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Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report
	ML101200509
Person / Time
Site:	Fermi
Issue date:	04/28/2010
From:	Plona J; DTE Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NRC-10-0036
	Download: ML101200509 (234)
	v • d • e

Joseph H.

Joseph H. Plona Plana Site Site Vice President President N. Dixie 6400 N. Newport., MI 48166 Dixie Highway, Newport, 48166 Tel: 734.586.5910 Tel: 734.586.5910 Fax: 734.586.4172 734.58(i,4172 DTE Energy April 28, 28, 2010 2010 //

NRC-10-0036 NRC-10-0036 u.

U. S. Nuclear Regulatory Commission Nuclear Regulatory Commission Document Control Attention: Document Attention: Control Desk Desk Washington D Washington DC C 20555-0001 Fermi 2

References:

1) Fermi

References:

Docket No. 50-341 NRC Docket NRC License License No. NPF-43 License No. NPF-43

2) Facility Operating License 2)

Appendix Specifications 5.6.2 and 5.6.3 Appendix A, Technical Specifications

Subject:

Annual Radiological Environmental Annual Radiological Environmental Operating Report and Radioactive Radioactive Effluent Release Release Report Radiological Environmental The 2009 Annual Radiological Operating Report and The Radioactive Environmental Operating Radioactive Effluent Release Report for Fermi 2 are enclosed. These reports are being transmittep Effluent transmitted in Regulatory Guide accordance with Reference 2 and Regulatory accordance 1.21, Revision 1.

Guide 1.21, 1. The enclosed enclosed' reports cover the time period from January 1 through DecemberDecember 31, 31, 2009.

regarding these reports, please contact Mr.

questions regarding Should you have any questions Mr. David Radiological Engineering at (734) 586-5112.

Keskitalo, General Supervisor, Radiological Sincerely, Sincerely, Enclosures cc: NRC Project Manager [w/o Enclosures]

[w/Enclosures]

NRC Resident Office [wlEnclosures]

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

[w/Enclosures]

Regional Administrator, Region III [wlEnclosures]

Supervisor, Electric Operators,

[w/Enclosures]

Michigan Public Service Commission [wlEnclosures]

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report FERMI2 NUCLEAR POWER PLANT DETROIT EDISON COMPANY OPERATING LICENSE NO. NPF - 43 Fermi 2 - 2009 Annual Radioactive Effluent Release Report for the period of January 1, 2009 through December 31,2009 Prepared by:

Fermi 2 Radiological Engineering 1

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Table of Contents Page Executive Summary 4 Introduction 5 Noble Gases 5 Iodines and Particulates 5 Tritium 6 Plant Effluent Monitoring 6 Exposure Pathways to People 7 Dose Assessment 8 Radioactive EJJluent Monitoring Results 9 Summary of Radioactive Waste Shipments 12 Additional Required Information 13 Appendices 13 ODCM Monitors Out of Service 13 Outside Temporary Tanks 13 Meteorological Tables 13 Major Changes to Radioactive Waste Systems 13 Appendix A: Effluent and Radwaste Data 14 Regulatory Limits for Radioactive Ejjluents 15 Gaseous Ejjluents 15 Liquid Ejjluents 16 Measurements and Approximations of Total Activity in Radioactive Ejjluents 17 Gaseous Ejjluents 17 Fission and Activation Gases 17 Radioiodines 17 Particulates 18 Tritium 18 Gross Alpha 19 Liquid Ejjluents 19 Statistical Measurement Uncertainties 19 Gaseous Release by Individual Nuclide 19 Particulate Radionuclides (Curies) 20 Noble Gases (Curies) 21 Radioiodines (Curies) 21 Shipments ofRadwas te 21 Spent resins, sludges, etc. 21 Dry compressible waste, contaminated equipment, etc. 22 Irradiated components, control rods, etc. 23 Other 23 2

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Appendix B: Ground Water Protection Program Data and Analysis 24 List of Tables Page Table 1 Fission and Activation Gases (Noble Gases) Summary 9 Table 2 Radioiodines Summary 10 Table 3 Particulates Summary 10 Table 4 Tritium Summary 10 Table 5 2009 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 - 2009 Annual Radioactive Ejjluent Release Report Executive Summary This report is published to provide information regarding radioactive effluent monitoring at the Fermi 2 Nuclear Power Plant. The 2009 Annual Radioactive Effluent Release Report covers the period from January 1, 2009 through December 31, 2009.

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 releases ofliquid radioactive effluents from Fermi 2 in 2009. There has not been a liquid radioactive discharge from Fermi 2 since 1994. Data on radioactive isotopes released in gaseous effluents are contained in the body of the report and in Appendix A.

The highest potential single organ dose to a person living offsite due to iodines, particulates, and tritium released from the plant was calculated to be 0.07 mrem, which is 0.5% of the applicable limit found in 10 CFR 50, Appendix I.

During 2009, 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 2009.

Data on radioactivity contained in radwaste shipments to points offsite are contained in the body of the report and in Appendix A. Additional sections address whether there were any effluent monitors which were out of service for more than 30 days in 2009, any revisions to the Offsite Dose Calculation Manual, or any major changes in radwaste processmg.

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 2009 quarterly ground water sampling, from approximately 40 monitor wells around Fermi 2 (ground water sampling has been performed under this program since the fall of2007). 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.

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Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Introduction During the normal operation of a nuclear power plant, most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces which have been activated are present in the primary coolant water. The four types of radioactive material released are noble gases, iodine, particulates, and tritium.

Noble Gases Some of the fission products released in airborne effluents are radioactive 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 ofiodine-131 and iodine-133, which are radioisotopes of iodine with half1ives 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.

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Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report The main contribution of radioactive iodine to human radiation dose is to the thyroid gland, where the body concentrates iodine. This exposure results from inhalation or ingestion of these iodines. Radioactive cesiums and cobalts, when ingested or inhaled, contribute to radiation exposure of tissues such as the muscle, liver, and intestines. These iodines and particulates are also a source of external radiation exposure if deposited on the ground.

Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in radioactive 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 liquid radioactive waste discharges since 1994. Plant personnel are alert for evidence of unmonitored liquid tritium releases, but no such releases have been detected.

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 ofliquid and gaseous wastes which contain radioactivity. For example, the 2.0 and 2.2 minute holdup pipes delay the release of radioactive gases so that radioactive decay can occur prior to release. The offgas system provides additional delay for such gases.

Radioactivity monitoring systems are used to 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 - 2009 Annual Radioactive Ejjluent Release Report All wastes are evaluated to identify the specific concentrations of radionuclides being released. Sampling and analysis provide a more sensitive and precise method of determining effluent composition than monitoring instruments.

A meteorological tower is located on the Fermi 2 site. It is linked to computers which record the meteorological data. This data is used in calculating dispersion and deposition factors, which are essentially dilution factors between plant release points and points offsite. Coupled with the effluent release data, these factors are used to calculate dose to the public.

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

Exposure Pathways to People Radiological exposure pathways define the methods by which people may become exposed to radioactive material. The major pathways of concern are those which could cause the highest calculated radiation dose. These projected pathways are determined from the type and amount of radioactive material released, the environmental transport mechanism, and the use of the environment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological 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 - 2009 Annual Radioactive Ejjluent 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. The doses calculated may be delivered to the whole body or to a specific organ. 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 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 ofliquid, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption). These calculations produce a conservative estimation of the dose.

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Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Radioactive E.fJluent Monitoring Results This section summarizes the results of effluent monitoring and offsite dose calculation for the year 2009. 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 releases ofliquid radioactive effluents from Fermi 2 in 2009. There has not been a liquid radioactive discharge from Fermi 2 since 1994. The 2009 gaseous effluent releases are summarized in the following tables. There were no abnormal releases of radioactive material, i.e., releases not performed in accordance with the Fermi 2 license and implementing procedures, in 2009.

The data in the following tables represent continuous and batch releases. In 2009, there were six containment purges in which radioactivity was detected. The total time for these purges was 6954 minutes. Based on recorded start and stop times, the shortest of these purges lasted 13 7 minutes, the longest lasted 2815 minutes, and the average purge length was 1159 minutes.

Note that some values in the following summary tables are preceded by the "less than" symbol. For gross alpha radioactivity releases, the "less than" value is in units of microcuries per cubic centimeter (/lCi/cc) and represents the lower limit of detection (LLD) value for a single sample.

Table 1 - Fission and Activation Gases (Noble Gases) Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (curies) 5.66E+00 2.07E+00 4.97E+00 1.70E+00 Average Release 7.28E-01 2.63E-01 6.25E-01 2.14E-01 Rate for Period

(/lCi/sec) 9

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Table 2 - Radioiodines Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total 1-131 9.S1E-04 3.19E-04 2.76E-04 1.44E-04 (curies)

Average Release 1.22E-04 4.06E-OS 3.47E-OS 1.81E-OS Rate for Period (f.l,Ci/sec)

Table 3 - Particulates Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Particulates with 1.17E-04 S.94E-04 9.88E-04 3.2SE-04 half lives> 8 days (curies)

Average l.S0E-OS 7.S6E-OS 1.24E-04 4.09E-OS Release Rate for Period (f.l,Ci/sec)

Gross Alpha <S.2E-1S <S.2E-1S <S.2E-1S <S.2E-1S Radioactivity (f.l,Ci/cc)

Table 4 - Tritium Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Release 2.0SE+01 1.42E+01 2. 80E+0 1 1.09E+01 (curies)

Average Release 2.63E+00 1.81E+00 3.S2E+00 1. 37E+00 Rate for Period (f.l,Ci/sec)

The offsite dose impact of the above releases was evaluated by calculating organ doses to the most highly exposed individual living near the plant due to 1-131,1-133, tritium, and particulates with half lives greater than 8 days. This exposure is assumed to be occurring via the pathways of inhalation, vegetation ingestion, and direct radiation from material deposited on the ground. The results of this calculation are shown in the following table:

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Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Table 5 2009 Gaseous Effluent Dose to Organ Receptor with Highest Single Organ Dose Bone 5.65E-03 mrem Liver 2.59E-02 mrem Thyroid 6.96E-02 mrem Kidney 2.59E-02 mrem Lung 2.58E-02 mrem GI-LLI 2.59E-02 mrem Total body 2.59E-02 mrem The highest single organ dose is 6.96E-02 mrem to the thyroid. This is 0.5% of the federal limit of 15 mrem specified in 10 CFR 50, Appendix I.

Another dose calculation normally performed on the above release data is that for gamma and beta air dose at the site boundary due to noble gases. In 2009, gamma air dose was 3.33E-03 mrad, 0.03% of the 10 mrad annual limit; beta air dose in 2009 was 3.23E-03 mrad, 0.02% 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 2009, there was no direct radiation dose attributed to the operation of Fermi 2 beyond the site boundary, based on analysis of offsite TLD readings. Also, as shown above, offsite dose due to effluents is a small fraction of the 40 CFR 190 limits. Therefore, Fermi 2 was in compliance with 40 CFR 190 in 2009.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s/year), and persons ice fishing on Lake Erie near the plant (240 hour0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months s/year), to be visitors. Using ODCM assumptions about these categories of visitors, the maximum potential dose to a visitor to Fermi 2 in 2009 was 2.40E-03 mrem to the maximally exposed organ (thyroid) and 1.70E-03 mrem to the total body.

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Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Summary of Radioactive Waste Shipments The radioactivity and volume of Fermi 2 solid waste received at the Clive, UT, facility in 2009 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 5.24E+01 j

cunes 2.20E+02 +/-25 Dry compressible waste, mJ 1.21E+02 contaminated equipment, etc. cunes 8.62E+00 +/-25 Irradiated components, control m 0 j

rods, etc. cunes 0 N/A Other mJ 0 cunes 0 N/A Radioactive solid waste shipments from Fermi 2 in 2009 (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 transportati on Spent resin, sludges, etc. 12 Tractor trailer EnergySolutions, Oak Ridge, TN with cask EnergySolutions, Clive, UT Dry compressible waste, 23 Tractor trailer EnergySolutions, Oak Ridge, TN contaminated equipment, etc.

Oil 1 Tractor trailer EnergySolutions, Oak Ridge, TN Mixed waste 1 Closed van Permafix (D.S.S.L), Kingston, TN 12

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Additional Required Information Appendices The contents of Appendix A, Effluent and Radwaste Data, are described on page 9. The Fermi 2 Integrated Groundwater Protection Program was implemented in the fourth quarter of2007. Appendix B contains a description of this program, sampling data, and a discussion of sampling results.

ODCM Revisions The ODCM was not revised once in 2009; therefore no ODCM appendix is included.

ODCM Monitors Out of Service The Offgas Radiation Monitor, Division 2, was out of service from January 6, 2009 to June 15,2009, and again from October 8,2009 to November 10, 2009. 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 2009 so that there was no loss of ability to monitor offgas radiation levels, and no compensatory sampling was required.

Outside Temporary Tanks No outside temporary tank exceeded the 10 curie content limit (excluding tritium and dissolved or entrained noble gases) in 2009.

Meteorological Tables Meteorological tables for 2009 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 2009 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 2009.

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Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Appendix A Effluent and Radwaste Data 14

Fermi 2 - 2009 Annual Radioactive Ejjluent 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 - 2009 Annual Radioactive Ejjluent 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 radionuc1ides 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 16

Fermi 2 - 2009 Annual Radioactive Ejjluent 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 I Fission and Activation Gases Samples are obtained from each of the six plant radiation monitors which continuously monitor the five ventilation exhaust points. The fission and activation gases are quantified by gamma spectroscopy analysis of periodic samples.

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

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

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

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

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Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report IlL Particulates Samples are obtained from each of the six plant effluent radiation monitors which continuously monitor the five ventilation exhaust points. The particulates are collected on a filter and then quantified by gamma spectroscopy analysis.

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

Quarterly, the filters from each ventilation release point are composited and then radiochemically separated and analyzed for strontium (Sr)-89/90.

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

IV. Tritium Samples are obtained from each of the six plant effluent radiation monitors which continuously monitor the five ventilation exhaust points. The sample is passed through a bottle containing water and the tritium is "washed" out to the collecting water. Portions of the collecting water are analyzed for tritium using liquid scintillation counting techniques. For each sample, the duration of sample and sample flow rate is used to determine the concentration. From the flow rate of the ventilation system, a release rate can be determined.

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

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Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report V. Gross Alpha The gaseous particulate filters from the six plant effluent radiation monitors are stored for one week to allow for decay of naturally occurring alpha emitters. These filters are then analyzed for gross alpha radioactivity by gas proportional counting, and any such radioactivity found is assumed to be plant related. The quantity of alpha emitters released can then be determined from sample flow rate, sample duration, and stack flow rate.

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

B. Liquid Effluents The liquid radwaste processing system and the liquid effluent monitoring system are described in the Fermi 2 UFSAR. Fermi 2 released no radioactive liquid effluents in 2009.

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 (~Ci/cc) for individual samples, and indicate that the nuclide in question was not detected in gaseous effluent samples in the indicated quarter of 2009. For quantities of gross alpha radioactivity and tritium in gaseous effluents, see Tables 3 and 4 on page 10 of this report.

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Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report A. Particulate Radionuclides (Curies)

Nuclide Quarter 1 Quarter 2 Quarter 3 Quarter 4 Mn-S4 1.03E-OS 4.63E-OS 1.9SE-04 2AlE-OS Co-S8 4.37E-06 1. 76E-OS 2.S2E-04 1. 89E-OS Co-60 6.03E-06 7.l6E-OS 1. 84E-04 2.S0E-OS Na-24 <lAE-ll <lAE-ll 3.28E-03 <lAE-ll Cr-Sl <8.2E-13 2.26E-04 9.20E-OS 7.77E-OS Zn-6S <4.3E-13 <4.3E-13 S.9lE-OS 8.74E-06 Zn-69m <1.0E-ll S.18E-OS lA7E-03 <1.0E-ll Tc-99m <3.3E-13 2.32E-OS 1.0lE-03 2.08E-OS Ba-139 9.62E-02 1.22E-02 2A4E-02 7.02E-02 La-140 SA7E-OS <lAE-12 <lAE-12 6.90E-OS Ba-140 7.l8E-06 <S.3E-13 <S.3E-13 4.SSE-OS Y-9lm 1.0SE-02 6.8SE-04 2.99E-03 1.00E-02 Rb-89 9.78E-03 <7.2E-ll <7.2E-ll <7.2E-ll Cs-138 3.32E-02 <3.8E-ll 3.l8E-03 4.66E-02 As-76 6AlE-03 4.2lE-03 3.S7E-03 9.76E-03 Br-82 7.04E-06 <1.lE-12 1.S0E-OS S.03E-06 Mn-S6 <lAE-ll <lAE-ll 9.32E-03 <lAE-ll Re-188 <1.lE-ll <1.lE-ll S.67E-OS <1.lE-ll Sr-89 8.93E-OS <lAE-14 3.99E-OS 3.77E-OS Sr-90 <6.7E-IS <6.7E-IS <6.7E-IS <6.7E-IS Fe-SS <S.2E-IS 2.32E-04 1.66E-04 8.69E-OS Cs-134 <4.6E-14 <4.6E-14 <4.6E-14 <4.6E-14 Cs-137 <2.3E-13 <2.3E-13 <2.3E-13 <2.3E-13 Ce-14l <1.8E-13 <1.8E-13 <1.8E-13 <1.8E-13 Ce-143 <1.6E-12 <1.6E-12 <1.6E-12 <1.6E-12 Ce-144 <6.2E-13 <6.2E-13 <6.2E-13 <6.2E-13 Total 1.56E-Ol 1.78E-02 5.03E-02 1.37E-Ol 20

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report B. Noble Gases (Curies)

Nuclide Quarter 1 Quarter 2 Quarter 3 Quarter 4 Ar-41 <1.OE-07 3.S8E-OI 1. 29E+00 6.77E-OI Kr-87 <1.SE-07 <1.SE-07 <1.SE-07 <1.SE-07 Kr-88 <7.7E-08 <7.7E-08 <7.7E-08 <7.7E-08 Kr-8Sm <3.0E-08 8.97E-02 4.89E-OI 2.07E-OI Xe-133 <7.SE-08 <7.SE-08 1. 72E-01 <7.SE-08 Xe-133m <1.7E-07 <1.7E-07 <1.7E-07 <1.7E-07 Xe-13S <2.SE-08 <2.SE-08 7.18E-02 <2.SE-08 Xe-13Sm 6.23E-OI 4.ISE-OI 8.34E-OI 3.32E-OI Xe-137 3.60E+00 <1.8E-06 <1.8E-06 <1.8E-06 Xe-138 1.44E+00 1.21E+00 2.IIE+00 4.88E-OI Total 5.66E+OO 2.07E+OO 4.97E+OO 1.70E+OO C. Radioiodines (Curies)

Nuclide Quarter 1 Quarter 2 Quarter 3 Quarter 4 1-131 9.SIE-04 3.19E-04 2.76E-04 1.44E-04 1-132 1.39E-02 7.0SE-04 4.38E-04 3.7IE-04 1-133 9.68E-03 1.46E-03 1.86E-03 9.39E-04 1-134 2.ISE-02 <2.9E-II 1. 13E-03 <2.9E-II 1-13S 1.30E-02 6.46E-04 8.80E-04 2.08E-04 Total 5.90E-02 3. 13E-03 4.58E-03 1.66E-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 2009.

a. Spent resins, sludges, etc. All waste in this category in 2009 was Class A waste and consisted of spent resins and sludges. It was shipped in 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.

21

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Spent resins, sludges, etc.

Activity Isotope mCi Percent Ag-110m 2.27E+01 0.01%

Ba-140 3.68E-01 0.00%

C-14 1. 18E+01 0.01% LLD Co-57 2.63E+00 0.00%

Co-58 9.65E+02 0.44%

Co-60 2.54E+04 11.54%

Cr-51 1. 27E+03 0.58%

Cs-134 1. 64E+02 0.07%

Cs-137 1.04E+03 0.47%

Fe-55 1.71E+05 77.52%

Fe-59 6.96E+02 0.32%

H-3 1. 67E+02 0.08%

1-129 1.40E+00 0.00%

1-131 1.34E-01 0.00%

La-140 1.61E-01 0.00%

Mn-54 1. 55E+04 7.02%

Nb-95 8.90E+00 0.00%

Ni-63 1. 73E+03 0.78%

Sb-124 5.08E+01 0.02%

Sr-89 1. 17E+02 0.05%

Tc-99 1.23E+01 0.01%

Zn-65 2.37E+03 1.08%

Zr-95 1. 27E+01 0.01%

Total Activity 2.20E+05 100.00%

Volume Shipped 3

(m ) 5.24E+01

b. Dry compressible waste, contaminated equipment, etc. Waste in this category in 2009 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.

22

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Dry Active Waste Activity Isotope mCi Percent C-14 8.21E+01 0.95%

Co-58 4.05E+01 0.47%

Co-60 1.41E+03 16.41 %

Cr-51 7. 12E+01 0.83%

Cs-137 1.95E-02 0.00%

Fe-55 6.40E+03 74.18%

Fe-59 2.92E+01 0.34%

H-3 9.35E+01 1.08%

1-129 3.84E+00 0.04%

Mn-54 5.35E+02 6.21%

Ni-63 1.05E+01 0.12%

Sb-124 4.50E-01 0.01%

Tc-99 8.91E+01 1.03%

Zn-65 7.05E+01 0.82%

Total Activity (mCi) 8.62E+03 100.00%

Volume Disposed (mJ) 1.21E+02

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

d. Other: No waste in this category was shipped to a disposal site.

23

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Appendix B Ground Water Protection Program Data and Analysis 24

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report INTRODUCTION In conformance with the voluntary industry ground water protection initiative (Nuclear Energy Institute 07-07), Fermi 2 maintains an Integrated Ground Water Protecti on Program (IGWPP) comprised of 56 monitor wells, 38 of which are sampled quarterly for plant-related radioisotopes. These monitor wells are not only used to monitor ground-water flow in the shallow (surficial) and deep (bedrock) aquifers, but they also provide ground-water sample points, separate of the site's existing, long-term Radiological Environmental Monitoring Program (REMP) wells.

Fermi 2 utilizes a contract laboratory for analysis of ground-water samples taken as part of the site's IGWPP. Ground-water samples taken as part of the quarterly sampling program are analyzed for tritium (H-3) using liquid scintillation and plant-related gamma-emitting radioisotopes using gamma spectroscopy. Each year Fermi 2 also takes ground-water samples from selected wells to test for the presence of plant-related hard-to-detect (HTD) radionuclides (iron-55, Strontium-89, and Strontium-90).

Ground-water samples taken during the first half of 2009 were only analyzed by gamma spectroscopy if the corresponding split sample was positive for tritium. During the second half of 2009 all samples of ground water were analyzed by gamma spectroscopy regardless of the results of the tritium analysis on the corresponding split sample.

RESULTS Samples analyzed for gamma-emitting radionuclides, as well as HTDs, are counted to environmental lower limits of detection (LLD) for each given radioisotope of interest.

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 pCilL which is 1110 of the EPA's drinking water limit of20,000 pCilL. Fermi 2's contract laboratory achieved LLDs for tritium of 562 pCilL, or less, for all ground-water samples taken during 2009.

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 004D, EF2-07-006D, EF2-07-009D, EF2-07-0l5D, and EF2-07-020D. The positive results for tritium from water in these monitor wells range from 279 - 527 pCilL. The monitor wells where tritium has been detected in ground water are evenly distributed across the Fermi 2 site.

Plant-related gamma-emitting radioisotopes were not detected in any samples collected from deep monitor wells in 2009.

25

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report 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 550 pCilL.

Plant-related gamma-emitting radioisotopes and hard-to-detect radioisotopes were not detected in any ground-water samples collected from shallow monitor wells in 2009.

DISCUSSION This is the second 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 2009 have shown that most of the site's wells have never had a positive result for that radionuclide. In 2009, positive ground water results for tritium ranged from 206 to 549 pCi/L. During the first quarter sampling all ground water samples produced results for tritium less than the lower-limit of detection.

Because Fermi's contract laboratory has started using a lower LLD, the apparent distribution of positive tritium results is more wide-spread than in previous years. The 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.

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 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 from washout. 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.

In 2009 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. These conditions suggest that if any ground-water flow occurs between the two aquifers it would be upward from the bedrock aquifer to the surficial aquifer. Plant components, outside of buildings, that contain large quantities of tritiated water are either 26

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report 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 in monitor wells screened in the surficial aquifer. Under these conditions (hydrogeological and plant construction) it is highly improbable that the positive tritium values 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-2l0, 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 attributed to the high uncertainty associated with results at or near an analytical method's lower detection limit.

Table 1: Deep Monitor Well Tritium Analysis Results for Year 2009 MONITOR LAB WELL EVENT ID QA TYPE ID PARAMETER PREFIX VALUE UNITS EF2-07-00lD P -2009-G-Q 1 Note 1 EF2-07-00lD P-2009-G-Q2 Note 1 EF2-07-00lD P-2009-G-Q3 Note 1 EF2-07-00lD P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07-003D P -2009-G-Q 1 Note 1 EF2-07-003D P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07-003D P-2009-G-Q3 NORMAL GEL H-3 < LLD PCIIL EF2-07-003D P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07-004D P -2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-004D P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07-004D P-2009-G-Q3 NORMAL GEL H-3 339 PCIIL EF2-07-004D P-2009-G-Q4 NORMAL GEL H-3 321 PCIIL EF2-07-006D P -2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-006D P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07-006D P-2009-G-Q3 NORMAL GEL H-3 279 PCIIL EF2-07-006D P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07-008D P -2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-008D P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07-008D P-2009-G-Q3 NORMAL GEL H-3 < LLD PCIIL EF2-07-008D P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07-009D P -2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-009D P-2009-G-Q2 NORMAL GEL H-3 489 PCIIL EF2-07-009D P-2009-G-Q3 DUPLICATE GEL H-3 527 PCIIL EF2-07-009D P-2009-G-Q3 NORMAL GEL H-3 517 PCIIL EF2-07-009D P-2009-G-Q4 NORMAL GEL H-3 312 PCIIL EF2-07-015D P -2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-015D P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07-015D P-2009-G-Q3 NORMAL GEL H-3 239 PCIIL EF2-07-015D P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07-020D P -2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-020D P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL 27

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report EF2-07-020D P-2009-G-Q3 NORMAL GEL H-3 363 PCIIL EF2-07-020D P-2009-G-Q4 DUPLICATE GEL H-3 415 PCIIL EF2-07-020D P-2009-G-Q4 NORMAL GEL H-3 442 PCIIL EF2-07-029D P -2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-029D P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07-029D P-2009-G-Q3 NORMAL GEL H-3 < LLD PCIIL EF2-07-029D P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL Note 1: Well could not be sampled - in construction area.

Table 2: Shallow Monitor Well Tritium Analysis Results for Year 2009 MONITOR LAB WELL EVENT ID QA TYPE ID PARAMETER PREFIX VALUE UNITS EF2-07 -002S P-2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07 -002S P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07 -002S P-2009-G-Q3 NORMAL GEL H-3 < LLD PCIIL EF2-07 -002S P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07-003S P-2009-G-Q2 Note 1 EF2-07-003S P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07-003S P-2009-G-Q3 NORMAL GEL H-3 < LLD PCIIL EF2-07-003S P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07 -005S P-2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07 -005S P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07 -005S P-2009-G-Q3 NORMAL GEL H-3 253 PCIIL EF2-07 -005S P-2009-G-Q4 NORMAL GEL H-3 267 PCIIL EF 2-07 -007 S P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF 2-07 -007 S P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF 2-07 -007 S P-2009-G-Q3 NORMAL GEL H-3 378 PCIIL EF 2-07 -007 S P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07 -008S P-2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07 -008S P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07 -008S P-2009-G-Q2 DUPLICATE GEL H-3 < LLD PCIIL EF2-07 -008S P-2009-G-Q3 NORMAL GEL H-3 < LLD PCIIL EF2-07 -008S P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07-012S P-2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-012S P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL EF2-07-012S P-2009-G-Q3 NORMAL GEL H-3 251 PCIIL EF2-07-012S P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07-013S P-2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-013S P-2009-G-Q2 NORMAL GEL H-3 376 PCIIL EF2-07-013S P-2009-G-Q3 NORMAL GEL H-3 409 PCIIL EF2-07-013S P-2009-G-Q4 NORMAL GEL H-3 < LLD PCIIL EF2-07-014S P-2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-014S P-2009-G-Q2 NORMAL GEL H-3 446 PCIIL EF2-07-014S P-2009-G-Q3 NORMAL GEL H-3 363 PCIIL EF2-07-014S P-2009-G-Q4 NORMAL GEL H-3 303 PCIIL EF2-07-015S P-2009-G-Q 1 NORMAL GEL H-3 < LLD PCIIL EF2-07-015S P-2009-G-Q2 NORMAL GEL H-3 < LLD PCIIL 28

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report EF2-07-015S P-2009-G-Q3 NORMAL GEL H-3 < LLD pcrlL EF2-07-015S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL EF2-07-016S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF2-07-016S P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL EF2-07-016S P-2009-G-Q3 NORMAL GEL H-3 < LLD pcrlL EF2-07-016S P-2009-G-Q4 NORMAL GEL H-3 267 pcrlL EF2-07-017S P-2009-G-Q 1 DUPLICATE GEL H-3 < LLD pcrlL EF2-07-017S P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL EF2-07-017S P-2009-G-Q3 NORMAL GEL H-3 < LLD pcrlL EF2-07-017S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL EF2-07-018S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF2-07-018S P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL EF2-07-018S P-2009-G-Q4 Note 2 EF2-07-018S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL EF2-07-019S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF2-07-019S P-2009-G-Q2 NORMAL GEL H-3 462 pcrlL EF2-07-019S P-2009-G-Q3 NORMAL GEL H-3 517 pcrlL EF2-07-019S P-2009-G-Q3 DUPLICATE GEL H-3 386 pcrlL EF2-07-019S P-2009-G-Q4 NORMAL GEL H-3 234 pcrlL EF2-07 -020S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF2-07 -020S P-2009-G-Q2 NORMAL GEL H-3 < 263 pcrlL EF2-07 -020S P-2009-G-Q3 NORMAL GEL H-3 < 219 pcrlL EF2-07 -020S P-2009-G-Q4 NORMAL GEL H-3 345 pcrlL EF 2-07 -021 S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF 2-07 -021 S P-2009-G-Q2 NORMAL GEL H-3 461 pcrlL EF 2-07 -021 S P-2009-G-Q3 NORMAL GEL H-3 549 pcrlL EF 2-07 -021 S P-2009-G-Q4 NORMAL GEL H-3 524 pcrlL EF2-07 -022S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF2-07 -022S P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL EF2-07 -022S P-2009-G-Q3 NORMAL GEL H-3 < LLD pcrlL EF2-07 -022S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL EF 2-07 -023 S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF 2-07 -023 S P-2009-G-Q2 NORMAL GEL H-3 275 pcrlL EF 2-07 -023 S P-2009-G-Q3 NORMAL GEL H-3 259 pcrlL EF 2-07 -023 S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL EF2-07 -024S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF2-07 -024S P-2009-G-Q2 NORMAL GEL H-3 279 pcrlL EF2-07 -024S P-2009-G-Q3 NORMAL GEL H-3 330 pcrlL EF2-07 -024S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL EF 2-07 -025 S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF 2-07 -025 S P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL EF 2-07 -025 S P-2009-G-Q3 NORMAL GEL H-3 442 pcrlL EF 2-07 -025 S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL EF2-07 -026S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF2-07 -026S P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL EF2-07 -026S P-2009-G-Q3 NORMAL GEL H-3 < LLD pcrlL EF2-07 -026S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL EF2-07 -027S P-2009-G-Q 1 DUPLICATE GEL H-3 < LLD pcrlL EF2-07 -027S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF2-07 -027S P-2009-G-Q2 NORMAL GEL H-3 413 pcrlL 29

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report EF2-07 -027S P-2009-G-Q3 NORMAL GEL H-3 249 pcrlL EF2-07 -027S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL EF2-07 -028S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF2-07 -028S P-2009-G-Q2 DUPLICATE GEL H-3 < LLD pcrlL EF2-07 -028S P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL EF2-07 -028S P-2009-G-Q3 NORMAL GEL H-3 < LLD pcrlL EF2-07 -028S P-2009-G-Q4 NORMAL GEL H-3 263 pcrlL EF2-07-029S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF2-07-029S P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL EF2-07-029S P-2009-G-Q3 NORMAL GEL H-3 220 pcrlL EF2-07-029S P-2009-G-Q3 DUPLICATE GEL H-3 286 pcrlL EF2-07-029S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL EF 2-07 -031 S P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL EF 2-07 -031 S P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL EF 2-07 -031 S P-2009-G-Q3 NORMAL GEL H-3 < LLD pcrlL EF 2-07 -031 S P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL RHR-lO P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL RHR-lO P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL RHR-lO P-2009-G-Q3 NORMAL GEL H-3 225 pcrlL RHR-lO P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL RHR-11 P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL RHR-11 P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL RHR-11 P-2009-G-Q3 NORMAL GEL H-3 231 pcrlL RHR-11 P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL RHR-18 P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL RHR-18 P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL RHR-18 P-2009-G-Q2 DUPLICATE GEL H-3 < LLD pcrlL RHR-18 P-2009-G-Q3 NORMAL GEL H-3 212 pcrlL RHR-18 P-2009-G-Q4 NORMAL GEL H-3 434 pcrlL RHR-21 P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL RHR-21 P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL RHR-21 P-2009-G-Q4 Note 2 RHR-21 P-2009-G-Q4 NORMAL GEL H-3 307 pcrlL RHR-9 P-2009-G-Q 1 NORMAL GEL H-3 < LLD pcrlL RHR-9 P-2009-G-Q2 NORMAL GEL H-3 < LLD pcrlL RHR-9 P-2009-G-Q3 NORMAL GEL H-3 206 pcrlL RHR-9 P-2009-G-Q4 NORMAL GEL H-3 < LLD pcrlL Note 1: Well could not be sampled - in construction area.

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

30

Fermi 2 - 2009 Annual Radioactive Ejjluent Release Report Map of Monitor Well Locations N

31

FERMI2 NUCLEAR POWER PLANT DETROIT EDISON COMPANY OPERATING LICENSE NO. NPF - 43 Fermi 2 - 2009 Annual Radiological Environmental Operating Report for the period of January 1,2009 through December 31, 2009 Prepared by:

Fermi 2 Radiological Engineering

Fermi 2 - 2009 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 Terrestrial Monitoring 7 Milk Sampling 7 Groundwater Sampling 8 Garden Sampling 9 Aquatic Monitoring 10 Drinking Water Sampling 10 Surface Water Sampling 12 Sediment Sampling 13 Fish Sampling 15 Land Use Census 17 2009 Land Use Census Results 18 Appendix A Sampling Locations A-1 AppendixB Environmental Data Summary B-1 Appendix C Environmental Data Tables C-1 AppendixD Environmental Program Exceptions D-1 Direct Radiation Monitoring D-1 Atmospheric Monitoring D-1 Terrestrial Monitoring D-1 Milk Sampling D-1 Garden Sampling D-2 Groundwater Sampling D-2 Aquatic Monitoring D-2 Drinking Water Sampling D-2 Surface Water Sampling D-2 Sediment Sampling D-2 Fish Sampling D-2 11

Fermi 2 - 2009 Annual Radiological Environmental Operating Report AppendixE Interlaboratory Comparison Data, Framatome ANP Environmental Laboratory's Quality Assurance Programs Interlaboratory Comparison Program/or 2009 E-1 111

Fermi 2 - 2009 Annual Radiological Environmental Operating Report List of Figures Page Figure 1 Fermi 2 Annual Average TLD Gamma Exposure 4 Figure 2 Historical Gross Beta and Iodine-I3I Activity in Air Samples 6 Figure 3 Fermi 2 Air Particulate Gross Betafor 2009 6 Figure 4 Historical Strontium-90 Activity in Local Milk Samples 8 Figure 5 Historical Gross Beta Activity in Drinking Water Samples 12 Figure 6 Historical Cesium-I37 Activity in Sediment Samples 15 Map 1 Sampling Locations By Station Number (within 1 mile) App.-A Map 2 Sampling Locations By Station Number (I to 5 miles) App.-A Map 3 Sampling Locations By Station Number (greater than 5 miles) App.-A List of Tables Page Table 1 2009 Average Gross Beta Concentrations in Air Particulates 5 Table 2 Closest Residences 19 Table 3 Closest Gardens 20 Table 4 Milk Locations 21 Table 5 Closest Meat Locations 22 Table A-I Direct Radiation Sample Locations A-I Table A-2 Air Particulate and Air Iodine Sample Locations A-7 Table A-3 Milk Sample Locations A-7 Table A-4 Garden Sample Locations A-8 Table A-5 Drinking Water Sample Locations A-8 Table A-6 Surface Water Sample Locations A-9 Table A-7 Groundwater Sample Locations A-9 Table A-8 Sediment Sample Locations A-IO Table A-9 Fish Sample Locations A-IO Table B-1 Radiological Environmental Monitoring Program Summary B-1 IV

Fermi 2 - 2009 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 31,2009.

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

Environmental Laboratory. 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 2009 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 14.9 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 2009 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 2009.

Terrestrial monitoring results for 2009 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 2009.

1

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Aquatic monitoring results for 2009 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 2009.

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

2

Fermi 2 - 2009 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 (mRlstd qtr), with a standard quarter being 91 days.

3

Fermi 2 - 2009 Annual Radiological Environmental Operating Report In 2009, the average exposure for TLDs at all off-site indicator locations was 14.9 mRlstd qtr and for all control locations was 14.0 mRlstd qtr. These exposures are consistent with preoperational and past operational measurements as shown in Figure 1.

Fermi 2 Annual Average TLD Gamma Exposure 25 20 0"

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1- Indicator ~~ Control 1 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-I3I 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 radionuc1ides. 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 - 2009 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-l pCi/cubic meter for indicator samples and 2AOE-l pCi/cubic meter for control samples which was a factor of ten times greater than background gross beta. Gamma spectroscopic analyses of the particulate filters indicated cesium-137, cerium-141, cerium-144, ruthenium-l03, ruthenium-l06, 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-l 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) of7.0E-2 pCi/cubic meter.

During 2009, two hundred and fifty-four (254) 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 3.13E-2 pCi/cubic meter and 3.07E-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 2009.

2009 Average Gross Beta Concentrations in Air Particulates (pCilm3)

Table 1 Station Description (sector/distance) Annual Average API-l (I) Estral Beach (NEllA mi.) 2.68E-2 API-2 (I) Site Boundary (NNW/0.6 mi.) 2.94E-2 API-3 (I) Site Boundary (NW/0.6 mi.) 2.80E-2 API-4 (C) North Custer Rd. (W1l4 mi.) 3.07E-2 API-5 (I) Site Boundary (SIl.2 mi.) 4.09E-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 - 2009 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 JE-01 Chinese Weapon Test Activty in Air Samples Chernobyl Event

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-o-Indicator Gross Beta 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 pei/cubic meter.

Fermi 2 Air Particulate Gross Beta 2009 6.E-02 5.E-02

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Collection Date 1--0-- Indicator ****fl**** Control I Figure 3 - Fermi 2 Air Particulate Gross Beta for 2009; 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 - 2009 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 2009 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-89190. 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 2009, 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-89190 began in 1988, and strontium-90 is routinely detected in both indicator and control milk samples because of past atmospheric nuclear weapons testing.

During 2009, thirty four (34) milk samples were collected and analyzed for iodine-131, gamma emitting radionuclides, and strontium-89190. 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).

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Fermi 2 - 2009 Annual Radiological Environmental Operating Report The indicator samples had an average strontium-90 concentration of 1.65E+0 pCi/liter and the control sample had concentration of 1.32E+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 concentrati on of strontium -90 and the average concentrati ons 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-gO Activity in Local Milk Samples 6.0 Q) 4.0

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a CD 8N 8a N N N Average Sr-90 Activity ***********Calculated Decay I 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 - 2009 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 2009, sixteen (16) groundwater samples were collected and analyzed for gamma emitting radionuclides and tritium. During 2009, 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 I.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 - 2009 Annual Radiological Environmental Operating Report activity is attributed to fallout from past atmospheric weapons testing and to the nuclear accident at Chernobyl.

During 2009, twelve (12) vegetable samples were collected and analyzed for iodine-131 and other gamma emitting radionuclides. No iodine-131 was detected in vegetable samples during 2009. The only gamma emitting radionuclides detected were naturally occurring potassium-40 and beryllium-7 in both indicator and control samples.

Terrestrial monitoring results for 2009 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 2009 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-89190, and gamma emitting radionuclides. The monthly samples for each location are combined on a quarterly basis and analyzed for tritium activity.

10

Fermi 2 - 2009 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 of3.25E+2 pCi/liter. The presence ofcesium-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 2008, the average annual gross beta activity for indicator samples was 3.64E+0 pCi/liter and 3.09E+0 pCi/liter for control samples. The analysis for strontium-89190 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 2009, twenty-four (24) drinking water samples were collected and analyzed for gross beta, gamma emitting radionuclides, strontium-89190, and tritium. The average gross beta for indicator samples was 4.53E+0 and 4.00E+0 pCi/liter for control samples. No gamma emitting radionuclides or strontium-89190 activity was detected in drinking water samples during 2009. Eight (8) quarterly composite drinking water samples were prepared and analyzed for tritium. No tritium activity was detected in drinking water samples during 2009.

11

Fermi 2 - 2009 Annual Radiological Environmental Operating Report 12.0 Historical Gross Beta Activity in Drinking Water Samples Chinese Weapons Test 10.0

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~ ~ ~ ~ ~ ~ N ~ N ~ N Indicator Gross Beta *~~~~~{}~~~~~~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-89190 and gamma emitting radionuc1ides. 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 - 2009 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 concentrati on of 3 . 15E+2 pCi/li ter. Thi s tri ti um acti vi ty represents the background concentration due to naturally occurring tritium and tritium produced during past atmospheric nuclear weapons testing.

From 1985 to 2008, as part of the operational program, surface water samples were analyzed for gamma emitting radionuclides and tritium. The analysis for strontium-89190 did not begin until 1988, and strontium-90 was detected in both indicator and control samples. The average strontium-90 concentration for this time period was 1. 13E+O pCi/liter. In 1990, two indicator samples showed detectable activity for cesium-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 2009, twenty-four (24) surface water samples were collected and analyzed for gamma emitting radionuclides and strontium-89190. From these samples, eight (8) quarterly composite samples were prepared and analyzed for tritium. During 2009, no gamma emitting radionuclides, strontium-89190 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 - 2009 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-89190. 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 2008, 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-89190 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 ofliquid effluent from Fermi 2. The sample results were well below any regulatory reporting limits and were consistent with the activity released from the plant in liquid effluents as per the approved effluent program. The dose impact was negligible due to these effluents.

In 2009, ten (10) sediment samples were collected and analyzed for gamma emitting radionuclides and strontium 89190. Strontium-90 was detected in one indicator sample with a concentration of 4.46E+2 pCi/kilogram. Cesium-137 was not detected in any indicating sediment samples. The presence of strontium-90 in sediment samples is due to fallout from past atmospheric nuclear weapons testing. Naturally occurring radionuclides potassium-40 and beryllium-7 were also detected in sediment samples for this sampling period.

14

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Historical Cesium-137 Activity in Sediment Samples 7.E -+D2 6.E-+D2 E 5.E-+D2 III

~ 4.E-+D2

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Figure 6 - Historical Cesium-137 Activity in Sediment Samples. As the calculated trend shows, the concentration ofcesium-137 in Lake Erie sediments is decreasing with time. This supports the fact that cesium -13 7 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 2009. Using the data from these years, and the statistical method ofleast 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-89190.

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 - 2009 Annual Radiological Environmental Operating Report From 1985 to 2008, 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-89190 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 2009, twenty-two (22) fish samples were collected and analyzed for gamma emitting radionuclides and strontium-89190. Only naturally occurring potassium-40 was detected in both control and indicator fish samples for 2009.

Aquatic monitoring results for 2009 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 2009 and no adverse long-term trends are shown in the aquatic monitoring data.

16

Fermi 2 - 2009 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 - 2009 Annual Radiological Environmental Operating Report 2009 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 2009 Land Use Census was performed during the month of August. The 2009 census data were obtained with the use of a hand-held Global Positioning System (GPS) and aerial imagery using Google Earth. These data were compared to the 2006 data to determine any significant changes in the use of the land. The results of the census are tabulated in Tables 2 - 5 of this report.

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

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

Fermi 2 - 2009 Annual Radiological Environmental Operating Report 2009 LAND USE CENSUS Closest Residences Table 2 Azimuth Distance Change Sector I Year I (degrees) I (miles) I (miles)

N I 2008 I 8.9 I 1.11 I I 2009 I 8.9 I 1.11 I 0.00 NE I 2008 I 34.7 I 1.10 I I 2009 I 34.7 I 1.10 I 0.00 NNE I 2008 I 16.6 I 1.08 I I 2009 I 16.6 I 1.08 I 0.00 NNW I 2008 I 334.9 I 1.09 I I 2009 I 334.9 I 1.09 I 0.00 NW I 2008 I 309.7 I 1.07 I I 2009 I 309.7 I 1.07 I 0.00 S I 2008 I 169.6 I 1.03 I I 2009 I 169.6 I 1.03 I 0.00 SSW I 2008 I 200.1 I 1.12 I I 2009 I 200.1 I 1.12 I 0.00 SW I 2008 I 229.3 I 1.26 I I 2009 I 229.3 I 1.26 I 0.00 W I 2008 I 259.2 I 1.19 I I 2009 I 259.2 I 1.19 I 0.00 WNW(a) I 2008 I 302.3 I 0.71 I I 2009 I 302.3 I 0.71 I 0.00 WSW I 2008 I 236.3 I 1.39 I I 2009 I 236.3 I 1.39 I 0.00 (a) = Location of "maximum exposed individual" 19

Fermi 2 - 2009 Annual Radiological Environmental Operating Report 2009 LAND USE CENSUS Closest Gardens Table 3 Azimuth Distance Change Sector I Year I (degrees) I (miles) I (miles)

N I 2008 I 358.5 I 2.13 I I 2009 I 358.5 2.13 I 0.00 NE I 2008 I 38.9 I 1.98 I I 2009 I 51.8 1.85 I 0.13 NNE I 2008 I 30.6 I 1.91 I I 2009 I 30.6 1.91 I 0.00 NNW I 2008 I 326.7 I 1.40 I I 2009 I 332.1 2.57 I -1.17 NW I 2008 I 319.3 I 2.34 I I 2009 I 315.5 1.51 I 0.83 S I 2008 I 185.4 I 1.38 I I 2009 I 169.6 1.03 I 1.38 SSW I 2008 I No Data I No Data I I 2009 I 201.9 1.59 I 1.59 SW I 2008 I No Data I No Data I I 2009 I No Data I No Data I W I 2008 I 266.7 I 1.70 I I 2009 I 266.7 I 1.70 I 0.00 WNW I 2008 I 297.7 I 4.40 I I 2009 I 297.7 4.40 I 0.00 WSW I 2008 I 250.5 I 2.38 I I 2009 I 250.5 I 2.38 I 0.00 20

Fermi 2 - 2009 Annual Radiological Environmental Operating Report 2009 LAND USE CENSUS Milk Locations Table 4 Azimuth Distance Change Sector I Year I (degrees) I (miles) I (miles) I Type N I 2008 I No Data I I I 2009 I No Data I I I NE I 2008 I No Data I I I 2009 I No Data I I I NNE I 2008 I No Data I I I 2009 I No Data I I I NNW I 2008 I No Data I I I 2009 I No Data I I I NW I 2008 I No Data I I I 2009 I No Data I I I S I 2008 I No Data I I I 2009 I No Data I I I SSW I 2008 I No Data I I I 2009 I No Data I I I SW I 2008 I No Data I I I 2009 I No Data I I I W I 2008 I No Data I I I 2009 I No Data I I I WNW I 2008 I 297.4 I 2.38 I Goat I 2009 I 297.4 I 2.38 I 0.00 I Goat WSW I 2008 I No Data I I I 2009 I No Data I I I 21

Fermi 2 - 2009 Annual Radiological Environmental Operating Report 2008 LAND USE CENSUS Closest Meat Locations Table 5 Azimuth Distance Change Sector Year (degrees) (miles) (miles) Type N 2008 9.6 4.29 2009 No Data No Data NE 2008 No Data No Data 2009 No Data No Data NNE 2008 12.1 2.17 Beef 2009 No Data No Data NNW 2008 338.2 4.36 Sheep 2009 338.2 4.36 0.00 Sheep NW 2008 321.4 3.02 Beef 2009 321.4 3.02 0.00 Beef S 2008 No Data No Data 2009 No Data No Data SSW 2008 No Data No Data 2009 No Data No Data SW 2008 No Data No Data 2009 No Data No Data W 2008 No Data No Data 2009 No Data No Data WNW 2008 287.5 1.65 Beef 2009 287.5 1.65 0.00 Beef WSW 2008 252.4 2.94 Beef 2009 No Data No Data 2.94 Beef 22

Appendix A Sampling Locations

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations Table A-I Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type n NE/38° 1.3 mi. Estral Beach, Pole on Q Lakeshore 23 Poles S of Lakeview. (Special Area)

T2 NNE/22° 1.2 mi. Pole at termination of Q Brancheau st.

(Special Area)

T3 N/9° 1.1 mi. Pole, NW comer of Swan Q Boat Club fence. (Special Area)

T4 NNW/337° 0.6 mi. Site boundary and Toll Rd. Q on Site fence by API #2.

T5 NW/3l3° 0.6 mi. Site boundary and Toll Rd. Q on Site fence by API #3.

T6 WNWI294° 0.6 mi. On Site fence at south end Q of N. Bullet Rd.

T7 W1270° 14.0 mi. Pole, at Michigan Gas Q C substation on N. Custer Rd., 0.66 miles west of Doty Rd.

T8 NW/305° 1.9 mi. Pole on Post Rd. near NE Q comer of Dixie Hwy. and Post Rd.

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

no N/6° 2.1 mi. Pole, S side of Massarant- Q 2 poles W of Chinavare.

I = Indicator C = Control a= On-site Q = Quarterly A-I

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A -1 continued)

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

Tl2 NNE129° 6.3 mi. Pointe Mouille Game Area Q Field Office, Pole near tree, N area of parking lot.

Tl3 N/356° 4.1 mi. Labo and Dixie Hwy. Pole Q on SW comer with light.

Tl4 NNW/337° 4.4 mi. Labo and Brandon Pole on Q SE comer near RR.

Tl5 NW/3l5° 3.9 mi. Pole, behind building at the Q comer of Swan Creek and Mill st.

Tl6 WNW1283° 4.9 mi. Pole, SE comer of War and Q Post Rd.

Tl7 W127l ° 4.9 mi. Pole, NE comer of Nadeau Q and Laprad near mobile home park.

Tl8 WSWI247° 4.8 mi. Pole, NE comer of Mentel Q and Hurd Rd.

Tl9 SW1236° 5.2 mi. Fermi siren pole on Q Waterworks Rd. NE comer of intersection - Sterling State Park Rd. Entrance Drive/Waterworks.

T20 WSWI257° 2.7 mi. Pole, S side of Williams Q Rd, 9 poles W of Dixie Hwy. (Special Area)

T2l WSWI239° 2.7 mi. Pole, N side of Pearl at Q Parkview Woodland Beach. (Special Area)

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

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A -1 continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T22 SI172° 1.2 mi. Pole, N side of Pointe Aux Q Peaux 2 poles W of Long -

Site Boundary.

T23 SSWI195° 1.1 mi. Pole, S side of Pointe Aux Q Peaux 1 pole W of Huron next to Vent Pipe - Site Boundary.

T24 SW1225° 1.2 mi. Fermi Gate along Pointe Q Aux Peaux Rd. on fence wire W of gate Site Boundary.

T25 WSWI252° 1.4 mi. Pole, Toll Rd. - 12 poles S Q of Fermi Drive.

T26 WSWI259° 1.1 mi. Pole, Toll Rd. - 6 poles S Q of Fermi Drive.

T27 SW1225° 6.8 mi. Pole, NE comer of Q McMillan and East Front S1. (Special Area)

T28 SW1229° 10.6 mi. Pole, N side of Mortar Q C Creek between Hull and LaPlaisance.

T29 WSWI237° 10.3 mi. Pole, NE comer of S Dixie Q C and Albain.

T30 WSWI247° 7.8 mi. E side S end of foot bridge, Q S1. Mary's Park comer of Elm and Momoe S1.

(Special Area)

T3l WSWI255° 9.6 mi. 1st pole W of entrance Q C drive Milton "Pat" Munson Recreational Reserve on North Custer Rd.

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

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A -1 continued)

Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type T32 WNW1295° 10.3 mi. Pole, comer of Stony Creek Q and Finzel Rd.

T33 NW/3l7° 9.2 mi. Pole, W side of Grafton Q Rd. 1 pole N of Ash and Grafton intersection.

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

T35 N/359° 6.9 mi. Pole, S Side of S Huron Q River Dr. across from Race S1. (Special Area)

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

T37 NNEl2lo 9.8 mi. Pole, S comer of Adams Q and Gibraltar across from Humbug Marina.

T38 WNWI294° 1.7 mi. Residence - 6594 N. Dixie Q Hwy.

T39 S1176° 0.3 mi. SE comer of Protected Q 0 Area Fence (PAF).

T40 S1170° 0.3 mi. Midway along OBA - P AF. Q 0 T4l SSEI161 ° 0.2 mi. Midway between OBA and Q 0 Shield Wall on P AF.

T42 SSEI149° 0.2 mi. Midway along Shield Wall Q 0 onPAF.

T43 SEI131 ° 0.1 mi. Midway between Shield Q 0 Wall and Aux Boilers on PAF.

T44 ESEI109° 0.1 mi. Opposite OSSF door on Q 0 PAF.

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

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Direct Radiation Sample Locations (Table A -1 continued)

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

T47 S1185° 0.1 mi. South of Turbine Bldg. Q 0 rollup door on PAF.

T48 SW1235° 0.2 mi. 30 f1. from comer of AAP Q 0 onPAF.

T49 WSW1251 ° 1.1 mi. Comer of Site Boundary Q fence north ofNOC along Critical Path Rd.

T50 W/270° 0.9 mi. Site Boundary fence near Q main gate by the south Bullet Street sign.

T5l N/3° 0.4 mi. Site Boundary fence north Q 0 of north Cooling Tower.

T52 NNE120° 0.4 mi. Site Boundary fence at the Q 0 comer of Arson and Tower.

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

T54 S1189° 0.3 mi. Pole next to Fermi 2 Q 0 Visitors Center.

T55 WSW1251 ° 3.3 mi. Pole, north side of Nadeau Q Rd. across from Sodt Elementary School Marquee.

T56 WSWI256° 2.9 mi. Pole, entrance to Jefferson Q Middle School on Stony Creek Rd.

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

Fermi 2 - 2009 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 W1260° 2.7 mi. Pole, north side of Q Williams Rd. across from Jefferson High School entrance.

T58 WSWI249° 4.9 mi. Pole west of Hurd Q Elementary School Marquee.

T59 NW1325° 2.6 mi. Pole north of S1. Charles Q Church entrance on Dixie Hwy.

T60 NNW1341 ° 2.5 mi. 1st pole north of North Q Elementary School entrance on Dixie Hwy.

T6l W1268° 10.1 mi. Pole, SW comer of Stewart Q and Raisinville Rd.

T62 SW1232° 9.7 mi. Pole, NE comer of Albain Q and Hull Rd.

T63 WSWI245° 9.6 mi. Pole, NE comer of Dunbar Q and Telegraph Rd.

T64 WNWI286° 0.2 mi. West of switchgear yard on Q 0 PAF.

T65 NW1322° 0.1 mi. PAF switchgear yard area Q 0 NW of RHR complex.

T66 NE/50° 0.1 mi. Behind Bldg. 42 on PAF. Q 0 T67 NNW1338° 0.2 mi. Site Boundary fence West Q 0 of South Cooling Tower.

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

T69 NW1306° 0.8 mi Langton Rd. five poles East Q of Leroux Rd.

T70 NNW1333 ° 1.1 mi Leroux Rd. last pole North Q of Fermi Dr.

T7l WNW1300° 1.1 mi Leroux Rd. six poles North Q of Fermi Dr.

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

Fermi 2 - 2009 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-l NE139° 1.4 mi. Estral Beach Pole on W Lakeshore, 18 Poles S of Lakeview (Nearest Community with highest XlQ).

API-2 NNW1337° 0.6 mi. Site Boundary and Toll W Road, on Site Fence by T -4.

API-3 NW1313° 0.6 mi. Site Boundary and Toll W Road, on Site Fence by T -5.

API-4 W1270° 14.0 mi. Pole, at Michigan Gas W C substation on N. Custer Rd., 0.66 miles west of Doty Rd.

API-5 S1188° 1.2 mi. Pole, N comer of Pointe W Aux Peaux and Dewey Rd.

I = Indicator C = Control W= Weekly Milk Sample Locations Table A-3 Meteorological Distance Station Sector/Azimuth from Reactor Collection Number (Degrees) (Approx.) Description Frequency Type M-2 NW1319° 5.4 mi. Reaume Farm - 2705 E M-SM Labo.

M-8 WNWI289° 9.9 mi. Calder Dairy - 9334 Finzel M-SM C Rd.

I = Indicator C = Control M=Monthly SM = Semimonthly A-7

Fermi 2 - 2009 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-l NNE121 0 3.8 mi. 9501 Turnpike Highway. M FP-9 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-l 1.1 mi. Momoe Water Station N M Side of Pointe Aux Peaux 112 Block W of Long Rd.

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

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

Fermi 2 - 2009 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 11.7 mi. DECo's Trenton Channel M C Power Plant Intake Structure (Screenhouse #1).

SW-3 SSEI160° 0.2 mi. DECO's Fermi 2 General M Service Water Intake Structure.

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

GW-2 SSWI208° 1.0 mi. 4 ft S of Pointe Aux Peaux Q (PAP) Rd. Fence 427 ft W of where PAP crosses over Stoney Point's Western Dike.

GW-3 SW1226° 1.0 mi. 143 ft W of PAP Rd. Gate, Q 62 ft N of PAP Rd. Fence.

GW-4 WNWI299° 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 - 2009 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-l SSEI165° 0.9 mi. Pointe Aux Peaux, SA Shoreline to 500 ft offshore sighting directly to Land Base Water Tower.

S-2 E/8l ° 0.2 mi. Fermi 2 Discharge, approx. SA 200 ft offshore.

S-3 NE139° 1.1 mi. Estral Beach, approx. 200 SA ft offshore, off North shoreline where Swan Creek and Lake Erie meet.

S-4 WSW1241 ° 3.0 mi. Indian Trails Community SA Beach.

S-5 NNE120° 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 NNE13lo 9.5 mi. Near Celeron Island. SA C F-2 E/86° 0.4 mi. Fermi 2 Discharge (approx. SA 1200 ft offshore).

F-3 SWI227 ° 3.5 mi. Brest Bay. SA C I = Indicator C = Control SA = Semiannually A-IO

LAKE ERIE r

LAKE ERIE MAP - 2 SAMPLING LOCATIONS N

BY STATION NUMBER (1 To 5 MILES)

LEGEND T- DIRECT RADIATION API- AIR PARTICULATES/AIR IODINE S- SEDIMENTS DW/SW- DRINKING WATER/SURFACE WATER GW- GROUND WATER o M- MILK FP- FOOD PRODUCTS F- FISH SCALE IN MILES

GROSSE POINTE PK LIVONIA DEARBOR HEIGHTS TM SYLVANIA MAP - 3 SAMPLING LOCATIONS N BY STATION NUMBER (GREATER THAN 5 MILES)

LEGEND T- DIRECT RADIATION API- AIR PARTICULATES OR AIR IODINE S- SEDIMENTS DW/SW- DRINKING WATEP/SURFACE WATER 5 o 5 10 GW- GROUND WATER M- MILK FP- FOOD PRODUCTS SCALE IN MILES F- FISH

Appendix B Environmental Data Summary

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Table B-1 Radiological Environmental Monitoring Program Summary Name of Facility: EmicoFermiUnit2 Docket No.: 50-341 Reporting Period: January - December 2009 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 14.9 (190/190) T -49 (Indicator) 19.4 (4/4) 14.0 (16/16) None mRlstd qtr 206 10.9 to 21.9 16.7 to 21.9 12.1 to 16.4 Airborne Gross Beta 254 1.00E-2 3.l3E-2 (2041204) API-5 (Indicator) 4.09E-2 (51151) 3.07E-2 (50/50) None Particulates 1.l2E-2 to 6.26E-2 1.l2E-2 to 6.26E-2 1. 52E-2 to 4.94E-2 pCi/cu. m. Gamma Spec. 20 Be-7 N/A l.33E-l (14/16) API-5 (Indicator) 1.89E-l (4/4) 1.47E-l (4/4) None 8.20E-2 to 2.39E-l 1.40E-l to 2.39E-l 1. 06E-l to 1. 72E-l 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-l03 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-14l N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None Airborne Iodine 1-131 254 7.00E-2 <MDA <MDA None pCi/cu. m.

B-1

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Table B-1 Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: EmicoFermiUnit2 Docket No.: SO-34l Reporting Period: January - December 2009 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 Milk 1-131 34 1.00E+0 <MDA <MDA None pCi11 Sr-89 34 N/A <MDA <MDA None Sr-90 N/A 1.6SE+0 (2117) M-2 (Indicator) 1.6SE+0 (2117) l.32E+0 (1117) None 1.2SE+0 to 2.04E+0 1.2SE+0 to 2.04E+0 Gamma Spec. 34 Be-7 N/A <MDA <MDA None K-40 N/A l.37E+3 (17117) M-8 (Control) 1.4SE+3 (17117) 1.4SE+3 (17117) None 1.20E+3 to l.S4E+3 l.30E+3 to 1.69E+3 l.30E+3 to 1.69E+3 Mn-S4 N/A <MDA <MDA None Co-S8 N/A <MDA <MDA None Fe-S9 N/A <MDA <MDA None Co-60 N/A <MDA <MDA None Zn-6S N/A <MDA <MDA None Zr-9S N/A <MDA <MDA None Nb-9S N/A <MDA <MDA None Ru-l03 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 l.SOE+l <MDA <MDA None Cs-137 1.80E+l <MDA <MDA None Ba-140 l.SOE+l <MDA <MDA None La-140 l.SOE+l <MDA <MDA None Ce-14l N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None Vegetation 1-131 12 6.00E+l <MDA <MDA None pCilkgwet Gamma Spec. 12 Be-7 N/A 4.20E+2 (1/7) FP-l (Indicator) 4.20E+2 (1/7) <MDA None K-40 N/A 2.94E+3 (7/7) FP-9 (Control) 3.8SE+3 (SIS) 3.8SE+3 (SIS) None 1.61E+3 to 3.6SE+3 2.8SE+3 to 4.94E+3 2.8SE+3 to 4.94E+3 B-2

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Table B-1 Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: EmicoFermiUnit2 Docket No.: 50-341 Reporting Period: January - December 2009 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 Vegetation Mn-54 N/A <MDA <MDA None (cont.) Co-58 N/A <MDA <MDA None pCilkgwet 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-l03 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 6.00E+l <MDA <MDA None Cs-137 8.00E+l <MDA <MDA None Ba-140 N/A <MDA <MDA None La-140 N/A <MDA <MDA None Ce-14l N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None Drinking Water Gross Beta 24 4.00E+0 4.53E+0 (8/12) DW-l (Indicator) 4.53E+0 (8/12) 4.00E+0 (3/12) None pCi11 3.50E+0 to 7.80E+0 3.50E+0 to 7.80E+0 3.20E+0 to 4.80E+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-5l N/A <MDA <MDA None Mn-54 1.50E+l <MDA <MDA None Co-58 1.50E+l <MDA <MDA None Fe-59 3.00E+l <MDA <MDA None Co-60 1.50E+l <MDA <MDA None Zn-65 3.00E+l <MDA <MDA None Zr-95 1.50E+l <MDA <MDA None Nb-95 1.50E+l <MDA <MDA None B-3

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Table B-1 Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: EmicoFermiUnit2 Docket No.: 50-341 Reporting Period: January - December 2009 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-l03 N/A <MDA <MDA None (cont.) pCi11 Ru-106 N/A <MDA <MDA None Cs-134 1.50E+l <MDA <MDA None Cs-137 1.80E+l <MDA <MDA None Ba-140 1.50E+l <MDA <MDA None La-140 1.50E+l <MDA <MDA None Ce-14l N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None H-3 8 2.00E+3 <MDA <MDA None Surface Water Sr-89 24 N/A <MDA <MDA None pCi11 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-5l N/A <MDA <MDA None Mn-54 1.50E+l <MDA <MDA None Co-58 1.50E+l <MDA <MDA None Fe-59 3.00E+l <MDA <MDA None Co-60 1.50E+l <MDA <MDA None Zn-65 3.00E+l <MDA <MDA None Zr-95 1.50E+l <MDA <MDA None Nb-95 1.50E+l <MDA <MDA None Ru-l03 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 1.50E+l <MDA <MDA None Cs-137 1.80E+l <MDA <MDA None Ba-140 1.50E+l <MDA <MDA None La-140 1.50E+l <MDA <MDA None Ce-14l N/A <MDA <MDA None B-4

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Table B-1 Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: EmicoFermiUnit2 Docket No.: 50-341 Reporting Period: January - December 2009 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 Surface Water Ce-144 N/A <MDA <MDA None (cont.) pCi11 H-3 8 2.00E+3 <MDA <MDA None Groundwater Gamma Spec. 16 pCi11 Be-7 N/A <MDA <MDA None K-40 N/A 9.60E+l (1/12) GW -2 (Indicator) 9.60E+l (114) <MDA None Cr-5l N/A <MDA <MDA None Mn-54 1.50E+l <MDA <MDA None Co-58 1.50E+l <MDA <MDA None Fe-59 3.00E+l <MDA <MDA None Co-60 1.50E+l <MDA <MDA None Zn-65 3.00E+l <MDA <MDA None Zr-95 1.50E+l <MDA <MDA None Nb-95 1.50E+l <MDA <MDA None Ru-l03 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 1.50E+l <MDA <MDA None Cs-137 1.80E+l <MDA <MDA None Ba-140 1.50E+l <MDA <MDA None La-140 1.50E+l <MDA <MDA None Ce-14l N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None H-3 16 2.00E+3 <MDA <MDA None Sediment Sr-89 10 N/A <MDA <MDA pCilkgdry Sr-90 N/A 4.46E+2 (112) S-3 (Indicator) 4.46E+2 (112) <MDA None Gamma Spec. 10 Be-7 N/A <MDA S-5 (Control) 6.90E+2 (112) 6.90E+2 (112) None K-40 N/A 1.15E+4 (8/8) S-2 (Indicator) 1. 66E+4 (212) l.32E+4 (212) 3.84E+3 to 2.22E+4 1.09E+4 to 2.22E+4 1.l0E+4 to 1.54E+4 None B-5

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Table B-1 Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: EmicoFermiUnit2 Docket No.: 50-341 Reporting Period: January - December 2009 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 Sediment (cont.) Mn-54 N/A <MDA <MDA None pCi/kgdry 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-l03 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 <MDA None Ba-140 N/A <MDA <MDA None La-140 N/A <MDA <MDA None Ce-14l N/A <MDA <MDA None Ce-144 N/A <MDA <MDA None Fish Sr-89 22 N/A <MDA <MDA None pCi/kgwet Sr-90 N/A <MDA <MDA None Gamma Spec. 22 Be-7 N/A <MDA <MDA None K-40 N/A 2.74E+3 (7/7) F -2 (Indicator) 2.74E+3 (7/7) 2.66E+3 (15/15) None 1.92E+3 to 3.64E+3 1.92E+3 to 3.64E+3 2.lOE+3 to 3.l6E+3 Mn-54 l.30E+2 <MDA <MDA None Co-58 l.30E+2 <MDA <MDA None Fe-59 2.60E+2 <MDA <MDA None Co-60 l.30E+2 <MDA <MDA None Zn-65 2.60E+2 <MDA <MDA None B-6

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Table B-1 Radiological Environmental Monitoring Program Summary (cont.)

Name of Facility: Enrico Fermi Unit 2 Docket No.: 50-341 Reporting Period: January - December 2009 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 Fish (cont.) Zr-95 N/A <MDA <MDA None pCi/kgwet Nb-95 N/A <MDA <MDA None Ru-l03 N/A <MDA <MDA None Ru-106 N/A <MDA <MDA None Cs-134 l.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-14l 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 aDCM 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 aDCM control 3.12.1.

Note: ather nuclides were considered in analysis results, but only those identifiable were reported in addition to aDCM listed nuclides.

B-7

Appendix C Environmental Data Tables

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 TLD ANALYSIS (mR/Std Qtr)

STATION FIRST SECOND THIRD FOURTH NUMBER QUARTER QUARTER QUARTER QUARTER T -1 13.41 12.63 14.13 12.95 T-2 (a) 13.64 13.63 12.54 T-3 10.94 12.11 13.11 12.62 T-4 13.47 15.25 15.16 14.59 T-5 14.35 15.37 16.89 15.75 T-6 14.40 14.43 16.55 14.87 T-7 14.42 15.40 16.36 15.74 T-8 14.07 16.15 16.02 15.47 T-9 13.17 13.82 15.48 14.34 T-lO 14.66 14.09 15.55 15.24 T -11 13.09 12.85 14.05 13.45 T -12 12.67 12.04 14.32 13.64 T -13 14.45 15.09 16.85 16.32 T -14 14.67 15.67 16.38 16.19 T -15 12.67 12.79 14.06 12.96 T -16 15.88 17.06 18.47 18.55 T-17 12.96 12.51 13.63 12.99 T -18 13.35 13.77 15.27 13.64 T -19 16.17 15.84 16.81 16.27 T-20 15.72 15.64 17.26 16.10 T -21 12.94 13.10 14.09 13.14 T-22 14.29 14.38 15.27 13.46 T-23 12.86 14.01 15.14 13.67 T-24 12.66 11.92 15.77 13.10 T-25 15.40 16.29 16.93 16.84 T-26 18.42 16.80 17.90 17.48 T-27 12.16 11.32 12.97 12.06 T-28 12.13 12.75 14.04 14.10 T-29 12.28 12.78 13.68 13.12 T-30 13.19 13.72 13.93 13.94 T -31 14.17 13.83 15.63 13.95 T-32 14.71 15.32 15.99 15.12 T-33 11.78 12.61 13.37 12.39 T-34 13.60 14.63 15.94 14.55 T-35 13.97 13.38 14.41 13.51 T-36 13.74 13.21 15.69 14.72 T-37 13.64 14.01 15.39 14.21 T-38 15.88 15.30 16.31 16.18 T-39 61.50 50.49 56.85 56.33 T-40 51.31 38.35 47.12 37.72 T-41 92.48 76.89 82.93 79.67 T-42 91.80 78.65 85.23 81.83 T-43 108.96 76.09 90.35 89.03 T-44 86.29 45.62 80.98 78.16 T-45 57.10 45.62 50.14 47.34 T-46 40.82 36.38 43.77 36.03 T-47 101.85 74.96 82.04 68.82 (a) TLD mIssmg, see AppendIx D - Program Execullon.

C-l

Fermi 2 - 2009 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 46.53 38.12 43.83 42.25 T-49 16.73 19.32 21.88 19.78 T-50 14.99 15.22 17.11 15.78 T -51 11.53 10.82 12.69 12.66 T-52 14.25 14.40 15.85 15.32 T-53 26.49 23.51 27.86 25.93 T-54 18.15 16.30 18.84 18.22 T-55 14.58 15.81 16.90 15.86 T-56 (a) 14.55 15.98 15.09 T-57 16.56 16.98 19.82 18.04 T-58 12.54 12.38 14.98 13.05 T-59 12.78 12.88 15.99 13.82 T-60 14.44 15.07 16.94 15.24 T -61 14.98 15.48 16.62 15.97 T-62 14.68 14.98 16.41 15.98 T-63 12.87 12.37 14.75 13.71 T-64 25.09 23.00 23.86 21.95 T-65 25.77 (a) (a) 24.81 T-66 143.13 115.08 122.86 128.06 T-67 17.75 17.03 19.15 17.64 T-68 16.50 17.14 18.70 17.14 T-69 14.89 16.20 17.95 16.79 T-70 14.08 15.11 16.83 15.50 T -71 15.16 16.53 18.40 16.89 (a) TLD missing, see Appendix D - Program Execution.

C-2

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-l FIRST QUARTER Date Activitr 11712009 3.57E-02 +/- 2.80E-03 111412009 2.85E-02 +/- 2.70E-03 112112009 3.93E-02 +/- 2.90E-03 113012009 4.12E-02 +/- 2.70E-03 2/412009 3.03E-02 +/- 3.30E-03 211112009 3.30E-02 +/- 2.70E-03 211812009 1.96E-02 +/- 2.30E-03 212512009 3.07E-02 +/- 2.70E-03 3/312009 3.57E-02 +/- 3.10E-03 311012009 3.27E-02 +/- 2.50E-03 311712009 3.18E-02 +/- 2.50E-03 312412009 3.08E-02 +/- 2.40E-03 3/3112009 1.63E-02 +/- 2.60E-03 API-l SECOND QUARTER Date Activiqr 41712009 1.96E-02 +/- 2.30E-03 411412009 2.73E-02 +/- 2.40E-03 412112009 2.40E-02 +/- 2.40E-03 412912009 2.29E-02 +/- 2.30E-03 5/612009 l.73E-02 +/- 2.30E-03 511312009 1.61E-02 +/- 2.50E-03 512012009 2.23E-02 +/- 2.60E-03 512712009 2.23E-02 +/- 2.50E-03 6/312009 2.00E-02 +/- 2.40E-03 611012009 l.36E-02 +/- 2.50E-03 611712009 1.60E-02 +/- 2.40E-03 612412009 2.08E-02 +/- 2.20E-03 C-3

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-l THIRD QUARTER Date Activitr 7/812009 1.84E-02 +/- 2.50E-03 711512009 2.27E-02 +/- 2.40E-03 712212009 1.89E-02 +/- 2.20E-03 712912009 3.08E-02 +/- 2.70E-03 8/512009 3.07E-02 +/- 2.60E-03 811312009 2.67E-02 +/- 2.70E-03 811912009 3.59E-02 +/- 2.80E-03 812612009 1.96E-02 +/- 2.20E-03 91212009 1.88E-02 +/- 2.50E-03 9/912009 4.32E-02 +/- 3.20E-03 911612009 4.55E-02 +/- 3.20E-03 912312009 1.88E-02 +/- 2.70E-03 9/3012009 2.43E-02 +/- 2.90E-03 API-l FOURTH QUARTER Date Activiqr 101712009 1.83E-02 +/- 2.80E-03 1011412009 2.34E-02 +/- 2.70E-03 1012112009 2.48E-02 +/- 2.80E-03 1012812009 2.21E-02 +/- 2.90E-03 111412009 2.47E-02 +/- 2.90E-03 1111112009 3.37E-02 +/- 3.10E-03 1111812009 2.54E-02 +/- 2.90E-03 1112512009 3.66E-02 +/- 3.00E-03 121212009 3.16E-02 +/- 3.00E-03 12/912009 2.33E-02 +/- 2.40E-03 1211612009 3.78E-02 +/- 3.50E-03 1212212009 3.59E-02 +/- 2.90E-03 1212912009 2.87E-02 +/- 3.20E-03 C-4

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-2 FIRST QUARTER Date Activitr 11712009 3.55E-02 +/- 2.80E-03 111412009 3.64E-02 +/- 2.80E-03 112112009 4.32E-02 +/- 2.90E-03 113012009 4.76E-02 +/- 2.80E-03 2/412009 3.31E-02 +/- 3.30E-03 211112009 4.48E-02 +/- 2.90E-03 211812009 2.65E-02 +/- 2.40E-03 212512009 3.19E-02 +/- 2.70E-03 3/312009 3.77E-02 +/- 3.10E-03 311012009 3.41E-02 +/- 2.50E-03 311712009 3.99E-02 +/- 2.60E-03 312412009 3.76E-02 +/- 2.50E-03 3/3112009 2.07E-02 +/- 2.60E-03 API-2 SECOND QUARTER Date Activiqr 41712009 2.06E-02 +/- 2.30E-03 411412009 2.47E-02 +/- 2.30E-03 412112009 2.68E-02 +/- 2.40E-03 412912009 2.06E-02 +/- 2.30E-03 5/612009 2.30E-02 +/- 2.40E-03 511312009 2.11E-02 +/- 2.50E-03 512012009 2.18E-02 +/- 2.60E-03 512712009 2.28E-02 +/- 2.60E-03 6/312009 l.76E-02 +/- 2.40E-03 611012009 2.18E-02 +/- 2.60E-03 611712009 1. 95E-02 +/- 2.40E-03 612412009 1.59E-02 +/- 2.20E-03 C-5

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-2 THIRD QUARTER Date Activitr 71112009 2.61E-02 +/- 2.70E-03 7/812009 2.14E-02 +/- 2.50E-03 711512009 1.97E-02 +/- 2.40E-03 712212009 1.86E-02 +/- 2.20E-03 712912009 2.74E-02 +/- 2.60E-03 8/512009 2.38E-02 +/- 2.50E-03 811312009 2.49E-02 +/- 2.60E-03 811912009 3.42E-02 +/- 2.70E-03 812612009 1.64E-02 +/- 2.10E-03 91212009 1.95E-02 +/- 2.50E-03 9/912009 3.41E-02 +/- 3.10E-03 911612009 3.81E-02 +/- 3.10E-03 912312009 1.60E-02 +/- 2.70E-03 API-2 FOURTH QUARTER Date Activiqr 101712009 1.59E-02 +/- 2.70E-03 1011412009 2.37E-02 +/- 2.80E-03 1012112009 3.17E-02 +/- 2.90E-03 1012812009 3.20E-02 +/- 3.10E-03 111412009 2.83E-02 +/- 2.90E-03 1111112009 4.79E-02 +/- 3.30E-03 1111812009 2.83E-02 +/- 3.00E-03 1112512009 4.60E-02 +/- 3.20E-03 121212009 3.31E-02 +/- 3.00E-03 12/912009 3.49E-02 +/- 2.60E-03 1211612009 5.22E-02 +/- 3.40E-03 1212212009 4.96E-02 +/- 3.10E-03 1212912009 3.29E-02 +/- 3.30E-03 C-6

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-3 FIRST QUARTER Date Activitr 11712009 3.92E-02 +/- 2.90E-03 111412009 4.28E-02 +/- 2.90E-03 112112009 4.03E-02 +/- 2.90E-03 113012009 4.76E-02 +/- 2.80E-03 2/412009 3.49E-02 +/- 3.30E-03 211112009 4.03E-02 +/- 2.80E-03 211812009 2.61E-02 +/- 2.40E-03 212512009 3.10E-02 +/- 2.70E-03 3/312009 3.53E-02 +/- 3.10E-03 311012009 3.37E-02 +/- 2.50E-03 311712009 3.54E-02 +/- 2.50E-03 312412009 2.84E-02 +/- 2.40E-03 3/3112009 2.07E-02 +/- 2.60E-03 API-3 SECOND QUARTER Date Activiqr 41712009 2.24E-02 +/- 2.30E-03 411412009 2.68E-02 +/- 2.40E-03 412112009 2.83E-02 +/- 2.40E-03 412912009 2.08E-02 +/- 2.30E-03 5/612009 2.41E-02 +/- 2.40E-03 511312009 l.71E-02 +/- 2.50E-03 512012009 2.02E-02 +/- 2.50E-03 512712009 2.40E-02 +/- 2.60E-03 6/312009 1.94E-02 +/- 2.40E-03 611012009 1.80E-02 +/- 2.50E-03 611712009 l.70E-02 +/- 2.40E-03 612412009 1.56E-02 +/- 2.10E-03 C-7

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-3 THIRD QUARTER Date Activitr 71112009 2.50E-02 +/- 2.70E-03 7/812009 l.75E-02 +/- 2.40E-03 711512009 2.14E-02 +/- 2.40E-03 712212009 l.73E-02 +/- 2.10E-03 712912009 2.93E-02 +/- 2.60E-03 8/512009 2.79E-02 +/- 2.50E-03 811312009 2.56E-02 +/- 2.60E-03 811912009 3.28E-02 +/- 2.70E-03 812612009 1.50E-02 +/- 2.10E-03 91212009 2.13E-02 +/- 2.50E-03 9/912009 3.33E-02 +/- 3.00E-03 911612009 3.53E-02 +/- 3.00E-03 912312009 l.74E-02 +/- 2.70E-03 API-3 FOURTH QUARTER Date Activiqr 101712009 1.55E-02 +/- 2.70E-03 1011412009 2.76E-02 +/- 2.80E-03 1012112009 2.43E-02 +/- 2.80E-03 1012812009 2.56E-02 +/- 3.00E-03 111412009 2.12E-02 +/- 2.80E-03 1111112009 3.54E-02 +/- 3.10E-03 1111812009 2.88E-02 +/- 3.00E-03 1112512009 4.62E-02 +/- 3.20E-03 121212009 3.05E-02 +/- 3.00E-03 12/912009 3.07E-02 +/- 2.50E-03 1211612009 3.93E-02 +/- 3.20E-03 1212212009 4.19E-02 +/- 3.00E-03 1212912009 3.00E-02 +/- 3.20E-03 C-8

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-4 FIRST QUARTER Date Activitr 11712009 4.45E-02 +/- 3.00E-03 111412009 4.16E-02 +/- 2.90E-03 112112009 4.45E-02 +/- 2.90E-03 113012009 4.94E-02 +/- 2.80E-03 2/412009 3.92E-02 +/- 3.40E-03 211112009 4.79E-02 +/- 3.00E-03 211812009 2.97E-02 +/- 2.40E-03 212512009 (a) 3/312009 3.72E-02 +/- 3.70E-03 311012009 3.36E-02 +/- 2.50E-03 311712009 3.92E-02 +/- 2.60E-03 312412009 3.57E-02 +/- 2.50E-03 3/3112009 2.22E-02 +/- 2.60E-03 API-4 SECOND QUARTER Date Activiqr 41712009 2.39E-02 +/- 2.40E-03 411412009 3.23E-02 +/- 2.40E-03 412112009 2.68E-02 +/- 2.40E-03 412912009 2.25E-02 +/- 2.30E-03 5/612009 2.53E-02 +/- 2.40E-03 511312009 2.50E-02 +/- 2.60E-03 512012009 2.28E-02 +/- 2.60E-03 512712009 2.97E-02 +/- 2.70E-03 6/312009 2.27E-02 +/- 2.50E-03 611012009 2.26E-02 +/- 2.60E-03 611712009 2.89E-02 +/- 2.60E-03 612412009 1.95E-02 +/- 2.10E-03 (a) See Appendix D - Program Execution.

C-9

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-4 THIRD QUARTER Date Activitr 71112009 2.43E-02 +/- 2.70E-03 7/812009 1.85E-02 +/- 2.40E-03 711512009 2.51E-02 +/- 2.50E-03 712212009 1.89E-02 +/- 2.20E-03 712912009 2.71E-02 +/- 2.60E-03 8/512009 3.08E-02 +/- 2.60E-03 811312009 2.63E-02 +/- 2.70E-03 811912009 3.19E-02 +/- 2.70E-03 812612009 l.78E-02 +/- 2.20E-03 91212009 2.22E-02 +/- 2.50E-03 9/912009 3.62E-02 +/- 3.20E-03 911612009 4.61E-02 +/- 3.20E-03 912312009 1.98E-02 +/- 2.70E-03 API-4 FOURTH QUARTER Date Activiqr 101712009 1.52E-02 +/- 2.70E-03 1011412009 2.23E-02 +/- 2.70E-03 1012112009 3.49E-02 +/- 2.90E-03 1012812009 2.88E-02 +/- 3.10E-03 111412009 3.03E-02 +/- 2.90E-03 1111112009 4.17E-02 +/- 3.20E-03 1111812009 2.52E-02 +/- 2.90E-03 1112512009 4.82E-02 +/- 3.20E-03 121212009 2.67E-02 +/- 2.90E-03 12/912009 2.82E-02 +/- 2.50E-03 1211612009 4.26E-02 +/- 3.20E-03 1212212009 4.75E-02 +/- 3.00E-03 1212912009 3.05E-02 +/- 3.20E-03 C-lO

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-5 FIRST QUARTER Date Activitr 11712009 5.34E-02 +/- 3.10E-03 111412009 5.70E-02 +/- 3.10E-03 112112009 6.08E-02 +/- 3.10E-03 113012009 6.26E-02 +/- 3.00E-03 2/412009 5.24E-02 +/- 3.60E-03 211112009 5.77E-02 +/- 3.10E-03 211812009 3.08E-02 +/- 2.50E-03 212512009 4.37E-02 +/- 2.90E-03 3/312009 4.44E-02 +/- 3.20E-03 311012009 5.28E-02 +/- 2.80E-03 311712009 5.93E-02 +/- 2.90E-03 312412009 5.42E-02 +/- 2.70E-03 3/3112009 3.89E-02 +/- 2.90E-03 API-5 SECOND QUARTER Date Activiqr 41712009 3.80E-02 +/- 2.60E-03 411412009 4.27E-02 +/- 2.60E-03 412112009 4.53E-02 +/- 2.70E-03 412912009 3.78E-02 +/- 2.50E-03 5/612009 4.04E-02 +/- 2.60E-03 511312009 3.17E-02 +/- 2.70E-03 512012009 3.60E-02 +/- 2.80E-03 512712009 3.86E-02 +/- 2.80E-03 6/312009 3.09E-02 +/- 2.60E-03 611012009 2.82E-02 +/- 2.70E-03 611712009 3.13E-02 +/- 2.60E-03 612412009 1.12E-02 +/- 2.20E-03 C-11

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE GROSS BETA (pCi/cubic meter)

API-5 THIRD QUARTER Date Activitr 71112009 3.86E-02 +/- 3.00E-03 7/812009 2.82E-02 +/- 2.60E-03 711512009 3.69E-02 +/- 2.60E-03 712212009 2.77E-02 +/- 2.30E-03 712912009 4.04E-02 +/- 2.80E-03 8/512009 4.81E-02 +/- 2.80E-03 811312009 4.40E-02 +/- 2.90E-03 811912009 5.45E-02 +/- 3.00E-03 812612009 2.58E-02 +/- 2.30E-03 91212009 3.13E-02 +/- 2.70E-03 9/912009 4.99E-02 +/- 3.40E-03 911612009 5.85E-02 +/- 3.40E-03 912312009 2.88E-02 +/- 2.90E-03 API-5 FOURTH QUARTER Date Activiqr 101712009 2.01E-02 +/- 2.80E-03 1011412009 2.49E-02 +/- 2.80E-03 1012112009 4.30E-02 +/- 3.00E-03 1012812009 3.34E-02 +/- 3.10E-03 111412009 3.71E-02 +/- 3.10E-03 1111112009 4.17E-02 +/- 3.20E-03 1111812009 3.64E-02 +/- 3.10E-03 1112512009 5.03E-02 +/- 3.30E-03 121212009 3.33E-02 +/- 3.00E-03 12/912009 4.40E-02 +/- 2.70E-03 1211612009 4.35E-02 +/- 3.20E-03 1212212009 5.36E-02 +/- 3.10E-03 1212912009 3.24E-02 +/- 3.20E-03 C-12

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-l FIRST QUARTER Date Activity 11712009 < 2.90E-02 111412009 < 3.20E-02 112112009 < 2.40E-02 113012009 < 3.50E-02 2/412009 < 4.10E-02 211112009 < 2.80E-02 211812009 < 3.00E-02 212512009 < 2.40E-02 3/312009 < 3.lOE-02 311012009 < 2.60E-02 311712009 < 3.lOE-02 312412009 < 2.80E-02 3/3112009 < 2.60E-02 API-l SECOND QUARTER Date Activity 41712009 < 4.60E-02 411412009 < 3.40E-02 412112009 < 3.30E-02 412912009 < 2.00E-02 5/612009 < 3.lOE-02 511312009 < 3.50E-02 512012009 < 2.70E-02 512712009 < 2.40E-02 6/312009 < 3.60E-02 611012009 < 2.70E-02 611712009 < 2.10E-02 612412009 < 3.lOE-02 C-13

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-l THIRD QUARTER Date Activity 7/812009 < 2.70E-02 711512009 < 3.lOE-02 712212009 < 2.30E-02 712912009 < 2.80E-02 8/512009 < 3.lOE-02 811312009 < 3.20E-02 811912009 < 3.00E-02 812612009 < 2.60E-02 91212009 < 2.80E-02 91912009 < 2.80E-02 911612009 < 3.40E-02 912312009 < 2.90E-02 9/3012009 < 3.80E-02 API-l FOURTH QUARTER Date Activity 101712009 < 4.60E-02 1011412009 < 4.50E-02 1012112009 < 2.60E-02 1012812009 < 3.80E-02 111412009 < 4.30E-02 1111112009 < 3.60E-02 1111812009 < 2.20E-02 1112512009 < 5.50E-02 121212009 < 2.60E-02 121912009 < 2.60E-02 1211612009 < 3.20E-02 1212212009 < 4.80E-02 1212912009 < 3.70E-02 C-14

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-2 FIRST QUARTER Date Activity 11712009 < 4.10E-02 111412009 < 2.90E-02 112112009 < 3.lOE-02 113012009 < 3.30E-02 2/412009 < 4.00E-02 211112009 < 3.20E-02 211812009 < 3.30E-02 212512009 < 2.60E-02 3/312009 < 3.30E-02 311012009 < 3.20E-02 311712009 < 3.40E-02 312412009 < 3.00E-02 3/3112009 < 2.20E-02 API-2 SECOND QUARTER Date Activity 41712009 < 5.60E-02 411412009 < 3.40E-02 412112009 < 2.40E-02 412912009 < 2.30E-02 5/612009 < 3.80E-02 511312009 < 4.00E-02 512012009 < 2.60E-02 512712009 < 3.40E-02 6/312009 < 3.90E-02 611012009 < 3.50E-02 611712009 < 2.90E-02 612412009 < 2.90E-02 C-15

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-2 THIRD QUARTER Date Activity 71112009 < 2.80E-02 71812009 < 2.40E-02 711512009 < 4.00E-02 712212009 < 3.00E-02 712912009 < 3.40E-02 8/512009 < 2.90E-02 811312009 < 3.60E-02 811912009 < 4.10E-02 812612009 < 2.40E-02 91212009 < 3.50E-02 91912009 < 2.60E-02 911612009 < 3.70E-02 912312009 < 2.60E-02 API-2 FOURTH QUARTER Date Activity 101712009 < 2.90E-02 1011412009 < 4.90E-02 1012112009 < 2.40E-02 1012812009 < 3.30E-02 111412009 < 3.80E-02 1111112009 < 2.40E-02 1111812009 < 3.60E-02 1112512009 < 4.70E-02 121212009 < 3.60E-02 121912009 < 2.80E-02 1211612009 < 2.80E-02 1212212009 < 4.40E-02 1212912009 < 3.80E-02 C-16

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-3 FIRST QUARTER Date Activity 11712009 < 3.80E-02 111412009 < 3.30E-02 112112009 < 3.40E-02 113012009 < 4.30E-02 2/412009 < 3.lOE-02 211112009 < 2.90E-02 211812009 < 2.80E-02 212512009 < 2.80E-02 3/312009 < 2.90E-02 311012009 < 2.80E-02 311712009 < 3.70E-02 312412009 < 3.90E-02 3/3112009 < 2.90E-02 API-3 SECOND QUARTER Date Activity 41712009 < 4.70E-02 411412009 < 3.lOE-02 412112009 < 2.40E-02 412912009 < 3.20E-02 5/612009 < 4.40E-02 511312009 < 3.90E-02 512012009 < 1.90E-02 512712009 < 3.30E-02 6/312009 < 3.60E-02 611012009 < 2.90E-02 611712009 < 2.70E-02 612412009 < 3.70E-02 C-17

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-3 THIRD QUARTER Date Activity 71112009 < 3.40E-02 71812009 < 2.60E-02 711512009 < 3.60E-02 712212009 < 4.10E-02 712912009 < 3.40E-02 8/512009 < 3.90E-02 811312009 < 3.40E-02 811912009 < 3.50E-02 812612009 < 2.60E-02 91212009 < 3.40E-02 91912009 < 2.90E-02 911612009 < 3.20E-02 912312009 < 4.10E-02 API-3 FOURTH QUARTER Date Activity 101712009 < 3.50E-02 1011412009 < 3.40E-02 1012112009 < 2.40E-02 1012812009 < 4.30E-02 111412009 < 4.40E-02 1111112009 < 3.20E-02 1111812009 < 4.00E-02 1112512009 < 4.40E-02 121212009 < 3.lOE-02 121912009 < 6.50E-02 1211612009 < 2.50E-02 1212212009 < 5.50E-02 1212912009 < 4.40E-02 C-18

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-4 FIRST QUARTER Date Activity 11712009 < 3.90E-02 111412009 < 3.30E-02 112112009 < 2.80E-02 113012009 < 4.00E-02 2/412009 < 3.40E-02 211112009 < 2.00E-02 211812009 < 3.40E-02 212512009 < (a) 3/312009 < 4.30E-02 311012009 < 1.90E-02 311712009 < 2.00E-02 312412009 < 3.lOE-02 3/3112009 < 2.40E-02 API-4 SECOND QUARTER Date Activity 41712009 < 4.40E-02 411412009 < 4.40E-02 412112009 < 2.70E-02 412912009 < 1.60E-02 5/612009 < 3.50E-02 511312009 < 3.70E-02 512012009 < 2.50E-02 512712009 < 2.60E-02 6/312009 < 3.30E-02 611012009 < 2.30E-02 611712009 < 2.80E-02 612412009 < 3.60E-02 (a) See Appendix D - Program Execution.

C-19

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-4 THIRD QUARTER Date Activity 71112009 < 4.40E-02 71812009 < 2.80E-02 711512009 < 2.70E-02 712212009 < 2.10E-02 712912009 < 3.40E-02 8/512009 < 3.lOE-02 811312009 < 3.20E-02 811912009 < 2.80E-02 812612009 < 2.60E-02 91212009 < 4.10E-02 91912009 < 3.30E-02 911612009 < 3.lOE-02 912312009 < 4.20E-02 API-4 FOURTH QUARTER Date Activity 101712009 < 4.10E-02 1011412009 < 4.10E-02 1012112009 < 2.70E-02 1012812009 < 3.70E-02 111412009 < 5.20E-02 1111112009 < 3.00E-02 1111812009 < 3.40E-02 1112512009 < 4.20E-02 121212009 < 2.90E-02 121912009 < 6.50E-02 1211612009 < 2.80E-02 1212212009 < 4.70E-02 1212912009 < 4.50E-02 C-20

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-5 FIRST QUARTER Date Activity 11712009 < 4.40E-02 111412009 < 2.60E-02 112112009 < 2.80E-02 113012009 < 3.50E-02 2/412009 < 4.20E-02 211112009 < 3.20E-02 211812009 < 3.30E-02 212512009 < 2.30E-02 3/312009 < 3.00E-02 311012009 < 2.30E-02 311712009 < 3.40E-02 312412009 < 3.80E-02 3/3112009 < 3.50E-02 API-5 SECOND QUARTER Date Activity 41712009 < 4.30E-02 411412009 < 4.60E-02 412112009 < 2.60E-02 412912009 < 3.40E-02 5/612009 < 4.20E-02 511312009 < 2.90E-02 512012009 < 2.00E-02 512712009 < 3.00E-02 6/312009 < 3.90E-02 611012009 < 2.10E-02 611712009 < 2.80E-02 612412009 < 2.40E-02 C-21

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR IODINE - 131 (pCi/cubic meter)

API-5 THIRD QUARTER Date Activity 71112009 < 3.60E-02 71812009 < 2.80E-02 711512009 < 3.50E-02 712212009 < 3.70E-02 712912009 < 2.80E-02 8/512009 < 3.50E-02 811312009 < 3.lOE-02 811912009 < 3.lOE-02 812612009 < 2.30E-02 91212009 < 3.80E-02 91912009 < 3.70E-02 911612009 < 3.90E-02 912312009 < 2.60E-02 API-5 FOURTH QUARTER Date Activity 101712009 < 4.30E-02 1011412009 < 3.40E-02 1012112009 < 2.70E-02 1012812009 < 3.50E-02 111412009 < 4.00E-02 1111112009 < 3.00E-02 1111812009 < 3.70E-02 1112512009 < 5.80E-02 121212009 < 3.70E-02 121912009 < 4.40E-02 1211612009 < 3.00E-02 1212212009 < 4.40E-02 1212912009 < 5.lOE-02 C-22

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-l (indicator)

(pCi/cubic meter)

INuclide First Quarter Second Quarter Be-7 < 7.80E-02 l.17E-Ol +/- 3.50E-02 K-40 < 3.30E-02 < 3.50E-02 Mn-54 < 3.20E-03 < 4.30E-03 Co-58 < 4AOE-03 < 6.00E-03 Fe-59 < 1.30E-02 < 6.00E-03 Co-60 < 9.30E-04 < 1.50E-03 Zn-65 < 8.20E-03 < 3.00E-03 Zr-95 < 6.30E-03 < 8.00E-03 Nb-95 < 9.20E-03 < 7.80E-03 Ru-l03 < 7.20E-03 < 6.60E-03 Ru-106 < 2.60E-02 < 3AOE-02 Cs-134 < 2.00E-03 < 3.10E-03 Cs-137 < 2.10E-03 < 8.50E-04 Ba-140 < 1.20E-Ol < 4.00E-02 La-140 < 1.20E-Ol < 4.00E-02 Ce-141 < 9.90E-03 < 6.50E-03 Ce-144 < 9.60E-03 < 9.50E-03 API-l (indicator)

(pCi/cubic meter)

INuclide Third Quarter Fourth Quarter Be-7 1.12E-Ol +/- 1.60E-02 9AOE-02 +/- 1AOE-02 K-40 < 2.10E-02 < 3.00E-02 Mn-54 < 2.30E-03 < 2.20E-03 Co-58 < 3.00E-03 < 1.90E-03 Fe-59 < 9.30E-03 < 7.00E-03 Co-60 < 1.60E-03 < 7.30E-04 Zn-65 < 5.60E-03 < 7.20E-03 Zr-95 < 4.20E-03 < 4.90E-03 Nb-95 < 6.10E-03 < 5.60E-03 Ru-l03 < 5.lOE-03 < 3.90E-03 Ru-106 < l.70E-02 < 2.10E-02 Cs-134 < l.70E-03 < l.70E-03 Cs-137 < 1.90E-03 < 1.50E-03 Ba-140 < 5.00E-02 < 3.60E-02 La-140 < 5.00E-02 < 3.60E-02 Ce-141 < 6.20E-03 < 4AOE-03 Ce-144 < 6.70E-03 < 6AOE-03 C-23

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-2 (indicator)

(pCi/cubic meter)

INuclide First Quarter Second Quarter Be-7 lAOE-Ol +/- 2.80E-02 1.26E-Ol +/- 2.50E-02 K-40 < 4.10E-02 < 4AOE-02 Mn-54 < 2.60E-03 < 3.80E-03 Co-58 < lAOE-03 < 5.lOE-03 Fe-59 < 1.90E-02 < 5.30E-03 Co-60 < 3.70E-03 < lAOE-03 Zn-65 < 1.20E-02 < 2.80E-03 Zr-95 < 6.50E-03 < 9.00E-03 Nb-95 < 9.lOE-03 < 2.60E-03 Ru-l03 < 6.00E-03 < 5.80E-03 Ru-106 < 3.00E-02 < 7AOE-03 Cs-134 < 2.20E-03 < 3.30E-03 Cs-137 < 2.60E-03 < 2AOE-03 Ba-140 < 2.20E-Ol < 9.60E-02 La-140 < 2.20E-Ol < 9.60E-02 Ce-141 < 8AOE-03 < 6.70E-03 Ce-144 < 8.60E-03 < 9.00E-03 API-2 (indicator)

(pCi/cubic meter)

INuclide Third Quarter Fourth Quarter Be-7 < 7.70E-02 8.20E-02 +/- 1.80E-02 K-40 < 5AOE-02 < 2.90E-02 Mn-54 < 3.50E-03 < 3.lOE-03 Co-58 < 4.50E-03 < 4.60E-03 Fe-59 < 5.80E-03 < 1AOE-02 Co-60 < 4.90E-03 < 1.20E-03 Zn-65 < 1.50E-02 < 7.90E-03 Zr-95 < 7.60E-03 < 9.lOE-03 Nb-95 < 9.50E-03 < 8.70E-03 Ru-l03 < 7AOE-03 < 4AOE-03 Ru-106 < 2.20E-02 < 2.30E-02 Cs-134 < 2.60E-03 < 2.80E-03 Cs-137 < 8.00E-04 < 3.70E-03 Ba-140 < l.lOE-Ol < l.70E-02 La-140 < l.lOE-Ol < l.70E-02 Ce-141 < l.lOE-02 < 5.90E-03 Ce-144 < 8.00E-03 < 7.50E-03 C-24

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-3 (indicator)

(pCi/cubic meter)

INuclide First Quarter Second Quarter Be-7 l.03E-Ol +/- 2.20E-02 lA3E-Ol +/- 2.20E-02 K-40 < 4.10E-02 < 3.70E-02 Mn-54 < 2.00E-03 < 2.30E-03 Co-58 < 3.60E-03 < 2.80E-03 Fe-59 < 1AOE-02 < l.OOE-02 Co-60 < 4.60E-03 < 2.60E-03 Zn-65 < 9.70E-03 < 6.60E-03 Zr-95 < 2.50E-03 < 4.70E-03 Nb-95 < l.OOE-02 < 6.30E-03 Ru-l03 < 6.80E-03 < l.lOE-03 Ru-106 < 2.80E-02 < 2.10E-02 Cs-134 < 2.50E-03 < 2.20E-03 Cs-137 < 3.20E-03 < 1.50E-03 Ba-140 < 2.lOE-Ol < 1.80E-02 La-140 < 2.lOE-Ol < 1.80E-02 Ce-141 < 9.lOE-03 < 4.80E-03 Ce-144 < 6.70E-03 < 7.lOE-03 API-3 (indicator)

(pCi/cubic meter)

INuclide Third Quarter Fourth Quarter Be-7 8.20E-02 +/- 2.70E-02 l.09E-Ol +/- 1.80E-02 K-40 < 5.30E-02 < 3.80E-02 Mn-54 < l.OOE-03 < 2.00E-03 Co-58 < 6.30E-03 < 3AOE-03 Fe-59 < 1.60E-02 < 6.90E-03 Co-60 < 6.20E-03 < 2.70E-03 Zn-65 < 7.70E-03 < 6.90E-03 Zr-95 < 1.30E-02 < 7.90E-03 Nb-95 < 1.20E-02 < 6.60E-03 Ru-l03 < 1.90E-03 < 4.90E-03 Ru-106 < 2.20E-02 < 1.60E-02 Cs-134 < 3.70E-03 < l.70E-03 Cs-137 < 3.50E-03 < 1.80E-03 Ba-140 < 4.00E-02 < 3.70E-02 La-140 < 4.00E-02 < 3.70E-02 Ce-141 < 8.50E-03 < 4.60E-03 Ce-144 < 8.20E-03 < 9.50E-03 C-25

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-4 (control)

(pCi/cubic meter)

INuclide First Quarter Second Quarter Be-7 1. 72E-O 1 +/- 2.60E-02 1.57E-Ol +/- 2.lOE-02 K-40 < 3.80E-02 < 4.00E-02 Mn-54 < 1.90E-03 < 1.20E-03 Co-58 < 4.30E-03 < 4.70E-03 Fe-59 < 2.10E-02 < 1.80E-02 Co-60 < 3.10E-03 < 9.50E-04 Zn-65 < 4.20E-03 < 5.00E-03 Zr-95 < 7.90E-03 < 7.70E-03 Nb-95 < 9.00E-03 < 4.50E-03 Ru-l03 < 6.70E-03 < 4.50E-03 Ru-106 < 2.70E-02 < 1.80E-02 Cs-134 < 2.10E-03 < 2.20E-03 Cs-137 < 2.30E-03 < 2.30E-03 Ba-140 < 1.60E-Ol < 5.00E-02 La-140 < 1.60E-Ol < 5.00E-02 Ce-141 < 1.OOE-02 < 6.30E-03 Ce-144 < 9.90E-03 < 8AOE-03 API-4 (control)

(pCi/cubic meter)

INuclide Third Quarter Fourth Quarter Be-7 l.06E-Ol +/- 2.30E-02 1.53E-Ol +/- 2.50E-02 K-40 < 3.70E-02 < 2.90E-02 Mn-54 < 2.80E-03 < 2.70E-03 Co-58 < 4.60E-03 < 5.20E-03 Fe-59 < 1AOE-02 < 1.60E-02 Co-60 < 3.20E-03 < 3.10E-03 Zn-65 < 5 AOE-03 < 6.30E-03 Zr-95 < 1.20E-02 < 5.70E-03 Nb-95 < 6AOE-03 < 7.20E-03 Ru-l03 < 5.lOE-03 < 7 AOE-03 Ru-106 < 2.60E-02 < 2.30E-02 Cs-134 < 2.10E-03 < 2.80E-03 Cs-137 < 2.20E-03 < 2.60E-03 Ba-140 < 8.60E-02 < 4.50E-02 La-140 < 8.60E-02 < 4.50E-02 Ce-141 < 6.70E-03 < 5.90E-03 Ce-144 < 8.70E-03 < 6.90E-03 C-26

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 AIR PARTICULATE QUARTERLY COMPOSITE ANALYSIS API-5 (Indicator)

(pCi/cubic meter)

INuclide First Quarter Second Quarter Be-7 2.39E-Ol +/- 3.30E-02 1. 82E-O1 +/- 2.20E-02 K-40 < 2.90E-02 < 4.10E-02 Mn-54 < 2.50E-03 < 2.30E-03 Co-58 < 5.80E-03 < 4.60E-03 Fe-59 < 2.10E-02 < 1.00E-02 Co-60 < 4.50E-03 < 9AOE-04 Zn-65 < 9.60E-03 < 1.80E-03 Zr-95 < 6.60E-03 < 6.80E-03 Nb-95 < l.lOE-02 < 6.30E-03 Ru-l03 < 9.80E-03 < 3.00E-03 Ru-106 < 2.50E-02 < 2AOE-02 Cs-134 < 2.50E-03 < 2.50E-03 Cs-137 < 2.60E-03 < 5.30E-04 Ba-140 < 2AOE-Ol < 7.70E-02 La-140 < 2AOE-Ol < 7.70E-02 Ce-141 < 9.50E-03 < 5.lOE-03 Ce-144 < 8.50E-03 < 6.90E-03 API-5 (Indicator)

(pCi/cubic meter)

INuclide Third Quarter Fourth Quarter Be-7 1.93E-Ol +/- 3.lOE-02 1AOE-O 1 +/- 1. 90E-02 K-40 < 4.50E-02 < 3.00E-02 Mn-54 < 2.70E-03 < 1.50E-03 Co-58 < 7AOE-03 < 2.90E-03 Fe-59 < l.70E-02 < 9.90E-03 Co-60 < 6.30E-03 < 2.10E-03 Zn-65 < 1.00E-02 < 5.70E-03 Zr-95 < 3.00E-03 < 7.90E-03 Nb-95 < 7.60E-03 < 8.70E-03 Ru-l03 < 7AOE-03 < 5.20E-03 Ru-106 < 3.20E-02 < 2.20E-02 Cs-134 < 2.60E-03 < 2.80E-03 Cs-137 < 8.00E-04 < 1.60E-03 Ba-140 < 4.00E-02 < 3.00E-02 La-140 < 4.00E-02 < 3.00E-02 Ce-141 < 6.80E-03 < 6.20E-03 Ce-144 < l.lOE-02 < 8.70E-03 C-27

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-2 (Indicator)

(pCilliter)

I Nuclide 22-JAN 19-FEB 26-MAR 1-131 < 7AOE-01 < 8.60E-01 < 7.90E-01 Sr-89 < 6.20E+00 < 6.90E+00 < 7.lOE+00 Sr-90 < 1AOE+OO < 1.70E+00 < 1AOE+OO Be-7 < 4.90E+01 < 7.00E+01 < 5.20E+01 K-40 1. 54E+03 +/- 7.20E+01 1.30E+03 +/- 7.90E+01 1.36E+03 +/- 5.80E+01 Mn-54 < 5AOE+00 < 7.70E+00 < 6.00E+00 Co-58 < 6.60E+00 < 8.lOE+00 < 5.70E+00 Fe-59 < 1.60E+01 < 1.70E+01 < 1.30E+01 Co-60 < 8.lOE+00 < 7.80E+00 < 6.70E+00 Zn-65 < 3.20E+01 < 2.00E+01 < 1.80E+01 Zr-95 < 1.30E+01 < 1AOE+01 < 1.1 OE+O 1 Nb-95 < 8.60E+00 < 8.90E+00 < 7.60E+00 Ru-103 < 6.70E+00 < 8.30E+00 < 6AOE+00 Ru-106 < 6.00E+01 < 6.30E+01 < 5.20E+01 Cs-134 < 7.80E+00 < 7.50E+00 < 6.20E+00 Cs-137 < 7.00E+00 < 8.70E+00 < 6.00E+00 Ba-140 < 1.1 OE+O 1 < 1AOE+01 < 1.30E+01 La-140 < 1.1 OE+O 1 < 1AOE+01 < 1.30E+01 Ce-141 < 1.00E+01 < 1.1 OE+O 1 < 8.70E+00 Ce-144 < 3.50E+01 < 4.20E+01 < 3.20E+01 I Nuclide 22-APR 2 I-MAY 28-MAY 1-131 < 9.30E-01 < 9.lOE-01 < 9.00E-01 Sr-89 < 9.90E+00 < 6.50E+00 < 7.00E+00 Sr-90 < 1.70E+00 1.25E+00 +/- 3.70E-01 < 1.80E+00 Be-7 < 4.50E+01 < 5.lOE+01 < 6.80E+01 K-40 1.39E+03 +/- 6.80E+01 1A7E+03 +/- 7.lOE+01 1.21E+03 +/- 7.90E+01 Mn-54 < 6.50E+00 < 7.60E+00 < 7AOE+00 Co-58 < 6.70E+00 < 7AOE+00 < 7.90E+00 Fe-59 < 1.70E+01 < 1.70E+01 < 1.80E+01 Co-60 < 8.20E+00 < 7.50E+00 < 8.20E+00 Zn-65 < 1.80E+01 < 2.90E+01 < 1.70E+01 Zr-95 < 1.00E+01 < 1.20E+01 < 1AOE+01 Nb-95 < 6.lOE+00 < 8.50E+00 < 8.lOE+00 Ru-103 < 5.60E+00 < 8.00E+00 < 9.20E+00 Ru-106 < 5AOE+01 < 6.60E+01 < 7.60E+01 Cs-134 < 5.50E+00 < 7AOE+00 < 7.90E+00 Cs-137 < 6AOE+00 < 6.50E+00 < 6.90E+00 Ba-140 < 1.30E+01 < 1.50E+01 < 1.50E+01 La-140 < 1.30E+01 < 1.50E+01 < 1.50E+01 Ce-141 < 7.60E+00 < 1.1 OE+O 1 < 1.1 OE+O 1 Ce-144 < 2.80E+01 < 3.70E+01 < 4.20E+01 C-28

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-2 (Indicator)

(pCilliter)

I Nuclide 11-JUN 25-JUN 16-JUL 1-131 < 7.90E-01 < 9.30E-01 < 8.80E-01 Sr-89 < 5AOE+00 < 7.00E+00 < 5AOE+00 Sr-90 < 1.l0E+00 < l.30E+00 < 1AOE+OO Be-7 < 6.80E+01 < 5.80E+01 < 6AOE+01 K-40 1A2E+03 +/- 8.80E+01 1A2E+03 +/- 6.90E+01 1.28E+03 +/- 7AOE+01 Mn-54 < 7.60E+00 < 7.lOE+00 < 7.60E+00 Co-58 < 5.80E+00 < 7.lOE+00 < 7.50E+00 Fe-59 < l.70E+01 < 1.60E+01 < l.70E+01 Co-60 < 9.70E+00 < 7.20E+00 < 8AOE+00 Zn-65 < 2AOE+01 < 1.80E+01 < 1.80E+01 Zr-95 < 1.80E+01 < 1.20E+01 < 1.50E+01 Nb-95 < 9.60E+00 < 8AOE+00 < 7.30E+00 Ru-103 < 8.80E+00 < 8.10E+00 < 7.60E+00 Ru-106 < 8.20E+01 < 5.80E+01 < 7.60E+01 Cs-134 < 8.lOE+00 < 6.50E+00 < 6.50E+00 Cs-137 < 9.60E+00 < 7.20E+00 < 7.70E+00 Ba-140 < 1.00E+01 < 1.50E+01 < l.30E+01 La-140 < 1.00E+01 < 1.50E+01 < l.30E+01 Ce-141 < 1.20E+01 < 1.00E+01 < 1.00E+01 Ce-144 < 4.30E+01 < 3.60E+01 < 3 AOE+O 1 I Nuclide 30-JUL 13-AUG 27-AUG 1-131 < 7.60E-01 < 9.00E-01 < 8.lOE-01 Sr-89 < 7.20E+00 < 6.60E+00 < 9.20E+00 Sr-90 < 1AOE+OO < 1.50E+00 2.04E+00 +/- 4.70E-01 Be-7 < 6.30E+01 < 5AOE+01 < 4AOE+01 K-40 1. 54E+03 +/- 8.00E+01 1A9E+03 +/- 6.80E+01 1. 24E+03 +/- 6.70E+01 Mn-54 < 7.30E+00 < 6.20E+00 < 5.00E+00 Co-58 < 7.60E+00 < 6.00E+00 < 7.lOE+00 Fe-59 < l.70E+01 < 1.60E+01 < 2.00E+01 Co-60 < 9.lOE+00 < 7.30E+00 < 6.60E+00 Zn-65 < l.70E+01 < l.30E+01 < 1.60E+01 Zr-95 < 1AOE+01 < 1.20E+01 < 1.l0E+01 Nb-95 < 9.20E+00 < 8.70E+00 < 5.60E+00 Ru-103 < 7.30E+00 < 6.70E+00 < 6.30E+00 Ru-106 < 6.80E+01 < 5.30E+01 < 5.80E+01 Cs-134 < 6.lOE+00 < 6.00E+00 < 6.30E+00 Cs-137 < 7.70E+00 < 6.00E+00 < 8.00E+00 Ba-140 < 1.50E+01 < 1AOE+01 < 1AOE+01 La-140 < 1.50E+01 < 1AOE+01 < 1AOE+01 Ce-141 < 1.00E+01 < 9.70E+00 < 8.00E+00 Ce-144 < 3.lOE+01 < 3.30E+01 < 2.90E+01 C-29

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-2 (Indicator)

(pCilliter)

I Nuclide 9-SEP 24-SEP I5-0CT 1-131 < 8.50E-01 < 9.20E-01 < 8.90E-01 Sr-89 < 7AOE+00 < 4.20E+00 < 8.50E+00 Sr-90 < 1.80E+00 < l.30E+00 < l.70E+00 Be-7 < 5.80E+01 < 5.90E+01 < 7.20E+01 K-40 1A6E+03 +/- 7.50E+01 l.37E+03 +/- 6.70E+01 1. 27E+03 +/- 7.70E+01 Mn-54 < 6.20E+00 < 6.70E+00 < 7.20E+00 Co-58 < 7.30E+00 < 7.30E+00 < 9.00E+00 Fe-59 < l.70E+01 < l.70E+01 < 1.60E+01 Co-60 < 9.00E+00 < 6.90E+00 < 9.lOE+00 Zn-65 < 2.00E+01 < l.70E+01 < 2.50E+01 Zr-95 < 1.50E+01 < l.30E+01 < 1.50E+01 Nb-95 < 9.50E+00 < 8.20E+00 < 1.l0E+01 Ru-103 < 8.80E+00 < 7.50E+00 < 8.80E+00 Ru-106 < 6.80E+01 < 5.50E+01 < 6.00E+01 Cs-134 < 7.90E+00 < 7.00E+00 < 6AOE+00 Cs-137 < 7.lOE+00 < 6.60E+00 < 7.lOE+00 Ba-140 < 1AOE+01 < 1.50E+01 < 1AOE+01 La-140 < 1AOE+01 < 1.50E+01 < 1AOE+01 Ce-141 < 1.l0E+01 < 9.50E+00 < 1.l0E+01 Ce-144 < 3.90E+01 < 3.50E+01 < 4.00E+01 I Nuclide 19-NOV 13-DEC 1-131 < 9AOE-01 < 8.00E-01 Sr-89 < 6.70E+00 < 6.60E+00 Sr-90 < 1.80E+00 < 2.00E+00 Be-7 < 4AOE+01 < 8.00E+01 K-40 l.36E+03 +/- 6.00E+01 1.20E+03 +/- 8.30E+01 Mn-54 < 5.20E+00 < 9.70E+00 Co-58 < 5.80E+00 < 9.70E+00 Fe-59 < 1.50E+01 < 2.00E+01 Co-60 < 6.60E+00 < 9AOE+00 Zn-65 < l.70E+01 < 3.80E+01 Zr-95 < 1.l0E+01 < 1.60E+01 Nb-95 < 6.lOE+00 < 1.50E+01 Ru-103 < 5.70E+00 < 1.l0E+01 Ru-106 < 5.60E+01 < 7.50E+01 Cs-134 < 5AOE+00 < 1.00E+01 Cs-137 < 5.30E+00 < 9.50E+00 Ba-140 < 1.50E+01 < 1.20E+01 La-140 < 1.50E+01 < 1.20E+01 Ce-141 < 7AOE+00 < 1AOE+01 Ce-144 < 2.60E+01 < 5.00E+01 C-30

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Control)

(pCilliter)

I Nuclide 22-JAN 19-FEB 26-MAR 1-131 < 9.lOE-01 < 9.60E-01 < 8.20E-01 Sr-89 < 7.00E+00 < 5.90E+00 < 7.80E+00 Sr-90 < 1.70E+00 < 1AOE+OO < 1.60E+00 Be-7 < 4.50E+01 < 5.60E+01 < 5.lOE+01 K-40 1.38E+03 +/- 6AOE+01 1 AOE+03 +/- 7.50E+01 1A4E+03 +/- 7.80E+01 Mn-54 < 6.00E+00 < 7.50E+00 < 6.20E+00 Co-58 < 6.00E+00 < 7.50E+00 < 7.00E+00 Fe-59 < 1.80E+01 < 1.90E+01 < 1.80E+01 Co-60 < 8.lOE+00 < 8.20E+00 < 8.80E+00 Zn-65 < 1.60E+01 < 1.80E+01 < 1.80E+01 Zr-95 < 9.30E+00 < 1.30E+01 < 1.50E+01 Nb-95 < 6.80E+00 < 9.00E+00 < 9.00E+00 Ru-103 < 6.lOE+00 < 8.30E+00 < 8.lOE+00 Ru-106 < 4.60E+01 < 6.80E+01 < 6.80E+01 Cs-134 < 5.90E+00 < 7.30E+00 < 6AOE+00 Cs-137 < 6.80E+00 < 7.50E+00 < 7.90E+00 Ba-140 < 1.50E+01 < 1.1 OE+O 1 < 1.50E+01 La-140 < 1.50E+01 < 1.1 OE+O 1 < 1.50E+01 Ce-141 < 7.60E+00 < 1.00E+01 < 9.20E+00 Ce-144 < 2.70E+01 < 3.80E+01 < 3 AOE+O 1 I Nuclide 22-APR 2 I-MAY 28-MAY 1-131 < 7.50E-01 < 9.20E-01 < 9AOE-01 Sr-89 < 8.60E+00 < 5.70E+00 < 5.70E+00 Sr-90 < 1AOE+OO < 1.00E+00 < 1AOE+OO Be-7 < 5.30E+01 < 5.00E+01 < 6.80E+01 K-40 1AOE+03 +/- 7AOE+01 1A3E+03 +/- 6.90E+01 1.30E+03 +/- 8.70E+01 Mn-54 < 6.lOE+00 < 7.lOE+00 < 8.lOE+00 Co-58 < 7.70E+00 < 6.60E+00 < 8.lOE+00 Fe-59 < 1.60E+01 < 1.80E+01 < 1.80E+01 Co-60 < 8.60E+00 < 7.90E+00 < 1.1 OE+O 1 Zn-65 < 1.80E+01 < 1.80E+01 < 1.60E+01 Zr-95 < 1.00E+01 < 1.20E+01 < 1.50E+01 Nb-95 < 8.lOE+00 < 7.90E+00 < 1.00E+01 Ru-103 < 8.lOE+00 < 7.lOE+00 < 1.30E+01 Ru-106 < 6.80E+01 < 5.70E+01 < 8.30E+01 Cs-134 < 7AOE+00 < 6.90E+00 < 8.60E+00 Cs-137 < 7.20E+00 < 6.50E+00 < 8.00E+00 Ba-140 < 1.20E+01 < 1.50E+01 < 1.30E+01 La-140 < 1.20E+01 < 1.50E+01 < 1.30E+01 Ce-141 < 1.00E+01 < 9.70E+00 < 1.20E+01 Ce-144 < 3. 80E+0 1 < 3.80E+01 < 4AOE+01 C-31

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Control)

(pCilliter)

I Nuclide II-JON 25-JON I6-JUL 1-131 < 7.90E-Ol < 9.20E-Ol < 9.00E-Ol Sr-89 < 5.00E+00 < 7.lOE+00 < 6.90E+00 Sr-90 < 1.00E+00 1.32E+00 +/- 4.lOE-Ol < 2.00E+00 Be-7 < 5.20E+Ol < 4.60E+Ol < 6.70E+Ol K-40 1. 54E+03 +/- 8.20E+Ol 1.45E+03 +/- 5.60E+Ol 1.46E+03 +/- 8.90E+Ol Mn-54 < 7.00E+00 < 5.00E+00 < 9.00E+00 Co-58 < 6.80E+00 < 5.70E+00 < 8.00E+00 Fe-59 < 1.90E+Ol < 1.40E+Ol < 2.30E+Ol Co-60 < 8.50E+00 < 6.00E+00 < 9.90E+00 Zn-65 < 1.60E+Ol < 1.60E+Ol < 2.00E+Ol Zr-95 < 1.20E+Ol < 9.70E+00 < 1.70E+Ol Nb-95 < 8.30E+00 < 7.00E+00 < 1.30E+Ol Ru-l03 < 6.80E+00 < 5.80E+00 < 1.1 OE+O 1 Ru-106 < 7.30E+Ol < 5.lOE+Ol < 7.80E+Ol Cs-134 < 6.90E+00 < 5.70E+00 < 8.50E+00 Cs-137 < 8.60E+00 < 5.70E+00 < 9.lOE+00 Ba-140 < 1.50E+Ol < 1.20E+Ol < 1.40E+Ol La-140 < 1.50E+Ol < 1.20E+Ol < 1.40E+Ol Ce-141 < 8.60E+00 < 8.30E+00 < 8.00E+00 Ce-144 < 3.20E+Ol < 2.90E+Ol < 3.90E+Ol I Nuclide 30-JUL 13-AUG 27-AUG 1-131 < 7.90E-Ol < 9.50E-Ol < 9.60E-Ol Sr-89 < 8.60E+00 < 6.90E+00 < 7.20E+00 Sr-90 < 1.70E+00 < 1.50E+00 < 1.10E+00 Be-7 < 5.60E+Ol < 4.30E+Ol < 5.lOE+Ol K-40 1.47E+03 +/- 6.60E+Ol 1.46E+03 +/- 5.60E+Ol 1.48E+03 +/- 7.00E+Ol Mn-54 < 6.20E+00 < 5.40E+00 < 6.80E+00 Co-58 < 6.lOE+00 < 4.90E+00 < 7.00E+00 Fe-59 < 1.1 OE+O 1 < 1.30E+Ol < 1.70E+Ol Co-60 < 6.80E+00 < 6.40E+00 < 7.30E+00 Zn-65 < 1.60E+Ol < 1.40E+Ol < 1.80E+Ol Zr-95 < 1.1 OE+O 1 < 9.40E+00 < 1.1 OE+O 1 Nb-95 < 6.80E+00 < 6.20E+00 < 7.80E+00 Ru-l03 < 6.30E+00 < 6.00E+00 < 7.60E+00 Ru-106 < 6.40E+Ol < 4.80E+Ol < 6.lOE+Ol Cs-134 < 6.lOE+00 < 5.20E+00 < 6.00E+00 Cs-137 < 5.80E+00 < 5.40E+00 < 6.70E+00 Ba-140 < 1.30E+Ol < 9.90E+00 < 1.1 OE+O 1 La-140 < 1.30E+Ol < 9.90E+00 < 1.1 OE+O 1 Ce-141 < 9.00E+00 < 7.70E+00 < 9.60E+00 Ce-144 < 3.30E+Ol < 2.90E+Ol < 3.20E+Ol C-32

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 MILK ANALYSIS M-8 (Control)

(pCilliter)

I Nuclide 9-SEP 24-SEP 15-0CT 1-131 < 9.50E-Ol < 9.50E-Ol < 9.lOE-Ol Sr-89 < 6.50E+00 < 6.50E+00 < 7.70E+00 Sr-90 < 1.60E+00 < 1.60E+00 < 1.50E+00 Be-7 < 4.60E+Ol < 4.60E+Ol < 6.20E+Ol K-40 lA8E+03 +/- 6.20E+Ol lA8E+03 +/- 6.20E+Ol lAOE+03 +/- 7.70E+Ol Mn-54 < 4.70E+00 < 4.70E+00 < 7.60E+00 Co-58 < 5.70E+00 < 5.70E+00 < 7.50E+00 Fe-59 < 1AOE+Ol < 1AOE+Ol < 1.60E+Ol Co-60 < 7.20E+00 < 7.20E+00 < 9.80E+00 Zn-65 < 1.50E+Ol < 1.50E+Ol < 2.00E+Ol Zr-95 < 9.60E+00 < 9.60E+00 < 1.30E+Ol Nb-95 < 6AOE+00 < 6AOE+00 < 8.70E+00 Ru-l03 < 6.20E+00 < 6.20E+00 < 8.lOE+00 Ru-106 < 5.30E+Ol < 5.30E+Ol < 4.80E+Ol Cs-134 < 5.70E+00 < 5.70E+00 < 6.lOE+00 Cs-137 < 5.60E+00 < 5.60E+00 < 1.00E+Ol Ba-140 < 1AOE+Ol < 1AOE+Ol < 1.30E+Ol La-140 < 1AOE+Ol < 1AOE+Ol < 1.30E+Ol Ce-141 < 8.00E+00 < 8.00E+00 < 8.60E+00 Ce-144 < 2AOE+Ol < 2AOE+Ol < 3.00E+Ol I Nuclide 19-NOV 17-DEC 1-131 < 9.50E-01 < 9AOE-01 Sr-89 < 6.70E+00 < 8.60E+00 Sr-90 < 1.80E+00 < l.70E+00 Be-7 < 4.80E+01 < 4.20E+01 K-40 1.69E+03 +/- 6.50E+01 1A1E+03 +/- 4.20E+01 Mn-54 < 5.90E+00 < 4.60E+00 Co-58 < 5.90E+00 < 4.80E+00 Fe-59 < 1AOE+01 < 1.l0E+01 Co-60 < 5.60E+00 < 4.50E+00 Zn-65 < 1AOE+01 < 1.80E+01 Zr-95 < 1.l0E+01 < 8.50E+00 Nb-95 < 7.50E+00 < 3.80E+00 Ru-103 < 7.lOE+00 < 5.70E+00 Ru-106 < 5.70E+01 < 3.70E+01 Cs-134 < 6.30E+00 < 4.80E+00 Cs-137 < 6.60E+00 < 4.50E+00 Ba-140 < 1.30E+01 < 1.50E+01 La-140 < 1.30E+01 < 1.50E+01 Ce-141 < 9.90E+00 < 9.50E+00 Ce-144 < 3.30E+01 < 2.30E+01 C-33

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 VEGETABLE ANALYSIS FP-l (Indicator)

(pCilkg wet)

I Nuclide 30-ruL Cabba~e 30-rut Collards 30-rut Mustard Greens 1-131 < 3.90E+01 < 4.20E+01 < 5.20E+01 Be-7 < 3.60E+02 < 3.60E+02 < 6.70E+02 K-40 3.01E+03 +/- 3.lOE+02 3.65E+03 +/- 4.lOE+02 3A2E+03 +/- 4.lOE+02 Mn-54 < 3.60E+01 < 5.50E+01 < 5.50E+01 Co-58 < 4.lOE+01 < 5.50E+01 < 5.80E+01 Fe-59 < 7.lOE+01 < 1AOE+02 < l.30E+02 Co-60 < 5.20E+01 < 6.70E+01 < 5.50E+01 Zn-65 < 9.70E+01 < l.lOE+02 < 8.90E+01 Zr-95 < 7.lOE+01 < 9AOE+01 < 8.50E+01 Nb-95 < 4.20E+01 < 5.00E+01 < 6.50E+01 Ru-103 < 3.20E+01 < 4.lOE+01 < 5AOE+01 Ru-106 < 3.50E+02 < 4.20E+02 < 5.30E+02 Cs-134 < 3.50E+01 < 4.70E+01 < 5AOE+01 Cs-137 < 3.60E+01 < 4.lOE+01 < 5.70E+01 Ba-140 < 7.50E+01 < 1.20E+02 < 1.50E+02 La-140 < 7.50E+01 < 1.20E+02 < 1.50E+02 Ce-141 < 5.90E+01 < 5.30E+01 < 6AOE+01 Ce-144 < 1.90E+02 < l.70E+02 < 2AOE+02 FP-l (Indicator)

(pCilkg wet)

I Nuclide 30-ruL Red Cabbage 2-SEP Broccoli 2-SEP Cabbage 1-131 < 4.30E+01 < 5.00E+01 < 4.50E+01 Be-7 < 4.50E+02 < 2.lOE+02 < 2AOE+02 K-40 2.99E+03 +/- 4.20E+02 2.33E+03 +/- 2AOE+02 1.61E+03 +/- 2.70E+02 Mn-54 < 4.70E+01 < 2.60E+01 < 3.20E+01 Co-58 < 5.90E+01 < 2.90E+01 < 3.90E+01 Fe-59 < l.lOE+02 < 6.90E+01 < 9.00E+01 Co-60 < 5.60E+01 < 3.20E+01 < 5AOE+01 Zn-65 < 1.20E+02 < 5.90E+01 < 7.70E+01 Zr-95 < l.OOE+02 < 4.00E+01 < 6.70E+01 Nb-95 < 9.lOE+01 < 3.lOE+01 < 4.lOE+01 Ru-103 < 6.00E+01 < 3.20E+01 < 3.30E+01 Ru-106 < 5.30E+02 < 2.60E+02 < 3.20E+02 Cs-134 < 5.60E+01 < 3.00E+01 < 2.70E+01 Cs-137 < 5AOE+01 < 3.00E+01 < 3.80E+01 Ba-140 < l.lOE+02 < 4.50E+01 < 3.90E+01 La-140 < l.lOE+02 < 4.50E+01 < 3.90E+01 Ce-141 < 6.80E+01 < 4.lOE+01 < 4.20E+01 Ce-144 < 2.50E+02 < 1.50E+02 < 1.50E+02 C-34

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FP-l (Indicator)

(pCilkg wet)

I Nuclide 2-SEP Lettuce 1-131 < 4.50E+01 Be-7 4.20E+02 +/- l.30E+02 K-40 3.54E+03 +/- 3.80E+02 Mn-54 < 4.50E+01 Co-58 < 4.80E+01 Fe-59 < 8.00E+01 Co-60 < 5.20E+01 Zn-65 < 7.70E+01 Zr-95 < 5.90E+01 Nb-95 < 5.30E+01 Ru-103 < 4.00E+01 Ru-106 < 4.00E+02 Cs-134 < 3.60E+01 Cs-137 < 4.lOE+01 Ba-140 < 7.30E+01 La-140 < 7.30E+01 Ce-141 < 4.50E+01 Ce-144 < 1.50E+02 C-35

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 VEGETABLE ANALYSIS FP-9 (Control)

(pCilkg wet)

I Nuclide 30-mL Collards 30-mL Cabbage 30-JUL Red Cabbage 1-131 < 5AOE+01 < 4.60E+01 < 4.OOE+01 Be-7 < 3.80E+02 < 3AOE+02 < 4.20E+02 K-40 4.94E+03 +/- 3.80E+02 2.85E+03 +/- 3.50E+02 3.63E+03 +/- 4.30E+02 Mn-54 < 3.80E+01 < 4.20E+01 < 5.50E+01 Co-58 < 3.90E+01 < 3.70E+01 < 4.50E+01 Fe-59 < 8.50E+01 < l.lOE+02 < l.lOE+02 Co-60 < 5.20E+01 < 4.70E+01 < 5.90E+01 Zn-65 < l.lOE+02 < 1.20E+02 < 8.20E+01 Zr-95 < 7.90E+01 < 9.20E+01 < l.lOE+02 Nb-95 < 4.50E+01 < 5.30E+01 < 4.50E+01 Ru-103 < 4.80E+01 < 4.90E+01 < 5.50E+01 Ru-106 < 3.70E+02 < 4.80E+02 < 4.OOE+02 Cs-134 < 3.50E+01 < 4.30E+01 < 4.90E+01 Cs-137 < 3.20E+01 < 4.80E+01 < 3.00E+01 Ba-140 < 8.30E+01 < l.lOE+02 < 7.00E+01 La-140 < 8.30E+01 < l.lOE+02 < 7.00E+01 Ce-141 < 5.80E+01 < 6.30E+01 < 4.50E+01 Ce-144 < 1.90E+02 < 1.90E+02 < 1AOE+02 FP-9 (Control)

(pCilkg wet)

I Nuclide 2-SEP Broccoli 2-SEP Cabbage 1-131 < 4.80E+01 < 4AOE+01 Be-7 < 4AOE+02 < 3.90E+02 K-4O 3.37E+03 +/- 4.60E+02 4A7E+03 +/- 4.50E+02 Mn-54 < 4.50E+01 < 3.90E+01 Co-58 < 5.90E+01 < 5.lOE+01 Fe-59 < 8.70E+01 < l.lOE+02 Co-60 < 4.80E+01 < 4.60E+01 Zn-65 < 1AOE+02 < 8.00E+01 Zr-95 < l.lOE+02 < 7.90E+01 Nb-95 < 6AOE+01 < 5.90E+01 Ru-103 < 5.70E+01 < 4.30E+01 Ru-106 < 4.90E+02 < 3.20E+02 Cs-134 < 4.80E+01 < 4.20E+01 Cs-137 < 6.50E+01 < 5.00E+01 Ba-14O < l.OOE+02 < 1.80E+01 La-14O < l.OOE+02 < 1.80E+01 Ce-141 < 5.60E+01 < 6.lOE+01 Ce-144 < 1.80E+02 < 2.00E+02 C-36

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-l (Indicator)

(pCilliter)

I Nuclide 29-JAN 25-FEB 3 I-MAR GR-B 3.50E+00 +/- 1.10E+00 3.90E+00 +/- 1.10E+00 3.50E+00 +/- 1.00E+00 Sr-89 < 4.80E+00 < 4.30E+00 < 5.30E+00 Sr-90 < 1 AOE+OO < 1.20E+00 < 1.60E+00 Be-7 < 6.20E+OI < 5.lOE+OI < 5.50E+OI K-40 < 8.20E+OI < 9.90E+OI < 1.10E+02 Mn-54 < 6.80E+00 < 6.90E+00 < 6.lOE+00 Co-58 < 7.30E+00 < 7.00E+00 < 6.20E+00 Fe-59 < 1.20E+OI < 2.00E+OI < 1.60E+OI Co-60 < 5.80E+00 < 5AOE+00 < 6.20E+00 Zn-65 < 2.lOE+OI < l.70E+OI < 1.80E+OI Zr-95 < l.30E+OI < 1.20E+OI < l.30E+OI Nb-95 < 8.20E+00 < 8.lOE+00 < 7.60E+00 Ru-I03 < 7.lOE+00 < 7.60E+00 < 7.60E+00 Ru-106 < 7.50E+OI < 5AOE+OI < 6.30E+OI Cs-134 < 6.70E+00 < 8AOE+00 < 7.50E+00 Cs-137 < 6.30E+00 < 6.90E+00 < 6.90E+00 Ba-140 < 1.20E+OI < 1AOE+OI < l.30E+OI La-140 < 1.20E+OI < 1AOE+OI < l.30E+OI Ce-14I < 1.1 OE+O 1 < 1.20E+OI < 1.1 OE+O 1 Ce-144 < 3.50E+OI < 4.00E+OI < 3.70E+OI I Nuclide 29-APR 27-MAY 24-JUN GR-B 3.80E+00 +/- 1.10E+00 4.20E+00 +/- 1.10E+00 4.50E+00 +/- 1.10E+00 Sr-89 < 7.90E+00 < 6.60E+00 < 7.20E+00 Sr-90 < l.70E+00 < l.70E+00 < 1 AOE+OO Be-7 < 3.20E+OI < 4.lOE+OI < 4.30E+OI K-40 < 6.70E+OI < 8.20E+OI < 7AOE+OI Mn-54 < 4.00E+00 < 5.80E+00 < 5.lOE+00 Co-58 < 4.lOE+00 < 5.50E+00 < 5.80E+00 Fe-59 < 9.60E+00 < 1.1 OE+O 1 < l.30E+OI Co-60 < 4.lOE+00 < 4.20E+00 < 6.50E+00 Zn-65 < 9.20E+00 < 1AOE+OI < 1.20E+OI Zr-95 < 7.50E+00 < 1.1OE+OI < 9AOE+00 Nb-95 < 5AOE+00 < 5.80E+00 < 6.80E+00 Ru-I03 < 5.20E+00 < 6.70E+00 < 6.lOE+00 Ru-106 < 3.50E+OI < 5.90E+OI < 5.00E+OI Cs-134 < 4.00E+00 < 5.80E+00 < 5.90E+00 Cs-137 < 3.60E+00 < 5.60E+00 < 5.70E+00 Ba-140 < 1.1 OE+O 1 < l.30E+OI < l.30E+OI La-140 < 1.1 OE+O 1 < l.30E+OI < l.30E+OI Ce-14I < 7.60E+00 < 8.50E+00 < 8.lOE+00 Ce-144 < 2.30E+OI < 3.lOE+OI < 2.50E+OI C-37

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW-l (Indicator)

(pCilliter)

I Nuclide 29-JUL 26-AUG 30-SEP GR-B < 3.lOE+OO 7.80E+OO +/- 1.20E+OO < 3.00E+OO Sr-89 < 6.60E+OO < 5.70E+OO < 5.50E+OO Sr-90 < 1 AOE+OO < 1.80E+OO < 9.50E-Ol Be-7 < 5.lOE+Ol < 4.50E+Ol < 4.70E+Ol K-40 < l.OOE+02 < l.OOE+02 < 9.30E+Ol Mn-54 < 6.80E+OO < 5AOE+OO < 6.50E+OO Co-58 < 6.30E+OO < 5.70E+OO < 6.90E+OO Fe-59 < 1.50E+Ol < l.lOE+Ol < 1.60E+Ol Co-60 < 6.90E+OO < 5.70E+OO < 7.00E+OO Zn-65 < 1.50E+Ol < l.lOE+Ol < 2.20E+Ol Zr-95 < l.OOE+Ol < l.lOE+Ol < l.lOE+Ol Nb-95 < 7.30E+OO < 5.30E+OO < 6AOE+OO Ru-l03 < 8.00E+OO < 5.80E+OO < 6.20E+OO Ru-106 < 6.30E+Ol < 4.20E+Ol < 5.20E+Ol Cs-134 < 6.80E+OO < 4.70E+OO < 6.30E+OO Cs-137 < 5.90E+OO < 5.20E+OO < 6.00E+OO Ba-140 < l.30E+Ol < 8.60E+OO < 1 AOE+Ol La-140 < l.30E+Ol < 8.60E+OO < 1 AOE+Ol Ce-141 < l.lOE+Ol < 1.20E+Ol < 7.90E+OO Ce-144 < 3 AOE+O 1 < 2.90E+Ol < 2.70E+Ol I Nuclide 28-0CT 25-NOV 29-DEC GR-B 3.30E+OO +/- l.OOE+OO 5.00E+OO +/- l.lOE+OO < 3.00E+OO Sr-89 < 7.80E+OO < 5.80E+OO < 5.60E+OO Sr-90 < 2.00E+OO < 2.00E+OO < 1 AOE+OO Be-7 < 4.20E+Ol < 2.30E+Ol < 6.lOE+Ol K-40 < 4.70E+Ol < 4.80E+Ol < 8.70E+Ol Mn-54 < 4AOE+OO < 2.80E+OO < 6.80E+OO Co-58 < 4.50E+OO < 3.00E+OO < 6.lOE+OO Fe-59 < 9AOE+OO < 6.80E+OO < l.30E+Ol Co-60 < 5.20E+OO < 3 AOE+OO < 7.20E+OO Zn-65 < l.lOE+Ol < 6.00E+OO < 2.70E+Ol Zr-95 < 7.60E+OO < 5.20E+OO < l.lOE+Ol Nb-95 < 5.00E+OO < 4.00E+OO < 8.50E+OO Ru-l03 < 5.30E+OO < 3 AOE+OO < 7.50E+OO Ru-106 < 4.lOE+Ol < 2.20E+Ol < 6.lOE+Ol Cs-134 < 4.60E+OO < 2.60E+OO < 6.70E+OO Cs-137 < 4AOE+OO < 2.90E+OO < 7.90E+OO Ba-140 < l.lOE+Ol < l.OOE+Ol < l.30E+Ol La-140 < l.lOE+Ol < l.OOE+Ol < l.30E+Ol Ce-141 < l.OOE+Ol < 4.30E+OO < 9.90E+OO Ce-144 < 2.20E+Ol < 1.20E+Ol < 3.80E+Ol C-38

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW -2 (Control)

(pCilliter)

I Nuclide 29-JAN 25-FEB 3 I-MAR GR-B 3.20E+00 +/- 1.00E+00 < 3.lOE+00 < 3.00E+00 Sr-89 < 5.00E+00 < 4.50E+00 < 6.00E+00 Sr-90 < 1.50E+00 < l.30E+00 < 1.90E+00 Be-7 < 4.70E+OI < 6.60E+OI < 4.20E+OI K-40 < 1.00E+02 < 1.10E+02 < 8.50E+OI Mn-54 < 6AOE+00 < 8.90E+00 < 6.30E+00 Co-58 < 6.50E+00 < 8.30E+00 < 5.80E+00 Fe-59 < 1.60E+OI < 1AOE+OI < 1AOE+OI Co-60 < 7.70E+00 < 1.00E+OI < 7.lOE+00 Zn-65 < l.70E+OI < 2.30E+OI < 1.20E+OI Zr-95 < 1.1 OE+O 1 < 1.50E+OI < 8AOE+00 Nb-95 < 6.80E+00 < 1.20E+OI < 5.50E+00 Ru-I03 < 6.90E+00 < 8.70E+00 < 7.60E+00 Ru-106 < 5AOE+OI < 6.90E+OI < 4.60E+OI Cs-134 < 5.70E+00 < 8.80E+00 < 5.60E+00 Cs-137 < 6.70E+00 < 7.20E+00 < 6.00E+00 Ba-140 < 1.1 OE+O 1 < l.30E+OI < 1.50E+OI La-140 < 1.1 OE+O 1 < l.30E+OI < 1.50E+OI Ce-14I < 1AOE+OI < 9.70E+00 < 8.00E+00 Ce-144 < 2.80E+OI < 3.70E+OI < 2AOE+OI I Nuclide 29-APR 27-MAY 24-JUN GR-B < 3.00E+00 < 2.90E+00 < 3.lOE+00 Sr-89 < 8.00E+00 < 7.00E+00 < 7.60E+00 Sr-90 < l.70E+00 < 1.80E+00 < 1.50E+00 Be-7 < 3 AOE+O 1 < 5.60E+OI < 4.80E+OI K-40 < 6.20E+OI < 1.10E+02 < 7.20E+OI Mn-54 < 3.20E+00 < 7AOE+00 < 5.30E+00 Co-58 < 3.90E+00 < 8AOE+00 < 6.20E+00 Fe-59 < 8AOE+00 < 1.60E+OI < 1.00E+OI Co-60 < 4.50E+00 < 6.00E+00 < 4.90E+00 Zn-65 < 9.30E+00 < 1.80E+OI < 1.20E+OI Zr-95 < 6.80E+00 < 1AOE+OI < 1.00E+OI Nb-95 < 5.00E+00 < 8.80E+00 < 7.30E+00 Ru-I03 < 4.60E+00 < 7.70E+00 < 6AOE+00 Ru-106 < 3.70E+OI < 7.lOE+OI < 5.70E+OI Cs-134 < 3.60E+00 < 8.lOE+00 < 5.80E+00 Cs-137 < 3.80E+00 < 8.20E+00 < 5.00E+00 Ba-140 < 1.00E+OI < 9.90E+00 < l.30E+OI La-140 < 1.00E+OI < 9.90E+00 < l.30E+OI Ce-14I < 5.90E+00 < 8.50E+00 < 8.70E+00 Ce-144 < 2.20E+OI < 4.lOE+OI < 2.80E+OI C-39

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 DRINKING WATER ANALYSIS DW -2 (Control)

(pCilliter)

I Nuclide 29-JUL 26-AUG 30-SEP GR-B 4.80E+OO +/- l.lOE+OO < 3.00E+OO < 3.00E+OO Sr-89 < 6AOE+OO < 4.90E+OO < 6.00E+OO Sr-90 < l.30E+OO < 1.50E+OO < 9.50E-Ol Be-7 < 4.50E+Ol < 5.20E+Ol < 5.00E+Ol K-40 < 8.lOE+Ol < 8AOE+Ol < l.OOE+02 Mn-54 < 5.50E+OO < 6.70E+OO < 5.80E+OO Co-58 < 5.70E+OO < 6.60E+OO < 5.50E+OO Fe-59 < 1.20E+Ol < l.30E+Ol < 1.20E+Ol Co-60 < 6.20E+OO < 6.30E+OO < 7AOE+OO Zn-65 < l.lOE+Ol < 1.50E+Ol < 1.50E+Ol Zr-95 < 9.70E+OO < 1 AOE+Ol < l.OOE+Ol Nb-95 < 6AOE+OO < 6AOE+OO < 7.00E+OO Ru-l03 < 5.70E+OO < 6.90E+OO < 6.30E+OO Ru-106 < 4.60E+Ol < 5.90E+Ol < 4.90E+Ol Cs-134 < 5.00E+OO < 5.50E+OO < 5.30E+OO Cs-137 < 5.80E+OO < 6.20E+OO < 6.70E+OO Ba-140 < l.lOE+Ol < 1 AOE+Ol < 1.50E+Ol La-140 < l.lOE+Ol < 1 AOE+Ol < 1.50E+Ol Ce-141 < 6.50E+OO < 9.80E+OO < 8.lOE+OO Ce-144 < 2.20E+Ol < 3.30E+Ol < 2.70E+Ol I Nuclide 28-0CT 25-NOV 29-DEC GR-B < 3.00E+OO 4.00E+OO +/- l.lOE+OO < 3.00E+OO Sr-89 < 5.lOE+OO < 6.30E+OO < 5.70E+OO Sr-90 < l.30E+OO < l.70E+OO < 1.50E+OO Be-7 < 3.50E+Ol < 3 AOE+O 1 < 5.00E+Ol K-40 < 8.00E+Ol < 5.20E+Ol < l.lOE+02 Mn-54 < 4.00E+OO < 3.60E+OO < 7.90E+OO Co-58 < 4.50E+OO < 3.90E+OO < 7AOE+OO Fe-59 < l.OOE+Ol < 9.50E+OO < 1.50E+Ol Co-60 < 5.00E+OO < 3.90E+OO < 5AOE+OO Zn-65 < l.lOE+Ol < l.lOE+Ol < 2.20E+Ol Zr-95 < 7.60E+OO < 6.80E+OO < 1.20E+Ol Nb-95 < 4.80E+OO < 4.90E+OO < 8.60E+OO Ru-l03 < 4.90E+OO < 4.90E+OO < 9.lOE+OO Ru-106 < 3.80E+Ol < 2.90E+Ol < 6.20E+Ol Cs-134 < 4.20E+OO < 3.30E+OO < 8.00E+OO Cs-137 < 4AOE+OO < 3.50E+OO < 7.70E+OO Ba-140 < 1.20E+Ol < l.lOE+Ol < 1 AOE+Ol La-140 < 1.20E+Ol < l.lOE+Ol < 1 AOE+Ol Ce-141 < 6.20E+OO < 6.50E+OO < 1.80E+Ol Ce-144 < 1.80E+Ol < 1.80E+Ol < 4.lOE+Ol C-40

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-2 (Control)

(pCilliter)

I Nuclide 29-JAN 25-FEB 3 I-MAR Sr-89 < 6.lOE+00 < 4.50E+00 < 5.80E+00 Sr-90 < 1.70E+00 < 1.30E+00 < 1.10E+00 Be-7 < 6.20E+OI < 5.90E+OI < 4.80E+OI K-40 < 8.70E+OI < 1.10E+02 < 9.90E+OI Mn-54 < 6.80E+00 < 7.50E+00 < 7.70E+00 Co-58 < 7.80E+00 < 6.lOE+00 < 6.90E+00 Fe-59 < 1.30E+OI < 1.30E+OI < 1.70E+OI Co-60 < 8AOE+00 < 7.30E+00 < 7.60E+00 Zn-65 < 1.50E+OI < 1.90E+OI < 1.60E+OI Zr-95 < 1.20E+OI < 1.30E+OI < 1.00E+OI Nb-95 < 1.30E+OI < 9.00E+00 < 8.30E+00 Ru-I03 < 7.lOE+00 < 8.lOE+00 < 6.30E+00 Ru-106 < 6.60E+OI < 6.90E+OI < 5.80E+OI Cs-134 < 6.70E+00 < 8.00E+00 < 6.60E+00 Cs-137 < 8.70E+00 < 6AOE+00 < 8.lOE+00 Ba-140 < 1.30E+OI < 1.30E+OI < IAOE+OI La-140 < 1.30E+OI < 1.30E+OI < IAOE+OI Ce-14I < 1.10E+OI < 1.00E+OI < 8.20E+00 Ce-144 < 4.lOE+OI < 3.90E+OI < 2.80E+OI I Nuclide 29-APR 27-MAY 24-JUN Sr-89 < 7AOE+00 < 6.70E+00 < 6.80E+00 Sr-90 < 1.50E+00 < 1.70E+00 < lAOE+OO Be-7 < 3.lOE+Ol < 6.00E+Ol < 5.00E+Ol K-40 < 5.70E+Ol < 9.lOE+Ol < 8.90E+Ol Mn-54 < 3.60E+00 < 5.20E+00 < 5.00E+00 Co-58 < 3.90E+00 < 6.60E+00 < 5.90E+00 Fe-59 < 8.70E+00 < 1.50E+Ol < 1.10E+Ol Co-60 < 3.70E+00 < 7.lOE+00 < 7.80E+00 Zn-65 < 1.20E+Ol < 1.80E+Ol < 1.50E+Ol Zr-95 < 6.60E+00 < 1.30E+Ol < 1.20E+Ol Nb-95 < 6.00E+00 < 8.20E+00 < 8.60E+00 Ru-l03 < 4.80E+00 < 7.30E+00 < 7.60E+00 Ru-106 < 3.30E+Ol < 6.50E+Ol < 6.00E+Ol Cs-134 < 3.80E+00 < 6.60E+00 < 7AOE+00 Cs-137 < 3.60E+00 < 8.20E+00 < 5.90E+00 Ba-140 < 1.10E+Ol < 1.30E+Ol < lAOE+Ol La-140 < 1.10E+Ol < 1.30E+Ol < lAOE+Ol Ce-14l < 7.90E+00 < 1.10E+Ol < 1.00E+Ol Ce-144 < 1.90E+Ol < 3.50E+Ol < 3AOE+Ol CAl

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-2 (Control)

(pCilliter)

I Nuclide 29-JUL 26-AUG 30-SEP Sr-89 < 7.lOE+OO < 5.lOE+OO < 6.00E+OO Sr-90 < 1.50E+OO < 1.50E+OO < 9.30E-Ol Be-7 < 6.30E+Ol < 5.70E+Ol < 4.50E+Ol K-40 < 1.20E+02 < 9.30E+Ol < 7.20E+Ol Mn-54 < 6.90E+OO < 7.00E+OO < 5.90E+OO Co-58 < 7.60E+OO < 6.50E+OO < 6AOE+OO Fe-59 < 1.50E+Ol < 1.50E+Ol < 1.50E+Ol Co-60 < 7.lOE+OO < 7.lOE+OO < 6.70E+OO Zn-65 < l.70E+Ol < lAOE+Ol < lAOE+Ol Zr-95 < l.lOE+Ol < l.OOE+Ol < 9.30E+OO Nb-95 < 8.20E+OO < 5.lOE+OO < 6AOE+OO Ru-l03 < 5.80E+OO < 7.80E+OO < 5.80E+OO Ru-106 < 6.80E+Ol < 6.00E+Ol < 5.00E+Ol Cs-134 < 6.20E+OO < 7.00E+OO < 5.30E+OO Cs-137 < 8AOE+OO < 7.lOE+OO < 6.90E+OO Ba-140 < 1.50E+Ol < l.lOE+Ol < l.30E+Ol La-140 < 1.50E+Ol < l.lOE+Ol < l.30E+Ol Ce-141 < l.lOE+Ol < 9AOE+OO < 6.20E+OO Ce-144 < 3.20E+Ol < 3.80E+Ol < 2.30E+Ol I Nuclide 28-0CT 25-NOV 29-DEC Sr-89 < 4.90E+OO < 5.50E+OO < 5.90E+OO Sr-90 < 1.20E+OO < 1.90E+OO < 1.50E+OO Be-7 < 4.30E+Ol < 4.60E+Ol < 5.90E+Ol K-40 < 8.00E+Ol < 7.50E+Ol < 1.20E+02 Mn-54 < 4.90E+OO < 5.lOE+OO < 8AOE+OO Co-58 < 5.lOE+OO < 5.30E+OO < 7.70E+OO Fe-59 < l.OOE+Ol < 1.20E+Ol < 1.80E+Ol Co-60 < 5.00E+OO < 6.20E+OO < 9.60E+OO Zn-65 < l.lOE+Ol < 1.60E+Ol < 1.60E+Ol Zr-95 < 9.00E+OO < 8.60E+OO < lAOE+Ol Nb-95 < 6.lOE+OO < 6AOE+OO < 9AOE+OO Ru-l03 < 5.70E+OO < 6AOE+OO < 8.90E+OO Ru-106 < 4.20E+Ol < 5.50E+Ol < 7.lOE+Ol Cs-134 < 4AOE+OO < 5.50E+OO < 7AOE+OO Cs-137 < 5.lOE+OO < 6.20E+OO < 8.20E+OO Ba-140 < lAOE+Ol < 1.50E+Ol < 1.50E+Ol La-140 < lAOE+Ol < 1.50E+Ol < 1.50E+Ol Ce-141 < 7AOE+OO < 8.00E+OO < l.lOE+Ol Ce-144 < 2.60E+Ol < 2.50E+Ol < 4.lOE+Ol C-42

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-3 (Indicator)

(pCilliter)

I Nuclide 29-JAN 25-FEB 3 I-MAR Sr-89 < 5.lOE+00 < 5.60E+00 < 5.60E+00 Sr-90 < 1AOE+OO < l.70E+00 < l.70E+00 Be-7 < 6.20E+OI < 4AOE+OI < 5.90E+OI K-40 < 9.20E+OI < 9AOE+OI < 1.l0E+02 Mn-54 < 7AOE+00 < 7AOE+00 < 7.60E+00 Co-58 < 7AOE+00 < 6.00E+00 < 7.80E+00 Fe-59 < 1.50E+OI < 1.60E+OI < 1.80E+OI Co-60 < 7.00E+00 < 6.90E+00 < 7.80E+00 Zn-65 < 3.00E+OI < 1.60E+OI < 1.90E+OI Zr-95 < 1.20E+OI < 1.l0E+OI < 1AOE+OI Nb-95 < 1.l0E+OI < 7.00E+00 < 9.70E+00 Ru-I03 < 7.80E+00 < 5.lOE+00 < 7.70E+00 Ru-106 < 7.50E+OI < 6.50E+OI < 7.00E+OI Cs-134 < 6.90E+00 < 6.00E+00 < 6.60E+00 Cs-137 < 7.50E+00 < 6AOE+00 < 7.00E+00 Ba-140 < 1.20E+OI < l.30E+OI < 1.50E+OI La-140 < 1.20E+OI < l.30E+OI < 1.50E+OI Ce-14I < 1.20E+OI < 8.70E+00 < 9.60E+00 Ce-144 < 4.00E+OI < 2.90E+OI < 3.60E+OI I Nuclide 30-APR 27-MAY 24-JUN Sr-89 < 7.50E+00 < 6.50E+00 < 7.60E+00 Sr-90 < 1.50E+00 < 1.60E+00 < 1.50E+00 Be-7 < 6.50E+OI < 4.50E+OI < 4.70E+OI K-40 < 1.20E+02 < 9.20E+OI < 7.lOE+OI Mn-54 < 8.30E+00 < 5.50E+00 < 6.00E+00 Co-58 < 8.30E+00 < 6AOE+00 < 5.30E+00 Fe-59 < 2.lOE+OI < 1AOE+OI < 1.20E+OI Co-60 < 9.90E+00 < 6.20E+00 < 5.30E+00 Zn-65 < 1.80E+OI < 1AOE+OI < l.30E+OI Zr-95 < l.30E+OI < 1.l0E+OI < 1.l0E+OI Nb-95 < 1.l0E+OI < 7.70E+00 < 6.70E+00 Ru-I03 < 8.30E+00 < 7.50E+00 < 6.70E+00 Ru-106 < 8.20E+OI < 5.90E+OI < 5.00E+OI Cs-134 < 8.60E+00 < 5.60E+00 < 5.60E+00 Cs-137 < 7.80E+00 < 5AOE+00 < 5.20E+00 Ba-140 < l.30E+OI < 1.20E+OI < 1.20E+OI La-140 < l.30E+OI < 1.20E+OI < 1.20E+OI Ce-14I < l.70E+OI < 8.lOE+00 < 9.00E+00 Ce-144 < 4.00E+OI < 3.30E+OI < 3.lOE+OI C-43

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 SURFACE WATER ANALYSIS SW-3 (Indicator)

(pCilliter)

I Nuclide 29-JUL 26-AUG 30-SEP Sr-89 < 7.lOE+OO < 5.30E+OO < 5.70E+OO Sr-90 < 1.50E+OO < 1.60E+OO < 9.lOE-Ol Be-7 < 4.lOE+Ol < 4.30E+Ol < 6.lOE+Ol K-40 < l.lOE+02 < 8.60E+Ol < 8.20E+Ol Mn-54 < 7.70E+OO < 5.80E+OO < 7.60E+OO Co-58 < 7.lOE+OO < 5.80E+OO < 7.50E+OO Fe-59 < 1.60E+Ol < 1.20E+Ol < l.30E+Ol Co-60 < 8.30E+OO < 6AOE+OO < 7.70E+OO Zn-65 < l.70E+Ol < 1 AOE+Ol < 2.80E+Ol Zr-95 < 9.30E+OO < 8.50E+OO < l.lOE+Ol Nb-95 < 7.60E+OO < 5.20E+OO < l.lOE+Ol Ru-l03 < 6.90E+OO < 5.90E+OO < 7.50E+OO Ru-106 < 7AOE+Ol < 5.30E+Ol < 6AOE+Ol Cs-134 < 6AOE+OO < 5.30E+OO < 6.60E+OO Cs-137 < 6.60E+OO < 6.30E+OO < 7.70E+OO Ba-140 < 1.50E+Ol < l.lOE+Ol < 1.50E+Ol La-140 < 1.50E+Ol < l.lOE+Ol < 1.50E+Ol Ce-141 < 8.60E+OO < 7.lOE+OO < l.OOE+Ol Ce-144 < 3.20E+Ol < 2.50E+Ol < 3.90E+Ol I Nuclide 28-0CT 25-NOV 29-DEC Sr-89 < 4.90E+OO < 5.90E+OO < 6.lOE+OO Sr-90 < 1.20E+OO < 2.00E+OO < 1.60E+OO Be-7 < 5.90E+Ol < 4.lOE+Ol < 5.00E+Ol K-40 < 8.20E+Ol < 7.90E+Ol < 8.70E+Ol Mn-54 < 5.60E+OO < 4.80E+OO < 7.00E+OO Co-58 < 5.20E+OO < 4.70E+OO < 7.30E+OO Fe-59 < l.lOE+Ol < l.OOE+Ol < l.70E+Ol Co-60 < 6.20E+OO < 5.50E+OO < 7.lOE+OO Zn-65 < 1.20E+Ol < l.70E+Ol < 1.50E+Ol Zr-95 < 8.70E+OO < 8.00E+OO < 1.20E+Ol Nb-95 < 5AOE+OO < 5.80E+OO < 6.60E+OO Ru-l03 < 6.90E+OO < 5.lOE+OO < 6AOE+OO Ru-106 < 4.30E+Ol < 4.70E+Ol < 6AOE+Ol Cs-134 < 6.20E+OO < 4.50E+OO < 6AOE+OO Cs-137 < 5.70E+OO < 4.80E+OO < 6.70E+OO Ba-140 < 1.20E+Ol < 1 AOE+Ol < l.30E+Ol La-140 < 1.20E+Ol < 1 AOE+Ol < l.30E+Ol Ce-141 < 7.60E+OO < 7.60E+OO < 8.00E+OO Ce-144 < 2.70E+Ol < 1.80E+Ol < 2.90E+Ol C-44

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 DRINKING AND SURFACE WATER QUARTERL Y COMPOSITE SAMPLES Tritium (pCilliter)

I Station First Quarter Second Quarter DW-l < 4.30E+02 < 4.50E+02 DW-2 < 4.30E+02 < 4.50E+02 SW-2 < 4.30E+02 < 4.40E+02 SW-3 < 4.30E+02 < 4.50E+02 I Station Third Quarter Fourth Quarter DW-l < 4.lOE+02 < 4.00E+02 DW-2 < 4.lOE+02 < 4.00E+02 SW-2 < 4.lOE+02 < 4.00E+02 SW-3 < 4.lOE+02 < 4.00E+02 C-45

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-l (Indicator)

(pCilliter)

I Nuclide First Quarter Second Quarter Be-7 < 5.00E+Ol < 6AOE+Ol K-40 < l.OOE+02 < 8.60E+Ol Mn-54 < 7.30E+OO < 5.50E+OO Co-58 < 6.80E+OO < 6.80E+OO Fe-59 < l.30E+Ol < l.70E+Ol Co-60 < 9.60E+OO < 6.60E+OO Zn-65 < 1.80E+Ol < l.70E+Ol Zr-95 < l.OOE+Ol < l.30E+Ol Nb-95 < 6.60E+OO < 8.70E+OO Ru-l03 < 6.60E+OO < 7.20E+OO Ru-106 < 6.60E+Ol < 7.50E+Ol Cs-134 < 5.70E+OO < 7.20E+OO Cs-137 < 7.lOE+OO < 6.50E+OO Ba-140 < 1.50E+Ol < 1 AOE+Ol La-140 < 1.50E+Ol < 1 AOE+Ol Ce-141 < 7.90E+OO < l.lOE+Ol Ce-144 < 3.00E+Ol < 3.70E+Ol H-3 < 4.30E+02 < 4.20E+02 I Nuclide Third Quarter Fourth Quarter Be-7 < 3.50E+Ol < 5AOE+Ol K-40 < 6.80E+Ol < 9.00E+Ol Mn-54 < 4.00E+OO < 6AOE+OO Co-58 < 4.60E+OO < 7AOE+OO Fe-59 < 9.20E+OO < l.30E+Ol Co-60 < 4AOE+OO < 8.90E+OO Zn-65 < 9.30E+OO < 2.60E+Ol Zr-95 < 7.lOE+OO < l.lOE+Ol Nb-95 < 5.00E+OO < 6.80E+OO Ru-l03 < 4.30E+OO < 6.50E+OO Ru-106 < 3.70E+Ol < 5.80E+Ol Cs-134 < 3.90E+OO < 6.00E+OO Cs-137 < 4.00E+OO < 6.60E+OO Ba-140 < l.30E+Ol < l.30E+Ol La-140 < l.30E+Ol < l.30E+Ol Ce-141 < 9.00E+OO < 8.50E+OO Ce-144 < 1.80E+Ol < 2.90E+Ol H-3 < 2AOE+02 < 3.90E+02 C-46

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-2 (Indicator)

(pCilliter)

I Nuclide First Quarter Second Quarter Be-7 < 5.00E+Ol < 5.80E+Ol K-40 < 8.60E+Ol < l.lOE+02 Mn-54 < 5.90E+OO < 7.60E+OO Co-58 < 6.lOE+OO < 6.80E+OO Fe-59 < 1 AOE+Ol < 1.50E+Ol Co-60 < 8.60E+OO < 8.70E+OO Zn-65 < 2.60E+Ol < 1.80E+Ol Zr-95 < 9.60E+OO < l.30E+Ol Nb-95 < 9.90E+OO < 9.30E+OO Ru-l03 < 6.50E+OO < 8.70E+OO Ru-106 < 5.90E+Ol < 6.70E+Ol Cs-134 < 6.00E+OO < 7.60E+OO Cs-137 < 6.60E+OO < 8.00E+OO Ba-140 < 1 AOE+Ol < 1 AOE+Ol La-140 < 1 AOE+Ol < 1 AOE+Ol Ce-141 < 7.90E+OO < l.lOE+Ol Ce-144 < 2.80E+Ol < 3.80E+Ol H-3 < 4.30E+02 < 4.30E+02 I Nuclide Third Quarter Fourth Quarter Be-7 < 3.lOE+Ol < 6.00E+Ol K-40 < 7.00E+Ol 9.60E+Ol +/- 2AOE+Ol Mn-54 < 3.50E+OO < 7.20E+OO Co-58 < 4AOE+OO < 7.20E+OO Fe-59 < 9.lOE+OO < 1.50E+Ol Co-60 < 4.30E+OO < 8.60E+OO Zn-65 < 1.50E+Ol < 1.80E+Ol Zr-95 < 7.20E+OO < l.30E+Ol Nb-95 < 4.50E+OO < 8.60E+OO Ru-l03 < 4.20E+OO < 8.00E+OO Ru-106 < 3.70E+Ol < 6.lOE+Ol Cs-134 < 3.50E+OO < 7.20E+OO Cs-137 < 3.90E+OO < 7.20E+OO Ba-140 < l.lOE+Ol < l.30E+Ol La-140 < l.lOE+Ol < l.30E+Ol Ce-141 < 4.60E+OO < l.lOE+Ol Ce-144 < 1.80E+Ol < 4.lOE+Ol H-3 < 2.30E+02 < 3.90E+02 C-47

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW-3 (Indicator)

(pCilliter)

I Nuclide First Quarter Second Quarter Be-7 < 5AOE+Ol < 4.80E+Ol K-40 < 9.70E+Ol < 8.70E+Ol Mn-54 < 5AOE+OO < 6AOE+OO Co-58 < 5.60E+OO < 7.lOE+OO Fe-59 < l.lOE+Ol < 1 AOE+Ol Co-60 < 7.90E+OO < 6.20E+OO Zn-65 < 2.00E+Ol < 2.30E+Ol Zr-95 < 1.20E+Ol < l.30E+Ol Nb-95 < 7.60E+OO < 8.50E+OO Ru-l03 < 6.90E+OO < 7.60E+OO Ru-106 < 6.50E+Ol < 6AOE+Ol Cs-134 < 8AOE+OO < 6.00E+OO Cs-137 < 7AOE+OO < 5.20E+OO Ba-140 < 1 AOE+Ol < 1.50E+Ol La-140 < 1 AOE+Ol < 1.50E+Ol Ce-141 < 8.lOE+OO < 8.70E+OO Ce-144 < 2.90E+Ol < 3.60E+Ol H-3 < 4.20E+02 < 4.30E+02 I Nuclide Third Quarter Fourth Quarter Be-7 < 3.00E+Ol < 5.20E+Ol K-40 < 6.lOE+Ol < 9.50E+Ol Mn-54 < 3 AOE+OO < 7.70E+OO Co-58 < 4.00E+OO < 6.80E+OO Fe-59 < 9.80E+OO < 1 AOE+Ol Co-60 < 4.50E+OO < 8AOE+OO Zn-65 < 8.90E+OO < 2.lOE+Ol Zr-95 < 5.70E+OO < l.lOE+Ol Nb-95 < 4.50E+OO < 6.50E+OO Ru-l03 < 3.90E+OO < 8.00E+OO Ru-106 < 3.00E+Ol < 6.00E+Ol Cs-134 < 3.30E+OO < 6AOE+OO Cs-137 < 3.60E+OO < 8.30E+OO Ba-140 < l.30E+Ol < 1 AOE+Ol La-140 < l.30E+Ol < 1 AOE+Ol Ce-141 < 5.20E+OO < 8.lOE+OO Ce-144 < 1.50E+Ol < 3.lOE+Ol H-3 < 2AOE+02 < 3.90E+02 C-48

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 GROUNDWATER ANALYSIS GW -4 (Control)

(pCilliter)

I Nuclide First Quarter Second Quarter Be-7 < 5.70E+Ol < 4.50E+Ol K-40 < l.lOE+02 < 8.20E+Ol Mn-54 < 7AOE+OO < 4AOE+OO Co-58 < 6.20E+OO < 5.00E+OO Fe-59 < l.70E+Ol < l.lOE+Ol Co-60 < 8.lOE+OO < 5.90E+OO Zn-65 < 1.60E+Ol < l.lOE+Ol Zr-95 < l.30E+Ol < 8.lOE+OO Nb-95 < 8.70E+OO < 6.30E+OO Ru-l03 < 8.60E+OO < 5.30E+OO Ru-106 < 7.00E+Ol < 4AOE+Ol Cs-134 < 7.90E+OO < 4.60E+OO Cs-137 < 7AOE+OO < 5AOE+OO Ba-140 < 1.20E+Ol < 1 AOE+Ol La-140 < 1.20E+Ol < 1 AOE+Ol Ce-141 < l.OOE+Ol < 6.30E+OO Ce-144 < 3.50E+Ol < 2.20E+Ol H-3 < 4.30E+02 < 4.30E+02 I Nuclide Third Quarter Fourth Quarter Be-7 < 3.lOE+Ol < 6.00E+Ol K-40 < 5.90E+Ol < 1.20E+02 Mn-54 < 3.50E+OO < 7.00E+OO Co-58 < 3.30E+OO < 7.20E+OO Fe-59 < 9.00E+OO < 1.60E+Ol Co-60 < 4.20E+OO < 8.60E+OO Zn-65 < l.30E+Ol < 2.00E+Ol Zr-95 < 7.00E+OO < 1.20E+Ol Nb-95 < 4.50E+OO < 8.90E+OO Ru-l03 < 4.00E+OO < 6.90E+OO Ru-106 < 3.lOE+Ol < 6.70E+Ol Cs-134 < 3.50E+OO < 7AOE+OO Cs-137 < 3.70E+OO < 7.50E+OO Ba-140 < l.30E+Ol < l.30E+Ol La-140 < l.30E+Ol < l.30E+Ol Ce-141 < 5.20E+OO < 9.lOE+OO Ce-144 < 1.60E+Ol < 2.90E+Ol H-3 < 3.80E+02 < 4.00E+02 C-49

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 SEDIMENT ANALYSIS S-1 (Indicator)

(pCilkg dry)

I Nuclide 28-MAY 9-NOV Sr-89 < l.70E+02 < 2.00E+02 Sr-90 < 1.50E+02 < 1.80E+02 Be-7 < l.30E+02 < 1.80E+02 K-40 1AOE+04 +/- 2.70E+02 8.98E+03 +/- 2.90E+02 Mn-54 < l.70E+Ol < 2.00E+Ol Co-58 < 1.60E+Ol < 2.00E+Ol Fe-59 < 4.20E+Ol < 5.00E+Ol Co-60 < 1.80E+Ol < 2.lOE+Ol Zn-65 < 7.70E+Ol < 9.30E+Ol Nb-95 < 3.lOE+Ol < 4.lOE+Ol Zr-95 < 2.00E+Ol < 2.20E+Ol Ru-l03 < l.70E+Ol < 2.00E+Ol Ru-106 < l.30E+02 < 1AOE+02 Cs-134 < 1.60E+Ol < 2.00E+Ol Cs-137 < l.70E+Ol < 1.90E+Ol Ba-140 < 8.20E+Ol < 1AOE+02 La-140 < 4.70E+Ol < 7.20E+Ol Ce-141 < 2.90E+Ol < 3 AOE+O 1 Ce-144 < 1.l0E+02 < 1.l0E+02 S-2 (Indicator)

(pCilkg dry)

I Nuclide 28-MAY 9-NOV Sr-89 < 2.00E+02 < 2.70E+02 Sr-90 < 1.90E+02 < 2AOE+02 Be-7 < 5.70E+02 < 2.90E+02 K-40 2.22E+04 +/- 8.20E+02 1.09E+04 +/- 5.30E+02 Mn-54 < 7.80E+Ol < 4.00E+Ol Co-58 < 7.30E+Ol < 4.60E+Ol Fe-59 < 2.00E+02 < 1.20E+02 Co-60 < 7.50E+Ol < 4.00E+Ol Zn-65 < 3.lOE+02 < 2.30E+02 Zr-95 < l.30E+02 < 6.60E+Ol Nb-95 < 9AOE+Ol < 5.lOE+Ol Ru-l03 < 7.50E+Ol < 4AOE+Ol Ru-106 < 5.80E+02 < 3 AOE+02 Cs-134 < 7.lOE+Ol < 3.60E+Ol Cs-137 < 7.20E+Ol < 5.00E+Ol Ba-140 < 4.00E+02 < 2AOE+02 La-140 < 2AOE+02 < 1.20E+02 Ce-141 < l.30E+02 < 6.60E+Ol Ce-144 < 4.20E+02 < 2.20E+02 C-50

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 SEDIMENT ANALYSIS S-3 (Indicator)

(pCilkg dry)

I Nuclide 19-MAY 19-NOV Sr-89 < 2.70E+02 < 1.20E+02 Sr-90 4A6E+02 +/- 7.60E+Ol < 1.00E+02 Be-7 < 2.00E+02 < 3.20E+02 K-40 3.84E+03 +/- 1.30E+02 1.21E+04 +/- 5AOE+02 Mn-54 < 1.80E+Ol < 3 AOE+O 1 Co-58 < 1.90E+Ol < 3.80E+Ol Fe-59 < 4AOE+Ol < 9.90E+Ol Co-60 < 1.70E+Ol < 3.90E+Ol Zn-65 < 6.80E+Ol < 1.20E+02 Zr-95 < 3.50E+Ol < 7.00E+Ol Nb-95 < 2.90E+Ol < 4.30E+Ol Ru-l03 < 2.30E+Ol < 3.80E+Ol Ru-106 < 1.50E+02 < 3.20E+02 Cs-134 < 2AOE+Ol < 3.90E+Ol Cs-137 < 1.60E+Ol < 3.50E+Ol Ba-140 < 1.80E+02 < 2.00E+02 La-140 < 8.60E+Ol < 1.10E+02 Ce-141 < 3.50E+Ol < 5.20E+Ol Ce-144 < 8.80E+Ol < 1.60E+02 S-4 (Indicator)

(pCilkg dry)

I Nuclide 2-JUN 12-NOV Sr-89 < 2.00E+02 < 2.30E+02 Sr-90 < 2.lOE+02 < 2.20E+02 Be-7 < lAOE+02 < 2AOE+02 K-40 9.02E+03 +/- 3.lOE+02 1.12E+04 +/- 3.90E+02 Mn-54 < 2.00E+Ol < 2AOE+Ol Co-58 < 2.20E+Ol < 2.60E+Ol Fe-59 < 5.70E+Ol < 6AOE+Ol Co-60 < 2.lOE+Ol < 2.80E+Ol Zn-65 < 6.80E+Ol < 1.20E+02 Zr-95 < 3.lOE+Ol < 4.70E+Ol Nb-95 < 3.lOE+Ol < 3 AOE+O 1 Ru-l03 < 1.60E+Ol < 2.50E+Ol Ru-106 < 1.60E+02 < 1.90E+02 Cs-134 < 1.60E+Ol < 3.00E+Ol Cs-137 < 2AOE+Ol < 2AOE+Ol Ba-140 < 8.60E+Ol < 1.50E+02 La-140 < 4.50E+Ol < 8.lOE+Ol Ce-141 < 2AOE+Ol < 4.50E+Ol Ce-144 < 9.50E+Ol < 1.60E+02 C-51

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 SEDIMENT ANALYSIS S-5 (Control)

(pCilkg dry)

I Nuclide 19-MAY 9-NOV Sr-89 < 2.80E+02 < IAOE+02 Sr-90 < 2.70E+02 < l.30E+02 Be-7 < 4.60E+02 6.90E+02 +/- 2.00E+02 K-4O 1.l0E+04 +/- 6.lOE+02 1. 54E+04 +/- 8.60E+02 Mn-54 < 5.30E+OI < 6.30E+OI Co-58 < 5AOE+OI < 4AOE+OI Fe-59 < 1.50E+02 < 2.30E+02 Co-60 < 5.60E+OI < 8AOE+OI Zn-65 < 2.30E+02 < 2.20E+02 Zr-95 < 9AOE+OI < 1.l0E+02 NB-95 < 6.60E+OI < 8.80E+OI Ru-I03 < 7.00E+OI < 5.50E+OI Ru-106 < 4.lOE+02 < 4.60E+02 Cs-134 < 7.00E+OI < 1 AOE+02 Cs-137 < 4.60E+OI < 7AOE+OI Ba-140 < 5.60E+02 < 4.00E+02 La-140 < 3.30E+02 < 2AOE+02 Ce-141 < 1.20E+02 < 1.00E+02 Ce-144 < 3.60E+02 < 3 AOE+02 C-52

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-l (Control)

(pCilkg wet)

I Nuclide 19-MAY Crappie 19-MAY White Perch 19-MAY Yellow Perch Sr-89 < 2.70E+02 < 2.00E+02 < 1.80E+02 Sr-90 < 2.40E+02 < 1.80E+02 < 1.60E+02 Be-7 < 8.50E+02 < 4.50E+02 < 3.70E+02 K-40 3.16E+03 +/- 5.70E+02 2. 84E+03 +/- 3.lOE+02 2.85E+03 +/- 4.00E+02 Mn-54 < 9.50E+Ol < 3.50E+Ol < 5.80E+Ol Co-58 < 1.l0E+02 < 3.60E+Ol < 4.60E+Ol Fe-59 < 2.40E+02 < 1.l0E+02 < 1.50E+02 Co-60 < 1.00E+02 < 4.40E+Ol < 4.30E+Ol Zn-65 < 2.30E+02 < 1.00E+02 < l.30E+02 Zr-95 < 1.60E+02 < 8.30E+Ol < 8.70E+Ol Nb-95 < l.30E+02 < 4.30E+Ol < 6.00E+Ol Ru-l03 < 9.40E+02 < 3.60E+02 < 4.30E+02 Ru-106 < 8.40E+Ol < 4.00E+Ol < 3.80E+Ol Cs-134 < 9.60E+Ol < 3.20E+Ol < 5.20E+Ol Cs-137 < 4.lOE+02 < 2.20E+02 < 2.50E+02 Ba-140 < 4.lOE+02 < 2.20E+02 < 2.50E+02 La-140 < l.70E+02 < 6.90E+Ol < 7.80E+Ol Ce-141 < 4.00E+02 < 2.lOE+02 < 1.90E+02 Ce-144 < 2.70E+02 < 2.00E+02 < 1.80E+02 I Nuclide 10-NOV Shad 10-NOV RockBass lO-NOV Steel Head Sr-89 < 1.l0E+02 < 2.lOE+02 < 1.00E+02 Sr-90 < 9.30E+Ol < l.70E+02 < 8.50E+Ol Be-7 < 5.80E+02 < 7.70E+02 < 7.lOE+02 K-40 2.90E+03 +/- 5.70E+02 2.99E+03 +/- 5.70E+02 2.69E+03 +/- 5.90E+02 Mn-54 < 4.90E+Ol < 9.80E+Ol < 6.70E+Ol Co-58 < 7.90E+Ol < 1.l0E+02 < 9.70E+Ol Fe-59 < 1.20E+02 < 2.50E+02 < l.30E+02 Co-60 < 9.30E+Ol < 1.l0E+02 < 9.60E+Ol Zn-65 < 2.30E+02 < 2.60E+02 < 2.40E+02 Zr-95 < l.70E+02 < l.70E+02 < l.70E+02 Nb-95 < 6.90E+Ol < 1.l0E+02 < 6.60E+Ol Ru-l03 < 7.80E+02 < 7.20E+02 < 7.00E+02 Ru-106 < 8.lOE+Ol < 1.00E+02 < 7.50E+Ol Cs-134 < 8.30E+Ol < 1.00E+02 < 9.40E+Ol Cs-137 < 1.80E+02 < 4.00E+02 < 2.50E+02 Ba-140 < 1.80E+02 < 4.00E+02 < 2.50E+02 La-140 < 1.l0E+02 < 1.20E+02 < 9.90E+Ol Ce-141 < 3.20E+02 < 3.40E+02 < 3.lOE+02 Ce-144 < 1.l0E+02 < 2.lOE+02 < 1.00E+02 C-53

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-2 (Indicator)

(pCilkg wet)

I Nuclide 14-May Sucker 14-MAY S1lll Bass 14-MAY Walleye Sr-89 < 1.50E+02 < 1.60E+02 < l.70E+02 Sr-90 < l.30E+02 < l.30E+02 < 1AOE+02 Be-7 < 4.60E+02 < 3 AOE+02 < 3 AOE+02 K-40 2.57E+03 +/- 2.90E+02 2A9E+03 +/- 3.20E+02 2.83E+03 +/- 4.lOE+02 Mn-54 < 3.90E+OI < 4.90E+OI < 5.90E+OI Co-58 < 5.00E+OI < 5.20E+OI < 6.30E+OI Fe-59 < l.30E+02 < 1.50E+02 < 1.90E+02 Co-60 < 4.20E+OI < 4.20E+OI < 5.60E+OI Zn-65 < 1.20E+02 < 1.20E+02 < 9.50E+OI Zr-95 < 8.lOE+OI < 8.70E+OI < l.lOE+02 Nb-95 < 5.90E+OI < 6.90E+OI < 3.80E+OI Ru-I03 < 3 AOE+02 < 4.50E+02 < 5.70E+02 Ru-106 < 4.50E+OI < 3.00E+OI < 4AOE+OI Cs-134 < 3.lOE+OI < 3.80E+OI < 5.00E+OI Cs-137 < 3.20E+02 < 3.20E+02 < 2.60E+02 Ba-140 < 3.20E+02 < 3.20E+02 < 2.60E+02 La-140 < 9.50E+OI < 9.lOE+OI < l.OOE+02 Ce-141 < 1.80E+02 < 2.00E+02 < 1.90E+02 Ce-144 < 1.50E+02 < 1.60E+02 < l.70E+02 I Nuclide 14-MAY White Perch 22-0CT Muskellunge 22-0CT Walle~e Sr-89 < 2.70E+02 < 2.20E+02 < 1AOE+02 Sr-90 < 2.20E+02 < 1AOE+02 < 9.lOE+OI Be-7 < 5.lOE+02 < 9.00E+02 < 6.00E+02 K-40 2.33E+03 +/- 4.00E+02 3.64E+03 +/- 6.70E+02 3 AOE+03 +/- 4.70E+02 Mn-54 < 3.80E+OI < 8.00E+OI < 7.lOE+OI Co-58 < 5.60E+OI < l.lOE+02 < 8.00E+OI Fe-59 < 1.90E+02 < 2.lOE+02 < 2.00E+02 Co-60 < 5.50E+OI < 7.lOE+OI < 6.00E+OI Zn-65 < 1AOE+02 < 2.50E+02 < 2.30E+02 Zr-95 < 1.50E+02 < 1.90E+02 < 1.80E+02 Nb-95 < 8.00E+OI < 1.20E+02 < 9.30E+OI Ru-I03 < 4.60E+02 < 5.60E+02 < 4.60E+02 Ru-106 < 5AOE+OI < 6.90E+OI < 9.80E+OI Cs-134 < 5.30E+OI < 7.30E+OI < 6.50E+OI Cs-137 < 4.20E+02 < 6AOE+02 < 5AOE+02 Ba-140 < 4.20E+02 < 6AOE+02 < 5AOE+02 La-140 < 9.lOE+OI < 1.60E+02 < 1AOE+02 Ce-141 < 2.00E+02 < 2.60E+02 < 3 AOE+02 Ce-144 < 2.70E+02 < 2.20E+02 < 1AOE+02 C-54

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F-2 (Indicator)

(pCilkg wet)

I Nuclide 22-0CT White Perch Sr-89 < 1.90E+02 Sr-90 < 1.20E+02 Be-7 < 9.30E+02 K-40 1. 92E+03 +/- 5.60E+02 Mn-54 < 1.l0E+02 Co-58 < 1.l0E+02 Fe-59 < 2.60E+02 Co-60 < 7.40E+Ol Zn-65 < 2.40E+02 Zr-95 < 2.30E+02 Nb-95 < 1.20E+02 Ru-l03 < 1.00E+03 Ru-106 < 9.20E+Ol Cs-134 < 9.30E+Ol Cs-137 < 6.60E+02 Ba-140 < 6.60E+02 La-140 < l.70E+02 Ce-141 < 1.90E+02 Ce-144 < 1.20E+02 C-55

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F -3 (Control)

(pCilkg wet)

I Nuclide I5-MAY Catfish I5-MAY Drum I5-MAY Sucker Sr-89 < 1.90E+02 < 2.30E+02 < 2.60E+02 Sr-90 < 1AOE+02 < 1.50E+02 < l.70E+02 Be-7 < 5.00E+02 < 8.70E+02 < 6.lOE+02 K-40 2.19E+03 +/- 4.60E+02 2.lOE+03 +/- 5.20E+02 2.64E+03 +/- 4AOE+02 Mn-54 < 7.20E+Ol < 8.30E+Ol < 7.80E+Ol Co-58 < 6.90E+Ol < 1.l0E+02 < 7.30E+Ol Fe-59 < 2.30E+02 < 2.50E+02 < 2.50E+02 Co-60 < 8.80E+Ol < 1.20E+02 < 8.20E+Ol Zn-65 < l.30E+02 < 2AOE+02 < 1.90E+02 Zr-95 < 1.l0E+02 < 1.90E+02 < 1.50E+02 Nb-95 < 7.80E+Ol < 1.20E+02 < 7.70E+Ol Ru-l03 < 6.20E+02 < 6.70E+02 < 5.90E+02 Ru-106 < 5.50E+Ol < 8.60E+Ol < 6.60E+Ol Cs-134 < 7.50E+Ol < 8.lOE+Ol < 7AOE+Ol Cs-137 < 5.00E+02 < 3.70E+02 < 3.80E+02 Ba-140 < 5.00E+02 < 3.70E+02 < 3.80E+02 La-140 < 1.00E+02 < l.30E+02 < 1.20E+02 Ce-141 < 2.50E+02 < 3.00E+02 < 2AOE+02 Ce-144 < 1.90E+02 < 2.30E+02 < 2.60E+02 I Nuclide 15-MAY Sun Bass 15-MAY Walleye 15-MAY White Perch Sr-89 < l.70E+02 < 2.50E+02 < 2AOE+02 Sr-90 < 1.20E+02 < 1.60E+02 < 1.60E+02 Be-7 < 5.20E+02 < 4.30E+02 < 6.30E+02 K-40 2. 96E+03 +/- 3AOE+02 2. 72E+03 +/- 5.00E+02 2. 72E+03 +/- 3.70E+02 Mn-54 < 6.lOE+Ol < 6.30E+Ol < 4.20E+Ol Co-58 < 4.80E+Ol < 5.20E+Ol < 7.50E+Ol Fe-59 < 1AOE+02 < 2.20E+02 < 1.60E+02 Co-60 < 5AOE+Ol < 5AOE+Ol < 5.50E+Ol Zn-65 < 1.00E+02 < 1.90E+02 < 1.l0E+02 Zr-95 < 1.l0E+02 < 1.l0E+02 < 1.l0E+02 Nb-95 < 6.80E+Ol < 1.00E+02 < 6.90E+Ol Ru-l03 < 4.20E+02 < 6.20E+02 < 3.90E+02 Ru-106 < 5.00E+Ol < 6.60E+Ol < 5.00E+Ol Cs-134 < 4.00E+Ol < 7.90E+Ol < 5.30E+Ol Cs-137 < 2.60E+02 < 4AOE+02 < 3.00E+02 Ba-140 < 2.60E+02 < 4AOE+02 < 3.00E+02 La-140 < 1.00E+02 < 1.00E+02 < 1.l0E+02 Ce-141 < 2AOE+02 < 2.60E+02 < 2.60E+02 Ce-144 < l.70E+02 < 2.50E+02 < 2AOE+02 C-56

Fermi 2 - 2009 Annual Radiological Environmental Operating Report FERMI 2 FISH ANALYSIS F -3 (Control)

(pCilkg wet)

I Nuclide 4-NOV Sucker 4- NOV Walleye 4-NOV Yellow Perch Sr-89 < 1.50E+02 < lAOE+02 < 1.80E+02 Sr-90 < 1.l0E+02 < 1.00E+02 < l.30E+02 Be-7 < 5.50E+02 < 7.00E+02 < 5.50E+02 K-40 2.15E+03 +/- 4.30E+02 2.22E+03 +/- 5.lOE+02 2.83E+03 +/- 4.30E+02 Mn-54 < 6.lOE+Ol < 6AOE+Ol < 6.70E+Ol Co-58 < 8AOE+Ol < 1.00E+02 < 7.90E+Ol Fe-59 < 1.60E+02 < 1.90E+02 < 1.80E+02 Co-60 < 7.30E+Ol < 7.00E+Ol < 7.70E+Ol Zn-65 < 1.80E+02 < 2.00E+02 < 2.00E+02 Zr-95 < 1.50E+02 < lAOE+02 < l.30E+02 Nb-95 < 7.70E+Ol < 6.00E+Ol < 8.lOE+Ol Ru-l03 < 3.80E+02 < 6.lOE+02 < 6AOE+02 Ru-106 < 4AOE+Ol < 8AOE+Ol < 5AOE+Ol Cs-134 < 5.20E+Ol < 7.30E+Ol < 7AOE+Ol Cs-137 < 2.20E+02 < 2.20E+02 < 2AOE+02 Ba-140 < 2.20E+02 < 2.20E+02 < 2AOE+02 La-140 < 8.60E+Ol < 1.l0E+02 < 8.70E+Ol Ce-141 < 2.00E+02 < 3.50E+02 < 2.30E+02 Ce-144 < 1.50E+02 < lAOE+02 < 1.80E+02 C-57

Appendix D Environmental Program Exceptions

Fermi 2 - 2009 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 2009, 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 2009. 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 2009, two hundred eighty-four (284) TLDs were placed in the field for the REMP program and all but four (4) TLDs were collected and processed.

T -2 was found missing during the first quarter collection and was replaced with the next quarter's TLD.

T -56 was found missing during the first quarter collection and was replaced with the next quarter's TLD.

T -65 was unobtainable during the second and third quarters due to Independent Spent Fuel Storage Installation (ISFSI) pad construction.

Atmospheric Monitoring During 2009, two hundred sixty (260) air samples were placed in the field and all but one (1) particulate filter and charcoal filter was collected and processed. There were no changes to the Atmospheric Monitoring program during 2009.

On 2/2512009, air sample located at API-4 was not collected due to pump failure. Air sampling equipment was replaced with a spare sampler. For this reason, the first quarter composite sample is considered less than representative.

Terrestrial Monitoring - None Milk Sampling - None D-1

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Garden Sampling - None Groundwater Sampling - None Aquatic Monitoring - None Drinking Water Sampling - None Surface Water Sampling - None Sediment Sampling All scheduled sediment samples were collected in 2009. On 12/02/09, Radiological Engineering was notified by the REMP vendor analysis Lab (Areva NP Inc.) that iodine-131 was detected in the sediment sample collected at location S-5 on 11/9/09. Location S-5 is located approximately 15 miles north and upstream from Fermi 2 Power Plant near Trenton Channel Power Plant. Due to the distance and flow direction S-5 is designated as the control or background sample and is considered to be unaffected by Fermi 2 operations. The iodine-131 was determined to be the result of effluent from the city of Trenton's municipal wastewater treatment facility as a result of nuclear medicine.

Fish Sampling - None D-2

Appendix E Interlaboratory Comparison Data Areva NP Inc. Environmental Laboratory's Quality Assurance Programs

Fermi 2 - 2009 Annual Radiological Environmental Operating Report Interlaboratory Comparison Program for 2009 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 Areva NP Inc.'s participation in an interlaboratory comparison program.

E-I

March 02, 2010 EL 034/10 TO: Distribution FROM: J. M. Raimondi

SUBJECT:

AREVA NP Environmental Laboratory Annual Quality Assurance Report for Environmental Analyses (January - December 2009)

Attached is the AREVA NP Environmental Laboratory (E-LAB) annual quality assurance report covering Environmental Analyses. This report includes analytical Quality Control (QC) programs in support of client Radiological Environmental Monitoring Programs (REMP), analysis of additional radionuclides in environmental samples that are typically outside the REMP scope, and QC of environmental Thermoluminescent Dosimetry (TLD). QC programs associated with the analysis of effluent samples (10CFR 50), waste samples (10CFR61), bioassay samples, and personnel dosimetry are included in separate reports.

For Radiological Environmental Monitoring Programs (REMP):

99.2% of 904 individual QC analyses evaluated during this annual period met E-LAB acceptance criteria for bias.

99.0% of 705 QC analyses met the Laboratory QC acceptance criteria for precision.

For All Environmental Analyses:

99.1 % of 923 individual QC analyses evaluated during this annual period met E-LAB acceptance criteria for bias.

99.1 % of 765 QC analyses met the Laboratory QC acceptance criteria for precision.

The AREVA NP Environmental Laboratory (10# 11823) maintained accreditation for six radiological analytes in the potable and non-potable water categories from the State of New York Department of Health under the National Environmental Laboratory Accreditation Program (NELAP). A total of 18 out of the 18 Proficiency Test results were rated "Acceptable" this period.

For Environmental Dosimetry:

100% of the 84 individual environmental dosimeters met E-LAB acceptance criteria for bias and precision.

100% of the 14 mean dosimeter responses met E-LAB acceptance criteria for bias.

Please contact Cynthia Harrington at (508) 573-6660 or me at (508) 573-6651 if you have any questions.

Manager, Environmental Laboratory CLH/kem ATTACHMENTS An AREVA and Siemens company Environmental Laboratory - 29 Research Drive, Westborough, MA 01581-3913 Tel: 5085736650 - Fax: 508573 6680

Distribution Page 2 EL 034/10 March 2, 2010 Distribution R. Bevily - Entergy/Grand Gulf P. Blount - Dominion/Surry D. Calloway - Entergy/Arkansas Nuclear One J. Callaghan -AREVA NP J. Doroski - Dominion/Millstone A. Dubois - EntergylWaterford J. Furfaro - Entergy/Fitzpatrick C. Graham - Ameren U.E.lCalioway N. Hansen - Southern California Edison R. Hedgepeth - Indiana MichiganlD. C. Cook S. Langdon - Progress Energy T. Lashley - Detroit Edison/Fermi II W. Ng. - Dominion/Millstone D. Perkins - FP&LlSeabrook D. Robinson - FP&LlSeabrook M. Scannell - FP&LlSeabrook K. Sejkora - Entergy/Pilgrim J. Shelton - PSEG S. Skibniowsky - EntergyNermont Yankee B. Spell - Entergy/River Bend M. Strum -AREVA NP

, J. Sukosky - Dominion/Surry A. Thomas - AREVA N P J. Watts - Texas Utilities/Comanche Peak

For Environmental Analyses January - December 2009 QUALITY ASSURANCE TRENDING ANALYSIS 80 60 40 20 o ~~~~~=-~~.~~.~-:~--~-M.--~

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-80 ENVIRONMENTAL LABORATORY 29 Research Drive Westborough, MA 01581-3913

AREVA NP ENVIRONMENTAL LABORATORY ANNUAL QUALITY ASSURANCE STATUS REPORT FOR ENVIRONMENTAL ANALYSES JANUARY - DECEMBER 2009 EL 034/10 Prepared By: Date:

Approved By: Date:

AREVA NP Environmental Laboratory 29 Research Drive Westborough, MA 01581-3913 Telephone: (508) 573-6650 Fax: (508) 573-6680

TABLE OF CONTENTS I. INTRODUCTION ............................................................................................................... 1 A. Quality Control Programs for Environmental Sample Analyses ............................ 1

1. Inter-laboratory and Third Party ................................................................. 1

2. Intra-laboratory .......................................................................................... 2 B. Quality Control Programs for Environmental Dosimetry ........................................ 2

1. Inter-laboratory and Third Party ................................................................. 2

2. Intra-laboratory .......................................................................................... 3 C. Quality Assurance Program (Internal and External Assessments and Audits) ...... 3 II. Performance Evaluation Criteria ....................................................................................... 4 A. Acceptance Criteria for Environmental Sample Analysis ..................................... .4

1. Internal Process Control Samples ............................................................ .4

2. Backgrounds .............................................................................................. 6

3. Blanks ........................................................................................................ 6

4. NRC Resolution Criteria ............................................................................ 6

5. DOE Evaluation Criteria ............................................................................. 7 B. QC Investigation Criteria and Result Reporting for Environmental Sample Analysis ................................................................................................................. 7

1. QC Investigation Criteria ............................................................................ 7

2. Reporting of Analytical Results to Laboratory Customers ......................... 7 C. Acceptance Criteria for Environmental Dosimetry ................................................. 8

1. Internal and Third Party Evaluations .......................................................... 8 D. QC Investigation Criteria and Result Reporting for Environmental Dosimetry ...... 9

1. QC Investigation Criteria ............................................................................ 9

2. Reporting of Environmental Dosimetry Results to Laboratory Customers 9 E. Self-Assessment Program ................................................................................... 10 III. QUALITY CONTROL SYNOPSIS FOR ENVIRONMENTAL SAMPLE ANALYSES ....... 10 A. General Discussion ............................................................................................. 10 B. Result Summary .................................................................................................. 10

1. Analytics Environmental Cross Check Program ...................................... 10

2. Summary of Participation in the MAPEP Monitoring Program ................. 11

3. ERA PT Program and New York ELAP PT Program ............................... 11

4. Process Control Program for REMP Analyses ........................................ 11 F:\AOMIN\CORRES\EL 034-10 ii

TABLE OF CONTENTS (continued)

5. Process Control Program for Environmental Analysis of Additional Radionuclides .......................................................................................... 12

6. Analytical Blanks ..................................................................................... 12

7. Overall Data Summary for the Reporting Period January-December 2009

................................................................................................................. 12

8. Summary of Environmental Quality Control Results by Year .................. 12 IV. QUALITY CONTROL SYNOPSIS FOR ENVIRONMENTAL Dosimetery ....................... 13 A. General Discussion ............................................................................................. 13 B. Result Trending ................................................................................................... 13 V. Status of Condition Reports (CR) .................................................................................... 14 VI. Status of Audits/Assessments ......................................................................................... 14 A. Internal ................................................................................................................ 14 B. External ............................................................................................................... 14 VII. UPDATED PROCEDURES ISSUED DURING JANUARY-DECEMBER 2009 ............... 14 VIII. REFERENCES ................................................................................................................ 15 F:\AOMIN\CORRES\EL 034- iii

TABLE OF CONTENTS (continued)

APPENDIXA INTER/INTRA-LABORATORY, ENVIRONMENTAL MONITORING ANALYTICS, DOE, AND ERAIELAP QUALITY CONTROL PROGRAM RESULTS APPENDIX B ENVIRONMENTAL DOSIMETRY QUALITY CONTROL PROGRAM RESULTS F:\AOMIN\CORRES\EL 034- iv

TABLE OF CONTENTS (continued)

LIST OF TABLES

1. AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIEGLERANALYTICS ENVIRONMENTAL CROSSCHECK PROGRAM RESULTS BY ACCEPTANCE CRITERIA, MEDIA, AND ANALYSIS CATEGORIES - JANUARY - DECEMBER2009

2. AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIEGLERANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION

3. DEPARTMENT OF ENERGY MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM RESULTS - AREVA NP ENVIRONMENTAL LABORATORY

4. NEWYORK STATE DEPARTMENT OF HEALTH ENVIRONMENTAL LABORATORY APPROVAL PROGRAM PROFICIENCY TEST RESULTS - AREVA NP ENVIRONMENTAL LABORATORY

5. AREVA NP ENVIRONMENTAL LABORATORY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) INTRA-LABORATORY ENVIRONMENTAL PROCESS CONTROL RESULTS BY ACCEPTANCE CRITERIA, MEDIA, AND ANALYSIS CATEGORIES-JANUARY - DECEMBER 2009

6. AREVA NP ENVIRONMENTAL LABORATORY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) INTRA-LABORATORY AND INTER-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY MEDIA - JANUARY - DECEMBER 2009

7. AREVA NP ENVIRONMENTAL LABORATORY ADDITIONAL ENVIRONMENTAL ANALYSES INTRA-LABORATORY AND INTER-LABORATORY BIAS AND PRECISION BY ANALYSIS TYPE - JANUARY - DECEMBER 2009

8. AREVA NP ENVIRONMENTAL LABORATORY ALL ENVIRONMENTAL ANALYSES INTRA-LABORATORY AND INTER-LABORATORY BIAS AND PRECISION BY ANALYSIS TYPE - JANUARY - DECEMBER 2009

9. AREVA NP ENVIRONMENTAL LABORATORY ENVIRONMENTAL BIAS AND PRECISION BY YEAR

10. PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED E-LAB INTERNAL CRITERIA-JANUARY - DECEMBER 2009

11.

SUMMARY

OF THIRD PARTY DOSIMETERY TESTING - JANUARY - DECEMBER 2009

12. PERCENTAGE OF MEAN DOSIMETER ANALYSES (N=6) WHICH PASSED TOLERANCE CRITERIA - JANUARY - DECEMBER 2009

13. AREVA NP ENVIRONMENTAL LABORATORY CONDITION REPORT (CR) STATUS-JANUARY - DECEMBER 2009

14. UPDATED INSTRUMENTATION/ANALYTICAL PROCEDURES RELEVANT TO ENVIRONMENTAL SAMPLE ANALYSIS AND ENVIRONMENTAL DOSIMETRY ISSUED DURING JANUARY - DECEMBER 2009 F:\AOMIN\CORRES\EL 034- v

I. INTRODUCTION This report covers the Quality Assurance (QA) Program for the environmental monitoring aspects of the AREVA NP Environmental Laboratory (E-LAB) for 2009. The AREVA NP Environmental Laboratory QA Program is designed to monitor the quality of analytical processing associated with environmental, bioassay, effluent (1 OCFR Part 50), and waste (10CFR Part 61) sample analysis, as well as dosimetry processing. Due to the broad scope of quality control programs in which the E-LAB participates, this report covers only the following categories: Radiological Environmental Monitoring Program (REMP) analyses, additional environmental analyses that are outside the typical REMP scope, and direct radiation monitoring using environmental Thermoluminescent Dosimeters (TLDs). QA activities associated with waste analyses (10CFR 61), effluent analyses (10CFR 50), bioassay analyses, and personnel dosimetry are presented in separate reports.

This report includes:

Intra-laboratory QC results analyzed during the reporting period.

Inter-laboratory QC results, analyzed prior to the reporting period, for which "known values" were not previously available.

Inter-laboratory QC results, analyzed during the reporting period, for which "known values" were available.

Any other inter-laboratory QC results for which performance results are not available will be included in the next annual report.

Manual 100, "Laboratory Quality Assurance Plan", Revision 13 (Reference 1), became effective on June 4,2009, and Manual 120, "Dosimetry Services Quality System Manual", Revision 15 (Reference 2), became effective on October 16, 2009. The text of this report reflects the latest revisions of these manuals, as do the trending graphs and any data evaluations performed after the effective date.

A. Quality Control Programs for Environmental Sample Analyses

1. Inter-laboratory and Third Party The E-LAB participates in the following inter-laboratory and third party quality control programs for environmental radioanalyses:

Environmental Crosscheck Program administered by Eckert &

Ziegler Analytics, Inc.,

Environmental Resource Associates (ERA) Proficiency Test (PT)

Program or equivalent State administered ELAP PT program,

Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP)

The E-LAB purchases single-blind QC matrix spike samples from Eckert

& Ziegler to verify the analysis of sample matrices processed at the E-LAB. The E-LAB'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 F:\AOMIN\CORRES\EL 034- 1

inter-laboratory comparison program requirements discussed in NRC Regulatory Guide 4.15, revision 1.

The MAPEP program is administered by the Radiological and Environmental Sciences Laboratory (RESL) and consists of four media (water, soil, vegetation, and air filter) submitted twice each year. The MAPEP samples are designed to evaluate the ability and quality of analytical facilities performing sample measurements that contain hazardous and radioactive (mixed) analytes.

The ERA PT program and state administered ELAP PT programs consist of radionuclides in water submitted twice per year. These programs are used to maintain certification with the National Environmental Laboratory Accreditation Program (NELAP). The certification is necessary to perform analysis for projects that must meet EPA regulations for the Clean Water Act (CWA), Resource Conservation & Recovery Act (RCRA), or the Safe Drinking Water Act (SDWA).

2. Intra-laboratory The internal QC Program is designed to include QC functions such as instrumentation checks (to insure proper instrument response), blank samples (to which no analyte radioactivity has been added),

instrumentation backgrounds, duplicates, as well as overall staff qualification analyses and process controls. Both process control and qualification analyses samples seek to mimic the media type of those samples submitted for analysis by the various laboratory clients. These process controls (or process checks) are either actual samples submitted in duplicate in order to evaluate the precision of laboratory measurements, or blank samples which have been "spiked" with a known quantity of a radioisotope that is of interest to Laboratory clients. These QC samples, which represent either "single" or "double blind" unknowns, are intended to evaluate the entire radiochemical and radiometric process.

The E-LAB administers the QC program in accordance with an annual quality control and audit assessment schedule (Reference 3). The plan, which is approved on or before January 15th of each year and reviewed for adequacy at monthly LQARC meetings, describes the scheduled frequency and scope of quality assurance and control actions considered necessary for an adequate program. The magnitude of the process control program combines both internal and external sources targeted at 5% of the routine sample analysis load.

B. Quality Control Programs for Environmental Dosimetry

1. Inter-laboratory and Third Party The E-LAB participates in the following inter-laboratory and third party quality control programs for Panasonic environmental dosimeters:

F:\AOMIN\CORRES\EL 034- 2

Third-party testing conducted by Battelle Pacific Northwest Laboratories

In-plant testing programs conducted by various users of E-LAB dosimetry.

Under the third party program, sets of six dosimeters are irradiated to ANSI specified testing criteria by Battelle Pacific Northwest Laboratories and are submitted for processing as "unknowns." The bias and precision of TLD processing is measured against this standard (Reference 4) and are used to indicate trends and changes in performance.

Standard test methods for in plant testing of Panasonic whole body and extremity dosimeters are described in the E-LAB report entitled "In Plant External Dosimetry Quality Assurance Testing Program" (Reference 5).

This protocol provides standard test methods that may be used at plant sites utilizing E-LAB dosimeters. Clients have developed their own dosimetry test procedures modeled after Reference 5. Results of In-plant testing programs are not included in this report.

2. Intra-laboratory The in house testing program conducted by the E-LAB QA Officer, involves in-house irradiations of sets of six Panasonic environmental dosimeters according to the schedule given in Reference 3. These dosimeters are submitted for processing as "unknowns." The bias and precision of TLD processing is measured against criteria given in Reference 2 and are used to indicate trends and changes in performance.

Instrumentation checks, although routinely performed and representing between 5-10% of the TLDs processed, are not presented in this report.

C. Quality Assurance Program (Internal and External Assessments and Audits)

During each annual reporting period, at least one internal assessment is conducted in accordance with the pre-established schedule in Reference 3. In addition, the E-Lab may be audited by prospective customers during a pre-contract audit, and/or by existing clients who wish to conduct periodic audits in accordance with their contractual arrangements. A National Environmental Laboratory Accreditation Program (NELAP) audit is performed every two years as part of maintaining certification to perform EPA-related analyses.

An internal assessment of Dosimetry Services activities is conducted annually by the E-LAB QA Officer (Reference 3). The purpose of this assessment is to review analytical procedures, results, materials or components to identify opportunities to improve or enhance processes and/or services. In addition, a National Voluntary Laboratory Accreditation Program (NVLAP) audit is performed triennially of the dosimetry services area.

F:\AOMIN\CORRES\EL 034- 3

II. PERFORMANCE EVALUATION CRITERIA A. Acceptance Criteria for Environmental Sample Analysis The E-LAB has adopted a QC 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), the E-LAB will utilize the criteria for the specific program.

For inter-laboratory or third party QC programs that have no preset acceptance criteria (e.g. the Analytics Environmental Cross-check Program), results will be evaluated in accordance with E-LAB internal acceptance criteria. Replicate analyses, performed in support of third party QC programs, will also be evaluated for precision in accordance with E-LAB internal acceptance criteria.

1. Internal Process Control Samples Internal Process Control (PC) results are evaluated in accordance with two separate E-LAB acceptance criteria. A full discussion of the analytical services acceptance criteria can be found in Reference 1. The first criterion concerns bias, which is defined as the deviation of anyone result from the known value. The second criterion concerns precision, which deals with the ability of the measurement to be faithfully replicated by comparison of an individual result with the mean of all results for a given sample set. Quality control deviations falling outside the E-LAB acceptance criteria are discussed in the appendices.

(a) Bias For each analytical measurement tested, the bias is the percent deviation of the reported result relative to the expected value (value of the spike known by comparison with or derivation from a standard reference material). The percent deviation relative to the known is calculated as follows:

( H'I - H)

I 100 Hi where:

H: = the value of the ith measurement in a category being tested Hi = the actual quantity in the test sample as defined by the spike The Laboratory internal criterion for bias is that an analysis is considered in agreement if the value is within +/-20% of the known value. If this condition is not met, the two-sigma range about the analyzed value is established. If the known value falls within the specified range, the analysis is considered in agreement.

F:\AOMIN\CORRES\EL 034- 4

Deviations from this general criterion, for specific radionuclides, are given in Table 1 and Reference 1.

E-LAB acceptance criteria are applied when the sample concentration is 10 or more times the method M DC. Otherwise, the "known value" and associated uncertainty are compared to the measured result and uncertainty using a two-tailed standard statistical test at the 95% confidence level.

(b) Precision For a group of test measurements containing a given spiked level, the precision is the percent deviation of individual results relative to the mean reported measurement. At least two values are required for the determination of precision. The percent deviation relative to the mean reported measurement is calculated as follows:

where:

H: = the reported measurement for the ith analytical measurement H = the mean analytical measurement n = the number of samples in the test group The E-LAB criterion for precision is that an analysis is considered in agreement if the individual value is within +/-20% of the mean value. If this condition is not met, the two-sigma range about the analyzed value is established. If the mean value falls within the specified range, the analysis is considered in agreement.

Deviations from this general criterion, for specific radionuclides, are given in Tables 1.

(c) Mean Bias For each group of analytical measurements tested, the mean bias is the percent deviation of the mean reported result relative to the expected value. The mean percent deviation relative to the expected value is calculated as follows:

F:\AOMIN\CORRES\EL 034- 5

where:

H = the mean analytical measurement Hi = the actual quantity in the test sample as defined by the spike

2. Backgrounds As discussed in Reference 1, backgrounds represent the ambient signal response, recorded by measuring instruments, which is independent of radioactivity contributed by the radionuclides being measured in the sample. Backgrounds will not normally contain any three-sigma statistically positive activity of the target parameters. The background signal is subtracted from the sample's signal.

3. Blanks Wherever possible, equivalent media for preparing laboratory processing blanks will be used. Synthetic matrices may be used for bioassay if equivalency is proven.

4. NRC Resolution Criteria Some Laboratory clients use the NRC Resolution Criteria to evaluate double blind Part 50 performance. NRC Resolution Criteria are based on an empirical relationship that combines prior experience and the accuracy needs of the program. As "Resolution" increases, the acceptability of one's measurement becomes more selective. Conversely, as "Resolution" decreases, agreement levels are widened to account for the increase in uncertainty.

F:\AOMIN\CORRES\EL 034- 6

5. DOE Evaluation Criteria The Radiological & Environmental Sciences Laboratory (RESL) inter-comparison program, MAPEP, defines three levels of performance:

Acceptable, Acceptable with Warning, and Not Acceptable. Performance is considered acceptable for a mean with a bias :'S:20% of the reference value for the analyte. Performance is acceptable with warning for a mean result bias of >20% but :'S:30% of the reference value. If the bias is greater than 30%, the results are deemed not acceptable. The MAPEP includes low activity "sensitivity tests" and individual radionuclide-free "false positive tests."

B. QC Investigation Criteria and Result Reporting for Environmental Sample Analysis

1. QC Investigation Criteria Summarized below are the investigation criteria applied to QC analyses that failed E-LAB bias criteria. The Condition Report process tracks investigation results.

(a) No investigation is necessary when an individual QC result falls outside the QC performance criteria for bias or precision.

(b) Investigations shall be initiated when the mean of a QC process batch or the mean of three consecutive individual QC processes is outside the performance criterion for bias. Investigations shall also be initiated when more than one sample in a QC process batch or the mean of three consecutive individual QC processes is outside the performance criterion for precision.

2. Reporting of Analytical Results to Laboratory Customers A similar set of guidelines was developed, applicable to reporting of results. The guidelines are as follows:

If an investigation is required for a process (normally after consecutive QC process check failures), and if the QC results requiring the investigation have a mean bias from the known of greater than +/-

(applicable E-LAB bias criterion +5%) for environmental processing then the Laboratory Quality Assurance Review Committee (LQARC) shall meet to determine the disposition of client results.

F:\AOMIN\CORRES\EL 034- 7

C. Acceptance Criteria for Environmental Dosimetry

1. Internal and Third Party Evaluations (a) Bias For each dosimeter tested, the measure of bias is the percent deviation of the reported result relative to the delivered exposure.

The percent deviation relative to the delivered exposure is calculated as follows:

( H'I - H)

I 100 Hi where:

H: = the corresponding reported exposure for the ith dosimeter (i.e., the reported exposure)

Hi = the exposure delivered to the ith irradiated dosimeter (i.e., the delivered exposure)

(b) Mean Bias For each group of test dosimeters, the mean bias is the average percent deviation of the reported result relative to the delivered exposure. The mean percent deviation relative to the delivered exposure is calculated as follows:

where:

H: = the corresponding reported exposure for the ith dosimeter (i.e., the reported exposure)

Hi = the exposure delivered to the ith irradiated test dosimeter (i.e., the delivered exposure) n = the number of dosimeters in the test group (c) Precision For a group of test dosimeters irradiated to a given exposure, the measure of precision is the percent deviation of individual results relative to the mean reported exposure. At least two values are required for the determination of precision. The measure of precision for the ith dosimeter is:

F:\AOMIN\CORRES\EL 034- 8

where:

H: = the reported exposure for the ith dosimeter (i.e., the reported exposure)

H = the mean reported exposure; i.e., R LH:(~)

=

n = the number of dosimeters in the test group (d) E-LAB Internal Tolerance Limits Tolerance limits for bias and precision applied to in-house and accredited third party testing were adopted on November 13, 1987. These criteria are only applied to individual test dosimeters irradiated with high-energy photons (Cs-137 or Co-60) and are as follows for Panasonic Environmental dosimeters: +/- 20.1 % for bias and +/- 12.8% for precision.

D. QC Investigation Criteria and Result Reporting for Environmental Dosimetry

1. QC Investigation Criteria E-LAB Manual 120 (Reference 2) specifies when an investigation is required due to a QC analysis that has failed the E-LAB bias criteria. The criteria are as follows:

(a) No investigation is necessary when an individual QC result falls outside the QC performance criteria for accuracy.

(b) Investigations are initiated when the mean of a QC processing batch is outside the performance criterion for bias.

2. Reporting of Environmental Dosimetry Results to Laboratory Customers (a) All results are to be reported in a timely fashion.

(b) If the QA Officer determines that an investigation is required for a process, the results shall be issued as normal. If the QC results, prompting the investigation, have a mean bias from the known of greater than +/-20% for environmental dosimetry, the results shall be issued with a note indicating that they may be updated in the future, pending resolution of a QA issue.

(c) Environmental dosimetry results do not require updating if the investigation has shown that the mean bias between the original results and the corrected results, based on applicable correction factors from the investigation, does not exceed +/-20%.

F:\AOMIN\CORRES\EL 034- 9

E. Self-Assessment Program In accordance with Reference 1, the E-LAB has established a Self-Assessment policy where all Laboratory staff members are strongly encouraged to continually evaluate laboratory activities for quality enhancements, cost savings, and time savings.

III. QUALITY CONTROL SYNOPSIS FOR ENVIRONMENTAL SAMPLE ANALYSES A. General Discussion Two-year trending graphs are provided in Appendix A of this report to allow evaluation of trends or biases. In the event that an analysis does not meet E-LAB performance criteria, a brief explanation is included on the graph. It should be noted that MAPEP and ERA/ELAP samples are evaluated against criteria specific to those programs. Therefore, only MAPEP sample results which fell in the "Warning" or "Non-Agreement" categories will be addressed in Appendix A.

Beginning in 2009, ELAP samples are no longer included on the trending graphs due to the unique way in which the acceptance limits are calculated.

If any questions arise regarding previous analyses, please refer to the annual status report corresponding to the sample analysis date. In all cases, the QC database is available for each individual analysis to back-up the data presented on the graph.

B. Result Summary During this annual reporting period, thirty-two nuclides associated with seven media types were analyzed by means of the E-LAB's internal process control, MAPEP, ERA/ELAP and by Eckert & Ziegler Analytics QC programs. Media types representative of client company analyses performed during this reporting period were selected.

Presented below is a synopsis of the media types evaluated.

Air Filter Charcoal (Air Iodine) Water Milk Sediment/soil Vegetation Fish

1. Analytics Environmental Cross Check Program During this period the Eckert & Ziegler Analytics cross check program provided 426 individual environmental analyses for bias and 426 for precision evaluation (Table 1). Of the 426 analyses evaluated for bias, 98.6% (420/426) of all results fell within E-LAB acceptance criteria. Of the 426 analyses evaluated for precision, 99.8% (425/426) fell within E-LAB tolerance limits. Appendix A graphically summarizes the results by two-year trending graphs.

Table 2 provides a report of the E-LAB's participation in the Eckert &

Ziegler Analytics' cross check program for the fourth quarter of 2008 and the first three quarters of 2009. Using the E-LAB's internal acceptance F:\AOMIN\CORRES\EL 034- 10

criteria as the basis of evaluation, 141 out of 142 mean results were within agreement criteria. The single failure pertained to the gross alpha analysis of the 1st quarter 2009 water sample and was addressed by Condition Report (CR) 09-21.

2. Summary of Participation in the MAPEP Monitoring Program.

During this reporting period, two sets of MAPEP samples were processed and reported (Table 3). Using the DOE acceptance criteria as the basis of evaluation, 65 out of 74 mean results came within agreement criteria.

For MAPEP 20, six results fell into the "warning" category as follows: Pu-238 and Pu-239/40 on the filter, Cs-137, Mn-54, and K-40 in soil, and Am-241 in water. CR 09-12 and CR-09-13 were issued to investigate the plutonium and americium low biases, respectively. CR-09-14 was issued to investigate the high biases in soil, including Zn-65, which was "not acceptable". Two results for MAPEP 21 fell into the "warning" category, as follows: Pu-239/40 in water and Am-241 in water. CR 09-12 and CR-09-13 remain open to investigate the plutonium and americium low biases, respectively.

3. ERA PT Program and New York ELAP PT Program During this reporting period, a total of 18 individual results were evaluated by the New York State Department of Health ELAP program. Using the evaluation criteria set by NELAP, 100% (18/18) of the radionuclides were "Satisfactory". Table 4 provides a report of the Laboratory's participation in this PT program.

The AREVA NP Environmental Laboratory (Lab 10# 11823) maintained NELAP accreditation from the New York State Department of Health through the Environmental Laboratory Approval Program for the following methods for both potable and non-potable waters:

Gross Alpha, Method EPA 900.0

Gross Beta, Method EPA 900.0

lodine-131, Method ASTM D4785-00a

Photon Emitters, Method EPA 901.1

Radioactive Cesium, Method EPA 901.1

Tritium, Method EPA 906.0

4. Process Control Program for REMP Analyses The E-Lab internal (intra-laboratory) process control program evaluated 478 individual analyses for bias and 133 analyses for precision for standard REMP media and nuclides. The results are summarized in Table 5.

Of the 478 internal process control analyses evaluated for bias, 99.8%

met Laboratory acceptance criteria. Also, 95.5% of the 133 results for precision were found to be acceptable.

F:\AOMIN\CORRES\EL 034- 11

Table 6 presents the internal process control data combined with Eckert &

Ziegler Analytics cross-check data (evaluated for bias and precision) and individual MAPEP analyses (evaluated for precision only) for standard REMP media and nuclides. For this data set, 99.2% of the 904 analyses evaluated for bias and 99.0% of the 705 analyses evaluated for precision met Laboratory acceptance criteria.

To support the efforts required for the EPRI Groundwater Monitoring Program at client sites, the E-LAB performs low-level QC testing specifically for H-3 in water. The E-LAB prepares these spikes internally using a low activity H-3 spike obtained from Eckert & Ziegler Analytics.

Activities ranged from approximately 1,700 - 9,000 pCilL. A chart of low activity H-3 spike performance is provided in Appendix A. All 2009 analyses were within the acceptance criteria.

5. Process Control Program for Environmental Analysis of Additional Radionuclides To support the efforts of various monitoring programs at client sites, the E-LAB performs low-level analyses of additional nuclides that are not normally included in a standard REMP. The QC analysis results for these nuclides are presented in Table 7 by analysis type. Eighteen of 19 analyses (94.7%) evaluated for accuracy met E-Lab acceptance criteria.

One hundred percent of the 60 analyses evaluated for precision met the E-LAB acceptance criteria.

6. Analytical Blanks During this reporting period, statistically positive activity, (activity greater than three (3) times the standard deviation) was not reported for any of the 149 environmental analytical blanks analyzed.

7. Overall Data Summary for the Reporting Period January-December 2009 The intra- and inter-laboratory QC data for all environmental process control nuclide analyses, evaluated to internal E-LAB performance criteria, are summarized in Table 8, presented by analysis type.

Excluded from this table are evaluations of MAPEP and ELAP samples for accuracy, as these samples are evaluated to program specific acceptance criteria. Nine hundred fifteen of 923 individual results evaluated to internal E-LAB performance criteria (99.1 %) fell within the E-LAB bias acceptance criteria, while 99.1 % of the 765 analyses passed the acceptance criteria for precision.

8. Summary of Environmental Quality Control Results by Year The historical summary of the E-LAB process control program performance for the environmental monitoring function is provided in Table 9. For 2009, 99.1 % of the analyses fell within the E-LAB acceptance criteria for bias as compared to a historical percentage of 97.0. Similarly, 99.1 % of the analyses evaluated for precision met the E-LAB acceptance criteria as compared to 99.4% of analyses for the 33-year operating history.

F:\AOMIN\CORRES\EL 034- 12

Trending graphs associated with the performance results for this program are given in Appendix A.

IV. QUALITY CONTROL SYNOPSIS FOR ENVIRONMENTAL DOSIMETERY A. General Discussion Summaries of the performance tests for the reporting period are given in Tables 10 through 12 and Appendix B. Results are presented only for performance tests conducted under well-characterized conditions. Results are reported for the twelve-month period January-December 2009.

Table 10 provides a summary of individual dosimeter results evaluated against the E-LAB internal acceptance criteria for high-energy photons only. During this period, 100% (84/84) of the individual dosimeters, evaluated against these criteria met the tolerance limits for accuracy and 100% (84/84) met the criterion for precision.

Table 11 presents the third-party testing results for dosimeters processed during this annual period. The mean percent bias and standard deviation for each group of six dosimeters are shown.

Table 12 provides the performance results for each group (N=6) of dosimeters evaluated against the internal tolerance criteria (third party and in-house irradiations). Overall, 100% (14/14) of the dosimeter sets evaluated against the internal tolerance performance criteria met these criteria.

B. Result Trending One of the main benefits of performing quality control tests on a routine basis is to identify trends or performance changes. The results of the Panasonic environmental dosimeter performance tests are presented in Appendix B for a two year period. The results are evaluated against each of the performance criteria listed in Section II, namely: individual dosimeter bias, individual dosimeter precision, and mean bias.

All of the results presented in Appendix B are fade corrected to the irradiation date and plotted sequentially by processing date. This allows assessment of performance without the confounding effect of the variation in number of days between irradiation and readout. Therefore, the results include any bias produced by the fade algorithm.

If fade is not corrected to the date of irradiation, the possibility of a bias due to signal fading exists. When Dosimetry Services processes a TLD, the software calculates a fade correction using one half the number of days between the processing date and the anneal date. The use of the midpoint for fade correction can bias the results of performance tests of TLDs irradiated at either the beginning or end of a wear period. Results for performance tests conducted near the beginning of the period will be biased low and those irradiated near the end of a period will be biased high, assuming there are no other system biases.

For individual Panasonic environmental TLDs processed in 2009, 100% of the 84 tests came within the E-LAB bias and precision tolerance limits. All 14 F:\AOMIN\CORRES\EL 034- 13

Panasonic environmental TLD test sets (mean bias, n=6) were reported within the internal tolerance criteria for bias.

V. STATUS OF CONDITION REPORTS (CR)

Table 13 provides a synopsis of CR activity for environmental processing during 2009.

Twenty-two condition reports were closed and nineteen were opened during this reporting period. As of December 31, 2009, a total of eight CRs remain open, two of which are older than 6 months.

VI. STATUS OF AUDITS/ASSESSMENTS A. Internal Corporate QA Audit No. 09-11, was conducted from July 6,2009 through July 10, 2009. The audit was conducted to verify compliance with E-LAB QA Manual 100 and Dosimetry QA Manual 120. There were no findings or recommendations pertaining to the E-LAB.

One additional internal QA assessment was conducted for processes involved in the environmental monitoring area during 2009. Internal Assessment 09-02 evaluated areas of the E-Lab Quality Assurance Program applicable to N ELAC accredited techniques. Condition reports were issued to document the findings from this assessment, and recommendations were entered into the E-Lab task tracking system.

B. External A National Voluntary Laboratory Accreditation Program (NVLAP) audit was conducted from May 6, 2009 to May 8, 2009 in the Dosimetry Services area. No nonconformities were reported. Recommendations were entered into the E-Lab task tracking system.

The Exelon Nuclear audit, No. SR-2009-23, was conducted from August 10, 2009 through August 14,2009. There were three findings issued. The E-LAB responded to these items and the findings were closed on October 1, 2009.

VII. UPDATED PROCEDURES ISSUED DURING JANUARY-DECEMBER 2009 A list of procedures, pertaining to environmental monitoring, which were updated during 2009 is included in Table 14.

F:\AOMIN\CORRES\EL 034- 14

VIII. REFERENCES

1. AREVA NP Environmental Laboratory Manual 100 "Laboratory Quality Assurance Plan", Revision 13, June 4,2009.

2. E-LAB Manual No.120, "Dosimetry Services Quality System Manual", Rev. 15, October 16, 2009.

3. AREVA NP Environmental Laboratory 2009 Quality Control and Audit Assessment Schedule.

4. American National Standard for Performance Testing of Extremity Dosimeters, ANSI N13.32-1995 (Draft), Health Physics Society, 1313 Dolley Madison Blvd.,

Suite 402, McLean, VA 22101.

5. "In-Plant External Dosimetry Quality Assurance Testing Program," E-LAB, Revision 2, December 1986.

F:\AOMIN\CORRES\EL 034- 15

TABLE 1 AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL CROSSCHECK PROGRAM RESULTS BY ACCEPTANCE CRITERIA, MEDIA AND ANALYSIS CATEGORIES JANUARY - DECEMBER 2009 Bias Criteria (1) Precision Criteria (1)

WITHIN OUTSIDE WITHIN OUTSIDE CRITERIA CRITERIA CRITERIA CRITERIA I. Air Particulate Gross Alpha 11 1 12 0 Gross Beta 12 0 12 0 Gamma 54 0 54 0 II. Air Charcoal Gamma 12 0 12 0 III. Milk Gamma 120 0 120 0 Iodine (ll) 12 0 12 0 Sr-89 6 0 6 0 Sr-90 6 0 6 0 IV. Water Gross Alpha 9 3 12 0 Gross Beta 12 0 12 0 Gamma 118 2 119 1 Iodine (ll) 12 0 12 0 Sr-89 12 0 12 0 Sr-90 12 0 12 0 Tritium 12 0 12 0 Total Number In Range: 420 6 425 1 Percentage of Total Processed 98.6 1.4 99.8 0.2 Sum of Analyses: 426 426 (1) Bias and PrecIsion as noted In Table 1.

F:\AOMIN\CORRES\EL 034- 16

TABLE 1 AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL CROSSCHECK PROGRAM RESULTS BY ACCEPTANCE CRITERIA, MEDIA AND ANALYSIS CATEGORIES JANUARY - DECEMBER 2009 (Continued)

A. Percent Bias Acceptance Criteria

'S:20 (or within 2 sigma of known, see Reference 1)

For Gross Alpha and Beta :'S:25 (or within 2 sigma of known)

For Sr-89/90 :'S:25 (or within 2 sigma of known)

B. Percent Precision Acceptance Criteria

'S:20 (or within 2 sigma of mean, see Reference 1). Exceptions as above.

F:\AOMIN\CORRES\EL 034- 17

TABLE 2 AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION RATIO SAMPLE QUARTER! SAMPLE REPORTED KNOWN PERFORMANCE NUCLIDE UNITS E-LABI NUMBER YEAR MEDIA VALUE VALUE EVALUATION ANALYTICS E6346-162 4th/200S Water Gross Alpha pCilL 104 114 0.91 Aareement E6346-162 4th/200S Water Gross Beta pCilL 20S 204 1.02 Agreement E6347-162 4tn /200S Water 1-131LL pCilL 57.5 64.1 0.90 Agreement E6347-162 4th/200S Water 1-131 pCilL 54.3 64.1 0.S5 Agreement E6347-162 4tn /200S Water Ce-141 pCilL 209 224 0.93 Agreement E6347-162 4th/200S Water Cr-51 pCilL 299 2SS 1.04 Agreement E6347-162 4tn /200S Water Cs-134 pCilL 141 157 0.90 Agreement E6347-162 4th/200S Water Cs-137 pCilL 134 140 0.96 Agreement E6347-162 4tn /200S Water Co-5S pCilL 115 122 0.94 Agreement E6347-162 4th/200S Water Mn-54 pCilL 172 17S 0.97 Agreement E6347-162 4tn /200S Water Fe-59 pCilL 122 117 1.04 Agreement E6347-162 4th/200S Water Zn-65 pCilL 203 214 0.95 Agreement E6347-162 4tn /200S Water Co-60 pCilL 154 156 0.99 Agreement E634S-162 4th/200S Water Sr-S9 pCilL 7S.S 97.7 0.S1 Agreement E634S-162 4tn /200S Water Sr-90 pCilL 14.1 13.4 1.05 Agreement E6349-162 4th/200S Water H-3 pCilL 10300 10200 1.01 Agreement E6350-162 4tn /200S Charcoal 1-131 pCi 53.1 53.6 0.99 AQreement E6351-162 4th/200S Filter Gross Alpha pCi 72.3 63.2 1.14 Aareement E6351-162 4tn /200S Filter Gross Beta pCi 127 113 1.12 Agreement E6352-162 4th/200S Filter Ce-141 pCi 112 119 0.94 Agreement E6352-162 4tn /200S Filter Cr-51 pCi 152 153 0.99 Agreement E6352-162 4th/200S Filter Cs-134 pCi 77.S S3.6 0.93 Agreement E6352-162 4tn /200S Filter Cs-137 pCi 76.S 74.6 1.03 Agreement E6352-162 4th/200S Filter Co-5S pCi 63.1 64.9 0.97 Agreement E6352-162 4tn /200S Filter Mn-54 pCi 91.S 94.6 0.97 Agreement E6352-162 4th/200S Filter Fe-59 pCi 60.4 62.5 0.97 Agreement E6352-162 4tn /200S Filter Zn-65 pCi 110 114 0.96 Agreement E6353-162 4th/200S Milk 1-131LL pCilL 72.4 79.9 0.91 Aareement E6353-162 4tn /200S Milk 1-131 pCilL 74.3 79.9 0.93 Agreement E6353-162 4th/200S Milk Ce-141 pCilL 1S4 191 0.96 Agreement E6353-162 4tn /200S Milk Cr-51 pCilL 235 246 0.96 Agreement E6353-162 4th/200S Milk Cs-134 pCilL 125 134 0.93 Agreement E6353-162 4tn /200S Milk Cs-137 pCilL 119 120 1.00 Agreement E6353-162 4th/200S Milk Co-5S pCilL 105 104 1.01 Agreement E6353-162 4tn /200S Milk Mn-54 pCilL 152 152 1.00 Agreement E6353-162 4th/200S Milk Fe-59 pCilL 107 100 1.06 Agreement E6353-162 4tn /200S Milk Zn-65 pCilL 177 1S3 0.97 Agreement E6353-162 4th/200S Milk Co-60 pCilL 135 133 1.01 Agreement F:\AOMIN\CORRES\EL 034- 1S

TABLE 2 AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION (Continued)

SAMPLE QUARTERJ SAMPLE NUCLIDE UNITS REPORTED KNOWN RATIO PERFORMANCE NUMBER YEAR3 MEDIA VALUE VALUE E*LABJ EVALUATION ANALYTICS E6558-162 51 1 /2009 Water Gross Alpha pCilL 120 162 0.75 Non-Aareement1 51 E6558-162 1 /2009 Water Gross Beta pCilL 189 203 0.93 Agreement 51 E6559-162 1 /2009 Water 1-131LL pCilL 63.2 69.0 0.92 Agreement 51 E6559-162 1 /2009 Water 1-131 pCilL 58.8 69.0 0.85 Agreement 51 E6559-162 1 /2009 Water Ce-141 pCilL 114 120 0.95 Agreement 51 E6559-162 1 /2009 Water Cr-51 pCilL 365 387 0.94 Agreement 51 E6559-162 1 /2009 Water Cs-134 pCilL 107 119 0.90 Agreement 51 E6559-162 1 /2009 Water Cs-137 pCilL 136 141 0.96 Agreement 51 E6559-162 1 /2009 Water Co-58 pCilL 145 151 0.96 Agreement 51 E6559-162 1 /2009 Water Mn-54 pCilL 165 162 1.02 Agreement 51 E6559-162 1 /2009 Water Fe-59 pCilL 128 127 1.01 Agreement 51 E6559-162 1 /2009 Water Zn-65 pCilL 192 197 0.97 Agreement 51 E6559-162 1 /2009 Water Co-60 pCilL 184 180 1.02 Agreement 51 E6560-162 1 /2009 Water Sr-89 pCilL 80.5 94.5 0.85 Agreement 51 E6560-162 1 /2009 Water Sr-90 pCilL 14.9 15.1 0.99 Agreement 51 E6561-162 1 /2009 Water H-3 pCilL 4090 4480 0.91 Agreement 51 E6562-162 1 /2009 Charcoal 1-131 pCi 70.5 79.4 0.89 Agreement E6563-162 51 1 /2009 Filter Gross Alpha pCi 140 122 1.15 Aareement L 51 E6563-162 1 /2009 Filter Gross Beta pCi 168 153 1.10 Agreement 51 E6564-162 1 /2009 Milk 1-131LL pCilL 72.9 79.3 0.92 Agreement 51 E6564-162 1 /2009 Milk 1-131 pCilL 69.1 79.3 0.87 Agreement 51 E6564-162 1 /2009 Milk Ce-141 pCilL 91.7 94.9 0.97 Agreement 51 E6564-162 1 /2009 Milk Cr-51 pCilL 300 305 0.98 Agreement 51 E6564-162 1 /2009 Milk Cs-134 pCilL 85 93.7 0.91 Agreement 51 E6564-162 1 /2009 Milk Cs-137 pCilL 115 111 1.04 Agreement 51 E6564-162 1 /2009 Milk Co-58 pCilL 121 119 1.01 Agreement 51 E6564-162 1 /2009 Milk Mn-54 pCilL 135 128 1.05 Agreement 51 E6564-162 1 /2009 Milk Fe-59 pCilL 109 99.9 1.09 Agreement 51 E6564-162 1 /2009 Milk Zn-65 pCilL 155 156 0.99 Agreement 51 E6564-162 1 /2009 Milk Co-60 pCilL 146 142 1.03 Agreement 51 E6565-162 1 /2009 Milk Sr-89 pC ilL 80.1 97.7 0.82 Agreement 51 E6565-162 1 /2009 Milk Sr-90 pCilL 14.5 15.6 0.93 Agreement The percent difference of the mean value from the known value exceeded the Manual 100 criterion for accuracy. CR 09-21 was issued to investigate the failure.

2 Eckert & Ziegler Analytics changed the filter preparation method by reducing the thickness of the filter coating from 0.85 mg/cm 2 to 0.5 mg/cm 2 An instrument recalibration, performed with a .5 mg/cm 2 coated filter, yielded an increase in alpha efficiency of 16%. Application of the new efficiency to the measured result yields a percent difference from the Analytics known value of -1.1 %.

3These results were erroneously decay corrected to 03/20109 rather than the true reference date of 03/19/09. This table reflects the results as reported to Analytics, prior to correction. All corrected results, other than gross alpha in water, met the agreement criteria. CR 09-29 was issued to address the reference date error.

F:\AOMIN\CORRES\EL 034- 19

TABLE 2 AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION (Continued)

RATIO SAMPLE QUARTER! SAMPLE REPORTED KNOWN PERFORMANCE NUCLIDE UNITS E-LABI NUMBER YEAR MEDIA VALUE VALUE EVALUATION ANALYTICS E6711-162 2 nd /2009 Water Gross Alpha pCilL 272 281 0.97 Agreement E6711-162 2 nd /2009 Water Gross Beta pCilL 157 141 1.11 Agreement E6712-162 2 nd /2009 Water 1-131LL pCilL 83.5 88.3 0.95 Agreement E6712-162 2 nd /2009 Water 1-131 pCilL 87.4 88.3 0.99 Agreement E6712-162 2 nd /2009 Water Ce-141 pCilL 206 216 0.96 Agreement E6712-162 2 nd /2009 Water Cr-51 pCilL 290 304 0.95 Agreement E6712-162 2 nd /2009 Water Cs-134 pCilL 111 126 0.88 Agreement E6712-162 2 nd /2009 Water Cs-137 pCilL 148 146 1.02 Agreement E6712-162 2 nd /2009 Water Co-58 pCilL 70.3 69.8 1.01 Agreement E6712-162 2 nd /2009 Water Mn-54 pCilL 107 104 1.03 Agreement E6712-162 2 nd /2009 Water Fe-59 pCilL 97.7 92.9 1.05 Agreement E6712-162 2 nd /2009 Water Zn-65 pCilL 142 133 1.07 Agreement E6712-162 2 nd /2009 Water Co-60 pCilL 231 237 0.97 Agreement E6713-162 2 nd /2009 Water Sr-89 pCilL 77.8 91.1 0.85 Agreement E6713-162 2 nd /2009 Water Sr-90 pCilL 13.1 13.6 0.96 Agreement E6714-162 2 nd /2009 Water H-3 pCilL 12300 13300 0.92 Agreement E6715-162 2 nd /2009 Charcoal 1-131 pCi 92.5 95.1 0.97 Aareement E6716-162 2 nd /2009 Filter Gross Alpha pCi 102 118 0.86 Aareement E6716-162 2 nd /2009 Filter Gross Beta pCi 60.3 59.3 1.02 Agreement E6717-162 2 nd /2009 Filter Ce-141 pCi 79.7 85.6 0.93 Agreement E6717-162 2 nd /2009 Filter Cr-51 pCi 116 121 0.96 Agreement E6717-162 2 nd /2009 Filter Cs-134 pCi 46.9 49.9 0.94 Agreement E6717-162 2 nd /2009 Filter Cs-137 pCi 59.8 57.9 1.03 Agreement E6717-162 2 nd /2009 Filter Co-58 pCi 27.4 27.7 0.99 Agreement E6717-162 2 nd /2009 Filter Mn-54 pCi 41.0 41.3 0.99 Agreement E6717-162 2 nd /2009 Filter Fe-59 pCi 34.8 36.9 0.94 Agreement E6717-162 2 nd /2009 Filter Zn-65 pCi 52.4 52.9 0.99 Agreement E6717-162 2 nd /2009 Filter Co-60 pCi 88.3 94.0 0.94 Agreement E6718-162 2 nd /2009 Milk 1-131LL pCilL 94.7 102 0.93 Aareement E6718-162 2 nd /2009 Milk 1-131 pCilL 97.7 102 0.96 Agreement E6718-162 2 nd /2009 Milk Ce-141 pCilL 275 284 0.97 Agreement E6718-162 2 nd /2009 Milk Cr-51 pCilL 395 400 0.99 Agreement E6718-162 2 nd /2009 Milk Cs-134 pCilL 146 166 0.88 Agreement E6718-162 2 nd /2009 Milk Cs-137 pCilL 187 192 0.97 Agreement E6718-162 2 nd /2009 Milk Co-58 pCilL 90.0 91.9 0.98 Agreement E6718-162 2 nd /2009 Milk Mn-54 pCilL 138 137 1.01 Agreement E6718-162 2 nd /2009 Milk Fe-59 pCilL 130 122 1.06 Agreement E6718-162 2 nd /2009 Milk Zn-65 pCilL 185 175 1.05 Agreement E6718-162 2 nd /2009 Milk Co-60 pCilL 316 312 1.01 Agreement F:\AOMIN\CORRES\EL 034- 20

TABLE 2 AREVA NP ENVIRONMENTAL LABORATORY ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL CROSS CHECK PROGRAM PERFORMANCE EVALUATION (Continued)

RATIO SAMPLE QUARTER! SAMPLE REPORTED KNOWN PERFORMANCE NUCLIDE UNITS E-LABI NUMBER YEAR MEDIA VALUE VALUE EVALUATION ANALYTICS E6823-162 3rd /2009 Water Gross Alpha pCilL 275 324 0.85 Agreement E6823-162 3rd /2009 Water Gross Beta pCilL 281 287 0.98 Agreement E6824-162 3rd /2009 Water 1-131LL pCilL 100.9 98.4 1.02 Agreement E6824-162 3rd /2009 Water 1-131 pCilL 87.7 98.4 0.89 Agreement E6824-162 3rd /2009 Water Ce-141 pCilL 258 264 0.98 Agreement E6824-162 3rd /2009 Water Cr-51 pCilL 199 212 0.94 Agreement E6824-162 3rd /2009 Water Cs-134 pCilL 108 118 0.92 Agreement E6824-162 3rd /2009 Water Cs-137 pCilL 175 177 0.99 Agreement E6824-162 3rd /2009 Water Co-58 pCilL 94.8 95.4 0.99 Agreement E6824-162 3rd /2009 Water Mn-54 pCilL 200 198 1.01 Agreement E6824-162 3rd /2009 Water Fe-59 pCilL 146 141 1.04 Agreement E6824-162 3rd /2009 Water Zn-65 pCilL 198 195 1.01 Agreement E6824-162 3rd /2009 Water Co-60 pCilL 149 154 0.97 Agreement E6825-162 3rd /2009 Water Sr-89 pCilL 88.9 105 0.85 Agreement E6825-162 3rd /2009 Water Sr-90 pCilL 18.1 18.5 0.98 Agreement E6826-162 3rd /2009 Water H-3 pCilL 13500 14100 0.96 Agreement E6827-162 3rd /2009 Charcoal 1-131 pCi 89.5 92.0 0.97 Aareement E6828-162 3rd /2009 Filter Gross Alpha pCi 251 265 0.95 Aareement E6828-162 3rd /2009 Filter Gross Beta pCi 239 235 1.02 Agreement E6829-162 3rd /2009 Milk 1-131LL pCilL 97.2 98.6 0.99 Aareement E6829-162 3rd /2009 Milk 1-131 pCilL 104 98.6 1.06 Agreement E6829-162 3rd /2009 Milk Ce-141 pCilL 270 275 0.98 Agreement E6829-162 3rd /2009 Milk Cr-51 pCilL 217 221 0.98 Agreement E6829-162 3rd /2009 Milk Cs-134 pCilL 111 123 0.90 Agreement E6829-162 3rd /2009 Milk Cs-137 pCilL 188 185 1.02 Agreement E6829-162 3rd /2009 Milk Co-58 pCilL 99.2 99.4 1.00 Agreement E6829-162 3rd /2009 Milk Mn-54 pCilL 210 206 1.02 Agreement E6829-162 3rd /2009 Milk Fe-59 pCilL 159 147 1.08 Agreement E6829-162 3rd /2009 Milk Zn-65 pCilL 209 204 1.02 Agreement E6829-162 3rd /2009 Milk Co-60 pCilL 160 160 1.00 Agreement E6830-162 3rd /2009 Milk Sr-89 pCilL 91.8 107 0.86. Agreement E6830-162 3rd /2009 Milk Sr-90 pCilL 18.1 18.8 0.96 Aareement F:\AOMIN\CORRES\EL 034- 21

TABLE 3 DEPARTMENT OF ENERGY MIXED ANAL YTE PERFORMANCE EVALUATION PROGRAM RESULTS AREVA NP ENVIRONMENTAL LABORATORY REPORTED MAPEP SAMPLE MATRIXI REFERENCE RADIO- MEAN % PERFORMANCE VALUE 10 UNITS DATE NUCLIDE VALUE BIAS EVALUATION Bq/Units Bq/Units MAPEP-09-RdF20 Filter (8q/filter) 1-Jan-09 Am-241 0.1712 0.205 -16.5 Acceptable MAPEP-09-RdF20 Filter (8q/filter) 1-Jan-09 Cs-134 2.85 2.93 -2.7 Acceptable MAPEP-09-RdF20 Filter (8q/filter) 1-Jan-09 Cs-137 1.576 1.52 3.7 Acceptable MAPEP-09-RdF20 Filter (8q/filter) 1-Jan-09 Co-57 1.302 1.30 0.2 Acceptable MAPEP-09-RdF20 Filter (8q/filter) 1-Jan-09 Co-60 1.196 1.22 -2.0 Acceptable MAPEP-09-RdF20 Filter (8q/filter) 1-Jan-09 Mn-54 2.36 2.2709 3.9 Acceptable MAPEP-09-RdF20 Filter (8q/filter) 1-Jan-09 Pu-238 0.1394 0.1763 -20.9 Warning I MAPEP-09-RdF20 Filter (8q/filter) 1-Jan-09 Pu-239/240 0.1246 0.157 -20.6 Warning' MAPEP-09-RdF20 Filter (8q/filter) 1-Jan-09 Sr-90 0.571 0.640 -10.8 Acceptable MAPEP-09-RdF20 Filter (8q/filter) 1-Jan-09 Zn-65 1.374 1.36 1.0 Acceptable MAPEP-09-MaS20 Soil (8q/kg) 1-Jan-09 Cs-134 521 467 11.6 Acceptable MAPEP-09-MaS20 Soil (8q/kg) 1-Jan-09 Cs-137 750 605 24.0 Warning L MAPEP-09-MaS20 Soil (8q/kg) 1-Jan-09 Co-57 0.33 N/A N/A Acceptable MAPEP-09-MaS20 Soil (8q/kg) 1-Jan-09 Co-60 3.97 4.113 N/A Acceptable MAPEP-09-MaS20 Soil (8q/kg) 1-Jan-09 Mn-54 387 307 26.1 Warning L MAPEP-09-MaS20 Soil (8q/kg) 1-Jan-09 K-40 714 570 25.3 Warning L MAPEP-09-MaS20 Soil (8q/kg) 1-Jan-09 Sr-90 250 257 -2.7 Acceptable MAPEP-09-MaS20 Soil (8q/kg) 1-Jan-09 Zn-65 317 242 31.0 UnacceptableL MAPEP-09-RdV20 Veg.(8q/sample) 1-Jan-09 Cs-134 3.22 3.40 -5.3 Acceptable MAPEP-09-RdV20 Veg.(8q/sample) 1-Jan-09 Cs-137 0.984 0.93 5.8 Acceptable MAPEP-09-RdV20 Veg.(8q/sample) 1-Jan-09 Co-57 2.50 2.36 5.9 Acceptable MAPEP-09-RdV20 Veg.(8q/sample) 1-Jan-09 Co-60 0.037 N/A N/A Acceptable MAPEP-09-RdV20 Veg.(8q/sample) 1-Jan-09 Mn-54 2.37 2.30 3.0 Acceptable MAPEP-09-RdV20 Veg.(8q/sample) 1-Jan-09 Sr-90 1.184 1.260 -6.0 Acceptable MAPEP-09-RdV20 Veg.(8q/sample) 1-Jan-09 Zn-65 1.52 1.354 12.3 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Am-241 0.506 0.636 -20.4 Warning J MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Cs-134 19.9 22.5 -11.6 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Cs-137 0.045 N/A N/A Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Co-57 18.11 18.9 -4.2 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Co-60 16.58 17.21 -3.7 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 H-3 337 330.9 1.8 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Fe-55 52.1 48.2 8.1 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Mn-54 14.67 14.66 0.1 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Ni-63 43.4 53.5 -18.9 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Pu-238 0.987 1.18 -16.4 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Pu-239/240 0.689 0.853 -19.2 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Sr-90 6.66 7.21 -7.6 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 U-234 2.84 2.77 2.5 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 U-238 2.92 2.88 1.4 Acceptable MAPEP-09-MaW20 Water (8q/L) 1-Jan-09 Zn-65 13.36 13.6 -1.8 Acceptable CR-09-12 was Issued to investigate these negative biases. ~.

CR-09-14 was Issued to investigate these positive biases. CR-

~,

09-13 was issued to investigate this negative bias F:\AOMIN\CORRES\EL 034- 22

TABLE 3 DEPARTMENT OF ENERGY MIXED ANAL YTE PERFORMANCE EVALUATION PROGRAM RESULTS AREVA NP ENVIRONMENTAL LABORATORY Continued REPORTED MAPEP SAMPLE MATRIX! REFERENCE RADIO- MEAN % PERFORMANCE VALUE 10 UNITS DATE NUCLIDE VALUE BIAS EVALUATION Bq/Units Bq/Units MAPEP-09-RdF21 Filter (8q/filter) 1-Jul-09 Cs-134 -0.006 N/A Acceptable MAPEP-09-RdF21 Filter (8q/filter) 1-Jul-09 Cs-137 1.437 1.40 2.6 Acceptable MAPEP-09-RdF21 Filter (8q/filter) 1-Jul-09 Co-57 6.7 6.48 3.4 Acceptable MAPEP-09-RdF21 Filter (8q/filter) 1-Jul-09 Co-60 1.010 1.03 -1.9 Acceptable MAPEP-09-RdF21 Filter (8q/filter) 1-Jul-09 Mn-54 5.77 5.49 5.1 Acceptable MAPEP-09-RdF21 Filter (8q/filter) 1-Jul-09 Zn-65 4.44 3.93 13.0 Acceptable MAPEP-09-MaS21 Soil (8q/kg) 1-Jul-09 Cs-134 1.7 N/A Acceptable MAPEP-09-MaS21 Soil (8q/kg) 1-Jul-09 Cs-137 730 669 9.1 Acceptable MAPEP-09-MaS21 Soil (8q/kg) 1-Jul-09 Co-57 624 586 6.5 Acceptable MAPEP-09-MaS21 Soil (8q/kg) 1-Jul-09 Co-60 342 327 4.6 Acceptable MAPEP-09-MaS21 Soil (8q/kg) 1-Jul-09 Mn-54 880 796 10.6 Acceptable MAPEP-09-MaS21 Soil (8q/kg) 1-Jul-09 K-40 403 375 7.5 Acceptable MAPEP-09-MaS21 Soil (8q/kg) 1-Jul-09 Sr-90 410 455 -9.9 Acceptable MAPEP-09-MaS21 Soil (8q/kg) 1-Jul-09 Zn-65 1328 1178 12.7 Acceptable MAPEP-09-RdV21 Veg.(8q/sample) 1-Jul-09 Cs-134 0.02 N/A Acceptable MAPEP-09-RdV21 Veg.(8q/sample) 1-Jul-09 Cs-137 2.41 2.43 -0.8 Acceptable MAPEP-09-RdV21 Veg.(8q/sample) 1-Jul-09 Co-57 7.63 8.0 -4.6 Acceptable MAPEP-09-RdV21 Veg.(8q/sample) 1-Jul-09 Co-60 2.46 2.57 -4.3 Acceptable MAPEP-09-RdV21 Veg.(8q/sample) 1-Jul-09 Mn-54 7.75 7.9 -1.9 Acceptable MAPEP-09-RdV21 Veg.(8q/sample) 1-Jul-09 Zn-65 -0.10 N/A Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Am-241 0.811 1.04 -22.0 Warning 1 MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Cs-134 28.6 32.2 -11.2 Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Cs-137 40.9 41.2 -0.7 Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Co-57 34.8 36.6 -4.9 Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Co-60 14.67 15.4 -4.7 Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 H-3 585 634.1 -7.7 Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Fe-55 58.9 60.8 -3.1 Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Mn-54 -0.082 N/A Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Ni-63 39.6 44.2 -10.4 Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Pu-238 0.0111 0.018 N/A Acceptable Pu- 1.260 MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 1.64 -23.2 Warning 2 239/240 MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Sr-90 12.06 12.99 -7.2 Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Tc-99 8.89 10 -11.1 Acceptable MAPEP-09-MaW21 Water (8q/L) 1-Jul-09 Zn-65 27.8 26.9 3.3 Acceptable 1 These results are being addressed In conjunction with CR 09-13.

2These results are being addressed in conjunction with CR 09-12.

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TABLE 4 NEW YORK STATE DEPARTMENT OF HEALTH ENVIRONMENTAL LABORATORY APPROVAL PROGRAM PROFICIENCY TEST RESULTS AREVA NP ENVIRONMENTAL LABORATORY REPORTED ELAP ELAP ELAP LOT#i MATRIX! RADIO* PERFORMANCE VALUE VALUE ACCEPTANCE REF. DATE UNITS NUCLIDE EVALUATION pCi/L pCi/L LIMITS ALPBT 226304/07/09 Water pCilL Gross Alpha 31.8 43.7 25.6 - 61.8 Satisfactory ALPBT 226304/07/09 Water pCilL Gross Beta 51.0 49.4 37.3 - 61.5 Satisfactory PWTRIT 226604/07/09 Water pCilL Tritium 13100 14200 12600 - 15800 Satisfactory PWGAMA 2262 04/07/09 Water pCilL Ba-133 56.4 56.2 48.1 - 64.3 Satisfactory PWGAMA 2262 04/07/09 Water pC ilL Cs-134 48.5 49.1 42.2 - 56.0 Satisfactory PWGAMA 2262 04/07/09 Water pC ilL Cs-137 88.3 87.5 78.5 - 96.4 Satisfactory PWGAMA 2262 04/07/09 Water pCilL Co-60 101 107 97.3 -117 Satisfactory PWGAMA 2262 04/07/09 Water pCilL Zn-65 312 318 282 - 354 Satisfactory PWIODINE 2264 4/07/09 Water pC ilL 1-131 21.8 23.0 18.9-27.2 Satisfactory REPORTED ELAP ELAP ELAP LOT#/ MATRIX! RADIO- PERFORMANCE VALUE VALUE ACCEPTANCE REF. DATE UNITS NUCLIDE EVALUATION pCi/L pCi/L LIMITS ALPBT 276309/29/09 Water pCilL Gross Alpha 28.0 39.2 22.8 - 55.6 Satisfactory ALPBT 276309/29/09 Water pCilL Gross Beta 35.1 31.2 21.6 - 40.9 Satisfactory PWTRIT 2766 09/29/09 Water pCilL Tritium 19600 20800 18500 - 23100 Satisfactory PWGAMA 2762 09/29/09 Water pCilL Ba-133 23.9 26.5 21.4 - 31.5 Satisfactory PWGAMA 2762 09/29/09 Water pCilL Cs-134 71.2 69.7 60.7 - 78.7 Satisfactory PWGAMA 2762 09/29/09 Water pCilL Cs-137 159 173 158 -188 Satisfactory PWGAMA 2762 09/29/09 Water pCilL Co-60 63.2 66.8 59.8 - 73.8 Satisfactory PWGAMA 2762 09/29/09 Water pCilL Zn-65 154 171 150 -192 Satisfactory PWIODINE 2764 09/29/09 Water pC ilL 1-131 14.5 15.1 12.0 - 18.2 Satisfactory F:\AOMIN\CORRES\EL 034-10 24

TABLE 5 AREVA NP ENVIRONMENTAL LABORATORY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

INTRA-LABORATORY ENVIRONMENTAL PROCESS CONTROL RESULTS BY ACCEPTANCE CRITERIA, MEDIA, AND ANALYSIS CATEGORIES JANUARY - DECEMBER 2009 Bias Criteria (1) Precision Criteria (1), (2)

WITHIN OUTSIDE WITHIN OUTSIDE CRITERIA CRITERIA CRITERIA CRITERIA I. Air Particulate Gross Beta 255 0 0 0 II. Air Charcoal Gamma-Quantitative 156 0 0 0 III. Food (Aquatic/Terrestrial)

Gamma 0 0 16 0 Sr-90 0 0 4 0 IV. Milk Gamma 0 0 0 0 Iodine (ll) 3 0 3 0 Sr-89 0 0 0 0 Sr-90 0 0 0 0 V. Soil/Sed.

Gamma 0 0 0 0 Sr-90 0 0 0 0 H-3 0 0 6 0 VI. Vegetation (Aquatic/Terrestrial)

Gamma 0 0 0 0 Iodine (ll) 0 0 0 0 VII. Water Gross Alpha 5 1 8 0 Gross Beta 6 0 10 2 Gamma 26 0 56 2 Iodine (ll) 0 0 0 2 Sr-89 0 0 0 0 Sr-90 3 0 0 0 Tritium 23 0 24 0 Total Number In Range: 477 1 127 6 Percentage of Total Processed 99.8 0.2 95.5 4.5 Sum of Analyses: 478 133 (1) Bias and PrecIsion as noted In Table 1, (2) Some PrecIsion data generated from non-positive client samples for specific contractual eval uations.

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TABLE 6 AREVA NP ENVIRONMENTAL LABORATORY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

INTRA-LABORATORY AND INTER-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY MEDIA JANUARY - DECEMBER 2009 Bias Criteria (1) Precision Criteria (1), (2)

WITHIN OUTSIDE WITHIN OUTSIDE CRITERIA CRITERIA CRITERIA CRITERIA I. Air Particulate Gross Alpha 11 1 12 0 Gross Beta 267 0 12 0 Gamma 54 0 87 0 Sr-90 0 0 2 0 II. Air Charcoal Gamma-Quantitative 168 0 12 0 III. Food (Aquatic/Terrestrial)

Gamma 0 0 16 0 Sr-90 0 0 4 0 IV. Milk Gamma 120 0 120 0 Iodine (ll) 15 0 15 0 Sr-89 6 0 6 0 Sr-90 6 0 6 0 V. Soil/Sed.

Gamma 0 0 36 0 Sr-90 0 0 5 0 H-3 0 0 6 0 VI. Vegetation (Aquatic/Terrestrial)

Gamma 0 0 27 0 Iodine ell) 0 0 0 0 Sr-90 0 0 3 0 VII. Water Gross Alpha 14 4 20 0 Gross Beta 18 0 22 2 Gamma 144 2 205 3 Iodine (ll) 12 0 12 2 Sr-89 12 0 12 0 Sr-90 15 0 16 0 Tritium 35 0 42 0 Total Number In Range: 897 7 698 7 Percentage of Total Processed 99.2 0.8 99.0 1.0 Sum of Analyses: 904 705 (1) Bias and PrecIsion as noted m Table 1. (2) Data mcludes mtra-Iaboratory and Analytlcs cross-checks evaluated for accuracy and precision and MAPEP samples evaluated for precision only.

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TABLE 7 AREVA NP ENVIRONMENTAL LABORATORY ADDITIONAL ENVIRONMENTAL ANALYSES INTRA-LABORATORY AND INTER-LABORATORY BIAS AND PRECISION BY ANALYSIS TYPE JANUARY - DECEMBER 2009 Bias Criteria (1) Precision Criteria (1), (2)

WITHIN OUTSIDE WITHIN OUTSIDE CRITERIA CRITERIA CRITERIA CRITERIA I. Am-241 Filter 0 0 2 0 Soil 0 0 0 0 Water 0 0 4 0 II. C-14 Soil 0 0 6 0 Water 3 0 0 0 III. Fe-55 Water 3 0 5 0 IV. Ni-63 Water 3 0 5 0 V. Pu-238 Filter 0 0 2 0 Soil 0 0 0 0 Water 0 0 4 0 VI. Pu-239 Filter 0 0 2 0 Soil 0 0 0 0 Water 0 0 4 0 VI. Ra-226 Water 2 0 4 0 VII. Ra-228 Water 2 0 4 0 VIII. Tc-99 Water 0 0 2 0 IX. Th-230 Water 1 1 4 0 X. U-234 Water 2 0 6 0 XI. U-238 Water 2 0 6 0 Total Number In Range: 18 1 60 0 Percentage of Total Processed 94.7 5.3 100 0 Sum of Analyses: 19 60 (1) Bias and PrecIsion as noted m Table 1. (2) Data mcludes mtra-Iaboratory and Analytlcs cross-checks evaluated for accuracy and precision and MAPEP samples evaluated for precision only.

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TABLE 8 AREVA NP ENVIRONMENTAL LABORATORY ALL ENVIRONMENTAL ANALYSES INTRA-LABORATORY AND INTER-LABORATORY BIAS AND PRECISION BY ANALYSIS TYPE JANUARY - DECEMBER 2009 Bias Criteria (1) Precision Criteria (1), (2)

WITHIN OUTSIDE WITHIN OUTSIDE CRITERIA CRITERIA CRITERIA CRITERIA I. Gross Alpha Air Filter 11 1 12 0 Water 14 4 20 0 II. Gross Beta Air Filter 267 0 12 0 Water 18 0 22 2 III. Gamma Air Filter 54 0 87 0 Charcoal-Quantitative 168 0 12 0 Food 0 0 16 0 Milk 120 0 120 0 Soil/Sediment 0 0 36 0 Vegetation 0 0 27 0 Water 144 2 205 3 IV. Iodine (LL)

Milk 15 0 15 0 Vegetation 0 0 0 0 Water 12 0 12 2 V. Sr-89 Milk 6 0 6 0 Water 12 0 12 0 VI. Sr-90 Air Filter 0 0 2 0 Food 0 0 4 0 Milk 6 0 6 0 Soil/Sediment 0 0 5 0 Vegetation 0 0 3 0 Water 15 0 16 0 VII. Tritium Soil 0 0 6 0 Water 35 0 42 0 F:\AOMIN\CORRES\EL 034- 28

TABLE 8 AREVA NP ENVIRONMENTAL LABORATORY ALL ENVIRONMENTAL ANALYSES INTRA-LABORATORY AND INTER-LABORATORY BIAS AND PRECISION BY ANALYSIS TYPE JANUARY - DECEMBER 2009 Continued Bias Criteria (1) Precision Criteria (1), (2)

WITHIN OUTSIDE WITHIN OUTSIDE CRITERIA CRITERIA CRITERIA CRITERIA VII. Am-241 Filter 0 0 2 0 Soil 0 0 0 0 Water 0 0 4 0 IX. C-14 Soil 0 0 6 0 Water 3 0 0 0 X. Fe-55 Water 3 0 5 0 XI. Ni-63 Water 3 0 5 0 XII. Pu-238 Filter 0 0 2 0 Soil 0 0 0 0 Water 0 0 4 0 XIII. Pu-239 Filter 0 0 2 0 Soil 0 0 0 0 Water 0 0 4 0 XIV. Ra-226 Water 2 0 4 0 XV. Ra-228 Water 2 0 4 0 XVI. Tc-99 Water 0 0 2 0 XVII. Th-230 Water 1 1 4 0 XVIII. U-234 Water 2 0 6 0 XIX. U-238 Water 2 0 6 0 Total Number In Range: 915 8 758 7 Percentage of Total Processed 99.1 0.9 99.1 0.9 Sum of Analyses: 923 765 F:\AOMIN\CORRES\EL 034- 29

TABLE 9 AREVA NP ENVIRONMENTAL LABORATORY ENVIRONMENTAL BIAS AND PRECISION BY YEAR Bias Precision Deviation from Known Deviation from Mean Bias Criteria (1) Precision Criteria (2)

Within # Outside % Within # Within # Outside % Within Year Criteria Criteria Criteria Criteria Criteria Criteria 2009 915 8 99.1 758 7 99.1 2008 1125 41 96.5 841 15 98.2 2007 798 17 97.9 488 1 99.8 2006 689 5 99.3 589 2 99.7 2005 1069 3 99.7 507 0 100.0 2004 1294 10 99.2 862 2 99.8 2003 828 13 98.5 515 1 99.8 2002 863 7 99.2 471 3 99.4 2001 578 22 96.3 394 2 99.5 2000 574 18 97.0 448 1 99.8 1999 467 13 97.3 357 2 99.4 1998 496 7 98.6 432 4 99.1 1997 515 11 97.9 363 0 100.0 1996 907 24 97.4 800 3 99.6 1995 403 12 97.1 267 0 100.0 1994 529 14 97.4 336 1 99.7 1993 443 29 93.9 312 1 99.7 1992 728 21 97.2 797 1 99.9 1991 770 19 97.6 822 4 99.5 1990 728 34 95.5 761 2 99.7 1989 689 28 96.1 710 4 99.4 1988 632 22 96.6 632 1 99.8 1987 702 27 96.3 718 3 99.6 1986 813 27 96.8 815 0 100.0 1985 718 25 96.6 682 0 100.0 1984 837 31 96.4 850 0 100.0 1983 794 36 95.7 798 4 99.5 1982 585 30 95.1 743 12 98.4 1981 443 29 93.9 404 1 99.8 1980 442 37 92.3 490 1 99.8 1979 199 20 90.9 354 16 95.7 1978 242 20 92.4 361 14 96.3 1977 58 8 87.9 119 7 94.4 Total # in Range: 21,873 668 97.0 18,796 115 99.4

%in Range 97.0 3.0 99.4 0.6 Total Number 22,541 18,911 (1) Bias as noted In Table 1, (2) PrecIsion as noted In Table 1.

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TABLE 10 PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED E-LAB INTERNAL CRITERIA JANUARY - DECEMBER 2009(1), (2)

Number % Passed Precision Dosimeter Type % Passed Bias Criteria Tested Criteria Panasonic 84 100 100 Environmental (1)This table summarizes results of tests conducted by E-LAB and the Third-party tester.

(2)Environmental dosimeter results are free in air.

TABLE 11

SUMMARY

OF THIRD PARTY DOSIMETER TESTING JANUARY - DECEMBER 2009(1), (2)

Exposure Dosimeter Type ANSI Category % (Bias +/- SO)'"

Period Panasonic Environmental FH 2009 II 8.1 +/- 2.0 SH 2009 II -1.8 +/- 2.5 (1)Performance criteria are the same as the internal criteria.

(2)Results are expressed as the delivered exposure for environmental TLD. ANSI HPS N13.29-1995 (Draft) Category II, High energy photons (Cs-137 or Co-60).

TABLE 12 PERCENTAGE OF MEAN DOSIMETER ANALYSES (N=6) WHICH PASSED TOLERANCE CRITERIA JANUARY - DECEMBER 2009(1), (2)

% Passed Number of Dosimeter Type Tolerance Evaluations Limit Panasonic 14 100 Environmental(2)

(1)This table summarizes results of tests conducted by E-LAB and the Third-party tester.

(2)Environmental dosimeter results are free in air.

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TABLE 13 AREVA NP ENVIRONMENTAL LABORATORY CONDITION REPORT (CR) STATUS JANUARY - DECEMBER 2009 (OPEN) (CLOSED)

CR# INITIATION CLOSE-OUT DESCRIPTION STATUS AS OF 12/31/09 DATE DATE CLOSED-The paperwork was checked for errors, the sample was recounted, and a new alpha filter was used to calibrate the alpha/beta system. None of these actions produced a reason found for the failure. Two subsequent sets of Analytics filters were acceptable. Since the precision for the failed filters was <

3rd qtr. 2007 Analytics 5% over time and among different calibrations, it appears that environmental cross CR 08-01 23-Jan-08 23-Mar-09 variability in the preparation of the filters themselves may be the check filters failed bias cause of the failures. Prior to 2003, the bias and precision criteria for gross alpha acceptance criteria for gross alpha on a filter were +/- 25%.

Assuming that variability in either the absorption or source distribution of the filters is responsible for the variation in the observed accuracy, LQARC approved a change in the criteria to +/- 25.

CLOSED- Updated QC summary reports containing results with accurate decay corrections were sent to clients as required. E-Decay correction errors Lab Procedure 790, Laboratory Batch Quality Control Handling, CR 08-09 07- Mar-08 19-May-09 on past QC Summary was created to formalize the required steps to create an Report. accurate QC Summary Report. The signatures of the preparer and an independent reviewer are now required on QC Summary Reports.

CLOSED - These QC samples contain Ba-133 to approximate an energy close to 1-131. The samples were counted on the manual germanium detectors instead of the automatic sample changer. The sample geometry on these detectors is more The mean of three sensitive to summing than the changer. Ba-133 summing consecutive charcoal CR 08-23 22-Jul-08 25-Mar-09 corrections have been determined for each manual detector.

PCs failed the accuracy Charcoal cartridges containing Ba-133 and counted on the criterion manual detectors have been corrected for summing. All Ba-133 corrected data is within the acceptance criteria. There is no effect on client charcoal cartridges which are analyzed for 1-131 concentration.

CLOSED - The gamma spectrometry analysis report was found to be missing the Zr-95 result when greater than 29 nuclides Zr-95 missing from CR 08-30 15-0ct-08 22-Apr-09 are reported. Sixty-nine reports for five clients were affected.

analysis report Updated reports were sent to clients. A multi-page report was developed and approved for use on 04/14/2009.

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TABLE 13 AREVA NP ENVIRONMENTAL LABORATORY CONDITION REPORT (CR) STATUS JANUARY - DECEMBER 2009 (Continued)

(OPEN) (CLOSED)

CR# INITIATION CLOSE-OUT DESCRI PTION STA TUS AS OF 12/31109 DATE DATE CLOSED - The investigation indicated that either the duplicate was not the same sample as the original or that severe settling occurred in the sample container. The reason could not be verified since the original sample had been discarded. In the future, samples will be labeled to ensure that they are not Gross beta analysis of a discarded until the duplicate evaluation is complete. Also, water sample failed the CR 08-36 4-Nov-08 26-Mar-09 because decay correction is not applied to gross beta analyses, Manual 100 criteria for duplicates for this analysis will be submitted simultaneously.

duplicates Training was conducted and the entire laboratory staff was counseled to ensure that water samples are shaken vigorously and the analysis aliquot is taken immediately after shaking, and to ensure that sample labels are double-checked when retrieving samples for analysis.

CLOSED - All spectra associated with the two MAPEP water samples were reviewed, and no improvement was noted in the peak start/stop selection by the analyst. Multiple counts were performed using different detectors and were analyzed by different people. All of the stored spectra provide virtually identical results for Pu-238. The problem does not lie with the instrumentation or the analyst's selection of peak regions.

Four sample aliquots were subsequently submitted for the MAPEP Series 19 Pu- MAPEP 21 water. The first two were processed using standard 238 in water fell into the environmental methods the third and fourth were processed CR 08-38 18-Nov-08 21-Dec-09 warning category with a using a sample fusion preparatory step. This was performed to

-28.6% bias determine if the oxidation state of the plutonium provided by MAPEP was not being converted completely during the process. There appears to be no benefit in modifying the preparation method as the bias for all samples remains consistently at (-20-25%). MAPEP Series 21 samples contai ned both Am-241 and Pu-239/240 and were reported with

-22.0% and -23.2% biases. Continued problems with environmental transuranic analysis required a new Condition Report. This CR was closed and further investigation into the negative bias will be documented in CR 09-33.

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TABLE 13 AREVA NP ENVIRONMENTAL LABORATORY CONDITION REPORT (CR) STATUS JANUARY - DECEMBER 2009 (Continued)

(OPEN) (CLOSED)

CR# INITIATION CLOSE-OUT DESCRI PTION STA TUS AS OF 12/31109 DATE DATE CLOSED - The MAPEP AP filter was counted 3 times on the same gamma detector. Background spectra, with and without a sample holder were reviewed and no Co-60 was detected. All 3 counts of the MAPEP filter identified the 1173 peak and 2 identified the 1332 peak. The root cause appears to be the low uncertainty reported by the E-LAB. Only one of 42 other Labs MAPEP Series 19 Co-60 reported a lower uncertainty than AREVA, and this Lab also on a filter fell into the not failed the test. The distribution of results reported by the CR 08-39 18-Nov-08 26-Mar-09 acceptable category due various participants showed that ten Labs reported results to reporting a false between 0.02 and 0.03 Bq, the highest frequency. However, positive result. the uncertainties reported by these Labs were sufficiently large that they passed the false positive test. Since the distribution of reported results centers roughly around the value reported by the E-Lab, and since Co-57 was also present on the filter at a concentration of 1.5 Bq, it appears that the source of the Co-60 found on the filter could be a contaminant in the Co-57 source used rather than contamination obtained at the E-LAB.

CLOSED - The root cause of this QC failure was not determined conclusively. It appears that a low-level MAPEP Series 19 Sr-90 contaminant bled through the separation columns on only one in soil was a false of the strontium-90 samples and due to the low activity level, positive test. No result cannot be positively identified. The second analysis result was CR 08-40 18-Nov-08 21-Dec-09 was reported by the within the acceptance criteria of the MAPEP program as a false AREVA Lab due to positive check. However, due to the inconsistency, neither inconsistent results val ue could be reported. The previous MAPEP test, series 18, (positive and negative).

had a successful Sr-90 in soil test with a bias of -7.3% and the subsequent MAPEP test, series 20, had a bias of -2.7%.

CLOSED - A new chemist, recently trained to perform sample Gamma spectrometry preparation did not specify the correct geometry in LlMS. This results generated using chemist also performed the gamma spectrometry analyses and CR 08-41 26-Nov-08 26-Mar-09 incorrect efficiency files did not identify the error. All affected results were updated and were reported to three reissued. The chemist was counseled and retrained on proper customers. geometry selection. Finally, the software was revised to make it easier for a reviewer to identify similar errors.

CLOSED - The filter was retrieved prior to disposal in its original bag which was inside a larger bag containing empty filter bags One client AP sample from another client. A designated storage area for air filters and CR 08-42 17-Dec-08 26-Mar-09 was inadvertently thrown other small samples separate from the sample preparation area in the trash.

was established. The sample control staff was counseled concerning proper sample handling.

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TABLE 13 AREVA NP ENVIRONMENTAL LABORATORY CONDITION REPORT (CR) STATUS JANUARY - DECEMBER 2009 (Continued)

(OPEN) (CLOSED)

CR# INITIATION CLOSE-OUT DESCRI PTION STA TUS AS OF 12/31109 DATE DATE CLOSED - The U-232 tracer was assigned the original certificate value, not the concentration obtained from the verification analysis. The LI MS data were reviewed to ensure that the correct tracer concentration was recorded. Procedures U-232 tracer verification, 720 and 730 were revised to allow for broader verification limits YA942324-A was outside for tracers requiring radiochemical processing as part of the CR OS-43 17-Dec-OS 07-Jul-09 the limits of Procedure verification. No client results required updating since 730. recalculation of analysis results for the change in the tracer known value would result in a change in the reported value of less than 1/3 of the acceptance criteria for the analysis. A similar situation for Th-229 tracer, discovered during the investigation of this CR was similarly corrected.

CLOSED - No errors were identified with either the chemistry data or the source certificates. The cause of the failure was investigated in conjunction with CR 09-04, which involved Fourth Qtr 200S P61 Fe- another process check failure for Fe-55. No definitive cause for 55 Process Checks failed the failures was determined. In order to ensure accuracy of CR 09-02 20-Jan-09 07-Aug-09 Manual 100 criteria for client results, the senior radiochemist is performing Fe-55 precision analyses for all Part 50 and Part 61 samples. The process will be closely monitored to see if any procedural steps need enhancement. In addition, an Fe-55 spike will continue to be processed with each batch of samples.

CLOSED - The samples were reprocessed from the container submitted for the process checks and from the master stock Q1-2009 Fe-55 P61 PC CR 09-04 1S-Feb-09 25-Aug-09 solution. Both sets passed the Manual 100 accuracy criterion.

failed with high bias.

Corrective actions are the same as those documented for CR 09-02.

The gross beta count rates for a few environmental water CLOSED - Based upon the analysis of six duplicate samples, samples were measured the omission of Step B.2.g did not have a significant effect on to be higher than the gross beta activity determination. Procedure 320 was expected. Recounts of revised to add a hold time between sample preparation and these samples over a 24 CR 09-06 24-Mar-09 14-Apr-09 analysis and to clarify the use of a desiccator to store the hour period showed a samples. No change was made to the requirement to dry the significant decrease in samples in the oven (Step B.2.g). Analysts were retrained on the gross beta count Procedure 320 and the necessity of adhering to the written rates for some samples.

procedures.

A review of Procedure 320 revealed that Step B.2.g was not performed.

CLOSED - The spreadsheet was revised, documented, and a Ra-224 decay correction V&V was performed, to allow for Ra-224 decay using this should use Th-22S from CR 09-10 11-May-09 OS-Jul-09 option. E-Lab radium procedures were revised to incorporate sample collection to this Ra-224 decay correction, and worksheets were revised to radium separation step allow chemists to record the radium separation time.

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TABLE 13 AREVA NP ENVIRONMENTAL LABORATORY CONDITION REPORT (CR) STATUS JANUARY - DECEMBER 2009 (Continued)

(OPEN) (CLOSED)

CR# INITIATION CLOSE-OUT DESCRI PTION STA TUS AS OF 12/31109 DATE DATE Ra-228 samples have CLOSED - E-Lab Procedure 305 was revised to incorporate precipitate which may be additional steps, if required, to allow the Chemist to perform and CR 09-11 22-May-09 07-Aug-09 causing unusual matrix document changes or additional steps taken to dissolve the spike results and solids.

incorrect recovery values OPEN - The MAPEP Series 21 filter was processed by the Part61 chemist with acceptable results. The apparent cause of MAPEP Series 20 Pu-the Series 20 failure is a small container of tracer, stored in the 238 and Pu-239/240 on a environmental chemistry lab., that may have concentrated over filter fell into the warning CR 09-12 08-Jun-09 time. To verify this, an aliquot of MAPEP 21 water (which also category with mean showed a low bias for Pu) is being reanalyzed in the biases of -20.9% and -

environmental chemistry lab., using the Part 61 tracer. There is 20.6%, respectively.

no impact on client results, as the E-Lab does not process any environmental samples for transuranic analysis.

OPEN - The apparent cause of the Series 20 failure is a small container of tracer, stored in the environmental chemistry lab.,

MAPEP Series 20 Am- that may have concentrated over time. To verify this, an aliquot 241 in water fell into the of MAPEP 21 water (which also showed a low bias for Am-241)

CR 09-13 08-Jun-09 warning category with a is being reanalyzed in the environmental chemistry lab., using mean bias of -20.4%. the Part 61 tracer. There is no impact on client results, as the E-Lab does not process any environmental samples for transuranic analysis.

CLOSED - It was determined that, due to the extremely fine MAPEP Series 20 nature of the soil particles, the material settled over time to a Gamma in soil fell into more compact geometry than the calibration height. A recount the warning and "not of the sample with additional soil added to reach the calibrated CR 09-14 08-Jun-09 03-Sep-09 acceptable" categories geometry produced results that were within 10% of the MAPEP with mean biases for values for all nuclides. The sample preparation technician was several nuclides ranging trained on techniques specific to soil samples with very fine from +24% to +31 %.

granules.

CLOSED - Review of the analysis report code revealed that the sample receipt date on the report was pulled from the sample reference date field in the LI MS database. Further review confirmed that all other data was correct. This incorrect Gamma spectrometry database link occurred during a revision to the report. The analysis reports sent out CR 09-15 09-Jun-09 01-JUL-09 analysis report has been revised and all affected reports were with incorrect sample updated and sent to clients. The QA officer counseled the receipt date.

programmer and the reviewer on the importance of verifying the accuracy of all data appearing on a report, form, or screen, whenever a change is made, in accordance with Procedure 600.

F:\AOMIN\CORRES\EL 034- 36

TABLE 13 AREVA NP ENVIRONMENTAL LABORATORY CONDITION REPORT (CR) STATUS JANUARY - DECEMBER 2009 (Continued)

(OPEN) (CLOSED)

CR# INITIATION CLOSE-OUT DESCRI PTION STA TUS AS OF 12/31109 DATE DATE CLOSED - Fe-55 and Ni-63 weight and recovery calculations were performed differently depending on whether the LlMS calculations were used or the worksheet was used. The Discrepancies in discrepancy is a result of accounting for the recovery aliquot in CR 09-18 30-Jun-09 21-Dec-09 Procedure 365 two different, but equally valid ways. There is no impact on customer results since the final calculated concentrations of Fe-55 and Ni-63 are the same using both methods. For clarity, the calculations were removed from the worksheet.

CLOSED - The same chemist prepared the second quarter cross-check samples for gross alpha analysis while being First Qtr 2009 Analytics observed by a senior chemist. The second quarter results were environmental water -3.2% from the known value. The senior chemist observed the cross-check failed processing chemist prepare another aliquot of the first qtr.

CR 09-21 20-Jul-09 29-Dec-09 Manual 100 accuracy cross-check water and also the third qtr. samples. The gross criteria for gross alpha alpha reanalysis results showed biases within Manual 100 analysis. criteria. Corrective actions included instructing the processing chemist to take her time and increase the rinses and policing performed for gross alpha\beta analysis of water samples.

CLOSED - The "TPU 1-Sigma" heading on the report was inappropriately changed to "TPU 2-Sigma" for some clients during the last revision of the analysis report routine. The incorrect TPU header occurred because the programmer didn't Typographical error realize that the analysis reports include the TPU results identified on calculated at 1-sigma despite the counting uncertainty value CR 09-22 23-Jul-09 17-Nov-09 environmental gamma requested by the customer. Originally, the V&V of the revision spectrometry analysis to the report did not consist of a test of all of the special cases report. of the report. All affected clients were contacted, and updated reports were issued. Procedure 600 was revised to require that all permutations of a revised software product are tested. In addition, the testing must be reviewed by two independent people who are knowledgeable of the required specifications.

OPEN - One action item resulting from Internal Assessment 08-02, on Source Preparation, remains open. The verification attem pt on the Th-230 secondary standard 9414-C was outside Corrective Actions from the Procedure 720 criterion. A new standard was received from CR 09-24 13-Aug-09 Internal Assessment 08-NIST and has been verified. The old standard was used only to 02, Source Preparation prepare matrix spikes and control spikes for select clients. The impact of using this source after the verification due date is being evaluated.

F:\AOMIN\CORRES\EL 034- 37

TABLE 13 AREVA NP ENVIRONMENTAL LABORATORY CONDITION REPORT (CR) STATUS JANUARY - DECEMBER 2009 (Continued)

(OPEN) (CLOSED)

CR# INITIATION CLOSE-OUT DESCRI PTION STA TUS AS OF 12/31109 DATE DATE OPEN - The AREVA IS department immediately limited access to "read-only" for all but a limited number of employees During the 2009 designated by the Lab Manager. Procedure and manual files in EXELON audit, the E- the E-Lab library directory were compared to those stored in the Lab file server directory corporate document storage system. All of the documents in CR 09-26 13-Aug-09 containing E-Lab the E-Lab library directory were identical to the controlled manuals and procedures copies in the corporate system, for the items compared. Other did not have security directories requiring security controls were identified and set to controls "read-only". The E-Lab has monitored these directories to assure that controls remain in place, and will continue to monitor them quarterly. This CR is ready to close.

CLOSED - The root cause of the missed five-year review was that it was never added to the "Next Review Date" index for procedures. This is a second index maintained in addition to The five-year review for regular procedure index. The "Next Review Date" indices were Procedure 466 was eliminated, and the Procedure and Manual indices were revised CR 09-28 02-0ct-09 22-Dec-09 missed and the Manual to allow sorting by "Next Review Date". The project Index listed the wrong administrator was counseled on the requirement to make sure revision for Manual 100. that all dates are updated when issuing a revised procedure or manual index. In addition, Procedure 010, was revised to incorporate all of the steps required to revise and issue a procedure or manual.

OPEN - The reference date used to calculate the 1st Quarter Analytics Environmental cross-check samples was in error by First quarter Analytics one day. There is no impact on client results, as the changes in environmental cross-CR 09-29 22-0ct-09 concentrations are not sufficient to cause any of the analyses to check reference date was fail the Manual 100 accuracy criteria. All results are being in error by one day.

updated, however, and are discussed in the 2009 annual quality assurance report.

OPEN - The apparent causes were determined to be an Client EDD file had unsatisfactory turnaround time for independent review of the CR 09-30 22-0ct-09 incorrect sample receipt completed receipt paperwork, and lack of management date notification of the error so that it could be corrected on the analysis report and in the EDD. Corrective actions are pending.

OPEN - A single spiked water sample, containing 3 One of 5 gamma radionuclides, was used as a gamma instrumentation qualification samples qualification sample. The sample was counted five times, and CR 09-31 30-NOV-09 failed Manual 100 the results of one count failed the Manual 100 accuracy criteria accuracy criteria for all 3 for all three nuclides. The reason for the failure is under nuclides investigation.

OPEN - The client sample in question was an analytical blank.

A review of all projects requiring batch QC was performed. The H-3 MDC for one client required MDCs for the blanks were not listed on the analysis CR 09-33 21-Dec-09 sample not <400pCi/L reports for all projects, however, the analysis reports do not need to be updated as the required MDCs were met for the blanks. Corrective actions are pending.

F:\AOMIN\CORRES\EL 034- 38

TABLE 14 UPDATED INSTRUMENTATION/ANALYTICAL PROCEDURES RELEVANT TO ENVIRONMENTAL SAMPLE ANALYSIS AND ENVIRONMENTAL DOSIMETRY ISSUED DURING JANUARY - DECEMBER 2009 PROCEDURE REVISION EFFECTIVE TITLE

SUMMARY

OF REVISION NUMBER NUMBER DATE Updated disposal discussions to place Part 50 sample disposal under LlMS control. Added verification of disposal Sample Storage and 120 20 09/30/09 methods by CHO/Haz Waste personnel.

Accountability Clarified storage of Part 50/61 liquid scintillation vials. Deleted sewerage disposal option. Added a reference.

Minor editorial changes. Slight changes Preparation of to order of steps for ease of processing.

Environmental and Eliminated duplication in several 305 Bioassay Media for 24 08/10/09 sections. Added a new 0.5 L Marinelli Analysis of beaker geometry. Updated Ra-228 Gamma Ray Emitters preparation and counting sections for CR 09-11.

Preparation and Analysis of Environmental Water Minor editorial changes. Added ability to and modify non-EPA drinking water hold 320 27 09/15/09 Soil/Sediment/Sludge times if a client requested it and Samples for Gross management approved.

Alpha and/or Gross Beta Radioactivity The Determination of Minor editorial changes. Section A.1 lodine-131 in Vegetation /Food Crops sample Environmental Media 340 30 11/30/09 preparation steps were revised to Using Anion incorporate enhancements made to the Exchange procedure.

Chromatography Reagents section: 15. Nickel carrier-replaced "preparation of with The Determination of "commercially available solution".

55Fe, 63Ni, 89, 9O S r, 24. Strontium tracer values were 241Am, 242Cm, changed from "5,000 - 10,000 dpm/ml,"

365 243/244 Cm and 238pU, 16 11/25/09 to "5,000 - 20,000 dpm/mL". The sample 239/240pU, 241pU in fraction volume taken for ICP analysis Environmental and was clarified for Fe-55 and Ni-63.

Bioassay Matrices Weight notations in the procedure and FORMS were deleted to conform to the LlMS process.

F:\AOMIN\CORRES\EL 034-10 39

TABLE 14 UPDATED INSTRUMENTATION/ANALYTICAL PROCEDURES RELEVANT TO ENVIRONMENTAL SAMPLE ANALYSIS AND ENVIRONMENTAL DOSIMETRY ISSUED DURING JANUARY - DECEMBER 2009 (Continued)

PROCEDURE REVISION EFFECTIVE TITLE

SUMMARY

OF REVISION NUMBER NUMBER DATE Changed 3M HN03 to 8M as necessary in various sections of the procedure.

Changed the amount of3% EDTA rinse The Determination of solution to 1OOOmL for a 2000g milk Sr-89,90 in sample. The soil method (Strong Acid 368 Environmental Media 13 11/20109 Leach) section of the procedure was Via Cerenkov changed to reflect the method that elicits Counting the best recovery for a majority of the soil samples routinely processed. The flow chart was corrected to reflect procedural changes.

Precaution number 5 in the previous revision erroneously stated that Ra-224 may be in equilibrium with Th232. This The Determination of revision corrects "Th-232" to "Th-228" as 382 Radium Isotopes In 5 07/10109 this is the correct parent\daughter Bioassay Matrices equilibrium condition for Ra-224. No changes were required of the software as the decay correction calculation correctly uses the Th-228 half-life.

Precaution number 5 in the previous revision erroneously stated that Ra-224 The Determination of may be in equilibrium with Th232. This Radium Isotopes in revision corrects "Th-232" to "Th-228" as 385 Environmental 8 07/10109 this is the correct parent\daughter Matrices by Alpha equilibrium condition for Ra-224. No Spectrometry changes were required of the software as the decay correction calculation correctly uses the Th-228 half-life.

Precaution number 5 in the previous The Sequential revision erroneously stated that Ra-224 Determination of may be in equilibrium with Th232. This Isotopic Uranium, revision corrects "Th-232" to "Th-228" as 395 Thorium and Radium 5 07/10109 this is the correct parent\daughter in Environmental equilibrium condition for Ra-224. No Matrices by Alpha changes were required of the software as Spectrometry the decay correction calculation correctly uses the Th-228 half-life.

Operation and Calibration of the Revised to add the correct AREVA NP 430 Beta-Gamma 15 05/25/09 Protection of Proprietary Information Coincidence Units for statement.

1-131 Development, Step E.7 was revised to require the Documentation, analyst to ensure that all possible 600 13 11/02/09 Verification, and permutations of the end product are Validation of tested, and to require that two F:\AOMIN\CORRES\EL 034- 40

TABLE 14 UPDATED INSTRUMENTATION/ANALYTICAL PROCEDURES RELEVANT TO ENVIRONMENTAL SAMPLE ANALYSIS AND ENVIRONMENTAL DOSIMETRY ISSUED DURING JANUARY - DECEMBER 2009 (Continued)

PROCEDURE REVISION EFFECTIVE TITLE

SUMMARY

OF REVISION NUMBER NUMBER DATE Computer Software independent people knowledgeable of the required specifications review the V&V. Quality impact: This change will significantly improve the V&V process.

Minor editorial changes. Added a Report Generation 692 4 09/29/09 reference. Added a description of Using LlMS sample disposal reports.

Modified the equipment history section to permit use of a FORM or logbook.

Quality Control of Modified the FORM for ease of use.

710 Laboratory 20 08/06/09 Added dosimetry references and Instrumentation descriptions of calibration, QC and maintenance. Updated the liquid scintillation backQround statements.

Reformatted the entire procedure for ease of use. Added a reference for 8eta-Gamma counter QC. Modified the 8eta-Preparation of 715 21 07/14/09 Gamma QC limit to 6% based on the Tolerance Charts newly added Reference. Specified that the 1-sigma value be compared to the 1% value for nuclear instruments.

Verification criteria for radioactive standards and source matrices were revised. Source verification forms were Preparation of added to enable better documentation of Radioactive 720 21 06/18/09 prepared sources. Process check Standards and solutions with the exception of C-14 shall Source Matrices be valid for two years. Quality impact:

enhanced due to non-ambiguity and better documentation.

Preparation and Verification criteria for stable carriers and Verification of 730 23 06/15/09 radiotracers were revised to ensure Carriers and consistency with procedure 720.

Radiotracers Good Laboratory 755 0 07/07/09 New procedure created.

Practices Revised the procedure to reflect the new Guidelines for deionized water systems installed in the Maintaining the ELGA 765 4 05/18/09 environmental & part 50/61 lab areas.

MEDICA 15 Water Quality Impact: enhanced due to state of Systems the art water quality.

F:\AOMIN\CORRES\EL 034- 41

TABLE 14 UPDATED INSTRUMENTATION/ANALYTICAL PROCEDURES RELEVANT TO ENVIRONMENTAL SAMPLE ANALYSIS AND ENVIRONMENTAL DOSIMETRY ISSUED DURING JANUARY - DECEMBER 2009 (Continued)

PROCEDURE REVISION EFFECTIVE TITLE

SUMMARY

OF REVISION NUMBER NUMBER DATE Duplicate sample submittal steps were added to indicate when duplicate samples should be analyzed at the same time as the reference samples. Sample preparation steps were added for MAPEP soil and vegetation samples. A step was added to require that internal assessment Laboratory Quality reports be issued within 30 days of 770 Assurance and 4 09/29/09 completion of the assessment. A step Control Programs was added to define internal assessment findings and recommendations and require that findings be documented in a Condition Report. Quality impact:

Improved quality through timely documentation of assessment findings and recommendations.

Several steps were added to make the procedure flow better. Flexibility to start Laboratory Batch sample analyses prior to creation of the 790 Quality Control 2 03/16/09 batch QC samples, with management Handling approval, was added. Unnecessary sections of FORM 790.2 were deleted.

Calibration of the A precaution was added to allow a grace 1014 Panasonic UD-71 OA 12 11/03/09 period of +1-33% to the calibration TLD Reader periodicity requirement.

Daily Quality Control A step was added to require that the Response Check of room temperature and humidity be 1030 the Panasonic 11 11/03/09 recorded in the logbook each day the UD-710A TLD instrument is used.

Reader F:\AOMIN\CORRES\EL 034- 42

APPENDIXA INTER/INTRA-LABORATORY, ENVIRONMENTAL MONITORING ANALYTICS, DOE, AND ERA/ELAP QUALITY CONTROL PROGRAM RESULTS F:\AOMIN\CORRES\EL 034-10 A-1

2008 - 2009 Environmental Am-241 Accuracy Results for Alpha Spectrometry 35 25

~-----------------------

15 Fe en 5 MAPEP co m --Zero 0~ -5

- - Control

. . - ~. - - - - - - - - - - - -!-- - - - - t - - -

-15 limits

-25

-35+-----~------~------~------~----~------~------~------T Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date CR-09-13 was issued to investigate these negative biases.

F:\AOMIN\CORRES\EL 034 A-2

2008 - 2009 Environmental Am-241 Accuracy Results for Gamma Spectrometry 35 25

~-----------------------

15 Fe en 5 co --Zero m

0~ -5

- - Control limits

-15

~-----------------------

-25

-35+-----~------~----~------~----------~------~----~

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-3

2008 - 2009 Environmental 8a-133 Accuracy Results 40 30 20 Fe 10 ELAP en co m 0 --Zero 0~

-10 1~~_~t ~- ~_n_tr_ol_lim_it_sl

-20

-30

-40+-----~,------~,------~,-------~,-----~,-----~,----~,------~,

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-4

2008 - 2009 Environmental C-14 Accuracy Results 35~------------------------------------------------------~

25

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

15 5 Fe

--Zero

-5

- - Control limits

-15

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

-25

-35+-----~,-------~,-----~,----~,------~,-------~,-----~,----~,

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-5

2008 - 2009 Environmental Ce-141 Accuracy Results 30~--------------------------------------------------------~

20 Fe 10

Analytics rn

.!!! * *

Zero III 0~

0

-10

- - Control limits

-20 - - - - - - - - - - - - - - - - - - - - - - -

-30+-----~------~------~----~------~------~----~------~

Jan-08 Apr-08 Jul-08 Oct -08 Jan-09 Apr-09 Jul-09 Oct-09 Oec-09 Analysis Date F:\AOMIN\CORRES\EL 034 A-6

2008 - 2009 Environmental Charcoal Filter Accuracy Results 35 ~--------------------------------------------------------------~

25 15 Fe 5

Analytics

-5 ---Zero

- Control limits

-15

-25

-35 +-------~------~------~------~----~------~------~------~~

Dec-O? M ar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date All 2008 charcoal results originally reported without the application of summing corrections were updated in accordance with CR 08-23. The graph reflects the updated data.

F:\AOMIN\CORRES\EL 034 A-7

2008 - 2009 Environmental Co-57 Accuracy Results 30~--------------------------------------------------------

20 - - - - - - - - - - - - - - - - - - - - - - - PC 10 MAPEP o , --Zero

-10

- - Control limits

-20

-30+-----~------~------~----~------~----~------~----_T Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Ana Iys is Date F:\AOMIN\CORRES\EL 034 A-8

2008 - 2009 Environmental Co-58 Accuracy Results 30~----------------------------------------------------------~

20 Fe 10

Analytics rn III 0

Zero 0~ * **

** - - Control

-10

limits

-20 - - - - - - - - - - - - - - - - - - - - - - -

-30+-------~----~------~------~------~----~------~------~

Jan-08 Apr-08 Jul-08 Oct-08 Jan-09 Apr-09 Jul-09 Oct-09 Oec-09 Analysis Date F:\AOMIN\CORRES\EL 034 A-9

2008 - 2009 Environmental Co-GO Accuracy Results 60~--------------------------------------------------------~

Fe 40

Analytics 20 MAPEP o

-20 L~ *

--r----------------

--Zero

- - Control

-40 limits

)K ELAP

-60

-80+---~~------~------~----~--------------~----~------~

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Analysis Date F:\AOMIN\CORRES\EL 034 A-10

2008 - 2009 Environmental Cr-51 Accuracy Results 30~----------~----------------------------------------------~

20 Fe 10 *

Analytics rn *

.~ Zero III 0 0~

-10 * * *

- - Control limits

-20

-30+-------~~Mr~------_rl~----~------~----~------~------~

Jan-08 Apr-08 Jul-08 Oct-08 Jan-09 Apr-09 Jul-09 Oct-09 Oec-09 Analysis Date F:\AOMIN\CORRES\EL 034 A-11

2008 - 2009 Environmental Cs-134 Accuracy Results 40 Fe 30 20

Analytics 10 MAPEP rn

.~

III 0

--Zero 0~

-10

- - Control

-20 limits ELAP

-30

-40+-------~----~------~------~------~----~------~------~

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Analysis Date F:\AOMIN\CORRES\EL 034 A-12

2008 - 2009 Environmental Cs-137 Accuracy Results 40 Fe 30

_ _ _ _ _ _ _ _ _ _ _ _ _ _ L.- _ _ _ _ _ _ _ _ _

20

Analytics 10 MAPEP rn III 0

---Zero 0~

-10

- - Control

-20 limits ELAP

-30

-40 +-------~------~----+-~------~------~------~------~----~

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Analysis Date CR-09-14 was issued to investigate the positive biases in the MAPEP soil sample.

F:\AOMIN\CORRES\EL 034 A-13

2008 - 2009 Environmental Fe-55 Accuracy Results 35 25 PC 15 MAPEP en 5 co m

0~ -5 --Zero

-15 - - Control limits

-25

-35+-----~------~----~----~------~----~------~----_T Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-14

2008 - 2009 Environmental Fe-59 Accuracy Results 30~----------------------------------------------------------~

20 - - - - - - - - - - - - - - - - - - - -*- - - Fe 10 *

Analytics rn

.!!! --Zero III 0 0~

-10

* - - Control limits

-20 - - - - - - - - - - - - - - - - - - - - - - -

-30+-------~--4-~------~------~------~----~------~------~

Jan-08 Apr-08 Jul-08 Oct-08 Jan-09 Apr-09 Jul-09 Oct-09 Oec-09 Analysis Date F:\AOMIN\CORRES\EL 034 A-15

2008 - 2009 Environmental Gross Alpha Filter Accuracy Results 35 25 ~-----------------------

15 I

Analytics rn 5

--Zero III 0~

-5 I

, * - - Control limits

-15

-25 ~-----------------------

-35+-----~,-------~,----~,------~,-------~,----~,------~,------~,

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-16

2008 - 2009 Environmental Gross Alpha Water Accuracy Results 60 ~----------------------------------------------------------------,

40 Fe 20

Analytics en co

ELAP m 0 0~

-20 II

---Zero Control limits

""'I-

-40 I

-60 +-------~------~------~------~------~------~------~------__T Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date The percent difference of the mean value from the known value exceeded the Manual 100 criterion for accuracy for one set of Analytics samples. CR 09-21 was issued to investigate the failure.

F:\AOMIN\CORRES\EL 034 A-17

2008 - 2009 Environmental Gross Beta Filter Accuracy Results 35 25 15 Fe en 5 co m

Analytics 0~ -5 --Zero

- - Control limits

-15

-25

-35+-----~------~----~------~----~----~------~----__r Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-18

2008 - 2009 Environmental Gross Beta Water Accuracy Results 60~--------------------------------------------------------

40 20 L--------------------- ~

Analytics en I co m

ELAP 0

0~

--Zero

-20 - - Control limits

-40

-60+-----~------~----~------ __------~----~------~----_T Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-19

2008 - 2009 Environmental H-3 Accuracy Results 40~----------------------------------------------------------~

Fe 30 20 - - - - - - - - - - - - - - - - - - - - - - - -

Analytics 10 MAPEP o --Zero

-10 I *

- - Control

-20 -- limits

~ ELAP

-30

-40+-----~~----~------~------~------~----~------~------~

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Analysis Date F:\AOMIN\CORRES\EL 034 A-20

2008 - 2009 Low Level Environmental H-3 Accuracy Results 40~---------------------------------------------------------,

Fe 30 20 - - - - - - - - - - - - - - - - - - - - - - - -

Analytics 10 MAPEP o --Zero

-10

- - Control

-20 -- limits

)K ELAP

-30

-40+-----~r_----~------~----~------ __------~----~------_r Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Analysis Date F:\AOMIN\CORRES\EL 034 A-21

2008 - 2009 Environmental 1-131 Accuracy Results for Gamma Spectrometry 40 ~------------------------------------------------------------~

30 Fe 20 - - - - - - - - - - - - - - - - - - - - - - - -

10

Analytics o

* * * ---Zero

-10

-20 I * - - Control limits

-30

-40 +-------~------~------~------~------~------~------~----__r Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Analysis Date Two individual Analytics results fell outside the accuracy criterion. No investigation was necessary per Manual 100 F:\AOMIN\CORRES\EL 034 A-22

2008 - 2009 Low Level Environmental 1-131 Accuracy Results 40 Fe 30 20 ------------------------

Analytics rn 10 MAPEP

.!!! A A

I-III 0 ~ dill 0~ )I(

if

Zero

-10

i--------------

- - Control

-20 limits

)I( ELAP

-30

-40 I I I I I I I I Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Analysis Date F:\AOMIN\CORRES\EL 034 A-23

2008 - 2009 Environmental K-40 Accuracy Results 35 25 15

~-------t _____l ______ --- MAPEP en 5 co m Zero 0~ -5

- - Control limits

-15

~-----------------------

-25

-35 I I I I I I I I Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date CR-09-14 was issued to investigate the positive biases in the MAPEP soil sample.

F:\AOMIN\CORRES\EL 034 A-24

2008 - 2009 Environmental Mn-54 Accuracy Results 30 ~----------------------------------~---------------------

20 - - - - - - - - - - - - - - - - - - - - -

PC 10 *

Analytics en co

m 0 MAPEP 0~

Zero

-10

- - Control limits

-20 - - - - - - - - - - - - - - - - - - - - -

-30 +-----~------~------~----~------~------~----~------~

Jan-08 Apr-08 Jul-08 Oct-08 Jan-09 Apr-09 Jul-09 Oct -09 Oec-09 Analysis Date CR-09-14 was issued to investigate the positive biases in the MAPEP soil sample.

F:\AOMIN\CORRES\EL 034 A-25

2008 - 2009 Environmental Ni-63 Accuracy Results 35~----------------------------------------------------~

25 PC 15 MAPEP 5

-5 --Zero

-15 - - Control limits

-25

-35+-----~------~----~----~------~----~------~----~

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-26

2008 - 2009 Environmental Pu-238 Accuracy Results 30 20 ~-----------------------

10 Fe en 0 MAPEP co m ---Zero 0~ -10 I - - Control

-20 ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Iii- - - - - -- - - _"-----___I_im_its_----"

-30

-40 +----~--~---~---~---~---~---+---~

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date CR-09-12 was issued to investigate these negative biases.

F:\AOMIN\CORRES\EL 034 A-27

2008 - 2009 Environmental Pu-239 Accuracy Results 30 20 ~-----------------------

10 Fe en 0 MAPEP co m Zero 0~ -10

- - Control

~--------------l----t---

-20 limits

-30

-40 I I I I I I I I Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date CR-09-12 was issued to investigate these negative biases.

F:\AOMIN\CORRES\EL 034 A-28

2008 - 2009 Environmental Ra-226 Accuracy Results 35~---------------------------------------------------------

25

~-----------------------

15 Fe 5

--Zero

-5

- - Control limits

-15

~-----------------------

-25

-35+-----~,-------~,-----~,----~,------~,-------~,----~,------~,

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-29

2008 - 2009 Environmental Ra-228 Accuracy Results 35~---------------------------------------------------------

25

~-----------------------

15 Fe 5

--Zero

-5

- - Control limits

-15

~-----------------------

-25

-35+-----~,-------~,-----~,----~,------~,-------~,----~,------~,

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-30

2008 - 2009 Environmental Sr-89 Accuracy Results 60 40 20 ~-----------------------

Analytics Zero rn 0 III ~

0~

-20

~ I I II - - Control

~-------- ... ... - - - - - - - - - - - - - - limits

-40

-60 f

-80 I I I I I I I I Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-31

2008 - 2009 Environmental Sr-90 Accuracy Results 60~--------------------------------------------------------~

Fe 40 20

Analytics o+---~--------~.~-------------=.------~------~.~----~~---I MAPEP

I *

-20

-40

---f----- --Zero

-60 i - - Control limits

-80+-----~------~------~----~------~------~----~------~

Jan-08 Apr-08 Jul-08 Oct -08 Jan-09 Apr-09 Jul-09 Oct-09 Oec-09 Analysis Date F:\AOMIN\CORRES\EL 034 A-32

2008 - 2009 Environmental Tc-99 Accuracy Results 35 25

~-----------------------

15 MAPEP en 5 co --Zero m

0~ -5

- - Control limits

-15

~-----------------------

-25

-35+-----~,------~,------~,------~,------~,------~,------~,------~,

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-33

2008 - 2009 Environmental Th-230 Accuracy Results 35 25 15

~----~------------------

Fe en 5 co m A Zero 0~ -5

- - Control limits

-15

~-----------------------

-25

-35 I I I I I I I I I Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-34

2008 - 2009 Environmental U-234 Accuracy Results 35~----------------------------------------------------~

25

- - - - - - - -:tIL- - - - - - - - - - - - - PC 15 MAPEP 5

-5 --Zero

-15 - - Control limits

-25

-35+-----~------~----~----~------~----~------~----~

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-35

2008 - 2009 Environmental U-238 Accuracy Results 35~----------------------------------------------------~

25 PC 15 MAPEP 5

-5 --Zero

-15 - - Control limits

-25

-35+-----~------~----~----~------~----~------~----~

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Date F:\AOMIN\CORRES\EL 034 A-36

2008 - 2009 Environmental Zn-65 Accuracy Results 60 ~------------------------------------------------------------~

Fe 40

Analytics 20 - - - - - - - - - - - - - -

I- - - - - - - - - -

MAPEP o ---Zero

_1111' _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

-20 - - Control limits

-40 ~ ELAP

-60 +-------~------~------~------~------~------~------~----~

Dec-O? Mar-08 Jun-08 Sep-08 Dec-08 Mar-09 Jun-09 Sep-09 Dec-09 Analysis Date CR-09-14 was issued to investigate the positive biases in the MAPEP soil sample.

F:\AOMIN\CORRES\EL 034 A-37

APPENDIX B ENVIRONMENTAL DOSIMETRY QUALITY CONTROL PROGRAM RESULTS F:\AOMIN\CORRES\EL 034-10 8-1

2008 - 2009 Environmental TLD Individual Accuracy Results 25~-----------------------------------------------------------

Fe 15

Battelle 5 --Zero I - - Control

-5

limits

-15

-25+-----~------~------~----~------~------~----~------~-

Jan-08 Apr-08 Jul-08 Oct -08 Jan-09 Apr-09 Jul-09 Oct -09 Oec-09 Read Date F:\AOMIN\CORRES\EL 034 B-2

2008 - 2009 Environmental TLD Individual Precision Results 25~---------------------------------------------------------, ~---------

Fe 15

Battelle r:::::

.2 5

.!a (J

CI) s...

Zero a..

0~

-5 *

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-15 limits

-25+-----~------~----~------~----~------~----~------~~

Jan-08 Apr-08 Jul-08 Oct-08 Jan-09 Apr-09 Jul-09 Oct-09 Oec-09 Read Date F:\AOMIN\CORRES\EL 034 B-3

2008 - 2009 Environmental TLD Mean Accuracy Results 25~---------------------------------------------------------, ~---------

Fe 15

Battelle 5

--Zero

-5

- - Control

-15 limits

-25+-----~------~----~------~----~------~----~------~~

Jan-08 Apr-08 Jul-08 Oct-08 Jan-09 Apr-09 Jul-09 Oct-09 Oec-09 Ana Iys is Date F:\AOMIN\CORRES\EL 034 B-4

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