL H-3 <LLD PCI/L MW-21 P-2010O-G-Q2 NORMAL GEL H-3 <LLD PCI/L MW-21 P-2010-G-Q3 NORMAL GEL H-3 <LLD PCI/L MW-21 P-2010O-G-Q4 Note 2 MW-9 P-2010-G-QI NORMAL GEL H1-3 <LLD PCFIL MW-9 P-2010-G-Q2 NORMAL GEL H1-3 <LLD PCI/L MW-9 P-2010O-G-Q3 NORMAL GEL H-3 <LLD PCI/L MW-9 P-2010O-G-Q4 Note 2 Note 1: Sample was broken in transit to contract laboratory.

Note 2: Well could not be sampled - obstructed by equipment.

Note 3: Well could not be sampled - due to ponding at location.

32

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Fermi 2 - 2010 Annual Radioactive Effluent Release Report Appendix C Offsite Dose Calculation Manual Revision 34

OFFSItE DOSE CALCULATION MANUAL Pages Revised in Latest Revision

ý0-1, 3-6, 3-24, 3-25, 3-44, 5-4, 7-4, 7-19, and 10-9 Implementation Plan These revisions go into effect upon approval.

CONTROLLED DSN Reision Informatfon and Procedures DS eiinChange#f DTC File # 11 TRM VOL 11 20 10-01 6-ODM TMTRM 1754 IP Code Date Approved Released By Date Issued Recipient I__I__ N/0___ NIA~~ L/ 1d)

FERMI 2 ODCM - TRM VOLUME 11 0-1 Rev. 20

FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOLUME 11I- LIST OF EFFECTIVE PAGES OFFSITE DOSE CALCULATION MANUAL Revision Pag Revision 0-1 20 3-15 13 19- 110 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 20 2-1 13 3-25 20 2-2 14 3-26 18 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 18 3-1 13 3-33 18 3-2 14 3-34 13 3-3 14 3-35 18 3-4 15 3-36 13 3-5 13 3-37 18 3-6 20 3-38 13ab 3-7 14 3-39 13 3-8 14 3-40 13 3-9 13 3-41 13 3-10 18 3-42 13 3-11 13 3-43 13 3-12 13 3-44 20 iao 3-13 19 3-45 13 3-14 13 3-46 13 FERMI 2 ODGM - TRM VOLUME 11 LEP-!l Rev. 20 122010

FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOLUME Il- LIST OF EFFECTIVE PAGES OFFSITE DOSE CALCULATION MANUAL PaeRevision EmQe Revision 4-1 13 6-19 13 4-2 13 6-20 13 al 4-3 13 6.21 13I 1o 4-4 13 6-22 13 4-5 13 4-6 13 4-7 13 7-1 13 4-8 13 7-2 18 7-3 13 5-1 13 7-4 2012-o 5-2 13 7-5 13 5-3 13 7-6 13 5-4 20 *7-7 13 1-1 5-5 13 7-8 13 121 7-9 13 6-1 13 7-10 18 6-2 13 7-11 13 6-3 14 7-12 14 6-4 13 7-13 18 6-5 13 7-14 18 6-6 13 7-15. 13 6-7 14 7-16 13 6-8 14 7-117 18 6-9 13 7-18 13 6-10 13 7-19 20 21 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 11 LEP-2 Rev. 20 122010

FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOLUME 11I- LIST OF EFFECTIVE PAGES OFFSITE DOSE CALCULATION MANUAL Paqe Revision Page Revision 7-27 13 9-1 13 7-28 13 9-2 13 7-29 13 9-3 IB 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 19 7-37 13 10-6 19 7-38 13 10-7 19 7-39 13 10-8 19 7-40 13 10-9 20 7-41 13 10-10 13 2o 7-42 13 10-11 13 7-43 13 10-12 13 7-44 13 10-13 18 7-45 13 10-14 18 7-46 13 10-15 18 7-47 '13 7-48 13 7-49 13 7-50 13 8-1 13 8-2 13 8-3 13 8-4 13 8-5 13 8-6 13 8-7 13 8-8 13 8-9 13 FERMI 2 ODCM - TRM VOLUME 11 L.EP-3 Rev, 20 122010

TABLE OF CONTENTS Page 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 3/4.11.2.1 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, Iodine-133, Tritium, and Radionuclides in Particulate Form 3-29 3/4.11.2.4 Offgas Treatment System 3-30 3/4.11.2.5 Ventilation Exhaust Treatment System 3-31 3/4.11.2.8 Venting or Purging 3-32 3/4.11.4 Radioactive Effluents Total Dose 3-33 3/4.12.1 Radiological Environmental Monitoring Program 3-44 3/4.12.2 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

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 (D11-N402) 6-10 6.3.3 Generic, Conservative Alarm Setpoint for D11-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)

Page 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 Page 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 3.12.1-1 Radiological Environmental Monitoring Program 3-40 3.12.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3-41 4.12.1-1 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 II 0-5 Rev. 13

TABLE OF CONTENTS (continued)

TABLES (continued)

Page 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 Page Figure 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

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 11 1-1 Rev. 13

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 11 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 II 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 arelimited to 2E-4 uCi/ml 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

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 II 2-5 Rev. 14

TABLE 2.1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY S ................................... .................................At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D ................................................ .................. .At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W ....... ....... ...................... ........ ............ At least once per 7 days.

M ................... ......... .. ................. .. ........... At least once per 31 days.

Q .................. ............................... ................. At least once per 92 days.

SA ................................................................ ..... A t least once per 184 days.

A .................................................................. At least once per 366 days.

R ......... ..... ............................................ At least once per 18 months (550 days).

S/U ........................................ ................... rior 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(a) .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 3/4.0 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:

1. Mode 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />;

2. Mode 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and

3. Mode 4 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.

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

3/4.0 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

3/4.0 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 provsion 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 II 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 alarm/trip 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

~.... .. . -, ,

~~A~'wMX;!h**'h ,,.

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line Dll-N007 1 110

2. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Circulating Water Reservoir Decant Line D11-N402 1 111

3. FLOW RATE MEASUREMENT DEVICES*

a. Liquid Radwaste Effluent Line G11-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. The circulating water reservoir decant line flow rate device was deleted from this table; the Liquid Radwaste Effluent Line flow rate 12.] I) device refers to a monitor on the radwaste blowdown line from the Waste Sample Tanks, upstream of the circulating water decant line.

FERMI 2 ODCM - TRM VOLUME II 3-6 Rev. 20

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 4.11.1.1.1, 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10- 7 microcurie/ml, for Cs-137. 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line P P R(3) Q(1) (2)

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Circulating Water Reservoir Decant Line D M R(3) Q(5)

D11-N402

3. FLOW RATE MEASUREMENT DEVICES (4)

a. Liquid Radwaste Effluent Line D(4) N.A. R Q 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 II 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.

Note: Page content was last changed with ODCM Revision 15.

FERMI 2 DCM -TRM VOLUME 3-10 Rev. 18

TABLE 3.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Functionally Applicability Action Capable

1. REACTOR BUILDING EXHAUST PLENUM EFFLUENT 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

2. OFFGAS MONITORING SYSTEM (At the 2.2 minute delay piping)

a. Noble Gas Activity Monitor - Providing Alarm 1 ** 126

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.

1. 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

5. RADWASTE BUILDING 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

6. ONSITE STORAGE BUILDING VENTILATION EXHAUST RADIATION MONITOR

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.

FERMI 2 ODCM - TRM VOLUME II 3-12 Rev. 13

TABLE 3.3.7.12-1 (Continued)

S-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 <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. 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 <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. 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 provided that:

a. The offgas system is not bypassed,

b. The reactor building exhaust plenum noble gas effluent (downstream) monitor is FUNCTIONALLY CABAPLE, and

c. Grab samples are taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and these samples are analyzed for principal emitters within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with calculation of offgas radioactivity rate.

Otherwise, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

FERMI 2 ODCM - TRM VOLUME II 3-13 Rev. 19

TABLE 4.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Modes in Instrument Channel Source Channel Functional Which Check Check Calibration st Surveillance Required

1. REACTOR BUILDING EXHAUST PLENUM

a. Low Range Noble Gas Activity Monitor - D M R(2) Q(1)

• Providing Alarm

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 N.A. R Q *

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(1) #

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 N.A. 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 W N.A. N.A. N.A.

d. Sampler Flow Rate Monitor 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 Functional Which Check Check Calibration Test Surveillance Required

5. 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. *

d. Sampler Flow Rate Monitor D N.A. R Q

• I6. ONSITE STORAGE BUILDING VENTILATION EXHAUST RADIATION MONITOR

a. Low Range Noble Gas Activity Monitor D M R(2) Q(1) *

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 N.A. R Q

• 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.

1. 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, y 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 3/4.11.1 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 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 1 0 -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 4.11.1.1.1-1.

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 3.11.11.1 FERMI 2 ODCM - TRM VOLUME II 3-17 Rev. 13

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/ml)

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 1 x 10- 5 Each Batch Composited Gross Alpha 1 x'0-7 P Q 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 x10 - 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 x10-8 NA Q Composited Fe-55 1 x 10- 6 FERMI 2 ODCM - TRM VOLUME II 3-18 Rev. 14

TABLE 4.11.1.1.1-1 (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 s b E

• V

• 2.22 x 106

• Y *exp (- It)

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 ideritifiable, 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 3/4.11.2 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. For 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

TABLE 4.11.2.1.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM of Aptfv drf I 4rTamwj~

Gaseow,Ae]ease 4,T7c~ Aayi Anal 4' Tp Frequfeng,aL-.. .

4 A. Containment P! jP,S rnia am Ix10 PUGPeEach PURGE Each PURGE Emittersb Treatment) Grab Sample p1 H-3 I x 0-B. Reactor Building Exhaust Plenum Mc,e MG Principal Gamma I~x0-Standby Gas Emittersb Treatment Systemh Grab Sample MG H-3 I x 0-

0. Radwaste Building Principal Gamma Turbine Building M M Emittersb 1 x 10-4 On-Site Storage Grab Sample M H-3 1 x 10-6 Facility D. All Release Types W9 1-131 1 x 01 as listed in B and C Continuousf Absorbent Sample 1-133 1 x100 above._______________________________________

W9 Principal Gamma Continuousf Particulate Sample Emittersb i x 10- 1, (1-131, others)

Gross Alpha CniuufComposite Sr.-89, Sr-90, Fe-55 I X10-1O Contiuous~ Particulate Sample Continuousf Noble Gas Monitor Noble Gas Gross 1 x 0-Beta or Gamma E. Offgas Vent Pipe N.A.k N.A.k Principal Gamma 1 x 10-Grab Sample Emittersb FERMI 2ODCM -TRM VOLUME 11 3-24 Rev. 20

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:

4.66

• s LLD -=

E *V

• 2.22 x10 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, 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.

bThe principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138, Ar-41, Kr-85m, and I1lO Xe-135m 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 areto 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. 20

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 increased requirement does not apply if the noble gas monitor shows that effluent activity has not 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.

within 48 gSamples shall be changed at least once per-7 days and analyses shall be completed hours after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 3 days following each shutdown, startup or THERMAL POWER be change exceeding 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and analyses shall at which the noble gas monitor completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing, at any release point shows that effluent activity has increased more than a factor of 3.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. When samples collected for periods between 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of any PURGING.

iln 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of any VENTING or PURGING and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING through other than SGTS.

kOffgas Vent Pipe sampling is performed as directed by Radiation Protection to supplement Reactor Building Exhaust Plenum monthly grab sampling. The Offgas Vent Pipe sample point is upstream of the Reactor Building Exhaust Plenum.

FERMI 2 ODCM - TRM VOLUME I11 3-26 Rev. 18

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 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 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 II 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 II 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 fuel defined in 40 CFR Part 190) due to releases of radioactivity and to radiation from uranium 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 action to days, pursuant to 10 CFR 50.4, a Special Report that defines the corrective 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 K 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 determined in 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be with the accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance methodology and parameters in the ODCM.

and from 4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units parameters in outside storage tanks shall be determined in accordance with the methodology and the ODCM. This requirement is applicable only under conditions set forth in Control 3.11.4, ACTION a.

Note: Page contentwas last chang ed with ODCM Revision_16..

3-32 Rev. 18 FERMI 2 ODCM - TRM VOLUME 11

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 bf fadibactivity ng the result of plant effluents In an environmental sampling niedium 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.

Note: Page content was last changed with ODCM Revision 16.

FERMI 2 ODCM - TRM VOLUME 11 3-33 Rev. 18

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 Quarterly Gamma dose quarterly.

1. DIRECT RADIATIONb 67 routine monitoring stations, 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.

The balance of the stations, 8, should be placed in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

Samples from 5 locations. Continuous sampler Radioiodine Canister:

2. AIRBORNE 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 loading, analysis following filter annual average ground level change:d X/Q.

Gamma isotopic

b. 1 sample from the vicinity of analysise of composite a community having the (by location) quarterly.

highest calculated annual average ground level X/Q.

c. 1 sample from a control location, as for example 15-30 km distant and in the least prevalent wind directionc.

Note: Page content was last changed with ODCM Revision 15.

3-35 Rev. 18 FERMI 2 ODCM - TRM VOLUME 11

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 ofAnalysis

3. WATERBORNE

a. Surfacef a. 1 sample upstream. Composite sample Gamma isotopic

b. 1 sample downstream. over 1-month periodg analysise monthly.

Composite for tritium analysis quarterly.

b. Ground Samples from 1 or 2 sources only Quarterly Gamma isotopice and if likely to be affectedh. tritium analysis quarterly.

c. Drinking Sa. 1 sample of each of 1 to 3 of Composite sample 1-131 analysis on each the nearest water supplies over 2-week periodg composite when the that could be affected by its when 1-131 analysis is dose calculated for the discharge. performed, monthly consumption of the perfom, m y water is greater than 1 composite otherwise.

b. 1 sample from a control mrem per year. 1 S location. Composite for gross beta and gamma isotopic analysese monthly. Composite for tritium analysis quarterly.

d. Sediment from shoreline Semiannually 1 sample from downstream area Gamma isotopic with existing or potential recreational value, analysise semiannually.

FERMI 2 ODCM - TRM VOLUME II 3-36 Rev. 13

TABLE 3.12.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

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 i.

than 1 mrem per yr

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 analysis e on edible Invertebrates recreationally important are not seasonal. 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 harvestJ. Gamma isotopic

c. Food Products class of food products from analysese on edible any area that is irrigated by portions.

water in which liquid plant 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/Q if locations are available and milk 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 performed.

Note: Page content was last changed with ODCM Revision 16.

FERMI 2 ODCM - TRM VOLUME 11 3-37 Rev. 18

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. Refer to 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

Jlf 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 (pCi/l) Particulate or (pCi/kg, wet) (pCi/1) Products Gases (pCi/m3 ) (pCi/kg, wet)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-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)b,c Water Airborne Fish Milk Food Sediment Analysis (pCilI) 'Particulateor (pCi/kg, wet) ý(p Ciii) Products (pCi/kg, dry)

Gases .(pCi/rn3 ) (p=Clkg, wet) gross beta 4 0.01 H-3 2000 IMn-54 15 130 IFe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Z,r-Nb-95 15 1-131 ld0.07 1 60 Cs-1 34 15 0.05 130 15 60 150 ICs-1 37 18 0.06 150 18 80 180

[Ba-La-140 15 15 FERMI 2 ODCM - TRM VOLUME 11 3-41 Rev. 13

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 *s b E* V*2.22 *Y exp(- /t)

Where:

K 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, 2 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 Il 2

nearest meat animal, the nearest residence and the nearest garden* of greater than 50 m (500 ft 2 ) 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).

I

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 11 3-44 Rev, 20

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 II 3-45 Rev. 13

Figure 3.0-1: Map Defining Unrestricted Areas and Si bundary for Radioactive Gaseous and Liquid Effluents NORMAL RADIOLOGICAL RELEASE POINTS ) \ . '^' _ "

LEGEND A

- - - - LIOUIDUNRESTRICTED AREABOUNDARY

- - .. -- GASEOUS UNRESTRICTED

/

AREABOUNDARY / I I GASEOUS RELEASE ELEVATIONS / /

1. REACTOR BUILDING - 751 FT )/

2. RAOWASTE BUILDING - 729 FT

3. -SI TE STDRAGE BUILDING - 76 FT / / LAKEE i O/ U

4. TURBINEBUILDING - 720 FT V //

^  ; E RIE LIOUID RELEASE POINT

- SEE ENLARGED VIEW D

S* [ATER NTAKE SI I 2.RADWASTEBUILOING 3 SI TE

/ON- I .1 BUILDING STORFAGCE Ca SWIMLATH PTE AUX PEAUX 1I _ . , - Il RE I. ACTOR BUILDING 5

S " .4.TURBINEBUILDING 1 ENLARGED VIEW FERMI 2 ODCM - TRM VOLUME 11 3-46 END OF SECTION 3.0 Rev. 13

SECTION 4.0 BASES FERMI 2 ODCM - TRM VOLUME 11 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 and 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 I, 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 II 4-2 Rev. 13

RADIOACTIVE EFFLUENTS BASES 3/4.11.1.2 DOSE This control is provided to implement the requirements of Sections II.A, Ill.A, and IV.A of Appendix 1, 10 CFR Part 50. The control implements the guides set forth in Section II.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 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 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 ensures 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 to 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 1,10 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 1.111, "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 II 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 II.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 1.111, "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-131, iodine-133, 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 II.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 II.B and II.C of Appendix 1, 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 II.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/m 2 .

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 II 4-8 Rev. 13

SECTION 5.0 ADMINISTRATIVE CONTROLS FERMI 2 ODCM - TRM VOLUME 11 5-1 Rev. 13

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),

• • • ln 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.

The Annual Radioactive Effluent Release Reports shall include the results of analysis of all onsite groundwater and rainwater sampling and a description of any detected onsite radioactive leaks or spills into groundwater. Any groundwater related events, or groundwater sample results exceeding ODCM REMP reporting thresholds, voluntarily communicated per NEI 07-07, Objective 2.2 shall also be described in these reports (NEI 07-07 Acceptance Criterion 2.4.c).

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. 20

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 Page-6.0-Offsite Dose Calculation Manual Pg .-

PART 11 CALCULATIONAL METHODS

SECTION 6.0 LIQUID EFFLUENTS FERMI 2 ODCM - TRM VOLUME 11 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 Instrumentation 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 D11-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 (D11-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 (D11-N008) provides additional control of potential radioactive effluents. D11-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, D11-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 II 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 ODCM 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 3.11.1.1.

To meet this specification, the alarm setpoints for liquid effluent monitors are determined in accordance with the following equation:

SCL(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 D11-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:

MPCF=_ C' MPC, (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 3.11.1.1.

Based on the MPCF, the maximum allowable release rate can be calculated by the following equation:

DF MAX RR <_

• SF (PCF *(1 + BF))+ H3MPCF (6-3) where:

MAX RR = maximum acceptable waste tank discharge rate (gal/min)

(Monitor #G11-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:

C.

CL= -

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:

S < Z(C,

• SEN,)* DF* H3F* SF MPCF* (1 + BF)* RR (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 (D11-N402)

ODCM 3.3.7.11 requires that the setpoint for the CWR Decant Line Radiation Monitor D11-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 D11-N402 alarm setpoint can be calculated by the equation:

S (Ci

• SEN,)* SF '

SP - + Bkg MPCF (6-7)

FERMI 2 ODCM - TRM VOLUME II 6-9 Rev. 13

where:

SP = setpoint in counts per minute (cpm)

Ci = concentration of each radionuclide i in the CWR decant line effluent (pCi/ml)

SENi = monitor sensitivity for nuclide i based on calibration curve (cpm/(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 D11-N402 The D11-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 D11-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 D11-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 10 -4 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 pCi/ml. D11-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 D11-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 D11-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 D11-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 D11-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:

yMC *} RR (I + BF)

MPC,) DF + RR H3F (6-8)

FERMI 2 ODCM - TRM VOLUME II 6-11 Rev. 13

where:

Ci = 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 D11-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 II 6-12 Rev. 13

6.4 Contaminated GSW or RHR System - Quantifying and Controlling Releases The GSW Radiation Monitor (D11-N008) provides an indication of contamination of this system. The Monitors D11-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 D11-N402 or D11-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 (D11-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 II 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 modeling, 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

S= 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 + 05 [(U,, / D,) + (U,

• BFj)] 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-11 of Regulatory Guide 1.109 (mrem/pCi) 1.14E + 05 10 (pCi/uCi) *103(ml/kg) 8760 (hr 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 4.11.1.1.1-1, 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,h, = D,(31 / d)

(6-14)

D,iax, = Dmax(31 / d)

(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 II 6-18 Rev. 13

TABLE 6.0-1 Fermi 2 Site Specific Liquid Ingestion Dose Commitment Factors Aio (mrem/hr per uCiIml)

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 4.18E+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 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+l - 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.OOE+2 8.35E+3 Co 2.20E+l 3.66E+l - - 5.59E+2 Co-58 -9.38E+l 2.1OE+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+l 7.69E+0 - - - 4.27E+2 Cu-64 -1.05E+l 4,92E+O - 2.64E+l - 8.94E+2 Zn-65 2.32E+4 7.38E+4 3.34E+4 - 4.94E+4 - 4.65E+4 Zn-69 4.94E+l 9.44E+l 6.57E+O - 6.14E+l - 1.42E+l Br-82 - - 2.28E+3 --- 2.62E+3

-- 83 - - 4.07E+l - - - 5.86E+l 34 - - 5.27E+l - - - 4.14E-4 Br-85 - - 2.17E+O - - - 1.O1E-15 Rb-86 - 1.01IE+5 4.71 E+4 - - - 1.99E+4 Rb-88 - 2.90E+2 1.54E+2 - - - 4.01E-9 Rb-89 - 1.92E+2 1.35E+2 - - - 1. 12E-1 1 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+l - - - 2.11IE+3 Sr-92 1.68E+2 - 7.26E+0 - - - 3.32E+3 Y-90 6.36E-1 - 1.70E-2 - - - 6.74E+3 Y-91 m 6.OOE-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+l - 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+l Tc-1O01 1.07E-2 1.54E-2 1.51 E-1 - 2.78E-1 7.88E-3 4.63E-14

-.RMI 2 ODCM - TRM VOLUME 11. 6-19 Rev. 13

TABLE 6.0-1 Fermi 2 Site Specific Liquid Ingestion Dose Commitment Factors Aio (mrem/hr per uCI/ml)

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Ru-1 03 5.58E+O 2,40E+0 -2.13E+l 6.51 E+2 Ru-I 05 4.64E-1 -1 .83E-1 6.OOE+O 2.84E+2 Ru-1l06 8.29E+l 1.05E+l 1.60E+2 -5.37E+3 Rh-103m -----

Rh-1 06 -

Ag-11Orn 1.87E+O 1.73E+O 1.03E+0 3.41 E+0 7.08E+2 Sb-1 24 2.41 E+1 4.56E-1 9.56E+O 5.84E-2 - 1.88E+l 6.84E+2 Sb-1 25 1.54E+l 1.72E-1 3.66E+0 1.57E-2 -1.19E+I' 1.70E+2 Te-125m 2.58E+3 9.36E+2 3.46E+2 7.77E+2 1.05E+4 - 1.03E+4 Te-1 27mn 6.52E+3 2.33E+3 7.95E+2 1.67E+3 2.65E+4 - 2.19E+4 Te-127 .1.06E+2 3.81E+l 2.29E+l 7.86E+l 4.32E+2 - 8.37E+3 Te-129m 1.11 E+4 4.13E+3 1.75E+3 3.81 E+3 4.63E+4 - 5.58E+4 Te-1 29 3.03E+l 1.14E+l 7.37E+0 2.32E+l 1.27E+2 - 2.28E+l Te-1 31mr 1.67E+3 8.15E+2 6.79E+2 1.29E+3 8.26E+3 - 8.1 OE+4 Te-1 31 1.90E+l 7.93E+0 5.99E+0 1.56E+l 8.32E+l - 2.69E+0 Te-132 2.43E+3 1.57E4-3 1.47E+3 1.73E+3 1.51 E+4 - 7.43E+4 1-130 3.18E+l 9.39E+l 3,71 E+l 7.96E+3 1.47E+2 - 8.09E+l

-131 1.75E+2 2.51 E+2 1.44E+2 8.21 E+4 4.30E+2 - 6.61 E+1

2 8.55E+O 2.29E+l 8.OOE+Q 8.00E+2 3.64E+l - 4.30E+O

.,-133 5.98E+l 1.04E+s2 3.17E+l 1.53E+4 1.82E+2 - 9.35E+l 1-134 4.46E+0 1.21E+l 4.34E+0 2.10E+2 1.93E+l - 1.06E-2 1-135 1.87E+l 4.89E+'1 1.81 E+l 3.22E+3 7.83E+l - 5.52E+l Cs-134 2.98E+5 7.1IOE+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-1 37 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+l 2.23E-3 Ba-1 39 1.53E+0 1.09E-3 4.48E-2 - 1.02E-3 6j19E-4 2.72E+0 Ba-140 3.20E+2 4.03E-1 2.10E+l - 1.37E-1 2.30E-1 6.60E+2 Ba-141 7.44E-1 5.62E-4 2.51 E-2 - 5.23E-4 3.1 9E-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 - -- 6.11IE+3 La-142 8.46E-3 3.84E-3 9.58E-4 - -- 2.81 E+l Ce-141 8.05E-2 5.45E-2 6.18E-3 - 2.53E-2 - 2.08E+2 Ce-143 1.42E-2 1.05E+l 1.16E-3 - 4.62E-3 - 3.92E+2 Ce-144 4.20E+O 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-1O0 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+l - - - 8.12E+4 Np-239 3.59E-2 3.53E-3 1.94E-3 - 1.10E-2 - 7.24E+2

• :RMI 2 ODCM -TRM VOLUME 11 6-20 Rev. 13

TABLE 6.0-2 Bioacc,umulation Factors (BFi)

(Pci/kg per pC!iliter)*

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-1 336, and silver and antimony, which are taken from UCRL 50564, Rev 1, October 1972.

FERMI 2 ODCM - TRM VOLUME 11 6-21 Rev. 13

FIGURE 6.0-1 Liquid Radioactive Effluent Monitoring and Processing Diagram Rors Drin

-still a

EryterTa-k A Watr ---- Roor Dr:An Biil T

nk Ta-k 3 W-f,~~= .--... E.PC*

T-Tk Behqal

^txTCar

• Till*U --------- D ---------*

HIh 1L WateWaste IL jLe Wwle RmOW Fro6OrcWaw

.- ^ -- ~^, ^

w-ase I cal<<ta~ _

Simple bT<<kA kple thple Smiple T-kt ISa ple Skpl.

T>>t C RfBBrwor eeri W~su,. .- -

Wa.a --

Ri-

-- -- I- -- I 1- -- I L __

rn Too"-' 01 T-?~~ a=&]

nl T.

tA.e Frf, FERMI22 ODCM FERMI ODCM --TRM TRM VOLUME VOLUME II11 6-22 6-22 Rev. 13 Rev. 13 END OF SECTION 6.0 END 6.0

SECTION 7.0 GASEOUS EFFLUENTS FERMI 2 ODCM - TRM VOLUME 11 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 th6ie fiVe gaseous release pbints (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 smaii 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.

Note: Page content was last changed with ODCM Revision 16.

FERMI 2 ODCM - TRM VOLUME 11 7-2 Rev. 18

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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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:

S 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.

S Once per quarter, analysis of a composite particulate sample of all releases that quarter for Sr-89 and Sr-90.

S Once per month, analysis of a grab sample for principal gamma emitters (noble gases and tritium).

- Analysis of a grab sample for principal gamma emitters (noble gases) from the Offgas Vent Pipe sample lines, as needed to supplement RB Exhaust Plenum sampling. Normally performed monthly in conjunction with RB Exhaust Plenum grab sampling.

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.

Gaseous releases of Carbon-14 may be determined by calculation, without the use of sampling. Pre-operationbl calculations, since adjusted for power uprate, estimated the annual gaseous release of C-14 to be 9.88 Ci, all from the containment building (UFSAR Appendix 11A, Table IV-1). This value may be used for C-14 release reporting; alternative calculations, some of which are under development at the time of this ODCM revision, may also be used if judged to be more accurate and if approved by Fermi management.

FERMI 2 ODCM - TRM VOLUME II 7-4 Rev. 20

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:

FRAC = 1.67E + 01* x / Q* VF* Y(C,

• K,)

FRAC 500 (7-1)

F 1.67E +o01* /Q F* (C,*[L,+1.M,)

FRAC [

3000 (7-2)

Where:

FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate Z/Q = annual average meteorological dispersion to the controlling site boundary location from Table 7.0-3 (sec/m 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/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)

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* C)

SP <C + Bkg FRAC (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-133 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-133 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 + 01* / Q

• VF * (K,

• C,)

(7-4)

D = 1.67E+01* / Q* VF* ,([ + 1.1M, * )

(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)

S/ Q = 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)

Ki = 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

R 500 *AF S1.

67 + 01

• Q* (Ki,*C,)

(7-6) or 3000 *AF 1.67E+ 01 * / Q* ([L, + 1.1Mi]* 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 Plenum 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 mixture The determination of doses in the environment from releases is dependent on the of the radioactive material. Also, NRC Regulatory Guide 1.21 requires reporting of individual radionuclides released in gaseous effluents. Therefore, Detroit Edison must these determine the quantities of the individual radionuclides released. For noble gases, 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 reactor gases). Noble gases have been detected almost exclusively in the building effluent.

As necessary to supplement grab sampling at the Reactor Building Exhaust Plenum, samples are taken from the Offgas Veit Pipe sample lines, hrmally on the same frequency as RB Exhaust Plenum samples. The Offgas Vent Pipe are more sample point is upstream of the RB Exhaust Plenum and noble gases concentrated at this point. Dilution factors are applied to Offgas Vent Pipe noble gas sample concentrations when the same nuclides are detected in both locations so that concentrations detected in RB Exhaust Plenum samples may be compared to concentrations based on Offgas Vent Pipe samples; the more conservative concentration values are used in release calculations.

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 the torus equipment hatches has been open for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and equilibrium with atmosphere may be assumed after at least one torus hatch has been open for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. Exceptions 7.2.2.

to this special sampling are allowed as noted nrevirously in nr.*M Section 7-10 Rev. 18 FERMI 2 ODCM - TRM VOLUME ii

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 perliter Ci = 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/yr to 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= I //Q,*R-3*VF,*16.7* Ci, (7-9)

Where:

FERMI 2 ODCM - TRM VOLUME II 7-11 Rev. 13

DR = total maximum organ dose rate for all release points (mrem/yr)

S/ Qr = atmospheric dispersion factor for release point r to the controlling SITE BOUNDARY location (sec/m3 ) from Table 7-3 or plant procedures RI-3 = 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 following 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 be ODCM 4.11.2.2 requires that an assessment of releases of noble gases quarterly performed at least once per 31 days to evaluate compliance with the 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 noble gases are be used to calculate the gamma-air and beta-air doses. If for each detected at multiple release points, these equations must be performed such release point, and the calculated air doses must be summed.

Dr = 3.17E-08* g/Q*f (M

• Q,)

(7-10) and D, =3.17E-08* Z/Q* (N,*Q,)

(7-11)

Where:

D = air dose due to gamma emissions for noble-gas radionuclides (mrad)

Dp = air dose due to beta emissions for noble gas radionuclides (mrad)

X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3).

of Qi = cumulative release of noble gas radionuclide i over the period interest (pCi)

Mi = air dose factor due to gamma emissions from noble gas 3

radionuclide i (mrad/yr per pCi/m , from Table 7.0-2)

Ni = air dose factor due to beta emissions from noble gas 3

radionuclide i (mrad/yr per pCi/m , Table 7.0-2) 3.17 E - 08 = 1/3.15 E + 07 (year/sec)

Note: Page content was last changed with ODCM Revision 15.

TRM VOCLUM 7-13 RevM81 F ERMI 2DCM

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 than releases of 1-131, 1-133, tritium, and particulates with half-lives greater 8 days:

D = ZZ (W,. SF *3.17E- 8* Ripo * )

p r i (7-14)

Where:

in Dao = dose or dose commitment to Organ o of age group a (identified 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) D/Q, atmospheric deposition for vegetation, milk and

-2 ground plane exposure pathways (m )

dose factor (mrem/yr per pCi/m ) or (m - mrem/yr per pCi/sec) 3 2 Raipo =

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.

Note: Page content was last changed with ODCM Revision 15. ..

7-14 Rev. 18 FERMI 2 ODCM - TRM VOLUME 11

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:

S0.5 (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 ODCM - 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:

Dna = Dna, * (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

TABLE 7.0-1 Values for Evaluating Gaseous Release Rates and Alarm Setpoints Allocation Allocated Dose Release Point Flow Rate Factor Rate Limit (liter/min) (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 Divl D11-P275 Organ = 150 Standby Gas 1.12E5 0.10 T Body = 50 Treatment System Skin = 300 Div IID11-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-P299 Reactor Building 2.57E6 0.50 T Body =125 Ventilation* Skin = 750 Gulf Atomic Organ = 375 Monitors D11-N408, N410

• D11-N408 and N410 will start the SGTS, close the Drywell Purge/Vent Valves, isolate Rx Building Ventilation System, isolate Control Center, and initiate emergency recirculation mode.

Note: Page content was last changed with ODCM Revision 17.

FERM 2 ODCM -TRM VOLUME !! 7-17 Rev. 18

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 iN (mrem/yr per (mremlyr per (mradlyr per (mrad/yr per pCiIm3 ) pCi/m 3 ) pCi/mn3 ) PCi/rn 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 1.61E+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 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-1 31 m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3,53E+02 1,05E+03 Xe-135m 3.12E+03 7.11IE+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-1 37 1.42E+03 1.22E+04 1.51E+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 11 7-18 Rev. 13

TABLE 7.0-3 Controlling Locations, Pathways, and Atmospheric Dispersion for Dose Calculations*

ODCM Control Location Pathway(s) Controlling /Q DIQ Age Group (sec/m 3 ) (11m2) 3.11.2.1a site boundary noble gases N/A RB: 1.25E-6 N/A (0.57 mi, NW) direct exposure TB: 5.71E-6 RW: 2.66E-6 3.11.2.1b site boundary inhalation child RB: 1.25E-6 NIA (0.57 mi, NW) TB: 5.71E-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: 5.71E-6 RW: 2.66E-6 11.2.3 residence vegetation adult RB: 1.10E-6 1.59E-8 a (0.71 ml, 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, FERMI 2 ODCM - TRM VOLUME 0I 7-19 Rev. 20

Table 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors Raipo, Inhalation Pathway Dose Factors - ADULT (mrem/yr per /1Ci/m 3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 - 1.26E43 1.26E+3 1.26E+3 i.26E*3 1.26E+3 1.26E*3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 4

Na-2 1.02E+4 1.02E+4 1.02F+4 1.02E+4 i.02E4 1.02E+4 1.02E+4 P-32 1.32E+6 7.71Ev4 8.64E+4 5.01E4 Cr-51 - S,95E+1 2.28Evl 1.44E+4 3.32E*3 1.00Ev2 Hn-54 - 3.96E+4 - 9.84E+3 1.40E+6 7.74E+4 6.30E+3 Mn-56 - 1.24E+0 - 1.30E+O 9.44E+3 2.02E+4 1.83E-1 Fe-55 2.46E+4 1.70E+4 - - 7.21 Ev' 6.03E+3 3.94E+3 Fe-59 1.18E+4 2.78E+4 - - I.02E+6 I.88Ev5 1.06E+4 Co-57 - 6.92Ei2 - - 3.70E+5 3.14E+4 6.71E+2 Co-58 - 1.58E+3 - - 9.28E+5 1.06E+5 2.07E+3 Co-60 - 1.15E+4 - - 5.97E+6 2.BSE.5 1.48E+4 Hi-63 4.32E+5 3.14Ev4 - - 1.78E+5 1.34E+4 1.45E+4 NI-65 1.54E+0 2.10E-1 - - 5.60E+3 1.23E+4 9.12E-2 Cu-64 - 1.46E+O - 4.62E+O 6.78E43 4.90E+4 6.15E-1 Zn-65 3.24E+4 1.03Ev5 - 6.90E+4 8.64E+5 5.34Et4 4.66E+4 Zn-69 3.38E-2 6,S1E-2 - 4..22E-2 9.20E+2 1.63E-1 4 ..

52E-3 Br-82 - - - - - 1.04E+4 1.35Ev4 Br-83 - - - - - 2.32E+2 2.41Ev2 Br-84 - - - - - 1.64E-3 3.13E+2 Br-B5 - - - - - - 1.28E+1 Kb-86 - 1.35E+5 - - - 1.66Ev-4 5.90Ev4 Rb-88 - 3.87Ev2 - - - 3.34E-9 1.93E+2 Rb-89 - 2.56E+2 - - - - 1.70E+2 Sr-89 3.04E*5 - - - 1.40Et6 3.50E+5 8.72Ev3 Sr-90 9.92E+7 - - - 9.60E+6 7.22E+5 6.10E+6 Sr-91 6.19Ev- - - - 3.65E+4 1.91E+5 2.50E+O Sr-92 6.74E+0 - - - 1.65Ev4 4.30E+4 2.91E-1 Y-90 2.09E+3 - - - 1.70E+5 5.06Ev5 5.61E+I Y-91N 2.61E-1 - - - 1.92Ev3 1.33E+O 1.02E-2 Y-91 4.62EvS - - - 1.70E+6 3.85E+5 1.24E+4 Y-92 1.03E+1 - - - 1.57Ev4 7.35E+4 3.02E-1 Y-93 9.44E+1 - - - 4.85Ev4 4.22E+5 2.61E#O Zr-95 1.07Ev5 3.44E+4 - 5.42Ev4 1.77E+6 1.50Ev5 2.33Ev4 Zr-97 9.68E+1 1.96Ev1 - 2.97E+1 7.87Ev4 5.23EvS 9.04E+O Nb-95 1.41E+4 7.82E+3 - 7.74Ev3 5,05EvS 1.04Ev5 4.21E+3 Nb-97 2.22E-1 5.62E-2 - 6.554E-2 2.40E+3 2.42E+2 2.05E-2 Ho-99 - 1.21Ev2 - 2.91E+2 9.12E+4 2.48E+5 2.30E+1 Tc-99a 1.03E-3 2.91E-3 - 4.42E-2 7.64E+2 4.16E+3 3.70E-2 Tc-101 4.18E-5 6.02E-5 - 1.08E-3 3.99E+2 - 5.90E-4 Ru-103 1.53E*? - - 5.83E+3 5.05Ev5 1.10E+5 6.58E+2 Ru-105 7.90E-1 - - 1,02E+O 1.10E+4 4.82Ev4 3.11E-1 Ru-106 6.91E-4 - - 1.34E45 9.36E+6 9.12E+S 8.72E+-3 Rh-103m - - -

Rh-106 - -

A.-SO11 1.i.OBE4 1.00E+4 - 1.97E+4 4.63Ev6 3.02Ev5 5.94E+3 Sb-124 3.12E+4 5.89Ev2 7.55Ev1 - 2.48E+6 4.06E+5 1.24Ev4 Sb-125 5.34E+4 5.95Ev2 5.40E1 1.74E+6 1.01E+S

.- 1.26Ev4 Te-125m 3.42E-3 1.58E+3 1.05E-3 1.24E+4 3.14Ev5 7.06E-4 4.67E+2 Te-127w 1.26E4 5.77EM13 3.29E+3 4.5BE+4 9.60Ev5 1.50E+5 1.57Ev3 Te-127 1.40E+0 6.42E-1 1.06E+0 5.10E+O 6.51E,3 5.74Ev4 3.10E-1 Te-129z 9.76Ev3 4.67E4-? 3.44E+3 3.66E4 4 1.16Evb 3.83ti-5 1.58E+3 Te-129 4.98E-2 2.39E-2 3.90E-2 1.87E-1 1.94E+3 1.57E+2 1.24E-2 Te-131m 6.99Evi 4.36E+1 5.50Ev- 3.09E+2 1.4i12v 5.56Ev5 2.90Ev1 Te-131 1,11E-2 5.95E-3 9.36E-3 4,37E-2 I.39Ev- 1.84E*1 3.59E-3 Te-132 2.60Ev2 2.15E+2 1.90Ev2 1.46E+3 2.88E+5 5.10Ev5 1.62E+?

1-130 4,58Ev3 1.34E+4 1,14E+6 2,09E+4 - 7.69E-3 5.28Ev3 1-131 2.52Ev4 3.58Ev' 1.19E-7 6.13Ev4 - 6.28E43 2.05oE4 I-132 1.16E+3 3.26E13 1.14EvS 5.18Ev3 4.06E*2 1.16Ev3 1-133 8.64Ev3 1.48Ev4 2.15E-6 2.581+4 - B.ABE-3 4.52E43 FERMI 2 ODCM -TRM VOLUME ii 7-20 Rev. 13

Table 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors R,io Inhalation Pathway Dose Factors - ADULT (cont.)

(mrem/yr per yLCi/m 3 )

Nuclide bone Liver Thyroid Kidney Lung GI-LL1 T. ody 1-134 6. 44E+2 1 .73E+3 2.98E+4 2. 7 E4-3 - 1.01Ea'O 6.15E+2 1-135 2,68Erl 6 .98E+ 3 4.48E+5 1. 11E+4 - 5.25E43 2. 57E* 3 Ca-134 3.73E+5 8,48E45 - 2.87E+5 9.76E+4 1.04E+4 7.28E+S Cs-136 3.90E+4 1.46E*5 - 8.56E+4 1.20E+.4 1.17E+4 1.10E+5 Cx-137 4.78E+5 6.21E-5 - 2,22E+5 7.52E.-4 8.40E+3 4.28E#5 Co-138 3.31E+2 6.21E+2 - 4.80E+2 4.86E+1 1.86E-3 3.24E42 Ba-139 9.36E-1 6.66E-4 - 6.22E-4 3.76E+3 8.96E+2 2.74E-2 D~a-140 3.90E+4 4.90E+1 - 1.67E41 1.27E+6 2.18E+S 2.57E+3 BA-141 1.OoE-1 7.53E-5 - 7.OOE-5 1.94E+3 1.16E-7 3.36E-3 Ba-142 2.63E-2 2.70E-5 - 2.29E-5 1.19E+3 - 1.66E-3 L.a-140 3.44E+2 i.74E+2 - - 1.36E+S 4.58E+ý5 4.58E41 La-14.2 6.83E-1 3.10E-1 - - 6,33E+3 2.11E+3 7.72E-2 Cc-141 1.99E+4 i.35E.-4 - 6..26E+3 3.62E+5 1.20E+5 i.53E+3 Ce-143 1.86E+2 1.38E+2 - 6.08E+1 7.98E+4 2.26E+S 1.53E+1 Ce-144 3.43E+6 i.43E+6 - 8.48E+5 7.78E+6 8.16E+S 1.84E+5 Pr-143 -9.36E+3 3. 75E+3 - 2.16E43 2. 81E+5 2.OOE+5, 4. 64E+.2 Pr-144 3.01E-2 1.25E-2 - 7.05E-3 1.02E+3 2.15E-8 1.53E-3 Nd-147 5,27E+3 610E*3 - 3.56E+3 2.21E+5 1,73E+S 3.65E+2 W-187 8.48E+0 7,08E+0 - - 2.90E+4 1.55EtS 2.48E+O lNp-239 2.30E+2 2.26E-il - 7.00E+1 3.76Ei-4 1,19E+S 1.24E+1 FERMI 2 ODCM -TRM VOLUME 11 7-21 Rev. 13

Table 7.0-4 R,ipo, Inhalation Pathway Dose Factors - TEENAGER (mrem/yr per ACi/m 3 )

Nuclide BRne Liver Thyroid Kidney Luns C1-LLI 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 4.87E+3 4,87E*3 4.87E+3 4.87E+3 4.87E*3 4.,7E+3 4

Na-2 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 P-32 1.89E+6 i.IOE+5 9.28E+4 7.16E+4 Cr-51 - 7.50E+1 3.07E+ 2.10E+4 3.OOE*3 1.35E+2 Hn-54 - 5.11E+4 - 1.27E+4 1.98E+6 6.68E+4 8.AOE+3 hn-56 - 1.70E+O - 1.79E+O 1.52E+4 5.74E+4 2.52E-1 Fe-55 3.34E+4 2.38E+4 - - 1.24E+5 6.39E+3 5.54E+3 Fe-59 1.59E+4 3,70E+4 - - 1.53E+6 1.78E+5 1.43E.4 Co-57 - 6,92E+2 - - 5.86E+5 3.14E+4 9.20Et2 Co-58 - 2.07E+3 - - 1.34E+6 9.52E+4 2.78E+3 Co-60 - 1.51E+4 - - 8.72E-6 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34E+4 - - 3.07E+5 1.42E+4 1.98E+4 Ni-65 2.18E+0 2.93E-1 - - 9.36E+3 3.67E+4 1.27E-1 Cu-64 - 2.03E+O - 6.41E+O 1.11E+4 6.14E+4 8.48E-1 Zn-65 3.86E+4 1.34E+5 - 8.64E+4 1.24E+6 4.66E+4 6.24E+4 Zn-69 4.83E-2 9.20E-2 - 6.02E-2 1.58E+3 2.85E+2 6.46E-3 Br-82 - - - - 1.82E+4 Br-83 - - - - - 3.44E+2 4

Br-8 - - - - - 4.33E+2 Br-BS - - - - - 1.83E+1 Rb-86 - i.90E+5 - - - 1.77E+4 8,40E+4 Rb-8B - 5.46E+2 - - - 2.92E-5 2.72E+2 Rb-89 - 3.52Et2 - - - 3.38E-7 2.33E12 Sr-89 4.34E+5 - - - 2.42E+6 3.71E+5 1.25E+4 Sr-90 1.08E+8 - - - 1.65E+7 7.65E+5 6.68E+6 Sr-91 8.BOE+1 - - - 6.07E+4 2.59E+5 3.51E+O Sr-92 9.52E+O - - - 2.74E+4 1.19E+5 4.06E-1 Y-90 2.98E+3 - - - 2.93E+5 5.59E+5 B.OOEl1 Y-91x 3.70E-1 - - - 3.20E+3 3.02E+1 1.42E-2 Y-91 6.61E+5 - - - 2.94E+6 4.09E+5 1.77E*4 Y-92 1.47E+1 - - - 2.68E+4 1.65E+5 4.29E-1 Y-93 1.35E+2 - - - 8.32E+4 5.79E+5 3.72E+O Zr-95 1.46E+5 4.58E+4 - 6.74E+4 2.69E+6 1.49E+5 3.15E+4 Zr-97 1.38E42 2.72E+1 - 4.12E+1 1.30E+5 6.30E+5 1.26Eti Hb-95 1.86E+4 i.03E+4 - 1.OOE+4 7.51E+5 9.68E+4 5.66E+3 Nb-97 3.14E-1 7.78E-2 - 9.12E-2 3.93E.3 2.17E+3 2.84E-2 Ho-99 - 1.69E*2 - 4.11E+2 1.54E+S 2.69E+5 3.22E+1 Tc-99m 1.38E-3 3.86E-3 - S.76E-2 1.15E+3 6.13E+3 4.99E-2 Tc-1O1 5.92E-5 8.40E-5 - 1.52E-3 6.67E*2 8.72E-7 8.24E-4 Ru-103 2.10E+3 - - 7.43E+3 7.B3E+S 1.09E,5 8.96E+2 Ru-i05 1.12EO - - 1.41E+O 1.82E+4 9.04E.4 4.341-1 Ru-106 9,84E+4 - - 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Rh-103m -

Rh-106 -

A.g-110m 1.31E+4 1.31E+4 2.50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 - 3.85E+6 3.98E45 1.68E+4 Sb-125 7.38E+4 B.OBE+2 7.04E.i - 2.74E+6 9.92Es-4 1.72E+4 Te-125m 4.B8183 2,24E-3 1.40E+3 - 5.36E-5 7,50E+4 6,67E+2 Te-127m 1.80E+4 8.16E-3 4.3BE-3 6.54E-4 1.66E+6 1.59E+5 2.1BE'3 Te-127 2,O1E+O 9.12E-1 1.42E+o 7.28E+O 1.12E+4 8.08E+4 4,42E-1 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2,25E+3 Te-129 7.10E-2 3.38E-2 5.I1E-2 2.66E-1 3.30E+3 1.62E*3 1.76E-2 Te-131% 9.84E+1 6.OIE1l 7.25E+l 4,39E+2 2,38E+5 6.21E+5 4.02E-1 Te-131 1.5BE-2 S.32E-3 1.24E-2 b. IBE-2 2.34E+3 1.S5U+i 5.04E-3 Te-132 3.60E+2 2.90E+2 2.46E+2 I.95E-3 4.49E-5 4.63E45 2.19E-2 1-130 6.24E*3 1.79E-4 1. 49E6 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+4 3-132 1.59E+3 4.38E+3 1.51E+5 6.92E13 - 1.27E-3 1.58E+)

1-133 1.22E+4 2.051E4 2,92E+6 3.59E+4 - 1.03E+4 6.22E-3 FERMI 2 ODCM - TRM VOLUME 11 7-22 Rev. 13

Table 7.0-4 R,ipo, Inhalation Pathway Dose Factors - TEENAGER (Cont.)

(mremlyr per 3 gLCi/m )

Nuclide Bone Liver Thyroid Kidney Lung CG-LL1 T.Body 1-134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 - 2.0t+l1 9,40E+2 1-135 3.70E+3 9.44E+3 6.21E+5 1.49E+4 - 6.95E+3 3.49E43 Cf-134 5.02E+5 1.13E+6 - 3.75Es5 1.46E+5 9.76E+3 5.49E45 Cs-136 5.15Es4 1.94E+5 - 1.10E+5 1.78E+4 1.09E+4 1.37E+S Co-137 6.70E+5 8.48E+5 - 3.04EtS 1.21E+5 8.48E+3 3.11E+S Ci-i38 4.66E+2 8.56E+2 - 6.62E+2 7.87E+1 2.70E-1 4.46E+2 BA-139 1.34E4O 9.44E-4 - 8.88E-4 6.46E*1 6.45E+3 3.90E-2 BA-140 5.47E+4 6.70E+1 2.28E+1 2.03E+6 2.29E+5 3.52Et3 ba-141 1.42E-1 1.06E-4 - 9.84E-5 3.29E+3 7.46E-4 4.74E-3 Ra-142 3.70E-2 3.70E-5 - 3.14E-5 1.91E*3 - 2.27E-3 LA-140 4.79E+2 2.36E+2 - - 2.14E*5 4 .87E.t5 6.26E+1 La-142 9.60E-1 4.25E-1 - - I..02E4 1.20E+4 1.06E-1 Ce- 141 2.84E+' 1.90E+4 - .BBE+3 6.14E+5 1.26E+5 2.17E+3 Ce-143 2.66E+2 1.94E+2 - 8.64E+ 1 1.30E+5 2.55E+5 2.16E+1 Ce-i14 4.89E+6 2.02Eot. 1.21E+6 1.34E+7 8.64E+S 2.62E+5 Pr-143 1.34E+4 5.31E+3 - 3.09Ei3 4.83E+5 2.14E+5 6.62E+2 Pr-144 4.30E-2 1.76E-2 - 1.01E-2 1.75E+3 2.35E-4 2.1BE-3 Nd-1 47 7.86E+3 8.56E+3 - 5.02E+3 3.72E+S 1.82E+5 5.13E+2 W-187 1.20E+1 9.76E+O - - 4.74E+4 1.77E+5 3.43E4O Np-239 3.38E+2 3.19E+1 - 1.00E+2 6.49E+4 1.32E+5 1.77E+1 FERMI 2 ODCM - TRM VOLUME 11 7-23 Rev.13

Table 7.0-4 Raip,, Inhalation Pathway Dose Factors - CHILD 3

(mrem/yr per YICi/m )

Nuclide Bone Liver Thyroid Kidney Lung GI-LL1 T. Body N-3 *1 1.12E+k 1.12E+3 1,12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3. 59E+4 6.73E+3 6. 73E.t3 6.73E+3 6.73E+3 6. 73E+3 6. 73E+3 Na-24 1. 61E+4 1 .61 E+4 1I. 6I1E+4 i.61 E+4 ~.6 1E+4 I .61 E+4 i .61E+4 P-32 2.60E+6 i .14E* 5 - - - 4 .22E+4 9.BBE+4 Cr-51 - - 8.5SSE+ 1 2. 43Ei II .70E+4 1.08 E+ 3 1.54E+2 4

Kn-5 - 4 .29E.-4 - I .OOE+4 1.58E+6 2.29E+4 9. 51E+3 Mn-56 - I .66E+O - 1. 67E+O 1. 31E+4 1. 23E+S 3.12E- 1 Fe-55 4.74E+4 2. 52E+4 - ~ I . 1¶E+ 5 2. 87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 - 1.27E+6 7,07E+4~ 1.67E+4 co-57 - 9.03E+2 - - 5.07E+5 1.32E+4 1.07E+3 Co-59 - 1.77E+3 - - .11E+6 3.44E+4 3.i6E+3 Co-60 - 1.31E+4 - 7.07Eti6 9.62E+4 2.26E+4 Ni-63 8.21E+5 4.63E+4 - - 2.75E+5 6.33E+3 2.80Ee14 Nj-65 2. 99E+0 2.96E-1 - - B.18E+3 8.40E+4 1. 64E-1 Cu-64 - i.99E+O - 6.03E+O 9.SBE+3 3.67E+4 1.07E+O Zn-65 4. 26E+4 1. 13E4 5 - 7. 14E+4 9. 95E+5 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 - - - - - - I4.74E+2 Br-84. - - - - - - 5.48E+2 Br-85 - - - - - - 2.53E+1 Rlb-86 - 1.98E+5 - - - 7.99E+3 1.14E+5 Rb-88 - 5.62E+2 - - - 1.72E+1 3.66E+2 Rb-89 - 3.45E+2 - - - 1.89E+0 2.90E+2 Sr-89 5.99E+5 - - - 2.16E+6 1.67E+5 i.72E+4 Sr-90 1.01E+8 - - - 1.48E+7 3.43E+S 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+5 5.2SE-i Y-90 4.11 E+3 - - - 2.62E+5 2.68E+S 1.11E+2 Y-91M S.07E-1 - - - 2.81E+3 1.72E+3 1.84E-2

'2-91 9.i4E+S - - - 2.63E+6 1.84E+5 2. 442E+A Y2-92 2.04E+1 - - - 2.39E+4 2.39E+S 5.81iE-1 Y-93 1.86E+2 - - - 7 .44E+4 3. 89E+5 5.112 +0 Zr-95 1. 90E+5 4. 18E.'4 - 5.96E+4 2. 23E+6 6. 11 E+4 3 .70E+4.

Zr-97 1.88E+2 2.72E+1 - 3.89E+1 1.13E+5 3.51E*5 1.60E+i Nb-95 2.35E+4 9.18E*3 - 8.62E+3 6.14E+5 3.70E.'4 6.55Et3 Nb-97 4.29E-1 7.70E-2 - B.S5E-2 3.42E+3 2.78E+A. 3.60E-2 m4o-99 - 1.72E+2 - 3.92E+2 1.35E+5 1.27E+5 4.26E+1 TC-99m 1 .7BE-3 3.48E-3 - 5.07E-2 9.51E+2 4.81E+3 5.77E-2 Tc-101 8.10E-5 8.51E-5 - 1.4SE-3 S.BSE+2 1.63E+i 1.08E-3 Ru-103 2.79E+3 - - 7.03E+3 6. 62E+5 4.48E+4 1.07E+3 Ru-105 1.53E+O - - 1.34E+0 1.59E.'4 9.95E.'4 5.S5E-1 6

llu-10 1.36E+ 5 - - 1.84E+5 i.43E+7 4.29E+5 i.69E+4 Rh-103= - - - - - - -

Rlh-106 - - - - - -

Ag-1O0m 1,69E..4 1.14E+4 - 2.12E+4 5.48E+6 1.00E+5 9.14E+3 Sb-124 5,74E+4 7. 40E+ 2 1.26E+2 - 3. 24E+6 1.64E+S 2. 00E+4 Sb-125 9.842E+4 7. 59E+2 9.10E-1 - 2.32E+6 4 .03E+4 2.,07E+4 Te-125mn 6. 73E+3 2.33E+3 I .92E+3 - 4.77E+5 3.38E+4' 9.14E+2 Te-127m 2.49E+4. 8.55E+3 6.07E+3 6. 36E+4 1.48E+6 7, 14E+4 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+5 3.04E+3 Te-129 9.77E-2 3.50E-2 7. 14E-2 2.57E-1 2.93E*3 2.552.-'.2.38E-2 Te-131ma 1.34E#2 5.92E+1 9.77E+1 4.OOE*2 2,06E+5 3.08E+5 5.07E+1 Te-131 2.17E-2 8.44E-3 1.70E-2 5.88E-2 2.05E.3 1,33E43 6.59E-3 Te- 132 4.81E42 2,72E23 3.,17E+2 1.77E-3 3.77E2*5 i.38E-5 2.63E22 1-130 B. 18E+3 1.642E'4 1.85E+6 2. 45E.'4 - 5. 112E.3 B.44E*3 I-M3 4.BIE+4 4.81E+4 1.62E+7 7.88E+4' - 2.84E+3 2.73E-4 1-132 2.12E43 4.07E+3 1.94E+5 6.25E+3 - 3.202+3 1.88E+3 1-133 1.66E+A 2.03E+4 3.85E+6 3.38E+4 - 5.48E+3 7.70E*3 FERMI 2 ODCM -TRM VOLUME 11 7-24 Rev. 13

Table 7.0-4 R,aipo, Inhalation Pathway Dose Factors - CHILD (Cont.)

3 (mrem/yr per y.Ci/m )

Nuclide gone Liver Thyroid Kidney LunS GI-LLI T. body 1-134 i.17Ev3 2.16E+3 5.07E+4 3.30E+3 - 9 '55E+2 9.95E42 1-135 4.92E+'3 8.73E+3 7.92E-tS 1.34E+4 - 4.44E+3 4.14E*3 ce-134. 6.51E+5 1.01E+6 - 3.30E+5 i.21E+5 3.85E+3 2.25E+5 cm-136 6.51E+4 1.71E+5 - 9.55E+4 1.45E+4 4.18E.-3 1.16E+5 Cs-137 9.07E+5 8.25E+S- - 2. 82E+5 1.04E+5 3. 62E+3 I .28E+5 ca-138 6.33E+2 8.40E+2 - 6.22E+2 6,81E+1 2,70E+2 5,55E+2 B,-139 i .84E0 9. 84E-4 B.,62E-4 5. 77E+3 5.77E+4 5. 37E-2 B.-140 7.40E+4 6.48E+1 - 2.11E+1 1.74E+6 1.02E+5 4,33E+3 B&-i41 1.96E-1 1.09E-4 - 9.47E-5 2.92E+3 2.75E+2 6.36E-3 B.-142 5.00E-2 3.60E-5 - 2.91E-5 1.64E+3 2.74E+0 2.79E-3 L.A-140 6. 44E+2 2. 25E+2 - - 1.83E+5 2. 26E+5 7.55E+1 La-142 1.30E+0 4-1I1E-li - - 8.70E+3 7.59E+4 I .29E- I Ce-141 3.92E+4 1.95E+4 - 8.55E+3 5,44E+S 5.66E+4 2.90E+3 Cc-143 3.66E+2 1.99E+2 - 8.36E+1 1.15E+5 1.27E+5 2.87E+1 Ce-144 6.77E+6 2.12E+6' - 1.17E+6 1.20E+7 3.89E+5 3.61E+5 Pr-143 1.85E+4 5.55E+3 - 3.OOE+3 4.33E+5 9.73E,I4 9.14E+2 Pr-144 5.96E-2 1.85E-2 - 9.77E-3 1.57E+3 1.97E+2 3.OOE-3 Sd-147 1.08E+4 8.73E+3 - 4.81E+3 3.28E+S 8.21E+4 6.81E+2 W4-187 1.63E+1 9.66E+O - - 4.11E+4 9.10E.-4 4.33E+O Np-239 4.b66F2 3.34E+1 - 9.73E+1 5.81E+4 6,40E+4 2.35E+l FERMI 2 ODCM -TRM VOLUME 11 7-25 Rev. 13

Table 7.0-4 Raipo, Inhalation Pathway Dose Factors - INFANT (mrem/yr per yCi/mn3 )

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 - 6.47E+2 6.47E+2 6.47E*2 6:47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 Na-24 1.06E+4 i.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 P-32 2.03E+6 1.12E+S 1.61E+4 7.74E*4 Cr-51 - 5.75E-i 1.32E+l 1.28E+4 3.57E+2 8.95E+1 Hn-54 2.53E+4 - 4.98E43 1.OOE+6 7.06E-3 4.98E+3 Hn-56 1.54E+O - 1.1OE+O i.25E+4 7.17E+4 2.21E-1 Fe-55 1.97E+4 1.17E+4 - - 8.69E+4 1.09E+3 3.33E+3 Fe-59 1.36E+4 2.35E+4 - - 1.02E+6 2.48E+4 9.48E+3 Co-57 - 6.51E+2 - - 3.79E+5 4.86E+3 6.41Et2 Co-58 - 1.22E+3 - - 7.77E+5 i.11E+4 1.82E+3 Co-bO - 8.02E+3 - - 4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 - - 2.09E+5 2.42E+3 1.16Et4 Ni-65 2.39E+O 2.84E-1 - - 8.12E43 5.01E+4 1.23E-1 Cu-64 - 1.BBE+O - 3.98E+0 9.30E+3 1.50E+4 7.74E-1 Zn-6S 1.93E+4 6.26E+4 - 3.25E+4 6.47E+5 5.14E*4 3.11E*4 Zn-69 5.39E-2 9.67E-2 - 4.02E-2 1.47E+3 1.32E+4 7.18E-3 Br-82 - - - 1.33E+4 Br-83 - - 3.81E+2 Br-84 - - - 4.OOE+2 Br-85 - - - 2.04E+1 Rb-86 - 1.90E+5 - - - 3.04E+3 8.82E+4 Rb-88 - 5.57E+2 - - - 3.39E+2 2.7E+2 Rb-89 - 3.21E+2 - - - 6.82E+1 2.06E+2 Sr-89 3.98EtS - - 2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 - 1.12E+7 1.31E+5 2.59E+6 Sr-91 9.56E+i - 5.26E+4 7.34E+4 3.46E+O Sr-92 1.05E+1 - 2.38E+4 1.40E+5 3.91E-I Y-90 3.29E+3 - 2.69E+5 1.04E+5 8.82E+1 Y-91m 4.,7E-1 - 2.79Et3 2.35E+3 1.39E-2 Y-91 5.88E+5 - - - 2.5E+6 7.03E+4 1.57E+4 Y-92 1.64E1 - - - 2.45E+4 1.27E+5 4.61E-1 Y-93 1.50E+2 - - - 7.64E+4 1.67E+5 4.07E+O Zr-95 1.15E+5 2.79E+4 - 3.11E+4 1.75E+6 2.17E+4 2.03E+4 Zr-97 1.50E+2 2.56E+i - 2.59E+1 1.1OE+5 1.40E+S 1.17E+1 Nb-95 1.57Ev4 6.43E+3 - 4.72E+3 4.79E5 1.27E+4 3.78E#3 Nb-97 3.42E-1 7.29E-2 - 5.70E-2 3.32E+3 2.69E+4 2.63E-2 no-99 - 1.65E+2 - 2.65E+2 1.35E+5 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-1O1 6.51E-5 8.23E-5 - 9.79E-4 5.84E+2 8.44E+2 8.12E-4 Ru-103 2.02Et3 - - 4.24E+3 5.52Et5 1.61E+4 6.79E+2 Ru-105 1.22E+O - - 6.99E-1 1.57E+4 4.84E+4 A.WOE-l Ru-106 8.68E+4 - - 1.07E+5 1.16E+7 1.64E+5 1.09E+4 Rh-103m Rh-106 As-1lOm 9.98E+3 7.22E+3 - 1.09E+4 3.67E+6 3.30E*4 5.00E3 Sb-124 3.79E+4 5.56E+2 1.O1E+2 - 2.65E+6 5.91E+4 1.20Et4 Sb-125 5.17E+4 4.77Et2 6.23E+1 - 1.64E+6 1.47E+4 1.09E+4 Te-125m 4.76E+3 1.99E+3 1.62E+3 4.47E+S 1.29E+4 6.58E+2 Te-127m 1.67E+4 6.90E+3 4.,7E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 Te-127 2.23E+0 9.53E-1 1.85E+O 4.86EtO 1.03E+4 2.44E+4 4.89E-1 Te-129u 1.41E+4 6.09Et3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 Te-129 7.88E-2 3.47E-2 6.75E-2 1.75E-1 3,00E+3 2.63E+4 1.88E-2 Te-M31m 1.07E+2 5.S0E+I 8.93E+1 2.b5E+2 1.99E+5 1.19E+5 3.63E+1 Te-131 1.74E-2 8.22E-3 1.58E-2 3.99E-2 2.06E*3 8.22E+3 5.OOE-3 Te-132 3.72E+2 2.37E+2 2.79E+2 1.03E+3 3.40EtS 4,41E+4 1.76E+2 1-130 6.36Et3 1.39E+4 1.60E+6 1.53E+4 - 1.99E+3 5.57E+3 1-131 3.79E+4 4.44E+4 1.48E,7 5.18E+4 - 1.06E43 1.96E+4 1-132 1.69E+3 3.54E-3 1.69E*5 3.95E+3 - 1.90E+3 i.26E+3 1-133 1.32E+4 1.92E+4 3.56E+6 2.24E+4 - 2.16E+3 5.60E+3 FERMI 2 ODCM -TRM VOLUME 11 7-26 Rev. 13

Table 7.0-4 Raipo, Inhalation Pathway Dose Factors - INFANT (Cont.)

3 (mrem/yr per JLCi/m )

Huclide &one Liver Thyroid Kidney Luns GI-LLI T.kody 1-134 9.21E+2 1.88E+3 4.45E+4 2.09E+3 - 1.29E+3 6.65E+2 1-135 3.86E+3 7.60E+3 6.96E+5 B.47E43 - 1.83E+3 2.77E,3 Cs-134 3.96E+5 7.03E+5 - ,.90E+5 7.97E+4 1.33E+3 7.45E.4 Cm-136 4.83E-4 1.35E+5 - 5.64E+4 1.18E+4 1.43E+3 5.29E+4 Cs-137 5.49E+5 6.12E+5 - 1.72E+5 7.13E+4 1.33E43 4.55E+4 Cx-138 5.05E+2 7.81E+2 - 4.10E+2 6.54E+i 8.76E42 3.98E+2 BA-139 1.48E+O 9.84E-4 - 5.92E-4 5.95Ei3 5.10E+4 4.30E-2 Ba-140 5.60E+4 5.60E+1 - 1.34E*l 1.60E+6 3.84E+4 2.90E+3 Ba-141 1.57E-1 1.08E-4 - 6.50E-5 2.97E+3 4.75E+3 4.97E-3 sa-142 3.98E-2 3.30E-5 - 1.90E-5 1.55E+3 6.93E+2 1.96E-3 LA-1M0 5.05E+2 2.OOE+2 - 1.68E5 8.48E+4 5.15E+1 La-142 1.03E+0 3.77E-1 - - 8.22E+3 5.95E+4 9.04E-2 Ce-141 2.77E+4 1.67E+4 - 5.25E*3 5.17E+5 2.16E+4 1.99E+3 Ce-143 2.93E+2 1.93E+2 - 5.b4E+1 1.16E+5 4.97E+4 2.21E+1 Ce-144 3.19E+6 1.21E+6 - 5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 - 1.97Et3 4.33E+5 3.72E+4 6.99E+2 Pr-144 4.79E-2 i.85E-2 - 6.72E-3 1.61E+3 4.28E+3 2.41E-3 Nd-147 7.94E+3 8.13E+3 - 3.ISE+3 3.22E+5 3.12E+4 5.00E+2 W-187 1.30E+1 9.02E+O - - 3,96E+4 3.56E+4 3.12E+O Np-239 3.71E+2 3.32E+1 - 6.62E+1 5.95E+4 2.49E+4 1.88E+1 FERMI 2 ODCM - TRM VOLUME II 7-27 Rev. 13

Table 7.0-4 Raipo, Grass-Cow-Milk Pathway Dose Factors - ADULT (mrem/yr per L Ci/m 3 ) for H-3 and C-14 2

(m x mrem/yr per .Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung CI-LLI 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+' 7.26E+4 7.26E+4 7.26E+4 4

Na-2 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 P-32 1.71E+10 1.06E+9 - - - 1.92E+9 6.60E+8 Cr-51 - - 1.71E'4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-4 - 8.40E+6 - 2.50E+6 - 2.57E+7 1.60E+6 Hn-56 - 4.23E-3 - 5.38E-3 - 1.35E-1 7.51E-4 Fe-55 2.51E+7 1.73E+7 - - 9.67E+6 9.95E+6 4.04E+6 Fe-59 2.98E+7 7.00E+7 - - 1.95E+7 2.33E+8 2.68E+7 Co-57 - 1.28E+6 - - - 3.25EK7 2.13E+6 Co-58 - 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+8 Ni-65 3.70E-1 4.81E-2 - - - 1.22E+0 2.19E-2 Cu-64 - 2.41E+4 - 6.08E+4 - 2.05E+6 1.13E+4 Zn-65 1.37E+9 4.36E+9 - 2.92E+9 - 2.75E+9 1.97E+9 Zn-69 -

Br-82 - - - 3.72E+7 3.25E+7 Br-83 - - - - 1.49E-1 1.03E-1 Br-8 - -

Br-85 Rb-86 - 2.59E+9 - - - 5.11E+8 1.21E+9 Rb-88 -

Rb-89 -

Sr-89 1.45E+9 - - - 2.33E+8 4.16E+7 Sr-90 4.68E+10 - - - 1.35E+9 1.15E+10 Sr-91 3.13E4 - - - - 1.49E 1.27E+3 Sr-92 4.89E-1 - - - - 9.68E+0 2.11E-2 Y-90 7.07E1 - - - - 7.50E+5 1.90E+0 Y-91 -

Y-91 8.60E+3 - - - - 4.73E+6 2.30E+2 Y-92 5.42E-5 - - - - 9.49E-1 1.58E-6 Y-93 2.33E-1 - - - - 7.393 6.43E-3 Zr-95 9.46E+2 3.03E+2 - 4.76E+2 - 9.62E+5 2.05E+2 Zr-97 4.26E-1 8.59E-2 - 1.30E-1 - 2.66E+4 3.93E-2 Nb-95 8.25E*4 4.59E+4 - 4.54E+4 - 2.79E+8 2.47E+4 Nb-97 - - - - 5.47E-9 Mo-99 - 2.52E+7 - 5.72E+7 - 5.85E+7 4.80E+6 Tc-99m 3.25E+0 9.19E+0 - 1.40E+2 4.50E+0 5.44E+3 1.17E+2 Tc-101 - -

Ru-103 1.02E+3 - - 3.B9E+3 - 1.19E£5 4.39E+2 Ru-105 8.57E-4 - - 1.11E-2 - 5.24E-1 3.38E-4 Ru-106 2.04E*4 - - 3.94E+4 - 1.32E*6 2.58E+3 Rh-103m - - -

Rh-106 - - -

Ag-110 5.83E+7 5.39E7 - 1.06E+8 - 2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E4 - 2.00E.7 7.31E+8 1.02E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4' 1.58Ei7 2.25Et8 4.86E*6 Te-125m 1.63EK7 5.90E+6 4.90E+6 6.63E-7 - 6.50E+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 - 1.54E+8 5.58E+6 Te-127 6.72E+2 2.41Et2 4.98E*2 2.74E'3 - 5.30E'+4 1.45E+2 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 - 3.04E+8 9.57E+6 Te-129 -

Te-131m 3.61E+5 1.77E+5 2.80Ei5 1.79E+6 - 1.75Et7 1.47E+5 Te-131 Te-132 2.39E+6 1.55E*6 1.71E+6 1.49E+7 - 7.32E+7 1.45E+6 1-130 4.26E+5 1.26E+6 1.07E+8 1.96E+6 - 1.08E+6 4.96E+5 1-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 - 1.12EB8 2.43E+8 1-132 1.64E-1 4.37E-1 1.53E.1 6.97E-1 - 8.22E-2 1.53E-1 1-133 3.97E+6 6.90EK6 i.01E*9 1.20E+7 - 6.20E+6 2.10E*6 FERMI 2 ODCM - TRM VOLUME II 7-28 Rev. 13

Table 7.0-4 Raipo, Grass-Cow-Milk Pathway Dose Factors - ADULT (CONT.)

(mrem/yr per JlCi/m 3) for H-3 and C-14 2

(i x mrem/yr per UCi/sec) for others Nuclide bone Liver Thyroid Kidney Lung C1-LL1 T. Sody 1-134 1-135 1.39E+4 3.63E+4 2.40E+6 5.83E+4 - 4.10E+4 1.34E+4 Co-134 5.65E+9 1.34E+10 - 4.35E+9 1.44E+9 2.35E+8 1.iOE+1O CU-136 2.61E+B 1.03E+9 - 5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 1.O1E+10 - 3.43E+9 I.i4E+9 1.95E+8 6.61E-9 Cx-138 Ba-139 4.70E-8 8.34E-8 1.38E-9 BX-140 2.69E+7 3.38Ei4 - .15E+4 1.93E+4 5.54E+7 1.76E+6 Ba-141 BA-142 LA-40 A.49E+O 2.26E+O - - 1.66E+5 5.97E-1 La-142 - 3.03E-8 -

Ce-141 4.84E+3 3.27E+3 1.52E+3 - 1.25E+7 3.71E+2 Ce-143 4.19E41 3.09E+4 1.36E+1 1.16E+6 3.42E+O Cc-144 3.58E5 1.50E45 8.87E+4 - l.21E+B 1.92E+4 Pr-143 1.59E+2 6.37E+l 3.68E+1 - 6.96E+5 7.88EF+

Pr-144 Nd-147 9.42E+1 1.09E+2 - 6.37E+1 - 5.23E+5 6.52E+O W-1B7 6.56E+3 5.48E+3 - - 1.80E+6 1.92E+3 Np-239 3.66E+o 3,60E-1 - iEs - 7.39Et12 1.98E-1 FERMI 2 ODCM - TRM VOLUME 11 7-29 Rev. 13

Table 7.0-4 Raipo , Grass-Cow-Milk Pathway Dose Factors - TEENAGER (mrem/yr per /LCi/m 3 ) for H-3 and C-14 (m 2 x mrem/yr per yLCi/sec) for others Nuclide Bone Liver Thyroid Kidney Luns GI-LLI T.Body H-3 - 9.94E2 994E+29.94E+2 9. 94E+2 9.94E+2 9.

994E2 C-14 6.70E+5 1.34E+5 1.34E 5 1.34E+5 1.34£E5 1.34E+5 1.34E+5 Na-24 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 P-32 3.15E+10 1.95E+9 - - - 2.65E+9 1.22E+9 Cr-51 - - 2.78E+4 1.10E+4 7.13E+4 8.40E+6 S.00E+4 Hn-54 - 1.40E+7 - 4.17E+6 - 2.87E+7 2.78E+6 Hn-56 - 7.51E-3 - 9.50E-3 - 4.94E-1 1.33E-3 Fe-55 4.45E+7 3.16E+7 - - 2.00E+7 1.37EL7 7.36E+6 Fe-59 5.20E+7 1.21E*8 - - 3.82E*7 2.87E+8 4.68E+7 Co-57 - 2.25E+6 - - - 4.19E+7 3.76E+6 Co-58 - 7.95E+6 - - - 1.10£E8 1.83E+7 Co-60 - 2.78E+7 - - - 3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 - - - 1.33E+8 4.O1E+8 Ni-65 6.78E-1 8.66E-2 - - - 4.70E+0 3.94E-2 Cu-64 - 4.29E+4 - 1.09E+5 - 3.33E+6 2.02E+4 Zn-65 2.11E+9 7.31E+9 - 4.68E+9 - .3;10E+9 3.41E+9 Zn-69 - -

Br-82 - - - - - - 5.64E+7 Br-83 - - - - - - 1.91E-1 Br-84 - - -

Br-85 - - - -

Rb-86 - 4.73E+9 - - - 7.00E+8 2.22E+9 Rb-88 - - - - -

Rb-89 - - - - -

Sr-89 2.67E+9 - - - - 3.18E+8 7.66E+7 Sr-90 6.61E+10 - - - - 1.86E+9 1.63E+10 Sr-91 5.75E+4 - - - - 2.61E+5 2.29E+3

.Sr-92 8.95E-1 - - - - 2.28E+1 3.81E-2 Y-90 1.30E+2 - - - - 1.07E+6 3.50E+O Y -

Y-91 1.58E+4 - - - 6.48E+6 4.24E+2 Y-92 1.00E-4 - - - - 2.7SE+0 2.90E-6 Y-93 4.30E-1 - - - - 1.31E+4 1.18E-2 Zr-95 1.65E+3 5.22E+2 - 7.67E+2 - 1.20E+6 3.59E+2 Zr-97 7.75E-1 1.53E-1 - 2.32E-1 - 4.15E+4 7.06E-2 Nb-95 1.41E+5 7.80E+4 - 7.57E+4 - 3.34E+8 4.30E+4 Nb-97 - - - 6.34E-8 Ho-99 - 4.56E+7 - 1.04E+8 - 8.16E+7 8.69E+6 Tc-99m 5.64E+0 1.57E*1 - 2.34E+2 8.73E+0 1.03E+4 2.04E+2 Tc-101 Ru-103 1.81E+3 - - 6.40E43 - 1;52E+5 7.75E+2 Ru0l5 1.57E-3 - - 1.97E-2 - 1.26E+0 6.08E-4 Ru-106 3.75E+4 - - 7.23E4 - 1.80E+6 4.73E+3 Rh-103m - -

Rh-106 -

AA-110m 9.63E+7 9.11E+7 - 1.74E+8 - 2.56E+10 5.54E*7 Sb-124 4.59E+7 8.46E+5 1.04E+5 - 4.01E+7 9.25E+8 1.79E.7 Sb-125 3.65E+7 3.99E+5 3.49E*4 - 3.21E*7 2.84E+8 8.54E+6 Te-125m 3.00E+7 1.08E+7 8.39E.6 - - 8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 - 2.10E+8 1.00E*7 Te-127 1.24E+3 4.41E+2 8.59E*2 5.04E+3 - 9.61E+4 2.68E,2 Te-129. 1.11E+8 4.10E+7 3.57E+7 4.62E+8 - 4.15E+8 1.75E+7 Te-129 - - - 1.67E-9 - 2.18E-9 Te-131m 6.57E+5 3.15E+5 4.74Et 3.'29E+6 - 2.53E+7 2.63E+5 Te-131 Te-132 4.28E+6 2.71E£6 2.86E+6 2.60Et7 - . 8.58E+7 2.55E+6 1-130 7.49E+5 2.17E*6 1.77E+8 3.34E+6 - 1.67E*6 8.66E+5 1-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 - 1.49E+8 4.04E+8 1-132 2.90E-1 7.59E-1 2.56E+1 1.20E*0 - 3.31E-1 2.72E-1 1-133 7.24E+6 1.23E+7 1.72E+9 2.15Et7 - 9.30E+6 3.75E+6 FERMI 2 ODCM - TRM VOLUME II 7-30 Rev. 13

Table 7.0-4 Raipo, Grass-Cow Milk-Pathway Dose Factors - TEENAGER (Cont.)

(mrem*/yr per UIC i/rn 3 ) for H-3 and C-14 (mn2 x mrem/yr per /I Ci/sec) for others Hucl ide lobe Liver Thyroid Kidney Lun G1-LL1 T. ody 1-134 - - - - --

1-135 2.47E*4 6.35E+4 4,08E+6 1.ODOE+5 - 7.03E+4 2.35E+4 Cr.-134 9. 81 E+9 2. 31E-t10 - 7.34E+9 2,80E+9 2.87E.&b 1.07E+10 Ca-136 4.45E+8 1.75E+9 - 9.53E*8 1.5OE*8 1.41E.8 L1.1E+9 Co-137 1.34E+10 1.78E+10 - 6.06E+9 2.35E+9 2.53E+B 6.20E+9 Cg-M3 Bx-139 8.69E-8 - - 7.75E-7 2.53E-9 DA-140 4.85E+7 5.95E+4 - 2.02E+4 4.DOE+4 7.49E+7 3.13E+6 Ba-141 - - -

Ba-142 - - - - - - -

LA-140 8.06E+O 3.96E+O - - - 2.27E+5 1.05E+O LA-142 - - - - - 2.23E-7 -

Ce-141 8.87E+3 5.92E+3 - 2.79E+3 - 1.69E+7 6.81E+2 Cc-143 7.69E+1 5.60E+4 - 2.51E+1 - 1.68E+6 6.251EO Ue-144 6.58E+5 2.72E+5 - 1.63E+5 - 1.66E+B 3.54E+A Pr-143 2.92E+2 1,17E+2 - 6.77E+1 - 9.61E+S 1.45E+i Pr-144 - - - - - -

H~d-147 1.81E+2 1.97E+2 - 1.16E+2 - 7.11E+5 1.18E+1 W-187 1.20Ef4 9.78E+3 - - 2.65E+6 3.43E+3 Np-239 6.99E+0 6.59E-1 2.07E+0 - 1.06E+5 3.66E-1 FERMI 2 ODCM -TRM VOLUME 11 7-31 Rev. 13

Table 7.0-4 R,ipo, Grass-Cow-Milk Pathway Dose Factors, - CHILD (mrem/yr per yCi/m 3) for H-3 and C-14 2

(i x mrem/yr per pL1Ci/sec) for others Nuclide Sone Liver Thyroid Kidney Lung GI-LL1 T.Body H-3 - 1,57E-3 1.57E+3 i.57E-3 1.57E+3 1,57E*3 1.57E+3 C-14 1.65Ei6 3.29E+ 3.29E+S 3.29E+5 3.29E45 3.29E,5 3.29E+5 Na-24 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 P-32 7.77E+10 3.64E49 2.15E9 3.OOE+9 Cr-51 - - 5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+S Hn-54 - 2.09EI7 - S.87E+6 - 1.76E+7 5.58E+6 Kn-56 - 1.31E-2 - 1.58E-2 - i.90E+0 2.95E-3 Fe-55 1.12E+8 5.93E+7 - - 3.35E+7 1.10E+7 1.84E+7 Fe-59 1.20E+8 1.95E*8 - 5.65E+7 2.03E+8 9.71E+7 Co-57 - 3.84E+6 - - - 3.14E+7 7.77E+6 Co-58 - 1.21E-7 - - - 7.08E+7 3.72E+7 Co-60 - 4.32E+7 - 2.39E+8 1.27E+8 Ni-63 2.96E+i0 1.59E+9 1.07E+B 1.01E*9 Ni-65 1.66E+0 1.56E-1 - 1.915*1 9.115-2 Cu-b4 - 7.55E+4 - 1.82E5+ - 3.54E*6 4.56E*4 Zn-65 4.13E49 1.10E+10 - 6.94E+9 - 1.93E+9 6.85E+9 Zn-69 - - - - - 2.14E-9 -

Br-82 - - - - - - 1.15E+8 Br-83 - - - - - - 4.69E-1 Br-B4 - - - -

Br-85 -

Rb-86 - 8,77E+9 5.64E+8 5.39E+9 Rb-88 Rb-89 Sr-89 6.62E+9 - 2.56E*8 1.89E+8 Sr-90 1.12E+11 - 1.51E+9 2.83E+10 Sr-91 1.41E+5 - - - - 3.12E+5 5.33E+3 Sr-92 2.19E0O - 4.14E+1 8.76E-2 Y-90 3.22E+2 - 9.15E+5 8.61E+O Y-91A Y-91 3.91E+4 - 5.21E+6 I.04E+3 Y-92 2.46E-4 - 7.10E+0 7.03E-6 Y-93 1.06E+0 - 1.57E+4 2.90E-2 Zr-95 3.84E+3 8.45E+2 - 1.21E+3 - 8.81E+5 7.52E+2 Zr-97 1.89E+0 2.72E-1 - 3.91E-i - 4.13E44 1.61E-1 Nb-95 3.18E+5 1.24E+5 - 1.16E+5 - 2.29E54 8.84+4

- 1.45E-6 -

Nb-97 mo-99 8.29E+7 - 1.77E+8 - 6.86E+7 2.05E+7 Tc-99a 1.29E+1 2.54E*1 - 3.68E42 1.29E+1 1.44E+4 4.20E+2 Tc-1O1 Ru-103 4.29E*3 - - 1.oBE+4 - 1.11E+S 1.65E-3 Ru-10S 3.82E-3 - - 3.36E2 - 2.49E+0 1.39E-3 Ru-106 9.24E+4 - - 1.25E+5 - 1.44E+6 1.15+4 Rh-103m - -

Rh-106 - - -

As-110m 2.09E+8 1.41E+8 - 2.63E+8 - 1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+B 2.40E+5 - 6.03E+7 6.79E+8 3.81E+7 Sb-125 8.70E+7 1.41E*6 8.06E*4 - 4.85+7 2.08E+8 1.82E+7 Te-125M 7.38E+7 2.0O5+7 2.07E+7 - - 7.12E+7 9.84E+6 Te-127x 2.08E+8 5.60E+7 4.97E+7 5.93E+8 - 1.68E+8 2.47E+7 Te-127 3.06E+3 8.25E*2 2.12E+3 8.71E*3 - - 1.20E*5 6.56E*2 Te-129m 2.72E+8 7,61t.7 8.78E+7 8.O0E+8 - 3.325+8 4.23E+7 Te-129 2.87E-9 - 6.12E-8 -

Te-131m 1.60E+6 5.53E+S 1.14E+6 S.35E+6 - 2.24E+7 5.89E+S Te-131 Te-132 1.02E+7 4.52E+6 6.58E+6 4.205+7 - 4.55E+7 5.46E+6 1-130 1.75E+6 3,54E+6 3-90E+8 5.29E.6 - 1.66E+6 1.82E*6 1-131 1.30E+9 1.31E.9 4.34E+11 2.15E*9 - 1.17L*8 7.46E+8 1-132 6.86E-1 1.26E+O 5.85E+1 1.93E+0 - 1.48E+0 5.80E-1 1-133 1.765*7 2.18E+7 4.04E+9 3.63E+7 - 8.77E+6 8.23E+6 FERMI 2 ODCM - TRM VOLUME 11 7-32 Rev. 13

Table 7.0-4 R,ip,, Grass-Cow-Milk Pathway Dose Factors - CHILD (CONT.)

3 (mnrem/yr per /LC i/rn ) for H-3 and C-14 2

(in x mnrem/yr per yLCi/sec) for others Nuclide &.one Liver Thyroid Kidney Lung GI-LLI T. tody 1-134 - - - - - -

1-135 5.84E+4 1.05E+5 9. 30F+6 1.61E+S - 8.OOE+4 4.97E+4 c.-134 2.26E+10 3.7iE+10 - 1.15E+10 4.13E+9 2.00E+8 7.83E+9 ca-136 1.O0E+9 2.76E+9 - 1.47E+9 2.i9E+8 9.70E+7 1.79E+9 cm-137 3.22E+10 3.09E+10 - 1.01E+io 3.62E+9 i.93E+8 4.55E+9 Co-138 - - - - - - -

Sat-139 2.14E-7 -i.23-laE-5 6.19E-9 BA-140 1.17E+B 1,03E4-5 - 3.34E+4 6.12E+4 5.94E+7 6.84Ei-6 BiA-14i - - - - - - -

LA-M$. 1.93E+1 6.74E+0 - - 1.88E+5 2.27E+O La-142 - - - - 2.51E-6 -

Ce-141 2.19E+4 1.09E+4 - 4.78E+3 - la36E+7 1.62E+3 Ce-143 1.89E+2 1.02E+S - 4.29E+1 - .1.50E+6 1.48E+1 Ce-144 1.62E+6 5.09E+5 - 2.82E+5 - 1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 - 1.17E+2 - 7.BOE+S 3.59E+1 Fr-144 - - - - - -

Nd-147? 4.45E+2 3.60E+2 - 1.9BE+2 - 5.71E+S 2.79E+1 W-187 2,91E+4 1.72E+4 - - - 2.42E*6 7.73E.0 Np-239 1.72E+1 1.23E+O - 3.57E+O - 9.14E4-4 8.68E-1 FERMI 2 ODCM -TRM VOLUME 11 7-33 Rev. 13

Table 7.0-4 Raipo, Grass-Cow-Milk Pathway Dose Factors - INFANT 3

(mrem/yr per / nCi/m ) for H-3 and C-14 2

(m x mrem/yr per g Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H - 2,38E+3 2.38E+3 2.38E+3 2.3BE+3 2.38E+3 2.38E23 C-14 3.23E+6 6.89£-5 6.89E+5 6.89E5 6.+5 6.89+E+ 6.895 6.89E+5 24 Na- 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 P-32 1.60E+11 9.42E9 - - - 2.17E+9 6.21E+9 Cr-51 - - 1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Hn-54 - 3.89E+7 - 8.63E+6 - 1.43E+7 8.83E+6 Hn-56 - 3.21E-2 - 2.76E-2 - 2.91E+0 5.53E-3 Fe-55 1.35E+8 8.72E+7 - - 4.27E+7 1.11E+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 - - 1.16E+8 1.88E+8 1.55E+8 Co-57 - 8.95E+6 - - - 3.05E+7 1.46E+7 Co-58 - 2.43E+7 - - - 6.05E+7 6.06E+7 Co-60 - 8.81E+7 - - - 2.10E+8 2.08E+8 NI-63 3.49E+10 2.16E+9 - - - 1.07E+8 1.21E+9 N1-65 3.51E+0 3.97E-1 - - - 3.02E+1 1.81E-1 Cu-64 - 1.88E+5 - 3.17E+5 - 3.85E+6 8.69E+4 Zn-65 5.55E+9 1.90E+10 - 9.23E+9 - 1.61E+10 8.78E+9 Zn-69 - - - - - 7.36E-9 Br-82 - - - - - - 1.94E+8 Br-83 - - - - - - 9.95E-1 Br-84 - -

Br-85 Rb-86 - 2.22E+10 - - - 5.69E+8 1.10E+10 Rb-88 Rb-89 Sr-89 1.2610 - - - - 2.59E+8 3.61E+8 Sr-90 1.22E+11 - - - 1.52E+9 3.10E+10 Sr-91 2.94E+5 - - - - 3.48E+5 1.06E+4 Sr-92 4.65E+0 - - - - 5.01E+1 1.73E-1 Y-90 6.80E+2 - ' - - 9.39E+5 1.82E+1 Y-91m -

Y-91 7.33+4 - - - - 5.26E+6 1.95E+3 Y-92 5.22E-4 - - - - 9.97E+0 1.47E-5 Y-93 2.25E+0 - - - - 1.78E+4 6.13E-2 Zr-95 6.83E+3 1.66E+3 - 1.79E+3 - 8.28E+5 1.18E+3 Zr-97 3.99E+0 6.85E-1 - 6.91E-1 - 4.37E+4 3.13E-1 Nb-95 5.93E+5 2.44E+5 - 1.75E+5 - 2.06E+8 1.41E+5 Nb-97 - - - - 3.70E-6 Mo-99 - 2.12E+8 - 3.17E+8 - 6.98E+7 4,13E+7 Tc-99m 2.69E+1 5.55E+1 - 5.97E+2 2.90E+1 1.61E+4 7.15E+2 Tc-101 - -

Ru-103 8.69E+3 - - 1.81E+4 - 1.06E+5 2.91E+3 Ru-105 8.06E-3 - - 5.92E-2 - 3.21E0 2.71E-3 Ru-106 1.90+5 - - 2.25E+5 - 1.44E+6 2.38E+4 Rh-103m Rh-106 - - -

Ag-110o 3.86E+8 2.82E+8 - 4.03E+8 - 1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E5 - 1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E6 1.B7E*5 - 9.38E+7 1.99E+8 3.07E+7 1.51Et8 5.04E+7 5.07E7 - 7.18E+7 2.04E+7 Te-125m Te-127m 4.21E+8 1.40E*8 1.22E+8 1.04E+9 1.70E+8 5.10E+7 Te-1 7 2

6.50E+3 2.18E.3 5.29E+3 1.59E+4 1.36E+5 1,40E+3 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 3.34E+8 8.62E+7 29 - 1.66E-7 Te-1 2.08E-9 - 1.75E-9 5.18E-9 Tc-131m 3.38E+6 1.36E+6 2.7bE+6 9.35E*6 - 2.29E+7 1.12E+6 Te-131 1.54E+7 6.51E+7 - 3.85E+7 9.72E+6 Te-132 2.10E*7 1.04E*7 1-130 3.60E+6 7.92E+6 8.88E+8 8.70E6 - 1.70E+6 3.18E+6 1-131 2.72E+9 3.21E+9 1.05E412 3.75E 9 - 1.15E.8 1.41E*9 1-132 1.42E+0 2.89£+0 1.35E+2 3.22E+0 - 2.34E+0 1.03E+0 1-133 3.72E+7 5.41E+7 9.84E+9 6.36E+7 - 9.16E+6 1.58E*7 7-34 Rev. 13 FERMI 2 ODCM - TRM VOLUME II

Table 7.0-4 Rai po, Grass -Cow-Milk Pathway Dose Factors - INFANT (CONT.)

(mrem/yr per yICi/m 3 ) for H-3 and C-14 (Mi2 x mrem/yr per /iCi/sec) for others Huclide boog Liver Thyroid Kidney Lunmg C1-LL1 T.tody 1-134 - - i.01E-9 - ~

1-135 1.21E+5 2.41E+5 2.i6E+7 2.69E+5 - 8.7S.E+4 B.B0E+4 c.-134 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 - 2.30E49 4.70E+8 8.76E+7 2.15E+9 Cx-137 5.15E+10 6.02E+i0 - 1.62E+10 6.55E+9 1.88E+8 4.27E49 cr-138 - - - - - - -

Ba-139 4.55E-7 - - - 2.88E-5 1.32E-8 RA-W4 2.41E+8 2.41E+5 - 5.73E+4 1.48E+5 5.92E+7 1.24E+7 BA-141 - - - - --

2 RA-14 - - - - - --

Le-140 4.03E+1 1.59E+l - 1.87E+S 4.D9E+0 LA-142 - - - - 5.21E-6 -

Ce-141 4.331+4 2.64E+4 - B.15E43 - 1.37E+7 3.11E+3 ce-143 4.00E+2 2.65E+5 - 7.72E+1 - 1.55E+6 3.02E+i Ce-144 2.33E+6 9.52E+S - 3.85E+5 - 1.331+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 - 2.08E+2 - 7.89E+5 7.41E11 Pr-144 - - - - - --

Nd-147 8.82E+2 9.06E+2 - 3.49E+2 - 5.74145 5.55E+1 W-187 6.12E+4 4.261+4 - - - 2.50E+6 1.47E+4 Np-239 3.641+1 3.25E+0 - 6.49E+0 - 9.40E+4 1.84E+0 FERMI 2 ODCM -TRM VOLUME 11 7-35 Rev. 13

Table 7.0-4 R,ipo, Grass-Cow-Meat Pathway Dose Factors - ADULT (mrem/yr per yCi/m 3 ) for H-3 and C-14 (m2 x mremlyr per yt Cisec) for others Nuclide Bone Liver Thyroid Kidney Luru GI-LL1 T.Body H-3 - 3.25Et2 3.25E*2 3.25E*2 3.25E+2 3.25E+2 3.25E+2 C-14 3.33E+5 6.66E+4 6.66E+4 6.66E*4 6.66E+4 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 4.65Ei9 2.89Et8 - . 23E+8 1 .BUk9 Cr-51 - 4.22E+3 1.56E+3 9.38E+3 I.78E+6 7.07E+3 Hn-54 9.15E+6 2.72E+6 2.B0E47 1.75E+6 Mn-56 Fe-55 2.93M+8 2.02E+B - - .13E+B 1.16EB 4.72E+7 Fe-59 2.67E+g 6.27E+B - 1.75E+8 2.09E+9 2.40E+8 Co-57 - 5.64E+6 - 1.43E+g 9.37E+6 Co-58 - 1.83E+7 - 3.70E+8 4.lbE+7 Co-60 - 7.52E+7 - 1.41E+9 1.66E+B Ni-63 1.89Etl0 1.31E+9 - 2.73E+8 6.33E+B Ni-65 Cu-64 2.95E-7 7.45E-7 - 2.52E-5 1.39E-7 Zn-65 3.56E+8 1.13E+9 7.57E*B - 7.13E+B 5.12E+8 Zn-69 - -

Br-B2 - - I . 44E*3 1.26E+3 Br-83 - -

Br-84 - -

Br-BS Rb-B6 - 4.87E+B 9.60E+7 2.27E48 Rb-B8 Rb-89 Sr-B9 3.01E+B E8 - - 4.B4E+7 8.65E+6 Sr-90 1.24E+10 - - 3.59E+8 3.05E+9 Sr-91 1.38E-9 Sr-92 - - - - - -

Y-90 1.07E+2 1.13E+6 2.,6E+O Y-91A Y-91 1.13E+6 6.24E+B 3.03E+4 Y-92 Y-93 2.08E-7 Zr-95 1.88E+6 6.04E+5 - 9.48E+5 - 1.91E+9 4.09E+5 Zr-97 1.83E-5 3.69E-6 - 5.58E-6 - 1.14E+0 1.69E-6 Nb-95 2.29E+6 1.28E+6 - 1.26E+6 - 7.75E+9 6.86E+5 Nb-97 -

Mo-99 - 1.09E+5 2.46E45 2.52E+5 2.07E+4 Tc-99m -

Tc-101 -

Ru-103 '1.06E+8 4.03E+8 1.23E+10 4.55E+7 Ru-105 Ru-106 2.80E+9 5.40E+9 1.81E+l1 3.54E+8 Rh-103m -

Rh-106 -

AS-110m 6.69E+6 6.19E.6 1.22E+7 2.52E+9 3.67E+6 Sb-124 1.98E+7 3.774E+S 4.80E+4 - 1.54E+7 5.62E+B 7.85E+6 Sb-125 1.91E+7 2.13E+S i.94E+4 - 1.47E+7 2.10E.8 4.54E.6 Te-125m 3.59E+8 1.30E+8 1.08EB I.46E+9 - I.43E+9 4.B1E+7 Te-127k 1.12E+9 3.99E+8 2,85E8 4.53E+9 - 3.74E+9 1.36E+8 Te-127 1.09E-9 - 2.10E-18 Te-129m 1.14E+9 4.27E+8 3.93E-8 4.77E+9 - 5.76E+9 1.81E+B Te-129 Te-13l1 4.51E+2 2.21E+2 3.50Et2 2.24E+3 2.19E+4 1.84E+2 Te-131 Te-132 1.40E+6 9.07E+5 i.O0E+6 B.73E+6 4.29E+7 B.51E*5 1-130 2.35E-6 6.94E-6 5.BBE-4 1.OBE-5 - 5.98E-6 2.74E-6 1-131 1.08E+7 1.54Et7 5.05E+9 2.64E+7 - 4.07E+6 8.83E+6 1-132 1-133 4.30E-1 7.47E-1 1.1OEt2 1.30E+O - 6.72E-1 2.2HE-1 FERMI 2 ODCM - TRM VOLUME 11 7-36 Rev. 13

Table 7.0-4 Raipo Grass-Cow-Meat Pathway Dose Factors - ADULT (CONT) 3 (mrem/yr per k1Cilm ) for H-3 and C-1i4 (in x mrem/yr per JlLCi/sec) for others 2

Liver Thyroid KZidney Luns GI-LLI T.AodY Nuclide tone 1-134-1a-135 .74 1.56E+9 - 5.06E4-8 i.68E+8 2.74E+7 i.2$E+9 4.67E4-7 - 2.60E+7 3.56E+6 5.30E+6 3.36E+7 cz-136 1.18E+7 1.19E+9 - 4.05E+8 1.35E+8 2.31E07 7.81E+8 cr,-137 8.72E+$

co-138 - -

s.-139 - -

3.61E+4 1.23F+4 2.07E+4 5.92E+7 1.89E+6 B.-140 2.88E+7 -

BA-142 - -

3..A-140 3.60E-2 I.81E-2 - - - 1.33E+3 4.79E-3 L.a-i42 - - -

1.40E+4 9.48E43 4.40E+3 - 3.62E+7 1.O8E+3 Ce-141 -

2.09E-2 1.SSE41l 6.80E-3 - 5.78E+2 1.71E-3.

ce-14~3 1.4,6E+6 6.09E+5 - 3;61E+S 4.93E+b 7.83E+4 Ce-144 -

2,13E+4 8.54E+3 - 4.93E*3 - 9.33E+7 1.06E+3 Pr-143 Pr-144a -

Nd-147 7.08E+3 8.18E+3 - 4.78E+3 - 3.93E+7 4.90E+2 W-197 2,16E-2 1.81E-2 - - - S.92E+0 6.32E-3 2.56E-1 2.51E-2 - 7.84E-2 - 5.15E*3 1.39E-2 Np-239 FERMI 2 ODCM -TRM VOLUME 11 7-37 Rev. 13

Table 7.0-4 R,ipo, Grass-Cow-Meat Pathway Dose Factors - TEENAGER 3

(mrem/yr per i Ci/m ) for H-3 and C-14 2

(m x mrem/yr per J Ci/sec) for others Nuclide Bone 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 1.94E+2 C-14 2.81E+5 5.62E+4 5.62E+4 5.62E+4 5.62E+4 5.62E+4 5.62E+4 Na-24 1.47E-3 1.47E-3 1.47E-3 1.47E-3 1.47E-3 1.47E-3 1.47E-3 P-32 3.93E+9 2.44E+8 - - - 3.30E+8 1.52E+8 Cr-51 - - 3.14E+3 1.24E+3 8.07E+3 9.50E+5 5.65E+3 4 1.38E+6 Mn-5 - 6.98E+6 - 2.08E+6 - 1.43E+7 Mn-56 Fe-55 2.38E+8 1.69E+8 1.07E+8 7.30E+7 3.93E+7 Fe-59 2.13E+8 4.98E+8 1.57E+8 1.18E1+9 1.92E+8 Co-57 - 4.53E+6 - 8.45E+7 7.59E+6 Co-58 - 1.41E+7 - - - 1.94E+8 3.25E+7 Co-60 - 5.83E+7 - - - 7.60E+8 1.31E+8 Ni-63 1.52E+10 1.07E+9 - - - 1.71E+8 5.15E+8 81-65 Cu-64 2.41E-7 - 6.10E-7 - 1.87E-5 1.13E-7 Zn-65 2.50E+8 8.69E+8 - 5.56E+8 - 3.68E+8 4.05E+8 Zn-69 - -

Br-82 - - - - 9.98E+2 Br-83 - -

8r-84 - -

8r-85 - -

Rb-86 - 4.06E+8 - - - 6.01E+7 1.91E+8 Rb-88 -

Rb-89 -

Sr-89 2.54Ei - - - - 3.03E+7 7.29E+6 Sr-90 8.05E+9 - - - - 2.26E+8 1.99E+9

- - - - 1.10E-9 -

Sr-91 Sr-92 y-90 8,98E+1 - - - - 7.40E+5 2.42E+0 Y-91m Y-91 9.56E+5 - - - - 3.92E+8 2.56E+4 Y-92 Y-93 - - - - - 1.69E-7 -

Zr-95 1.51E+6 4.76E+5 - 6.99E45 - 1.10E+9 3.27E+5 Zr-97 1.53E-5 3.02E-6 - 4.58E-6 - 8.18E-1 1.39E-6 Nb-95 1.79E+6 9.94E+5 - 9.64E+5 - 4.25E+9 5.47E+5 Nb-97 -

Mo-99 - . 8.98+4 - 2.06E+5 - 1.61E+5 1.71E+4 Tc-99m -

Tc-101 - - -

Ru-103 8.60E+7 - - .03E+8 - 7.18E+9 3.68E+7 Ru-105 Ru-106 2.36E+9 - - 4.55E+9 - 1.13E+11 2.97E+8 Rh-103m -

Rh-106 -

As-110m 5.06E+6 4.79E+6 - 9.14E+6 - 1.35E+9 2.91E+6 Sb-124 1.62E+7 2.98E+S 3.67E+4 - 1.41E+7 3.26E+8 6.31E+6 Sb-125 1.56E+7 1.71E+5 1.49E+4 - 1.37E+7 1.22E+8 3.66E+6 2

Te-1 5m 3.03E+8 1.09E+8 8.47E+7 - - 8.94E+8 4.05E+7 Te-127m 9.41E+8 3.34E+8 2.24E+8 3.82E+9 - 2.35E+9 1.12E+8 Te-127 - - - - - 1.75E-8 -

Te-129m 9.58E+8 3.56E+8 3.09E+8 4.01Et9 - 3.60E+9 1.52E+8 Te-129 Te-131m 3.76E+2 1.80E+2 2.71E+2 1.88E+3 - 1.45E+4 1.50E+2 Te-131 3 2.30E+7 Te-1 2 1.15E+6 7.26E+5 7.66E+5 b.97E+6 - 6.84E+5 1-130 1.89E-6 5.48E-6 4.47E-4 8.44E-6 - 4,21E-6 2.19E-6 1-131 8.95E+6 1,.25E+7 3.66E+9 2.16E+7 - 2.48E+6 6.73E+6 I-132 1-133 3.59E-1 b.10E-1 8.51E+1 1.07E+0 - 4.61E-1 1.86E-1 7-38 Rev. 13 FERMI 2 ODCM - TRM VOLUME 11

Table 7.0-4 Raipo, Grass-Cow-Meat Pathway Dose Factors - TEENAGER (CONT.)

(mrem/yr per 'LCi/m 3 ) for H-3 and C-14 (2x mrem/yr per yLCi/sec) for others Nuclidt &one Livtr Thyroid Kidney Lung CI-LLI T. body I---3-- - - --- - - - -- -- - - - ---

-- -- r- -- - -

1-134 - - - - - - -

Cx-134 5.21E+B 1.23E+9 - 3.91E+S 1.49E+B 1.53E+7 S.71E+8 Cm-136 9.22E+6 3.63E+7 - 1.97E+7 3.11E+6 2.92E+6 2.44E+7 C&-137 7.24E+8 9.63E+8 - 3.28E+B 1.27E+B 1.37E47 3,36E+B Ca-138 - - -

Ba-139 - - -

Ba-140 2.38E+7 2.91E+'. 9.88E+3 1.96E+4 3.67E+7 1.53E+6 B~a-142 - - - - -

LA-i4o 2.96E-2 1.45E-2 - - - 8.35E+2 3.87E-3 L.a-142 - - -- --

Ce-WA 1.18Ei-4 7.86E+3 - 3.70E+3 - 2.25E+7 9.03E+2 Ce-143 1.76E-2 1.28E+i 5.74E-3 - 3.85E+2 1.43E-3 Ce-i44 i.23E+6 5.08E+5 - 3.04E+5 - 3.09E+8 6.60E+4' Pr-143 1.79E+4 7-15E+3 - 4.16E+3 - 5,90E+7 8.92E+2 Pr-144 - - - -

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 Hp-239 2.23E-1 2.11E-2 - 6.61E-2 - 3.39E+3 1.17E-2 FERMI 2 ODCM - TRM VOLUME 11 7-39Re.1

Table 7.0-4 R,ipo, Grass-Cow-Meat Pathway Dose Factors - CHILD 3

(mrem/yr per /1Ci/n ) for H-3 and C-14 (M2 x mrem/yr per ALCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lurks GI-LLI T.Body H-3 - 2.34E*2 2.34E+2 2.34E+2 2.34E+2 2.34E*2 2.34E42 C-I14 5.29E+5 I.06E+5 1.06E+5 1.06Et5 1.06E5 I.D6E+5 1.06E+5 Nx-24 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 P-32 7.41+9 3.47E+8 2.05E68 2.86E+8 Cr-51 - - 4.89E+3 1.34E+3 8.93E+3 4.67E+5 8.81E*3 Mn-54 7.99E+6 2.24E46 6.70E+6 2.13E+6 Mn-56 Fe-55 4.57E+8 2.42E+8 - 1.37E+8 4.49E+7 7.51E+7 Fe-59 3.78E+8 6.12E+8 - 1.77E+8 6.37E+8 3.05E+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 - - - 1.05E+8 9.91E+8 Ni-65 Cu-64 3.24E-7 7.82E-7 - 1.52E-5 1.96E-7 Zn-65 3.75E+8 1.00E+9 6.30E+8 - 1.76E+8 6.22E+8 Zn-69 Or-82 1.56E+3 Br-83 Br-84 Br-85 Rb-86 - 5.76E+8 3.71E+7 3.54E+8 Xb-88 Rb-89 Sr-89 4.82E+8 - 1.86E+7 1.38E+7 Sr-90 1.04E+10 - 1.40E+8 2.64E+9 Sr-91 1.01E-9 K

Sr-92 Y-90 1.70E+2 - - - - 4.84E+S 4.55E+0 Y-91S Y-91 1.81E+6 2.41E+8 4.83E+4 Y-92 Y-93 - 1.55E-7 Zr-95 2.68E+6 5.89E+5 - 8.43E+5 - 6.14E+8 5.24E+5 Zr-97 2.84E-5 4.10E-6 - 5.89E-6 6.21t-1 2.42E-6 Nb-95 3.09E+6 1.20E+6 - 1.13E+6 - 2.23E+9 8.61E+5 Nb-97 -

No-99 - 1.25E+5 2.67E+5 1.03E+5 3.09E+4 Tc-99m -

Tc-101 -

Ru-103 1.56E+8 3.92E+8 4.02E-9 5.98E+7 Ru-105 Ru-106 4.442+9 5.99E+9 6.90E+10 5.54E+8 Rh-103m -

Rh-106 -

AS-110m 8,40E+6 5.67E+6 - 1.06E+7 - 6.75E+8 4.53E+6 Sb-124 2.93E+7 3.80E-5 6.46E*4 - 1.62E+7 1.83E+8 1.03E.7 Sb-125 2.85E+7 2.19E*5 2.6424 - 1.59E*7 6.80E+7 5.96E+6 Te-1Q5% 569E48 1.54E+8 1.60E+B - - 5.49E+8 7.59E+7 Te-127& 1.77E+9 4.78E+8 4.24E-8 5,06E.9 - 1.44E+9 2.11E*8 Te-12? 1.21E-9 - 1.66E-8 -

Te-129m 1,81E.9 5.04E+8 5.822.8 5.30E+9 - 2.20E+9 2.8OE+8 Te-129 Te-131m 7.00E42 2.42E*2 4.98E-2 2.342+3 9.82E+3 2.58E+2 Te-131 Te-132 2.09E+6 9.27E*5 1.35E+6 8.60E+6 9.33E+6 1.122.6 1-130 3.39E-6 6.85E-6 7.54E-4 1,022-5 - 3.20E-6 3.53E-6 1-131 1,66E+7 1.67EL7 5.522-9 2.74E+7 - 1.49E+6 9.492.6 1-132 1-133 6.68E-1 8.26E-1 1.53E+2 1.38E+O - 3.33E-1 3.12E-1 FERMI 2 ODCM - TRM VOLUME I1 7-40 Rev. 13

Table 7.0-4 R,ipo, Grass -Cow-Meat Pathway Dose Factors - CHILD (CONT.)

(inrem/yr per /1 LCi/m 3 ) for H-3 and C-14 2

(in x mrem/yr per /1 Ci/sec) for others Nuclide Done Liver Thyroid Kidney Lun,g GI-LLI T. body cm-134 9.22E+8 1.51E+9 - 4.69E+8 1.68E+8 8.15E+6 3.19E*b Cx-136 i.59E+7 4.37E+7 - 2.33E+7 1.47E+6 1.54E+6 2.83E+7 us-137 1.33E+9 1.28E+9 - 4.16Es-8 1.50E+8 7.99E+6 1.88E+B CA-138 - - - - - -

Ba-139 - - - - --

BA-140 4.39E+7 3.85E+4 - 1.2SE+4 2.29E+4 2.22E+7 2.56E4.6 Ba-W4 Ba-142 - - -

L&a-140 5.41E-2 1.89E-2 - - 5.27E+2 6.38E-3 La- 14 2 - - - - - - -

Cc-141 2.22E+4 1.11E+4 - 4.84E+3 - 1.38E+7 1.64E+3 Ce-143 3 .30E-2 I .79E+ I - 7.51E-3 - 2.62E+2 2.59E-3 Cc-144 2.32E+6 7.26E+5 - 4.02E+5 - 1.89E+8 1.24E+5 Pr-143 3.39EtI4 1.02E+4 - S.SIEi-3 - 3.66E+7 1.68E+3 Pr-144 - - - - - - -

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+O 9.92E-3 Np-239 4.20E-1 3.02E-2 - 8.73E-2 - 2.23E.'3 2.12E-2 FERMI 2 ODCM -TRM VOLUME I1 7-41 Rev. 13

Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - ADULT (mrem/yr per /1Ci/m 3) for H-3 and C-14 (M2 x mrem/yr per JCi/sec) for others Nuclide Bone Liver Thyroid . Kidney Lung CG-LLI T. Body 0-3 - 2.26E+3 2.26Et3 2.26E+3 2.26E+3 2.26Et3 2.26E*3 C-14 8.97E+5 1.79E+5 1.79Et5 1.79E+5 1.79E+S 1.79E+5 1.79E+5 Na-24 2.76E+ 5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 P-32 i.40E+9 8.73E+7 1.58E+8 5.42E+7 Cr-51 - - 2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Mn-54 - 3.11E+8 - 9.27E+7 - 9.54E+8 5.94E+7 Hn-56 - 1.61E+1 - 2.04E+1 - 5.13E+2 2.85E+0 Fe-55 2.09E+8 1.45E+B - 8.06E47 8.29E+7 3.37Et7 Fe-59 1.27E+8 2.99E+8 - 8.35E+7 9.96E+B 1.14E+8 Co-57 - 1.17E+7 - - 2.97Et8 1.95E*7 Co-58 - 3.09E+7 - - 6.26E+B 6.92E+7 Co-60 - 1.67E+8 - - 3.14E+9 3.69E+B Ni-63 1.o4EL1o 7.21E+8 - - 1.50Ev8 3.49Ev8 Ni-65 6.5Evl 7.99Ev-O - - 2.03E+2 3.65E+0 Cu-64 - 9.27E+3 - 2.34E+4 - 7.90E+5 4.35E+j Zn-65 3.17E+B 1.0l1E9 - 6.75Ev8 - 6.36EvB 4.56E+8 Zn-69 8.75E-6 1.67E-5 - 1.09E-5 - 2.51E-6 1.16E-6 Br-82 - - - - - 1.73E+6 i.SIE+6 Br-83 - - - - - 4.63EvO 3.21EvO Br-84 - - - - -

Br-85 - - - - -

Rb-86 - 2.19E+8 - - - 4.32Ev7 1.02EvB Rb-88 Rb-89 Sr-89 9.96E+9 - - - - 1.60E+9 2.86E+8 Sr-90 6.05E-l1 - - - - 1.75Ev10 1.48E+11 Sr-91 3.2OE45 - - - - 1.52E+6 1.29E+4 Sr-92 4.27E2 - - - - .46E+3 1.85E+i Y-90 1.33Ev4 - - - - 1.41E+8 3.56E+2 Y-91m 5.83E-9 - - - - 1.71E-8 Y-91 5.13Ev6 - - - - 2.82E+9 1.37Ev5 Y-92 9.olE-1 - - - - 1.58E+4 2.63E-2 Y-93 1.74E+2 - - - - 5.52E+6 4.BOE+O Zr-95 1.19E+6 3.81Ev5 - 5.97E+5 - 1.21Ev9 2.58E+5 Zr-97 .3.33Ev2 6.73E+1 - 1.02E+2 - 2.0OEv7 3.08Ev1 Nb-95 1.42E+5 7.91Ev4 - 7.81Ev4 - 4.80E+8 4.25E+4 Nb-97 2.90E-6 7.34E-7 - 8.56E-7 - 2.71E-3 2.6BE-7 Ho-99 - 6.25E+6 - 1.41E+7 1 - 1.45Ev7 1.19E+6 Tc-99m 3.06Ev- 8.66E+0 - 1.32E+2 4.24Ev- 5.12Ev3 1;10E+2 To-101 Ru-103 4.80Ev6 - 1.83E+7 - 5.61EvB 2.07Ev6 Ru-105 5.39E1 - - 6.96E+2 - 3.30E+4 2.13E+1 Ru-106 1.93Ev8 - 3.72E-B - 1.25Ev10 2.44E+7 Rh-1031m - -

Rh-106 - -

A,%-110m 1.06Ev7 9.76Ev6 - 1.92E+7 - 3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E-S - 8.08Ev7 2.95Ev9 4.11E+7 Sb-125 1.36Ev8 1.52E+6 1,39Ev- - 1.05Ev- 1.50E49 3.25E+7 Te-12S5 9.66Ev7 3.50E47 2.90E+7 3.93Ev8 - 3.86EvB 1.29Ev7 Te-12?n 3.49Ev8 1.25Ev8 8.92Ev7 1,42E+9 - 1.7E+9 4.26E0-Te-127 5.76E+3 2.07E+3 4.27E+3 2.35E+4 - 4.54Ev5 1.25E+3 Te-129m 2.55E+8 9.50Ev7 8.75E47 1.06E+9 - I.28E49 4.03E+7 Tc-129 6.65E-4 2.50E-4 5.10E-4 2.79E-3 - 5.02E-4 1.62E-4 Te-131m 9.12E45 4.46E*5 7.06E+5 4.52E+6 - 4.43E*7 3.72E+S Te-131 Te-132 4.29Ev6 2.77E+6 3.06E+6 2.67E+7 - 1.31EvB 2.60E+6 1-130 3.96E+5 1.17E+6 9.90Ev7 1.82Ev6 - 1.01E+6 4.61E+S 1-131 8.09Ev7 1.16E+B 3.79E+10 1.98EvB - 3.05Ev7 6.63E-7 1-132 5.74E4i 1.54E+2 5.38Ev3 2.45E+2 - 2.89Ev- 5.38Eil 2-133 2.12Ev6 3.69Ev6 5.42EvB 6.44E+6 - 3.31E+6 1.12Ev6 FERMI 2 ODCM - TRM VOLUME ii 7-42 Rev. 13

Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - ADULT (CONT.)

(mrem/yr per yCiIm3) for H-3 and C-14 2

(i x mrem/yr per /LCi/sec) for others Nucl de gone Liver Thyroid Kidney Luing O1-LLI T.Body I-13 4 1.06E-4 2.88E-4 5.00E-3 4.59E-4 - 2.51E-7 1.03E-4 1-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 - 1.21E*5 3.94E+4 Cx-134 4.66E+9 1.11E+iO 3.59E+9 1.19E+9 1,94E+8 9.07E+9 Cs-136 4.20E+7 1.66E+B - 9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6.36E+9 8.70E+9 - 2.95E+9 9.81E+8 1.68E+8 5.70E+9 Cx-138 Bx-139 2.95E-2 2.10E-5 - i.96E-5 1.19E-5 5.23E-2 8.64E-4 Ba-140 i.29E+8 1.62E+5 5.49E+4 9.25E+4 2.65E+8 8.43E+6 U.-142 LA-140 1.97E+3 9.92E*2 - 7.28E+7 2.62E+2 La-142 1.40E-4 6.35E-5 - 4.64E-1 1.58E-5 Ce-141 1.96E+5 1.33E+5 6.17E+4 - 5.08E+8 i.51E+4 Ce-143 1.00E+3 7.42E+5 3.26E+2. - 2.77E+7 8.21E+l Ct-144 3.29E+7 1.38E+7 - .16E16 - l.l1E+10 1.77E+6 Pr-143 6.34E+4 2.54E+4 1.47E+4 - 2.78E+8 3.14E+3 Pr-144 Nd-147 3.34E+4 3.86E+4 2.25E+4 - 1.8SE+B 2.31E+3 W-187 3.82E+4 3.19E+4 - 1,05E+7 l.12E+4 Np-239 1.42E+3 1.40E+2 4.37E+2 - 2.87E+7 7.72E+l FERMI 2 ODCM -TRM VOLUME 11 7-43 Rev. 13

Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - TEENAGER 3

(mrem/yr per U Cim ) for H-3 and C-14 2

(m x mrem/yr per Y Cilsec) for others Nuclide Bone Liver Thyroid Kidney Luna CI-LL T.Body H-3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E,3 0-14 1.45E+6 2.91E45 2.91E+5 2.91E+5 2.91E+5 2.91E*5 2.91E+5 Na-24 2.45E S 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45Et5 P-32 1.61E+9 9.96E+7 - - - 1.35E+8 6.23E+7 Cr-51 - - 3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Hn-54 - 4.52E+8 - 1.35E+8 - 9.27E+8 8.97E+7 Mn-56 - 1.45E+1 - 1.83E+1 - 9.54E+2 2.58E+0 Fe-55 3.25E+8 2.31Et+8 - 1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 - 1.33E+8 9.98E+8 1.63E+8 Co-57 - 1.79E+7 - - - 3.34E+8 3.00E+7 Co-58 - 4.38E+7 - - - 6.04E+8 1.01E+8 Co-60 - 2.49E+8 - - - 3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 - - - 1.81E+8 5.45E+*8 Ni-65 5.73E+1 7.32E+0 - - - 3.97E+2 3.33E+0 Cu-64 - 8.40E+3 - 2.12E+4 - 6.51E+5 3.95E+3 Zn-65 4.24E+8 1.47E+9 - 9.41E+8 - 6.23E+8 6.86E+8 Zn-69 8.19E-6 1.56E-5 - .1.02E-5 - 2.88E-5 1.09E-6 Br-82 - - - - - - 1.33E+6 Br-83 - - - - - - 3.01E+0 Br-84 Br-85 Rb-86 - 2.73E+8 - - - 4.05E+7 1.28E+8 Rb-88 Rb-89 Sr-89 1.51E+10 - - - - 1.80E+9 4.33E+8 Sr-90 7.51E+11 - - - - 2.11E+10 1.85E+11 Sr-91 2.99E+5 - - - - 1.36E+6 1.19E+4 Sr-92 3.97E+2 - - - - 1.01E+4 1.69E+1 Y-90 1.24E+4 - - - - 1.02E+8 3.34E+2 Y-91m 5.43E-9 - - - - 2.56E-7 Y-91 7.87E+6 - - - - 3.23E+9 2.11E+5 Y-92 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+5 - 8.07E+5 - 1.27E+9 3.78E+5 Zr-97 3.09E+2 6.11E+1 - 9.26E+1 - 1.65E+7 2.81E+1 Nb-95 1.92E+5 1.06E+5 - 1.03E+5 - 4.55E+8 5.86E+4 Nb-97 2.69E-6 6.67E-7 - 7.80E-7 - 1.59E-2 2.44E-7 Ho-99 - 5.74E+6 - i.31E+7 - 1.03E+7 1.09E+6 Tc-99m 2.70E+0 7.54E+0 - 1.12E+2 4.19E+0 4.95E+3 9.77E+1 Tc-101 Ru-103 6.87E+6 - - 2.42E+7 - 5.74E+8 2.94E+6 Ru-105 5.00E+1 - - 6.31E+2 - 4.04E+4 1.94E+1 Ru-106 3.09E+8 - - 5.97E+8 - 1.48E+10 3.90E+7 Rh-103m - - -

Rh-106 - - -

As-llO. 1.52E+7 1.44E+7 - 2.74E+7 - 4.04E+9 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 - 1.35E+8 3.11E+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+S - 1.88E+8 1.66E+9 5.000+7 Te-125% 1.48E+8 5.34E+7 4.14E+7 - - 4.37E+8 1.98E+7 Te-127m 5.51E+8 1.96E+8 1.31E*8 2.24E+9 - 1.37E+9 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 1.18E+8 1.54E+9 - 1.38E+9 5.81E+7 Te-129 6.22E-4 2.32E-4 4.45E-4 2.61E-3 - 3.40DE-3 1.51E-4 Te-131m 8.44*E+5 4.05E+5 6.09E+5 4.22E+6 - 3.25E+7 3.380+5 Te-131 Te-132 3.90E+6 2.47E,6 2.60E+6 2.37E+7 - 7.82E+7 2.32E+6 2-130 3.54E+5 1.02E+6 8.35E+7 1.58*E+6 - 7.87E+5 4.09E+5 I-131 7.70E07 1.08E+8 3.14E+10iO 1.85E+8 - 2.13E+7 5.79E+*7 1-132 5.18E+1 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 5.86E+6 - 2,53E+6 1.02E*6 FERMI 2 ODCM - TRM VOLUME 11 7-44 Rev. 13

Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - TEENAGER (CONT.)

3 (mrem/yr per u.Ci/m ) for H-3 and C-14 2

(in x mlrem/yr per /iLCi/sec) for others H4uclide bone Liver Thyroid Kidney Lutis C1-LL1 T.A*dy 1-134 9.59E-5 2.54E-4 4.24E-3 4.01E-4 - 3.35E-6 9.13E-5 1-135 3,68E+4 9.48E+4 6.10E+6 1.50E+5 - 1.O5E,-5 3.S2E+4 Cs-134 7.09E*9 1.67E+10 - S. 30E+9 2.02E+9 2.08EtS  ?.74E+9 36 Cx-i1 4.29E+7 1.69E+8 - 9.19E+7 1.45E.t7 1.36E+7 1.13E+8 Cx-137 1.OlE+10 1.35Ei-10 - 4.59E+9 1.78E+9 1.92E+B A.69E+9 Co-138 - - - - - - -

Ba-139 2. 77E-2 1.95E-5 - 1.84E-5 1. 34E-5 2.47E-1 8.OBE-4 Ba-140 1.38E+8 1.69E+5 - 5.75E+4 1.14.E+S 2.13E+8 8.91E4.6 Bj-142 - - - - - - -

LA-140 1.80E+3 8.84E+2 - - - 5.08E+7 2.35E*2 La-142 1.28E-4 5.69E-5 - - - 1.73E+O 1.42E-5 Ce-141 2.82E+5 1.88E+5 - 8.86E+4 - 5.38E+8 2.16E+4 Ce-W4 9.37E+2 6.82E+5 - 3.06E+2 - 2.05K.7 7.62E+1 Ce-144 5.27Ei'7 2.18E+7 - 1.30E+7 - 1.33E+10 2, 83E+6 Pr-143 7.12E+4 2.84E+4 - 1.65E+4 - 2.34E+B 3.55E+3 Pr-144 - - -

Nd-147 3.63E+4 3.94E+4 - 2.32E+4 - 1.42E+B 2.36E+3 W-187 3.55E+4 2.90E+4 - - - 7.84E+6 1.02E+4 2

Nlp-39 1.38E+3 1.30E+2 - 4,09E+2 - 2,10E+7 7.24E+1 FERMI 2 ODCM -TRM VOLUME 11 7-45 Rev. 13

Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - CHILD (mrem/yr per yCi/rn 3 ) for H-3 ard C-14 (M2 x mrem/yr per JlCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LL1 T.Body H-3 4.01E3 4.01E*3 4.01E+3 4.01E+3 4.01E+3 4.01LE3 C-14 3.50E+6 7.01E+5 7.01E+S 7.01E+5 7.01E+5 7.01E+5 7.01E+5 Na-24 3.83E+S 3.83E.5 3.83E+5 3.83E+5 3.83E+5 3.83EtS 3.83E+5 P-32 3.37E+9 1.58E+8 - - 9.30E+7 1.30E+8 Cr-51 - 6,54E+4 1.79E+4 1.19E*5 6.25E+6 i.18E*5 hn-54 - 6.61E+8 - 1.8SE+8 - S.55E+8 1.76E+8 Kn-56 - 1.90E+1 - 2.29Et4 - 2.75E+1 4.28E+o Fe-55 8.OOE+8 4.24E+8 - 2.40E+8 7.86E+7 1.31E+8 Fe-59 4.OE1E8 6.49E+8 - 1.8BE+8 6.76E8B 3.23E+8 Co-57 - 2.99E+7 - - 2.45E+B 6.04E+7 Co-58 - 6.47E+7 - - 3.77E+8 1.98E+8 Co-60 - 3.78E+8 - - 2.10Et9 1.12E+9 NI-63 3.95E*10 2.11E+9 - - 1.42E+B 1.34E+9 Ni-65 1.05E+2 9.89E+O - - 1.21E+3 5.77E+O Cu-64 - 1.11E+4 - 2.68E+4 - 5.20E45 6.69E+3 Zn-65 B.12E+8 2.16E+9 - 1.36E+9' - 3.BOE+8 1.35E+9 Zn-69 1.51E-5 2.18E-5 - 1.32E-5 - 1.38E-3 2.02E-6 Br-82 - 2.04E+6 Br-83 - - 5.55E+0 Dr-84 -

Br-85 -

Rb-86 - 4.52E+8 2.91E+7 2.78E+8 Rb-88 Rb-89 Sr-89 3.59E*10 - 1.39E+9 1.03E+9 Sr-90 1.24E+12 - 1.67E+10 3.15E411 Sr-91 5.50E+5 - 1.21E+6 2.08E+4 Sr-92 7.2BE+2 - 1.38E+4 2.92E+1 Y-90 2.30E+4 - 6.56E+7 6.17E+Z2 Y-91m 9.94E-9 - 1.95E-5 Y-91 1.87E+7 - 2.49E+9 5.01E+5 Y-92 1.56E+O - 4.S1E+4 4.46E-2 Y-93 3,01Et2 - 4.48E+6 8.25E+O Zr-95 3.90E+6 8.58E+5 - 1.23E+6 - 8.95E+8 7.64E+5 Zr-97 S.64E+2 8.ISE+1 - 1.17E+2 - 1.23E'7 4.81E+1 Nb-95 4.10E+5 1.59E-5 - 1.50E+5 - 2.95E+8 1.14E+5 Nb-97 4.90E-6 8.85E-7 - 9.82E-7 - 2.73E-1 4.13E-7 Mo-99 - 7.83E+6 - 1.67E+7 - 6.48E+6 1.94E+6 Tc-99% 4.65E+0 9.12E+O - 1.33E+2 4.63E+0 5.19E+3 1.51E+2 Tc-i01 Ru-103 1.55E+7 - 3.89E*7 - 3.99E+8 5.94E+6 Ru-105 9.17El1 - 8.06E42 - 5.98E+4 3.33E+1 Ru-106 7.45E+8 - 1.01E+9 - 1.16E+40 9.30E+7 Rh-103m - -

Rh-106 - -

A-h110m 3.22E+7 2.17E+7 4.05Ei7 2.58E+9 1.74E+7 Sb-124 3.52E+8 4.57E+6 7.78E-5 - 1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 3.85E-6 4.62E-5 - 2.78E+8 1.19E+9 1.05E+8 Te-125m 3.51E+8 9.50E+7 9.84E+7 - - 3.38E+8 4.67E*7 Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 - 1.07E+9 1.57E+8 Te-127 1.00E-4 2.70E+3 6.93E+3 2.85E+4 - 3,91E+5 2.15E+3 Te-129n 8.54E+8 2.39E,8 2.75E+8 2.51E+9 - 1.04E+9 1.33E+8 Te-129 i. M5E-3 3.22E-4 8.22E-4 3.37E-3 - 7.17E-2 2.74E-4 7e-131m 1.54E.b 5.33E.5 1.10Et+ 5.16Et6 - 2.16E+7 5.681+5 Te-131 Te-132 6.98E+6 3.09E+b 4.50E+6 2.87E+7 - 3.11E.7 3.73E,6 1-130 6.21E+5 1.26E.6 1.38EB 1.88E+6 - 5.87E+5 6.47E+5 1-131 1.43E+8 1.44E+8 4.76E+10 2.36E+8 - 1.28E+7 8.18E+7 1-132 9.20E+1 1.69E+2 7.84E+3 2.59E+2 - 1.99E+2 7.77E+1 1-133 3.59E+6 4.44E+6 8.25E+8 7.40E+6 - 1.79E+6 1.68E+6 FERMI 2 ODCM - TRM VOLUME 11 7-46 Rev. 13

Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - CHILD (CONT.)

3 (mrem/yr per /jCiI/ ) for H-3 and C-14 2

(i x mrem/yr per yCi/sec) for others Nuclide sout Liver Thyroid Kidney Lung 1-LLXI T.Mody 1-134 1.70E-4 3.16E-4 7.2BE-3 4.84E-4 - 2.10E-4 1.46E-4 1-135 6.54E*4 1.18EtS 1.04E+7 1.81E+5 - 8.98E+4 5.57E+4 cA-134 1.60E+1O 2.63E+10 - 8.14E*9 2.92E+9 1.42E+8 5.54E+9 CU-136 8.06E+7 2.22E+8 - 1.1BE+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+10 2.29E+10 - 7.46E+9 2.68E+9 1.43E+8 3.38E+9 CS-138 Ro-139 5.11E-2 2.73E-5 - 2.38E-5 1.61E-5 2.95E+0 1.48E-3 BA-140 2.77E+8 2.43E+5 - 7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ba-141 Ba-142 LA-140 3.23E+3 1.13E+3 - - 3.15E+7 *3.81Et2 La-142 2.32E-4 7.40E-5 - - 1.47E+i 2.32E-5 Cc-141 1.23E+S 6.14E4 - 2.69E+4 - 7.66E+7 9.12E+3 Ce-143 1.73E+3 9.36E+5 - 3.93E+2 1.37E+7 1.36E42 Cc-144 1.27E+8 3.98E+7 2.21E+7 - 1.04E+io 6.78E+6 Pr-143 1.48Et5 4.46E - 2.41E*4 - 1.60E+8 7.37E+3 Pr-144 Nd-147 7.16E+4 5.80E+4 3.18E+4 - 9.18E+7 4.49E+3 W-187 6.47Ei4 3.83E+4 - - 5.38E+6 1.72E44 Hp-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

Table 7.0-4 Rai po, Ground Plane Pathway Dose Factors 2

(in x mrem/yr per /i.Ci/sec)

Nuclide Any Organ H-3 C- 14 Na-24 1.21E*7 P-32 Cr-51 4.68E+6 Hn-54 1.34E+9 Mn-56 9.05EiS F, F~e-59 2.75E+B Co-58 3.82E+8 Co-60 2.16E+10 Ni Ni-65 2.97E+5 Cu-64 6.09E+5 6

Zn- 5 7.45E+B Zn-69 Br-83 4 89E+3 Br- 84 2:03E+5 Br Rb-86 8.98E+6 Rb-68 3.29E+4 Rb-89 1.21E+5 Sr-89 2.16E+4 sr-90 Sr-91 2.19E+6 Sr-92 7.77E+5 (Y-91a Y-90 Y-91 4.48E+3 I.O0IE+5 1.08E+6 Y-92 1.B0E+S Y-93 I.Mt5E Zr-95 2.48E+8 Zr-97 2,94E+6 Nb-95 1.36E+8 MO-99 4.05E+6 Tc-99m 1.83E+S Tc-101 2.04E+4 Ru-103 1.09E+8 Ru-105 6.36E+S Ru-106 4.21E+B Hh- 103%

Rh-106 AS-110m 3.47E.'9 Te-125m i.55E+6 Te-127m 9.17Et4 Te-127 3.OOE+3 Te-129m 2.OOE+7 Te-129 2.60E.4 Te-131m 8.03E.-6 Te-131 2.93E.-4 T'e-132 4.22E+6 1-130 5.53E+6 1-131 1.72E+7 1-132 i.24E+6 1-133 2.47E+6 1-134 4,49E+5 1-135 2.56E+6 Cs-134 6.75E+9 Cs-136 1.49E+B Cs-137 1.04E+10 FERMI 2 ODCM -TRM VOLUME 11 7-48 Rev. 13

Table 7.0-4 R aipo, Ground Plane Pathway Dose Factors (CONT.)

2 (in x mrem/yr per [yCi/sec)

Audidda Any Organ Cs-138 3.59E+5 Ba-139 1.06E+S Ba-140 2.OSE*7 Ba-141 4. 18E+4 Ba-142 4.49E*4 La-140 1.91E+7 La-142 7.36E+5 Cc-141 1.36E47 Ce-14.3 2.32E+6 Ce-144 6.95E+7 Pr-143-Pr-144 1.83E+3 Nd-147 8.40E-6 W.-187 2.36E+6 Np-239 1.71E+6 FERMI 2 ODCM -TRM VOLUME 1I 7-49 Rev..13

FIGURE 7.0-1 GASEOUS RADIOACTIVE EFFLUENT MONITORING AND VENTILATION SYSTEMS DIAGRAM Key

- - $'Stack HEPA

- F"Ier R_drt Fiter SGTS Iv I Turblne RM do vt SWlS DIv I3 CorrtaiKrorth Maorrtbors SReactor B* ing CH. VACUUM F G Rx ldg xh Pl5nutm NOTE: The HEPA and charcoal filters identified on the Standby Gas Treatment System (SGTS) are engineered safety features and are not considered Ventilation evaluation for ExhaustinTreatment filters installed Systems (VETS). No effluent plant ventilation reduction was credited systems. Fermi 2 conforms to 10CFR50 in the Appendix UFSAR filtration 10CFR50 installed.

Appendix I I without FERMI 2 ODCM - TRM VOLUME II 7-50 END OF SECTION7.0 Rev. 13 FERMII 2 ODCM - TRM VOLUME 11 7-50 END OF SECTION 7.0 Rev. 13

SECTION 8.0 SPECIAL DOSE ANALYSIS FERMI 2 ODCM - TRM VOLUME 11 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 = 3.17 E -08* X/Q * (K *Q)

(8-1) and D s = 3.17E-08* X/Q *C [(L. +1.1M)

• 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 )

Qi = 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

Ki = 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 pCi/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 SDF = 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:

C = (Ci

• t) /365 (8-4)

FERMI 2 ODCM - TRM VOLUME II 8-5 Rev. 13

where:

Ci = 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 II 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 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

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-13 Fruits, Vegetables Teen 630 kg/y E-12 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 <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> 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 II 8-9 Rev. 13

SECTION 9.0 ASSESSMENT OF LAND USE CENSUS FERMI 2 ODCM - TRM VOLUME 11 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 effluent releases for a recent period of reactor operation, using the pathway for Table dose equations of the ODCM. In identifying the critical receptor 7.0-3, all age groups and all pathways relevant to ODCM 3.11.2.3 that may receptor be present at each evaluated location are considered. The critical the age group with the highest calculated is assumed to be a member of dose to the maximally exposed organ due to 1-131,1-133, tritium, and may have particulates with half lives greater than 8 days. Other receptors organs.

higher doses to other organs than the critical receptor has to those

4. Formulate a listing of locations of high dose significance in descending in order of relative dose significance. Include the relative dose significance the listing.

9.1.3 Program Updates current

1. If any receptor is identified with a higher relative dose than the critical receptor in ODCM Table 7.0-3, this receptor and its associated critical location and pathways should replace the previously identified receptor information in Table 7.0-3.

and

2. The Land Use Census data should be used to revise the REMP 3.12.2, Action Item b.

Section 10.0 of the ODCM in accordance with ODCM

3. Any changes in either the controlling location/pathway(s) (critical receptor) the REMP for the ODCM dose calculations (Section 7.7 and Table 7.0-3) or to NRC in (ODCM Section 10.0 and Table 10-1) shall be reported 5.9.1.8.

accordance with ODCM 3.12.2, Action Items a. and b. and ODCM NOTE: As permitted by footnote to ODCM 3.12.2, broadleaf vegetation in sampling may be performed at the SITE BOUNDARY in two locations, the garden census.

different sectors with highest predicted D/Qs, in lieu of ODCM Also, for conservatism in dose assessment for compliance with 3.11.2.3 (see also ODCM Section 7.7 and Table 7.0-3), hypothetical may be exposure location/pathway(s) and conservative dispersion factors assumed (e.g., milk cow at 5 mile location or garden at SITE BOUNDARY to in highest D/Q sector). By this approach, the ODCM is not subject year to year. A frequent revision as pathways and locations change from valid is verification that the hypothetical pathway remains conservative and still required. Also, for NRC reporting, the actual pathways and doses the actual should be reported along with the hypothetical. The reporting of of the more realistic pathway and doses provides a formal documentation dose impact.

16.

Note: Page content was last changed with ODCM Revision 9-3 Rev. 18 FERMI 2 ODCM - TRM VOLUME II

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 11 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 Meteorological Distance from Number Sector/Azimuth Reactor (Approx.) Description Media Frequency Direction T1 NE/38 0 1.3 mi Estral Beach Pole on Lakeshore, 23 Poles S of Lakeview Direct Radiation Q (Special Area)

T2 NNE/22 0 1.2 mi Pole at termination of Brancheau St. Direct Radiation Q (Special Area)

N/9 0 1.1 mi Pole, NW Corner of Swan Boat Club Fence Direct Radiation Q T3 (Special Area)

T4 NNW/337 0 0.6 mi Site Boundary and Toll Rd, on Site Fence by API #2 Direct Radiation Q T5 NW/3130 0.6 mi Site Boundary and Toll Rd, on Site Fence by API #3 Direct Radiation Q T6 WNW/294 0 0.6 mi Site boundary fence at south end of N. Bullit Rd. Direct Radiation Q W/270 0 14.0 mi Pole, at Michigan Gas substation on N. Custer Rd., 0.66 miles W of Direct Radiation Q T7 Doty Rd. (Control)

T8 NW/305 0 1.9 mi Pole on Post Rd. near NE Corner of Dixie Hwy. and Post Rd. Direct Radiation Q T9 NNW/334 0 1.5 mi Pole, NW Comer of Trombley and Swan View Road Direct Radiation Q T10 N/60 2.1 mi Pole, S Side of Masserant - 2 Poles W of Chinavare Direct Radiation Q T11 NNE/23 0 6.2 mi Pole, NE Corner of Milliman and Jefferson Direct Radiation Q NNE/290 6.3 mi Pointe Mouillee Game Area - Field Office, Pole near Tree, N Area of Direct Radiation Q T12 Parking Lot T13 N/356 0 4.1 mi Labo and Dixie Hwy - Pole on SW Comer with Light Direct Radiation Q T14 NNW/337 0 4.4 mi Labo and Brandon - Pole on SE Corner near RR Direct Radiation Q FERMI 2 ODCM - TRM VOLUME II 10-5 Rev. 19

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 T15 NW/3150 3.9 mi Pole, behind building at the comer of Swan Creek and Mill St. Direct Radiation Q T16i WNW/283 0 4.9 mi Pole, SE corner of War and Post Rds. Direct Radiation Q T17 W/2710 4.9 mi Pole, NE Corner of Nadeau and LaPrad near Mobile Home Park Direct Radiation .Q T18 WSW/247 0 4.8 mi Pole, NE Comer of Mentel and Hurd Direct Radiation Q SW/236 0 5.2 mi Fermi siren pole on Waterworks Rd, NE corner of intersection- Direct Radiation Q T19 Sterling State Park Rd Entrance Drive/Waterworks T20 WSW1257 0 2.7 mi Pole, S Side of Williams Rd. - 9 Poles W of Dixie Hwy. (Special Area) Direct Radiation Q T21 WSW/239 0 2.7 mi Pole, N Side of Pearl at Parkview - Woodland Beach (Special Area) Direct Radiation Q T22 S/1720 1.2 mi Pole, N Side of Pointe Aux Peaux 2 Poles W of Long - Site Boundary Direct Radiation Q SSW/1950 1.1 mi Pole, S Side of Pointe Aux Peaux - 1 Pole W of Huron next to Vent Direct Radiation Q T23 Pipe - Site Boundary SW/225 0 1.2 mi Fermi Gate along Pointe Aux Peaux Rd.- on fence wire W of Gate - Direct Radiation Q T24 Site Boundary T25 WSW/252 0 1.5 mi Pole, Toll Rd. - 12 Poles S of Fermi Dr. Direct Radiation Q T26 WSW/259 0 1.1 mi Pole, Toll Rd. - 6 Poles S of Fermi Dr. Direct Radiation Q T27 SW/225 0 6.8 mi Pole, NE Comer of McMillan and East Front St. (Special Area) Direct Radiation Q T28 SW/229 0 10.7 mi - Pole, N Side of Mortar Creek between Hull and LaPlaisance Direct Radiation Q T29 WSW/237 0 10.3 mi Pole, NE Comer of S Dixie and Albain Direct Radiation Q FERMI 2 ODCM - TRM VOLUME II 10-6 Rev. 19

TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Direct Radiation T30 WSW/247 0 7.8 mi E Side S end of footbridge, St. Mary's Park corner of Elm and Monroe Direct Radiation Q St. (Special Area)

T31 WSW/255 0 9.6 mi Ist Pole W of Entrance Drive Milton "Pat" Munson Recreational Direct Radiation Q Reserve - N. Custer Rd. (Control)

T32 WNW/295 0 10.3 mi Pole, Corner of Stony Creek and Finzel Rds. -Direct Radiation Q T33 NW/3170 9.2 mi Pole, W Side of Grafton Rd. 1 Pole N of Ash/Grafton Intersection Direct Radiation Q T34 NNW/338 0 9.8 mi Pole, SW Corner of Port Creek and Will-Carleton Rd Direct Radiation Q T35 N/359 0 6.9 mi Pole, S Side of S. Huron River Dr. across from Race St. (Special Direct Radiation Q Area)

T36 N/358 0 9.1 mi Pole, NE Corner of Gibraltar and Cahill Rds. Direct Radiation Q T37 NNE/21 0 9.8 mi Pole, S Corner of Adams and Gibraltar (across from Humbug Marina) Direct Radiation Q T38 WNW/294 0 1.7 mi Residence - 6594 N. Dixie Hwy.. Direct Radiation Q T39 S/1760 0.3 mi SE Comer of Protected Area Fence (PAF) Direct Radiation Q T40 S/1700 0.3 mi Midway along OBA - PAF Direct Radiation Q T41 SSE/161 0 0.2 mi Midway between OBA and Shield Wall - PAF Direct Radiation Q T42 SSE/1490 .0.2 mi Midway along Shield Wall - PAF Direct Radiation Q T43 SE/131 0 0.1 mi Midway between Shield Wall and. Aux Boilers - PAF Direct Radiation Q T44 ESE/109 0 0.1 mi Opposite OSSF Door- PAF Direct Radiation Q FERMI 2 ODCM - TRM VOLUME II 10-7 Rev. 19

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 Comer - PAF T46 ENE/67 0 0.2 mi NE Side Barge Slip - on Fence Direct Radiation Q T47 S/1850 0.1 mi South of Turbine Bldg. rollup door on PAF Direct Radiation ,Q T48 SW/235 0 0.2 mi .30 ft. from corner of AAP on PAF T49 WSW/251 0 1.1 mi Corner of site boundary fence north of NOC along Critical Path Rd. Direct Radiation Q T50 W/270 0 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 Q T52 NNE/20 0 0.4 mi Site boundary fence at the corner of Arson and Tower Direct Radiation Q T53 NE/55 0 0.2 mi Site boundary fence east of South Cooling Tower Direct Radiation Q T54 S/1890 0.3 mi Pole, next to Fermi 2 Visitors Center Direct Radiation Q T55 WSW/251 0 3.3 mi Pole, N side of Nadeau Rd, across from Sodt Elementary School Direct Radiation Q Marquee T56 WSW/255 0 4.9 mi Pole, entrance to Jefferson Middle School on Stony Creek Rd. Direct Radiation Q T57 W/260 0 2.7 mi Pole, north side of Williams Rd. across from Jefferson High School Direct Radiation Q entrance T58 WSW/249 0 4.9 mi Pole, west of Hurd Elementary School Marquee Direct Radiation Q T59 NW/325 0 2.6 mi Pole, north of St. Charles Church entrance on Dixie Hwy. Direct Radiation Q T60 NNW/341 0 2.5 mi 1st pole north of North Elementary School entrance on Dixie Hwy. Direct Radiation Q FERMI 2 ODCM - TRM VOLUME II 10-8 Rev. 19

TABLE 10.0-1 Radiological gnvironmental Monitoring Program, Fermi 2 Sample Locatlons and Associated Media Direct Radiation StaiT~ Mete.Slo"lo'g,16 ~ in 4e's -r i T61 W/268 0 10.1 m ~ Pole, SW Comner of Stewart and R-aisinville Rds. Direct RadiatUon SW/232 0 9.7 mi Pole, NW Corner of Albain and Hull Rds. Direct Radiation Q T62 WSW/245 0 9.6 M1 Pole, Corner of Dunbar and Telegraph Rds. Direct Radiatlon Q T63 WNW/28e 0 0.2 mi W of switchgear nard on PAF Direct Radiation Q T64 NW/322 0 0.i mi PAF syAtchciear yard area NW of RHR complex Direct Radiation Q T65 NE150 0 0.1 Mi Behind Bldg. 42 on PAF Direct Radiation Q T66 T67 NNW/33B9 02 mi Site boundar fence W of S cooling tower Direct Radiation0 WNW/303 a 0.6 mi Langton Rd seven poles E of Leroux Rd Direct Radiation Q T68 NW1306 0 0.8 mi Langton Rd f'ive poles E of Leroux Rd Direct Radiation. Q T69 NNW/333'0 1.1 ml Leroux Rd last ole N of Fermi Dr Direct Radiation Q 170 WNW1300') 1.1 Ml Leroux Rd six poles N of Fermi Dr Direct Radiation Q T71 WNW/302-3 0 0.175 m! Center of west 1SFS1 fence line Direct Radiation Q ISFS I-1 NW131. 0Y 0.186 m! Northwest corner of ISFSI fence Direct Radiation Q ISFSi-2 ISFSI-3 NW1313.20 0.166 mi Center of north ISFSI fence line Direct Radiation Q ~ j NW/315.6P 0.149 ml Northeast corner of ISFS I fence Direct Radiation Q ISFSI-4 NW1305.e 0 0.140 mi Center of east ISFSI fence line Direct Radiation Q ISFS1-5 WNW/294.1" 0.136 Mi Southeast corner of 1SFSI fence Direct Radiation Q ISrFSI-6 ISFSI-7 WNW1293.0 0 0.157 mi Center of south ISFS I fence line Direct Radiation0 WNW/293.CP 0.177 mi Southwest corner of ISFS I fence Direct Radiation Q ISFSJ-8 FERMI 2 ODCM - TRM VOLUME 11 10-9 Rev. 20

TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Fish and Sediment Station Meteorological Distance from Number Sector/Azimuth Reactor (Approx.) Description Media Frequency Direction______________________________________

SEDIMENTS S-1 SSE/1 650 0.9 mi Pointe Aux Peaux, Shoreline to 500 ft. offshore sighting directly to Sediment SA

__________________________Land Base Water Tower S-2 E/81 0 0.2 mi Fermi 2 Discharge, approx. 200 ft. offshore Sediment SA S-3 NE/39 0 1.1 mi Estral Beach, approx. 200 ft. offshore, off North shoreline where Sediment SA Swan Creek and Lake Erie meet S-4 WSW/2410 3.0 mi _ Indian Trails Community Beach Sediment S S-5 NNE/20 0 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/86 0 0.4 mi Fermi 2 Discharge (Approx. 1200 ft. offshore) Fish SA F-3 SW/227 0 3,5 mi Breast Bay Area (Control) Fish SA FERMI 200DCM - TRM VOLUME 11 10-10 Rev. 13

TABLt 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/2890 9.9 mi Calder Dairy - 9334 Finzel Rd. Milk _M

_____ -M FERMI 2 ODCM -TRM VOLUME 11 10-1i Rev. 13

TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Water Station Meteorological Distance from Number Sector/Azimuth Reactor (Approx.) Description Media Frequency Direction_________________________

DRINKING WATER DW-1 S11740 1.1 mi Monroe Water Station N Side of Pointe Aux Peaux 1/2 Block W of Drinking Water M

__________________________ _______ Long_Rd. _____ ___________

DW-2 N/80 18.5 mi Detroit Water Station, 14700 Moran Rd. Allen Park (Control) Drinking WaterM SURFACE WATER SW-2 NNE/20 0 11.7 mi DECo's Trenton Channel Power Plant Intake Structure (Screenhouse Surface Water M

________________________ ____________#1) (Control)________

SW-3 SSE/1 600 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 ft. W of Lake Erie, EF-1 Parking lot Groundwater near Groundwater Q gas_fired_peakers ___ ___________ _______

GW-2 SSW12080 1.0 mi 4 ft. S of Pointe Aux Peaux (PAP) Rd. Fence 427 ft. W of where PAP Groundwater Q crosses over Stony Point's Western Dike GW-3 SW12260 1.0 mi 143 ft. W of PAP Rd. Gate, 62 ft. N of PAP Rd. Fence Groundwater Q GW-4 WNW12990 0.6 mi 42 ft. S of Langton Rd., 8 ft. E of Toll Rd. Fence Groundwater 0 FERMI 200DCM - TRM VOLUME 11 10-12 Rev. 13

TABLE 10.0-1 Media Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Air Particulate Air Iodine Station Meteorological Distance fto07ia Estral Beach Pole on Lakeshore, 18 Poles S of Lakeview (Nearest Radioiodine W API-1 NE/39 0 1.4 mi

_ Community with highest X/Q) Particulates W Site Boundary and Toll Road, on Site Fence by T-4 Radioiodine W API-2 NNW/337 0 0.6 mi Particulates W 0 Site Boundary and Toll Road, on Site Fence by T-5 Radioiodine W API-3 i NW/313 0.6 mi

" Particulates W Pole, at Michigan Gas substation on N. Custer-Rdl, 0.66 miles W of Radioiodine W API-4 W/270 0 14.0 mi

__Doty Rd. (control) Particulates W Pole, N corner of Pointe Aux Peaux and Dewey Rd. Radioiodine W API-5 S/1880 1.2 mi

- Particulates W Note: Fage content was last changed with ODCM Revision 16.

10-13 Rev. 18 FERMI 2 ODCM - TRM VOLUME II

TABLE 10.0-1 Radiological Environmental Monitoring Program, Fermi 2 Sample Locations and Associated Media Food Products FP-1 INNE/21 0 3.8 mi 9501 Turnpike Highway Food Products M (when available)

FP-9 W/2610 10.9 mi 4074 North Custer Road Food Products M (when j available)

Note: Fage content was last changed with ODCM Revision 16.

FERMf 2 ODCM - TRM VOLUME II 10-14 Rev. 18

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 1.0 mi N 1.1 mi NNW 1.1 mi NW 1.1 mi WNW 0.7 mi W 1.2 mi WSW 1.6 mi SW 1.3 mi SSW 1.1 mi S 1.0 mi ESE-SSE Lake Erie END OF SECTION 10.0 Note: Page content was last changed with ODCM Revision 16.

FERMI 2 ODCM - TRM VOLUME II 10-15 Rev. 18

FERMI 2 NUCLEAR POWER PLANT DETROIT EDISON COMPANY OPERATING LICENSE NO. NPF - 43 Fermi 2 - 2010 Annual Radiological Environmental Operating Report for the period of January 1, 2010 through December 31, 2010 Prepared by:

Fermi 2 Radiological Engineering

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Table of Contents Page Executive Summary 1 Radiological Environmental Monitoring Program Results 3 Direct Radiation Monitoring 3 Thermoluminescent Dosimeters 3 Atmospheric Monitoring 4 Air Sampling 5 TerrestrialMonitoring 7 Milk Sampling 7 GroundwaterSampling 8 Garden Sampling 9 Aquatic Monitoring 10 Drinking Water Sampling 10 Surface Water Sampling 12 Sediment Sampling 13 FishSampling 15 Land Use Census 17 2010 Land Use Census Results 18 Appendix A Sampling Locations A-1 Appendix B EnvironmentalData Summary B-1 Appendix C Environmental Data Tables C-i Appendix D EnvironmentalProgramExceptions D-1 DirectRadiationMonitoring D-1 Atmospheric Monitoring D-1 TerrestrialMonitoring D-I Milk Sampling D-I Garden Sampling D-2 GroundwaterSampling D-2 Aquatic Monitoring D-2 Drinking Water Sampling D-2 Surface Water Sampling D-2 Sediment Sampling D-2 Fish Sampling D-2 11ii

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Appendix E InterlaboratoryComparisonData,GEL Laboratories' Quality Assurance Programs 2010 Annual Quality Assurance Report E-1 iii

Fermi 2 - 2010 Annual Radiological Environmental Operating Report List of Figures Page Figure1 Fermi 2 Annual Average TLD Gamma Exposure 4 Figure 2 HistoricalGross Beta andlodine-131 Activity in Air Samples 6 Figure 3 Fermi 2 Air ParticulateGross Betafor 2010 6 Figure4 HistoricalStrontium-90 Activity in Local Milk Samples 8 Figure 5 HistoricalGross Beta Activity in Drinking Water Samples 12 Figure 6 HistoricalCesium-137Activity in Sediment Samples 15 Map 1 Sampling Locations By Station Number (within 1 mile) App.-A Map 2 Sampling Locations By Station Number (1 to 5 miles) App.-A Map 3 Sampling Locations By Station Number (greaterthan 5 miles) App.-A List of Tables Page Table 1 2010 Average Gross Beta Concentrationsin Air Particulates 5 Table 2 ClosestResidences 19 Table 3 Closest Gardens 20 Table 4 Milk Locations 21 Table 5 ClosestMeat Locations 22 Table A-i DirectRadiationSample Locations A-i Table A-2 Air ParticulateandAir Iodine Sample Locations A-7 Table A-3 Milk Sample Locations A-7 Table A-4 GardenSample 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 RadiologicalEnvironmentalMonitoringProgramSummary B-1 iv

Fermi 2 -2010 Annual Radiological Environmental Operating Report Executive Summary This Annual Radiological Environmental Operating Report is a detailed report on the Radiological Environmental Monitoring Program (REMP) conducted at Detroit Edison's Fermi 2 nuclear power plant from January 1 through December 31, 2010.

Samples collected as part of the REMP program were analyzed by AREVA NP Inc.

Environmental Laboratory and GEL Laboratories, LLC. Radioactivity measurements for these samples are reported in terms of sample concentration. Standard units of measure for reporting radioactivity are the Curie (Ci) for the amount of activity, and the Roentgen (R) for the amount of radiation exposure in free air. The unit of radioactivity used in this report is the picocurie (pCi). A picocurie is one-one trillionth of a curie. The unit of direct radiation used in this report is milliroentgen (mR). A milliroentgen is one-one thousandth of a roentgen. All radioactivity measurements for samples found to contain radioactivity are reported with a 2 sigma counting error, a standard counting practice.

The Radiological Environmental Monitoring Program is divided into four major parts.

These four parts are direct radiation monitoring, atmospheric monitoring, terrestrial monitoring, and aquatic monitoring. The results of 2010 data showed that environmental radioactivity levels have not increased from background radioactivity levels detected prior to the operation of Fermi 2.

Direct radiation measurements were taken at 71 locations using thermoluminescent dosimeters (TLD). The average quarterly exposure was 14.2 mR/standard quarter for indicating locations. This average exposure is equivalent to the ambient radiation levels measured prior to the operation of Fermi 2.

Atmospheric monitoring results for 2010 showed only naturally occurring radioactivity and were consistent with levels measured prior to the operation of Fermi 2. No radioactivity attributable to activities at Fermi 2 was detected in any atmospheric samples during 2010.

Terrestrial monitoring results for 2010 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. No radioactivity attributable to activities at Fermi 2 was detected in any terrestrial samples during 2010.

1

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Aquatic monitoring results for 2010 of drinking water, surface 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. No radioactivity attributable to activities at Fermi 2 was detected in any aquatic samples during 2010.

REMP sampling did not identify any radioactivity attributable to the operation of Fermi 2.

2

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Results Direct Radiation Monitoring Radiation is a normal component of the environment resulting primarily from natural sources, such as cosmic radiation and naturally occurring radionuclides; and to a lesser extent, from manmade sources such as fallout from past nuclear weapons testing. The earth is constantly bombarded by cosmic radiation in the form of high energy gamma rays and particulates. The earth's crust also contains natural radioactive material, such as uranium and potassium-40, which contributes to the background radiation. Direct radiation monitoring primarily measures ionizing radiation from cosmic and terrestrial sources.

Thermoluminescent Dosimeters Fermi 2 uses thermoluminescent dosimeters (TLDs) to measure direct gamma radiation in the environs of Fermi 2.

Fermi 2 has 71 TLD locations within a fifteen mile radius of the plant. Of the 71 TLD locations, 16 are located on-site and are not used for comparison with the control locations. These 16 TLDs are affected by Hydrogen Water Chemistry's sky shine and are not representative of off-site dose. The TLDs are thoroughly tested to comply with NRC Regulatory Guide 4.13 and American National Standards Institute's (ANSI) publication N545-1975, which assure accurate measurements under varying environmental conditions before being placed in the field. Indicator TLDs are located within a ten mile radius of the plant and control TLDs are located at a distance that is outside the potential influence of the plant. While in the field, TLDs are exposed to background radiation and, if measurable, gaseous effluents and direct radiation from Fermi 2. Environmental TLDs are exchanged and processed on a quarterly basis. The TLDs' data are reported in terms of milliroentgen per standard quarter (mR/std qtr), with a standard quarter being 91 days.

3

Fermi 2 - 2010 Annual Radiological Environmental Operating Report In 2010, the average exposure for TLDs at all off-site indicator locations was 14.2 mR/std qtr and for all control locations was 13.7 mR/std qtr. These exposures are consistent with preoperational and past operational measurements as shown in Figure 1.

Fermi 2 Annual Average TLD Gamma Exposure 25 10 Preoperational Operational 5-

-o-Indicator -o-Control Figure 1 - Fermi 2 Annual Average TLD Gamma Exposure: The similarity between indicator and control results demonstrates that the operation of Fermi 2 has not caused any abnormal gamma exposure.

Atmospheric Monitoring A potential exposure pathway to people is inhalation of airborne radioactive materials.

Fermi 2 continuously samples the ambient air surrounding Fermi 2 for radioactivity. Air sampling began in 1979 during the preoperational program. At each sampling location, a mechanical air sampler is used to draw a continuous volume of air through two filters designed to collect particulates and radioiodines. Air samples are collected weekly and analyzed for gross beta radiation and iodine-131 gamma radiation. The particulate filters for each sampling location are combined on a quarterly basis to form a "composite sample" and are analyzed for gamma emitting radionuclides. There are four indicator sampling locations which were selected based on an evaluation of the predominant wind directions. A fifth sampling location is approximately fourteen miles west of the plant and is considered to be in a location unaffected by the operation of the plant. This is used as the control location.

4

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Air Sampling On October 16, 1980, the People's Republic of China conducted an atmospheric nuclear weapon test. The fallout from this test was detected in Fermi 2 preoperational environmental air samples in 1981 (see Figure 2). The average gross beta for 1981 was 1.60E-1 pCi/cubic meter for indicator samples and 2.40E-1 pCi/cubic meter for control samples which was a factor often times greater than background gross beta. Gamma spectroscopic analyses of the particulate filters indicated cesium- 137, cerium- 141, cerium-144, ruthenium-103, ruthenium-106, zirconium-95, niobium-95, manganese-54, and antimony-125 in the atmosphere as a result of this test. In 1986, as shown in Figure 2, there was a slight increase in gross beta activity and a 2.70E-1 pCi/cubic meter "spike" in the iodine-131 activity. These elevated levels in 1986 are attributed to the nuclear accident at Chernobyl on April 26, 1986. For all other years, the iodine-131 activity was below the lower limit of detection (LLD) of 7.0E-2 pCi/cubic meter.

During 2010, two hundred and fifty-three (253) 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 3.57E-2 pCi/cubic meter and 3.73E-2 pCi/cubic meter for control samples. None of the charcoal filters collected showed detectable levels of iodine-131. The following table contains the annual average gross beta results of all five sample locations for 2010.

2010 Average Gross Beta Concentrations in Air Particulates (pCi/m3)

Table 1 Station Description (sector/distance) Annual Average API-1 (I) Estral Beach (NE/1.4 mi.) 3.39E-2 API-2 (I) Site Boundary (NNW/0.6 mi.) 3.44E-2 API-3 (I) Site Boundary (NW/0.6 mi.) 3.20E-2 API-4 (C) North Custer Rd. (W/14 mi.) 3.73E-2 API-5 (I) Site Boundary (S/1.2 mi.) 4.22E-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.

5

Fermi 2 - 2010 Annual Radiological Environmental Operating Report In conclusion, the atmospheric monitoring data are consistent with preoperational and prior operational data and show no adverse long-term trends in the environment attributable to operation of Fermi 2 as illustrated in Figures 2 and 3.

Historical Gross Beta and Iodine - 131 Activty in Air Samples 3.E-01 Chinese Weapon Test 3.E-01 Chernobyl Event 2.E-01

.9 2.E-01 S 1.E-01 \ 1-131 L 5.E-02 O.E+0 -

Cm o i-) i c)

(7i C) Lo ) - Cm Lo r-- i )

--- Indicator Gross Beta -O- Control Gross Beta - Iodine - 131 Figure 2 - Historical Gross Beta and Iodine-131 Activity in Air Samples; The similarity between indicator and control gross beta results demonstrates that the operation of Fermi 2 has had no adverse long-term trends in the environment. The lower limit of detection (LLD) for iodine-131 is 0.07 pCi/cubic meter.

Fermi 2 Air Particulate Gross Beta 2010 8.E 7.E 6.E02 S5.E02 4.E02 -

S3.E-02 2.E-02 1.E-02 O.E+O0 . . . . . . ..

Collection Date

-o-Indicator --- Control Figure 3 - Fermi 2 Air Particulate Gross Beta for 2010; 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.

6

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Terrestrial Monitoring Radionuclides released to the atmosphere may deposit on soil and vegetation, and therefore, may eventually be incorporated into the human food chain. To assess the impact of Fermi 2 operations to humans from the ingestion pathway, samples of milk, green leafy vegetables, and groundwater are collected and analyzed for radioactivity. The following sections discuss the type and frequency of terrestrial sampling, analyses performed, and a comparison of 2010 data to previous operational and preoperational data.

Milk Sampling 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 are collected at both the control milk sample location and the location where milk is not available. Grass samples are analyzed for iodine-131 and other gamma emitting radionuclides. During 2010, no grass samples were scheduled or collected for the REMP.

Milk sampling began in 1979 during the preoperational program. During this time period, milk samples were analyzed for iodine-131 and other gamma emitting radionuclides. Cesium-137 and naturally occurring potassium-40 were the only radionuclides detected in milk samples during the preoperational program. The cesium-137 concentration averaged 3.60E+0 pCi/liter and is due to past atmospheric nuclear weapons testing. In 1986, after the nuclear accident at Chernobyl, iodine-131 and cesium-137 were detected in both indicator and control milk samples. The average concentration was 3.70E+0 pCi/liter for iodine-131 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 2010, thirty four (34) milk samples were collected and analyzed for iodine-131, gamma emitting radionuclides, and strontium-89/90. No iodine-131 was detected in any of the samples. Strontium-90 was detected in two indicator milk samples and one control milk sample and is due to fallout from past atmospheric weapons testing (see Figure 4).

7

Fermi 2 - 2010 Annual Radiological Environmental Operating Report The indicator samples had an average strontium-90 concentration of 1.36E+0 pCi/liter and the control sample had concentration of 1.54E+0 pCi/liter. Naturally occurring potassium-40 was detected in both indicator and control samples.

In 1970, the concentration of strontium-90 in Monroe County milk was 6.00E+0 pCi/liter according to the Michigan Department of Health's "Milk Surveillance," Radiation Data and Reports, Vol. 11-15, 1970-1974. Figure 4 shows the calculated radiological decay curve for the 1970 concentration of strontium-90 and the average concentrations since 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 determination 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 4.0 2.0 - "C ci~-W Cto Average Sr-90 Activity -- Calculated Decay Figure 4 - Historical Strontium-90 Activity in Local Milk Samples; the concentration of strontium-90 in local milk samples is decreasing with time and is below the calculated decay curve. This supports the fact that strontium-90 in local milk is due to fallout from past atmospheric nuclear weapons testing and not the operation of Fermi 2.

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. With the construction of new water plants and distribution systems, the water use trend in the area is from groundwater (local wells) to surface water (municipal water supply).

8

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Groundwater is collected on a quarterly basis from four wells surrounding Fermi 2. The groundwater is analyzed for gamma emitting radionuclides and tritium. Sampling location GW-4, which is located approximately 0.6 miles west northwest, is designated as the control location because it is up-gradient and is least likely to be affected by the operation of the plant. The other three sampling locations are down-gradient from Fermi 2 and designated as indicator locations.

Groundwater sampling began in 1987, during the operational period of the REMP program. From 1987 to 1996, naturally occurring potassium-40, cesium-137, and tritium were detected in both indicator and control samples. The average concentration was 7.71E+0 pCi/liter for cesium-137 and 1.50E+2 pCi/liter for tritium. The presence of cesium-137 and tritium in groundwater samples is due to fallout from past atmospheric nuclear weapons testing leaching into the soil and becoming incorporated into the groundwater. From 1997 to 2008, only naturally occurring potassium-40 activity was detected in groundwater samples.

In 2010, sixteen (16) groundwater samples were collected and analyzed for gamma emitting radionuclides and tritium. During 2010, naturally occurring potassium-40 activity was detected in one indicator groundwater sample. No other samples detected any activity.

Garden Sampling Fermi 2 collects samples of broad leaf vegetables from indicator locations identified by the annual Land Use Census. Samples are also collected at a control location that is at a distance and direction which is considered to be unaffected by plant operations. Samples are collected once a month during the growing season (June through September) and are analyzed for iodine-131 and other gamma emitting radionuclides.

Vegetable sampling started in 1982. During the preoperational period from 1982 to 1985, only naturally occurring potassium-40 was detected in both indicator and control vegetable samples. During the operational period from 1985 to 1990 and 1994 to 1995, only naturally occurring potassium-40 was detected in both indicator and control vegetable samples. However, in 1991, 1992, and 1993, cesium-137 was detected in one indicator sample each year and had an average concentration of 1.2E+1 pCi/kilogram.

Cesium-137 may become incorporated into plants by either uptake from the soil or direct deposition on foliar surfaces. Since cesium-137 is normally not detected in gaseous effluent samples from Fermi 2, and there have been no recent atmospheric weapons testing or nuclear accidents, the incorporation of cesium-137 by direct deposition is highly unlikely. The most probable source of cesium-137 in vegetable samples is the uptake of previously deposited cesium-137, which has leached into the soil. This cesium 9

Fermi 2 - 2010 Annual Radiological Environmental Operating Report activity is attributed to fallout from past atmospheric weapons testing and to the nuclear accident at Chernobyl.

During 2010, eight (8) vegetable samples were collected and analyzed for iodine-131 and other gamma emitting radionuclides. No iodine-131 was detected in vegetable samples during 2010. The only gamma emitting radionuclide detected was naturally occurring potassium-40 in both indicator and control samples.

Terrestrial monitoring results for 2010 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 sample. In conclusion, the terrestrial monitoring data show no adverse long-term trends in the terrestrial environment.

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

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

The following sections discuss the type and frequency of aquatic sampling, analyses performed, and a comparison of 2010 data to previous operational and preoperational data.

Drinking Water Sampling Fermi 2 monitors drinking water at one control location and one indicator location using automatic samplers. The automatic samplers collect samples at time intervals that are very short (hourly) relative to the sample collection period (monthly) in order to assure that a representative sample is obtained. Indicator water samples are obtained at the Monroe water intake located approximately 1.1 miles south of the plant. Detroit municipal water is used for the control samples and is obtained at the Allen Park water intake located approximately 18.6 miles north of the plant. Drinking water samples are collected on a monthly basis and analyzed for gross beta, strontium-89/90, and gamma emitting radionuclides. The monthly samples for each location are combined on a quarterly basis and analyzed for tritium activity.

10

Fermi 2 - 2010 Annual Radiological Environmental Operating Report In late 1980, as shown in Figure 5, an atmospheric nuclear weapon test was conducted by the People's Republic of China. As a result of this test, the average gross beta for 1981 was 9.80E+0 pCi/liter for water samples. Figure 5 also shows that, except for the Chinese weapons testing, the historic drinking water sample data are below or slightly above the lower limit of detection (4.00E+0 pCi/liter) required by US Environmental Protection Agency (USEPA) National Interim Primary Drinking Water regulations. Even during the Chinese weapons testing, the drinking water samples did not exceed the USEPA maximum allowable criteria of 5.00E+1 pCi/liter gross beta. In 1980 and 1983, cesium-137 was detected in drinking water samples at levels ranging from 5.40E+0 pCi/liter to 1.90E+1 pCi/liter. Tritium was also detected during the preoperational program and had an average of 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 2009, the average annual gross beta activity for indicator samples was 4.09E+0 pCi/liter and 3.46E+0 pCi/liter for control samples. The analysis for strontium-89/90 began in 1988, and strontium-90 has in the past been detected in both indicator and control samples. The average strontium-90 activity for indicator samples was 7.25E-1 pCi/liter and 7.56E-1 pCi/liter for control samples during this time period. Tritium was also detected in both indicator and control drinking water samples during this time period.

The average tritium activity for indicator samples was 2.52E+2 pCi/liter and 2.60E+2 pCi/liter for control samples. The presence of strontium-90 and detectable levels of tritium in these water samples is due to fallout from past atmospheric nuclear weapons testing and naturally occurring tritium.

In 2010, 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 4.24E+0 and 3.49E+0 pCi/liter for control samples. No gamma emitting radionuclides or strontium-89/90 activity was detected in drinking water samples during 2010. Eight (8) quarterly composite drinking water samples were prepared and analyzed for tritium. No tritium activity was detected in drinking water samples during 2010.

11

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Historical Gross Beta Activity 12.0 - in Drinking Water Samples 10.0 Chinese Weapons Test 8.0 -

2.0 -

0 .0 I I I I I I I I I I I I I I I I I I I I I I I I lF~

MD 00 0)

C3 0o 0 D 00 00 0

CO -

M-03 C

MD C0 M

3 C.0 M

80 C 0

CD 0 c, CD 0 c:,

---

Indicator Gross Beta -o--- Control Gross Beta ..... EPA LLD Figure 5 - Historical Gross Beta Activity in Drinking Water Samples. Since 1982, the annual concentrations of beta emitting radionuclides in drinking water samples collected from indicator locations have been consistent with those from control locations.

This shows that Fermi 2 has had no measurable radiological impact on local drinking water.

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

12

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Surface water sampling began in 1979, and the samples were analyzed for gamma emitting radionuclides and tritium. During this preoperational program, no gamma emitting radionuclides, except for naturally occurring potassium-40, were detected.

Tritium was detected in both indicator and control samples during this time period and had an average concentration of 3.15E+2 pCi/liter. This tritium activity represents the background concentration due to naturally occurring tritium and tritium produced during past atmospheric nuclear weapons testing.

From 1985 to 2009, as part of the operational program, surface water samples were analyzed for gamma emitting radionuclides and tritium. The analysis for strontium-89/90 did not begin until 1988, and strontium-90 was detected in both indicator and control samples. The average strontium-90 concentration for this time period was 1.13E+0 pCi/liter. In 1990, two indicator samples showed detectable activity for cesium-137 at an average concentration of 1.20E+1 pCi/liter. The presence of cesium-137 and strontium-90 in these water samples is due to fallout from past atmospheric nuclear weapons testing. Tritium was detected in both indicator and control surface water samples during this time period at a concentration of 2.31E+2 pCi/liter. This tritium activity is consistent with background levels measured during the preoperational program.

In 2010, twenty-four (24) surface water samples were collected and analyzed for gamma emitting radionuclides and strontium-89/90. From these samples, eight (8) quarterly composite samples were prepared and analyzed for tritium. During 2010, no gamma emitting radionuclides, strontium-89/90 or tritium was detected in surface water samples.

Sediment Sampling Sediments often act as a sink (temporary or permanent) for radionuclides, but they may also become a source, as when they are resuspended during periods of increased turbulence or are dredged and deposited elsewhere. Sediment, in the vicinity of the liquid discharge point, represents the most likely site for accumulation of radionuclides in the aquatic environment, and with long-lived radionuclides, a gradual increase in radioactivity concentration would be expected over time if discharges occur. Sediment, therefore, provides a long-term indication of change that may appear in other sample media (i.e., water and fish samples).

13

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Lake Erie shoreline and bottom sediments from five locations are collected on a semiannual basis (Spring and Fall) and are analyzed for gamma emitting radionuclides and strontium-89/90. There is one control location and four indicator locations. The control sample is collected near the Trenton Channel Power Plant's cooling water intake.

The indicator samples are collected at Estral Beach, north of 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 2009, cesium-137, strontium-90, and naturally occurring radionuclides were detected in sediment samples. The average cesium-137 concentration was 1.22E+2 pCi/kilogram for all samples. The analysis for strontium-89/90 began in 1988, and strontium-90 has been routinely detected at similar concentrations in both indicator and control samples. The average strontium-90 activity for indicator samples was 1.80E+2 pCi/kilogram and 1.98E+2 pCi/kilogram for control samples. The presence 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 as per the approved effluent program. The dose impact was negligible due to these effluents.

In 2010, ten (10) sediment samples were collected and analyzed for gamma emitting radionuclides and strontium 89/90. Cesium-137 was detected in one control sample with a concentration of 8.29E+1 pCi/kilogram. The presence of cesium-137 in sediment samples is due to fallout from past atmospheric nuclear weapons testing. Naturally occurring radionuclide potassium-40 was also detected in sediment samples for this sampling period.

14

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Historical Cesium-137 Activity in Sediment Samples 7.E02 -

6.E02 -

E 5.E 2 -

L 4.E02 -

E 3.E02 -

S2.E102 1.E02 I O.E+-OO 00 CO C4 Co CO 00 C) CN to Co to M

0) 0 0OM 03 0M 0)3 CD CD 0 0 0 Figure 6 - Historical Cesium-137 Activity in Sediment Samples. As the calculated trend shows, the concentration of cesium-137 in Lake Erie sediments is decreasing with time. This supports the fact that cesium-137 in Lake Erie sediments is due to fallout from past atmospheric nuclear weapons testing and not the operation of Fermi 2.

Figure 6 shows the historical concentration of cesium-137 in sediment samples from 1978 to 2010. Using the data from these years, and the statistical method of least squares, an exponential curve can be calculated that represents the cesium-137 concentration in sediment. This curve has a negative slope which indicates the overall concentration of cesium-137 in the environment is decreasing with time. This supports the fact that the inventory of cesium-137 in the environment is due to fallout from past atmospheric nuclear weapons testing and not from the operation of Fermi 2.

Fish Sampling Samples of fish are collected from Lake Erie at three locations on a semiannual basis.

There are two control locations and one indicator location. The two control locations are offshore of Celeron Island and in Brest Bay. The indicator location is approximately 1200 feet offshore of the Fermi 2 liquid effluent discharge. Edible portions of the fish are analyzed for gamma emitting radionuclides and strontium-89/90.

During the preoperational program, fish samples were analyzed for gamma emitting radionuclides. Only cesium-137 and naturally occurring potassium-40 were detected during this time period. The average concentration of cesium-137 for indicator samples was 3.53E+1 pCi/kilogram and 4.20E+1 pCi/kilogram for control samples. The presence of cesium-137 in these fish samples is due to fallout from past atmospheric nuclear weapons testing.

15

Fermi 2 - 2010 Annual Radiological Environmental Operating Report From 1985 to 2009, cesium-137 and naturally occurring potassium-40 were detected in fish samples. The average cesium-137 concentration for indicator samples was 3.82E+1 pCi/kilogram and 3.92E+1 pCi/kilogram for control samples. The analysis for strontium-89/90 began in 1990, and strontium-90 was routinely detected at similar concentrations in both indicator and control samples. The average strontium-90 concentration for indicator samples was 3.84E+1 pCi/kilogram and 3.15E+1 pCi/kilogram for control samples. The presence of cesium-137 and strontium-90 in these fish samples is due to fallout from past atmospheric nuclear weapons testing.

In 2010, twenty-five (25) fish samples were collected and analyzed for gamma emitting radionuclides and strontium-89/90. Only naturally occurring potassium-40 was detected in both control and indicator fish samples for 2010.

Aquatic monitoring results for 2010 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 sample during 2010 and no adverse long-term trends are shown in the aquatic monitoring data.

16

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Land Use Census The Land Use Census is conducted in accordance with the Fermi 2 Offsite Dose Calculation Manual (ODCM), control 3.12.2, and satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. This census identifies changes in the use of unrestricted areas to permit modifications to monitoring programs for evaluating doses to individuals from principal pathways of exposure. The pathways of concern are listed below:

• Inhalation Pathway - Internal exposure as a result of breathing radionuclides carried in the air.

• Ground Exposure Pathway - External exposure from radionuclides deposited on the ground.

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

• Vegetation Pathway - Internal exposure as a result of eating vegetables which have absorbed deposited radioactive material or which have absorbed radionuclides through the soil.

• Milk Pathway - Internal exposure as a result of drinking milk which may contain radioactive material as a result of dairy animals grazing on a pasture contaminated by radionuclides.

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

17

Fermi 2 - 2010 Annual Radiological Environmental Operating Report 2010 Land Use Census Results The Land Use Census is conducted in accordance with ODCM control 3.12.2 and satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. This census identifies changes in the use of unrestricted areas to permit modifications to monitoring programs for evaluating doses to individuals from principal pathways of exposure. The annual Land Use Census is conducted during the growing season and is used to identify, within a radius of 5 miles, the location of the closest residences, milk animals, meat animals, and gardens in each of the 11 land based meteorological sectors surrounding Fermi 2.

The 2010 Land Use Census was performed during the month of August. The 2010 census data were obtained with the use of a hand-held Global Positioning System (GPS). These data were compared to the 2009 data to determine any significant changes in the use of the land. The results of the census are tabulated in Tables 2 - 5 of this report.

No significant changes in the land use between 2009 and 2010 were found that would require changing the location of the "maximum exposed individual". There were no changes in the category of closest residences. There was a slight change in one meteorological sector in the category of closest gardens. See Table 3 for this change. The "maximum exposed individual" is located in the West-North-West sector and at one time participated in the REMP program. In the past few years this location did not have a garden, but in 2007-2008 a garden was planted at this location. In the category of closest milk locations, there was one change. A goat was identified in the North sector. All milk locations that were identified are pets and, any milk produced, is not use for human consumption. There were no changes found in the category of closest meat locations. 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 2010 land use that would require changing the location of the "maximum exposed individual". For that reason, the location of "maximum exposed individual" remains the same and is described as follows:

Azimuth Distance Age Maximum Pathway Sector (degrees) (miles) Group Organ Ingestion WNW 300.6 0.72 Adult Thyroid (vegetation) 18

Fermi 2 - 2010 Annual Radiological Environmental Operating Report 2010 LAND USE CENSUS Closest Residences Table 2 Azimuth Distance Change Sector Year (degrees) (miles) (miles)

N 2009 8.9 1.11 2010 8.9 1.11 0.00 NE 2009 34.7 1.10 2010 34.7 1.10 0.00 NNE 2009 16.6 1.08 2010 16.6 1.08 0.00 NNW 2009 334.9 1.09 2010 334.9 1.09 0.00 NW 2009 309.7 1.07 2010 309.7 1.07 0.00 S 2009 169.6 1.03 2010 169.6 1.03 0.00 SSW 2009 200.1 1.12 2010 200.1 1.12 0.00 SW 2009 229.3 1.26 2010 229.3 1.26 0.00 W 2009 259.2 1.19 2010 259.2 1.19 0.00 WNW(a) 2009 302.3 0.72 2010 302.3 0.72 0.00 WSW 2009 236.3 1.39 2010 236.3 1.39 0.00 (a) = Location of "maximum exposed individual" 19

Fermi 2 - 2010 Annual Radiological Environmental Operating Report 2010 LAND USE CENSUS Closest Gardens Table 3 Azimuth Distance Change Sector Year (degrees) (miles) (miles)

N 2009 358.5 2.13 2010 358.5 2.13 0.00 NE 2009 51.8 1.85 2010 51.8 1.85 0.00 NNE 2009 30.6 1.91 2010 30.6 1.91 0.00 NNW 2009 332.1 2.57 2010 332.1 2.57 0.00 NW 2009 315.5 1.51 2010 315.5 1.51 0.00 S 2009 169.6 1.03 2010 170.6 1.01 -0.02 SSW 2009 201.9 1.59 2010 201.9 1.59 0.00 SW 2009 None identified None identified 2010 None identified None identified W 2009 266.7 1.70 2010 266.7 1.70 0.00 WNW 2009 297.7 4.40 2010 297.7 4.40 0.00 WSW 2009 250.5 2.38 2010 250.5 2.38 0.00 20

Fermi 2 - 2010 Annual Radiological Environmental Operating Report 2010 LAND USE CENSUS Milk Locations Table 4 Azimuth Distance Change Sector Year (degrees) (miles) (miles) Type N 2009 None identified None identified 2010 9.9 4.32 4.32 Goat NE 2009 None identified None identified 2010 None identified None identified NNE 2009 None identified None identified 2010 None identified None identified NNW 2009 None identified None identified 2010 None identified None identified NW 2009 None identified None identified 2010 None identified None identified S 2009 None identified None identified 2010 None identified None identified SSW 2009 None identified None identified 2010 None identified None identified SW 2009 None identified None identified 2010 None identified None identified W 2009 None identified None identified 2010 None identified None identified WNW 2009 297.4 2.38 Goat 2010 297.4 2.38 0.00 Goat WSW 2009 None identified None identified 2010 None identified None identified 21

Fermi 2 - 2010 Annual Radiological Environmental Operating Report 2010 LAND USE CENSUS Closest Meat Locations Table 5 Azimuth Distance Change Sector Year (degrees) (miles (miles) Type N 2009 None identified None identified 2010 None identified None identified NE 2009 None identified None identified 2010 None identified None identified NNE 2009 None identified None identified 2010 None identified None identified NNW 2009 338.2 4.36 Sheep 2010 338.2 4.36 0.00 Sheep NW 2009 321.4 3.02 Beef 2010 321.4 3.02 0.00 Beef S 2009 None identified None identified 2010 None identified None identified SSW 2009 None identified None identified 2010 None identified None identified SW 2009 None identified None identified 2010 None identified None identified W 2009 None identified None identified 2010 None identified None identified WNW 2009 287.5 1.65 Beef 2010 287.5 1.65 0.00 Beef WSW 2009 None identified None identified 2010 None identified None identified 22

Appendix A Sampling Locations

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations Table A-1 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type Tl NE/38 0 1.3 mi. Estral Beach, Pole on Q I Lakeshore 23 Poles S of Lakeview. (Special Area)

T2 NNE/22 0 1.2 mi. Pole at termination of Q I Brancheau St.

(Special Area)

T3 N/9 0 1.1 mi. Pole, NW comer of Swan Q I Boat Club fence. (Special Area) 0 T4 NNW/337 0.6 mi. Site boundary and Toll Rd. Q I on Site fence by API #2.

0 T5 NW/313 0.6 mi. Site boundary and Toll Rd. Q I on Site fence by API #3.

T6 WNW/294 0 0.6 mi. On Site fence at south end Q I of N. Bullet Rd.

T7 W/270 0 14.0 mi. Pole, at Michigan Gas Q C substation on N. Custer Rd., 0.66 miles west of Doty Rd.

T8 NW/305 0 1.9 mi. Pole on Post Rd. near NE Q I corer of Dixie Hwy. and Post Rd.

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

T10 N/6 0 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-1

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A-i continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T11 NNE/23 0 6.2 mi. Pole, NE comer of Q I Milliman and Jefferson.

T12 NNE/29 0 6.3 mi. Pointe Mouille Game Area Q I Field Office, Pole near tree, N area of parking lot.

T13 N/356 0 4.1 mi. Labo and Dixie Hwy. Pole Q I on SW comer with light.

T14 NNW/3370 4.4 mi. Labo and Brandon Pole on Q I SE corer near RR.

T15 NW/3150 3.9 mi. Pole, behind building at the Q I comer of Swan Creek and Mill St.

T16 WNW/283 0 4.9 mi. Pole, SE comer of War and Q I Post Rd.

T17 W/271 0 4.9 mi. Pole, NE comer of Nadeau Q I and Laprad near mobile home park.

T18 WSW/247 0 4.8 mi. Pole, NE comer of Mentel Q I and Hurd Rd.

T19 SW/236 0 5.2 mi. Fermi siren pole on Q I Waterworks Rd. NE comer of intersection - Sterling State Park Rd. Entrance Drive/Waterworks.

T20 WSW/257 0 2.7 mi. Pole, S side of Williams Q I Rd, 9 poles W of Dixie Hwy. (Special Area)

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

I = Indicator C = Control 0 = On-site Q = Quarterly A-2

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A-i continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T22 S/172 0 1.2 mi. Pole, N side of Pointe Aux Q I Peaux 2 poles W of Long -

Site Boundary.

T23 SSW/195 0 1.1 mi. Pole, S side of Pointe Aux Q I Peaux 1 pole W of Huron next to Vent Pipe - Site Boundary.

T24 SW/225 0 1.2 mi. Fermi Gate along Pointe Q I 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 I of Fermi Drive.

T26 WSW/259 0 1.1 mi. Pole, Toll Rd. - 6 poles S Q I of Fermi Drive.

T27 SW/225 0 6.8 mi. Pole, NE comer of Q I McMillan and East Front St. (Special Area)

T28 SW/229 0 10.6 mi. Pole, N side of Mortar Q C Creek between Hull and LaPlaisance.

T29 WSW/237 0 10.3 mi. Pole, NE corer of S Dixie Q C and Albain.

T30 WSW/247 0 7.8 mi. E side S end of foot bridge, Q I St. Mary's Park corer of Elm and Monroe St.

(Special Area)

T31 WSW/255 0 9.6 mi. 1st pole W of entrance Q C drive Milton "Pat" Munson Recreational Reserve on North Custer Rd.

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

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A-i continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T32 WNW/295 0 10.3 mi. Pole, corer of Stony Creek Q I and Finzel Rd.

T33 NW/3170 9.2 mi. Pole, W side of Grafton Q I Rd. 1 pole N of Ash and Grafton intersection.

T34 NNW/338 0 9.8 mi. Pole, SW comer of Port Q I Creek and Will-Carleton Rd.

T35 N/359 0 6.9 mi. Pole, S Side of S Huron Q I River Dr. across from Race St. (Special Area)

T36 N/358 0 9.1 mi. Pole, NE comer of Q I Gibraltar and Cahill Rd.

T37 NNE/21 0 9.8 mi. Pole, S corer of Adams Q I and Gibraltar across from Humbug Marina.

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

T39 S/176 0 0.3 mi. SE corer of Protected Q O Area Fence (PAF).

T40 S/170 0 0.3 mi. Midway along OBA - PAF. Q O T41 SSE/161 0 0.2 mi. Midway between OBA and Q O Shield Wall on PAF.

T42 SSE/149 0 0.2 mi. Midway along Shield Wall Q O on PAF.

T43 SE/131 0 0.1 mi. Midway between Shield Q O Wall and Aux Boilers on PAF.

T44 ESE/109 0 0.1 mi. Opposite OSSF door on Q O PAF.

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

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A-i continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T45 E/86 0 0.1 mi. NE Corer of PAF. Q O T46 ENE/67 0 0.2 mi. NE side of barge slip on Q O fence.

T47 S/1850 0.1 mi. South of Turbine Bldg. Q O rollup door on PAF.

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

T49 WSW/251 0 1.1 mi. Corer 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 Bullet Street sign.

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

T52 NNE/20 0 0.4 mi. Site Boundary fence at the Q O corer of Arson and Tower.

T53 NE/55 0 0.2 mi. Site Boundary fence east of Q O South Cooling Tower.

T54 S/1890 0.3 mi. Pole next to Fermi 2 Q O Visitors Center.

T55 WSW/251 0 3.3 mi. Pole, north side of Nadeau Q I Rd. across from Sodt Elementary School Marquee.

T56 WSW/256 0 2.9 mi. Pole, entrance to Jefferson Q I Middle School on Stony Creek Rd.

I = Indicator C = Control 0 = On-site Q = Quarterly A-5

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A-i continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T57 W/260 0 2.7 mi. Pole, north side of Q I Williams Rd. across from Jefferson High School entrance.

T58 WSW/249 0 4.9 mi. Pole west of Hurd Q I Elementary School Marquee.

T59 NW/325 0 2.6 mi. Pole north of St. Charles Q I Church entrance on Dixie Hwy.

T60 NNW/341 0 2.5 mi. 1st pole north of North Q I Elementary School entrance on Dixie Hwy.

T61 W/268 0 10.1 mi. Pole, SW corer of Stewart Q I and Raisinville Rd.

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

T63 WSW/245 0 9.6 mi. Pole, NE comer of Dunbar Q I and Telegraph Rd.

T64 WNW/286 0 0.2 mi. West of switchgear yard on Q O PAF.

T65 NW/3220 0.1 mi. PAF switchgear yard area Q O NW of RHR complex.

T66 NE/50 0 0.1 mi. Behind Bldg. 42 on PAF. Q O T67 NNW/338 0 0.2 mi. Site Boundary fence West Q O of South Cooling Tower.

T68 WNW/303 0 0.6 mi Langton Rd. seven poles Q I East of Leroux Rd.

T69 NW/3060 0.8 mi Langton Rd. five poles East Q I of Leroux Rd.

T70 NNW/333 0 1.1 mi Leroux Rd. last pole North Q I of Fermi Dr.

T71 WNW/300 0 1.1 mi Leroux Rd. six poles North Q I of Fermi Dr.

I = Indicator C = Control 0 = On-site Q = Quarterly A-6

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Air Particulate andAir Iodine Sample Locations Table A-2 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type API-1 NE/39 0 1.4 mi. Estral Beach Pole on W I Lakeshore, 18 Poles S of Lakeview (Nearest Community with highest X/Q).

API-2 NNW/337 0 0.6 mi. Site Boundary and Toll W I Road, on Site Fence by T-4.

API-3 NW/3130 0.6 mi. Site Boundary and Toll W I Road, on Site Fence by T-5.

API-4 W/270 0 14.0 mi. Pole, at Michigan Gas W C substation on N. Custer Rd., 0.66 miles west of Doty Rd.

API-5 S/188 0 1.2 mi. Pole, N comer 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

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Garden Sample Locations Table A-4 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type FP-1 NNE/21 0 3.8 mi. 9501 Turnpike Highway. M I FP-9 W/261 0 10.9 mi. 4074 North Custer Road. M C I = Indicator C = Control M = Monthly (when available)

Drinking Water Sample Locations Table A-5 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type DW-1 S/174 0 1.1 mi. Monroe Water Station N M I Side ofPointe Aux Peaux 1/2 Block W of Long Rd.

DW-2 N/8 0 18.5 mi. Detroit Water Station M C 14700 Moran Rd, Allen Park.

I = Indicator C = Control M= Monthly A-8

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Surface Water Sample Locations Table A-6 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type SW-2 NNE/20 0 11.7 mi. DECo's Trenton Channel M C Power Plant Intake Structure (Screenhouse #1).

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

I = Indicator C = Control M = Monthly Groundwater Sample Locations Table A-7 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type GW-1 S/175 0 0.4 mi. Approx. 100 ft W of Lake Q I Erie, EF-1 Parking lot near gas fired peakers.

GW-2 SSW/208 0 1.0 mi. 4 ft S ofPointe Aux Peaux Q I (PAP) Rd. Fence 427 ft W of where PAP crosses over Stoney Point's Western Dike.

GW-3 SW/226 0 1.0 mi. 143 ft W of PAP Rd. Gate, Q I 62 ft N of PAP Rd. Fence.

GW-4 WNW/299 0 0.6 mi. 42 ft S of Langton Rd, 8 ft Q C E of Toll Rd. Fence.

I = Indicator C = Control Q = Quarterly A-9

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Sediment Sample Locations Table A-8 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type S-1 SSE/1650 0.9 mi. Pointe Aux Peaux, SA I Shoreline to 500 ft offshore sighting directly to Land Base Water Tower.

S-2 E/81 0 0.2 mi. Fermi 2 Discharge, approx. SA I 200 ft offshore.

S-3 NE/39 0 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.

0 S-5 NNE/20 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-1 NNE/31 0 9.5 mi. Near Celeron Island. SA C F-2 E/86 0 0.4 mi. Fermi 2 Discharge (approx. SA I 1200 ft offshore).

F-3 SW/227 0 3.5 mi. Brest Bay. SA C I = Indicator C = Control SA = Semiannually A-10

- t-vr 7/ -o J

<,2; / , -,

// 7 LAKE T6 Q' 6--

1 SMAP 1 '- T 12 SAMPLING LOCATIONS BY STATION NUMBER WITHIN 1I MI[E MILE L EGEND

• T- DIRECT PARTICULATES/ATR RADIATION IODINE o API- AIR 0 API- AIR PART TCULATES/AI IODINE A S- SEDIMENTS AA DW/Slvv DRINKIMG WATER/SURFACE DW/SW- DRINKING WATER/SURFACE WVATER WATER 2GW- GROUND GROUND WATER W,VAT ER El D M M- MILK 0 0.5 sF-FOOD PRODUCTS FP- FISH

.<1FP- FOOD - IN MILES SCALE F- FISH SCALE TN MILES

/ 7Ti i1 4*-*ri MAP 2 1 DW/SW-ADRINKING WATER/SURFACE WATER tiGROUNDGW- WATER /0F SMAP - 2 F- FISH SAMPL SCALE IN MILESLOCATIONS (1 To 5 MILES)

LEGEND . \

e T- DIRECT RADIATION 0 API- AIR PARTICULATES/AIR IODINE o API- AIR PARTICULATES/AIR IODINE A 5- SEDIMENTS Y

GW- GROUND WATER 0 1 M-(I MILK SFP- FOOD PRODUCTS

• IZFP- FOOD PRODUCTS F- FISH SCALE IN MILES

96 ROSE PoINTE PK LlOUTH MASSlSIAN SAMPLING LOCATIONS 11g iillBll§litlj!llllh NDl SNIW

.p\ l IiBi H

ý_n llull IIC iAP ,I O31 I -I- T O I c:ilSVIL Eiiý-;;i

'" 1 J2 0 D FISH rll~0 MA YBEE ;I M 8*liTili-s---ii-l

~~B~*rr~-~APIi T, Ai,R7 A K MAUMEE

ýý,HR I'S 1

@ T-RAD.ATTON DIRECT MAP 3iiiiiilii~i SAMPLINGLOCATION BY NUMBE STATIN --

M- MILK. A I A S- MAP- - 3 iiais~.

SEDIMENTS S SD SAMPLING BY STATTON LOCATIONS NUMBER (GREATER THAN 5 MILES)

LEGEND . \

0 API- AIR PARTICULATES OR AIR IODINE F- FISHM

Appendix B Environmental Data Summary

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Table B-l Radiological Environmental Monitoring Program Summary Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2010 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

Location with Highest Sample Type Type and Indicator Annual Mean Control Number of (Units) Number of Locations Locations Non-routine Analysis LLD Mean and Range Location Mean and Range Mean and Range Results Direct Radiation Gamma (TLD) 1.0 14.2 (187/187) T-49 (Indicator) 18.5 (4/4) 13.7 (15/15) None mR/stdqtr 202 10.0 to 20.9 16.7 to 20.9 10.7 to 16.3 Airborne Gross Beta 253 1.00E-2 3.57E-2 (202/202) API-5 (Indicator) 4.22E-2 (51/51) 3.73E-2 (51/51) None Particulates 8.00E-3 to 8.31E-2 2.00E-2 to 8.31E-2 1.44E-2 to 6.73E-2 pCi/cu. m. Gamma Spec. 20 Be-7 N/A 9.98E-2 (16/16) API-5 (Indicator) 1.33E-1 (4/4) 1.06E-1 (4/4) None 4.28E-2 to 1.92E-1 7.65E-2 to 1.92E-1 4.42E-2 to 1.57E-1 K-40 N/A <MDA <MDA None 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 Nb-95 N/A <MDA <MDA None Ru-103 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 5.00E-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 Ce-141 N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None Airborne Iodine I-131 254 7.00E-2 <MDA <MDA None pCi/cu. m.

B-1

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Table B-I Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2010 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchitown Township)

Location with Highest Sample Type Type and Indicator Annual Mean Control Number of (Units) Num-ber of Locations Locations Non-routine Analvsis LLD Mean and Ran-,e Location Mean and Range Mean and Range Results Milk 1-131 34 1.OOE+0 <MDA <MDA None PCili Sr-89 34 N/A <MDA <MDA None Sr-90 N/A 1.36E+0 (2/17) M-8 (Control) 1.54E+/-0 (1/17) 1.54E+/-0 (1/17) None 1.24E+0 to 1.48E+0 Gamma Spec. 34 Be-7 N/A <MDA <MDA None K-40 N/A 1.48E+3 (17/17) M-2 (Indicator) 1.48E+3 (17/17) 1.44E+3 (17/17) None 1.37E+3 to 1.66E+3 1.37E+3 to 1.66E+3 1.30E+3 to 1.56E+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 Nb-95 N/A <MDA <MDA None Ru-103 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 1.50E+l <MDA <MDA None Cs-137 1.80E+/-1 <MDA <MDA None Ba-140 1.50E+/-1 <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 Vegetation 1-131 8 6.00E+1 <MDA <MDA None pCi/kg wet Gamma Spec. 8 Be-7 N/A <MDA <MDA None K-40 N/A 3.13E+/-3 (4/4) FP-9 (Control) 5.11 E+3 (4/4) 5.11 E+3 (4/4) None

_______________________ _______2.44E+3 to 3.74E+3 _________4.48E+3 to 6.OOE+3 4.48E+3 to 6.OOE+3_______

B-2

Fermi 2 -2010 Annual Radiological Environmental Operating Report Table B-I Radiological Enviromnmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2010 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

Location with Highest Sample Type Type and Indicator Annual Mean Control Number of (Units) Number of Locations Locations INon-routine Analysis LLD Mean and Ranae Location Mean and Range Mean and Range Results Vegetation Mn-54 N/A <MDA <MDA None (cont.) Co-5 8 N/A <MDA <MDA None pCilkg wet 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 Nb-95 N/A <MDA <MDA None Ru-103 N/A <MDA <NMDA None Ru-106 N/A <MDA <IMTA None Cs-134 6.OOE+l <%MDA <MDA None Cs-137 8.00E+1 <MDA <M*,DA None Ba-140 N/A <MDA <MDA None La-140 N/A <NMDA <MDA None Ce-141 N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None Drinking Water Gross Beta 24 4.OOE+0 4.24E+0 (6/12) DW-1 (Indicator) 4.24E+/-0 (6/12) 3.49E+0 (5/12) None pCi/i 3.50E+0 to 5.30E+0 3.50E+0 to 5.30E+0 2.95E+0 to 4.30E+0 Sr-89 24 N/A <MDA <MDA None Sr-90 N/A <MDA <MDA None Gamma Spec. 24 Be-7 N/A <MDA <MDA None K-40 N/A <MDA <MDA None Cr-51 N/A <NMA <MDA None Mn-54 1.50E+/-l <MDA <MDA None Co-58 1.50E+l <MDA <MDA None Fe-59 3.00E+1 <MDA <MDA None Co-60 1.50E+/-1 <MDA <MADA None Zn-65 3.00E+1 <MDA <MDA None Zr-95 1.50E+I <MDA <MDA None Nb-95 1.50E+l <%MDA _______________<MDA I None _

B-3

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Table B-I Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2010 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

Location with Highest Sample Type Type and Indicator Annual Mean Control Number of (Units) Number of Locations Locations Non-routine Analysis LLD Mean and Range Location Mean and Range Mean and Range Results Drinking Water Ru-103 N/A <MJDA <MDA None (cont.) pCill Ru-i106 N/A <MDA <MDA None Cs-134 1.50E+l <MDA <MDA None Cs-137 1.80E+l <MDA <MDA None Ba-140 L.50E+1 <MDA <MDA None La-140 L.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 <MIDA <MDA None pCili Sr-90 N/A <MIDA <MDA None Gamma Spec. 24 Be-7 N/A <MIDA <MDA None K-40 N/A <MIDA <MDA None Cr-51 N/A <MIDA <MDA None Mn-54 I.50E+1 <MDA <MDA None Co-58 1.50E+1 <MDA <MDA None Fe-59 3.00E+1 <MDA <MDA None Co-60 1.50E+1 <MDA <MDA None Zn-65 3.00E+I <MIDA <MIDA None Zr-95 1.50E+1 <MDA <MDA None Nb-95 1.50E+l <SMDA <MDA None Ru-103 N/A <MIDA <MIDA None Ru-106 N/A <MIDA <MDA None Cs-134 1.50E+l <MDA <MIDA None Cs-137 L.80E+1 <MDA <MDA None Ba-140 I.50E+1- <MIDA <MIDA None La-140 L.50E+1 <MDA <MDA None Ce-141 N/A <MIDA <MIDA None B-4

Fermi 2 -2010 Annual Radiological Environmental Operating Report Table B-I Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2010 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

Location with Highest Sample Type Type and Indicator Annual Mean Control Number of (Units) Numnber of Locations Locations Non-routine Analysis LLD Mean and Ran ge Location Mean and Range Mean and Range Results Surface Water Ce-144 N/A <NMDA <,MDA None (cont.) pCill H-3 8 2.OOE+/-3 <MDA <NMDA None Groundwater Gamma Spec. 16 pCili Be-7 N/A <MDA <MDA None K-40 N/A 8.00E+1 (1/12) GW-2 (Indicator) 8.OOE+l (1/4) 3.28E+1 (1/4) None Cr-Si N/A <MDA <MDA None Mn-54 1.50E+/-l <MDA <MDA None Co-58 1.50E+/-1 <M7DA <MDA None Fe-59 3.00E+1 <MDA <MDA None Co-60 1.50EH-l <MDA <MDA None Zn-65 3.00E+I <MDA <MDA None Zr-95 1.50E+Il <MDA <MDA None Nb-95 1.50E+1 <MDA <MDA None Ru-103 N/A <%MDA <MDJA None Ru-106 N/A <MDJA <MDA None Cs-134 1.50E+1 <NMDA <MDA None Cs-137 1.80E+l <NMDA <MDA None Ba-140 1.50E+1 <%MDA <MDA None La-140 1.50E+l <MDA <MDJA None Ce-141 N/A <MDA <MDJA None Ce-144 N/A <MDA <MDA None H-3 16 2.OOE+/-3 <MDA <MDA None Sediment Sr-89 10 N/A <MDA <,MDA p Ci/kg dry Sr-90 N/A <MDA <MDA None Gamma Spec. 10 Be-7 N/A <MDA None K-40 N/A 1.24E+4 (8/8) S-2 (Indicator) 2.17E+4 (2/2) 1.21E+4 (2/2)

___________ __________________1.60E+2 to 2.56E+/-4 1.77E+4 to 2.56E+4 1.19E+4 to 1.23E+4 None B-5

Fermi 2 -2010 Annual Radiological Environmental Operating Report Table B-i Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2010 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

Location w,ith Highest Sample Type Type and Indicator Annual Mean Control Number of (Units) Number of Locations Locations Non-routine Anialysis LLD Mean and Range Location Mean and Range Mean and Range Results Sediment (cont.) Mn-54 N/A <MDA <MDA None p Cilkgdry 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 Nb-95 N/A <MDA <MDA None Ru-103 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 1.50E+2 <MDA <MDA None Cs-137 1.80E+2 <MDA S-5 (Control) 8.29E+l (1/2) 8.29E+l (1/2) None Ba-140 N/A <MDA <MDA None La-140 N/A <MDA <MIDA None Ce-141 N/A <MDA <MDA None

_______Ce-144 N/A <MDA <MDA None Fish Sr-89 25 N/A <MDA <MDA None pCilkg wet Sr-90 N/A <MDA <MDA None Gamma Spec. 25 Be-7 N/A <MDA <MDA None K-40 N/A 2.8 1lE+3 (8/9) F-2 (Indicator) 2.81lE+3 (8/9) 2.46E+3 (15/16) None 1.75E+3 to 3.56E+3 1.75E+3 to 3.56E+3 1.70E+2 to 4.OOE+3 Mn-54 1.30E+/-2 <MDA <MDA None Co-58 1.30E+I2 <MIDA <MIDA None Fe-59 2.60E+2 <MIDA <MDA None Co-60 1.30E+/-2 <MDA <MDA None

________Zn-65 2.60E+2 <MDA _ ______________<MDA None B-6

Fermi2 - 2010 Annual Radiological Environmental Operating Report Table B-l Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2010 Location of Facility: 30 miles southeast of Detroit, Michigan (Frenchtown Township)

Location with Highest Sample Type Type and Indicator Annua Mean Control Number of (Units) Number of Locations Locations Non-routine Analysis LLD Mean and Range Location Mean and Range Mean and Rang e Results Fish (cont.) Zr-95 N/A <MDA <MDA None pCi/kg wet Nb-95 N/A <MDA <MDA None Ru-103 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 1.30E+2 <MDA <MDA None Cs-137 1.50E+2 <MDA <MDA None 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 Direct Radiation mean and range values are based on off-site TLDs LLD = Fermi 2 ODCM LLD: nominal lower limit of detection based on 4.66 sigma error for background sample.

<MDA = Less than the lab's minimum detectable activity which is less than the LLD.

Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).

Locations are specified by Fermi 2 code and are described in Appendix A Sampling Locations.

Non-routine results are those which are reportable according to Fermi 2 ODCM control 3.12.1.

Note: Other nuclides were considered in analysis results, but only those identifiable were reported in addition to ODCM listed nuclides.

B-7

Appendix C Environmental Data Tables

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 TLD ANALYSIS (mR/Std Qtr)

STATION FIRST SECOND THIRD FOURTH NUMBER QUARTER QUARTER QUARTER QUARTER T-1 11.24 12.70 13.55 12.97 T-2 10.82 11.55 13.15 12.80 T-3 9.96 11.91 12.17 14.33 T-4 11.86 13.27 15.09 14.33 T-5 11.90 14.10 15.51 14.66 T-6 11.90 (a) 16.15 14.82 T-7 13.28 14.63 15.65 15.43 T-8 13.74 14.92 15.86 14.97 T-9 11.91 12.81 14.54 13.55 T-10 12.98 13.62 15.30 14.90 T-11 11.35 13.16 13.70 13.33 T-12 11.35 12.36 13.99 13.27 T-13 13.32 15.98 16.60 15.55 T-14 13.09 14.99 (a) 15.96 T-15 11.41 12.19 13.54 12.66 T-16 14.98 15.60 18.20 (a)

T-17 10.95 12.18 13.34 12.51 T-18 11.86 12.45 14.26 14.31 T-19 13.80 15.19 16.37 15.29 T-20 12.77 13.58 17.18 16.33 T-21 11.64 11.86 13.72 13.39 T-22 12.40 13.14 14.72 15.35 T-23 11.85 13.48 14.46 14.48 T-24 10.82 12.20 13.59 14.30 T-25 13.64 15.74 17.13 17.41 T-26 14.85 15.31 17.48 17.06 T-27 10.86 11.34 12.31 12.96 T-28 12.53 10.84 13.77 13.76 T-29 10.71 12.75 13.31 12.97 T-30 12.35 14.47 13.93 15.40 T-31 (a) 14.34 15.05 16.33 T-32 13.04 14.04 (a) 15.74 T-33 11.10 12.67 13.10 13.06 T-34 12.74 13.11 15.36 14.74 T-35 11.51 12.39 14.15 13.66 T-36 12.20 13.61 14.88 14.54 T-37 11.94 13.24 14.77 14.77 T-38 13.18 15.17 16.28 16.78 T-39 58.86 53.50 75.10 27.22 T-40 52.29 41.54 56.83 21.44 T-41 94.32 78.66 114.96 37.51 T-42 94.90 74.10 117.75 38.21 T-43 107.18 85.48 124.40 44.15 T-44 93.08 79.38 120.89 42.36 T-45 54.37 49.59 68.69 23.37 T-46 41.56 43.32 55.11 22.92 T-47 92.99 81.37 (a) 43.52 (a) TLD missing, see Appendix D - Program Execution.

C-1

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 TLD ANALYSIS (CONT.)

(mR/Std Qtr)

STATION FIRST SECOND THIRD FOURTH NUMBER QUARTER QUARTER QUARTER QUARTER T-48 43.641 41.11 55.78 32.28 T-49 16.65 18.17 20.88 18.21 T-50 12.44 (a) 16.25 16.28 T-51 10.25 10.45 12.08 11.45 T-52 13.74 (a) 16.90 13.79 T-53 25.32 26.90 32.61 18.98 T-54 16.53 17.95 21.10 14.29 T-55 13.27 14.78 16.58 16.60 T-56 12.42 13.85 15.12 14.70 T-57 15.18 17.11 18.46 18.18 T-58 11.41 12.39 14.07 13.88 T-59 11.60 12.76 14.20 13.56 T-60 13.20 14.02 16.99 15.42 T-61 13.32 14.26 15.96 17.52 T-62 13.65 14.17 16.52 18.74 T-63 11.60 11,74 13.53 14.59 T-64 22.57 22.65 28,17 16.29 T-65 25.32 24.88 31.17 18.43 T-66 142.98 125.91 176.00 60.14 T-67 16.49 17.60 21.27 16.18 T-68 14.56 15.86 19.10 17,57 T-69 14.67 14.89 17.72 17.51 T-70 13.17 14.08 16.30 15.88 T-71 13.41 15.12 17.45 17.99 (a) TLD missing, see Appendix D - Program Execution.

C-2

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-i FIRST QUARTER Date Activity__

6-Jan-10 2.59E-02~+12.20E-03 13-Jan-10 +- I.9E0 3,1 OE -03 20-Jan-10 3.78E-021 +/7, 2.60E-03_

27-Jan-10 2.45E-02~ +12.40E-03 3-Feb-10 2.16E-02 +1 3.50E-03 9-Feb-10 2.81E-&2 +12.80E-03 17-Feb-10 2.04E-02 + 2.-50F-03 2-Mar-10 1.74E-02+/- 260-0 10-Mar-10 280E-02/ 12.60E-03 1-Mar-10 2.29E-02+/-/ 2.30E-03 2-ar-10 2.44E-02+/ 2.70E-03 30-Mar-1 21E-02~ 1 2.30E-03 API-i SECOND QUARTER iDate. I________________

6-Apr-10 I2.67E-02, +1-2.80E-03 I 13-Apr-10 I1.92E-02j +1 2.30E-03 20-Ap 1 2.17E-02",(_+/- 12.40E-03 27-Apr-1(0 j 1.90E-02 +/- _12.30E-_03 4-May-10 t.30E-02 +/- 2.0E0 11-May-10 1.38E-021 +/- 2.i1OE-03 18-May-10 (a)]_I__

25-May-10 1.69E-02{ +/- 2.20E-03 1-Jun-10 1.88E-021 +/- 12.50E-03 (a)8-Jun-1 0 _2.22E-02' +/- 2,80E-03 15-Jun-10 1.43E-021 +/- L2.20E-03 22-Jun-10 _(a) __

29-Jun-10 3.70E-02I +12.66E-03 (a) See Appendix D - Program Execution.

C-3

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-1 THIRD QUARTER Date I Activit N, 6-Jul-10 4.94E-021 +/- 3.63E-03 13-Jul-10 5.36E-02 +1- 2.97E-03 20-Jul-10 4.65E-02 +/- 3.27E-03 27-Jul-10 4.73E-02 +/1 3.06E-03 I3-Aug-10 5.90E-02 +/- 3.37E-03 10-Aug-10 5.83E-02 +- 3.35E-03 17-Aug-10 4.83E-02 +/- 3.07E-03 24-Aug-10 5.05E-02 +/- 3.06E-03 31-Aug-10 5.12E-021 +/- 3.07-03 7-Sep-10 3.26E-02 +- 2.45E-03 14-Sep-10 3_60E-02 /- 2.79E-03 21 -Sep-10 4.13E-02 +/- 2.58E-03 28-Sep-10 3.12E-02 t/- 2.40E-03 API-1 FOURTH QUARTER DateC Activity 5-Oct-10 l 4.48E-02 +1- 2.86E-03 12-Oct-10 3.81E-02 +/- 2.67E-03 19-Oct-10 4.27E-02i +- 2.81E-03 26-Oct-10 3.19E-021 +- 2.43E-03 2-Nov-10 1 3.89E-021 +/ 2.68E-03 16-Nov-10 4.15E-021 +/- 2.79E-03 23-Nov-10 5.28E-02j +- 3.08E-03 30-Nov-10 4.95E-021 +- 3.04E-03 7-Dec-10 3.79E-02 +/- 2.68E-03 14-Dec-10 14.79E-02 +I- 3.04E-03 21-Dec-10 4.89E-02 +/- 3.02E-03 28-Dec-10 2.79E-02 +1/-2.32E-03 C-4

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-2 FIRST QUARTER Date Act4ivit I 6-Jan-101I 2.74E-02 +/-1-2.20E-03 3Jan-lo 3.02E-02~ +13.OE03 K 20-Jan-101 4.82E-02, +/-1 2.80E-03 i27-Jan-1~ 2.90E-02 +-2.-50E-03 3-Feb-10~- 3.14E-02 I/- {2.50E-03 9-Feb-101 3.30E-02I ;1-2.80E-03 17-Feb-101 2.28E-02 1- i2.50E-03 24-Feb-101 2.43E-021 +1-2.50E-03 2-ar ' 2.OOE- 021 +1-2.60E-03 10-Mar-10l 3.21E-021 +1-2.70E-03 17-Mar-10 2.19E-02i +1-2.30E-03 23-Mar-l10 3.11 E-02~ +12.80E-03_

30-Mar- 10 3.36E-02r +/2.50E-03 API-2 SECOND QUARTER Date I ~ActivityK 6-Apr-1iu L IA14-2 1 30E3 13-Apr-10j 2.64E-02+/ 2.40E-03 20-Apr-10 2.88E-02J 1 2.50E-03 27-Apr-10 3.09E-02 +1 2.50E-03

.. M...y...4 2.26E-02 +-2.40E-03 11-May-10 2,09E-02 +-2.20E-03 18-May-10 1.752E-021 1 2.10E-03 25-May-10 -,-2.08E,-,021+/- 2-20E.703-1-Jun-10 11.99E-02J 1 2.30E-03 (a)8-Jun-10~ 2.31E-02I +/-_13.IOE-03 15-Jun-10I 2.30E-02~ +/- 12.50E-03 22-Jun-101 1.79E-02, +/- 21E-6j 29-Jun-10! 2.56E-02: +/- 12.30E-03 (a) See Appendix D - Program Execution.

C-5

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-2 THIRD QUARTER Date ActivitN 6-Jul-10 5.70E-02 +/- 3.28E-03 13-Jul-10 5.50E-02 +/- 2.98E-03 20-Jul-10 3.98E-02 +/- 2.70E-03 27-Jul-10 4.64E-02: +/- 3.23E-03 3-Aug-10 4.51E-02: + 2.82E-03 10-Aug-10o 4.93E-02 /- 3.16E-03 17-Aug-10 4.20E-02 +/- 2.72E-03 24-Aug-10 4.61E-02 +- 2.88E-03 31-Aug-10 4.31 E-021 +- 2.80E-03 6-Sep-10 2.59E-02 t:/- 2.16E-03 13-Sep-10 3.92E-02 +- 2.93E-03 21-Sep-*10 3.87E-02 +/- 2.51E-03 2 -Sep-10 2.52E-02i +- 2.13E-03 API-2 FOURTH QUARTER Date Activity 5-Oct-10o 4.83E-02 +/- 2.97E-03 12-Oct-10. 3.58E-02 +/- 2.53E-03 19-Oct-10 4.81E-02 +- 3.00E-03 26-Oct-10 3.06E-02 + 2.36E-03 2-Nov-10 3.72E-02 +- 2.65E-03 16-Nov-10 t3.79E-02 +/- 2.69E-03 23-Nov-10..

.. 5.10E-02 3.16E-03 30-Nov-10 5.16E-02 +1-t3.07E-03 7-De.c-10 3.77E-.02t/- j2.64E-03 14-Dec-o10 4.35E-02 +/- 2.91E-03 21-Dec-10o 4.97E-02 13/-

3.06E-03 28-Dec-10 2.96E-02 /- 2.38E-03 C-6

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-3 FIRST QUARTER Date Activity 6-Jan-10 2.23E-021 +/- 2.10E-03 13-Jan-10 3.54E-02 +/-3.10E-03 20-Jan-10 5.06E-02 +/- 2.80E-03 S27-Jan-101 3.38E-02 +/- 2.60E-03 3-Feb-10 3.20E-02 +- 2.50E-03 9-Feb-10 2.93E-02 +-2.70E-03 17-Feb-10 2.09E-02 +i- 250E03 24-Feb-10 1.11E-021 +- 1.60E-03 2-Mar-10 8.00E-03 +/- 2.40E-03 10-Mar-10 2.92E-02 +/- 2.60E-03 17-Mar-10 2.73E-02 +/- 2.40E-03 _

S23-Mar-1l 2.42E-02 +/- 2.70E-03

'30-Mar-1-0 23 +- 230E-03 022/-.3 API-3 SECOND QUARTER Date Activi vt S 6-Apr-10 3.11E-02 +/- 2.90E-03

.13-Apr-1 2.18E-02 +/- i2.30E-03 20-Apr-10 2.35E-02 +/- 2.40E-03

.27-Apr-1 0 2.36E-02 +/- 2.40E-03 i 6 62 +/-_2.....2Mi.^

.... 4-May-10 .. ..^.^....

1.43E-02 ^2.20E-03

^ .

11-May-10 1.56E-02 +/- 2.10E-03 18-May-o10 1.15E-02 +/- 12.OOE-03 25-May-10 1.84E-02 +/- 2.20E-03 1-Jun-10 1.74E-02 +/- 2.20E-03 (a)8-Jun-10. 2.40E-02 +/- 3.10E-03 15-Jun-10 1.69E-02 +/- !2.30E-03 22-Jun-10 1.45E-02 +/- 2.10E-03 29-Jun-10 2.1 OE-02 +/- 2.20E-03 (a) See Appendix D - Program Execution.

C-7

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-3 THIRD QUARTER Date Activity 6-Jul-10 4.37E-02 +/1- 2.85E-03 13-Jul-10 5.47E-02 +/- 3.18E-03 20-Jul-10 .....

4:2 4> o2+ 2.891E-03 4.75E-02 27-Jul-10 4.24E-02+/- 3.09E-03 3-Aug-10. 4.71.E-02. - 2.90E-03 10-Aug-10 4.64E-02 3.00E-03 17-Aug-10 4.82E-02 +/- 2.93E-03 24-Aug-10o 4.85E-02 1+/- 2.92E-03 31-Aug-10 4.49E-02 +/- 2.87E-03 6-Sep-10 2.74E-02 +/- 2.28E-03 13-Sep-10 3.8,1E-02 +/-12.88E-03 21-Sep-10 3.28E-02 +1- 2.31E-03 28-Sep-0t 2.73E-02

• 2.28E-03 API-3 FOURTH QUARTER Date Activity 5-Oct-10o 4.99E-02 +/- 3.04E-03 12-Oct-10 3.16E-02 +- 2.36E-03 19-Oct-10 4.41E-02 +/ 2.89E-03 26-Oct-10 2.89E-02 +/- 2.39E-03 2-Nov-10 3.88E-02 +/- 2.71E-03 S16-Nov-10 4.53E-02 +/- 2.91E-03 23-Nov-10 5.30E-02 +/- 3.14E-03 30-Nov-10 3.83E-02 +- 2.65E-03 7-Dec-o10 3.37E-02 +- 2.49E-03 14-Dec-10 5.05E-02 +/- 3.12E-03 21-Dec-l10 4.30E-02 +/- 2.86E-03 28-Dec-10 2.48E-02 +/- 2.22E-03 C-8

Ferini 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

AiPI-4 FIRST QUARTER Date Activity 6-Jaii-tO 2.47E-02~ 1 2. 1OE-03 13-Jani-i1W 3.37E-02+1- 3. 1OE03 20-Jan-10, 4.54E-02 1- 2.70E-03 27-Jan-101 3.26E-02+1- 2.50E-03 3-Feb-10~ 3.39E-02+1- 2.5 OE-0,3 9-Feb-10~ 3.39E-02 1- ?2.80E-03 17-Feb-10, 2.i1IE-021 +1-2.50E-03 24-Feb-10, 2.17E-02: +1-2.50E-03 2-Mar-10, .7-2 1 26E0 10-Mar-10? 3.93E-02~ .0-3 17-Mar-10 2.60E-02; +1-2.30E-03 23-Mar-10t 3.06E-02+1- ý2.80E-03 L30-Mar-10? 2.97E-02; +/- 2.40-03 API-4 SECOND QUARTER Dte lb C 7 Activit ~

6-Apr-I()~ 4.0,4L-02? 1 3.10E-03~

13-Apr-10 2.3 8E-02? 1 2.40E-03 20-Apr-10?1 2,55E-02? 1 2.50E-03~

27-Apr-10? 2.84E-02? 1 2.50E-03~

4-May-10 1 92E-02 1- 2.30E-03 11 -May7l-1 1.95E-021 1-?2.20E-03 18-May-10 1.44E-02 1- 2. 1OE-031 2 5-May-101 1.82E-02+1- 2.20OE-03 1-Jun-101 2.53E-02? 1 2.30E-03 (a)8-Jun-101 2.50E-02? 1 2.70E-03 15-Jun-10, 1.80E-o?+-?7o6 22-Jun-10 1.78E-02?+- 2.20E-03~

29-Jun-101 2.16E-02~ 1 2,21DE-031 (a) See Appendix D - Program Execution.

C-9

Fermi 2 -2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-4 THIRD QUARTER Datiecivt 6-Jul- 10 I4.h2E-02~ +/-12.9j8E-03 13-Jul-lol 5.46E-09,+1 3.*23E-03 20-Jul-10 I4.31E-02j + t2.70E-03 27-Jul-10l 4.1OE-02ý +13.09E-03j 3-Aug- 10 4.89E-62i 1 36E6 10-Aug-10 I6.20E-02, 1 13.40E-03 17-Auga-10~ 5.63E-02+1- 3.29E-03 24-Aug-i10 6.31E-62 ----- 3-.47E 31-Aug1 5.44E-02 3.15E-03 6-Sep-10M 4.80E-02' +1 3.88E-03 13-e-O 3.92E-02: 1 2.96E-03 21-Sep-10 i 40E0 I2,58E-03 28-Sep-lO0 3.21E-02~ +1244E-03 API-4 FOURTH QUARTER 5-OLLtiO .8-012 +- 3.15E-03 12-Oc-t-1 0 4.W1E-012 +1 2.76E-03 1-9-",O,ct-10 -11 5.43E-02I +13.20E-0-3 26-Oc-1 3.02E-02j 1 2.39E-03 2-Nov-10 I4.64E-02 +1 2.95E-03 16___Nov-10 5 .78E-02 31.,31E-03 23-Nov-10 6.73E-02 +-3,54E-03 30-Nov-10I 5.OOE-02 +-3.13E-03 7-Dee-10 4.53E-02 +-2.90E-03 14-Dec-10I 5.64E-02 +/- 3.24E-03 21-Dec-101 5.50E-02 +-3.23E-03 28-Dec-10 2'.oE-021+-23-0 C-i10

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICUILATE GROSS BETA (pCi/cubic meter)

API-5 FIRST QUARTER Date IAtvt 6-Jan-10? 2.95E-02 i1 ~2.20E-03 13-Jan-10, 4.04E-02 31-

.2E'-6 20-Jan-10? 5.55E-02 1- 2.90E-03 27-Jan-10 3.49E-02~ +/-12.60E-03 3-Feb-1W~ 3.45E-02 +/-1 2.60E-03 9-Feb-10? 3.95E-02'+/-1 2.90E-03 17-Feb-101 2.24E-02:+1 2.50E-03 24 Fb101 2.44E-02.+1 2.50E-03 2-Mar-10j 2.27E-02 +1 2.70E-03 10-Mar-lO 10 ~ &2V 12.80E-03 17,-M-ar-10? 2.41E-021 21i.30E-01 f23-Mar-1013.59E--0-21 +1-2.90E-03 30-Mar-10,3.40E-02! +1-2.50E-03 API-5 SECOND QUARTER DaIte Activitv 6-Aprl-10 4.7-2E-U2?1 ?3,20E-03 13-Apr-10? 2.91E-02' + 2 .50E-03 20-Apr-10, 2.94E-02{ 21

.50E 27-Apr-10? 3.48E-02 21.60E-03J 4-My-0,2.50E-021 +1-2.40E-03 11-M-10 2.OOE-02 ?2.20 -03 18-May-10.1 2.03E-02? +12.20E-03 25-May-101 2.47E-02 [4 '2.30E-03 1-Jun-1 0 2.49E-02?+1 2,40E-03 (a)8-Jun-10, 2.26E-02~ 1 3.10E-03 15-Jun-1 0 2.22E-02? +12.30E-W3 22-Jun-1 0 2.37E-02? +12.20E-03 I29-Jun-101 2.63E-02' 1 2.30E-03 (a) See Appendix D - Program Execution.

C-1Il

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-5 THIRD QUARTER Date Activity 6-Jul-10 5.56E-02 +/- 3.19E-03 13-Jul- 10 6.47E-02 +1- 3.54E-03 20-Jul-10 .5.37E-02t +- 2.99E-03 27-Jul-10 4.48E-02 +1- 3.30E-03 3-Aug-10 4.89E-02 +/- 3.00E-03 I0-Aug-10 6.35E-02 +/- 3.39E-03 17-Aug-10O 6.12E-02 +/- 3.48E-03 24-Aug-10 6.90E-021 _+/- 3.55E-03 31 -Aug-10 6.26E-02i +- 3.35E-03 6-Sep-10 5.71E-02 +/- 3.24E-03 13-Sep-o10 4.06E-02 +/- 2.73E-03 21-Sep-o10 4.36E-02 +/- 3.07E-03 128-Sep-10 5.23E-02 +1- 2.86E-03 API-5 FOURTH QUARTER Date Activi(N 5-Oct-10 6.31E-02l +/- 3.32E-03 12-Oct-10 3.29E-02 j/-2.45E-03 19-Oct-10 3.35E-021 +- .2.55E-03 26-Oct-10i 4.01E-02 +/-4 2.76E-03 2-Nov-10o 4.90E-02 +/- j2.97E-03 16-Nov-10 6.33E-02 +/- 3.42E-03 23-Nov-O 8.31E-02 +/- 3.91E-03 30-Nov-10I 6.14E-02 +/- 3.36E-03 7-Dec-10 5.02E-02 +/- 2.21E-03 14-Dec-10 6.81E-02 +1- 3.54E-03 21-Dec-10 6.92E-02 +/- 3.67E-03 28-Dec-10 3.17E-02_- .J2.46E-03 C-12

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)

API-i FIRST QUARTER Date Activity 6-janl-10 < 3.30E-02 13-Jan-10z < 4.30E-02 20-Jan-10W <,1-50E-02 27-Jan- 10. < I2.70E-02 3-Feb-10ý < 6.20E-02 9-Feb- 10 <3.40E-02 17-Feb-10ý < 2.20E-02 24-Feb-10;, <~ 3.60E-02 2-Mar-101 < 3.20E-02 10-Mar- 10 < 2.60E-02 17-Mar-101 <3.90E-02 23-Mar-10: <13.30E-02 30-Mar-101- <13.30E-02, API-i SECOND QUARTER Date I Activit7 6-Apr-10 < ý3.70E-02 13-Apr-10, [2.90E-02 20-Apr-100 < 3.60E 27-Apr- 10 <3.30OE-02 4-Ma-l <3.30E-02 I8May-l10 (aiI77 I25-May-10 < 4.20E-02{

- 1Ju40 < 3.80E-02 (a)8-Jun-101 <4.80E-02 15-Jun-0 1I.75E-02 j,22-Jun-10 (a) 29-Jun-10ý < 2.90E-02 (a) See Appendix D - Program Execution.

C-i13

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-1 THIRD QUARTER Date Activity 6-Jul-10 < 2.05E-02 13-Jul-10i < 1.20E-02 20-Jul-101 < 1.68E-02 27-Jul-10: < 1.65E-02 3-Aug-10 i< 2.18E-02 10-Aug-101 < 1.37E-02 17-Aug-10i < 1.81E-02 24-Aug-101 < 1.42E-02 31-Aug-10 <1.68E-02 6-Sep-10 < 1.38E-02 13-Sep-10 < 1.50E-02 21-Sep-10 < 1.76E-02

.28-Sep-10 < 2.00E-02 API-1 FOURTH QUARTER 5-Oct-10 < 1.22E-02 12-Oct-10 <[1.36E-02 19-Oct-o10 <t1.46E-02 26-Oct-10 < 2.10E-02 2-Nov-10 < 1.39E-02 16-Nov-10 < 1.31E-02 23-Nov-10 < 9.66E-03 30-Nov-10j <t1.61E-02 7-Dec-10 < 1.19E-02 14-Dec-lO10 < 2.08E-02 21-Dec-10 < 1.75E-02 28-Dec-10 < 1.87E-02 C-14

Fermi 2 - 2010 Annual Radiological Environmnental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)

API-2 FIRST QUARTER Je ~~Activity~

6-Jan- 10 < 3.90E-02 13-Jan-10;_ <13.40E-02 20-Jan-10; < I3.OOE-02 27-Jan-101 <14.30E-02 3-Feb-101 < 4. 1OE-02 9-Feb- 10: < 340E-02 17-Feb-104 < 2.80E-02 24-Feb-10i < 3.20E-02 2-Mar-10' < 5.OOE-02 10-Mar-101 <j 3.70E-02 17-Mar- 10 i< 3.80E-02 23-Mar-10' < 3.90E-02 30-Mar-10; <4.30E-02 API-2 SECOND QUARTER mit~e I ACtivilty

~~ArA <3.80E-,02, l3-Ar-1~ <3.60E-02 20-Apr-i10 < 3.80E-02 27-Apr-10j <4.20E-02

-Ma-l <4.20E-02 11-Ma 1 < 5.60E-02 18-MY- <<2. 6E-02' 25-May-10 <13 36E-02 1-un-10 <6640-E,E-02 15-Jun-10 -<5.70E-02 22-Jun-W0 < 5.30E-02 29-Jun-10, < 6.30E-02 (a) See Appendix D -Program Execution.

C-i5

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMH 2 AIR IODINE - 131 (pCi/cubic meter)

API-2 THIRD QUARTER F Dat Activity 6-Jul-10' < t.18E-02 13-Jul-10' < 1.20E-02 20-Jul-1 <I1.38E-02 27-Jul-101 <[1.65E-02 3-Aug-101 <I1.40E-02_

110-Aug-101 <I 173E-02 17-Aug- 10 1<i 161E-02 24-Aug-101 <i150E-02 31-Aug-101 <i167E-0 6-Sep-10 <j 1.18E-02 13-Sep-101 <12.50E-02~

21-Sep-101 < 1.09E-02

?8-ep-10 <11.27E-02 API-2 FOURTH QUARTER Date: IActivit 12-Oct- 10 < 1.50E-02 Oct- 10 < 1.63Y-02 26-Oet-1Wj < 1.511"-02 2-Nov-101 <-1.58E-02 I 16-Nov-101 < 1.08F-02 23-Nov-W0 < 1.93E-02 30-Nov- 10 <I1.51E-02 7-Dec- t0 <.2I 0 14-Dec-ltO0 < 2. 11E-02 F21-Dec-10~ < 1.80E-02 28-Dec-10 < 2.66E-02 C-i16

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-3 FIRST QUARTER Date Activity 6-Jan-10 < 3.40E-02 13-Jan-10 < 5.50E-02 20-Jan-10 < 2.40E-02 27-Jan-10 <I 4.20E-02 3-Feb-10 < 3.70E-02 9-Feb-10 < 3.50E-02 17-Feb-10 < 2.70E-02 24-Feb-10 < 3.50E-02 2-Mar-10 < 4.90E-02 10-Mar-10 < 3.10E-02 17-Mar-101 < 3.40E-02 23-Mar-10 <410E-02 30-Mar-10 < 3.40E-02 API-3 SECOND QUARTER I Date ActivitN 6-A-10 < 4.40E-02 13-Apr-10 < 3.20E-02 20-Apr-10 < 4.00E-02 27-Apr-10 < 3.10E-02 4-May-10 < 5.30E-02 1i-May- 10 <I 4.30E-02 18-May-10 < 4.30E-02 25-May-10 < 4.20E-02 l-Jun-10 < 5.10E-02 (a)8-Jun-l10 < 4.10E-02 15-Jun-10 < 4.30E-021 22-Jun-lot0 < 5.40E-02 29-Jun-10 < 6.70E-02 (a) See Appendix D - Program Execution.

C-17

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-3 THIRD QUARTER Date Activity 6-Jul-10; <1.49LE,02 13-Jul-10z <Il1.52E-02 20-Jul-10 < 1.67E-02 27-Jul-10: <I1.61E-02 3-Aug-101~ <~1.40E-02 Aug-102 < 2.01E-02 17-Aug40: <{ 1.56E-02 24-Aug-10: < 1.25E-02 31-Aug-101 < 1.66E-02_

6-Sep-101 < 1.75E-02 13-Sep-101 < 1,78E-02 j21-Sev-101 < 1,27E-02_

28-Sep-101 <[i. 02 API-3 FOURTH QUARTER L Date I civ 5-Oct-lu, <i 1.54E-02_

--12-Oct-10[ <t .61E-02 19-Oct-101 <1 1.65E-02 O,0,c-t--,1,0 <I 1.42E-02 2-Nov- 10 <, 1.58E-02 1--l6--N-ov- 10 <1. 11E-02 23-Nov- 10 < 2.i76E-02 30-Nov- 10 <2.25E-02 7-Dec- 10 < 1.62E-02 14-Dec- 10 <

<2.70F-02 21-Dec-10l L.54E-02 28-Dec-10 <, 2.56E-0 C-i8

Fermi 2 - 2010 Annual Radiological Environmnental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)

API-4 FIRST QUARTER Date Activity 6-Jani-10; < 3.20E-02 13-Jan-10; 4.~40E-02 20-Jan-101<24E0 27-Jan-10: <13_80E-02 3-Feb-101 <13.40E-02 9-Feb- 10 <13.70E-02

_17-Feb-10' < 2.60E-02 24-Feb- 10 < 4.90E-02 2-Mar-10' <14.00E-02 10-Mar-10' < 3.30E-02 17-Mar-10' <13.80E-02 23-Maqr-10: < 3.OOE-02 30-Mar-101 < 3.40E-02 APT-4 SECOND QUARTER

[--ate -- 7 Activit=

6-pr I~ < 3.3ff-o2 l3:Ap4O~ :2.30E-02 20-Apr-10, < 4.40E702 27-Apr-101 < 4. 101'-02 4-May-10l <3.80V~-02 11-May-10j < 4.30E-02 18-Mayr10 _<ý2.8OE-O2 25-May-161 <14.50E-02 1-Jun-101 -- 5.30E-02 n-IP10 <: 2.80E-02 15-Jun-101 < 4,30E-02 22-Jun-10,I --<ý4,50E-02 29-Jun-10? <6.20E-02 (a) See Appendix D - Program Execution.

C-i19

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)

API-4 THIRD QUARTER 13-Jul-10, I1.20E-02 20-Jul- 10: <,1. 18E-02 27-Jul-10, < 2.19E-02---

Aug-101~< 1.83E-02 10-Aug-101 <_ 1.60E-02 Aug-101 < 1.64E-02 24-Aug-10__ < 1.97E-02_

31-Aug-101 < 1.63E-02 6-Sep-101 < 2.19E-02 13-e-0i< 11.59E-02 21-Sep-101 <I1 33E-02 28-Sep-10 1 3E0 API-4 FOURTH QUARTER Date I Activit.

5-Oct-101 <1 1.48E-021 F~1.5E-021 19-Oct-101 <1 1.53E-02 26-Oct- 101 1_.9 2 2-Nol-10, L.E0 16-Nov-101 < 7.87E-03 230-Nov-101 < v9E-021 7-Dee-iO <J .6-2 14-Dec-10I Ii8E0 21-Dec-10l <I 9.58E-031 28-Dec-101 <i 2.22E-021 C-20

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)

API-5 FIRST QUARTER F Date I Activity --

6-Jan-10. <<3.OOE-02 13-Jan-10,_ < 3.70E-02 20-Jan-10 < 3.OOE-02 27-Jan-10i <~ 2.80E-02 3-Feb-101 <3.90E-02 9-Feb- 10 <4.OOE-02 17-Feb-101 <1/2240E-02 24-Feb-1t0 <, 3.70E-02 2-Mar-101 <14.80E-02 10-Mar-10 <1~7E0 17-Mar-10" < 3.90E-02 j23-Mar-10 I< 4.70E-02 L30-Mar-10' <1 3.60E-02 API-5 SECOND QUARTER Date Activit 20Apr-10 < 4.10 E-021 27-Apr-101 < 2.70E-021 11-May-10~ <,6.60E-02

-1&

r8Ma <,3.10E-02--1 125-May-101 _< 3.80E-02I 1-Jn-1~ <6.80E-021 1(a)8-Jun-10: ~.3E0 1-5,-Ju T,in-10, < 390E-02' 22-Jun- 10 <14.80E-02

-.,2,9-Ju,n-l,0101, -< 6.90E-02 (a) See Appendix D - Program Execution.

C-2 1

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE -131 (pCi/cubic meter)

API-5 THIRD QUARTER 2Date Activity ]

6-Jul- 10~ <11.36E-02 20-Jul-10[ <~.7E-02 27-Jul-102 <1.26E-02 3-Aug-101 < 1.61E-02 10-Aug-102 < 1.58E-02 Aug-101 <I 1.31E-02 24-Aug-10: <L1.87E-02 31-Aug-10 __<_1.62E-02 6-Sp-10 < 1.72E-02 13Sp10' _< 1.70E-02 2

1-Sep-101 < 2.14E-02 28-Sep-101 <1 1.45E02 I API-5 FOURTH QUARTER Date ctivit 5-Oct-lO0 < 2.OOE-02 12-Oct-lo0 <12.17E-u2 26-Oc-101<,1.51E-02 2-Nov-i1O .6E0 16-Nov-10i j26E-02 23-Nov-10ý I i. 88E-02 30-N ov-10 <2 0 5E-0 7-Dec- 10I <1.43E-02 14-Dec-10 <I 1.86E-02 2 1-Dec-o 1 I138-0 28-Dec-lO "<ItiiiE'-'62 C-22

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-1 (indicator)

(pCi/cubic meter)

Nuclide First Quarter (a)Second Quarter Ba-140 < 4.80E-02 < 7.10E-02 Be-7 1.02E-01 +/- 1.60E-02 1.11E-01 +/- 2.90E-02 Ce-141 <' 5.20E-03 <1 1.340E-02 Ce-144 <j 7.50E-03 -- < 1.30E-02 Co-58 I <1 3.OOE-03____ <j 2.30E-03j Co-60 < 2.10E-03 < 1.90E-03 Cr-51.. .... <. ....

5.30E-02.. 40E-01 .....

< ....1....

Cs-134 < 1.70E-03 < 2.70E-03 r

Cs-137 1.30E-03 4.00E-03 Fe-59 < 9.30E-03 <I 3.00E-02 1-131 < _-9.40E-02 (inicto <i____ 2.90E-01,--- i K-40 < 2.70E-02 < 4.60E-021 -

La-140 < 4.80E-02 - - < 7.10E-021 Mn-54 <. 2.0E-03 .... ,... - -^<I ^^5.10E-03

&.2 [ --- -- -

Nb-95~~ --

Nb-9 5 < 6.50E-03, <1 1.10E-02 Ru-103 3.80E-03 < 1.20E-02i Ru-106 <. 1.90E-02 <<2.90E-021 Zn-65 <, 4.30E-03i <' 1.10E-02j Zr-95i < 6.60E-03 < 1.70E-02j API-1 (indicator)

(pCi/cubic meter)

Nuclide Third Quarter Fourth Quarter Ba-140 < 9.70E-C03{_ < 9.88E-03 j Be-7 7.71E-02 +/- 9.31E-03 j 4.28E-02 +/- 8.70E-03 Ce-141 i < 2.20E-03 I < 2.20E-03 Ce-144 3355E-03< 4 36'3[E-03 Co-58 < 1.73E-03 < 8.34E-04 Co-60 < 1.51E-031 < 1.31E-03 Cr-51 < 2.02E-02 I < 1.75E-02 (Cs-134 < 1.34E-03 - <, 1.25E-03j Cs-137 < 8.20E-04J < 1.04E-03, Fe-59 < 3.06E-03 <I 3.54E-03 1I-131 <' 3.20E-02] <1 2.34E-02, iK-40 < 1.30E-02 < 2.10E-02 -

La-140 < 2.20E-02 - < 9.88E-03g Mn-54 < 1,37E-03 <1 1.13E-03 Nb-95 < 1.35E-03 <.. 1 42E-03 Ru-103 < 1.86E-03 - <. 1.92E-03 (a) See Appendix D - Program Execution.

C-23

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-2 (indicator)

(pCi/cubic meter)

Nuclide First Quarter (a)Second Quarter Ba-140 < 5.90E-02 < 8.20E-02l Be-7 1......21E-1.- 1.80E-02 1.65E.-01 +/- 2.80E-02 Ce-141 <1 4.90E-03 < 7.70E-03 Ce-144 < 5.40E-031 --- < 7.80E-03 Co-58 < 3.9OE-03 < 1.70E-03 Co-60 < 2.80E-03 < 3.90E-03 Cr-51 < 5.00E-02 < 1.50E-02 Cs-134 < 1.90E-03 < 2.60E-03 Cs-137 < 1.90E-03 < 3.70E-03 Fe-59 <, 1.20E-02 - <[ 2.20E-02 1-131 < 7.10E-02 8.80E-02 K-40 <. 2.50E-02 < 4.80E-02 ..

La-140 < 5.90E-02 < 8.20E-02 Mn-54 < 2.10E-03 < 3.40E-03 Nb-95 < 5.10E-03 < 2.80E-03 Ru-103 < 3.90E-03 <. 7.90E-03 Ru-106 < 1.80E-02f < 3.40E-02 Zn-6 5...........< 7.2 E-3........... < 7.9 E-03 Zr-95 < 6.40E-03 1 < 7.60E-03 API-2 (indicator)

(pCi/cubic meter)

Nuclide Third Quarter Fourth Quairter Ba-140 <I 4.57E-02 . I < 1.50E-02' Be-7 6.76E-02 +/- 1.09E-02 4.77E-02 +/- 6 87E-03 Ce-14 < 3.30E-03 .. " < 2.09E-03j Ce-144 I<. 5.24E-03 .. < 2.88E-03j Co-58 _ < 1.65E-03 ..... < 9.03E-04

< 1.15E-03

<o-60 < 7.23E-04 Cr-51 <- 1.78E-02i <. 1.57E Cs-134 < 1.44E-03

. < 1.14E-03

,Cs-137 < 1.05E-03 < 8.71E-04 Fe-59 < 4.71E-03 < 2.44E-03

-131 < 519E-02 2 E-02 K-40 <1 1.38E-021 i <I 4.80E-02[

La-140 1i53E-02 < 1.50E-021 n-54 < .7.05E-04

<1 9.37E-04j Nb-95 <I 1.70E-03 < 1 1....8E-03 Ru-103 <1 2.01E-03i <[ 1.32E-03 .

Ru-106 < 9.34E-03 7.62E-03 Zn-65 < 2.9.9E-03 <. 2.28E-03.

Zr-95 <- 2.58E-03 j < 2.32E-03i (a) See Appendix D - Program Execution.

C-24

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-3 (indicator)

(pCi/cubic meter)

Nuclide Fi-rst Quarter (a) Seco.n Quarter Ba-140 < 7 7.90E-02 < 2.70E-02 Be-7 9.70E-02 1.60E-02 1.16E-01/- 2.20E-02 Ce-141 < 4.40E-03 < 7,10E-03

,Ce-144 < 5.30E-03 8.601E-03 Co-58 <i 8.20E-04 < 5.20E-03 Co-60 <I 3.50E03 .... < 1.50-E-03 Cr-51 < 4.10E-02 6.50E-02 Cs-134 <1 2.10E-031 < 6.90E-04 Cs-137 < 2.50E-030E0 -3. < 2.40E-03 Fe-59 . < 1.10E-02 .- <I 5.50E-03 1-131 F-<

9.90E-02 <- 1.20E-01 K-40 I < 2.70E-...02 _. < 4.70E-02 .. .

Ru-106 2.00E-02 < 2.80E-02 Zn-65 < 4.80E-03, <1 1.10E-021 Zr-95 < 5.40E-03 < 7.40E-03 -

API-3 (indicator)

(pCi/cubic meter) lNuclide Third Quarter Fourth Quarter Ba-140 <5 3.37E-02 <1 9.04E-031 Be-7 7.29-02 +1- 9.04E-03 4.45E-02 +/- 6.22E-03 Ce-141 I< 2.40E-03 1 81E-03 Ce-144 <1 4.07E-03. < 3 31E-03 Co-58 < 9.10EI-04

• 1.2E-03 -

Co-60 <1 1.20E-03I < 1.22E-03 Cr-51 <1 1.80E-02 <, 1.75E-02j Cs-134 < 1.42E-034 < 1.14E-03 Cs-137 < 9.92E-04 < 8.53E-04 Fe-59 < 4.13E-03 < 1.91E-03 1-131 < 3.42E-021 < 2.41E-02 1K-40_ <` 2.09E-02 1 1.81E-02,

'La-140 < 1.45E-02 < 9.04E-03 Mn-54 . < 1.02E-03. < 9 967E-04**

Nb-95-- <- 1.55E-03 j < 1OE-03 Ru-103 <5 1.51E-03 0 -3 I <- 160E Ru-106 <8 .92E-03_ < 832E-03 Zn-65 <5 23.8E-03. <_ 1287E-030 Zr-95 <i 2.22E-03 < 2.27E-03 (a) See Appendix D - Program Execution.

C-25

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-4 (control)

(pCi/cubic meter)

Nuclide First Quarter (a)Second Quarter Ba-140 < 1.30E-02 <l 3 3.00E-02 Be-7 1.14E-011 +/- 1 50E-02a 1 57E-01 +/- 2.60E-02; Ce-141 <a 4.60E-031 7.90E-03 Ce-144 < 6.60E-03 < 8.90E-03 Co-58 < 3.40E-031 . i <1 4.20E-03 .

Co-60 < 2.60E-03 . < 4 .80E-03 Cr-51 < 4.90E-02i _____ < 6.10E-02i .

Cs-134 <l 1 80E-03 i < 2.80E-03' Cs-137 < 1.50E-03l < 2.40E-03 Fe-59 " <i 8.30E-03 < 22 2.20E-02 1-131 < 7.00E-02 ____ <} 1.30E-01 K-401 < 1.70E-02i ___ < 3.50E-02 .....

La-140 < 6 .00E-02 _ < 3.00E-02 Mn-54 <' 2 10E-03 < 3.30E-03 Nb-95 < 5.60E-03 <1 7.00E-03 Ru-103 <1 4 80E-031 < 8.50E-03 Ru-106 < 1.70E-021 < 2.90E-02+

Zn-65 <I 4.80E-031 I <- 7.70E-03 -

Zr-95. < 5.60E-03< i < 1 1E-02.

API-4 (control)

(pCi/cubic meter)

Nuclide Third Quarter Fourth Quarter Ba-140 <ý 3.54E-02 < 1.06E-02!

Be-7 1.07E-01 +/- 9.19E-03; 4.42E-02 +/- 5.67E-03 Ce-141 < 2.66E-03 < 1.75E-03 Ce-144 < 4.48E-03 < 3.23E-03 Co-58

-,~~~~..

<a. . 8.80E-04

. . . . .. ... .. .. .2 .....

<1 1.16E-03 Co-60 <, 9.73E-04 <1 9.96E-04 Cr-51 < 1.79E-02, < 1.54E-021 Cs-134 I < 1.38E-03 <1 1.19E-03 Cs-137 <a 8.08E-04 < 8.71E-04 Fe-59 <, 3.96E-03, < 2.85E-03 1-131 < 4.24E-02 < 2.28E-02 K-40 <. 1.82E-02. . <a 2.05E-02

,La-140<, 1.31E-02.,,a < 1.06E-02 Mn-54 <, 8.65E-041 < 1.09E-03 Nb-95, <. 1.53E-031 < 1.24E-03

'Ru-103 a <a 1.78E-03a < 1.30E-03 Ru-106 < 8.77E-03j < 7.92E-03 Zn-65 a.<a 2.02E-03 1 <i 1.64E-031 Zr-95 a<a 2.75E-03 < 2.44E-03 (a) See Appendix D - Program Execution.

C-26

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-5 (Indicator)

(pCi/cubic meter)

Nuclide First Quarter (a)Second Quarter Ba-140 <l 3.70E-02 < 5.40E-02 Be-7 1.80E-01 /- 1.80E-02 1.92E-01 /- 2.60E-02 Ce-141 < 5.10E-03i < 7.90E-03 Ce-144 <1 ...............

...... 6.30E-03 ei4i.............. <1 9.80E-03 Co-58 <1 3.30E-03 1 I < 3.80E-03 Co-60 <1 2.20E-031 < 3.30E-03, Cr-51 <1 4.40E-02 < 6.10E-02 Cs-134 < 1.70E-032 <] 3.20E-03 __

Cs-137 . <. 1 10E _ _ < 2 60E-03 Fe-59 " < 7.60E-03 __ <1 1.20E-02 1-131 < 6.50E-02 < 9.20E-02, K-40 < 2 40E-02j _ i < 3.50E-02 La-140 I < 3 70E-021 I -

< 5.40E-02 Mn < 1.50E-031 <I 3. 10E-03 Nb-95 < 5.80E-03, <~ 6 .80E-03 Ru-103 < 4.80E-031 < 7.30E-03 Ru-106 <j 1.80E-02j <1 2.80E-02 Zn-65 < 6.00E-03 <I 6.10E-03 Zr-95 < 4.50EI-031 < 6.90E-03 API-5 (Indicator)

(pCi/cubic meter)

Nuclide Third Quarter Fourth Quarter Ba-140 < 3.11E-02 < 8.61E-03 Be-7 7.65E-02 - 9.66.-03 8.364E-02 +/- 7.19E-03 Ce-141 < 2.42E-03 < 1.72E-03 Ce-144 < 4.01E-03 . - < 3.42E-03 Co-58 < 1.32E-03 <1 9.71E-04 Co-60 < 1.46E-03, <1 5.43E-04 Cr-51 < 2.52E-02i <1 1.40E-02 Cs-137 < 1.29E-03 <' 6.37E-04 Fe-59 < 3.28E-03 < 3.04E-03 1-131 <. 3.88E-02 2.05E-02 K-40 < 1.89E-02 -. < 1.53E-02 Mn-54 < 9.17E-04 < 5.17E-04 eNb-95 <iT1.46E-03r <1 1.24E-03 LRu-106 I<i 9.83E-03. <. 7.07E-03 lZn-65 < 1.81E-03 < 2.29E-03

,Zr-95 <j 1.83E-03 - < 1.70E-03 (a) See Appendix D - Program Execution.

C-27

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-2 (Indicator)

(pCi/liter)

Nuclide 21-JAN 25-FEB 18-MAR Ba-140 < 1.20E+01i <I 1.50E+01 <: 1.50E01 Be-7 <. 5.50E+01 < 7.00E+ 01 6. 0E+i 0 Ce-141 <i 9.30E+00 < 1.20E+ 0 < 9.40E+00 .

Ce-144 _ <. 310E+01 < 4.00E+01- <F 3.50E+01 Co-58 < 6.20E+00 < 9. 30E+0 < 7.40E+00i Co-60 < 6 7.10E00 0 0E +0--

O-- ............. ................................ i - < .........

9.20E+00 ................... < 1.20E+01i . .........,....................

Cs -1 3- - - --

Cs-134 < 6.00E+00 . < 8.80E+ 00 <.....7.50E+o00o Cs-137 <i 6.90E+00 . 8.20E+00 < 9.20E+00 Fe-59 I < 150E+01 < 1.80E+0 j <2.OOE+01 I-131 <i 9.20E-01 < 9.00E-O01j - 9.60E-o01i K-40 1 52E+03 +/- 6 80E+01 1.43E+03 +/- 7 .7OE+01 1.37E+03 +/- 8.70E+01 La-140 La-140 . < 1...20E+01 1.20E+01 ...- .... I<

<. 15 . .. / ..............

E1 1.50E+01 . ..- <.. 1..50E+01...

<1.50E+01 I - -.

Mn-54 < 6.00E+00 < 8.80E+00 < 6.40E+o00 7N-9<5 < 7 10E+00 < 1.50E+01. < 8.O.E+oo" 0 Ru-103 < 7.40E+00 < 10E+00 -- < 740--E+00 Ru-106 < --570E+0 < 670E+ < 8.OOE+01 Sr-89 < 6.O0E+0 < 6.00E+00.. . . < 7.40E+00 Sr-90 < 1<70E+060 < 130E+00I - < 170E+00 ..

Zn-65 < 1i.60E+0 1- i < 3.80E+01 < . 2 30E+01 Zr-95 -- 0I

.E+01 50E+0...1 6E1..

Nuclide 7-APR 6-MAY 27-MAY Ba-140 < 1.30E+011 <i 1.30E+01j < 1.40E+01 _

Be-7 < 720E+01 < 5.90E+01 < 5.80E+01 Ce-141 < i.*oE+o0 <i 9.80E+-00 < 1,*10i+1..

Ce-144 <. 3.70oE+-01 <-63.70E+0i - - < 3.70E +-01.

Co-58 < 1.00E+01 < 6.70E+00 < 620E+00 Co-60.................... 1.30E+01

< .... ... l8 <l 7.20E+00 - ' ' <<t 6.00E+-00

'""""""..... + ....... ...- .

Cs-134 970E+00 < 6.80E+00 < 6.20E+00 Cs-137 <i 1.20E+01 < 660E+00 < 610E+OO Fe-59 <i 2.40E+01i < 1.60E+01 < 150E+O 1-131 < 8.30E-01F+ < 9.20E-01 .<. 7. 60E-01..............

K-40 1.54E+03 +/- 1 1OE+02 1.53E+03 j6.80E+01 1.53E+03 +/- 6.50E+01 La-140 < 1.30E+01 < 130E+01 < .40E+01 Mn-54 < 1 00E+01 6 50E+00 < 8.90E+

Nb-95 < 8.30E+00 < 6.80E+001 < 8.30E+00 _

Ru-103 < 9.70E+00 < 80OE+ 001 < 8. _10E+00 Ru-106 < 8.00E+01 < 650E+01, < 6.50E+01 Sr-89 I < 7.50E+00 < 7 00E+00 < 6.50E+00 Sr-90 I < 1.80E+00 < 1.80E+001 148E+00 +/- 4.80E-01 Zn-65 I <. 2.60E+01 _ < 1.50E+01 < 1.60E+01 Zr-95 <.. . 1.70E+01I _< 1 0E+01 I 1I.0E+ 0

. ....... C-28 C-28

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-2 (Indicator)

(pCi/liter)

Nuclide 10-JUN 24-JUN 8-JUL Ba-140 < 8.90E+00 <j 1.40E+01 < 7.07E+00 Be-7 5.60E+01 < 6.60E+01 < 1.50E+01 Ce-141 < 7.40E+00 <' 1.20E+01 < 3.14E+00 Ce-144 < 2.80E+01 < 3.50E+01 j < 1.27E+01.

Co-58 < 5.60E+00 < 6.20E+00 < 1.82E+00 .

Co-60 < 7.40E+00 < 7.40 E+001 < 2.10E+0 Cs-134 < 5.80E+00 < 6.501E+00 < 2.27E+00 Cs-137 < 5.40E+ 00i. < 7.40E+00i < 1.95E+ 00 Fe-59 < 1.50E+01 < 1.40E+01 < 4.09E+00 1-131 < 9.00E-01i _< 9.30E-01 < 4.95E-01I K-40 1.42E+03 +/- 6.20E+01 1.66E+03 +/- 7.00E+01 1.46E+03 +- 7.15E+01

,La-140 < 8.90E+00 < 1.40E+01jI < 2.09E+00 Mn-54 <I 5.80E+00 < 7.80E+00 < 1.87E+00 Nb-95....7.-0E+00< .... <... 8.10 E+00WI Ii< 1 93E+ 00 1Ru-103 < 6.40E+00 < 8.70E+00 < 1.78E-+00 Ru-16 ........... <. 5.20E+01 < 6.70E+1 <.. 1.65E+

9 ...............

Sr-89 ...........

.......< 6.20E+00 ........... ....

. .......< 6.10E+00 ..... <1 1.07E+00:

i <I 1Sr-901.70E+00 <1 1.80Eý+00k < 6.12E-01

[Zn-65 <I 1.60E+O .1 < 1..60E+0ov1 <, 4.42E+00}

Zr-95 < 1.00E+01 i <I 1.30E+01i <i 3.26E+00 Nuclide 29-JUL 12-AUG 26-AUG Ba-140 < 1.02E+01 - < 1.31E+01 __ <i 1.18E+01 Be-7 i <1 1.93E+01* " <i 2.45El+01 < 2.29E+01 Ce-141 i <i 3.90E+00 <I 4.88EW00 1 < 4.75E+00 Ce-144 l . ..........

.2

.5- < 1.59E+01

+

... {. .

............ < 1.92E+01

- O - -- _ _T <I 1.90E+01 8 1E + 00* . .. . .. . .

ICo-58 < 2.33E+00 < 2.57E+001 < 2.81E+00)

Co-60 <_ 2.66E.+00 < 3.02E+00 < 2.56E+00 Cs-134 ... ......... 2.95E+-00 ........ ........... - < 3 7E oo .. ... ... .....

337E+00 350E+00 .+.... ..

Cs-137 < 2.53E+00 < 2.74E+00 - <1 2.97E+00 Fe-59 < 5.28E+00 < 5.76E+001 < 6.22E+00 1-131 <1 6.48E-01 < 5 47E-01 < 4.65E-01 K-440- __ i40E+t+/- 6 96E+01 .-.....-..-..... . 1 47E+03.- . ..........

. +/- . ...................

7..

7.32E+01 1.44E+03 - +/_1-17.26E+01 La-140 <1 3.28E+00.. < 3 82E+00 < 3.50E+00 Mn-54 < 2.56E+00 2 .60E+00 <. 2.69E+00 i .

Nb-95 < 2.48E+t00 < 275E+00 < 2.70E+00 Ru-103 u - o ..... .......... ............

i ................... ........... ..-- < ...

..... 2.82E+00 .....-.------- ---- < 263E+00 Ru-106 < 2.06E+01 < 2.25E+01 <1 2.28E+01i

^__ j- ^ ^ ^ .QQ ... ....-............-.

... . . . .......... . .... . -- ^..._ ......

Sr-89 < 1.29E+00 -----------

---

< 1.70E+00 i---*----- < 1.75E+00 Sr-90 1.24E+00 +/- 4 08E-01 < 1 73E+00 <i 1 71E+00_

• n-65 <.. 6.38E+.00 < 6.83E+00.. _.....--< 6.76E+00O

'Zr-95 <. 4 .21E+00. < 4.77E+00i < 486E+00 C-29

Fermi 2 -2010 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-2 (Indicator)

(pCi/liter)

FlNuclide 9-SEP _[23-SEP _ _ 7-OCT _

Ba-140 < 1.01E+1Ol <, 9.82E+001 < 1.02E+01 Be-7 < 2.01E+01 < 1.57E+01 < 1.88E+01 Ce-141 < 4.10E+00 < 3.30E.+0W0 . < 3.70E+00 SCe-144< 1.54E+01. i< 1.21E+ 01i <j 1.40E+01 Co-58 < 2.54E+00 < 1.96E+00 i < 2.33E+00 Co-60 <2.83E+00 < 2.24E400 < 2.69Et00 Cs-134 < 3.02E+ 00 < 2.3 6E+00 3.18E+00 Cs-i37 < 2.54E+00j < 2.48E+00 < 2.40E+00 Fe-59 <1 5.76E+00 < 4.59E+00 < 5.77E+00 I-131 < 5.08E-01 < 5.04E-01i < 7.85E-01 K-40 1.53E+03 +- 7.98E+01 1.46E+031 - 7.40E+01 1.39E+03 +/- 7.15E+01 .

4 .................. ...,.... "..

La-140 < 2.90E+00 < 2.55E+00 <, 2.66E+00 Mn-54 . < 22.55E-+00 j .1.92E+0W < < 2.30E+00 Nb95 i <95 2.51E+0* I < 1.93E+00i <i 2.50E+00 Ru-103 < 2.57E+00 < 2.01E+00 < 2.21E+00 Ru-106 < 2.12E+01o < 1.85E+01 < 2.10E+01, Sr-89 < 1.33E+00 < 1.58E+001 < 1.21E+00 Sr-90 < 1.27E+00 < 3.07E+00 < 1.04E+00 Zn-65 < B 6.40E+00i

.._a4.'

6E /.. <.. '

<1 4.83E+00 < 5.06E+00

+o ..{.....................

Zr-95 < ,s.34..

4.22E+00 <

<. 2 1.2E+ 00..... i < 3.49E+001

........... ...^

2.65

... +00 < 4.22E+00 Nuclide 18-NOV 16-DEC CBa-140 < 1.06E+01 <l 3.28E+00 Be-7 < 2.12E+o01 < 1.86E+01 iCe-i41.

• <I4.02E+00I ..I~ -I-.52 E+00 i Ce-144 <i .60E+01 <i 1.38E+O1 Co-58 - < 2.40E+00 < 2.45E+00 _

Co-60 < 282E+00 < 2.60E+0 RCs-134 <* 312E+00 < 2.65E+00I Cs-137 < 3.02ElO+00l < 2.37E+00 Fe-59 <* 5.40E+6-- j <1 5.30E+00 1-131 < 4.62E-01I < 9.55E-01 K-40 I 147E+-03 +/- 7.74E+01 -- 1.49E+03 jLa-140 i< 3.388+0 - < 3.28E+00 Mn-54 <, 2.44E+00i <, 2.39E+00 Nb-95 2.54+00 < 2.37E+W00 l Ru-103 < 2.59E+00 < 2.24E+00 jRu-106 < 2.06E+01, < 2.00E+01 Sr-89 <1 1i2E+00 <i.61E+00 Sr-90 < 1.35E+00§ <! 1.66E+001 IZni-65 < 6.i3E+00 < 6.14E+001 Zr-95 I 4.34E+00 4.14E+00I C-30

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Control)

(pCi/liter)

Nuclide 21-JAN 25-FEB 18-MAR Ba-140 < 1.30E+01 < 1.40E+01 <1 1.30E+01 Be-7 < 5.60E+01 < 7.10E+01 < 4.40E+01 I Ce-141 < 8.00E+0O < 1.20E+01 < 5.10E+OO Ce-144 < 2.80E+01 < 3.80E+01 < 2.20E+O01 Co-58 < 6.90E+00 . < 8.20E+00 . 6.00E+0.

Co-60 < 8.30E+0o0 < 8 80E+0.OO .. < 7.90E+00

-s 4-Cs-134 - <- 7. 00E+00 .. 1..........

-oo oo . . . . . . . . ..................... < 8.50E+00

.................................< 4.90E+00 Cs-137 < 6.90E+00 < 8.00E+0* < 7.10E.00.

Fe-59 < 1.80E+01 < 1.80E-01 <j 1.50E+01

_ < 1.30E+01 < 1.30E+01- < 1.20E+01 1-131 <i 9.30E-01 - 9.30E-01 < 8.70E-01 K-40 1.37E+03 +/- 7.90E+01 1.33E+03 +/- 8.10E+01 1 .31E+03 +/- 5.80E+01 La-140 1.30E+01 <1 1.40E+01 <. 1.30E+01[

'Mn-54.. <i 7.70E+-00 iE< 8.

860E+00 O <1 5.OOE+00.

Nb-95 < 7.30E+00I _ <_ 110E+01. <. 7.30E+00 -

Ru-103 < 630E+00 _ <I 9.10E+OO < 6.20E+00.

Ru-106 < 6.30E+01 < 6.40E+O01 . 4.40E 01 Sr-895.... ..........<< ......

6.60E+00 .+ <i 6.20E+00 << 7 .77000 E+ 00 .. ..

0o Sr-90 <ý 1.90E+00 < 1.40E+ 00 <i 1.80E+ 00 Zn-65 < 1.80E+01 < 2.00E+01 i <. +i .

^Zr-95 <. 1.30E+01 i <. 1.50E-O1 0- j - .<i 1.100E+01 Ba-140 < 1.10E+01 I <l 1.50E+01 I < 1.20E+01 iBe-7 < 5.10E+01I < 4.90E01i 01 < 5.70E 01 Ce-141 < 8.40E+00 < 8.00E+00 1__90E01I Ce-144 < 3.10OE+01 1 <1 2.70E+01 <! 3.10E+01 Co-58 I < 6.50E+001 < 6.60E+00 < 5.60E+ 00 Co-60 < 7.20E+00 <j 7.50E+00' <I 5.90E+00 Cs-134 s.-..3.. .. .... 00E -oo

< 6.30E+00 .C...........

.......... 66.20E+00

.... < ..... 1 ... ..... <... < 6.10E+00 .. ....

Cs-137 < 6.00E+00 < 6.40E+00 <1 5.70E+00 I-131 < 1.20E+01 < 1.20E+01 < 1.70E+01 1-131 <i 9.80E-01 j _ <j 9.60E-01 <1 8.00E-01 K-404 ' 1.33E+03 +/ -*6.90E+01 1.33E+031 6.70E+01 1.56E+03 +/ 60E+01 La-140 < 1.1OE+01i _ <i 1.50E+01 i 1.20E+01 i

-54 1 < 6.90E+00 ____ <: 6.30E+001 - - < 6.10E+00 INb-95 - < 7.20E+00 < 7.10E+00 <_ 6.70E+00 Ru-103 < 6.30E+00 < 5.90E+00 __ <1 7.50E+00 Ru-106 < 5.40E+01T _ < 5.70E+01 < 5.00E+01 Sr-89 < 7.50E+00 < 8.OE+00 < 6.20E+00 Sr-90 I <1 1.80E+00 _. < 1_.1OE+00 < 1.50E+00

!Zn-65 <. 1.50E+01 __ < 1.70E_E+-I01 ___ <j 1.50E+01 Zr-95 <j 1.20E+01 __ i< 1.20E+01 <i 1.00E+01 C-31

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Control)

(pCi/liter)

Nuclide [ 10-JJUN 24-JUN 8-JUL Ba-140 < 1.50E+01 < 1.10E+01 < 5.80E+00 Be-7 < 5.20E+01 < 4.70E+01 < 1.26E+01

!Ce-141 < 8.20E-+00' < 9.60E+001 < 2.36E+00 Ce-144 < 260E+011 -- < 3 10E+01 < 979E+00 Co.-58 < 7.20E+0O i < 6.20E+00 <i 1.54E+600 ICo-60. . <. 9. 10. IE+I-00 1. . <- 5.70E+00'i_.... . <.. 1. .90E+00 Cs-134. < 680E+00 i <- 530E+00i -- < 1 96E+00 Cs-137 . -< 7.00E+00 + < 5.20E+00_i <- 1.73E+.00 Fe-59 < 1.70E+01 < 1.20E+01 < 374E+00 1-131 <... 9.20E-01 <r 9 20E-01 i I. < 6.62E-01 .

K-40 130E+03. +/- j7.70E+01 1.52E+03 +- 5.50E+01 1.48E+03o +/-6.98E+01 La-140 < 1.50E+01 ' i < 1 1OE+01 < 1.68E+00 Mn-54 < 7.50E+00-I <1 520E+00i, <j 1.64E+00 Nb-95 < 820E+00I < 6.90E+00t < 1.60E+00 --

Ru-103 < 7.90E+00I <i 7.50E+001.................... ... -<< 1.43E+00

^ . 1,I-

--,-- - 0t ->-._........... _ 2.- -@7 - ........ .. -..............

<<<i._-

....750E+00 <<1..

^ - 6.80E+001 .E.00.....^

<1 ^ 01I ................-...-........

<. 1.06E+00

.Sr-89 IR-..106 e

Sr-90 9-. . . .., , ._^........

. 5_

1.54E+00 QQ[-

80E+01- .. .. .....- --

+/- 4 00E-01 . <

4..90E+019!

1 70E+001 1.43E+

<8 6.09E-01I IZn-65 < 1.80E+01 < 1.20E+01 <V 3.70E+00 Zr-95^ < 1.10E+01 < 9.30E+00i <1 2.77E+00 Nuelide 29-JUL 12-AUG -126-AUG_

Ba-140 < 1.01E+01 < 1.23E+011 < 9.37E4+00 IBe-7 < 1.94E+01 <- 2.12E+01 <_1.63E+01 Ce-141 < 4.02E+00 i < 433E+00- < 3.47+00 Ce-144 < E 158E+01 < 1.69E+01 iE <i 1.3I3E-+01 C<o-58 < 2.64E+00 < 2.80E+00 I< 205E+00 Co-60 < 2.63E+00 < 3.11E+00 - _ < 2.19E+00 Cs-134 I< 3.03E+00 < 3.53E+001 <{ 2.56E+00 -.

Cs-137 i <l 2.55E+00 <1 2.59E+001 <1 2.11E+00 Fe-59 1< 5.83E+00 < 621E+00i < 506E+00 1-131__ < 6.33E <' 6.83E-01 - <I 5.96E-01 K-40 1.49E+03 +/- 18 11E+01 1.45E+03 +/- 8.16E+01 1.48E+03 +/- I7.84E+01 La-140 < 3.06E+00j < 3.87E+00 - < 2.62E+00 Mn-54 < 242E+00, < 2.71E+00 < 1.98E+00 INb-95 < 2.41E+00 < 2.56E+00 < 1.96E+00 lRu-103 < 2 35E+00 < 2.67E+00 < 2.12E+00 iRu-106 <f 2.19E+01 <- 2.33E+01 <- 1.73E+01 Sr-89 < 136E+00 < 1.1OE+00 < 1.27E+00 SSr-90 <I 1.73E+00 < 1.60E+00 <i 1.74E+00 Zn-65 <- 5.85E+00 < 6.43E+00 <I 4.74E+00

'Zr-95 <.- 4.30E+00 < 4.49E+00 <l 3.58E+00 C-32

Fermi 2 -2010 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Control)

(pCi/liter)

Nuclide 9-SEP [23-SE1P 7-OCT Ba-140 < 1.06E+01 < 1.05E+01 < 1.33E+01 Be-7 < 2.06E+01 < 1.68E+ 01 < 2.28E+01 Ce-141 < 4.35E+00 < 3.62E+00 < 4.60E+001 Ce-144 < 170E+01 < 1.29E+01 < 172E+01 Co-58 < 2.58E+00 < 2.09E+00 < 2.52E+00 Co-60 < 2.75E+00 < 2 13E+001 < 3.00E+00 Cs-134 < 2.84E+00 __ < 2.48E+00 < 3 22E+00 577E+

<l" 2.53E+00 59.................... 00 """ -' -' < -- ^ ^j- ... ....

Fe:

Cs-137 < 2.16E+00 <0 289,_077 Fe-59 < 5.77E+00 < 4 56E+00 < 6.32E+00 1-131 < 4.59E-01 < 6.18E-01 <ý 6.77E-01 K-40 1.53E+03 +/- 7.60E+01 1 53E+03_+/- 8.06E+01 1.47E+03 +/ 8 18E+01 La-140 < 2.94E+00 <1 3.19E+00 <1 3.68E+00 Mn-54 < 2.31E+00 < 2 0 4E+00 < 2 -39+00 Nb-95 < 2.60E+00 <. 2 1-E+ .00i < 2.62E+00 Ru-103 <. 2.54E+001 < 2 08E+001 - <i 2.65E+00 Ru-106 I < 2.15E+0 180E+01 < 2.23.E+01 Sr-89 <I 1.49E+00j <. 1 76E+00 <.. 9. 25E-0 1 Sr-90 < 1.36E+00 < 335E+-00 - - 18E+00 Zn-65 < 5.78E+00 < 5.07E+00 < 6.88E+00 lZr-95 <4 4.39E+001 i <z 3 59E+0W < 4.84E+00 Nuclide 18-NOV 16-DEC Ba-140 < _1.12E+01 . <[ 3.16E+00 Be-7 <l 2.07E+01

.I.. < 1.91E+01.

ICe-141 < 4.47E+o00 --- - < 3.68E+00 Ce-144 I < 1.68E+013.. <. 1.45E+01 Co-58 <i 2.45E+-002 - . <i 2.31E+-00 Co-60 < 3.24E+00 ___ < 2.85E+00 Cs-134 <

c s-- ................

..... 3.23E+00

. 3- + . ......... < 2.52E+00 Cs-137 <1 2.74E+00 <1 2.97E+00 Fe-59 < 6.50E+00 < 5,69E+00 I-131 _ < 5,74E-01 < 7.68E-01 K-40 1.49E+03 +/- 8.28E+01 1.45E+03 +/- 763E+01 La-140 <. 2E+.00 ... < .3.16E+00 lMn-54 _ <1 2.60E+00E < 2.33E+00f -j--__-

Nb-95 _ < 2.63E+00i < 2.39E+00 35E+Op --

R-l-3 [<

Ru-103 35E+00 2 < 2.31E+00 Ru-106 - <l 2.16E+O1 - < 2.15E+-01 Sr-89 <r 1 69E+00 < 1.78E+00 Sr-90 <1 1 39E+00I __ < 1.37E+00 Zn-65 <_ 6 77E+00l 1.___ < 5. 96E+00-oo Zr-95 <j 4.56E+00 _____ < 4.22E+00 C-33

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 VEGETABLE ANALYSIS FP-1 (Indicator)

(pCi/kg wet)

Nuclide 29-JUL Broccoli 29-JUL Cabbage 26-AUG Broccoli Ba-140 < 2.69E+01 <l 3.69E+01 < 9.89E+00 Be-7 < 4.74E+01 <: 5.75E+01 <j 3.79E+l01

^Ce-141

^. _... . ..

. ..i 8.14E+00

. ............. ,..,,....< 1.01E+01

..... <j 3.63E+00 ....

ICe-144 < 2.90E+01O j < 3.75E+01! <j 1.02E+01 d ^ .,_.. i--<<1i-;/_56 Co-58

.^

0:60 6.12E+00 <i 7.12E+00 <i2.39E+00 .

5.............

... ......< 9.45E+00 4...-.... . ... <"3 Co-60 < 7.56E+00 < 3.22E+-00 2 -, _9 Cs-134 _ < 7.24E+00 < 9.40E+00 <1 3,27E+00 a-6Cs-137

......... -+g< 6.00E+00 6.1 ............

< 803E+001 . ......... < 390E+00 +-........ ..-.....-...... .......

Fe-59 < 1.41E+01 < 1 66E+0 ...... 36E+00 aK_-40___

I-131 ' < 1._02E+o I < 1.22E+01 _ <1 2.86E+00.

_ 3.57E+03 +/- 1 .81E+02 2 76E+03 +/- 1 58E+02 3.74E+03 +/- 2.00E+02 La-140 7 .70E+00 1 E+01 35E+00 Mn-54 < 5.98E+00 < 7.39E+001 < 2.57E+00

,Nb-95< 586E+00 < 7.61E+00-i <i 2.46E+00 Ru-103 <l 6.01E+00 <: 7.03E+00p <i 2.38E+00 Ru-106

- 3..

< 5.69E+01

. --- .65E +i01 ... ...

< 6.24E+01*

< ....1 90E +01 .

< 2.29E+01

<I ..2...

.......... ..........8.40E +00......

+0. . ....................

Z n-65 . .i < 1 r 9 5......................

< i_ 2 +0 ......................................................................

Zr-95 _< 1.12E+01 < 1.26E+01

< 4.34E+00I ---.........

3 E FP-1 (Indicator)

(pCi/kg wet)

Nuclide 26-AUG Cabbage IBa-140 < 9.69E+00 Be-7 . <. 2.50E+01+

Ce-141. <1 3.87E+0O ICe-144 <i 1.15E+01 Co-58 <

< 2.27E+00 ICo-60 < 2.72E+00 Cs-134 <i 3.55E+001 Cs-137 -< 4.31E+001 -

Fe-59 <- 5.47E+00i 1-131 < 2.74E+00 K-40 2.44E+03 +/-1147E+02 lLa-140 < 3.33E+00 jMn-54 <i 2.40E+00 iNb-95 <i 2.26E+00

!Ru-103 < 2.11E+00 Ru-106 < 2.12E+01 Zn-65 < 5.86E+00 Zr-95 < 3.98E+00 C-34

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 VEGETABLE ANALYSIS FP-9 (Control)

(pCi/kg wet)

Nuclide 29-JL Broccoli 29-JUL Cabbage I 26-AUG Red Cbbage Ba-140 <. 3.03E+01 < 3.58E+01 < 4.62E+ 1 Be-7 < 4,84E+01 < 6.09E+0l1 < 8.44E+O1 Ce-141 I < 8.48E+00 - 1.11E+Oii . < 1.54E+ 01 Ce-144 <l 3.32E+.01 < 3.91E+O01j <j 5.84E+ 01 i Co-58_ < 6.40E+00 <. 7.76E+00 .. I <i 107E+010 Co-60..... < 6.79E+00 < 8.67E+00l - < 1 22E+01--

Cs-134_ < 7.61E+00 < 9.41E+00i < 1 41E+01 Cs-137 < 6.90E+00 < 7.97E+00 j <I 1.21E+ 01

.a...

Fe-59 I-* --i

..... -6

-2 *_

< 1.56E+01j _

. Z ...5 ..........................

< 1.

-. .^---...-

.i.

f.

<1 1.74E+01 _

< 2.55E+I01 K-40 4.48E+03 +/- 2.16E+02 4.83E+03 +/- j2.52E+02 6.OOE+03 +/- 3.33E+02 La-140 < 1.02E+01 I 1__ 37E+01 < 1 58E+ 01 Mn-54 i < 6.33E+00 _______

< 7.50E+00

<l 1.08E+01 .....

Nb-95...............

I -< --

6.29E+00 Be-7

< 7.96E+00 < 1.22E+01 Ru-103 < 6.10E+00 < 7.26E+00 +-- .. < 990E+00

<..9.9.E+0.....

Ru--106 < 5.71E+01 < 7 02Es01< <1 9.226+01 IZn-65 <1 I59E+01 < 1.99E-i-01 < 2.97001 r-95 1.15E01 i. < 1.. .33E+-3013

... 6 <+ 1291E+01 FP-9 (Control)

(pCi/kg wet)

Nuclide 26-AUG Swiss Chard Ba-140 <_ 4.48E+01 i iBe-7 <; 7.47E+01 Ce-144 < 4.8 IE-+01

,Co-58 <: 9.69E+00

'Co-60 <i 1.7E+01I

[Cs- 134 < 1.18E+01li Cs-137 <: 1.06E+01

'Fe-59 < 2. 13E+01 -

J-131 <: 1.32E+01

]K-40 5.13E+03 +/- l2.76E+02

'La-140 < 1.41E+01i1 -i -

'Mn-54 <1 1.08E+01, Nb < 1-03E+i3 01 Ru-103 < 9.03E+00 iRu-106 < 8.69E+01

.Zn-65 <i 2.39E+01 Zr-95 < 1.76E+0 1 C-35

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-1 (Indicator)

(pCi/liter)

Nuclide 27-JAN 24-FEB 30-MAR Ba-140 < 1.30E+01 < 1.40E+01 <ý 9.50E+00 Be-7 <i 5.10E+01 <1 4.40E+01 I <1 5.00E+01 Ce-141 << 8.60E+00 < 8.50E+001 < 9.20E+00 Ce-144 <2.90E+01 < 2.90E+01 < 3.20E+01I Co-58 < 6.10E+00 < 6.E00E+00 5.80E+00 Co-60 lQr-51. .... < 8.80E+00... < 7.80E+00:

. ......... ,.^.............^^ ^^.^----.--__----^ . ....-...... < 6.30E+00 i Cr-51 < 5.20E+01 < 4.70E+01 < 5.OOE+01 Cs-134 < 6.00E+00 < 6.70E+00- <I 5.60E +00_

Cs:-i 37 . <..... +. ..< .8)E 0 ..._ _. . ......_..... .. . . j..... ...........0 E+6.0.

SFe-5i9 --

< 1----,....

60E+01 <. 1..3.0E+011. < 1.30E+66 .

GR-B 5.20E+00 +/- 1.20E+00 < 3.10E+00 _5.30E+00 +/- .1E+00 K.-40 < 1.10E+02 < 1..00E+02 < 7.7.0E.+1 La-140 I 1.30E+0 1 < 1.40E+01 < 9.50E+00 IMn-54 <. 7.00E+00 <, 5.30E+00 <i 6.40E+00.i Nb-95 < 8.00E+00 < 7.60E00i < 7.50E+00 iRu-103 I < 26.40E+00 < 7.E+0 <I 7.10E+ 00 Ru-106 < 6.30E+01 <* 6.10E+01 < 5.60E+01 Ir- 89 < 4.30E+00 I,__ < 4.50E+00 < 5.20E+00...

Sr-90 < 1.40E-+00I <i 1.40E+00. < 1.30E+00 . i Zn-65 <1 1.90E+01 < 1.70E+01 < 1.20E+01 Izr-5 i<I 9.90E+001 i1.10+oE1i < 1.10E+01 Nuclide 27-APR 31-MAY 29-JUN iBa-140 <i 9.90E+00 < 130E+ 01 J <l 1.30E+01 Be-7 <1 2.80E+01l < 5.00E+01? <1 2.80E+01 C-141 < 700E+ 00 < 7.80+00 < 570E+o00 Ce-144 < 1.60E+01 < 2.40E+01 <1 1-40E+01 FCo-58 < 3.70E+oo < 6.40E+0 ...... < 3.20E+00 .......

Co-60 < 430E+00 - -3....

< ..... 400E+00 .0 1 _. 3.50E+00 Cr-51 31OE+0il1 3< < 480-E+01 < 3.0_E+01F Cs-134 < 3.60E+00 < 6.10E+00 I < 3.10E+00

[Cs-137 < 3.50E+001 < 4.80E+00 < 3.00E+00 Fe-59 < 8.70E+00 < 110E+O1 < 9.00E+0 GR-B 3.80E+00 +/- 1. 1OE+00 3.57E+00 +/1- 9.OOE- 1 3.50E+00 +- 1,10E+00 K-40 . <-I 6.20E+01 <, 6.80E+01 1 < 5.50E+01.

I lLa-140 < 99.90E+00 1, <. 1.30E+01 .. <i 1.30E+01 Mn-54 < 3.20E+00 < 5.30E+00 <i 3.OOE+oo00 Nb-95 < 3.90E+-00 <. 6.70E+00 4 20E+00 Ru-103 < 4'.OE+ 00 < 5.9E0 0 .- i < 3.60E+00 jRu-106 <I 3.10E+01 - ,.<< 4.70E+01j I < 2.60E+01 Sr Sr-89 l.-0E+0

<6.10E+001

<iiisoE+ ... 0..... ..............................

. 4.90E+00 --i 1.7--o..+o...

< 5.20E+00 --..-.

Sr-90

.. ........ .. < 1.80E+OO

-. ...... ..i . <. .. .. 1.80E+00

....... .. ..... < 1.70E+00 Zn-65 8.90E+001 < 140E+01

_<1 <I 8.60E+00 Zr-95 <1 6.20E+OOI < 9.30E+00, <I 5.60E+00 C-36

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-1 (Indicator)

(pCi/liter)

Nuclide 27-JUL 31-AUG 28-SEP Ba-140 < 1.28E+01 j < 1.06E+01 < 1.09E+01 Be-7 < 1.57E+01 < 1.60E+01i < 1.48E+01 Ce-141 <3 3.45E+00 I <ý 3.67E+00 < 3.23E+00 Ce-144 1.08E+01 < 1.25E+01 < .1-0E+01I Co-58 <.1.76E+001 <1 _1.92E+001. <. 1.69E+00.

Co-60 < 1.62E+00 . < 2.15E+00i < 1.73E+00.

Cr-51 < 1.87E+o01 < 1.97E+01o ___ < 1.82E+01J Cs-134 < 1.96E+00! < 2.43E+00 <_ 1.99E+00 Cs-137 < 1.64E+00 < 2.64E+00W < 2.22E+00 Fe-59 < 3.83E+00i < 4.38E+001 < 3.50E+00.

GR-B < 2.46E+00 < 2.18E+00 _ <_ 3.17E+00 K-40 < 2.39E+Ol <___2.72E+01 < 2.31E+01 _

La-140_- < 4.b0E+;00 <; 3.22E-+00. < 3.75E+001 Mn-54 < 1.60E+00, < 1.96E+00i < 1.48E+00 Nb-95 < 1.77E+00 < 1.94E+001 <, 1.77E+00i Ru-103 < 2.05E+001 i < 2.07E+00 <j 1.97E+00j Ru-1066 < 1.51E+01 < 1.69E+01i < -1.42E+01 -

Sr-89 <_ 1.15E+00 i-

-- < 1.26E+001o . . . < 1.36E+00 -

Sr-90 < 1.43E+00: < 1.23E+00 <1 1 1.2I7 2E+/-;

Zn-65 < 3.37E+001 _ _ < 3.84E+-00 3.42E+00o i<

Zr-95 3.17E+00 O ___~~~~

Zr-95 j- ^

< ^3.54E+00o Q ---------- ^-

J ^<I 3.12E+001 --1E -_^<

Nuclide 26-OCT 30 NOV 28-DEC Ba-140 < 1.31E+ 01 < 7.45E+00 <j 2.39E+00 Be

-7 <' 1.84 E+01 < 1 60

. E+01 < 1.42E+01 Ce-144 <4 1.33E-01 < 1.16E+01i <i 1.12E+01 Co-58 < 2.14E+00 < 1.86E+00 < 1.63E+00 Co-60 <0 2.02E+00 < 1.97E+00, <4 1.64E+00 -

Cr-51 < 2.10E+01 < 1.56E+Oli < 1.54E+01I Cs-134 < 2.53E00 <1 2.20E+00 < 1.99E+00 Cs-137 I<1 2.19E+00 < 1.77E+00! <4 1.58E+00, Fe-59 < 4.26E+00 < 3.45E+001 < 2.97E+00 GR-B 3.45E+00 - *< 4.09E+00 +/- 1.21E+00 < 2.95E+ 0 K:-40 < 2.13E+01- <; 1.71E+.01 .. <' 1.64E+01 La-140 < 3.81E+00 < 2.69E+00 < 2.39E+00 Mn-54 <4 1.96E+00 < 1.78E+00 < 1.57E+00 Nb-95 < 2.22E+00 < 1.73,E+00.. <. 1.75E+00 .

Ru-103 < 2.24E+00 -- < 1.67E+00 < 1.73E+001 Ru-106 <; 1.75E+01I < 1.64E+01 I I <4 1.41E+01 Sr-89 < 8.00E-01 < 1.17.E+00 < 1.50E+00 Sr-90 <ý 1.37E+I00, < 1.34E+00 < 1.57E+00 Zn-65 < 4.51EE+00 < 3.73E+00 <4 3.21E+00 Zr-95 < 3.83E+100 < 3.08E+001 < 3.06E+00 C-37

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-2 (Control)

(pCi/liter) rNuclide J27-JAN 24-FEB 30-MAR Ba-140 < 1.10E+01 < 1.30E+01 < 1.50E+01 1Be-7 < 8.OOE+01 < 5.30E+01, < 5.1 E+l1 Ce-141 ... <, 1.20.E+01 8..1O.E+o00 8.4.0Eo+0 ICe-144 <, 5.00E+01 < 2.80E+01i < 2.80E+01 Co-58 < 6.00E+OO < 6.1 OE+-00 i < 6.80E+00

,Co-60 < 8.50E+00 - 5.70E+00 < 7.00E+00 Cr-51 < 7.00E+01 < 5.20E+01 < 4.90E+O1I Cs-134 < 9.30E+00 < 6.20E+00 < 6.50E+-00 Cs-137 < 5.60E+00I < 5.20E+00 < 7.10E+00 Fe-59 < 1.30E+01 < 1.10E+01 < 1.60E+01_

GR-B <<30E+00 4.30Eo+00i +/- 1.1. E+ < 00280E 1 K-40o < 1.1OE+02 < 3.80E+O1 < 9.80E+01, La-140 < 1,10E+01 .1

<130E+0 50E+

lMn-54 < 7.70E+00 < 5.80E+00 <i 6.60E+00l Nb-95 < 8.30E+00I < 6.80E+00. < 7.60E+00 iRu-103* I < 9.50E+00 I 7.00E+00 . <i 6.50E+00.

,^ ^ ... - .""-^ -^ ... ^ ^.............

... ^E.. 6+0 . .. ..

Ru-16 < 8.40E+01 <' 5.90E+O1 j <j 5,30E+1j ISr-89 < 4.10E+00 < 4.60E+00 <. 580E+00 ISr-90 < 1-30E+ <, 1.40E+00 j 1i50E+O0 Zn-65 -- < 1.80E+01 <1 1.40E+01 < 1.60E-1+01 Zr-95 < 130E+01 < 1.00E+01 < 1.30Et+01 Nuclide 27-APR I 31 MAY 29-JUN Ba-140 < 1.40E+01 < 1.50E+01 < 8.10E+00 Be-7 < 5.60E+01 < 4.10E+01 i < 2.30E+01 Ce-141 < 1.70E+01 < 7.80E+00 < 5.70E+00 Ce-144 < 340E+01 < 1.80E+01 < 1.30E+01 Co-58 < 7.00E+00U < 4.50E+00 <I 2.70E+00 Co-60 8.50E+00 < 4.70E+00 < 240E+

Cr-51 < 6.50E+01 <1 4.50E+01 < 2.80E+01 Cs-134 < 7.00E+00 < 3.70E+006 < 2.30E+00 Cs-137 < 6.50E+00 < 3.90E+00 < 2.20E+00 iFe-59 <- 1.40E+01 1.10E+01 .. <1 5.60E+00 GR-B < 3.20E+O00 3.11E+00 +/- 8.80E-01 < 3.00E+00 K-40 < 9.30E+01 < 5.80E+01 I< 3.70E+01 La-140 1.4E <140 1.50E+01 - < 8.10E+00 Mn-54 < 570E+00i < 3.70E+00 <j 2.40E+00

,^ ^

Nb-95 ,_>>,.^i-.^ ^ ^,j

<1 7.60E+00 ...........- --- o--- .......... <- 4.30E+00

< 5.90E+003 Ru-103 ..... < - 9.20E+00 2 o .~.. .. < 540E+OO . . ....... ........

< 4.60E+00 . ...

iRu-106 < 660E+01 < 3.80E+01 i < 200E+01 Sr-89 < 5.80E+00 - <, 4.90E+OOI _ <~ 5.20E+00

< "'"j...............................

-- "-*****--[--i 80E+00' ............

-.1.80E+00 ..........

Sr-90 ... I. < 1-7 s;-90 1.80E+OOW < 170E+00 Zn-65 <j 1.40E+01 1 < 1.10E+01 <I 5.20E+00l Zr-95 -20E+o..-i-..

i <. 7.40E+00 _ <i 5.-0E+OOL_

C-38

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-2 (Control)

(pCi/liter) ucide 27-JUL 31-AUG 28-SEP.

Ba-140 < 1.06E+01 < 9.73E+00 < 9.19E+00 Be-7 .<i 44E+01* < 1.59E+01h <i 1.33E+0ii .

Ce-141 <. 3.OOE+00 < 3.28E+001I 2...94E+00

<.1.. .

CCe-144 < 9.80E+00 < 1.15E+01 - < 1.01E+01..

Co-58 < 1.72E+00 ' <1 1.73E+00 < 1.49E+00 Co-60 <1 1.61E+001 <( 1.88E+00 < 1.68E+00:

lCr-51 '(< 1.77E+o01i__l __ < 1.86E+011 I- < 152E+01 .

Cs-134 < 1.82E+00 < 2.17E+00 - <K 1.86E+00 J Cs-137 < 1.57E+00 _ <I 1.80E+00 __ <W 1.51E+001

[Fe-59 I < 3.40E+00 < 3.77E+00 < 3.09E+00 GR-B 2.95E+00 +/- 9.90E-01 3.58E+00 +/- 101E+00 < 3.44E+00 K-40 2.23E+01 2< " < 2.69E+01 < 2.30E+01 La-140 _ < 3.59E+00 i <i 3.35E+00' <- 2.72E+00 _

Mn-54 ............ ,-< ---

E 6 Nb*-9 -...... < 1.46E+00

... ... < 1.64E+001

... l.................. .................................. .... ... 1<41E+00 L.... - - _.. _

Nb < 1.76E+00 < 2.01E+00 < 1.55E+00 . .. .

... <. 194E+00

....... 9 ............-

Ru-103

. . ... .u--.. ....

1.79E+00 ...... < 1.60E+00 Ru-106 < 1.37E+01 < 1.68E+01 I < 1.35E+01 Sr-89 < 9.73E-01 <t 8.71E-01 < 1.75E+00 Sr-90 < 1.83E+00 1.21E+00 < 1.30E+00 Ba-140 _ <l 1.09E+01 < 8.02E+00 <l 2.55E+00 Be-7 < 1.53E+010< . . 1.4.8E+01 ....... ...........

i 51E+01 C-141 < 3.36E+001 < 3.33E+ 00 < 2.O8E+00 I Ce-144 I < 1.19E+01 <c 1.19E+01i < 1.17E+-01 Co-58 -- <- 1.90E+00- - < 1.82E+001 i <- 1.71E+001 Co-60 < 1.85E+00 < 1.81E+00 I< 1.82E+-00 Cr-51 1.80E+ .0.. < 1.64E-*01i < 1.62E+.01 Cs-134 < 2.08E+00 <2.24E+00 < 1.87E-+00 Cs-137 < 1.81E+00 < 1.90E+00 < 1.77E+00 Fe-59 <. 3.73E+00. < 3.80E+00j < 3.53E+00-GR-B 3.53E4+00 /- 1.29E+00 < 3.41E+00q <~ 320E+O00 K-40 1<

2.57E+01I < 1.99E+o 01 < 1.49E+01 La-140 <, 3.20E+00 <ý 2.48E+00 , < 2.55E+00 IMn-54 <.. 1.82E+00.~ < 1.65E+00 ... < 1.162E+001 Nb-95 < 1.91E+0 0 < 1.97E+00 . < *i.oE+.00 Ru-103 < 2.14E+00I <. 1.72E+00 i < 1.71E+00 Ru-106 < 1.63E+01 < 1.74E+01 < 1.56E+01 Sr-89 < 8.56E-01 < 1.08E+00i < 1.32E+00

'Sr-90 <: 1.87E+00 < t1.30E+001 <1 1.56E+00, Zn-65 < 3.84E+00 < 3.66E+00 i <i 3.51E+00 Zr-95 < 3.46E+00< 3.08E+00 < 2.82E+00 C-39

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-2 (Control)

(pCi/liter)

NuclideCH 27-AN ]24-FEB 30-MAR IBa-140 < 1.40E+01j < 1.50E+01 <j 1.20E+O 10 Be-7 < 5.60E+O 1 < 6.10E+01 . <i 4.90E+ 01 lCe-141 <1 8.70E+00+/- < 1.20E+01: < 8.003E+00 Ce-144 <1 3.40E+O1- < 4.20E+01 - <I 2.80E+01j ICo-58 I 740E+00 T <: 7.00E+00 <~ 7.20E+00 lCo-60 < 7.10E+00 < 9.30E+00 < 8.00E+00 Cr-51 <i 5.50E+01j - < 7.10E+01i < 5.2E+01 Cs-134 < 6.40E+001 <: 6.80E+00. < 660E+00

[Cs-137 < 6.OOE+00E < 9.00E+001 < 5.30E+00 JFe-59 < 1.20E+01 - - <. 1.50E+-01! < 1.101E+01 K <- 850E+O01 < 9.50E+-011 < 8_70E+01 La-140 < 1.40E+01 i ... < 1.50E+01i < 1.20E+01 Mn-54 < 5.00E+00 <1 7.90E+00 < 5.90E+001 Nb-95 < 7.50E+OO < 7.1 E+00 < 7E.....

E Ru-103 < 7.50E+00 < 8.70E+00 < 7.90E+00 Ru-106 <. 5.80E+01 < 8.30E+01 < 5.90E+i01 ___

Sr-89 < 410E+00 < 4.30E+00 <1 6.10E+00 Sr-90 <1 130E+00f < 1.00E+00

<" . < 1.50E+o00 2ln-65 <t -1.30E+01p< 1I60E+O1 I - < 1- 7 OE+O1 ___

Zr-95. . < 1...2...E+01 ... .... 1........

30.E+01 . ........ . < 1..20E+1.

Nuclide 27-APR 31-MAY 29-JUN Ba-140 < 1.40E+01 <1.30E+01

<1 <j 1.30E+ 01 Be-7_ < 6.10E+0o1 --i - <_ 7.00E+O01i < 5.00E+01 Ce-144 I < 2.60E+01 <. 5.0E+o i.01I < 3.00E+01I Co-58 <1 740E+W I 880E+000 .................< 5.90E+00 ..........................

^o-.___.___

__ <___+_................

................ . . . - 0 + .......

Co-60 <.......

9.40 E+00 ...... < 700E+00 < 6.70E+00............

jCr-51 < 5.30E+01 < 8.00E+01 < 6.20E+O1

0. ................................

+1*......... ... .....................

Cs-134 K 4.. .< < 7.OOE+00 E 0{....

.1. .... .. ... i*<-.. < 851.E+0 0............ < 520E+00 ICs-137 < 7.80E-+00 < 9.20E+001 --- i <- 5 .1OE+OO Fe-59 < 1.50E+01 < 2.00E+1 <1 1.20E+01 X-40 < 1.00E+02 < 9.50E+01 < 7.20E+01 La-140 1.40E+01 < 1.30E+01 1 <1 1.30E+01

\Mn-54 <, 6.60E+00 < 7.70E+00 <ý 5.70E+0 rNb-95 <.. 7.10E+00 < 9.00E+00 < 6.50E+0 Ru-103 < 7.90E+00 < 1 10E+01 < 7.10E+00C

'Ru-106 < 6.40E+Oi1 <- 8.80E+01[ i < 5. 10E+01 Sr-89 < 5.60E+00 < 520E+00 < 5.10E+00 Sr-90 -< 1.70E+00 i < 1.80E+00 <- 1.60E+00 -

Zn-65 < 1.30E+01 < 1.90E+01 I1 < 1.00E+01 Zr-95 < 1.30E+01 < 1.50E+01 < 9.30E+00 C-40

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-2 (Control)

(pCi/liter)

Nuclide 27-JUL 31-AUG 28-SEP Ba-140 < 1.26E+01 < 9.97E+00 < 1.19E+01 Be-7 1 < .67E+01 < 1.54E+01 < 1 57E+01 Ce-141 <1 3.75E+00 < 2.95E+00 <i 3.49E+00 Co-60 < 1 67E+00 j- < 1 71E+ 00-- <- .......... .93E+00 Cr-51 < 2.04E+01 < 1.68E+01 < 131E+01 Cs-134 < 1j 92E+00 .<< 1.87E+00 2.21E+00 Cs-137 I < 1.72E+00I <1 1.80E+00 < 1.93E+00 Fe-59 I 4.01E+00 <l 3.67E+00 <l 4.20E+00, K-40 < 2.30E+01 < 2.56E+01 < 2.82E+01

.14

.O

...-.- ____._._._1 La-1 40 < 4.46E+00 < 3.52E+00 <i 4.07E+00 Mn-54 < 1.80E+00 _ < 1.62E+00 < 1.80E+00 Nb-95 < 1.92E+00 <; 1.74E+00 < 2.03E+00 Ru-103 <I[2.04E+00l < 1.69E+00 i < 2.00E+00 Ru-106 < 1.63E+01l <_ 140E+01 < 1.53E+01 Sr <. 1.54E+00 __ < 1 42E+00. < 1.14E+00-Sr-90 < 1.57E+00 _ <1 67E+00o < 1.21E+00 Zn-65 <1 3.62E+00 <1 3.01E+00 < 3.61E+00 Zr-95 < 3.43E+0 <___307E+00 ... 3 17E+00 Nuclide 26-OCT 30-NOV 28-DEC Ba-140 < 1.24E+01 __ <l 1.02E+01 < 3.18E+00 Be-7 < 1.95E+011 __ _ < 1.96E+01 < 1.80E+01 Ce-141 < 4.18E+00 < 4.45E+00 <422E+00 Ce-144 <K 1.40E+01 < 1.73E+01 <i 1.56E+01 Co-58 <, 2.21E+00 < 2.02E+00 1.187E+00 Co-60 < 2.221E+00 < 2 E+00 <20E+00 C

Cr-51t .. ,...

s- 3 < 2.i0....I 2.22E+01 .....

. . ...... .... .p -+OOf

<< 2.17E+01

-:2 ..... ....... i ...<

< 207E+01 .................. ...........

Cs-134 < 2.57E+00 < 2.66E1+00 < 2.37E+00I Cs-137 < 2.12E+00 < 2. 28E+001 _ < 2 .OOE+00 --- ------

Fe-59 <, 4.79E+00 < 4.11E+00 <K 3.92E+00 K-40 1.92E+ 01. <. 2.18E+01j < 1i76E+ 01 .. .

La-140 < 4.66E+00 < 3.13E+00 < 3.18E+00 Mn-54 <K 2.12E+00 < 2.09E+00i < 2.02E1-00 i Ru-103 <... 2.25E+00o < 2.22E+001 < 2.18E+00 . ...

IRu-106 <1.96E+01 K< 2 07E+01 < 1.79E+01 Sr-89 34E-01 < 1.21E+0 i <1 .573E+00 ISr-90 < 11.iOE+00j < 1.80E+00 <j 1.45E+000

!Zn-65 < 4.19E+00 < 4.42E+00 < 3 99E+00 Zr-95 < 3. 85E00 < 3.97E+00 < 3.69E+00 C-41

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-3 (Indicator)

(pCi/liter)

Nuclide 27-JAN 24-FEB 30-MAR jBa-140 < 1.50E+01  ! <1 8.90E+00 < 1.30E+01 Be-7 < 6,30E+.01 <ý 3.60E+01 . 4.40E+ 01 Ce-141 < 1 10E+-01 < 4.40E+001 <i 7.00E+00 Ce-144 < 3.70E+-01 < 2.20E+01 < 2.40E+01 Co-58 < 8.00E+00 " < 4.40E+oo00 530E+00

< 5......

Co-60 <1 5,50E+00 <j 4.80E+00! <J 6.60E+00 Cr-51 <_ 6.00E+01 < 3.90E+01 <i 3.90E+01 Cs-134 <i 7 W60E+00 < 4.60E+00i .

< 540E+00i Cs-137 < 7.60E+00 < 4.10E+00 < 5.10E+00 Fe-59 <_ 1.70E+01 < 9.60E+00 _ - <j 120E+01 _

K-40 <1.20E+02

< < 7.10E+011 < 9.40E+01 La-140 < 1.50E+01o < 8.90E+00 < 1.30E+01 Mn-54 < 7.60E+00 < 4 30E+00 < 4.80E+00 Nb-95 < 830E+00 < 480E+00 < 6,50E+00 Ru-103 < 720E+00 < 4.80E+001 - < 5.90E+00 Re-59 3 - -- ------- . .............

.... ----- ---- < -- O E + 0 "

Ru-106 < 7.0E+01 i < 430E+01 _ < 4.90E+ 01.

Sr-89 < _4.30E+00 < 460E+00 __< 60E+00 Sr-90 <I 1.40E+00 < 1 40E+00 <- 1. -50E+0- __

- .Zn-65

..... <i 1.70E+01 ..... ....

... .....-........- 1 10E+O01U . ....-..

i...........-< "..-..

.......... _ ..<l_- 1.30E+01

.... .... .. 3_.- I.. .......-- J Zr-95 < 1.30E+01 < 8.00E+00- < 7.50E+00 Nuclide 27-APR 31-MAY 29-JUN Ba-140 <l 1.OOE+01 < 1.30E+01 < 1.30E+01 Be-7 <, 6.40E+01 <; 4.60E+j01 < 3.50E+01 Ce-141 < 8.30E+00 < 1.50E+01 < 1.10E+01 Ce-144 ^< ---

Ce^ 3.30E+01 4Tg ^

"" ^------

^ ---- ^ ~---^-- < 2.80E+

--- ---------- 1.60E+01 '^ 7^ .Z ,^

Co-58 < 720E+00 < 6,00E+00 < 4.60E+00 Co-60 < 7.50E+00 - < 5.90E+00 ------- < 4.40E+00 Cr-51 < 5.70E+01 <ý 5.10E+01 I < 3.50E+01 Cs-134 < 6.70'E+00 < 6.10E+ 00 3-.80E+00

-Cs-137 i< 7.10E+00 <. .5.20.E+ 00,. < 5.30E+00, Fe-59 < 1.30E+Oi < 1.30E+01 < 1.00E+01, K-40 <I 9.40E+01 < 7.90E+01 < 7.00E+01i La-140 <, 1.00E+O01 < 1.30E+01 <_ 1.30E+01 1iF__^

1 Mn-54io. 1_,. _-Y^ Eoo i-6.50E+00 5 50E+00 j--------*---------i<-~qx__.-^<I --^ ^ - - ----- - - <^_ 3.80E+00 .

SNb-95' <' 7.30E+00 < 7.10E+00 <1 5.50E+00, iRu-103 <l 8.20E+00 < 6.8 < 4.4E+00, 4.40E+00 TRu-106 <s 5.80E+01 < 5.20E+01 I < 3.40E+01, Sr-89 < 5.70E+00 < 450E+00 <1 4.50E+00, Sr-90 < 170E+00 < 1.60E+00 < 1.40E+00 Zn-65 <I 210E+01j 1.<iiOE+Oj11 8.50E+00 r-95 < 1.20E+01 < 1.00E+01 < 7.70E+00 C-42

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-3 (Indicator)

(pCi/liter)

Nuclide 27-JUL -  : 31-AUG 28-SEP Ba-140 <j 1.28E+01 < 1.31E+01 < 1.18E+01!

Be-7 < 1.56E+01 < 1.35E+01 < 1 75E+01 Ce-141 3.58E+00j < 2.96E+00W < 4.05E+00,

^4 4-I^ ,..! .'.^

Ce-144 < !...~~~~~

1.

---" K l 2--------------

1.12E+01,

---

< 9.17E+00 "----*-**- < 136E+011 Co-58 < 1.74E+00 < 1.45E+003 < 1.82E+00 1 Co-60 < 1.54E+00 < 1.43E+000- < 2 04E+00 Cr-51 <1 1.94E+01 < 1.78E+01 < 2.15E+01, Cs-134 <1 1.92E+00 < 1.72E-001 < 2 33E+00 Cs-137 < 1O60E+00 <. 1 48E+00 <- 193E+00 Fe-59 < 4.01E+00 < 3.35E+001 < 3 96E+00 K-40 < 2.51E+01 <I 2.12E+01 1 <* 266E+ 01 La-140 < 4.14E+00 < 4.44E+00 -- < 3-70E+00 Mn-54 < 1.64E+00 < 1.41E+00_ < 1 81E+00 Nb-95 <1 1.93E+00_ < 1.67E+00 <- 2.09E+00 Ru-103 < 1.93E+I00__ < 1.72E+W00 _ <1 2.11E+00 . ................... .

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

Ru-106 < " 1.51E+01i

. j ....... -

'.4 - ................................ <.F.. 1.24E+01 <j 1 69E+01 Sr-89 < 1.22E+00 < 9.83E-01 <1 i.23E+00 Sr-90 <. 1.94E+00. < 1.53E+00 - < i31E+00...

1.

lZn-65 <j 3.56E+00 _ j < 2__ 88E+00 ... i <j 3 41E+00 ....

r-95 < 3.46E00 _ < 2.69E+00 < 3 58E+00 Nuclide 26-OCT 30-NOV 28-DEC Ba-140 <I 1.50E+01 <i 9.20E+003 < 3.63E+00 Be-7 < 2.01E+01,_ < 1.67E+01i < 1.67E+01 Ce-141 <I 4.45E+00 l < 2.91E+001 i < 3.48E+00 Ce-144 <t 1.54E+01 i.. < 1.13E+01 .. < .

1 19E+01i ..

Co-58 < 2.31E+00 <l 2.18E+001 - < 1.84E+00 Co-60 < 2 39E+00 I < 2.54E- 00 <i 2.19E+00 Cr-51 < 2.53E+01 < 1.65E+01 <1 1.93E+01 ICs-134 <. 2_...77E+00 <. 2 42E+00' < 2.34E+00 Cs-1 37 < 2.27E+00 <: 3j51E+00 <- 185E+00 IFe-59.. <I 54.29E.+00. < 4 81E+00i < .50E+00 4

K-40 ......... .................6E+01 3.14E+01 . <... 1..92E+O1 La-140 <1 4.74E+00I < 3.02E+00 <* 3.63E+00 Mn-54 < 2.18E+o00 < 2.17E+00' _- <- 1.83E+00 Nb-95 <. 2.51E+00i . < 2 26E+00 j < 1.99E+00 Ru-103 < 2.48E-+00 < 1.92E+00 < 2.01E+00 Ru-106 < 1.95E-+01 .< 1.73E-+01 ..-..... -. . < 1i E+01 Sr-89 < 77.79E-01 <j 1 37E+00 . < 1.12E+00 iSr-90 < 1.00E+00 < 1.47E+00 < 1.30E+00 Zn-65 < 4.62E+00 .<< 4.99E+00 3.70E+00.

Zr-95 < 4.24E+00< 3.70E+001 < 336E+00 C-43

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 DRINKING AND SURFACE WATER QUARTERLY COMPOSITE SAMPLES Tritium (pCi/liter)

Station First Quater -Second Qua-ter DW-1 < 4.60E+02 < 4.20E+02 DW-2 I < 4.50E+02 < 4.20E+021 I I ..

SW-2 .i<o4,50E+02i < 4.105E+02 SW-3 < 4.50E+02 < 4O1E+02 DW-1 . .<+.I.....................................

9E O {<......................... 3.i3+O+2 i + i + + +. . .

Stationt Third Quarter Fourth Quartcr SW-3 ' 4.21E+ 02 < 5E+02 DW1 .. ............................... ........ 4.

C-44

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-1 (Indicator)

(pCi/liter)

Nuclide First Quarter Second Quarter Ba-140 < 1.30E+01 <l 1.30E+01 Be-7 < 4.90E+01i < 4.50E+ 01 Ce-141 < 7.80E+00 <6 6.60E+00 Ce-144 < 2.80E+01 <. 2.20E+O01 Co-58 < 5.70E+00I - -<-- 6.20E+00-..

ICo-60 <, 8.10E+00 < 6.OOE+00 Cs-134 < 6.20E+001 < 4.80E+OOI ICs-137 < 7.00E+00 6.80E+W00 Fe-59 < 1.40E+1 < 1.20E+01.

H-3 < 4.50E+021 < 4.20E+02I K-40 1.10 E+02 < 8.30E+01 La-140 < 1.30E+01 < 1.30E+01 Mn-54 < 5.70 E+001 < 5.OOE+00 Nb-95 < 6.60E+00

<i 59,0-E+OOI

< 5.80E+O00 Ru-103 <1 6.50E+OI00 < 5.90E+00. -

Ru-106 <.. 6.70E+01 4.80E+01j .

Zn-65 <& _31.60E+01I - < 1.OOE+01j Zr-95 < 1.1iE+ II < 9.50E+00 Nuclide Third Quarter Fourth Qtuarer Ba-140 < 1.11E+01 < 3.20E+00 Be-7 . <: 1.67E+01I - 1.71E+01 Ce-141 < 3.39E+00 - < 3.49E+00 Ce-144 j < 1.16E+01 < 1.28E+01}

Co-58 < 1 93E+00 < 1.93E+00 Co-6 0 < 2.17E+00 < 2.37E+00 Cs-134 < 2.31E+00 < 2.46E+00 Cs-137 < 1.83E+00I <1 1.89E+00' Fe-59 < 4.26E+00 < 4.19E+00 H-3 <3 3.24E+02 <, 3.36E+02 K-40 I < 2.74E+Ol01 < 3.05E+01 La-140 <J 3.75E+-00 - < 3.20E+00 Mn-54 < 1.81E+00< 1 81E Nb-95 1.97E00 < 1.98E+00 -------

Ru-103 < 2 0 5E+00 < 2.OOE+00 Ru-106 _ < 1.63E+01I _ <j 1.88E+01 Zn-65 < 3.72E+00 < 4.29E+00 Zr-95 i < 3.52E+00I i < 3.61E+00 C-45

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-2 (Indicator)

(pCi/liter)

Nuclide First Quarter Second Quarter Ba-140 1.30E+01 < 1.30E+01 Be-7 < 4.70E+01 <: 4.30EE+01, Ce-141 M

< 8.90E+00I < 8.80E+001 Ce-144 <~ 2.40E+Ol1 <1 300E+O 1 Co-58 < 6.50E+Ooj <- 5.90E+00!

Co-60 < 8.10E+O00o < 5.60E+00 Cs-134 <l 5.40E+00o I . < 6.00E+.00.

Cs-137 1 <i 6.60E+00 < 5.00E+00I SFe-59 _ < 1.50E+01 'I .... < i.50E+01 i H-3 < 4.50E+021 < 420E+02 K-40 < 1.OOE+02 8.00E+01 +/- 1.90E+01 La-1i40 < 1.30E+01- < 1i30E+_01 .

Mn-54 < 6.60E+00 < 6.30E+00 Nb-95 < 7.60E+00 < 6.20E+00 .. ..

Ru-103 < 6.70E+.00 <1 5 90E+00...-.....

Ru-106 < 6.90E+01 <I 5.60E+01 Zn-65 < 1.40E+01 < 1.30E+01 Zr-95 J 1.20E+01 iz*-*I~

l.1pE+O11 jlj~~~~ j~~lj

< _lrl~ ...

i_~....... ..

Nuclide Third Quarter Fourth Quarter Ba-140 < 9.66E+00 <l 2.62E+00 I Be-7 < 1.47E+0i1 <. 1.59E+Olj Ce-141 < 2.98E+00 < 3.06E+00

<I ~~~ ^ ^

^1.20E+01l - '- -- --

fC8 ~o ^~

Ce-144 ~ 1.07E+01

- ^ <

Co-58 < 1.59E+00 < 1.64E+00 ICo-60 < 1.92E+00 < 2.30E+00 ICs134 < 19"7E+006b < 2.20E+00I

< 167E+ 00<

.Cs-137 1.87E+00 Fe59 < 355E+00 < 3.44E+00 H3 < 3. 16E+02 <I 3.37E+02 K-4O < 2.55E+01 < 2.47E+01 La-140 < 3.74E+00 < 2.62E'+00 Mn-54 < 1.57E+i0 < 182E+00 Nb-95 < 1.75E+00 < 1.96E+00 Ru-103 <, 1.74E-+00i < 1.96E+00i lRu-106 < 1.46E+01 <, 1.49E+01I Zn-65 < 3.25E00 -- < 4.07E+00 Zr-95 < 3.11E+00 < 309E+00 C-46

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-3 (Indicator)

(pCi/liter)

Nuclide First Quarter Second Quarter Ba-140 <i 1.40E+01 < 1.30E+01

,Be-7 < 5.90E+01 <I 4.70E+01 Ce-141 8.60E+00

&< 1<

1.10E+O1I Ce-144 < 2,90E+01 <- 3.00E+O1I Co-58 < 8.20E+O00 <1 6.40E+001 Co-60 < 9.20E+00 <1 6.30E+00 Cs-134 < 6.90E+00 < 5.20E+00 Cs-137__ < 8.90E+00 < 5.00E+00 Fe-59 <i 1.60E+01 < 1.10E+01i He-3 . -- < 4.50E+02. < 4.20E+021 K-40 4 4 .. .....

< 1.20E+02 I < -8.60E+O1 La-140 a ........... < 1.40E+01 .........................< 1.30E+01.

4 0 E+ 01..................... .......................

Mn-54 < 7.10E+00 < 4.80E-00 !

Nb-95 <I 6.2 0 E+00 < 6 60E+00 Ru-103 < 8.10E+00 < 640E+00 -----------

Ru-106 <I 6.40E+01 < 5.10E+01 Zn-65 j < 1.70E+....._ ___01 < 1.30E+ 0 Zr<-95 < 1.20 E+ 01 l 1 __1.O00OE+O1l I__

Nuclide Third Quarter Fourth Quarter IBa-140 i < 3.00E+01 <j 3.72E+001 Be-1-7 < 6.10E+01- <I 1.75E+01O ICe-141 <. 3.40E+ 00. < 3.99E+00. ..

[Ce-144 <' 4.00E+OW <i 1.46E+01 Co-58 < 9.80E+00 < 2.15E+00 Co-60 < 4.50E+00+/- <1 2.14E+00 1Cs-134 8.90E+00j - <1 _2.47E+00l Cs-37 - < 5.70E+00 < 2.34E+00 Fe-59 1 4.50E+001 <, 4.70E+-00 1H-3 <i 3.90E+OOI < 3.37E+-02 K-40 < 3.00E+01 < 2.91E+01 La-140 < 3.30E+O00 < 3,72E+00 Mn-54 <* 3.60E+00 <l 2,07E+--00 Nb-95 < 1.30E+01 < 2.37E+00 Ru-103 <t 1.30E+O1 < 2.27E+00 Ru-106 <_ 5.20E+00 . < 1.81E+01 Zn-65 <- 1.50-E+01- < 4.28E+00 Zr-95 <[ 2.40E+02I <, 3.67E+00, C-47

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-4 (Control)

(pCi/liter) iNuchd First Quarter Secod Qater Ba-140 < 1.50E+01 < 9.40E+00 Be-7 < 5.00E+01 j <j 4.10E+01 Ce-141" <, 8.20E+00 - <" 7.50E+OO Ce-144 < 280E+Ot01 <1 2.40E+01 Co-58 <i 6.00E+00o _ < -

4.10E+00 Co-60 <l 8.50E+00 < 4.60E+00

< 6.40E +00<

Cs-134

ýCs-137

-i

• 9-i*e -* i...... .. l-*

i_* i:;i.................

<1 7.ooE+00 i--g3.70E+00.-

< 4.OOE+00 6E---..........-i.

Fe-59 <_ 1.50E+01 - 8.60E+00 IH-3 < 4.50E+02 - 4. 20E+02 K-40 10OE+02 66<.10E+-01 La-140_ < 150E+01 < 9.40E+00 Mn-54_ <

5.70E+00 I <I 4.20E+00 Nb-95 < 8.40E+00 I < 5.00E+00O Ru-103 _ < 630E+00 5 10E+001 Ru-106 < 5.50E+016 I <_ 4.40E+01 Zn-65 < 1.50E+-01 < 920E+00 Zr-95 <i 1.20E-01j < 710E00

^ 2 ........

---

._..........................1 O I Nuclide Third Quarter Fourth Quarter Ba-140 <I 1.24E+01 <1 3.89E+/-00 iBe -7 .. I <i. lT46+oi 19Ej1 .. j. 1.7E+01 Ce-1..41 <i 4.14E+0 ... < 353E+00 Ce-144 < 1.42E+01 <1. 39E+01 Co-58 < 2*4E+ 0E+00 jCo-60 < 2.11E+00 Go--7 < 224E+00 Cs-134 < 2.48E+00I < 2.07E+0 Cs-137 2."<

2oS05E+O i <2. 241E+p00 Fe-59 j<< 483E+00- < 3.90E+00E +OO

-3 <j 3.26E+02 < 3.89E+00 K-40 3.28E+01+/- 1i06E+01 <I 2.12E+00 La-140 < 4.59E+00 < 2.55E+00 hMn-54 < 1.95E+00 < 2.65E+01 Nb-95 < 2.26E-00 < 2.24E00 Ru-103 < 2.9E+00 < 178E 1.. .....

Ru-106 < 1.94E+01 < 3.33E+02 Zn-65 < 4.26Eoo+00 < 488E+00 Zr-95 I <i3.50E+00/ 3E

<. 3.67E+00 C-48

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 SEDIMENT ANALYSIS S-1 (Indicator)

(pCi/kg dry)

Nuclide 26-MAY 9-NOV Ba-140 < 1.20E+ 03 < 6.96E+03 iBe-7 B e:7..... ... ...<< 8.90E+02 9o^E * . . ..._ .. < 1.12E+03

.2..................................

Ce-141 < 2.20E+02 < 3.81E+102 Ce-144 < 5.30E+02 < 2.47E+02 Co-58 . <. 1.00E+02 _ < 8.85E+01 ...

Co-60 < 8.20E+01 < 4.38E+01' Cs-134 < 8..'2E+...1 00.

..... < 6.88E+01 Cs-137 < 8.50E+01.. < 4.74E+01 Fe-59 < 2.10E+02 __ < 3.44E+021 i K-40 6.89E+03 +/ 6.70E+0 1.19E+04 +/- 7.40E+021 La-140 < 7.20E+0321 < 6.96E+03j Mn-54 < 8.10E+01' < 5.57E+01 -1 _ _

Nb-95 < 1.30E+02 . <. 1.18E+02 ____

Ru-103 i1.40E+02 - <j 1.78E+02 Ru-106 < 6.20E+02 < 3.94E+02 Sr-89 __ __ 2.40E+02- < 2.65E+02 Sr-90 < 2.20E+02 i <1 1.03E+02 _

Zn-65 <1 2.80E+02 j < 1.24E+021 i Zr-95__ <. 1i.60E+02 - -..j.<j 2. 06E+02.

S-2 (Indicator)

(pCi/kg dry)

Nuclide J26-MAY 9-NOV Ba-140 < 1.30E+03 <l 9.01E+03-Be-7 < 8.00E+-02 < 1,08E+03V - -

-Ce144 < 420E+02] < 3.21E+02 Co-58 < 1.00E+02 < 955E+01t Co-60 j < 980E+01 i < 4.74E+01 Cs-134 < 8.30E+-01 I <I 6.42E-+01 Cs-137 n- --+ i JE

......<7.80E+012 ...............................................

<1 4.84E+01

........... +--

-Fe-59 -< 2.30E+02 _ <1 3.82E+02 K-40 2.56E+04 +/- 1 1OE+03 11.77E+04 +/- 9.68E+02 La-140 < 8.50E+02 < 9.01E+03 Mn-54 < 7.50E+01__ < 5.02E+01 Nb-95 <_ 1.70E+02 < 1.37E+02-Ru-103 < 1.30E+02 < 1.84E+02 Ru-106 < 5.50E+02 < 4.18E+02 Sr-89 <I 2.50E+02 <1 233E+02 lSr-90 <1 2.30E+02 <, 1.82E+02L Zn-65 < 4.50E+02 < 1.60E+02 Zr-95 <1 1.9_E+02 < 2.14E+02 C-49

Fermi 2- 2010 Annual Radiological Environmental Operating Report FERMI 2 SEDIMENT ANALYSIS S-3 (Indicator)

(pCi/kg dry)

Nuclide[ 26-MAY 19-NOV Ba-140 < 7.00E+02 l <i 7.16E+03 Be-7 < 3.90E+.02 < 8.37E+02 Ce-141 <' 8.30E+01' <' 2A41E+"02 Ce-144 < 2.10E+02, <ý 1.80E+021 Co-58 <. 4.60E+01j I <- 9,00E+01i Co-60 <i 5.60E+01 < 6.33E+01 Cs-134 <. 4.40E+I 01 63E+01 .

< 5..... .

Cs-137__ < 4.60E+01 <I 4.83E+01j Fe-59__ <. 2.00E+02 < 3.34E+02 __

K-40 1.28E+04 +- 6.70E+02 1 35E+04 +/- 18.59E+02 La-140 < 3.50E+02 <. 7 16E+03 Mn-54 < 450E+01 < 6.63E+01 _

Nb-95 l < 7 70E+0 < 1.24E+02 Ru-103 < 4.90E+01 - 1.55E+02 Ru-106 I <_ 330E+02j < 4.37E+02 Sr-89 _ <1 2.30E+02 < 2.56E+02 Sr-90 < 2.20E+02 1.69E+02

< 1t Zn < 1.50E+02 O2 < 1.54E+02j Zr-95 < 8.80E+01 < 1.92E+621 __

S-4 (Indicator)

(pCi/kg dry)

Nuclide 4-JUN 12-NOV Ba-140 < 3.50E+02 < 2.45E+02 Be-7 <~ 3.20E+02 < 5.05E+02 Ce-141 <- 6.40E+01 <i 9.70E+01 -

........ < 1.94E+02 Ce-144 e-4i Co- ..... < 1"80E+02 . . . 7,__^ ^ ......

Co-58 < 280E+01 493E+01 Co-60 < 260E+01 < 3.07E+01 Cs-134 < 3.40E+01 < 5.87E+01 -

ICs-137 < 3.00E+01 < 3.89E+01 Fe-59 < 9.40E+01 <- 1i33E+02 -

1K-40 1.60E+02 +/- 4.30E+02 1.04E+04 +/- 672E+02 La-140 < 3.30E+01 <I 2.45E+02 Mn-54 < 5.50E+01 < 4.50E+01 b-95 N'a < 09.............

1.09E+04 E +0i .... ._ _ _. ...._. < +

5.91E+01 Ru-103 < 4.20E+01 < 6.68E+01 R106 < 2.30E+02 < 3.39E+02 Sr-89 <. 2.50E+02 1.05E+02 ............

Sr-90 < 2.80E+02 _ < 8.78E+01 Zn-65 * < 1.40E+02 < 9.98E+01 7 . .... .........

_. . . .. - .

• i 8.. ^-t+

S < E+01C-50881E+

C-50

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 SEDIMENT ANALYSIS S-5 (Control)

(pCi/kg dry)

Nuclide 26-MAY 21-OCT Ba-140 <l 2.50E+03 l < 7.05E+03 Be-7 < 9.40E+02 < 1.49E+03 jCe-141 < 2.1OE+02 6.46E+02 Ce-144 < 4.30E02 < 3.03E+02, Co-58 <' 9.90E0 .+OlI 1.10E+02 .

Co-60 < 7.90E+01- <j 3.66E+O1 Cs-134 < 5.60E+o01 -< < 5.26E+01 Cs-137 < 7.30E+01,j 8.29E+01- +/- 1,71E+01 Fe-59 < 2,.50E+.02 < 4.84E+02 K-40 1.19E+04j +- 7.10E+02 - .23E+04 +/- 7.22E+02 La-140 < 3.70E+03, <1 7.04E+03, Mn-54 < 4.70E+01 1E 5......I Nb-95 I< .60E+02 < 1.49E+/-02 Ru-103 < 1.20E+02 < 2.61E+021 Ru-106 <i 5.20E+02, < 3.89E+021 Sr-89 < 2.50E+02 I . < 2.71E+02 Sr-90 < 2.40E+02 < 1.96E+02 Zn-65 < 2.20E+02, < 1.43E+ 02 60 Zr-95 1. E+0 2 i 2.58E+02 C-51

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-1 (Control)

(pCi/kg wet)

Nuclide 26-MAY Catfish 26-MAY Rock Bass 26-MAY White Bass Ba-140 < 3.20E+02 i < 1.70E+02 < 4.50E+01 Be-7 < 6.90E+02 < 4.60E+02 < 5.00E+02 Ce-141 < 1.20E+02 i < 6.80E-+01-- <i 7.10E+01 Ce-144 2.90E+ 0<i 2. O0E+02 < 2.10E+O02 Co-58 < 8.o00E+01 < 4.70E+01i I < 5.1E+1O Co-60 < 7.10E+0 -I- < 4.10E+01 { <j 5.10E+01 Cs-134 < 7. 7 0 E+01 4.40E+1 1< < 4.50E+01 Cs-137 <e 5.80E+01- < 5.60E+ 01 <1 4.90E+01 Fe-59 <; 1.80E+02 <ý 1.201E+3_02 < 1.60E+02, K-40 2.54E+03I +/- 450E+02 1 .7+02 +- 3 1OE+02 208E+03 +- 3.40E+02 La-140 < 3.20E+021 <i 4.60E+01i <- 50E+01' Mn-54 <1 6.80E+01 </ 5.70E3+01 < 4 10E+01 Nb-95 <1 9.80E+01 < 243E+03 < 7.80E+01 Ru-103 <i 7.40E+01 <; 5 50E+01 < 6.20E+01 Ru-106 <1 5.90E+02 < 3 3OE+02~ <i 3.70E+02.

Sr-89 <i 1.80E021 < 95oE+ 1 < 1 OE+02 Sr-90 1 10E+02I < 400E+01 < 6.80E+01 jZn-65 . < 1.50E+02 < 11E+02 < 1.40E+02 Zr-95 < 1.30E+02F <l 870E+-01 .1 10oE+02 Nuclide 26-MAY Yellow Perch 21-OCT Walleyc 21-OCT Sucker Ba-140 < 1.70E+02 i < 4.58E+03 < 4.88E+03 Be-7 < 5.50E+02 < 5.91E+021 < 8.28E+02 Ce-141 < 6.60E+01 < 2.09E+021 <1 2.71E+02 Ce-144 < 1.70E+02 *< 1.--

• • 41E+02 . 1.81E+02 Co-58 <. 5.20E+01 < 5.85E+01 <1 8.70E+01 FCo-60 <i 4.OOE+01Ii < 2.28E+01 < 2.85E+01-Cs-134" <i 4.00E+01 i <- 3.32E+01 <i 4. 1 .02E+

Cs-137 < 5.60E+01 < 2.48E+01 <I 3.77E+01 jFe-59 <I 1.50E+02 "- < 2.09E+ 02 < 2.40E1+02

K-40 2.59E+03 +/- 4 30E+02 3.41E+03 +/- 2.88E+02 2.97E+031 +- 2.83E+02 La-140 <I 1.70E+02I < 4.58E+03 < 4,88E+03 Mn-54 < 4.90E+01 < 2.55E+011 <, 3.88E+01 INb-95 <, 7.40E+010 < 6<.5E4:61 F_< 1.00E+02 Ru-103 < 4,00E+01 < 1.04E+021 <1 1.58E+02 Ru-106 < 530E+02 < 2.50E+02 I <I 3.69E+02 Sr-89 < 2.3002 < 1.83E+0202 <3+ 178E+02I Sr-90 < 1.40E+02 1 < 1.28E+02: < 1.38E+02 Zn-65 -< 1.20E+02 < 6.85E+01 i < 9.49E+01 Zr-95 < 9.70E+01I < 9.43E+O1, <ý 1.50E+02 C-52

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-1 (Control)

(pCi/kg wet)

Nuclicde 21-OCT Yellow Perch Ba-140 <, 5.72E+03 1Be-7 < 7.651 +02 iCe-141 <1 2.50E+02 Ce-144 < 1.65E+02 Co-58 < 6.53E+01*

Co-60 < 3.30E-A+01' Cs-134 < 4.22E+01i Cs-137l <i 2.60E+011 . .

Fe-59 < 2.42E+02 K-40 <i 2.72E+02 La140 <......5.72E+03

!Mn-54 i < 3.07E+01' Nb-95 < 6. 50E+01 i

.Ru-103....

< 1.38E+021 IRu-106 i <i 2.83E+021 Sr-89 < 2.55E+021 Sr-90 < 1.24E+021 jZn-65 < 8 70E+01i

!Zr-95 <: 1.21E+02i C-53

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-2 (Indicator)

(pCi/kg wet)

Nuclide 20-May Drum 20-MAY Redhorse Scke 20-MAY Walleye Ba-140 < 1.30E+02 < 3.40E+02 < 2.30E+02 l Be-7 < 430E+02 < 4.10E+02 < 4.10E+02 Ce-141 .]<8,30E+01 <i 8.60E+01 <1 8.70E+*01

'Ce-144 <I 2.00E+02 < 2.00E+02, <. 2.30E+02 co-58 < 3.8E+01 < 5.80E+01i <i 5.80E+01 ...

Co-60 < 48001 < 7.00E+01 < 5.00E+01 Cs-134 . < 4.20E+01 i <I 5.70E+i01 < 4.40E+O

[Cs-137 < 34.30E+01 < 470E+01 <j 2.80E+01 Fe-59 < 1.00E+02 <I 2.00E+02 i <I 1.70E+02 K-40 1 75E+03 +/- 3.20E+02 2.53h+03 4.30E+02 <j 9.40E+02 La-140 < 1.30E+02 < 340E+02 < 2.30E+02 .

Mn-54 < 4.20E+01i < 5.50E+01 < 4.40E+01 Nb-95 <i 6.50E+01 .<. 600.E+01 9.70E+

01 Ru-103 < 630E+01 < 6.50E+0 < 9.30E+01 Ru-106 _ < 4.50E-+02 - < 4.50E+02 <. 6.00E+02 Sr-89 < 1.30E+02 <1 1 50E+02 <1 7.20E+01I Sr-90 <_ 7.80E+01 < 8.60E+01 < 4.20E+ 01 Zn-65 < 1.00E+02l __ --- < 1.50E+02ý - <j 9.50E+01I Zr-95 820E+01

_I_ <18.20E+ I<

O<1.1E+__l__2-1 << 10.i +02 < 1.10E+02 Nuclide 20-MAY Wite Bass 2-NOV Northen Pike 2-NOV Waley Ba-140 < 3.40E+02 I < 1.65E+03 <l 8.81E+02!

Be-7 - < 4.60E+02 < 3.93E+02 < 223E+02,____

Ce-141. < 8 0..1 OE . . < 144E02 <I 6.67E+O t.1 J Cc-144 < 2. 10E+02 < 1.16E+02 <f5.10E+O1 a Co-58 < 6.60E+01 < 3.17E+01 <1 2.14E+01 I Co-60 < 5.00E+01 < 1.98E+01 < 9.18E+00 Cs-134 < 3.50E+01I < 2.08E+01 <a 1.05E+01 Cs-137 < 4.40E--01 < 1.77E+01 <j 1.06E+01 e-59 .1.27E+02

<... 1.40E+02 <. 7.63E+01 IK-40 2...20E+ 03 - .-3 70E+02 3.14E+.03 2.20+02 3.56E+03 +/- 2.20E+02 La-140 < 3.40E+.02 < 1.65E+03 < 8.81E+02 Mn-54 < 4.OE+O01 < 2.19E+01 <a 1.25E+01 Nb-95 <i 9.00E+0ol < 4.33E+01 < 2.31E+01 lRu-103 < 6.70E+01 < 643E+01 < 365E+01 Ru-106 < 4.50E+02 < 1.93E+02 < 8.94E+01 Sr-89 < 6.90E+01 < 2.73E+02< 2.59E+02 Sr-90 <a 4.20E+01 < 1.14E+02 < 9.53E+01....

Zn-65 < 1.80E+02 < 5.30E+01 3.42E+01 Zr-95 < 1.30E+02 <i 6.69E+01 * <, 4.07E+01 C-54

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-2 (Indicator)

(pCi/kg wet)

Nuclide 2-NOV Sucker 2-NOV Silver Bass 2-NOV Sheephead Ba-140 < 3.18E+03 < 4.23E+03 < 5.20E+03 Be-7 i< 6.94E+021 < 8.54E+02i < 9.38E+02 Ce-141 <1 2.19E+021 <, 2.81E+02 <2.69E+02 Ce-144 < 1.79E-02 < 2.21E+02z < 2.37E+O02 ICo-58 <i 5.91E+O I < 7.99E+O i < 9.24E+01 Co-60 <. 3.00E+01 < 4.07E+ 01 < 4.66E+01 Cs-134 < 3.77E+o1 < 5.07E+01 < 5.81E+01 Cs-137 < 3.12E+O01 < 4.18E+01 < 4.65E+O01 Fe-59 < 2.04E+02 < 2.57E+02 < 2.91E+02 K-40 3.21E+03 +/- 2.97E+02 3.08E+031 +/- 3.82E+02 I 3.o1E+03 +/- 3.78E+02

[La-140 < 3.18E+03 ......... 4.23E+031 <, 5.20E+03 IMn-54 < 3.26E+0l " -- <i 4.56E+0li <J 4.88E+01 iNb-95 < 7.04E+01 < 1.04E+02 < 1.03E+02 Ru-103 <, 1.09E+02 < 1.56EH+021 < 1.68E+02 Ru-106 < 3.01E+02 < 4.48E+02 < 4.23E+02 Sr-89 < 2.65E+02 <; 2.31E+02i - <1 2.72E+02, Sr-90 1.16E+02 < 1.06E+02 < 1.56E+02 Zn-65 < 7.81EE+01 < 1.03E+02 < i.14E+02r Zr-95 < 1.1OE+02i < 1.67E+02i <i 1.84E+02 C-55

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-3 (Control)

(pCi/kg wet)

NucHde 25-MAY Catish 25-MAY Drum 25-MAY Stcker Ba-140 < 5.40E+02! < 3.00E+02 <1 2.20E+02 fBe-7 <I 8.80E+02 < 4.40E+02 < 4.40E+02 Ce-141 < 1.30E+02 < 8.40E+01I <ý 7.40E+01 Ce-144 < 3.70E+02I < 2.20E+o02 <- 1.80E+02o Co-58 < 7.10E+01 < 5.30E+01i <, 5.50E+O01I Co-60 < 1.20E+02i < 5.00E+01 < 5.00E+01 tCs-134 < 9.50E+01 < 4.50E+0 1 < 4.50E+01[

Cs-137 < 9.60E+01 < 5.20E+O1 < 5.50E+01I Fe-59 < 2.20E+02 < 1.60E+02 < 1.70E+02 K-40 3.03E+03 +/- 6.10E+02 2.34E+03 +/- 3.90E+02 1.96E+03l +- 4.00E+02 La-140 <, 5.40E+021 <. 3.00E+02 <1 2.20E+02 Mn-54 8,00E+011---0E+0I< 5.70E+01+

N-95 < 1.40E+02i < 6<.70E+01 < 7.10E+01 Ru-103 < 1.50E+021 <, 7.10E+01 < 7.50E+O1

.u-106< 9.30E+02 < 5.10E02 < 4.70E+02...

Sr-89 < 8.20E+01 < 1.1OE+02F0 << 1.30E+02 Sr-90 < 5.30E+01 < 7.40E+01 <1 8.40E+01 Zn-65 240E02 1.40E+02 < 1.20E+0 Zr-95 < 1.70E+02 < 8.40E+O1 < 9.60E+01 Nuclide 25-MAY White Bass 25-MAY Wallee 25-MAY ite erch Ba-140S.......

.... . < 2.60E+02 ..... ......

........ <i 1.30E+02 < 1.80E+02 Be-7 < 3.80E+02 < 3.60E+02 < 5.70E+02 Ce-141 < 9.10E+O1 < 8.40E+01 - < 7.70E+01, Ce-144 - <j 1.70E+02 <, 1.80E+02 < 1.70E+02 Co-58 < 5.50E+01 ........ .... 5.30E+ 1 . 6 .60E+ ..

ICo-60 f < 5.70E+0i < 4.90E+01 < 5.80E+01 jCs-134 <i 5.20E+O1 < 4.40E+01 < 4.50E+01 Cs-137 < 2.80E+01 < 3.70E+01 <I 4.40E+01 IFe-59 < 1.40E+02 < 9.90E+01 < 1.10E+02 K-40 1.28E+03 +/- 3.70E+02 3.00E+03 +/- 3.50E+02 2.18E+O3 +/- 4.00E+02 La-140 < 2.60E+02, < 1.30E+02 < 1.80E+02, Mn-54 < 5.40E+olI < 4.00E+01 < 4.00E+01 Nb-95 < 7.10E+0-1 <: 5.90E+01 <i 6.20E+O1 Ru-103 < 7.50E+O1 < 6.20E+01 I < 6.50E+01j Ru-106 < 4.00E+02 <i 4.20E+02 <I 4.10E+02 Sr-89 < 2.00E+021 < 1.1*OE+02 < 1.60E+02 Sr-90 < 1.40E+02i < 7.10E+01 < 1.00E+02 iZn-65.. . ..

< 930E+O1

< 9.60E+01

< 1.50CE+-02 Zr-95 < 9.60E+O1 < 8.60E+01 < 8303 +0 11I C-56

Fermi 2 - 2010 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-3 (Control)

(pCi/kg wet)

Nuclide 24-NOV Cafish 24- NOV W-,flleye 24-NOV Yellow Perch Ba-140 < 5.89E+02 < 1.92E+02 < 3.06E+02 Be-7 < 3.16E+02 < 1.58E+02 1.49E+02 1

Ce-141 < 9.83E+01 <i 4.44E+01 < 4.88E+01 l L Ce-144 1<

1.18E+02' < 5.28E+01 < 6.15E.+.O.1.I ICo-58 <, 3.09E+01 < 1.95E+01 < 1.55E+01 Co-60 <I 2.30E+01 < 1.26E+01 1.32E+01 Cs-134 < 2.23E+01 < 1.39E+01 < 1.27E+01 Cs-137 < 2.14E+01 < 1. 18E+1 < 1.13E+ 01 Fe-59' < 1i05E+02 < 5.03E+01 <O 5.39E+01 K-40 2.47E+03 +/- 12.03E+02 4.00E+03 +/- 2.36E+02 2.84E+03 +/- 1.95E+02 La-140 <. 5.89E+02 < 1.92E+02 < 3.06E+02 Mn-54 < 2.14E+O01 < 1.23E+01 <i 1.13El01 Nb-95 < 3.60E-01 < 1.83E+01 < 1.93E+01 Ru-103 < 5.48E+01 < 2.38E+01 <. 2.62E+01*

Ru-106 < 2.07E+o02 <j 8.1 IE+o01 < 9.18E+01 Sr-89 < 1.31E+02 < 1.83E+021 < 1.81E+02 Sr-901< 1.13E+02 < 1.31E+02 < 1.16E+02 Zn-65 < 5.12E+01 < 3.69E+01l - <i 2.30E+o01 Zr-95 _< 657E+01 3.38E+01 < 2.93E+01 C-57

Appendix D Environmental Program Exceptions

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Environmental Program Exceptions 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 2010, missed samples were a result of missing field TLDs and air sampling equipment failure. The following sections list all missed samples, changes and corrective actions taken during 2010. 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 2010, two hundred eighty-four (284) TLDs were placed in the field for the REMP program and all but eight (8) TLDs were collected and processed.

• During the first quarter collection T-31 was found missing and was replaced with the next quarter's TLD.

• During the second quarter collection T-6, T-55, and T-52 were found missing and were replaced with the next quarter's TLDs.

• During the third quarter collection T-14, T-32,and T-47 were found missing and were replaced with the next quarter's TLDs.

• During the fourth quarter collection T-16 was found missing and was replaced with the next quarter's TLD.

Atmospheric Monitoring During 2010, two hundred sixty (260) air samples were placed in the field and all but two (2) particulate filter and charcoal filter was collected and processed. There were no changes to the Atmospheric Monitoring program during 2010.

• On 5/18/2010, air sample located at API-1 was not collected due to fuse failure. The fuse was replaced and the equipment was reenergized. For this reason, the second quarter composite sample is considered less than representative.

• All air samples collected on 6/8/2010, had reduced volumes due to loss of power during 6/6/2010 tornado event. All fuses were replaced and the equipment was reenergized. For this reason, the second quarter composite samples are considered less than representative.

• On 5/22/2010, air sample located at API-1 was not collected due to ground fault interruption (GFI) circuit failure. The GFI was replaced and the equipment was reenergized. For this reason, the second quarter composite sample is considered less than representative.

D-1

Fermi 2 - 2010 Annual RadiologicalEnvironmental OperatingReport TerrestrialMonitoring- None Milk Sampling - None GardenSampling - None GroundwaterSampling - None Aquatic Monitoring - None Drinking Water Sampling - None Surface Water Sampling - None Sediment Sampling - None Fish Sampling - None D-2

Appendix E Interlaboratory Comparison Data GEL Laboratories' Quality Assurance Programs

Fermi 2 - 2010 Annual Radiological Environmental Operating Report Interlaboratory Comparison Program for 2010 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. The following is GEL Laboratories' participation in an interlaboratory comparison program.

E-1

v Laboratories LLC 2010 ANNUAL QUALITY ASSURANCE REPORT FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

JANUARY 2010 - DECEMBER 2010 GEL LABORATORIES, LLC P.O. Box 30712, Charleston, SC 29417 843.556.8171

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 2 of 51 2010 ANNUAL QUALITY ASSURANCE REPORT FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

JANUARY 2010 - DECEMBER 2010 Prepared By: ,,/ February 15, 2011 Martha J. Harrison Date Quality Assurance Officer Approved By: / - February 15, 2011 Robert L. Pullano Date Director, Quality Systems

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 3 of 51 TABLE OF CONTENTS

1. Introd uction .................................................................... .......... ............................... ......

5

2. Quality Assurance Programs for Inter-laboratory, Intra-Laboratory, and Third Party C ross-C heck....................................................................................... ..6

3. Quality Assurance Program for Internal and External Audits.....................................7

4. Performance Evaluation Acceptance Criteria for Environmental Sample Analysis..........8

5. Performance Evaluation Samples....................................................8

6. Quality Control Program for Environmental Sample Analysis..................8..................8

7. Sum m ary of Data Results.......................................................... ....................... 9

8. Summary of Participation in Eckert & Ziegler Analytics Environmental Cross-Check Pro g ra m ................................................................................. ................................... 10

9. Summary of Participation in the MAPEP Monitoring Program....................................10

10. Summary of Participation in ERA (MRAD) PT Program.............................................10

11. Summary of Participation in the ERA PT Program...................................................11

12. Summary of Participation in the NY ELAP PT Program ............................................ 11

13. Quality Control Program for REMP Analyses........................ .............................. 12

14. Corrective Action and Request Report (CARR)................................................. 12 15 . Refe re nce s ................................................................................. .............................. 12

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 4 of 51 TABLE OF CONTENTS (CONTINUED)

LIST OF TABLES

1. 2010 RADIOLOGICAL PROFICIENCY TESTING RESULTS AND ACCEPTANCE CRITERIA

2. 2010 ECKERT & ZIEGLER ANALYTICS PERFORMANCE EVALUATION RESULTS

3. 2010 DEPARTMENT OF ENERGY MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) RESULTS

4. 2010 ERA PROGRAM PERFORMANCE EVALUATION RESULTS

5. 2010 ERA PROGRAM (MRAD) PERFORMANCE EVALUATION RESULTS

6. 2010 NEW YORK STATE DEPARTMENT OF HEALTH ENVIRONMENTAL LABORATORY APPROVAL PROGRAM (NYSDOH ELAP) PROFICIENCY TEST RESULTS

7. GEL 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

INTRA-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY MATRIX

8. GEL 2010 RADIOLOGICAL INTRA-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY MATRIX

9. GEL 2010 CORRECTIVE ACTION

SUMMARY

LIST OF FIGURES

1. COBALT-60 PERFORMANCE EVALUATION RESULTS AND % BIAS

2. CESIUM-137 PERFORMANCE EVALUATION RESULTS AND % BIAS

3. TRITIUM PERFORMANCE EVALUATION RESULTS AND % BIAS

4. IODINE-131 PERFORMANCE EVALUATION RESULTS AND % BIAS

5. STRONTIUM-90 PERFORMANCE EVALUATION RESULTS AND % BIAS

6. GROSS ALPHA PERFORMANCE EVALUATION RESULTS AND % BIAS

7. GROSS BETA PERFORMANCE EVALUATION RESULTS AND % BIAS

Lab aoratores LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 5 of 51

8. IODINE-131 PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 ANNUAL QUALITY ASSURANCE REPORT FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

1. Introduction GEL Laboratories, LLC (GEL) is a privately owned environmental laboratory dedicated to providing personalized client services of the highest quality. GEL was established as an analytical testing laboratory in 1981. Now a full service lab, our analytical divisions use state of the art equipment and methods to provide a comprehensive array of organic, inorganic, and radiochemical analyses to meet the needs of our clients.

At GEL, quality is emphasized at every level of personnel throughout the company.

Management's ongoing commitment to good professional practice and to the quality of our testing services to our customers is demonstrated by their dedication of personnel and resources to develop, implement, assess, and improve our technical and management operations.

The purpose of GEL's quality assurance program is to establish policies, procedures, and processes to meet or exceed the expectations of our clients. To achieve this, all personnel that support these services to our clients are introduced to the program and policies during their initial orientation, and annually thereafter during company-wide training sessions.

GEL's primary goals are to ensure that all measurement data generated are scientifically and legally defensible, of known and acceptable quality per the data quality objectives (DQOs), and thoroughly documented to provide sound support for environmental decisions.

In addition, GEL continues to ensure compliance with all contractual requirements, environmental standards, and regulations established by local, state and federal authorities.

GEL administers the QA program in accordance with the Quality Assurance Plan, GL-QS-B-001. Our Quality Systems include all quality assurance (QA) policies and quality control (QC) procedures necessary to plan, implement, and assess the work we perform. GEL's QA Program establishes a quality management system (QMS) that governs all of the activities of our organization.

This report entails the quality assurance program for the proficiency testing and environmental monitoring aspects of GEL for 2010. GEL's QA Program is designed to monitor the quality of analytical processing associated with environmental, radiobioassay, effluent (10 CFR Part 50), and waste (10 CFR Part 61) sample analysis.

This report covers the category of Radiological Environmental Monitoring Program (REMP) and includes:

• Intra-laboratory QC results analyzed during 2010.

• Inter-laboratory QC results analyzed during 2010 where known values were available.

SLaboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 6 of 51

2. Quality Assurance Programs for Inter-laboratory, Intra-laboratory and Third Party Cross-Check In addition to internal and client audits, our laboratory participates in annual performance evaluation studies conducted by independent providers. We routinely participate in the following types of performance audits:

• Proficiency testing and other inter-laboratory comparisons.

• Performance requirements necessary to retain Certifications

• Evaluation of recoveries of certified reference and in-house secondary reference materials using statistical process control data.

• Evaluation of relative percent difference between measurements through SPC data.

We also participate in a number of proficiency testing programs for federal and state agencies and as required by contracts. It is our policy that no proficiency evaluation samples be analyzed in any special manner. Our annual performance evaluation participation generally includes a combination of studies that support the following:

• US Environmental Protection Agency Discharge Monitoring Report, Quality Assurance Program (DMR-QA). Annual national program sponsored by EPA for laboratories engaged in the analysis of samples associated with the NPDES monitoring program. Participation is mandatory for all holders of NPDES permits.

The permit holder must analyze for all of the parameters listed on the discharge permit. Parameters include general chemistry, metals, BOD/COD, oil and grease, ammonia, nitrates, etc.

• Department of Energy Mixed Analyte Performance Evaluation Program (MAPEP). A semiannual program developed by DOE in support of DOE contractors performing waste analyses. Participation is required for all laboratories that perform environmental analytical measurements in support of environmental management activities. This program includes radioactive isotopes in water, soil, vegetation and air filters.

• ERA's MRAD-Multimedia Radiochemistry Proficiency test program. This program is for labs seeking certification for radionuclides in wastewater and solid waste. The program is conducted in strict compliance with USEPA National Standards for Water Proficiency study.

• ERA's InterLaB RadCheM Proficiency Testing Program for radiological analyses.

This program completes the process of replacing the USEPA EMSL-LV Nuclear Radiation Assessment Division program discontinued in 1998. Laboratories seeking certification for radionuclide analysis in drinking water also use the study. This program is conducted in strict compliance with the USEPA National Standards for Water Proficiency Testing Studies. This program encompasses Uranium by EPA method 200.8 (for drinking water certification in Florida/Primary NELAP), gamma

1Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 7 of 51 emitters, Gross Alpha/Beta, Iodine-131, naturally occurring radioactive isotopes, Strontium-89/90, and Tritium.

• ERA's Water Pollution (WP) biannual program for waste methodologies includes parameters for both organic and inorganic analytes.

• ERA's Water Supply (WS) biannual program for drinking water methodologies includes parameters for organic and inorganic analytes.

• New York State Department of Health Environmental Laboratory Approval Program Proficiency Testing Program for Potable Water (PW)

• Environmental Cross-Check Program administered by Eckert & Ziegler Analytics, Inc. This program encompasses radionuclides in water, soil, milk, naturally occurring radioactive isotopes in soil and air filters.

GEL procures single-blind performance evaluation samples from Eckert & Ziegler Analytics to verify the analysis of sample matrices processed at GEL. Samples are received on a quarterly basis. GEL's Third-Party Cross-Check Program provides environmental matrices encountered in a typical nuclear utility REMP. The Third-Party Cross-Check Program is intended to meet or exceed the inter-laboratory comparison program requirements discussed in NRC Regulatory Guide 4.15, revision 1. Once performance evaluation samples have been prepared in accordance with the instructions provided by the PT provider, samples are managed and analyzed in the same manner as environmental samples from GEL's clients.

3. Quality Assurance Program for Internal and External Audits During each annual reporting period, at least one internal assessment is conducted in accordance with the pre-established schedule from Standard Operating Procedure for the Conduct of Quality Audits, GL-QS-E001. The annual internal audit plan is reviewed for adequacy and includes the scheduled frequency and scope of quality control actions necessary to GEL's QA program. Internal audits are conducted at least annually in accordance with a schedule approved by the Quality Systems Director. Supplier audits are contingent upon the categorization of the supplier, and may or may not be conducted prior to the use of a supplier or subcontractor. Type I suppliers and subcontractors, regardless of how they were initially qualified, are re-evaluated at least once every three years.

In addition, prospective customers audit GEL during pre-contract audits. GEL hosts several external audits each year for both our clients and other programs. These programs include environmental monitoring, waste characterization, and radiobioassay. The following list of programs may audit GEL at least annually or up to every three years depending on the program.

• NELAC, National Environmental Laboratory Accreditation Program

• DOECAP, U.S. Department of Energy Consolidated Audit Program

• DOELAP, U.S. Department of Energy Laboratory Accreditation Program

• DOE QSAS, U.S. Department of Energy, Quality Systems for Analytical Services

• ISO/IEC 17025

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 8 of 51

• A2LA, American Association for Laboratory Accreditation

• DOD ELAP, US Department of Defense Environmental Accreditation Program

• NUPIC, Nuclear Procurement Issues Committee

• South Carolina Department of Heath and Environmental Control (SC DHEC)

The annual radiochemistry laboratory internal audit (10-RAD-001) was conducted in March 2010. Four findings, one observation, and two recommendations resulted from this assessment. Each finding was closed and appropriate laboratory staff addressed each observation and recommendation. The internal audit closed in June 2010.

4. Performance Evaluation Acceptance Criteria for Environmental Sample Analysis GEL utilized an acceptance protocol based upon two performance models. For those inter-laboratory programs that already have established performance criteria for bias (i.e.,

MAPEP, and ERA/ELAP), GEL will utilize the criteria for the specific program. For intra-laboratory or third party quality control programs that do not have a specific acceptance criteria (i.e. the Eckert-Ziegler Analytics Environmental Cross-check Program), results will be evaluated in accordance with GEL's internal acceptance criteria.

5. Performance Evaluation Samples Performance Evaluation (PE) results and internal quality control sample results are evaluated in accordance with GEL acceptance criteria. The first criterion concerns bias, which is defined as the deviation of any one result from the known value. The second criterion concerns precision, which deals with the ability of the measurement to be replicated by comparison of an individual result with the mean of all results for a given sample set.

At GEL, we also evaluate our analytical performance on a regular basis through statistical process control acceptance criteria. Where feasible, this criterion is applied to both measures of precision and accuracy and is specific to sample matrix. We establish environmental process control limits at least annually.

For Radiochemistry analysis, quality control evaluation is based on static limits rather than those that are statistically derived. Our current process control limits are maintained in GEL's AlphaLIMS. We also measure precision with matrix duplicates and/or matrix spike duplicates. The upper and lower control limits (UCL and LCL respectively) for precision are plus or minus three times the standard deviation from the mean of a series of relative percent differences. The static precision criteria for radiochemical analyses are 0 - 20%, for activity levels exceeding the contract required detection limit (CRDL).

6. Quality Control Program for Environmental Sample Analysis GEL's internal QA Program is designed to include QC functions such as instrumentation calibration checks (to insure proper instrument response), blank samples, instrumentation backgrounds, duplicates, as well as overall staff qualification analyses and statistical process controls. Both quality control and qualification analyses samples are used to be as similar as the matrix type of those samples submitted for analysis by the various laboratory clients. These performance test samples (or performance evaluation samples) are either

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 9 of 51 actual sample submitted in duplicate in order to evaluate the precision of laboratory measurements, or fortified blank samples, which have been given a known quantity of a radioisotope that is in the interest to GEL's clients.

Accuracy (or Bias) is measured through laboratory control samples and/or matrix spikes, as well as surrogates and internal standards. The UCLs and LCLs for accuracy are plus or minus three times the standard deviation from the mean of a series of recoveries. The static limit for radiochemical analyses is 75 - 125%. Specific instructions for out-of-control situations are provided in the applicable analytical SOP.

GEL's Laboratory Control Standard (LCS) is an aliquot of reagent water or other blank matrix to which known quantities of the method analytes are added in the laboratory. The LCS is analyzed exactly like a sample, and its purpose is to determine whether the methodology is in control, and whether the laboratory is capable of making accurate and precise measurements. Some methods may refer to these samples as Laboratory Fortified Blanks (LFB). The requirement for recovery is between 75 and 125% for radiological analyses excluding drinking water matrix.

Bias (%) = (observed concentration)

• 100 %

(known concentration)

Precision is a data quality indicator of the agreement between measurements of the same property, obtained under similar conditions, and how well they conform to themselves.

Precision is usually expressed as standard deviation, variance or range in either absolute or relative (percentage) terms.

GEL's laboratory duplicate (DUP or LCSD) is an aliquot of a sample taken from the same container and processed in the same manner under identical laboratory conditions. The aliquot is analyzed independently from the parent sample and the results are compared to measure precision and accuracy.

If a sample duplicate is analyzed, it will be reported as Relative Percent Difference (RPD).

The RPD must be 20 percent or less, if both samples are greater than 5 times the MDC. If both results are less than 5 times MDC, then the RPD must be equal to or less than 100%.

If one result is above the MDC and the other is below the MDC, then the RPD can be calculated using the MDC for the result of the one below the MDC. The RPD must be 100%

or less. In the situation where both results are above the MDC but one result is greater than 5 times the MDC and the other is less than 5 times the MDC, the RPD must be less than or equal to 20%. If both results are below MDC, then the limits on % RPD are not applicable.

Difference (%) = (high duplicate result - low duplicate result)

• 100 %

(average of results)

7. Summary of Data Results During 2010, forty-three radioisotopes associated with six matrix types were analyzed under GEL's Performance Evaluation program in participation with ERA, MAPEP, NYSDOH ELAP and Eckert & Ziegler Analytics. Matrix types were representative of client analyses performed during 2010. The list below contains the type of matrix evaluated by GEL.

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 10 of 51

• Air Filter

• Cartridge

• Water

• Milk

• Soil

• Vegetation Graphs are provided in Figures 1-8 of this report to allow for the evaluation of trends or biases. These graphs include radioisotopes Cobalt-60, Cesium-137, Tritium, Strontium-90, Gross Alpha, Gross Beta, and lodine-131. A summary of GEL's quality control for radiological analyses by isotopic analysis and matrix are represented in Table 8. Each LCS and DUP represents a batch of samples for each isotopic analysis. This summary contains the number of reportable quality control results for our clients.

8. Summary of Participation in the Eckert & Ziegler Analytics Environmental Cross-Check Program During 2010, Eckert & Ziegler Analytics provided samples for 106 individual environmental analyses. Of the 106 analyses, 99% (105 out of 106) of all results fell within the PT provider's acceptance criteria. The only analytical failure occurred with the analysis of Iron-59 in milk. For the corrective action associated with the Iron-59 failure, refer to CARR110209-542 (Table 9).

9. Summary of Participation in the MAPEP Monitoring Program During 2010, one set of MAPEP samples (MAPEP 22) was analyzed by the laboratory. Of the 66 analyses, 80% (53 out of 66) of all results fell within the PT provider's acceptance criteria. Thirteen analytical failures occurred: Plutonium-238 in water, Uranium-235 in filter, Uranium-238 in filter, Uranium-Total in filter, Americium-241 in filter, Cesium-134 in filter, Cesium-137 in filter, Cobalt-60 in filter, Manganese-54 in filter, Plutonium-239/240 in filter, Uranium-244/243 in filter, Uranium-238 in filter, and Uranium-238 in vegetation.

For the corrective action associated MAPEP 22, refer to CARR100617-496 (Table 9). The ICP-MS analysis of Uranium-235 and Uranium-238 failure was attributed to the use of the less vigorous digestion method (EPA Method 3050B). After contacting RESL, GEL discovered that they had used a more rigorous total dissolution process. The failure for Plutonium-238 was attributed to a data reviewer's error and lack of attention to detail to the region of interest that was not included in the data result. Approximately 400 additional counts should have been included. For the remaining isotopic failures, the error was attributed to analyst error and failure to follow the instructions from the PT provider.

10. Summary of Participation in the ERA MRaD PT Program During 2010, the ERA MRad program provided samples (MRAD-12 and MRAD-13) for 175 individual environmental analyses. Of the 175 analyses, 96% (169 out of 176) of all results fell within the PT provider's acceptance criteria. Six analytical failures occurred: Uranium-234 in soil, Uranium-238 in soil, Uranium-238 in vegetation, Plutonium-238 in water, Uranium-238 in water, and Bismuth-212 in soil.

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 11 of 51 For the corrective actions associated with MRAD 12 and MRAD-13, refer to corrective actions CARR100617-497 and CARR101210-527, respectively (Table 9). For MRAD-12, the ICP-MS analysis of Uranium-235 and Uranium-238 failure was attributed to the use of the less vigorous digestion method (EPA Method 3050B). After contacting RESL, GEL discovered that they had used a more rigorous total dissolution process. For Uranium-238 in vegetation, air and water, the failure was attributed to method sensitivity by gamma spectroscopy. Future PT analysis will be performed using a more sensitive method.

For MRAD-13, the failure for Bismuth-212 was attributed to a reporting error. The actual result (1660 pCi/kg) was within the acceptance range. The failure of Iron-55 was attributed to matrix interference. An additional recount with a smaller aliquot and fresh reagent rinses removed the interferant.

11. Summary of Participation in the ERA PT Program During 2010, the ERA program provided samples (RAD-80 and RAD-82) for 53 individual environmental analyses. Of the 53 analyses, 77% (41 out of 53) of all results fell within the PT provider's acceptance criteria. Twelve analytical failures occurred: Strontium-89 in water, Strontium-90 in water, Barium-133 in water, Cesium-134 in water, Cesium-137 in water, Cobalt-60 in water, Zinc-65 in water, Uranium (Natural) in water, Uranium (Nat) Mass in water, Strontium-90 in water, Cesium-134 in water, and Zinc-65 in water.

For the corrective actions associated with RAD-80 and RAD-82, refer to corrective actions CARR100318-487 and CARR100907-512, respectively (Table 9). For RAD-80, the Gross Alpha failure was attributed to a concentrated iron carrier. The Strontium-89 and Strontium-90 failures were attributed to the associated weights of the carriers utilized during the preparation and analysis.

For RAD-82, failures of the Gamma Emitters and the Naturals (Uranium) were attributed to analyst error and failure to follow the instructions from the PT provider. The failure of Strontium-89 and Strontium-90 was attributed to analyst error while diluting the sample.

12. Summary of Participation in the New York ELAP PT Program During 2010, the NYSDOH ELAP PT program provided 30 individual tests for radiological analysis. Of the 30 analyses, 83% (25 out of 30) of the results were within the PT provider's acceptance criteria. Five analytical failures occurred: Cesium-134 in water, Iodine-131 in water (two), Strontium-89 in water, and Radium-226 in water.

For the corrective actions associated with NY-337, refer to corrective action CARR101203-525 (Table 9). For Cesium-134, Iodine-131, Strontium-89 and Strontium-90, and Radium-226, the failures could not be determined. The laboratory continues to monitor results of internal quality control samples.

In addition, GEL (Lab ID# E87156, Lab Code# SC00012) maintained primary NELAP accreditation from the Florida Department of Health for the following methods in potable water and non-potable water. The radiological analytes and methods are listed below.

• Gross Alpha: EPA 900.0, EPA 1984 00-02

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 12 of 51

• Gross Beta: EPA 900.0

• Iodine-131: DOE 4.5.2.3, EPA 901.1, EPA 902.0

• Photon Emitters: DOE 4.5.2.3, EPA 901.1

• Radioactive Cesium: DOE 4.5.2.3, EPA 901.1

• Tritium: EPA 906.0

• Radium-226: EPA 903.1, EPA 1984 Ra-04

• Radium-228: EPA 904.0, EPA 1976 PP.24

• Radon: SM 20 7500 Rn, DOE 1990 Sr-02

• Strontium-89: EPA 905.0

• Strontium-90: EPA 905.0

• Uranium (Activity): DOE 1990 U-02, ASTM D5174-97, 02

13. Quality Control Program for REMP Analyses GEL's internal (intra-laboratory) quality control program evaluated 1590 individual analyses for bias and 1591 analyses for precision for standard REMP matrix and radionuclides. Of the 959 internal quality control analyses evaluated for bias, 100% met laboratory acceptance criteria. In addition, 100% of the 1591 results for precision were found to be acceptable. The results are summarized in Table 8.

GEL performs low-level analysis specifically for Tritium in water. A chart of low activity H-3 spike performance is provided in Figure 8. All 2010 analyses were within the acceptance criteria.

14. Corrective Action Request and Report (CARR)

There are two categories of corrective action at GEL. One is corrective action implemented at the analytical and data review level in accordance with the analytical SOP. The other is formal corrective action documented by the Quality Systems Team in accordance with GL-QS-E-002. A formal corrective action is initiated when a nonconformance reoccurs or is so significant that permanent elimination or prevention of the problem is required.

GEL includes quality requirements in most analytical standard operating procedures to ensure that data are reported only if the quality control criteria are met or the quality control measures that did not meet the acceptance criteria are documented. A formal corrective action is implemented according to GL-QS-E-002 for Conducting Corrective/Preventive Action and Identifying Opportunities for Improvement. Recording and documentation is performed following guidelines stated in GL-QS-E-012 for Client NCR Database Operation.

Any employee at GEL can identify and report a nonconformance and request that corrective action be taken. Any GEL employee can participate on a corrective action team as requested by the QS team or Group Leaders. The steps for conducting corrective action are detailed in GL-QS-E-002. In the event that correctness or validity of the laboratory's test results in doubt, the laboratory will take corrective action. If investigations show that the results have been impacted, affected clients will be informed of the issue in writing within five (5) calendar days of the discovery.

Table 9 provides the status of CARRs for radiological performance testing during 2010.

6Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 13 of 51

15. References

1. GEL Quality Assurance Plan, GL-QS-B-001

2. GEL Standard Operating Procedure for the Conduct of Quality Audits, GL-QS-E-001

3. GEL Standard Operating Procedure for Conducting Corrective/Preventive Action and Identifying Opportunities for Improvement, GL-QS-E-002

4. GEL Standard Operating Procedure for AlphaLIMS Documentation of Nonconformance Reporting and Dispositioning and Control of Nonconforming Items, GL-QS-E-004

5. GEL Standard Operating Procedure for Handling Proficiency Evaluation Samples, GL-QS-E-013

6. GEL Standard Operating Procedure for Quality Assurance Measurement Calculations and Processes, GL-QS-E-014

7. 40 CFR Part 136 Guidelines Establishing Test Procedures for the Analysis of Pollutants

8. ISO/IEC 17025-2005, General Requirements for the Competence of Testing and Calibration Laboratories

9. ANSI/ASQC E4-1994, Specifications and Guidelines for Quality Systems for Environmental Data Collection and Environmental Technology Programs, American National Standard

10. 2003 NELAC Standard, National Environmental Laboratory Accreditation Program

11. MARLAP, Multi-Agency Radiological Laboratory Analytical Protocols

12. 10 CFR Part 21, Reporting of Defects and Noncompliance 13.10 CFR Part 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants

14. 10 CFR Part 61, Licensing Requirements for Land Disposal and Radioactive Waste

15. NRC REG Guide 4.15 and NRC REG Guide 4.8

LaboratorleS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 14 of 51 TABLE I 2010 RADIOLOGICAL PROFICIENCY TESTING RESULTS AND ACCEPTANCE CRITERIA SampleAcceptance Known Range/

SapeSample Number QuarterlIYear Media Unit Analytel/ Nuclide GEL Value value Ratio Evaluation-RAD - 80 1"/2010 _ Water pCi/L Barium-133 73.5 72.9 61.0 -80.2 Acceptable RAD - 80 1"~/2010 Water pCi/L Cesium-i134 69.2 63.4 51.5- 69.7 Acceptable RAD - 80 1" /2010 _ Water pCi/L Cesium-137 118.0 120 108-134 Acceptable RAD - 80 1"/2010 Water pCi/L Cobalt-60 87.7 90 1 81 -101 Acceptable RAD - 80 1"'/ 2010 Water pCl/L Gross Alpha 51.3 42.5 22.0- 53.9 Acceptable RAD - 80 1 "t/ 2010 Water pCl/L Gross Beta 52.0 54.2 37.0-61.1 Acceptable RAD - 80 1/00 _ Water pCi/L Iodine-131 30.5 - 28.2 23.5-33.1 Acceptable RAD - 80 1"/2010O Water pCl/L Radium-226 16.9 17.8 13.2-20.3 Acceptable RAD - 80 1 /2010 Water I pCU/L Radium-228 20.4 18.2 12.3-21.8 Acceptable RAD - 80Not 0I 1A 2010 Water pCl/L Strontium-89 37.9 - 53.3 42.3- 60.9 Acceptable RAD - 80Not 1A

-8"V/2010 Water pCj/L Strontium-90 52.3 42.2 31.1 -48.4 Acceptable RAID - 80 1"/2010 Water pCi/L I Tritium 19200 18700 16400-20600 Acceptable RAD - 80 1/00 Water pCi/L Uranium (Nat) 49.0 50.2 40.7-55.8 Acceptable Uranium (Nat)

RAD - 80 1t/2010 Water ug/L Mass 67.3 73.2 159.4-81.4 Acceptable RAD - 80 1't /2010 Water pCl/L Zinc-65 213.0 210 189- 246 Acceptable E6922-278 2"' / 2010 _ Cartridge pci Iodine-131 9.02E+01 9.39E+01 0.96 Acceptable E6924-278 2' / 2010 Milk I pC!/L Iodine-1 31 8.25E+01 8.73E+01 0.95 Acce .ptable E6925-278 2 "d /2010 Water I pCi/L Iodine-131 1.OOE+02 9.61 E+01 1.04 Acceptable E6924-278 2 "d /2010 Milk pCi/L Iron-59 1.88E+02 1.78E+02 1.06 Acceptable E6925-278 2 n, /2010 _ Water pCl/L Iron-59 1.94E+02 1.79E+02 1.08 Acceptable E6924-278 2 n, /2010 Milk PCI/L Manganese-54 1.83E+02 1.78E+02 1.03 Acceptable E6925-278 2 nd/2010 Water pCl/L Manganese-54 1.90E+02 1.79E+02 1.06 Acceptable E6923-278 2 n, /2010 Milk pCU/L Strontium-89 9.73E+01 _1.31 E+02 0.75 Acceptable E6923-278 2n, /2010 Milk I pCi/L Strontium-90 1.38E+01 1.79E+01 0.77 Acceptable E6924-278 2n, /2010 Milk pCi/L Zinc-65 3.68E+02 3.45E+02 1.07 Acceptable E6925-278 2 n, /2010 Water pCi/L Zinc-65 3.72E+02 _3.48E+02 1.07 Acceptable E6924-278 2nId /2010 Milk pCl/L Cerium-141 2.01IE+02 2.02E+02 0.99 Acceptable E6925-278 2 Id /2010 _ Water pCj/L Cerium-141 2.04E+02 2.04E+02 1 1.00 Acceptable E6924-278 2" /2010 Milk pCi/L Cesium-134 2.41 E+02 2.53E+02 0.95 Acceptable E6925-278 2m / 2010 _ Water pC!/L Cesium-I134 2.56E+02 2.55E+02 1.00 Acceptable E6924-278 2d /2010 Milk pCi/ll Cesium-137 1.71 E+I02 1.79E+02 0.96 Acceptable E6925-278 2 "d /2010 _ Water pCi/L Cesium-137 1.81 E+02 1.81 E+02 1.00 Acceptable E6924-278 1 2"d /2010 1 Milk PCI/L Cobalt-58 1 2.03E+02 2.1.1E+02 0.96 1Acce .ptable E6925-278 2 Md/2010 Water pCl/L Cobalt-58 2.19E+02 2.13E+02 1.03 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 15 of 51 Acceptance Sample Sample Known Range/

Number Quarter/I Year Media Unit Analyte / Nuclide GEL Value value Ratio Evaluation E6924-278 2"d / 2010 Milk pCi/L Cobalt-60 2.47E+02 2.56E+02 0.97 Acceptable E6925-278 2n /2010 Water pCi/L Cobalt-60 2,67E+02 2.58E+02 1.03 Acceptable E6924-278 2n /2010 Milk pCi/L Cr-5i 5.54E+02 5.48E+02 1.01 Acceptable E6925-278 2n' /2010 Water I pCi/L Cr-5i 5.78E+02 5.54E+02 1.04 Acceptable E7054-278 2"d/2010 Milk pCi/L Cerium-141 2.61 E+02 2.61 E+02 1.00 Acceptable E7055-278 2n1 /2010 Water PCI/L Cerium-141 2.78E+02 2.63E+02 1.06 Acceptable E7054-278 2"' /2010 Milk pCi/L Cesium-134 1,76E+02 1.78E+02 0.99 Acceptable E7055-278 2d /2010 Water pCl/L Cesium-134 1,85E+02 1.79E+02 1.03 Acceptable E7054-278 2nd/2010 Milk pCi/L Cesium-137 1.61 E+02 1.58E+02 1.02 Acceptable E7055-278 2nd /2010 Water pC1/L Cesium-137 1.71 E+02 1.59E+02 1.07 Acceptable E7054-278 2,d /2010 Milk pCi/L Cobalt-58 1.45E+02 1.43E+02 1.02 Acceptable E7055-278 2~d /2010 Water pCi/L Cobalt-58 1.51 E+02 1.44E+02 1.05 Acceptable E7054-278 2 d /2010 Milk pC1/L Cobalt-60 1.90E+02 1.83E+02 1.04 Acceptable E7055-278 2d /2010 Water pCl/L Cobalt-60 1.94E+02 1.85E+02 1.05 Acceptable E7054-278 2d /2010 Milk pCl/L Cr-Si 3.81 E+02 3.61 E+02 1.05 Acceptable E7055-278 2 d /2010 Water pCi/L Cr-SI 3.86E+02 3.64E+02 1.06 Acceptable E7052-278 '2d / 2010 Cartridge pCi lodine-131 8.S8E+01 8.54E+01 1.00 Acceptable E7054-278 2n" /2010 Milk pCi/L Iodine-131 6.91E+01 7.40E+01 0.93 Acceptable E7055-278 2 d /2010 Water pCi/L Iodine-131 8.12E+01 7.22E+01 1.12 Acceptable E7054-278 2nd/2010 Milk pCl/L Iron-59 1.60E+02 1.37E+02 1.17 Acceptable E7055-278 2nd /2010 Water pCl/L Iron-59 1.60E+02 1.38E+02 1.16 Acceptable E7054-278 2nd/2010 Milk pCl/L Manganese-54 2.10E+02 2.07E+02 1.01 Acceptable E7055-278 2 "d/2010 Water pCl/L Manganese-54 2.30E+02 2.09E+02 1.1 Acceptable E7053-278 2d~ /2010 Milk pCi/L Strontium-89 7.91E+01 9.28E+01 0.8S Acceptable E7053-278 2d /2010 Milk pCl/L Strontium-90 1.12E+01 1.27E+01 0.88 Acceptable E7054-278 2 "d/2010 Milk pCl/L Zinc-65 2.71 E-02 2.S4E+02 1.07 Acceptable E7055-278 2 d /2010 Water pCi/ll Zinc-65 2.97E+02 2.56E+02 1.16 Acceptable NY-332 3262 2 'd / 2010 Water pCl/L Barium-133 27.8 25.6 20.6-30.5 Acceptable NY-332 3262 2 d / 2010 Water pCl/L Cesium-I134 14.8 14.0 10.7- 17.3 Acceptable NY-332 3262 2nd / 2010 Water pC11L Cesium-I137 124 123 112- 134 Acceptable NY-332 3262 2nd/ 2010 Water pCl/L Cobalt-60 98.3 99.5 90.3- 109 Acceptable NY-332 3263 2nd / 2010 Water pCl/L Gross Alpha 33.0 26.8 15.0-38.6 Acceptable NY-332 3263 2d / 2010 Water pC1/L Gross Beta 64.6 S4.0 41.3-66.7 Acceptable NY-332 3264 2d' /2010 Water pCl/[- lodine-131 23.4 26.4 21.9-31.0 Acceptable NY-332 3264 2nd / 2010 Water pCi/L Iodine-131 1 26.8 2 6.4 21.9-31.0 Acceptable NY-332 326S 2 "d/ 2010 Water pCl/L Radium-226 12.1 13.2 10.4-16.0 Acceptable NY-332 326S 2 nd/ 2010 Water pCl/L Radium-228 9.90 8.91 6.08 -11.7 Acceptablel

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 16 of 51 Acceptance Sample Sample Known Range/

Number Quarter I Year Media Unit Analyte/ Nuclide GEL Value value Ratio Evaluation NY-332 3261 2 "' /2010 Water pCi/L Strontium-89 46.7 41.9 33.4 -50.4 Acceptable NY-332 3261 1 2,d /2010 Water pCi/L Strontium-90 33.9 34.8 27.1 -42.5 Acceptable NY-332 3266 2 "' / 2010 Water pCl/L Tritium 9610 9490 8390- 10600 Acceptable NY-332 3265 2nId / 2010 Water pCi/L Uranium (activity) 48.81 44.7 37.9-51.4 Acceptable NY-332 3262 2n, / 2010 Water pCi/L Zinc-65 146 139 121 -156 Acceptable MRAD-12 2nd / 2010 Soil pCi/kg Actinium-228 1570 1850 1190- 2600 Acceptable MRAD-12 2nd /2010 Soil pCi/kg Americium-241 1130 1500 896- 1930 Acceptable MRAD-12 2nd /2010 _ Soil pCi/kg Americium-241 1120 1500 896-1930 Acceptable MRAD-12 2d /2010 _Vegetation pCi/kg Americium-241 2410 3140 1790-4310 Acceptable MRAD-12 2"' /2010 Vegetation pC!/kg Americium-241 3600 3140 1790-4310 Acceptable MRAD-12 2 "' / 2010 Air Filter pCi/Filter Americium-241 52.7 60.0 35.1 -82.3 Acceptable MRAD-12 2d / 2010 Air Filter pCi/Filter Americium-241 76 60 35.1 -82.3 Acceptable MRAD-12 2n, /2010 Water pCi/L Americium-241 79.1 95.6 65.5- 129 Acceptable MRAD-12 2n' / 2010 _ Water pCl/L Americium-241 123 95.6 65.5- 129 Acceptable MRAD-12 2 d / 2010 Soil pCi/kg Bismuth-212 1430 1640 430-2450 Acceptable MRAD-12 2"d/ 2010 Soil pCi/kg Bismuth-214 1080 1410 865-2030 Acceptable MRAD-12 2"' / 2010 Soil pC!/kg Cesium-134 3040 3110 2000-3740 Acceptable MRAD-12 2m / 2010 _Vegetation pCi/kg Cesium-i134 1750 1670 956-2310 Acceptable MRAD-1 2 2" / 2010 Air Filter pCi/Filter Cesium-I134 504 436 284 -540 Acceptable MRAD-12 2nd / 2010 Water pCi/L Cesium-I134 454 417 308-479 Acceptable MRAD-12 2nd/ 2010 Soil pC!/kg Cesium-I137 4330 4440 3400-5770 Acceptable MRAD-12 2~d / 2010 _Vegetation pCi/kg Cesium-i137 1550 1470 1080-2040 Acceptable MRAD-12 2 'd / 2010 _ Air Filter pCi/Filter Cesium-i137 785 701 527-921 Acceptable MRAD-12 2,d / 2010 Water pCi/L Cesium-I137 693 654 556-783 Acceptable MRAD-12 I 2,d /2010 Soil[ pCi/kg Cobalt-60 2120 2140 1560-2870 Acceptable MRAD-12 2nd /2010 -Vegetation pCi/kg Cobalt-60 2100 1970 1330-2830 Acceptable MRAD-12 2nd /2010 _ Air Filter pCi/Filter Cobalt-60 591 523 405-653 Acceptable MRAD-12 2nd/ 2010 Water pCl/L Cobalt-60 813 - 727 633-859 Acceptable MRAD-12 2nd/ 2010 Vegetation pCi/kq Curium-244 429 528 260-822 Acceptable MRAD-12 2r" / 2010 Air Filter pCi/Filter Gross Alpha 68.2 79.6 41.3-120 Acceptable MRAD-12 2m" / 2010 _ Air Filter pCi/Filter Gross Beta 72 70.4 43.4- 103 Acceptable MRAD-12 2 "d/ 2010 Air Filter pCi/Fllter Iron-55 375 - 359 158-559 Acceptable MRAD-12 2d / 2010 Sol[ pCi/kg Lead-212 1540 1520 980-2140 Acceptable MRAD-12 2r / 2010 Soil pC!/kg Lead-214 1300 1440 862-2140 Acceptable MRAD-12 2" / 2010 _ Soil pCi/kg Manganese-54 < 22.9 0 Acceptable MRAD-12 2m / 2010 _Vegetation pCi/kg Manganese-54 < 9.6 0.00 --- Acceptable

LaboratorieS LLC P.0. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 17 of 51 Acceptance Sample Sample Known Ran gel Number Quarter / Year Media Unit Analyte /Nuclide GEL Value value Ratio Evaluation MRAD-12 2n1 /2010 Air Filter pC!/Filter Manganese-54 < 5.07 0.00 - Acceptable MRAD-12 2nd / 2010 Water pCi/L Manganese-54 < 7.7 0.00 --- Acceptable MRAD-12 1 2"d/2010 Soil pCi/kg Plutonium-238 1360 1330 1761 - 1870 Acceptable MRAD-12 2d /2010 Vegetation pCi/kg Plutonium-238 3090 3040 1640-4450 Acceptable MRAD-12 2nd / 2010 Air Filter pCi/Filter Plutonium-238 63.9 64.1 44.0-84.3 Acceptable Not MRAD-12 2nd / 2010 Water pCi/L IPlutonium-238 79.5 109 82.4- 135 Acceptable MRAD-12 1 2n,/2010 Soil pCi/kg Plutonium-239 1220 1260 860- 1670 Acceptable MRAD-12 2nd/ 2010 Vegetation pCi/kg Plutonium-239 2830 2800 1740-3820 Acceptable MRAD-12 2nd~ / 2010 Air Filter pCi/Filter Plutonium-239 56.6 56.7 41.1 - 73.4 Acceptable MRAD-12 2r" /2010 Water pCi/L Plutonium-239 103 105 81.2-130 Acceptable MRAD-12 2d /2010 Soil pCi/kg Potassium-40 11100 10900 7900- 14800 Acceptable 25100-MRAD-12 2d /2010 Vegetation pCi/kg Potassium-40 40800 34900 49400 Acceptable MRAD-12 2 "d/2010 Soil pCi/kg Strontium-90 7870 8180 2960- 13300 Acceptable MRAD-12 2nd / 2010 Soil pCi/kg Strontium-90 7870 8180 2960- 13300 Acceptable MRAD-12 I 2d / 2010 Vegetation pCi/kg Strontium-90 7880 9120 5100- 12100 Acceptable MRAD-12 2d" / 2010 Air Filter pCi/Filter Strontium-90 178 187 82.3-291 Acceptable MRAD-12 2nd / 2010 Water pCl/L Strontium-90 708 719 456-961 Acceptable MRAD-12 2nd / 2010 Soil pCi/kg Thorium-234 1600 1610 511 -3070 Acceptable MRAD-12 2,d / 2010 Soil pCi/kg Uranium-234 1230 1620 1030-2010 Acceptable MRAD-12 2rd / 2010 Vegetation pCi/kg Uranium-234 1680 1720 1180- 2280 Acceptable MRAD-12 2' / 2010 Air Filter pCi/Filter Uranium-234 68.8 62.1 39.1 -92.0 Acceptable MRAD-12 2"d /2010 Water pCi/L Uranium-234 62.4 61.4 46.3-79.2 Acceptable Not MRAD-12 2r" / 2010 Soil pCi/kg Uranium-234 < 1158 1620 1030-2010 Acceptable MRAD-12 2rd / 2010 Soil pCi/kg Uranium-238 1600 1610 984-2040 Acceptable Not MRAD-12 2 r"/2010 Soil pCi/kg Uranium-238 908 1610 984-2040 Acceptable MRAD-12 2~d / 2010 Soil pCi/kg Uranium-238 1440 1610 984-2040 -Acceptable MRAD-12 2 "d/ 2010 Vegetation _pCi/kg Uranium-238 1604 1710 1200-2160 Acceptable MRAD-12 2 d / 2010 Vegetation pCi/kg Uranium-238 1770 1710 1200-2160 Acceptable Not MRAD-12 2 d / 2010 Vegetation pCi/kg Uranium-238 < 1240 1710 11200-2160 Acceptable MRAD-12 2 "d/2010 Air Filter pCi/Filter Uranium-238 61.5 61.5 139.4-87.3 Acceptable MRAD-12 2 rd/ 2010 Air Filter PC!/Filter Uranium-238 69.5 61.5 39.4-87.3 Acceptable MRAD-1 2 2nd / 2010 Air Filter pCi/Filter Uranium-238 < 61.2 61.5 39.4 -87.3 Acceptable MRAD-12 2nd / 2010 Water pC!/L Uranium-238 67.9 60.9 46.5-75.5 Acceptable MRAD-12 2d / 2010 Water pCi/L Uranium-238 66.1 60.9 46.5-75.5 Acceptable Not MRAD-12 2d"/ 2010 Water pC!/L Uranium-238 < 155 60.9 46.5-75.5 Acceptable MRAD-12 2"d / 2010 1 Soil pCi/kg Uranium-Total 2789 13300 11880-4460 Acceptable MRAD-1 2 2"d / 2010 Vegetation pCi/kg Uranium-Total 3536 13510 2410 -4530 Acceptable

LaboratorleS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 18 of 51 Acceptance Sample Sample Known Range/

Number Quarter/IYear Media Unit Analyte INuclide GEL Value value Ratio Evaluation Uranium-Total MRAD-12 2 "d / 2010 Soil ug/kg (mass) 2920 4820 2650 -6060 Acceptable Uranium-Total MRAD-12 2 n1 /2010 Vegetation ua/kg (mass) 5270 5120 3520-6610 Acceptable Uranium-Total MRAD-12 2 n1 /2010 Vegetation pCi/kg (mass) 5290 5120 3520-6610 Acceptable Uranium-Total MRADJ-12 2n' /2010 Air Filter ug/Filter (mass) 183 184 114-264 Acceptable Uranium-Total MRAD-12 2 "' /2010 Air Filter ug/Filter (mass) 208 184 114-264 Acceptable Uranium-Total MRAD-12 2 "d/2010 Air Filter ug/Filter (mass) 175 184 114-264 Acceptable Uranium-Total MRAD-12 2"' /2010 Water ug/L (mass) 213 182 143-225 Acceptable Uranium-Total MRAD-12 2 "d/ 2010 Water ug/L (mass) 198 182 143-225 Acceptable MRAD-12 2 "d/ 2010 Soil pCi/kg Zinc-65 2790 2470 1960-3310 Acceptable MRAD-12 2d~ / 2010 Vegetation pCi/kg Zinc-65 1630 1360 1983- 1860 Acceptable MRAD-12 2~d / 2010 Air Filter pCl/Filter Zinc-65 462 389 269- 539 Acceptable MRAD-12 2 d / 2010 Water pCl/L Zinc-65 632 533 452 -664 Acceptable Not RAD -82 3rd / 2010 Water pCi/L Barium-133 112.0 89.1 75.0 -98.0 Acceptable Not RAID - 82 3rd / 2010 Water I pCi/L Cesium-I134 115.0 88.3 72.4 -97.1 Acceptable Not RAID - 82 3 'd / 2010 Water pCl/L Cesium-I137 271 210 189- 232 Acceptable Not RAID - 82 3 'd / 2010 Water pCi/L Cobalt-60 98.4 72.8 65.5- 82.5 Acceptable RAD - 82 3rd / 2010 Water pCl/L Gross Alpha 65.5 61.1 32.0 -75.9 Acceptable RAID - 82 3 r'd / 2010 Water pCi/L Gross Beta 56.7 56.4 38.6-63.6 Acceptable RAD - 82 3r'd / 2010 Water I pCl/L Iodine-131 32.2 28.4 23.6-33.3 Acceptable RAD - 82 3 'd / 2010 Water pCl/L Radium-226 15.9 17.1 12.7-19.6 Acceptable RAID- 82 3 'd / 2 0 1 0 Water pCl/L Radium-228 18.9 16.1 10.8- 19.4 Acceptable RAD - 82 3r / 2010 Water pCi/L Strontium-89 60.6 55.3 44.1 -62.9 Acceptable Not RAID - 82 3r / 2010 Water pCi/L Strontium-90 47.1 32.8 24.0-38.0 Acceptable 17300-RAD - 82 3 rd/ 2010 Water pCl/L Tritium 18500 19800 21700 Acceptable Not RAID - 82 3r'd / 2010 Water pCl/L Uranium (Nat) 58.0 49.6 40.2-55.1 Acceptable Uranium (Nat) Not RAID - 82 3rd / 2010 Water ug/L Mass 89.1 72.3 58.7-80.4 Acceptable Not RAID- 82 3 'd / 2 0 1 0 Water pCl/L I Zinc-65 161 110 99.0- 131 Acceptable MAPE P-i10-MaS22 3r'd / 2010 Soil Bq/kg Americium-241 0.07 0.00 Acceptable MAPEP-1 0- Not RdF22 3 rd / 2010 Filter Bq/sample Americium-241 0.2637 0.146 0.102 - 0.190 Acceptable MAPEP-i10-RdV22 I 3rd / 2010 Vegetation Bq/sample Americium-241 0.179 0.225 0.158 - 0.293 Acceptable MAPEP-I10-MaS22 3rd / 2010 Soil Bq/kg Cesium-i134 744.67 733 513-953 Acceptable MAPEP Not RdF22 3rd / 2010 Filter Bg/sample Cesium-I134 1 4.323 12.13 1.49 -2.77 Acceptable MAPEP RdV22 3rd / 2010 Vegetation Bg/sample Cesium-i134 3.098 4.39 3.07 -5.71 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 19 of 51 SampleAcceptance SapeSample Known Range/

Number Quarter /Year Media Unit Analyte INuclide GEL Value value Ratio Evaluation MAPEP-1 0-MaS22 3 'd/ 2010 Soil Bq/kg Cesium-I337 831.7 779 545- 1013 Acceptable MAPEP-10 No

'd/ 2010 Filter Bq/sample Cesium-I137 3.070 1.53 1.07 -1.99 Acceptable MAPEF 10 3

-RdV22 3rd/ 2010 Vegetation Bq/sample Cesium-I137 2.185 3.06 2.14-3.98 Acceptable MAPEP MaS22 3rd/ 2010 Sol[ Bq/kg Cobalt-57 536.0 522 365- 679 Acceptable MAPEP RdV22 3rd/2010 Vegetation Op/sample Cobalt-57 0.009 0.00--------Acceptable MAPEP MaS22 3 'd/2010 Soil Sq/kg Cobalt-60 670.3 622 435-809 Acceptable MAPEP-10-No MAPE-10 '/, Filter Op/sample Cobalt-60 5.187 2.473 1.731 -3.215 Acceptable 3 2010 RdV22 3rd/ 2010 _Vegetation Bq/sample Cobalt-60 3.076 3.27 2.29-4.25 Acceptable MAPEP GrF22 3 'd/ 2 0 10 _ Filter Op/sample Gross Alpha 0.303 0.427 >0.0 - 0.054 Acceptable MAPEP GrF22 3 d 2010 Filter Op/sample Gross Oeat 1.433 1.29 0.65- 1.94 Acceptable MAPEP MaS22 3 'd / 2 0 10 _ Soil Op/kg Iron-55 03.6 0.00 Acceptable MAPEP MaS22 3r / 2010 Soil Bp/kg Manganese-54 940.7 049 594- 1104 Acceptable MAPEP-10-No MAPE-10 3 r, Filter Bp/sample Manganese-54 6.483 3.02 12.11 -3.93 Acceptable 2010 RdV22 8'd / 2 0 1 0 Vegetation Op/sample Manganese-54 0.004 0.00 --- Acceptable MAPEP-1 0-MaS22 3'r/ 2 0 10 Soil Op/kg Nickel-63 489 477 334-620 Acceptable MAPEP MaS22 3'r/ 2 0 10 Soil Op/kg Plutonium-238 17.9 24 16.9-31.3 Acceptable MAPEP-1 0-RdF22 3 rd/ 2 0 1 0 Filter Op/sample Plutonium-238 0.010 0.0010 --- Acceptable MAPEP-1 0-RdV22 3dd/ 2 0 10 _Vegetation Op/sample Plutonium-238 0.149 0.160 10.112 - 0.208 Acceptable MAPEP-1 0- Plutonium-MaS22 Vrd/ 2010 _ Soil Bq/kq 239/240 0.21 0.00 --- Acceptable MAPEP-1 0- Plutonium- 0.0582- Not RdF22 3 d/2 0 10 Filter Op/sample 239/240 0.164 0.0832 0.1082 Acceptable MAPEP dPlutonium-RdV22 3rd / 2010 _Vegetation Op/sample 239/240 0.0026 0.0008 --- Acceptable MAPEP-1 0-MaS22 3rd/ 2 0 10 Soil Op/kg Potassium-40 638.7 559 391 -727 Acceptable MAPEP MaS22 3 'd/ 2010 Soil Op/kg Strontium-90 261.0 288 202-374 Acceptable MAPEP RdF22 3 'd/ 2010 Filter Op/sample Strontium-90 -0.004 0.00 Acceptable MAPEP-1 0-RdV22 3 r/ 2010 Veqetation Op/sample Strontium-90 0.033 0.00 --- Acceptable MAPEP MaS22 3 d / 2010 Soil Op/kg Technetium-99 -3.0 0.00 Accetabl MAPE P- 0-etal MaS22 3d / 2010 Soil Op/kg Uranium-234/233 65.27 60 42-78 Acceptable MAPEP-10-No Filter Op/sample Uranium-234/233 0.137 0.068 0.040 -0.088 Acceptable MAPE-10 3 d 2010 RdV22 3 rd 2 0 1 0 Vegetation OpB/sample Uranium-234/233 0.184 0.216 0.151 -0.281 Acceptable MAPEP-1 0- 006 o 3 2010 Filter ug/sample Uranium-235 0.0756 0.0381 0.0495 Acceptable MAPE-10 d/

RAPd-220 0.0875 -

RV2 3r'/2010 Vegetafion_ ug/sample I Uranium-235 0.090 10.1250 1 0.1625 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 20 of 51 Acceptance Sample Sample Known Range/

Number Quarter/ Year Media Unit Analyte INuclide GEL Value value Ratio Evaluation MAPEP-1 0-MaS22 3 r/ 2010 Soil Bq/kg Uraniurn-238 70.23 64 45-863 Acceptable MAPEP Not RdF22 3,/ 2010 Filter Iug/sample Uraniumn-238 10.2 5.7 4.0-7.4 Acceptable MAPEP-1 0- Not RdF22 3 Id / 20 1 0 Filter Bq/sample Uranium-238 0.147 0.071 0.050 -0.092 Acceptable MAPEP-1 0- Not RdV22 3"~/2010 Vegetation ug/sample Uranium-238 12.5 17.9 12.5- 23.3 Acceptable MAPEP-1 0-RdV22 3rd /2 0 1 0 _Vegetation Bqlsarnple Uranium-238 0.184 0.223 0.156 -0.290 Acceptable MAPEP-1 0- Not RdF22 3 " /2 0 1 0 _ Filter ug/sample Uranium-Total 10.2 5.7 4.0-7.4 Acceptable MAPEP-1 0-RdV22 3 ' / 2010 _Vegetation ug/sample Uranium-Total 13.9 18.0 12.6-23.4 Acceptable MAPEP-1 0-MaS22 3r'd / 2010 Soil Bq/kg Zinc-65 -2.89 0.0 --- Acceptable MAPEP-1 0-RdF22 3 r"d/ 2 0 1 0 _ Filter Bq/sample Zinc-65 -0.106 0.00 Acceptable MAPE P RdV22 3 Id / 2 0 1 0 _Vegetation Bq/sample Zinc-65 6.844 7.10 4.97-9.23 Acceptable E7119-278 3 rd/ 2 0 1 0 Milk pCi/ll Cesium-134 1.37E+02 1.26E+02 1.09 Acceptable E7119-278 3 rd / 2 0 1 0 Milk pC[1L Cesium-137 1.68E+02 1.50E+02 1.12 Acceptable E7119-278 3 /2 0 1 0 Milk pCi/L Cobalt-58 1.13E+02 1.01 E+02 1.12 Acceptable E7119-278 3 /2 0 1 0 Milk pCl/L Cobalt-60 2.14E+02 1.97E+02 1.09 Acceptable E7119-278 /

3 'd 2 0 1 0 Milk pCi/L Cr-5i 3.90E+02 3.39E+02 1.15 Acceptable E7117-278 3 r'd / 2 0 1 0 Milk pCi/L Iodine-131 7.97E+01 8.02E+01 0.99 Acceptable E71 19-278 3rd / 2010 Milk pCi/L Iodine-i131 1.06E+02 9.69E+01 1.09 Acceptable Not E7119-278 3 d / 2 0 10 _ Milk pCl/L Iron-59 1.55E+02 1.19E+02 1.30 Acceptable E7119-278 3 rd / 2 0 10 _ Milk pCl/L Manganese-54 1.99E+02 1.69E+02 1.18 Acceptable E7118-278 3 rd,/ 2 0 10 Milk pCi/L Strontium-89 7.95E+01 9.34E+01 0.85 Acceptable E7118-278 3 d,/ 2 0 1 0 Milk I PCI/L Strontium-90 1.57E+01 1.67E+01 0.94 Acceptable E7119-278 3 rd,/ 2 0 1 0 Milk pCi/L Zinc-65 2.40E+02 2.06E+02 1.17 Acceptable 09071ON 3 'd/ 2 0 1 0 Water pCi/L Barium-133 86.9 92.9 78.3- 102 Acceptable Not 09071ON 3 rd,/ 2 0 1 0 Water pCi/ll Cesium-134 93.8 79.4 65.0-87.3 Acceptable 09071ON 3 d/ 2010 Water pCl/L Cesium-i137 55.5 54.6 49.1 -62.9 Acceptable 09071ON 3 /2 0 1 0 Water I pCl/L Cobalt-60 120.0 117 1105- 131 Acceptable 0907ION 3 rd/ 2010 Water pCI/L Uranium (Nat) 34.9 33.8 27.3-37.8 Acceptable Uranium (Nat) 09071ON 3 rd/ 2010 Water ug/L I Mass 48.6 49.3 39.8-55.1 Acceptable Not 09071ON 3 rd/ 2010 Water pCi/L Zinc-65 129 99.5 89.6- 119 Acceptable MAPEP-1 0-MaW22 /

3 /2010 Water Bq/L Americium-241 1.0323 1.30 10.91 -1.69 Acceptable MAP EP-1 0-MaW22 3 'd / 2010 Water Bq/L Cesium-i134 0.027 0.00 --- Acceptable MAP EP-1 0-MaW22 3 r/ 2010 Water Bq/L Cesium-137 63.1 60.6 42.4-78.8 Acceptable MAP EP-1 0-MaW22 3 r/ 2010 Water Bq/L Cobalt-57 29.2 26.3 19.8-36.8 Acceptable MAPEP MaW22 rd /20 10 Water Bq/L Cobalt-60 -0.021 0.00 7 Accep)table

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 21 of 51 Acceptance Sample Sample Known Range/

Number Quarter/IYear Media Unit Analyte INuclide GEL Value value Ratio Evaluation MAPEP-i10-GrW22 V d /2010 _ Water Bq/L Gross Alpha 0.559 0.676 >0.0 - 1.352 Acceptable MAPEP -GrW22 _ 3 '2010 Water I Bq1L Gross Beta 3.110 3.09 1.55-4.64 Acceptable MAP EP-1 0-MaW22 3rd / 2010 _ Water Bq/L Iron-55 0.24 0.00 Acceptable MAP EP-1 0-MaW22 3 r'd / 2 0 1 0 Water Bq/L Manganese-54 28.83 26.9 18.8-35.0 Acceptable MAP EP-1 0-MaW22 3d / 2010 Water Bq/L Nickel-63 57.7 59.9 41.9- 77.9 Acceptable MAPEP-1 0- Not MaW22 - 3 / 2010 Water Bq/L Plutonium-238 1.213 1.93 1.35 -2.51 Acceptable MAPEP-1 0- Plutonium-MaW22 3 ' / 2010 Water Bq/L 239/240 0.026 0.009------------Acceptable MAP EP-1 0-MaW22 3 r'd/ 2010 Water Bq/L Strontium-90 -0.01 0.00 --- Acceptable MAPEP-1 0-MaW22 3 d / 2010 Water Bq/L Technetlum-99 -0.4 0.00 --- Acceptable MAPEP-1 0-MaW22 3d / 2010 Water Bq/L Tritium 107 90.8 63.6 -118.0 Acceptable MAP EP-1 0-MaW22 3 /2 0 1 0 Water Bq/L Uranium-234/233 1.163 1.22 0.85- 1.59 Acceptable MAP EP-1 0-MaW22 3 d / 2010 Water Bq/L Uranium-238 1.223 1.25 0.88 -1.63 Acceptable MAPEP-1 0-MaW22 3r" / 2010 Water Bq/L Zinc-65 45.9 40.7 28.5- 52.9 Acceptable E7195-278 4"' /2010 Milk I pCl/L Cerium-141 1.39E+02 1.30E+02 1.07 Acceptable E7195-278 4"' /2010 Milk pCi/L Cesium-134 9.85E+01 9.30E+01 1.06 Acceptable E7196-278 4"' /2010 _ Water pCi/L Cesium-134 1.22E+02 1.18E+02 1.03 Acceptable E7195-278 4"' /2010 _ Milk pCl/L Cesium-137 9.87E+01 9.45E+01 1.04 Acceptable E7196-278 4"' /2010 Water pCi/L Cesium-137 1.24E+02 1.20E+02 1.03 Acceptable E7195-278 4"' /2010 Milk pCi/L Cobalt-58 7.02E+01 7.37E+01 0.95 Acceptable E7196-278 4"' /2010 Water pCi/L Cobalt-58 9.63E+01 9.35E+01 1.03 Acceptable E7195-278 4"' /2010 Milk pCl/L Cobalt-60 1.77E+02 1.71 E+02 1.04 Acceptable E7196-278 4"' /2010 _ Water pCl/L Cobalt-60 2.34E+02 2.17E+02 1.08 Acceptable E7195-278 4"' /2010 Milk pCl/L Cr-51 2.48E+02 2.34E+02 1.06 Acceptable E7196-278 4"' /2010 Water pCi/L Cr-Si 3.12E+02 2.97E+02 1.0S Acceptable E7193-278 4"' / 2010 _ Cartridge pc lodine-131 5.97E+01 6.02E+01 0.99 Acceptable E7195-278 4"' /2010 _ Milk pCl/L Iodine-131 - 1.012E+02 9.41 E+02 1.07 Acceptable E7196-278 4"' / 2010 Water PCI/L lodine-131 7.24E+01 6.44E+01 1.12 Acceptable E7195-278 4t' /2010 Milk PCI/L Iron-59 1.02E+02 9.112E+01 1.12 Acceptable E7196-278 4"' /2010 Water pCl/L Iron-59 - 1.422+02 1.16E+02 1.23 Acce ptable E7195-278 4"' /2010 Milk pCj/L Manganese-54 1.20E+02 1.192+02 1.01 Acceptable E7196-278 4" /2010 Water PCI/L Manganese-54 1.70E+02 1.52E+02 1.12 Acceptable E7194-278 4"' /2010 Milk I p/L Strontium-89 7.62E+01 9.282+01 0.82 Acetable E7194-278 4"' /2010 Milk pCi/L Strontium-90 - 1.302+01 1.472+01 0.88 Acceptable E7195-278 4"' /2010 _ Milk pCi/L Zinc-65 2.372+02 2.042+02 1.16 Acceptable E7196-278 4"' /2010 _ Water pCl/L Zinc-65 2.972+02 2.59E+02 1.1S Acceptable NY-337 3762 1 4"' / 2010 Water pCl/L Barium-133 - 5.5 1S5.9 143.3 -59.4 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 22 of 51 Acceptance Sample Sample Known Range/

Number Quarter/Year Media Unit Analyte/ Nuclide GEL Value value Ratio Evaluation Not NY-337 3762 4"' /2010 Water pCi/L Cesium-134 51.0 42.0 35.8-49.2 Acceptable NY-337 3762 4"' /2010 Water pCi/ll Cesium-137 29.3 27.3 22.4-32.1 Acceptable NY-337 3762 4" / 2010 Water pCi/L Cobalt-60 13.6 13.2 9.72- 16.7 Acceptable NY-337 3763 4"' /2010 Water pCi/L Gross Alpha 32.8 41.6 124.3-58.9 Acceptable NY-337 3763 4"' / 2010 Water pCl/L Gross Bela 29.3 27.5 18.3-36.7 Acceptable Not NY-337 3764 4"' /2010 Water I pCi/L Iodine-131 13.4 18.2 14.7-21.7 Acceptable Not NY-337 3764 4"' /2010 Water I pCi/L Iodine-131 13.5 18.2 14.7-21.7 ,Acceptable Not NY-337 3765 4" /2010 Water pCi/L Radium-226 13.2 10.6 8.30-12.9 Acceptable NY-337 3765 4"' / 2010 Water pC!/L Radium-228 6.51 6.07 3.91 -8.22 Acceptable Not NY-337 3761 4"' / 2010 Water PCI/L I Strontium-89 47.8 61.3 51.3- 71.4 Acceptable NY-337 3761 4"' / 2010 Water pCi/L Strontium-90 12.0 14.9 11.0- 18.8 Acceptable 13500-NY-337 3766 4"' /2010 Water pC!/L Tritium 14400 15300 17000 Acceptable NY-337 3765 4"' /2010 Water pCi/L Uranium (activity) 17.5 16.0 13.2-18.7 Acceptable NY-337 3762 4"' /2010 Water pC!/L Zinc-65 134 122 104-138 Acceptable 10051ON 4"' /2010 Water pC!/L Strontium-89 49.9 51.4 40.6-58.9 Acceptable 10051ON 4"' /2010 Water pC!/L Strontium-90 35.4 41.3 30.4-47.5 Acceptable RAD - 83 4"' /2010 Water pCi/L Strontium-90 41.5 43 31.7-49.3 Acceptable 1122101-1 4"'/2010 Water pCl/L Barium-133 66.3 65.9 54.9-72.5 Acceptable 112210H1 4"' /2010 _ Waler pCl/L Cesium-134 71.6 71.6 58.4-78.8 1Acceptable 112210H1 4"' /2010 - Water pC!/L Cesium-137 151 146 131 -163 Acceptable 112210H1 4"' /2010 Water pCi/L Cobalt-60 90.2 84.5 76.0-95.3 Acceptable 1122101-11 4"' /2010 Water pCl/L Zinc-65 207 186 167-219 Acceptable 1122101-2 4"' /2010 Water pCi/L Plutonium-238 102.0 108 81.7- 134 Acceptable 1122101-2 4"' /2010 Water pC!/L Plutonium-239 77.6 86.3 66.8- 107 Acceptable MRAD-13 4" / 2010 Soil IpCi/kg Actinium-228 1460 1830 1170-2580 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Americium-241 845 1120 669- 1440 Acceptable MRAD-13 4"' / 2010 Soil pCi/kq Americium-241 928 1120 669- 1440 Acceptable MRAD-13 4h' /2010 Vegetation pCi/kg Americium-241 4000 4760 2710-6540 Acceptable MRAD-13 4"' /2010 Air Filter pCi/Filter Americium-241 70.1 74.1 43.3-102 Acceptable MRAD-13 4"' / 2010 Water pCi/L Americium-241 164 176 120-238 Acceptable MRAD-13 4"' /2010 Water pCi/L Americium-241 178 176 120-238 Acceptable Not MRAD-13 4"' / 2010 Soil pC!/kg Bismuth-212 < 538 2070 543-3100 Acceptable MRAD-13 4"' /2010 Soil pC!/kg Bismuth-214 818 983 603-1410 Acceptable MRAD-13 4"' /2010 Soil pC!i/kg Cesium-134 2230 2240 1440-2700 Acceptable MRAD-13 4"' / 2010 Veqetation pCi/kg Cesium-134 1200 1040 595- 1440 Acceptable MRAD-13 4"' /2010 Air Filter pCi/Filter Cesium-i134 405 388 253-480 Acpal MRAD-13 4"' / 2010 Water pCi/L Cesium-134 495 492 363-565 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 23 of 51 Acceptance Sample Sample Known Range/

Number Quarter/IYear Media Unit Analyte I Nuclide GEL Value value Ratio Evaluation MRAD-13 4"' /2010 _ Soil pCi/kg Cesium-137 3400 3530 2700-4580 Acceptable MRAD-13 4"' / 2010 Vegetation .pCi/kg Cesium-137 1420 1260 924- 1750 Acceptable MRAD-13 4"' /2010 _ Air Filter pCi/Filter Cesium-137 532 514 386-675 Acceptable MRAD-13 4"' /2010 Water pCj/L Cesium-137 620 625 531 -749 Acceptable MRAD-13 4"' /2010 _ Soil pCi/kg Cobalt-60 4580 4780 3480-6420 Acceptable MRAD-13 4"' /2010 _Vegetation pCi/kg Cobalt-60 1130 1010 1683-1450 Acceptable MRAD-13 4"' /2010 Air Filter pCi/Filter Cobalt-60 531 479 371 -598 Acceptable MRAD-13 4"h /2010 Water pCl/L Cobalt-60 732 714 622-844 Acceptable MRAD-13 4t' /2010 Air Filter pCi/Filter Gross Alpha 74.2 52.3 27.1 -78.7 Acceptable MRAD3-13 4"' / 2010 Water pCj/L Gross Alpha 145 146 64.8-216 Acceptable MRAD-13 4"' / 2010 Air Filter pCi/Filter Gross Beta 55.6 52.7 32.5-77.0 _Acceptable MRAD-13 4"' / 2010 Water pCl/L Gross Beta 171 143 83.6-210 Acceptable MRAD-13 4"' / 2010 _ Air Filter pCI/Filter Iron-55 707 626 275- 974 Acceptable Not MRAD-13 4"' /2010 _ Water pCl/L Iron-55 1220 825 480-1100 Acceptable MRAD-13 4"' /2010 Soil pci/kg Lead-212 15S0 1640 1060-2310 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Lead-214 1030 969 580- 1440 Acceptable MRAD-13 4"' /2010 _ Soil pCi/kg Manganese-54 < 38.0 0.00 --- Acceptable MRAD-13 4"' /2010 _Vegetation pCi/kg Manganese-54 < 39.8 0.00------------Acceptable MRAD-13 4"' /2010 Water pCl/L Mannanese-54 <5 0.00------------Acceptable MRAD-13 4"' /2010 Soil pCi/kg Plutonium-238 1170 1280 733-1800 Acceptable MRAD-13 4"' /2010 Vegetation pCi/kg Plutonium-238 3740 4740 2560-6940 Acceptable MRAD-13 4"' /2010 - Air Filter pCi/Filter Plutonium-238 - 70.8 72.9 50.0-95.8 Acceptable MRAD-13 4"' / 2010 Water pCi/L Plutonium-238 157 162 122-201 Acceptable MRAD-13 4"' /2010 Soil pci/kg Plutonium-239 1070 1180 805-1570 Acceptable MRAD-13 4"' /2010 _Vegetation pCi/kg Plutonium-239 3590 4470 2770-6100 Acceptable MRAD-13 4'/ 2010 - Air Filter pCi/Filter Plutonium-239 - 65.6 69.6 50.5-90.1 Acceptable MRAD-13 4'/2010 _ Water pCI/L Plutonium-239 136 148 114-183 Acceptable MRAD-13 4"' /2010 _ Soil pCi/kg Potassium-40 10500 10700 7760-14500 Acceptable 16200-MRAD-13 4"' /2010 Vegetation pCi/kg Potassium-40 29000 22600 32000 Acceptable MRAD-13 4"' /2010 Soil pCi/kg Strontium-9O 10953 9270 3350-15100 Acceptable MRAD-13 4"' / 2010 -Vegetation pCi/kg Strontium-9O 9800 7810 4360- 10400 Acceptable MRAD-13 4"' /2010 Air Filter pCi/Filter Strontium-9O 80.2 159 70.0-247 Acceptable MRAD-13 4"' / 2010 - Water pCJ/L Strontium-90 817 921 585- 1230 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Thorium-234 1010 1340 425-2550 Acceptable 14100-MRAD-13 I 4"' /2010 Water PC&/ Tritium 20900 21600 31900 Acceptable MRAD-13 4"' /2010 _ Soil pCi/kg Uranium-234 899 1360 1862-1690 Acceptable MRADI-13 4"' /2010 Soil pCi/kg Uranium-234 1190 1360 862-1690 Acceptable MRAD-13 4"' /2010 1 Soil pCi/kg Uranium-234 1110 1360 862-1690 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 24 of 51 Acceptance Sample Sample Known Range/

Number Quarter / Year Media Unit Analyte / Nuclide GEL Value value Ratio Evaluation MRAD-13 4" / 2010 Vegetation pCi/kg Uranium-234 3600 4010 2750-5320 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Uranium-234 73.5 71.8 45.2- 106 Acceptable h

MRAD-13 4 / 2010 Air Filter pCi/Filter Uranium-234 69.9 71.8 45.2- 106 Acceptable th MRAD-13 4 /2010 Water pCi/L Uranium-234 106 109 82.2- 140 Acceptable MRAD-13 4"/ 2010 Water pCi/L Uranium-234 106 109 82.2- 140 Acceptable MRAD-13 4" /2010 Water pCi/L Uranium-234 104 109 82.2-140 Acceptable MRAD-13 4" /2010 Soil pCi/kg Uranium-238 1010 1340 819-1700 Acceptable MRAD-13 4" /2010 Soil pCi/kg Uranium-238 1080 1340 819-1700 Acceptable MRAD-13 4" /2010 Soil pCi/kg Uranium-238 903 1340 819-1700 Acceptable MRAD-13 4" /2010 Soil pCi/kg Uranium-238 1090 1340 819-1700 Acceptable MRAD-13 4 h /2010 Vegetation pC/kg Uranium-238 4000 3980 2800-5030 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Uranium-238 75.5 71.2 45.6-101 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Uranium-238 66.8 71.2 45.6 -101 Acceptable MRAD-13 4 h /2010 Water pCi/L Uranium-238 107 108 82.5- 134 Acceptable MRAD-13 4" /2010 Water pCi/L Uranium-238 114 108 82.5- 134 Acceptable MRAD-13 4" /2010 Water pCi/L Uranium-238 108 108 82.5- 134 Acceptable 1

MRAD-13 4 /2010 Soil pCi/kg Uranium-Total 2027.4 2770 1580-3740 Acceptable MRAD-13 4t /2010 Soil ug/kg Uranium-Total 2093 2770 1580-3740 Acceptable 1

MRAD-13 4 /2010 Soil pCi/kg Uranium-Total 2253 2770 1580-3740 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Uranium-Total 149 146 74.6-232 Acceptable MRAD-13 4"' /2010 Air Filter pCi/Filter Uranium-Total 142 146 74.6 -232 Acceptable MRAD-13 4" / 2010 Water pCi/L Uranium-Total 218 221 159-294 Acceptable MRAD-13 4" /2010 Water pCi/L Uranium-Total 226.8 221 159-294 Acceptable th MRAD-13 4 /2010 Water pCi/L Uranium-Total 217 221 159-294 Acceptable Uranium-Total MRAD-13 4" / 2010 Soil ug/kg (mass) 3240 4040 2220-5080 Acceptable Uranium-Total h

MRAD-13 4 /2010 Soil pCi/kg (mass) 2685 4040 2220-5080 Acceptable Uranium-Total h

MRAD-13 4 /2010 Soil ug/kg (mass) 3241 4040 2220-5080 Acceptable Uranium-Total MRAD-13 4' /2010 Soil ug/kg (mass) 2820 4040 2220-5080 Acceptable Uranium-Total MRAD-13 4"' /2010 Vegetation ug/kg (mass) 12000 11900 8180-15400 Acceptable Uranium-Total MRAD-13 4" /2010 Air Filter ug/Filter (mass) 224.5 213 132 -306 Acceptable Uranium-Total MRAD-13 4" /2010 Air Filter ug/Filter (mass) 201 213 132 -306 Acceptable Uranium-Total MRAD-13 4" /2010 Air Filter ug/Filter (mass) 192 213 132 -306 Acceptable Uranium-Total h

MRAD-13 4 /2010 Water ug/L (mass) 318 323 253-399 Acceptable Uranium-Total MRAD-13 4" /2010 Water ug/L (mass) 342 323 253-399 Acceptable Uranium-Total MRAD-13 4" /2010 Water ug/L (mass) 321 323 253-399 Acceptable MRAD-13 4"' /2010 Soil pCi/kg Zinc-65 2420 2300 1820- 3080 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 25 of 51 Acceptance Sample Sample Known Range/

Number Quarter/Year Media Unit AnalytelI Nuclide GEL Value value Ratio Evaluation MRAD-13 4"h/2010 Vegetation pC!/kg Zinc-65 1380 1210 874-1650 Acceptable MRAD-13 4"' /2010 Air Filter pCD/Filter Zinc-65 552 465 322-644 Acpal MRAD-13 4"' /2010 Water pCl/L -Zinc-65 557 489 414-610 Acceptable 122810P 4"' /2010 Water pCj/L Barium-133 70.9 68.9 57.5 -75.8 Acceptable 122810P 4"' /2010 Water pCi/L Cesium-134 43.0 43.2 34.5-47.5 Acceptable 122810P 4"' /2010 Water pCI/L Cesium-137 122 123 111 -138 Acceptable 122810P 4"' /2010 Water pCl/L Cobalt-60 58.7 53.4 48.1 -61.3 Acceptable]

122810P 4"'i /2010 Water pCi/L Zinc-65 116 102 91.8 - 122 Acceptable

LaboratorleS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 26 of 51 TABLE 2 2010 ECKERT & ZIEGLER ANALYTICS PERFORMANCE EVALUATION RESULTS

SUMMARY

Acceptance Sample Quarter / Sample Analyte I GEL Known Ran ge/

Number Year Media Unit Nuclide Value value Ratio Evaluation E7054-278 2" / 2010 Milk pCl/L Cerium-141 2.61E+02 2.61 E+02 1.00 Acceptable E7055-278 2 "' / 2010 Water pCl/L Cerium-141 2.78E+02 2.63E+02 1.06 Acceptable E6924-278 2 "d / 2010 Milk pCi/L Cerium-141 2.01IE+02 2.02E+02 0.99 _ Acceptable E6925-278 2" /2010 Water pCi/L Cerium-141 2.04E+02 2.04E+02 1.00 Acceptable E6924-278 2" /2010 Milk pCi/L Ceriurn-141 2.01 E+02 2.02E+02 0.99 Acceptable E6925-278 2"d /2010 Water pCl/L Cerium-141 2.04E+02 2.04E+02 1.00 Acceptable E7054-278 2 "d /2010 Milk pCi/L Cesium-137 1.61 E+02 1.58E+02 1.02 Acceptable E7055-278 2"d /2010 Water pCi/L Cesium-137 1.71 E+02 1.59E+02 1.07 Acceptable E6924-278 2"d /2010 Milk pCl/L Cesium-134 2.41E+02 2.53E+02 0.95 Acceptable E6925-278 2"d / 2010 Water pCi/L Cesium-134 2.56E+02 2.55E+02 1.00 Acceptable E6924-278 2"d /2010 Milk pCl/L Cesium-134 2.41 E+02 2.53E+02 0.95 Acceptable E6925-278 2"d /2010 Water pCj/L Cesium-134 2.56E+02 2.55E+02 1.00 Acceptable E7054-278 2 "d /2010 Milk pCl/L Cesium-134 1,76E+02 1.78E+02 0.99 Acceptable E7055-278 2"d /2010 Water pCl/L Cesium-134 1,85E+02 1.79E+02 1.03 Acceptable E6924-278 2 "d /2010 Milk pCl/L Cesium-137 1.71 E+02 1.79E+02 0.96 Acceptable E6925-278 2"d /2010 Water pC!/L Cesium-137 1.81 E+02 1.81 E+02 1.00 Acceptable E6924-278 2" /2010 Milk pCi/L Cesium-137 1.71 E+02 1.79E+02 0.96 Acceptable E6925-278 2"d /2010 Water pCi/L Cesium-137 1.81 E+02 1.81 E+02 1.00 Acceptable E7054-278 2"' /2010 Milk pCl/L Chromium-5i 3.81 E+02 3.61 E+02 1.05 Acceptable E7055-278 2 "d /2010 Water pCi/L Chromium-51 3.86E+02 3.64E+02 1.06 Acceptable E6924-278 2" /2010 Milk pCl/L Chromium-51 5.54E+02 5.48E+02 1.01 Acceptable

LaboratorleS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 27of 51 Acceptance Sample Quarter / Sample Analyte / GEL Known Range/

Number Year Media Unit Nuclide Value value Ratio Evaluation E6924-278 2 d /2010 Milk PCI/L Chromium-51 5.54E+02 5.48E+02 1.01 Acceptable E6925-278 2 "d /2010 Water PCi/L Chromium-51 5.78E+02 5.54E+02 1.04 Acceptable E7054-278 2 nd /2010 Milk pCi/L Cobalt-58 1.45E+02 1.43E+02 1.02 Acceptable E7055-278 2 nd /2010 Water pCi/l- Cobalt-58 1.51 E+02 1.44E+02 1.05 Acceptable E6924-278 2 nd /2010 Milk pCi/L Cobalt-58 2.03E+02 2.11 E+02 0.96 Acceptable E6925-278 2 n1 /2010 Water pCl/L Cobalt-58 2.19E+02 2.13E+02 1.03 Acceptable E6924-278 2 nd /2010 Milk pCi/L Cobalt-58 2.03E+02 2.11 E+02 0.96 Acceptable E6925-278 2 nd /2010 Water pCi/L Cobalt-58 2.19E+02 2.13E+02 1.03 Acceptable E7054-278 2 nd /2010 Milk pCi/L Cobalt-60 1.90E+02 1.83E+02 1.04 Acceptable E7055-278 2n1 /2010 Water pCi/L Cobalt-60 1.94E+02 1.85E+02 1.05 Acceptable E6924-278 2n1 / 2010 Milk IPCI/L Cobalt-60 _2.47E+02 2.56E+02 0.97 Acceptable E6925-278 2nd /2010 Water pCi/L Cobalt-60 2.67E+02 2.58E+02 1.03 Acceptable E6924-278 2nd / 2010 Milk pCi/L Cobalt-60 2.47E+02 2.56E+02 0.97 Acceptable E6925-278 2nd /2010 Water pCi/L Cobalt-6O 2.67E+02 2.58E+02 1.03 Acceptable E7052-278 2 d /2010 Cartridge pci lodine-131 8.58E+01 8.54E+01 1.00 Acceptable E7054-278 2d /2010 Milk pCl/L Iodine-131 6.91E+01 7.40E+01 -- 0.93 Acceptable E7055-278 2"d /2010 Water pCi/L Iodine-131 8.12E+01 7.22E+01 1.12 Acceptable E6922-278 2 d /2010 Cartridge pCi lodine-1 31 9.02E+01 9.39E+01 0.96 Acceptable E6924-278 2 nd /2010 Milk pCi/L Iodine-131- 8,25E+01 8.73E+01 0.95 Acceptable E6925-278 2d /2010 Water pCl/L Iodine-131 1.OOE+02 9.61E+01 1.04 Acceptable E6922-278 2 n / 2010 Cartridge PC Iodine-1 31 9.02E+01 9.39E+01 0.96 Acceptable E6924-278 2nd / 2010 Milk pCl/L lodine-131 8.25E+01 8.73E+01 0.95 Acceptable E6925-278 2 "d /2010 Water pCl/L Iodine-131 1.OOE+02 9.61E+01 1.04 Acceptable E7054-278 2"d /2010 Milk pCi/L Iron-59 1.60E+02 1.37E+02 1.17 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 28of 51 Acceptance Sample Quarter / Sample Analyte / GEL Known Range/

Number Year Media Unit Nuclide Value value Ratio Evaluation E6924-278 2 n1 /2010 Milk pCi/ll Iron-59 1.88E+02 1.78E+02 1.06 Acceptable E6925-278 2nd/21 Wae pC/ Irn5 1.402 17E0 108 Actbl E6924-278 2Id/2010 Water pC1/L Iron-59 1.88E+02 1.78E+02 1.08 Acceptable E6925-278 2 n1 /2010 Milkr pCl/t- Iron-59 1.94E+02 1.79E+02 1.06 Acceptable E6924-278 2 "d /2010 Water pCill M rangns-54 1.83E+02 1.78E+02 1.08 Acceptable E6925-278 2"d /2010 Milkr pC1/L Manganese-54 1.90E+02 1.79E+02 1.036cepal E6924-278 2n1 /2010 Water pC!/L Manganese-54 1.83E+02 1.78E+02 1.06 Acceptable E6925-278 2 n1 /2010 Milkr _pC!/L Manganese-54 1.90E+02 1.79E+02 1.03 Acceptable E7054-278 2 "d /2010 Water pCi/L Manganese-54 21.0E+02 2.07E+02 1.06 Acceptable E7055-278 2 "d / 2010 Milkr pCl/L Manganese-54 2.30E+02 2.09E+02 1.01 Acceptable E7053-278 2 nd /2010 Water pCi/L Strntiums-89 7.910E+01 9280E+01 1.15 Acceptable E6923-278 2 d /2010 Milk pC!/L Strontium-89 9739E+01 1.318E+02 0.85 Acceptable E6923-278 2nd /2010 Milk pC!/L Strontium-89 9.73E+01 1.31E+02 0.75 Acceptable E7053-278 2nd /2010 Milk pCV/L Strontium-890 1.12E+01 1.27E+01 0.75 Acceptable E6923-278 2 "' /2010 Milk pCl/L Strontium-90 1.38E+01 1.79E+01 0.88 Acceptable E6923-278 2nd /2010 Milk pCl/L Strontium-90 1.38E+01 1.79E+01 0.77 Acceptable E6924-278 2n, /2010 Milk pCi/L Zirntcu-65 3.68E+02 3.45E+02 10.7 Acceptable E6925-278 2n, /2010 Milkr pCi/L Zinc-65 3.72E+02 3.48E+02 1.07 Acceptable E6924-278 2 d / 2010 Water pCi/L Zinc-65 3.68E+02 3.45E+02 1.07 Acceptable E6925-278 2 "d /2010 Milkr pCj/L Zinc-65 3.72E+02 3.48E+02 1.07 Acceptable E7054-278 2 "d / 2010 Water pCl/L Zinc-65 2.712E+02 2.54E+02 1.07 Acceptable E7055-278 2 "d/2010 Milkr pCI/L Zinc-65 2.97E+02 2.56E+02 1.07 Acceptable E7119-278 3 'd/ 2 0 1 0 Milk pCi/L Cerium-141 1.27E+02 1.1OE+02 1.15 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 29 of 51 Acceptance Sample Quarter / Sample Analyte I GEL Known Range/

Number Year Media Unit Nuclide Value value Ratio Evaluation E7i119-278 3Vd'/2010 Milk pCi/L Cesium-i137 1.68E+02_ I1.50E+02 1.12 Acceptable E7119-278 3",d 2010 Milk pCi/L Chromium-51 3.90E+02 3.39E+02 1.15 Acceptable E7119-278 3 'dl/2010 Milk pCi/L Cobalt-58 1,13E+02 1.01 E+02 1.12 Acceptable E7119-278 3"'/ 2010 Milk pCi/L Cobalt-6O 2.14E+02 1.97E+02 1.09 Acceptable E7i117-278 3 'a/2010 Milk pCi/L Iodine-i131 7.97E+01 8.02E+01 0.99 Acceptable E7i119-278 3 'd / 2010 Milk __Ci/L Iodine-I131 1.06E+02 9.69E+01 1.09 Acceptable E7119-278 3 " /2010 Milk pCl/L Iron-59 1.55E+02 1.19E+02 1.30 Not Acceptable E7119-278 3 rd /2010 Milk PCI/L Manganese-54 1,99E+02 1.69E+02 1.18 Acceptable E7i118-278 3 'a / 2010 Milk _RCi/L Strontium-89 7.95E+01 9.34E+01 0.85 Acceptable E7i118-278 -3 'd / 2010 Milk pCl/L Strontium-90 1.67E+01 1.67E+01 0.94 Acceptable E7119-278 3 rd/ 20103 Milk pCl/L Zinc-65 2.40E+02 2.06E+02 1.17 Acceptable E7195-278 4"' / 2010 Milk pCi/L Cerium-141 1.39E+02 1.30E+02 1.07 Acceptable E7196-278 4"' /2010 Water pCi/L Cerium-141 1.74E+02 1.65E+02 1.05 Acceptable E7195-278 4"' /2010 Milk pCi/L Cesium-134 9.85E+01 9.30E+01 1.06 Acceptable E7196-278 4"' /2010 Water PCI/L Cesium-134 1.22E+02 1.18E+02 1.03 Acceptable E7195-278 4"' /2010 Milk pCl/L Cesium-137 9.87E+01 9.45E+01 1.04 Acceptable E7196-278 4"' /2010 Water pCj/L Cesium-137 1.24E+02 1,20E+02 1.03 Acceptable E7195-278 4"' /2010 Milk IPCI/L Chromium-51 2.48E+02 2.34E+02 1.06 Acceptable E7196-278 4"' /2010 Water PCI/L Chromium-5i 3.12E+02 2.97E+02 1.05 Acceptable E7195-278 4"' / 2010 Milk pCi/L Cobalt-58 7.02E+01 7.37E+01 0.95 Acceptable E7196-278 4"' / 2010 Water _pCi/L Cobalt-58 9.63E+01 9.35E+01 1.03 Acceptable E7195-278 4"' /2010 Milk IpCl/L Cobalt-60 1.77E+02 1-71E+02 1.04 Acceptable E7196-278 4"' /2010 Water pCI/L Cobalt-60 2.34E+02 2,17E+02 1.08 Acceptable E7193-278 4"' /2010 Cartridge pci Iodine-131 5.97E+01 6.02E+01 0.99 Acceptable E7195-278 4"' /2010 Milk pCi/L lodine-131 i.OiE+02 9.41 E+02 1.07 1Acceptable E7196-278 4"' /2010 Water pCi/L lodine-131 7.24.E+01 6.44E+01 1.12 Acceptable E7195-278 I4"' /2010 Milk pCi/1- 1 lron-59 1.02E+02 9.11E+01 1 1.12 Acceptable

LaboratorleS LLC P.O. Box 3071 2, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 30 of 51 Acceptance Sample Quarter / Sample Analyte I GEL Known Range/

Number Year Media Unit Nuclide Value value Ratio Evaluation E7195-278 4"' / 2010 Milk pCi/L Manganese-54 1.20E+02 1.19E+02 1.01 Acceptable E7196-278 4"' /2010 Water pCj/L Manganese- 4 1.70E+i02 1.52E+02 1.12 Acceptable E7194-278 4"' /2010 Milk pCi/L Strontium-89 7.62E+01 9.28E+01 0.82 Acceptable E7194-278 4"' /2010 Milk pCi/L Strontium-90 1.30E+01 1.47E+01 0.88 Acceptable E7195-278 4"a/2010 Milk pCl/L Zinc-65 2.37E+02 2.04E+02 1.16 1Acceptable E7196-278 4"' /2010 1Water pCi/L Zinc-65 2.97E+02 I2.59E+02 1 .15 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 31 of 51 TABLE 3 2010 DEPARTMENT OF ENERGY MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) RESULTS

SUMMARY

Acceptance Quarter I Sample GEL Known Range/

Sample Number Year Media Unit Analyte / Nuclide Value value Ratio Evaluation MAPEP-10-MaS22 3 /2010 Soil Bq/kg Americium-241 0.07 0.00 --- Acceptable MAPEP-10-MaS22 3 /2010 Soil Bq/kg Cesium-1 34 744.67 733 513-953 Acceptable MAPEP-10-MaS22 3d 2010 Soil Bq/kg Cesium-137 831.7 779 545-1013 Acceptable MAPEP-1 0-MaS22 3d //2010 Soil Bq/kq Cobalt-57 536.0 522 365 -679 Acceptable MAPEP-10-MaS22 3 "d/ 2010 Soil Bq/kg Cobalt-60 670.3 622 435-809 Acceptable MAPEP-10-MaS22 3 ~d/ 2010 Soil[ Bq/kg Iron-55 83.6 0.00------------Acceptable MAPEP-10-MaS22 3d / 2010 Soil[ Bqikg Manganese-54 940.7 849 594-1104 Acceptable MAPEP-10-MaS22 3 " / 2010 Soil Bq/kg Nickel-63 489 477 334-620 Acceptable MAPEP-1 0-MaS22 3 'd / 2010 Soil Bq/kg Plutonium-238 17.9 24 16.9 -31.3 Acceptable MAPEP-10-MaS22 3 rd/ 2010 Soil Bqikq Plutonium-239/240 0.21 0.00------------Acceptable MAPEP-1 0-MaS22 3 'd / 2010 Soil Bq/kg Potassium-40 638.7 559 391 - 727 Acceptable MAPE P-I10-MaS22 3 rd / 2010 Soil BgVkq Strontium-90 261.0 1288 202 -374 Acceptable MAPEP-10-MaS22 /

3 d 201 0 Soil Bq/kg Technetium-99 -3.0 0.00------------Acceptable MAPEP-10-MaS22 3 'd/ 2 0 1 0 Soil BcVkg Uranium-234/233 65.27 60 42-78 Acceptable MAPE P-I10-MaS22 3 'd / 2010 Soil Bq/kg Uranium-238 70.23 64 45 -83 Acceptable MAPEP-10-MaS22 3 ' /2010_ Soil Bq/kg Zinc-65 -2.89 0.0------------Acceptable MAPEP-1 0-MaW22 3 rd/ 2010 Water Bq/L Americium-241 1.0323 1.30 0.91 -1.69 Acceptable MAPEP-1 0-MaW22 3 'd / 2010 Water Bq/L Cesium-I134 0.027 0.00------------Acceptable MAPEP-10-MaW22 3 'd / 2 0 1 0 Water Bq/L Cesium-137 63.1 60.6 42.4-78.8 Acceptable MAPEP-1 0-MaW22 3 rd/ 2010 Water Bq/L Cobalt-57 29.2 28.3 19.8 -36.8 Acceptable MAPEP-1 0-MaW22 3 rd / 2010 Water Bq/L Cobalt-60 -0.021 0.00------------Acceptable MAPEP-1 0-MaW22 3 rd/ 2010 Water Bq/L Hydrogen-3 107 90.8 63.6 -118.0 Acceptable MAPEP-10-MaW22 3 rd/ 2 0 1 0 Water Bq/L Iron-55 0.24 0.00------------Acceptable MAPEP-1 0-MaW22 3 rd1 2010 Water Bq/IL Manganese-54 28.83 26.9 18.8 -35.0 Acceptable MAPEP-1 0-MaW22 3 rd/ 2010 Water l3g/L Nickel-63 57.7 59.9 41.9 -77.9 Acceptable MAPEP-1 0-MaW22 3 rd / 2010 Water Bq/L Plutonium-238 1.213 1.93 1.35 -2.51 Not Acceptable MAPEP-1 0-MaW22 3 rd/ 2010 Water Bq1L Plutonium-239/240 0.026 0.009-----------Acceptable MAPEP-10-MaW22 3 rd/ 2 01 0 Water Bq/L Strontium-90 -0.01 0.00 --- Acceptable MAPEP-10-MaW22 /

3 rd 2 0 1 0 Water Bq/L Technetium-99 -0.4 0.00------------Acceptable MAPEP-10-MaW22 3 rd /2010 Water Bq1L Uranium-234/233 1.163 1.22 0.85- 1.59 Acceptable MAPEP-1 0-MaW22 3 rd/ 2010 Water Bq/L Uranium-238 1.223 1.25 0.88 -1.63 Acceptable MAPEP-1 0-MaW22 3 rd/ 2010 Water Bq1L Zinc-65 45.9 40.7 28.5 -52.9 Acceptable MAPEP-10-GrW22 13r,d/ 2010 Water Bq/L I Gross Alpha 10.559 10.676 >0.0 - 1.352 Acceptable MAPEP-10-GrW22 3 rd/2 0 1 0 Water Bq/L Gross Beta 3.110 3.09 1.55 -4.64 Acceptable

EI LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 32 of 51 Acceptance Quarter I Sample GEL Known Ran gel Sample Number Year Media Unit Analyte INuclide Value value Ratio Evaluation MAPEP-10-RdF22 3 d 2010 Filter ug/sample Uranium-238 10.2 5.7 4.0- 7.4 Not Acceptable MAPEP-1 0-RdF22 3 '/2010 Filter ug/sample Uranium-Total 10.2 5.7 4.0 -7.4 Not Acceptable MAPEP-10-RdF22 3d1 2 01 0 Filter Bq/sample Americium-241 0.2637 0.146 0.102 - 0.190 Not Acceptable MAPEP-10-RdF22 3 d, 2 0 1 0 Filter Bq/sample _Cesium-134 4.323 2.13 1.49-2.77 Not Acceptable MAPEP-1 0-RdF22 3 /2010 Filter Bq/sample Cesium-I137 3.070 1.53 1.07 -1.99 Not Acceptable MAPEP-1 0-RdF22 /

3d /2010 Filter I Bq/sample Cobalt-57 0.0002 0.00 --- Acceptable MAPEP-1 0-RdF22 3 " / 2010 Filter Bq/sample Cobalt-60 5.187 2.473 1.731 - 3.215 Not Acceptable MAPEP-1 0-RdF22 3 'd / 2010 Filter Bg/sample Manganese-54 6.483 3.02 2.11 - 3.93 Not Acceptable MAPEP-10-RdF22 3 'd/2 0 1 0 Filter Bg/sam ple Plutonium-238 0.010 0.0010 --- Acceptable 0.0582 -

MAPEP-10-RdF22 3 'd/2 0 1 0 Filter Bglsam ple Plutonium-239/240 0.164 0.0832 0.1082 Not Acceptable MAPEP-10-RdF22 3 d /2 0 1 0 1 Filter Bq/sample Strontium-9O -0.004 0.00 Acceptable MAPEP-10-RdF22 3 /2 0 1 0 Filter Bq/sample Uranium-234/233 0.137 0.068 0.048 - 0.088 Not Acceptable MAPEP-10-RdF22 3d / 2010 Filter Bq/sample Uranium-238 0.147 0.071 0.050 - 0.092 Not Acceptable MAPEP-10-RdF22 3 'd / 2010 Filter Bq/sample Zinc-65 -0.106 0.00 --- Acceptable MAPEP-10-GrF22 3 ' / 2010 Filter Bq/sample Gross Alpha 0.303 0.427 >0.0 - 0.854 Acceptable MAPEP-10-GrF22 3 d /2010 Filter Bq/sample Gross Beta 1.433 1.29 0.65- 1.94 Acceptable 0.0875 -

MAPEP-10-RdV22 3 d / 2010 Vegetation ug/sample Uranium-235 0.090 0.1250 0.1625 Acceptable MAPEP-10-RdV22 3 d / 2010 Vegetation ug/sample Uranium-238 12.5 17.9 12.5-23.3 Not Acceptable MAPEP-10-RdV22 3d / 2010 Vegetation ug/sample Uranium-Total 13.9 18.0 12.6-23.4 Acceptable MAPEP-10-RdV22 3 d /2 0 1 0 Vegetation Bq/sample Americium-241 0.179 0.225 0.158 -0.293 Acceptable MAPEP-10-RdV22 3 'd / 2010 Vegetation Bq/sample Cesium-134 3.098 4.39 3.07- 5.71 Acceptable MAPEP-10-RdV22 3 rd / 2010 Vegetation Bq/sample Cesium-137 2.185 3.06 2.14-3.98 Acceptable MAPEP-10-RdV22 3 'd / 2010 Vegetation Bq/sample Cobalt-57 0.009 0.00 --- Acceptable MAPEP-10-RdV22 3 d / 2010 Vegetation Bq/sample Cobalt-60 3.076 13.27 2.29-4.25 Acceptable MAPEP-10-RdV22 3 rd/ 2010 Vegetation Bq/sam pie Manganese-54 0.004 0.00 --- Acceptable MAPEP-10-RdV22 3 d / 2010 Vegetation Eq/sample Plutonium-238 0.149 0.160 0.112 - 0.208 Acceptable MAPEP-10-RdV22 3 d/ 2010 Vegetation Eq/sample Plutonium-239/240 0.0026 0.0008 --- Acceptable MAPEP-10-RdV22 3 d / 2010 Vegetation Bq/sample Strontium-90 0.033 0.00-------------Acceptable MAPEP-10-RdV22 3 / 2010 Vegetation Eq/sample Uranium-234/233 0.184 0.216 0.151i-_0q28 Acceptable MAPEP-10-RdV22 3 ~d/ 2010 Vegetation Eq/sample Uranium-238 0.184 0.223 016-020 Acceptable MAPEP-10-RdV22 3 d /2010 Vegetation Eqsml ic6 .4 .0 49-.3 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 33 of 51 TABLE 4 2010 ERA PROGRAM PERFORMANCE EVALUATION RESULTS

SUMMARY

Sample Quarter/ Sample GEL Known Acceptance Number Year Media Unit Analyte / Nuclide Value value Range/ Ratio Evaluation RAD -80 1st/2010 Water pCi/L Barium-133 73.5 72.9 61.0-80.2 Acceptable RAD - 80 1t/ 2010 Water pCi/L Cesium-134 69.2 63.4 51.5-69.7 Acceptable RAD- 80 1 / 2 0 10 Water pCi/L Cesium-137 118.0 120 108-134 Acceptable RAD - 80 15/2010 Water pCi/L Cobalt-60 87.7 90 81 - 101 Acceptable RAD - 80 1s/2010 Water pCi/L Zinc-65 213.0 210 189-246 Acceptable RAD -80 1" /2010 Water pCi/L Gross Alpha 51.3 42.5 22.0-53.9 Acceptable RAD - 80 1s/ 2010 Water pCi/L Gross Beta 52.0 54.2 37.0 -61.1 Acceptable RAD - 80 1s/ 2010 Water pCi/L Radium-226 16.9 17.8 13.2-20.3 Acceptable RAD - 80 1 / 2010 Water pCi/L Radium-228 20.4 18.2 12.3-21.8 Acceptable RAD - 80 1" /2010 Water pCi/L Uranium (Nat) 49.0 50.2 40.7- 55.8 Acceptable RAD - 80 1s/2010 Water ug/L Uranium (Nat) Mass 67.3 73.2 59.4-81.4 Acceptable RAD -80 1s /2010 Water pCi/L Tritium 19200 18700 16400-20600 Acceptable RAD - 80 1" /2010 Water pCi/L Strontium-89 37.9 53.3 42.3-60.9 Not Acceptable RAD - 80 1"/ 2010 Water pCi/L Strontium-90 52.3 42.2 31.1 -48.4 Not Acceptable RAD -80 1t /2010 Water pCi/L Iodine-131 30.5 28.2 23.5-33.1 Acceptable RAD- 82 3 'd/ 2 0 1 0 Water pCi/L Barium-133 112.0 89.1 75.0-98.0 Not Acceptable RAD - 82 3 d / 2010 Water pCi/L Cesium-134 115.0 88.3 72.4 -97.1 Not Acceptable RAD - 82 3 rd /2010 Water pCi/L Cesium-137 271 210 189-232 Not Acceptable RAD - 82 3 d/ 2010 Water pCi/L Cobalt-60 98.4 72.8 65.5- 82.5 Not Acceptable RAD -82 3 d / 2010 Water pCi/L Zinc-65 161 110 99.0- 131 Not Acceptable RAD - 82 3 rd/ 2010 Water pCi/L Gross Alpha 65.5 61.1 32.0 - 75.9 Acceptable RAD - 82 3 rd

/ 2010 Water pCi/L Gross Beta 56.7 56.4 38.6 - 63.6 Acceptable RAD - 82 3 rd /2010 Water pCi/L Radium-226 15.9 17.1 12.7- 19.6 Acceptable RAD - 82 3 rd/ 2010 Water pCi/L Radium-228 18.9 16.1 10.8 - 19.4 Acceptable r

RAD - 82 3 d /2010 Water pCi/L Uranium (Nat) 58.0 49.6 40.2 - 55.1 Not Acceptable RAD - 82 3 rd / 2010 Water ug/L Uranium (Nat) Mass 89.1 72.3 58.7-80.4 Not Acceptable RAD - 82 3 rd /2010 Water pCi/L Tritium 18500 19800 17300- 21700 Acceptable RAD - 82 3 d /2010 Water pCi/L Strontium-89 60.6 55.3 44.1-62.9 Acceptable RAD - 82 3 d /2010 Water pCi/L Strontium-90 47.1 32.8 24.0 - 38.0 Not Acceptable RAD - 82 3 d / 2010 Water pCi/L Iodine-131 32.2 28.4 23.6- 33.3 Acceptable 090710N 3 d /2010 Water pCi/L Barium-133 86.9 92.9 78.3-102 Acceptable 090710N 3 rd / 2010 Water pCi/L Cesium-134 93.8 79.4 65.0 - 87.3 Not Acceptable 090710N 3 rd/ 2010 Water pCi/L Cesium-137 55.5 54.6 49.1 -62.9 Acceptable 090710N 3 d / 2010 Water pCi/L Cobalt-60 120.0 117 105 - 131 Acceptable 090710N 3 d 2010 Water pCi/L Zinc-65 129 99.5 89.6-119 Not Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 34 of 51 Sample Quarter / Sample GEL Known Acceptance Number Year Media Unit Analyte /Nuclide Value value Range/ Ratio Evaluation 0907ION 3 rd/2010 Water ug/L Uranium (Nat) Mass 48.6 49.3 39.8-55.1 Acceptable RAID - 83 4"' /2010 Water pCi/L Strontium-89 65.3 68.5 55.8-76.7 Acceptable RAD - 83 4"' /2010 Water pCl/l- Strontium-90 41.5 43 31.7 -49.3 Acceptable 10051ON 4"' /2010 Water pCi/L Strontium-89 49.9 51.4 40.6 -58.9 Acceptable 10051ON 4"' /2010 Water pCi/L Stronflum-90 35.4 41.3 30.4 -47.5 Acceptable 112210FIl 4"' /2010 Water pC!/L Barium-133 66.3 65.9 54.9-72.5 Acceptable 112210H1 4"' /2010 Water pCi/L Cesium-134 - 71.6 71.6 58.4-78.8 Acceptable 1122101-1 4"' /2010 1Water pCl/L Cesium-137 151 146 131 -163 Acceptable 1122101-11 4"' /2010 Water pCj/I- Cobalt-60 90.2 84.5 76.0-95.3 Acceptable 1122101-1 4"' /2010 Water pCJ/L Zinc-65 207 186 167-219 Acceptable 1122101-2 4"' /2010 Water pCi/L Plutonium-238 102.0 108 81.7-134 Acceptable 1122101-2 4"' /2010 Water PCI/L Plutonium-239 77.6 86.3 66.8-107 Acceptable 122810P 4"' /2010 Water pCi/ll Barium-133 70.9 68.9 57.5-75.8 Acceptable 122810P 4"' / 2010 Water pCi/L Cesium-134 43.0 43.2 34.5-47.5 Acceptable 122810P 4"' /2010 Water pC1/L Cesium-137 122 123 Ill -138 Acceptable 122810P 4"' /2010 Water pCi/L Cobalt-60 58.7 53.4 48.1 -61.3 Acceptable 122810P =4"'

/2010 Water pCi/L Zinc-65 116 102 91.8-122 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 35 of 51 TABLE 5 2010 ERA PROGRAM (MRAD) PERFORMANCE EVALUATION RESULTS

SUMMARY

Sample Quarter I Sample GEL Known Acceptance Number Year Media Unit Analyte / Nuclide Value value Range/ Ratio Evaluation MRAD-12 2"' /2010 Soil pCi/kg Actinium-228 1570 1850 1190-2600 Acceptable MRAD-1 2 2 "' /2010 Soil pCi/kg Americium-241 1130 1500 896 -1930 Acceptable MRAD-12 2 "d /2010 Soil pCi/kg Bismuth-212 1430 1640 430-2450 Acceptable MRAD-12 2"' / 2010 Soil pCi/kg Bismuth-214 1080 1410 1865-2030 Acceptable MRAD-12 2 n, / 2010 Soil pCi/kg Cesium-134 3040 3110 2000-3740 Acceptable MRAD-12 2 n, / 2010 Soil pCi/kg Cesium-137 4330 4440 3400-5770 Acceptable MRAD-12 2 nd /2010 Soil pC!/kg Cobalt-60 2120 2140 1560-2870 Acceptable MRAD-12 2 nd /2010 Soil pC!/kg Lead-212 1540 1520 980-2140 Acceptable MRAD-12 2d /2010 Soil ipCi/kg Lead-214 1300 1440 862-2140 Acceptable MRAD-12 2d /2010 Soil pCi/kg Manganese-54 < 22.9 0 --- Acceptable MRAD-12 2"~ /2010 Soil pCi/kg Potassium-40 11100 10900 7900- 14800 Acceptable MRAD-12 2 d /2010 Soil pCi/kg Thorium-234 1600 1610 511 -3070 Acceptable MRAD-12 2 d /2010 Soil pCi/kg Uranium-238 1600 1610 984-2040 Acceptable MRAD-12 2" / 2010 Soil pCi/kg Zinc-65 2790 2470 1960-3310 Acceptable MRAD-12 2 d /2010 Soil pCi/kg Strontium-90 7870 8180 2960-13300 Acceptable MRAD-1 2 2nd / 2010 Soil pCi/kg Uranium-234 < 1158 1620 1030- 2010 Not Acceptable MRAD-12 2nd / 2010 Soil pC!/kg Uranium-238 908 1610 984 -2040 Not Acceptable MRAD-12 2 "d / 2010 Soil ug/kg Uranium-Total (mass) 2920 4820 2650-6060 Acceptable MRAD-12 2n, / 2010 Soil pC!/kg Strontium-90 7870 8180 2960- 13300 Acceptable MRAD-1 2 2 nd / 2010 SoHl pCi/kg Americium-241 1120 1500 896 -1930 Acceptable MRAD-12 2 nd / 2010 Soil pCi/kg Plutonium-238 1360 1330 761 -1870 Acceptable MRAD-12 2 nd / 2010 Soil pCi/kg Plutonium-239 1220 1260 860- 1670 Acceptable MRAD-12 2 nd /12010 Soil pC!/kg Uranium-234 1230 1620 1030-2010 Acceptable MRAD-12 2 nd / 2010 Soil pC!/kg Uranium-238 1440 1610 984-2040 Acceptable MRAD-12 2nId / 2010 Soil pCi/kg Uranium-Total 2789 3300 1880-4460 Acceptable MRAD-12 2 nd / 2010 Soil ug/kg Uranium-Total (mass) 4350 4820 2650-6060 Acceptable MRAD-12 2nd / 2010 Vegetation pCi/kg Uraniurn-238 1604 1710 1200-2160 Acceptable MRAD-12 2n, / 2010 Vegetation ug/kg Uranium-Total (mass) 5270 5120 3520-6610 Acceptable MRAD-12 2n, / 2010 Vegetation pCi/kg Americium-241 2410 3140 1790-4310 Acceptable MRAD-12 2nd / 2010 Vegetation pCi/kg Curlum-244 429 528 260- 822 Acceptable MRAD-12 2 Id /12010 Vegetation pCi/kg Plutonium-238 3090 3040 1640-4450 Acceptable MRAD-12 2 d /2010 Vegetation pCi/kg Plutonium-239 2830 2800 1740-3820 Acceptable MRAD-12 2 d / 2010 Vegetation pCi/kg Uranium-234 1680 1720 1180-2280 Acceptable MRAD-12 2 "d / 2010 Vegetation pCi/kg Uranium-238 1770 1710 1200-2160 1Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 36of 51 Sample Quarter/ Sample GEL Known Acceptance Number Year Media Unit Analyte INuclide Value value Range/ Ratio Evaluation MRAD-12 2 d /2010 Vegetation pCi/kg Uranium-Total (mass) 5290 5120 3520-6610 Acceptable MRAD-12 2"' /2010 Vegetation pC!/kg Americium-241 3600 3140 1790-4310 Acceptable MRAD-12 2 "d /2010 Vegetation pC!/kg Cesium-134 1750 1670 956 -2310 Acceptable MRAD-12 2 d / 2010 Vegetation pCi/kg Cesium-137 1550 1470 1080-2040 Acceptable MRAD-12 2nd / 2010 Vegetation pCi/kg Cobalt-60 2100 1970 1330-2830 Acceptable MRAD-12 2 "d /2010 Vegetation pCi/kg Manganese-54 < 9.6 0.00 --- Acceptable MRAD-12 2 d /2010 Vegetation pCi/kg Potassium-40 40800 34900 25100 -49400 Acceptable MRAD-12 2 d /2010 Vegetation pCi/kg Uranium-238 < 1240 1710 1200-2160 Not Acceptable MRAD-12 2 "d / 2010 Vegetation pCi/kg Zinc-65 1630 1360 983- 1860 Acceptable MRAD-12 1 2 n1 /2010 Vegetation pCi/kg Strontium-90 7880 9120 5100-12100 Acceptable MRAD-12 1 2 nd / 2010 Air Filter pCi/Filter Uranium-238 61.5 61.5 39.4-87.3 Acceptable MRAD-12 2 "d / 2010 Air Filter ug/Filter Uranium-Total (mass) 183 184 114- 264 Acceptable MRAD-12 2 d /2010 1Air Filter pCi/Filter Americium-241 52.7 60.0 35.1 -82.3 Acceptable MRAD-12 2n' /2010 Air Filter pCi/Filter Plutonium-238 63.9 64.1 44.0-84.3 Acceptable MRAD-12 2 d /2010 Air Filter pCi/Filter Plutonium-239 56.6 56.7 41.1 -73.4 Acceptable MRAD-12 2 n' /2010 Air Filter pCi/Filter Uranium-234 68.8 62.1 39.1 -92.0 Acceptable MRAD-12 2nd /2010 Air Filter pCl/Filter Uranium-238 69.5 61.5 39.4-87.3 Acceptable MRAD-12 2nd/2010 Air Filter pCl/Filter I Uranium-Total 141 126 64.4-200 Acceptable MRAD-12 2n' / 2010 1Air_Filter ug/Filter Uranium-Total (mass) 208 184 114- 264 Acceptable MRADJ-12 2 n / 2010 Air Filter pCi/Filter Americium-241 76 60 35.1 -82.3 Acceptable MRAD-12 2 d / 2010 Air Filter pCi/Filter Cesium-134 504 436 284- 540 Acceptable MRAD-12 2" / 2010 Air Filter pCi/Filter Cesium-137 785 701 527-921 Acceptable MRAD-12 2"_/ 2010 Air Filter pCi/Filter Cobalt-60 591 523 405-653 Acceptable MRAD-12 2 "d / 2010 Air Filter pCi/Filter Manganese-54 < 5.07 0.00 --- Acceptable MRAD-12 2 "d/ 2010 Air Filter pCi/Filter Uranium-238 < 61.2 61.5 39.4-87.3 Acceptable MRAD-12 2 "' / 2010 Air_Filter pCi/Filter Zinc-65 462 389 269- 539 Acceptable MRAD-12 2 "d / 2010 Air Filter pCi/Filter Strontium-90 178 187 82.3-291 Acceptable MRAD-12 2 0' / 2010 Air Filter pCi/Fiter Iron-55 375 1359 158-559 Acceptable MRAD-12 2 "d / 2010 Air Filter ug/Filter Uranium-Total (mass) 175 184 114 - 264_ Acceptable MRAD-12 12" / 2010 Air Filter pCi/Filter 1 Gross Alpha 68.2 79.6 1 41.3- 120 Acceptable MRAD-12 1 2 "' / 2010 Air Filter pCi/ffillter Gross Beta 72 70.4 43.4- 103 Acceptable MRAD-12 2 "d / 2010 Water pC/ Uranium-238 67.9 _ 60.9 46.5- 75.5 Acceptable MRAD-12 2n' / 2010 Water ug/L Uranium-Total (mass) 213 182 143-225 Acceptable MRAD-12 2 "d / 2010 Water pCi/ Americium-241 79.1 95.6 65.5- 129 Acceptable MRAD-12 2 "d / 2010 Water pC!IL Plutonium-238 79.5 109 82.4- 135 Not Acceptable MRAD-12 2 d /2010 Water pCi/L Plutonium-239 103 105 81.2-130 Acceptable MRAD-12 2 d /2010 Water pC/ Uranium-234 62.4 61.4 46.3- 79.2 Acceptable MRAD-12 2 "d /2010 Water pCll Uranium-238 66.1 60.9 46.5- 75.5 Acceptable MRAD-12 2 d /2010 Water pC/ Uranium-Total 131.5 125 90.0-166 1Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 37 of 51 Sample Quarter I Sample GEL Known Acceptance Number Year Media Unit Analyte / Nuclide Value value Range/ Ratio Evaluation MRAD-1 2 2" / 2010 Water pCi/L Americium-241 123 95.6 65.5- 129 Acceptable MRAD-12 2 d /2010 Water pCi/L Cesium-134 454 417 308-479 Acceptable MRAD-12 2 d /2010 Water pC!/L Cesium-137 693 654 556-783 Acceptable MRAD-12 2 / 2010 Water pCi/L Cobalt-60 813 727 633-859 Acceptable MRAD-12 2 d /2010 Water pCi/L Manganese-54 < 7.7 0.00 --- Acceptable MRAID-12 2 "d / 2010 Water pC1/L Uranium-238 < 155 60.9 46.5-75.5 Not Acceptable MRAD-12 2 d / 2010 Water pCi/L Zinc-65 632 533 452-664 Acceptable MRAD-12 2 nd / 2010 Water pCi/L Strontium-90 708 719 456-961 Acceptable MRADJ-13 4"' /2010 Soil pC!/kg Actinium-228 1460 1830 1170-2580 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Americium-241 845 1120 669- 1440 Acceptable MRAD-13 4"' / 2010 Sol] pCi/kg Bismuth-212 < 538 2070 543 -3100 Not Acceptable MRAD-13 4"' /2010 Soil pCi/kg Bismuth-214 818 983 603-1410 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Cesium-134 2230 2240 1440-2700 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Cesium-137 3400 3530 2700-4580 -Acceptable MRAD-13 4"' /2010 Soil pCi/kg Cobalt-60 4580 4780 3480-6420 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Lead-212 1550 1640 1060-2310 Acceptable MRAD-13 4"' /2010 Soil pC!/kg Lead-214 1030 969 580-1440 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Manganese-54 < 38.0 0.00 --- Acceptable MRAD-13 4"h / 2010 Soil pC!/kg Potassium-40 10500 10700 7760 -14500 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Thorium-234 1010 1340 425-2550 Acceptable MRAD-13 4"' / 2010 Soil pC!/kg Uranium-238 1010 1340 819- 1700 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Zinc-65 2420 2300 1820-3080 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Americium-241 928 1120 669-1440 Acceptable MRAD-13 4"' /2010 Soil pC!/kg Plutonium-238 1170 1280 733-1800 Acceptable MRAD-13 4"' /2010 Soil pC!/kg Plutonium-239 1070 1180 805-1570 Acceptable MRAD-13 4"' /2010 SoHl pCi/kg Uranium-234 899 1360 862 -1690 Acceptable MRAD-13 4"' /2010 Soil pCI/kg Uranium-238 1080 1340 819-1700 Acceptable MRAD-13 4"' / 2010 Soil pC!/kg Uranium-Total 2027.4 2770 1580-3740 Acceptable MRAD-13 4"' / 2010 Soil ug/kg Uranium-Total (mass) 3240 4040 2220- 5080 Acceptable MRAD-1 3 4"' /2010 Soil pCi/kg Uranium-234 1190 1360 862 -1690 Acceptable MRAD-13 4"' /2010 Soil pCi/kg Uranium-238 903 1340 819-1700 Acceptable MRAD-13 4"' /2010 Soil ug/kg Uranium-Total 2093 2770 1580-3740 Acceptable MRAD-13 4"' / 2010 Soil pCi/kg Uranium-Total (mass) 2685 4040 2220-5080 Acceptable MRAD-13 4"' /2010 Soil pCi/kg Uranium-234 1110 1360 862-1690 Acceptable MRAD-13 4"' / 2010 Soil PCi/kg Uranium-238 1090 1340 819-1700 Acceptable MRAD-1 3 4"' / 2010 Soil pC/kg Uranium-Total 2253 2770 1580 -3740 Acceptable MRAD-13 4"' /2010 Soil ug/k Uraiu-_Total (mass) 3241 4040 2220-5080 Acceptable MRAD-13 4"h /2010 Soil ug/kg Uranium-Total (mass) 2820 4040 2220-5080 Acceptable MRAD-13 4"' / 2010 Soil IpC!/kg Strontium-90 10953 9270 3350 -15100 1 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 38 of 51 Sample Quarter / Sample GEL Known Acceptance Number Year Media Unit Analyte / Nuclide Value value Range/ Ratio Evaluation MRAD-13 4" /2010 Vegetation pCi/kg Plutonium-238 3740 4740 2560-6940 Acceptable MRAD-13 4' / 2010 Vegetation pCi/kg Plutonium-239 3590 4470 2770-6100 Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Uranium-234 3600 4010 2750-5320 Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Uranium-238 4000 3980 2800-5030 Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Uranium-Total 7834 8180 5620 - 10600 Acceptable MRAD-13 4" /2010 Vegetation ug/kg Uranium-Total (mass) 12000 11900 8180-15400 Acceptable MRAD-13 4' /2010 Vegetation pCi/kg Cesium-134 1200 1040 595-1440 Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Cesium-137 1420 1260 924-1750 Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Cobalt-60 1130 1010 683-1450 Acceptable h

MRAD-13 4 /2010 Vegetation pCi/kg Manganese-54 <39.8 0.00 ----- Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Potassium-40 29000 22600 16200- 32000 Acceptable MRAD-13 4' /2010 Vegetation pCi/kg Zinc-65 1380 1210 874-1650 Acceptable MRAD-13 4" /2010 Vegetation pCi/kg Strontium-90 9800 7810 4360 - 10400 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Uranium-234 73.5 71.8 45.2-106 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Uranium-238 75.5 71.2 45.6 -101 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Uranium-Total 149 146 74.6 -232 Acceptable MRAD-13 4"' /2010 Air Filter ug/Filter Uranium-Total (mass) 224.5 213 132-306 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Americium-241 70.1 74.1 43.3- 102 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Plutonium-238 70.8 72.9 50.0 -95.8 Acceptable MRAD-13 4' / 2010 Air Filter pCi/Filter Plutonium-239 65.6 69.6 50.5 -90.1 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Uranium-234 69.9 71.8 45.2-106 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Uranium-238 66.8 71.2 45.6-101 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Uranium-Total 142 146 74.6 -232 Acceptable MRAD-13 4" /2010 Air Filter ug/Filter Uranium-Total (mass) 201 213 132-306 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Cesium-134 405 388 253 -480 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Cesium-137 532 514 386 -675 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Cobalt-60 531 479 371 - 598 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Manganese-54 < 3.58 0.00 ----- Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Zinc-65 552 465 322 -644 Acceptable MRAD-13 4" / 2010 Air Filter pCi/Filter Strontium-90 80.2 159 70.0-247 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Iron-55 707 626 275- 974 Acceptable MRAD-13 4" /2010 Air Filter ug/Filter Uranium-Total (mass) 192 213 132 -306 Acceptable MRAD-13 4" /2010 Air Filter pCi/Filter Gross Alpha 74.2 52.3 27.1 -78.7 Acceptable h

MRAD-13 4 /2010 Air Filter pCi/Filter Gross Beta 55.6 52.7 32.5-77.0 Acceptable MRAD-13 4 h /2010 Water pCi/L Uranium-234 106 109 82.2-140 Acceptable MRAD-13 4"' /2010 Water pCi/L Uranium-238 107 108 82.5- 134 Acceptable MRAD-13 4" /2010 Water pCi/L Uranium-Total 218 221 159-294 Acceptable MRAD-13 4" /2010 Water ug/L Uranium-Total (mass) 318 323 253-399 Acceptable MRAD-13 4" /2010 Water pCi/L Americium-241 164 176 120-238 Acceptable

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 39 of 51 Sample Quarter I Sample GEL Known Acceptance Number Year Media - Unit Analyte /Nuclide Value value Range/ Ratio Evaluation MRAD-13 4"' /2010 Water pCi/L Plutonium-239 136 148 114-183 Acceptable MRAD-13 4"' /2010 Water pCi/L Uranium-234 106 109 82.2-140 Acceptable MRAD-13 4t' /2010 Water pC1/L Uranium-238 114 108 82.5 -134 Acceptable MRAD-13 4"' /2010 Water pCl/L Uraniumi-Total 226.8 221 159 -294 _ Acceptable MRAD-13 14"' /2010 Water ug/L Uranium-Total (mass) 342 323 253-399 Acceptable MRAD-13 4"' /2010 Water pCi/L Americium-241 178 176 120-238 Acceptable MRAD-13 4"' /2010 Water pCl/L Cesium-134 495 492 363-565 Acceptable MRAD-13 4"' /2010 Water pCi/L Cesium-137 620 625 531 -749 Acceptable MRAD-13 4"' /2010 Water pCi/L Cobalt-60 732 714 622- 844 Acceptable MRAD-13 4"' /2010 Water pCl/L Manganese-54 <5 0.00 --- Acceptable MRAD-13 4"' / 2010 Water pCl/L Zinc-66 557 489 1 414-610 Acceptable MRAD-13 4"' /2010 Water pCl/L Strontium-90 817 921 585- 1230 Acceptable MRAD-13 4"' / 2010 Water pCl/L Uranium-234 104 109 82.2- 140 Acceptable MRAD-13 4"' / 2010 Water pCl/L Uranium-238 108 108 82.5- 134 Acceptable MRAD-13 14"' / 2010 Water piL Uranium-Total 217 221 159-294 Acceptable MRAD-13 4"' /2010 Water ug/L Uranium-Total (mass) 321 323 253-399 Acceptable MRAD-13 4"' / 2010 Water pCi/L Iron-55 1220 825 480-1100 Acceptable MRAD-13 4"' /2010 Water pCi/L Gross Alpha 145 146 64.8-216 Acceptable MRAD-13 4"' /2010 Water pCl/L Gross Beta 171 143 83.6-210 1 Acceptable MRAD-13 4"' /12010 Water pCi/L Tritium 20900 21600 14100 -31900 Acceptable

ELaboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 40 of 51 TABLE 6 2010 NEW YORK STATE DEPARTMENT OF HEALTH ENVIRONMENTAL LABORATORY APPROVAL PROGRAM (NYSDOH ELAP) PROFICIENCY TEST RESULTS

SUMMARY

Quarter / Sample GEL Known Acceptance Sample Number Year Media Unit Analyte / Nuclide Value value Range/ Ratio Evaluation n

NY-332 3263 2" /2010 Water pCi/L Gross Alpha 33.0 26.8 15.0-38.6 Acceptable NY-332 3263 2nd /2010 Water pCi/L Gross Beta 64.6 54.0 41.3- 66.7 Acceptable NY-332 3262 2 nd /2010 Water pCi/L Cesium-134 14.8 14.0 10.7- 17.3 Acceptable NY-332 3262 2"d / 2010 Water pCi/L Barium-133 27.8 25.6 20.6 -30.5 Acceptable NY-332 3262 2nd /2010 Water pCi/L Zinc-65 146 139 121 - 156 Acceptable nd NY-332 3262 2 / 2010 Water pCi/L Cobalt-60 98.3 99.5 90.3 -109 Acceptable NY-332 3262 2"d / 2010 Water pCi/L Cesium-137 124 123 112 - 134 Acceptable "d

NY-332 3264 2 / 2010 Water pCi/L Iodine-131 23.4 26.4 21.9- 31.0 Acceptable NY-332 3264 2"d /2010 Water pCi/L lodine-131 26.8 26.4 21.9 -31.0 Acceptable "d

NY-332 3261 2 /2010 Water pCi/L Strontium-89 46.7 41.9 33.4 -50.4 Acceptable NY-332 3261 2"d/ 2010 Water pCi/L Strontium-90 33.9 34.8 27.1 -42.5 Acceptable NY-332 3266 2nd/2010 Water pCi/L Tritium 9610 9490 8390 -10600 Acceptable NY-332 3265 2nd / 2010 Water pCi/L Radium-226 12.1 13.2 10.4- 16.0 Acceptable NY-332 3265 2nd /2010 Water pCi/L Radium-228 9.90 8.91 6.08- 11.7 Acceptable d

NY-332 3265 2" / 2010 Water pCi/L Uranium (activity) 48.81 44.7 37.9 -51.4 Acceptable NY-337 3763 4 / 2010 Water pCi/L Gross Alpha 32.8 41.6 24.3- 58.9 Acceptable NY-337 3763 4 / 2010 Water pCi/L Gross Beta 29.3 27.5 18.3 -36.7 Acceptable NY-337 3762 4 h / 2010 Water pCi/L Cesium-134 51.0 42.0 35.8 -49.2 Not Acceptable NY-337 3762 4 h / 2010 Water pCi/L Cesium-137 29.3 27.3 22.4 -32.1 Acceptable h

NY-337 3762 4" /2010 Water pCi/L Cobalt-60 13.6 13.2 9.72-16.7 Acceptable NY-3373762 4' /2010 Water pCi/L Zinc-65 134 122 104-138 Acceptable NY-337 3762 4 h / 2010 Water pCi/L Barium-133 50.5 50.9 43.3 -59.4 Acceptable NY-337 3764 4" /2010 Water pCi/L lodine-131 13.4 18.2 14.7 -21.7 Not Acceptable NY-337 3764 4" /2010 Water pCi/L lodine-131 13.5 18.2 14.7- 21.7 Not Acceptable NY-337 3761 4 / 2010 Water pCi/L Strontium-89 47.8 61.3 51.3 - 71.4 Not Acceptable NY-337 3761 4" / 2010 Water pCi/L Strontium-90 12.0 14.9 11.0 - 18.8 Acceptable NY-337 3766 4 / 2010 Water pCi/L Tritium 14400 15300 13500 - 17000 Acceptable NY-337 3765 4" / 2010 Water pCi/L Radium-226 13.2 10.6 8.30- 12.9 Not Acceptable NY-337 3765 4" / 2010 Water pCi/L Radium-228 6.51 6.07 3.91 -8.22 Acceptable NY-337 3765 4" /2010 Water pCi/L Uranium (activity) 17.5 16.0 13.2- 18.7 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 41 of 51 FIGURE 1 COBALT-60 PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Cobalt-60 Performance Evaluation Results and % Bias 150.0 130.0 110.0 i 90.0 Co-60 70.0 M - -- - -Lower Control 50.0 Limit

- Upper Control 30.0 Limit 10,0

-10.0

-30.0

-50.0 2010 Analytical Date

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 42 of 51 FIGURE 2 CESIUM-137 PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Cesium-137 Performance Evaluation Results and % Bias 100.0-  !

80.0 60

.0 Cs-137 S40.0 - ------ Lower Control SLimit 0.0 . ------ Upper Control 20.0 -Limit 0.0

-20.0

-40.0 2010 Analytical Date

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 43 of 51 FIGURE 3 TRITIUM PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Tritium Performance Evaluation Results and % Bias 50.0 30.0 H-3 10.0

---

Lower Control i Limit S---- Upper Control

-10.0 Limit

-30.0

-50.0 2010 Analytical Date

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 44 of 51 FIGURE 4 STRONTIUM-90 PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Strontium-90 Performance Evaluation Results and % Bias 60.0 40.0 20.0 Sr-90

- - Lower Control 0.0 Limit S - - Upper Control Limit

-20.0

-40.0-

-60.0 2010 Analytical Date

d Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 45 of 51 FIGURE 5 GROSS ALPHA PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Gross Alpha Performance Evaluation Results and % Bias 100.0 80.0 60.0 40.0 i --- Gross Alpha 20.06

) - - Lower Control S0.0 Limit o ------ Upper Control

-20.0 Limit

-40.0-

-60.0

-80.0

-100.0 2010 Analytical Date

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 46 of 51 FIGURE 6 GROSS BETA PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Gross Beta Performance Evaluation Results and % Bias 100.0 80.0 60.0 40.0 SGross Beta 20.0 M'*!* ----- Lower Control U0.0 Limit

-20.0 - Upper Control

-2Limit 40.0

-60.0 -iiiii

-80.0

-100.0 2010 Analytical Date

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 47 of 51 FIGURE 7 IODINE-131 PERFORMANCE EVALUATION RESULTS AND % BIAS 2010 Iodine-131 Performance Evaluation Results and % Bias 40.0-20.0 0.0 1-131

-20.0 ----- Lower Control

- - Limit

- -- Upper Control

-40.0 -Limit

-60.0 -

-80.0 -

-100.0 2010 Analytical Date

LaboratorieS LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 48 of 51 TABLE 7 GEL 2010 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

INTRA-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY MATRIX Bias Criteria (+/-f25%) Precision Criteria (%RPD)

Laboratory Control Sample Duplicate 2010 (LOS) (DUP or LCSD)

WITHIN OUTSIDE WITHIN OUTSIDE CRITERIA CRITERIA CRITERIA CRITERIA Air Particulate Gross Alpha/Beta 325 0 326 0 Americium-241 16 0 16 0 Iodine-131 247 0 249 0 Gamma 23 0 23 0 Strontium-90 15 0 15 0

-Air Crrde-1 J Iodine-131 i __] 01__ 0 Milk____ __ ______ ____ __ ________ _

Gamma 63 0 1 64 0 Iodine-131 61 0 61 0 Strontium-90 33 0 34 0 Solid _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Gamma 27 0 29 0 Carbon-1 4 2 0 2 0 Iron-55 3 0 3 0 Nickel-63 3 0 3 0 Strontium-90 11 0

• 11 0 Tissue ______________________

Gamma 38 0 36 0 Stronru-0 0 j 3 0 J

Vegetation_____________________________

Gamma (Including Iodine) 59 0 61 0 Strontium-90 3 J 0 j 3 [0 Water Carbon-14 2 0 2 0 Gross Alpha/Beta 98 0 99 0 Gamma 177 0 170 0 Iodine-1131 46 0 47 0 Iron-55 33 0 33 0 Nickel-63 35 0 35 0 Strontium-90 80 0 81 0 Tritium 176 0 174 0 Total: 1590 0 1591 0 Note 1: The RPID must be 20 percent or less, ifboth samples are greater than 5 times the MDC. If both results are less than 5 times MDC, then the RPD must be equal to or less than 100%. Ifone result is above the MDC and the other is below the MVDC,then the RPD can be calculated using the MVDC for the result of the one below the MVDC.The RPD must be 100% or less. In the situation Where both results are above the MDC but one result is greater than 5 times the MDC and the other isless than 5 times the MVDC, the RPD must be less than or equal to 20%. Ifboth results are below MDC, then the limits on % RPD are not applicable.

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 49 of 51 TABLE 8 GEL 2010 RADIOLOGICAL INTRA-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY MATRIX INSTRUMENT LCS DUP LCS DUP LCS DUP LCS DUP ANALYSIS FILTER FILTER SWIPE SWIPE SOLID SOLID OIL OIL Americium-241 Alpha Spec 2 2 47 38 485 477 13 12 Americium-243 Alpha Spec 2 2 1 0 53 50 2 2 Carbon-14 Liquid Scintillation 4 3 38 32 98 99 9 9 Gamma (long list of isotopes) Gamma Spec 283 272 47 42 770 792 27 27 Gross Alpha/Beta Gas Flow 111 135 20 18 20 18 42 42 Iodine-129 Gamma Spec 99 88 28 28 28 28 9 9 Iodine-131 Gamma Spec 6 4 0 0 0 0 0 0 Iron-55 Liquid Scintillation 89 8 30 24 46 48 8 8 Alpha Spec and Isotopic Plutonium Liquid Scintillation 212 186 82 66 687 683 12 11 Isotopic Strontium Gas Flow 165 136 41 34 365 367 1 1 Isotopic Thorium Alpha Spec 82 59 0 0 371 372 0 0 Alpha Spec and ICP-Isotopic Uranium MS 137 112 13 10 713 697 24 24 Lead-210 Gas Flow 44 26 0 0 33 34 0 0 Nickel-59 Gamma Spec 65 60 28 22 64 64 7 7 Nickel-63 Liquid Scintillation 95 89 39 30 75 74 8 8 Neptunium-237 Alpha Spec 67 59 32 23 107 107 10 9 Polonium-210 Alpha Spec 18 6 0 0 5 6 0 0 Promethium-137 Liquid Scintillation 8 5 0 0 12 11 0 0 Radium-226 Lucas Cell 44 31 0 0 167 175 0 0 Radium-228 Gas Flow 29 25 0 0 129 124 0 0 Technetium-99 Liquid Scintillation 87 75 32 24 142 145 12 12 Tritium Liquid Scintillation 90 76 42 24 358 359 19 19 ANALYSIS INSTRUMENT MISC MISC MISC MiSC Americium-241 Alpha Spec 4 4 231 220 22 19 383 335 Americium-243 Alpha Spec 1 1 21 21 5 4 12 11 Carbon-14 Liquid Scintillation 5 5 110 108 34 33 218 175 Gamma (long list of isotopes) Gamma Spec 17 18 260 256 72 68 747 820 Gross Alpha/Beta Gas Flow 27 27 112 109 87 80 1169 1180 Iodine-129 Gamma Spec 1 1 88 88 21 21 162 94 Iodine-131 Gamma Spec 0 0 0 0 0 0 11 14 Iron-55 Liquid Scintillation 3 3 74 72 42 43 123 103 Alpha Spec or Liquid Isotopic Plutonium Scintillation 7 7 143 137 77 70 108 95 Isotopic Strontium Gas Flow 13 13 61 60 80 76 16 12 Isotopic Thorium Alpha Spec 13 13 145 132 8 8 289 359 Isotopic Uranium Alpha Spec 24 24 102 87 39 36 640 557 Lead-210 Gas Flow 0 0 0 0 0 0 114 108 Nickel-59 Gamma Spec 0 0 68 66 9 9 76 63 Nickel-63 Liquid Scintillation 5 5 74 72 50 51 172 143 Neptunium-237 Alpha Spec 3 3 0 0 16 15 193 168 Polonium-210 Alpha Spec 0 0 1 1 0 0 3 3 Promethium-137 Liquid Scintillation 1 1 5 5 3 3 6 2 Radium-226 Lucas Cell 2 2 25 25 5 5 502 505 Radium-228 Gas Flow 0 0 27 28 1 1 432 426 Technetium-99 Liquid Scintillation 15 15 179 175 39 40 41 41 Tritium Liquid Scintillation 9 9 125 122 8 8 898 824

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 50 of 51 TABLE 9 GEL 2010 CORRECTIVE ACTION

SUMMARY

GEL CORRECTIVE STATUS:

ACTION IDENTIFICATION OPEN/ ISSUE Cause and Disposition CLOSED CARR110209-542 OPEN Eckert & Ziegler Analytics Monitoring in progress Fe-59 Failure In Milk CARR100617-496 CLOSED MAPEP Series 22 PT The ICP-MS analysis of Uranium-235 Failures and Uranium-238 failure was attributed to the use of the less vigorous digestion method (EPA Method 3050B). After contacting RESL, GEL discovered that they had used a more rigorous total dissolution process.

The failure for Plutonium-238 was attributed to a data reviewer's error and lack of attention to detail to the region of interest that was not included in the data result. Approximately 400 additional counts should have been included. All analysts have been retrained on attention to detail of the ROI.

For the remaining isotopic failures, the error was attributed to analyst error and failure to follow the instructions from the PT provider.

CARR100617-497 CLOSED MRAD 12 PT Failures The ICP-MS analysis of Uranium-235 and Uranium-238 failure was attributed to the use of the less vigorous digestion method (EPA Method 3050B). After contacting RESL, GEL discovered that they had used a more rigorous total dissolution process.

For Uranium-238 in vegetation, air and water, the failure was attributed to method sensitivity by gamma spectroscopy. Future PT analysis will be performed using a more sensitive method.

CARR101210-527 CLOSED MRAD 13 PT Failures The failure for Bismuth-212 was attributed to a reporting error. The actual result (1660 pCilkg) was within the acceptance range. The failure of Iron-55 was attributed to matrix interference. An additional recount with a smaller aliquot and fresh reagent rinses removed the interferant.

SLaboratories LLC P.O. Box 30712, Charleston, SC 29417 2010 ANNUAL QUALITY ASSURANCE REPORT Page 51 of 51 CARR100318-487 CLOSED RAD-80 PT Failures The Gross Alpha failure was attributed to a concentrated iron carrier. The Strontium-89 and Strontium-90 failures were attributed to the associated weights of the carriers utilized during the preparation and analysis.

CARR100907-512 CLOSED RAD-82 PT Failures Failures of the Gamma Emitters and the Naturals (Uranium) were attributed to analyst error and failure to follow the instructions from the PT provider. The failure of Strontium-89 and Strontium-90 was attributed to analyst error while diluting the sample. All analysts were retrained to the proper processes.

CARR101203-525 CLOSED NY-337 PT Failures For Cesium-134, Iodine-131, Strontium-89 and Strontium-90, and Radium-226, the failures could not be determined. The laboratory continues to monitor results of internal quality control samples.