ML071210123

Annual Radiological Environmental Operating Report, January Through December 2006

ML071210123
Person / Time
Site:	Browns Ferry
Issue date:	04/27/2007
From:	Crouch W Tennessee Valley Authority
To:	Document Control Desk, NRC/NRR/ADRO
References
Download: ML071210123 (94)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Aabaama 35609-2000 April 27, 2007 10 CFR 50, APPENDIX I, Sections IV.B.2, IV.B.3, & IV.C U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:

In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) -UNITS 1, 2, AND 3 -ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) REPORT -JANUARY THROUGH DECEMBER 2006 In accordance with the BFN Technical Specifications (TS)Section 5.6.2 and 10 CFR 50, Appendix I, Section IV.B, TVA is submitting the AREOR report for BFN Units 1, 2, and 3. This report covers the period from January through December 2006.TS Section 5.6.2 requires that the enclosed AREOR report contain summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. In addition, the BFN Offsite Dose Calculation Manual, Section 5.1, requires the AREOR include the following information:

Results of land use censuses Summarized and tabulated results of the radiological environmental samples taken during the reporting period, in the format of Regulatory Guide 4.8, December 1975, and NUREG 1302, April 1991 Summary description of the radiological environmental monitoring program U.S. Nuclear Regulatory Commission Page 2 April 27, 2007 A map of sampling locations keyed to a table giving distances and directions from one reactor* Results of TVA's participation in the Interlaboratory Comparison Program The report concludes that based upon the analysis of the environmental sampling results and trend data, the exposure to members of the public which may have been attributable to BFN operation is negligible.

There are no regulatory commitments contained in this letter.If you have any questions, please contact me at (256) 729-2636.Sincerely, William D. Crouch Manager of Site Licensing and Industry Affairs Enclosure cc: See page 3 U.S. Nuclear Regulatory Commission Page 3 April 27, 2007 Enclosure cc (Enclosure):

U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 Mr. Malcolm T. Widmann, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Ronald Sanacore American Nuclear Insurers Town Center, Suite 300S 29 South Main Street West Hartford, Connecticut 06107-2430 Mr. Stanley Self West Morgan-East Lawrence Water Authority 6505 County Road 400 Hillsboro, Alabama 35643 ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR), JANUARY THROUGH DECEMBER 2006 (See Attached)

Annual Radiological Environmental Operating Report Browns Ferry Nuclear Plant 2006 ANNUJAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT BROWNS FERRY NUCLEAR PLANT 2006 TENNESSEE VALLEY AUTHORITY April 2007 TABLE OF CONTENTS Table of Contents .............................................

ii List of Tables .................................................

iv List of Figures ................................................

v Executive Summ ary ...........................................

1 Introduction

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2 Naturally Occurring and Background Radioactivity

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2 Electric Power Production

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4 Site/Plant Description

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6 Radiological Environmental Monitoring Program ....................

7 Direct Radiation M onitoring

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10 M easurement Techniques

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10 R esults ....................................................

11 Atmospheric M onitoring

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13 Sample Collection and Analysis ................................

13 R esults ....................................................

14 Terrestrial M onitoring

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16 Sample Collection and Analysis ................................

16 R esults ....................................................

16 Liquid Pathway M onitoring

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18 Sample Collection and Analysis ................................

18 R esults ....................................................

19 Assessment and Evaluation

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21 R esults ....................................................

21 Conclusions................................................

22 R eferences

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23-ii-Appendix A Radiological Environmental Monitoring Program and Sampling Locations

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27 Appendix B 2006 Program Modifications

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38 Appendix C Program Deviations

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40 Appendix D Analytical Procedures

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43 Appendix E Nominal Lower Limits of Detection (LLD) ................

46 Appendix F Quality Assurance/Quality Control Program ...............

51 Appendix G Land Use Survey ....................................

56 Appendix H Data Tables and Figures ..............................

61-111-LIST OF TABLES Table 1 Comparison of Program Lower Limits of Detection with Regulatory Limits for Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas and Reporting Levels .............

24-iv-EXECUTIVE

SUMMARY

This report describes the radiological environmental monitoring program conducted by TVA in the vicinity of the Browns Ferry Nuclear Plant (BFN) in 2006. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations.

Monitoring includes the sampling of air, water, soil, food crops, fish, shoreline sediment, and the measurement of direct radiation levels.Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations.

The vast majority of the activity detected from environmental samples was the result of naturally occurring radioactive materials.

Smiall amounts of Cs-137 were measured in a limited number of samples collected during 2006. The concentrations measured for Cs-137 were consistent with levels commonly found in the environment as a result of atmospheric nuclear weapons fallout.The level of activity measured in these samples would result in no measurable increase over background in the dose to the general public.

INTRODUCTION This report describes and summarizes results of radioactivity measurements made in the vicinity of BFN and laboratory analyses of samples collected in the area. The measurements are made to comply with the requirements of 10 CFR 50, Appendix A, Criterion 64 and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C and to determine potential effects on public health and safety. This report satisfies the annual reporting requirements of BFN Technical Specification 5.6.2 and Offsite Dose Calculation Manual (ODCM) Administrative Control 5.1.The data presented in this report include results from the prescribed program and information to help correlate the significance of results measured by this monitoring program to the levels of environmental radiation resulting from naturally occurring radioactive materials.

Naturally Occurring and Background Radioactivity Most materials in our world today contain trace amounts of naturally occurring radioactivity:

Potassium-40 (K-40), with a half-life of 1.3 billion years, is one of the major types of radioactive materials found naturally in our environment.

An individual weighing 150 pounds contains about 140 grams of potassium (Reference 1). This is equivalent to approximately 100,000 pCi of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body.Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-212, 214, lead (Pb)-212, 214, thallium (Tl)-208, actinium (Ac)-228, uranium (U)-238, 235, thorium (Th)-234,.radium (Ra)-226, radon (Rn)-222, carbon (C)-14, and hydrogen (H)-3 (generally called tritium).

The radiation from these materials makes up a part of the low-level natural background radiation.

The remainder of the natural background radiation comes in the form of cosmic ray radiation from outer space.It is possible to get an idea of the relative hazard of different types of radiation sources by evaluating the amount of radiation the U.S. population receives from each general type of radiation source. The following information is primarily adapted from References 2 and 3.

U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source MilliremlYear Per Person Natural background dose equivalent Cosmic 27 Cosmogenic 1 Terrestrial 28 In the body 39 Radon-222 200 Total 295 Release of radioactive material in natural gas, mining, ore processing, etc. 5 Medical (effective dose equivalent) 53 Nuclear weapons fallout less than 1 Nuclear energy 0.28 Consumer products 0.03 Total 355 (approximately)

As can be seen from the table, the natural background radiation dose equivalent to the U.S.population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation.

It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background cosmic and terrestrial radiation.

Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electrical generating plants. The basic process behind electrical power production in both types of plants is that fuel is used to heat water to produce steam which provides the force to turn turbines and generators.

In a nuclear power plant, the fuel is uranium and heat is produced in the reactor through the fission of the uranium. Nuclear plants include many complex systems to control the nuclear fission process and to safeguard against the possibility of reactor malfunction.

The nuclear reactions produce radionuclides commonly referred to as fission and activation products.

Very small amounts of these fission and activation products are released into the plant systems. This radioactive material can be transported throughout plant systems and some of it released to the environment.

The pathways through which radioactivity is released are monitored.

Liquid and gaseous effluent monitors record the radiation levels for each release. These monitors also provide alarm mechanisms to prompt termination of any release above limits.Releases are monitored at the onsite points of release and through the environmental monitoring program which measures the environmental radiation in areas around the plant. In this way, not only is the release of radioactive materials from the plant tightly controlled, but measurements are made in surrounding areas to verify that the population is not being exposed to significant levels of radiation or radioactive materials.

The BFN ODCM, which is required by the plant Technical Specifications, prescribes limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of these effluents.

The dose to a member of the general public from radioactive materials released to unrestricted areas, as given in NRC guidelines and in the ODCM, is limited as follows:

Liquid Effluents Total body Any organ Gaseous Effluents Noble gases: Gamma radiation Beta radiation Particulates:

Any organ<3 mrem/year<10 mrem/year<10 mrad/year<20 mrad/year<15 mrem/year The Environmental Protection Agency (EPA) limits for the total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are as follows: Total body Thyroid Any other organ<25 mrem/year<75 mrem/year<25 mrem/year Appendix B to 10 CFR 20 presents the regulatory limits for the annual average concentrations of radioactive materials released in gaseous and liquid effluents at the boundary of the unrestricted area. Table 1 of this report compares the nominal lower limits of detection for the BFN monitoring program with the regulatory limits for maximum annual average effluent concentrations released to unrestricted areas and levels requiring special reports to the NRC. The data presented in this report indicate compliance with the regulations.

SITE/PLANT DESCRIPTION Browns Ferry Nuclear Plant (BFN) is located on the north shore of Wheeler Reservoir at Tennessee River Mile 294 in Limestone County in north Alabama (Figure 1). Wheeler Reservoir averages I to 1-1/2 miles in width in the vicinity of the plant. The site, containing approximately 840 acres, is approximately 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama. The dominant character of land use is small, scattered villages and homes in an agricultural area. A number of relatively large farming operations occupy much of the land on the north side of the river immediately surrounding the plant. The principal crop grown in the area is cotton.Approximately 2500 people live within a 5-mile radius of the plant. The town of Athens has a population of about 17,000, while approximately 49,000 people live in the city of Decatur. The largest city in the area with approximately 160,000 people is Huntsville, Alabama, located about 24 miles east of the site.Area recreation facilities are developed along the Tennessee River. The nearest facilities are public use areas located 2 to 3 miles from the site. The city of Decatur has developed a large municipal recreation area, Point Mallard Park, approximately 15 miles upstream of the site. The Tennessee River is also a popular sport fishing area.BFN consists of three boiling water reactors.

Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974. Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors.

Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in March 1977.All three units were out of service from March 1985 to May 1991. Unit.2 was restarted May 24, 1991, and Unit 3 restarted on November 19, 1995. Recovery work for Unit 1 is ongoing.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within the reactor itself or one of the other plant systems. Plant effluent monitors are designed to detect the small amounts released to the environment.

Environmental monitoring is a final verification that the systems are performing as planned. The monitoring program is designed to sample the pathways between the plant and the people in the immediate vicinity of the plant. Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized.

The radiological environmental monitoring program is outlined in Appendix A.There are two primary pathways by which radioactivity can move through the environment to humans: air and water (see Figure 2). The air pathway can be separated into two components:

the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline.

The types of samples collected in this program are designed to monitor these pathways A number of factors were considered in determining the locations for collecting environmental samples. The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weather patterns, dose projections, population distribution, and land use. Terrestrial sampling stations were selected after reviewing such things as the locations of dairy animals and gardens in conjunction with the-air pathway analysis.

Liquid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and sediment.

Table A-2 (Appendix A,.Table 2: This method of notation is used for all tables and figures given in the appendices.)

lists the sampling stations and the types of samples collected from each.

Modifications made to the REMP program are described in Appendix.B.

Deviations in the sampling and analysis schedule are discussed in Appendix C.To determine the amount of radioactivity in the environment prior to the operation of BFN, a preoperational radiological environmental monitoring program was initiated in 1968 and operated until the plant began operation in 1973. Sampling and analyses conducted during the preoperational phase has provided data that can be used to establish normal background levels for various radionuclides in the environment.

The preoperational monitoring program is a very important part of the overall program. During the 1950s, 60s, and 70s, atmospheric nuclear weapons testing released radioactive material to the environment causing fluctuations in background radiation levels. This radioactive material is the same type as that produced in the BFN reactors.

Preoperational knowledge of radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of whether the operation of BFN is impacting the environment and thus the surrounding population.

The evaluation of the impact of plant operations also utilizes data from control stations that have been established in the monitoring program. Results of environmental samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to establish the-extent of BFN influence.

Sample analyses are performed by TVA's Environmental Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area Radiological Laboratory (WARL)in Muscle Shoals, Alabama. The analyses are conducted in accordance with written and approved procedures and are based on accepted methods. A summary of the analysis techniques and methodology is presented in Appendix D. Due to issues with lab equipment, a commercial vendor lab was utilized for performance of the Sr-89,90 analyses of soil samples. Data tables summarizing the sample analysis results are presented in Appendix H.

The radiation detection devices and analysis methods used to determine the radionuclide content of samples collected in the environment are very sensitive to small amounts of radioactivity.

The sensitivity of the measurement process is defined in terms of the lower limit of detection (LLD). A description of the nominal LLDs for the Radioanalytical Laboratory is presented in Appendix E.The ERM&I Laboratory applies a comprehensive quality assurance/quality control program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement process as soon as possible so they can be corrected.

This program includes instrument checks to ensure that the radiation detection instruments are working properly and the analysis of quality control samples. To provide for interlaboratory comparison program cross checks, the laboratory participated in a blind sample program administrated by Analytics, Incorporated.

In addition, samples are split with the EPA National Air and Radiation Environmental Laboratory and the State of Alabama. A complete description of the quality control program is presented in Appendix F.

DIRECT RADIATION MONITORING Direct radiation levels are measured at a number of stations around the plant site. These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and radioactivity that may be present as a result of plant operations.

Because of the relative large variations in background radiation as compared to the small levels from the plant, contributions from the plant are difficult to distinguish.

Radiation levels measured in the area around the BFN site in 2006 were consistent with levels from previous years and with levels measured at other locations in the region.Measurement Techniques Direct radiation measurements are made with thermoluminescent dosimeters (TLDs).TVA uses the Panasonic Model UD-814 dosimeter for measurement of the environmental radiation levels. This dosimeter contains four elements consisting of one lithium borate and three calcium sulfate phosphors.

The calcium sulfate phosphors are shielded by approximately 1000 mg/cm 2 plastic and lead to compensate for the over-response of the detector to low energy radiation.

TLDs are placed approximately 1 meter above the ground, with two or more TLDs at each monitoring location.

Monitoring points for TLDs are located in each of the sixteen compass sectors surrounding the site. One monitoring point is located in each sector near the site boundary and a second monitoring point is located at a distance of approximately five miles in each sector. Additional locations are distributed through the sectors out to a distance of approximately 32 miles. The TLDs are exchanged every 3 months and read with a Panasonic Model UD-710A automatic reader interfaced with a computer system for analysis of the data.

Since the calcium sulfate phosphor is much more sensitive than the lithium borate, the measured exposure is taken as the median of the results obtained from the calcium sulfate phosphors in all detectors from the monitoring location.

The values are corrected for gamma response, system variations, and transit exposure, with individual gamma response calibrations for each element.The system meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 for environmental applications of TLDs.Results All results are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />). The monitoring locations are grouped according to the distance from the plant. The first group consists of all locations within 1 mile of the plant. The second group lies between 1 and 2 miles, the third group between 2 and 4 miles, the fourth between 4 and 6 miles, and the fifth group is made up of all locations more than 6 miles from the plant. Past data have shown that the results from all monitoring points greater than 2 miles from the plant are essentially the same. Therefore, for purposes of this report, all locations 2 miles or less from the plant are identified as "onsite" stations and all others are considered "offsite." The quarterly gamma radiation levels determined from the TLDs deployed around BFN in 2006 are summarized in Table H-1. The results from all measurements at individual locations are presented in Table H-2. The exposures are measured in milliroentgens.

For purposes of this report, one milliroentgen (mR), one millirem (mrem), and one millirad are assumed to be numerically equivalent.

The rounded average annual exposures are shown below.Annual Average Direct Radiation Levels mR/Year BFN 2006 Onsite Stations 65 Offsite Stations 56 The data in Table H-i indicate that the average quarterly radiation levels at the BFN onsite locations are approximately 2.3 mR/quarter higher than levels at the offsite locations.

This difference is consistent with levels measured for preoperation and construction phases of TVA nuclear plant sites where the average radiation levels on site were generally 2-6 mR/quarter higher than the levels offsite. The causes of these differences have not been isolated; however, it is postulated that the differences are probably attributable to combinations of influences such as natural variationsin environmental radiation levels, earth-moving activities onsite, and the mass of concrete employed in the construction of the plant. Other undetermined influences may also play a part.Figure H-1 compares plots of the environmental gamma radiation levels from the onsite or site boundary locations with those from the offsite locations over the period from 1976 through 2006.All results reported in 2006 are consistent with direct radiation levels identified at locations which are not influenced by the operation of BFN. There is no indication that BFN activities increased the background direct radiation levels normally observed in the areas surrounding the plant.

ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as local, perimeter, and remote. In the current program, five local air monitoring stations are located on or adjacent to the plant site in the general direction of greatest wind frequency.

Three of these stations (LM-1, LM-2, and LM-3) are located on the plant side of the Tennessee River and two stations (LM-6 and LM-7) are located immediately across the river from the plant site. One additional station (station LM-4) is located at the point of maximum predicted offsite concentration of radionuclides based on meteorological data. Three perimeter air monitoring stations are located in communities out to about 13 miles from the plant, and two monitors used as controls are located out to 32 miles. The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appendix A.Results from the analysis of samples in the atmospheric pathway are presented in Tables H-3 and H-4. Radioactivity levels identified in this reporting period are consistent with background radioactivity levels.Sample Collection and Analysis Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfrn) through a 2-inch glass fiber filter. The sampling system consists of a pump, a magnehelic gauge for measuring the drop in pressure across the system, and a dry gas meter. This allows an accurate determination of the volume of air passing through the filter. The sampling system is housed in a metal building.

The filter is contained in a sampling head mounted on the outside of the monitor building.

The filter is replaced weekly. Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 weeks, composites of the filters from each location are analyzed by gamma spectroscopy.

Gaseous radioiodine is collected using a commercially available cartridge containing TEDA-impregnated charcoal.

This system is designed to collect iodine in both the elemental form and as organic compounds.

The cartridge is located in the same sampling head as the air particulate filter and is downstream of the particulate filter. The cartridge is changed at the same time as the particulate filter and samples the same volume of air. Each cartridge is analyzed for 1-131 by gamma spectroscopy analysis.Rainwater is sampled by use of a collection tray attached to the monitor building.

As water drains from the tray, it is collected in one of two 5-gallon jugs inside the monitor building.A 1-gallon sample, or the total volume available if less than one gallon, is removed from the container every 4 weeks. Any excess water is discarded.

Rainwater samples are analyzed only if the air particulate samples indicate the presence of elevated activity levels or if fallout is expected.

No rainwater samples from the vicinity of BFN were required to be analyzed in 2006.Results The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 2006 was consistent with levels reported in previous years. The average gross beta concentrations in samples collected at both indicator and control locations was 0.022 pCi/m 3.The annual averages of the gross beta activity in air particulate filters at these stations for the years 1968-2006 are presented in Figure H-2. Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981.Evidence of a small increase resulting from the Chernobyl accident can also be seen in 1986.These patterns are consistent with data from monitoring programs conducted by TVA at other nuclear power plant sites during construction and preoperational stages.Only naturally occurring radionuclides were identified by the monthly gamma spectral analysis of the air particulate samples.

There was no 1-131 detected in any charcoal cartridge samples collected during 2006. The results for the analysis of charcoal cartridges are reported in Table H-4.

TERRESTRIAL MONITORING Terrestrial monitoring is accomplished by collecting samples of environmental media that may transport radioactive material from the atmosphere to humans. Samples of soil and food crops are collected and analyzed to determine the potential impacts from exposure to this pathway.The results from the analysis of these samples are shown in Tables H-5 through H-1 1.A land use survey is conducted annually to locate milk producing animals and gardens within a 5-mile radius of the plant. No milk-producing animals have been identified within 5 miles of the plant. The results of the 2006 land use survey are presented in Appendix G.Sample Collection and Analysis Soil samples are collected annually from the air monitoring locations.

The samples are collected with either a "cookie cutter" or an auger type sampler. After drying and grinding, the sample is analyzed by gamma spectroscopy.

When the gamma analysis is complete, the sample is analyzed for Sr-89, 90.Samples representative of food crops raised in the area near the plant are obtained from individual gardens, comer markets, or cooperatives.

Types of foods may vary from year to year as a result of changes in the local vegetable gardens. In 2006, samples of apples, cabbage, corn, green beans, potatoes, and tomatoes were collected from local gardens. The edible portion of each sample is analyzed by gamma spectroscopy.

Results The only fission or activation product identified in soil samples was Cs-137. The average concentration measured in samples from indicator locations was 0.20 pCi/g. The average concentration for control locations was 0.21 pCi/g. These concentrations are consistent with levels previously reported from fallout. All other radionuclides reported were naturally occurring isotopes.

The results of the analysis of soil samples are reported in Table H-5. A plot of the annual average Cs-137 concentrations in soil is presented in Figure H-3. The concentration of Cs-137 in soil is steadily decreasing as a result of the cessation of weapons testing in the atmosphere, the 30-year half-life of Cs-137 and transport through the environment.

Only naturally occurring radioactivity was identified in food crops. The predominant natural radionuclide detected in samples of food crops was K-40. Analyses of these samples indicated no contribution from plant activities.

The results are reported in Tables H-6 through H-1 1.

LIQUID PATHWAY MONITORING Potential exposures from the liquid pathway can occur from drinking water, ingestion of fish, and from direct radiation exposure to radioactive materials deposited in the river shoreline sediment.The liquid pathway monitoring program conducted during 2006 included the collection of samples of surface (river/reservoir) water, groundwater, drinking water supplies, fish, and shoreline sediment.

Samples from the reservoir are collected both upstream and downstream from the plant.Results from the analysis of aquatic samples are presented in Tables H-12 through H-17.Radioactivity levels in water and shoreline sediment were consistent with background levels previously reported.

Trace levels of Cs-137 were identified in fish.Sample Collection and Analysis Samples of surface water are collected from the Tennessee River using automatic sampling systems from one downstream station and one upstream station. The upstream sample is collected from the raw water intake at the Decatur, Alabama water plant and is utilized as control sampling location for both surface and drinking water. A timer turns on the system at least once every two hours. The line is flushed and a sample collected into a collection container.

A I-gallon sample is removed from the container every 4 weeks and the remaining water in the jug is discarded.

The 4-week composite sample is analyzed by gamma spectroscopy and for gross beta activity.

A quarterly composite sample is analyzed for tritium.Samples are also collected by an automatic sampling system at the first downstream drinking water intake. This sample is collected at the intake for the water plant and is raw untreated water. These samples are collected in the same manner as the surface water samples.

These monthly samples are analyzed by gamma spectroscopy and for gross beta activity.

A quarterly composite is analyzed for tritium.At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source. These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity.

A quarterly composite sample from each station is analyzed for tritium.A groundwater well onsite is equipped with an automatic water sampler. Water is also collected from a private well in an area unaffected by BFN. Samples from the wells are collected every 4 weeks and analyzed by gamma spectroscopy.

A quarterly composite sample is analyzed for tritium.Samples of commercial and game fish species are collected semiannually from each of two reservoirs:

the reservoir on which the plant is located (Wheeler Reservoir) and the upstream reservoir (Guntersville Reservoir).

The samples are collected using a combination of netting techniques and electrofishing.

To sample edible portions of the fish, the fish are filleted.

After drying and grinding, the samples are analyzed by gamma spectroscopy.

Shoreline sediment was collected from two downstream recreational use areas and one upstream location.

The samples were collected at the normal water level shoreline and analyzed by gamma spectroscopy.

Results All radioactivity in surface water samples was below the detection limits except the gross beta activity and naturally occurring isotopes identified by gamma spectral analysis.

These results are consistent with previously reported levels. A trend plot of the gross beta activity in surface water samples from 1968 through 2006 is presented in Figure H-4. A summary table of the results for this reporting period is shown in Table H-12.

For drinking water (public water), gross beta activity averaged 2.6 pCi/liter at the downstream stations and 2.7 pCi/liter at control stations.

These results are consistent with previous monitoring results. The results are shown in Table H-13 and a trend plot of the gross beta activity from 1968 to 2006 is presented in Figure H-5.No fission or activation products were detected in groundwater samples from BFN REMP monitoring locations.

Only naturally occurring radon decay products (Pb-214 and Bi-214) were identified in these samples. Results from the analysis of groundwater samples are presented in Table H-14.Trace levels of Cs-137 were identified in three fish samples. These concentrations were consistent with data from previous monitoring years. The only other isotopes found in fish were naturally occurring radionuclides.

The results are summarized in Tables H-15 and H-16. Plots of the annual average Cs-137 concentrations in game fish are presented in Figure H-6.Only naturally occurring radionuclides were identified by the gamma spectral analyses of samples of shoreline sediment.

The results from the analysis of shoreline sediment are provided in Table H-17.

ASSESSMENT AND EVALUATION Potential doses to the public are estimated from measured effluents usihg computer models.These models were developed by TVA and are based on methodology provided by the NRC in Regulatory Guide1 .109 for determining the potential dose to individuals and populations living in the vicinity of a nuclear power plant. The results of the effluent dose calculations are reported in the Annual Radioactive Effluent Release Report. The doses calculated are a representation of the dose to a "maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates) are maximum expected values which will tend to overestimate the dose to this "hypothetical" person. The calculated maximum dose due to plant effluents are small fractions of the applicable regulatory limits. In reality, the expected dose to actual individuals is significantly lower.Based on the very low concentrations of radionuclides actually present in the plant effluents, radioactivity levels measured in the environment as a result of plant operations are expected to be negligible.

The results for the radiological environmental monitoring conducted for the BFN 2006 operations confirm this expectation.

Results As stated earlier in the report, the estimated increase in radiation dose equivalent to the general public resulting from the operation of BFN is negligible when compared to the dose from natural background radiation.

The results from each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences from the plant. During this report period, Cs-137 was identified in soil and fish samples. The distribution of Cs-137 in fish is consistent with fallout levels identified in samples during the preoperational phase of the monitoring program. The Cs-137 detected in soil was consistent with levels generally found in the environment as the result of past nuclear weapons testing.

Conclusions It is concluded from the above analysis of the environmental sampling results and from the trend plots presented in Appendix H that the exposure to members of the general public which may have been attributable to BFN is negligible.

The radioactivity reported herein is primarily the results of fallout or natural background radiation.

Any activity which may be present as a result of plant operations does not represent a significant contribution to the exposure of Members of the Public.

REFERENCES

1. Merril Eisenbud, Environmental Radioactivity.

Academic Press, Inc., New York, NY, 1987.2. National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing Radiation Exposure of the Population of the United States," September 1987.3. United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instruction Concerning Risks from Occupational Radiation Exposure," July 1981.

Table 1 COMPARISON OF PROGRAM LOWER LIMITS OF DETECTION WITH THE REGULATORY LIMITS FOR MAXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS.AND REPORTING LEVELS Concentrations in Water, pCi/Liter Effluent Reporting Lower limit Concentrationi Level 2 of Detection 3 Concentrations in Air, pCi/Cubic Meter Effluent Reporting Lower limit Concentrationi Level 2 of Detection 3 H-3 Cr-51 Mn-54 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ce-144 Ba-140 La-140 1,000,000 500,000 30,000 20,000 3,000 5,000 8,000 500 30,000 20,000 30,000 3,000 1,000 900 1,000 3,000 8,000 9,000 20,000 1,000 1,000 300 300 400 400 2 30 50 200 200 300 45 5 5 5 10 5 2 5 10 5 40 0.4 5 5 30 25 10 100,000 30,000 1,000 1,000 50 400 1,000 6 2,000 400 900 20 200 200 200 40 2,000 2,000 0.02 0.005 0.005 0.005 0.005 0.0011 0.0004 0.005 0.005 0.005 0.02 0.03 0.005 0.005 0.01 0.015 0.01 0.9 10 20 Note: I pCi =3.7 xl0 2 Bq.Note: For those reporting levels that are blank, no value is given in the reference.

I Source: Table 2 of Appendix B to 10 CFR 20.2 Source: BFN Offsite Dose Calculation Manual, Table 2.3-3.3 Source: Table E-1 of this report.

TENNESSEE VALLEY REGIOl (TVA NUCLEAR PLANT SITES)C K Y M t!10:5Q JACKSON#I ME MPHIS LEGEND M I S S.I I G EO RG I A-WATTS BAR NUCLEAR PLANT I -SEWUOYAH NUCLEAR PLANT-BELLEFONTENUCLEAR PLANT-BROWNS FERRY NUCLEAR PLANT Figure 2 ENVIRONMENTAL EXPOSURE PATHWAYS OF MAN DUE TO RELEASES OF RADIOACTIVE MATERIAL TO THE ATMOSPHERE AND LAKE.iere Airborne Releases Plume Exposure.IlJL MAN Liquid Releases Diluted By Lake J Animals (Milk,Meat)

Consumed By Animals Man 1 Shoreline Exposure I I 1~ýj Drinking Water.Fish"4 Vegetation Uptake From Soil APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND SAMPLING LOCATIONS Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway and/or Sample Number of Samples and Locationsb Sampling and Collection Frequency Type and Frequency of Analysis 1. AIRBORNE a. Particulates 00 Six samples from locations (in different sectors) at or near the site boundary (LM-1, LM-2, LM-3, LM-4, LM-6, and LM-7).Two samples from control locations greater than 10 miles from the plant (RM-1 and RM-6).Three samples from locations in communities approximately 10 miles from the plant (PM-I, PM-2, and PM-3).Same locations as air particulates.

Same locations as air particulates.

Continuous sampler operation with sample collection as required by dust loading but at least once per 7 days.Analyze for gross beta radioactivity greater than or equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change. Perform gamma isotopic analysis on each sample when gross beta activity is greater than 10 times the average of control samples. Perform gamma isotopic analysis on composite (by location) sample at least once per 31 days.b. Radioiodine

c. Rainwater Continuous sampler operation with charcoal canister collection at least once per 7 days.Composite sample at least once per 31 days.1-131 by gamma scan on each sample.Analyzed for gamma nuclides only if radioactivity in other media indicates the presence of increased levels of fallout Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway.and/or Sample Number of Samples and Locations b d. Soil e. Direct Samples from same locations as air particulates.

Two or more dosimeters placed at locations (in different sectors) at or near the site boundary in each of the 16 sectors.Two or more dosimeters placed at stations located approximately 5 miles from the plant in each of the 16 sectors.Two or more dosimeters in at least 9 additional locations of special interest.Sampling and Collection Frequency Once every year.At least once per 92 days.At least once per 92 days.Type and Frequency of Analysis Gamma scan, Sr-89, Sr-90 once per year.Gamma dose once per 92 days.Gamma dose once per 92 days.tLj 2. WATERBORNE

a. Surface Water b. Drinking water One sample upstream (TRM 306.0).One sample immediately downstream of discharge (TRM 293.5).One sample at the first potable surface water supply downstream from the plant (TRM 286.5).Collected by automatic sequential-type sampler with composite sample taken at least once per 31 days'.Collected by automatic sequential-type sampler with composite sample taken at least once per 31 daysc.Gross beta and gamma scan on 4-week composite.

Composite for tritium at least once per 92 days.Gross beta and gamma scan on 4-week composite.

Composite for tritium analysis at least once per 92 days.

Table A-i BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM" Exposure Pathway and/or Sample c. Drinking Water (Continued)

Number of Samples and Locations b Four additional samples of potable surface water downstream from the plant (TRM 282.6, TRM 274.9, TRM 259.8 and TRM 259.6).One sample at a control locationd (TRM 306).One sample adjacent to the plant (Well No. 6).One sample at a control location up gradient from the plant.One sample upstream from a recreational area (TRM 305).Sampling and Collection Frequency Grab sample taken from water supply at a facility using water from the public supply being monitored.

Sample collected at least once per 31 days.Collected by automatic sequential-type sampler with composite sample taken at least once per 31 days'.Collected by automatic sequential-type sampler with composite sample taken at least once per 31 days.Grab sample taken at least once per 31 days.Type and Frequency of Analysis Gross beta and gamma scan on 4-week composite.

Composite for tritium analysis at least once per 92 days.Same as downstream location.d. Ground water 0 Gamma scan on each composite.

Composite for tritium analysis at least once per 92 days.Gamma scan on each sample.Composite for tritium analysis at least once per 92 days.Gamma scan of each sample.e. Shoreline Sediment At least once per 184 days.

Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway and/or Sample e. Shoreline Sediment (Continued)

Number of Samples and Locationsb Sampling and Collection Frequency Type and Frequency of Analysis One sample from each of at least two At least once per 184 days.downstream locations with recreational use (TRM 293 and 279.5).Gamma scan of each sample.4. INGESTION a. Fish th Two samples representing commercial and game species in Guntersville Reservoir above the plant.Two samples representing commercial and game species in Wheeler Reservoir near the plant.At least once per 184 days.Gamma scan at least once per 184 days on edible portions.

Table A-1 BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway and/or Sample b. Fruits and Vegetables Number of Samples and Locationsb Samples of food crops such as greens, corn, green beans, tomatoes, and potatoes grown at private gardens and/or farms in the immediate vicinity of the plant.One sample of each of the same foods grown at greater than 10 miles distance from the plant.Sampling and Collection Frequency At least once per year at time of harvest.Type and Frequency of Analysis Gamma scan on edible portion.t'.)a. The sampling program outlined in this table is the program conducted during 2006.b. Sample locations, sector and distance from plant, are described in Table A-2 and A-3 and shown in Figures A-1, A-2, and A-3.c. Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.d. The sample location at the Decatur City Water Plant serves as a control sample for both surface water and drinking water.

Table A-2 BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Map Location Number'1 2 3 4 5 6 7 8 9 10 11 12 22 23 24 25 26 28 70 71 72 73 74 Station Sector PM-I NW PM-2 NE PM-3 SSE LM-7 W RM-1 W RM-6 E LM-I NNW LM-2 NNE LM-3 ENE LM-4 NNW LM-6 SSW Farm B NNW Well No.6 NW TRMc 282.6 TRM 306.0 TRM 259.6 TRM 274.9 TRM 293.5 TRM 259.8 TRM 286.5 TRM 305 TRM 293 TRM 279.5 Wheeler Reservoir (TRM 275-349)Guntersville Reservoir (TRM 349-424)Approximate Distance (Miles)13.8 10.9 7.5 2.1 31.0 23.4 1.0 0.9 0.9 1.7 3.0 6.8 0.02 11.4d 12.0d 34.4d 19.1d 0.5 d 34.2d 7.5d 1.05Indicator (I)or Control (C)I I I I C C I I I I I I I I C I I I I I C I I I I C Samples Collectedb AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S W W PW PW, SW PW PW SW PW PW SS SS SS F F a. See Figures A-1, A-2, and A-3 b. Sample codes: AP = Air particulate filter Cl F = Fish S R = Rainwater SW = Surface Water c. TRM = Tennessee River Mile.d. Miles from plant discharge at (TRM 294).= Charcoal filter (Iodine)= Soil PW SS W= Public drinking water= Shoreline sediment= Well water Table A-3 BROWNS FERRY NUCLEAR PLANT THERMOLUMINESCENT DOSIMETER (TLD) LOCATIONS Map Approximate Onsite (On)b Location Distance or Number' Station Sector (miles) Offsite (Off)I NW-3 NW 13.8 Off 2 NE-3 NE 10.9 Off 3 SSE-2 SSE 7.5 Off 5 W-3 W 31.0 Off 6 E-3 E 23.1 Off 7 N-I NNW 1.0 On 8 NNE-I NNE 0.9 On 9 ENE-1 ENE 0.9 On 10 NNW-2 NNW 1.7 On 38 N-2 N 5.0 Off 39 NNE-2 NNE 0.7 On 40 NNE-3 NNE 5.2 Off 41 NE-I NE 0.8 On 42 NE-2 NE 5.0 Off 43 ENE-2 ENE 6.2 Off 44 E-I E 0.8 On 45 E-2 E 5.2 Off 46 ESE-I ESE 0.9 On 47 ESE-2 ESE 3.0 Off 48 SE-I SE 0.5 On 49 SE-2 SE 5.4 Off 50 SSE-I SSE 5.1 Off 51 S-1 S 3.1 Off 52 S-2 S 4.8 Off 53 SSW-1 SSW 3.0 Off 54 SSW-2 SSW 4.4 Off 55 SW-1 SW 1.9 On 56 SW-2 SW 4.7 Off 57 SW-3 SW 6.0 Off 58 WSW-1 WSW 2.7 Off 59 WSW-2 WSW 5.1 Off 60 WSW-3 WSW 10.5 Off 61 W-1 W 1.9 On 62 W-2 W 4.7 Off 64 WNW-1 WNW 3.3 Off 65 WNW-2 WNW 4.4 Off 66 NW-I NW 2.2 Off 67 NW-2 NW 5.3 Off 68. NNW-I NNW 1.0 On 69 NNW-3 NNW 5.2 Off 75 N-IA N 1.0 On a. See Figures A-1, A-2, and A-3.b. TLDs designated "onsite" are those located 2 miles or less from the plant.TLDS designated "offsite" are those located more than 2 miles from the plant.

Figure A-1 Radiological Environmental Monitoring Locations Within 1 Mile of Plant 5 SSE Scale Mile!0 Figure A-2 Radiological Environmental Monitoring Locations From I to 5 Miles from the Plant Figure A-3 Radiological Environmental Monitoring Locations Greater than 5 Miles from the Plant APPENDIX B 2006 PROGRAM MODIFICATIONS APPENDIX B Radiological Environmental Monitoring Program Modifications During 2006 one direct radiation (TLD) location was eliminated.

This location was a redundant control distance location in the sector that was not providing value to the program. The location eliminated was W-4.

APPENDIX C PROGRAM DEVIATIONS APPENDIX C Program Deviations During 2006, problems with sampling equipment resulted in sample unavailability or inadequate sample volumes for four sets of air particulate filter and charcoal cartridge samples. The environmenital dosimeters at location NW-1 were missing at the end of the first quarter monitoring period. Table C-1 provides additional details on these program deviations.

Table C-I Radiological Environmental Monitoring Program Deviations Date 03/30/06 06/05/06 08/28/06 Station NW-1 LM-2 RM-1 Location 2.2 miles NW 0.9 miles NNE 31.0 miles W 23.4 miles E t'o Remarks The environmental dosimeters from this location were missing at the end of the first quarter. The dosimeters have been moved to more secure location in the same general area. The missed dosimeters were documented with PER 104716.The total sample volume for air filter and charcoal cartridge samples was not adequate due to a problem with the sampling pump. The problem was loss of electrical power due to severe thunderstorms.

The power was restored and the system returned to normal operation for the next sampling cycle. The missed samples were documented with PER 104714.The total sample volume for air filter and charcoal cartridge samples was not adequate due to a failure of the sampling pump.The problem was a failure of the drive motor. The motor was replaced and the system returned to normal operation for the next sampling cycle. The missed samples were documented with PER 109889.The total sample volume for air filter and charcoal cartridge samples was not adequate due to a failure of the sampling pump.The problem was a failure of the drive motor. The motor was replaced and the system returned to normal operation for the next sampling cycle. The missed samples were documented with PER 115234.The total sample volume for air filter and charcoal cartridge samples was not adequate due to a failure of the sampling pump.The problem was a bad motor bearing. The motor was replaced and the system returned to normal operation for the next sampling cycle.The missed samples were documented with PER 115562.11/20/06 RM-6 11/27/06 PM-1 13.8 miles NW APPENDIX D ANALYTICAL PROCEDURES Appendix D Analytical Procedures Analyses of environmental samples are performed by the radioanalytical laboratory located at the WARL facility in Muscle Shoals. All analysis procedures are based on accepted methods. A summary of the analysis techniques and methodology follows.The gross beta measurements are made with an automatic low background counting system.Normal counting times are 50 minutes. Water samples are prepared by evaporating 500 ml of samples to near dryness, transferring to a stainless steel planchet and completing the evaporation process. Air particulate filters are counted directly in a shallow planchet.After a radiochemical separation, samples analyzed for Sr-89, 90 are counted on a low background beta counting system. The sample is counted a second time after a 7-day ingrowth period. From the two counts the Sr-89 and Sr-90 concentrations canr be determined.

Water samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintillation.

A commercially available scintillation cocktail is used.Gamma analyses are performed in various counting geometries depending on the sample type and volume. Gamma counts are obtained with germanium detectors interfaced with a computer based multichannel analyzer system. Spectral data reduction is performed by the computer program HYPERMET.The charcoal cartridges used to sample gaseous radioiodine were analyzed by gamma spectroscopy using a high resolution spectroscopy system with germanium detectors.

The necessary efficiency values, weight-efficiency curves, and geometry tables are established and maintained on each detector and counting system. A series of daily and periodic quality control checks are performed to monitor counting instrumentation.

System logbooks and control charts are used to document the results of the quality control checks.

APPENDIX E NOMINAL LOWER LIMITS OF DETECTION (LLD)

Appendix E Nominal Lower Limits of Detection (LLD)A number of factors influence the LLD for a specific analytical method, including sample size, count time, count efficiency, chemical processes, radioactive decay factors, and interfering isotopes encountered in the sample. The most probable values for these factors have been evaluated for the various analyses performed in thte environmental monitoring program. The nominal LLDs are calculated from these values in accordance with the methodology prescribed in the ODCM. These nominal LLD values are presented in Table E-1. The maximum values for the lower limits of detection specified in the ODCM are shown in Table E-2. Milk samples are not currently collected and analyzed for the BFN REMP, but the nominal LLD values for the analysis of milk are included in the tables to maintain the historical record of the laboratory's measurement capabilities.

The nominal LLDs are also presented in the data tables. For analyses for which nominal LLDs have not been established, a LLD of zero is assumed in determining if a measured activity is greater than the nominal LLD.

TABLE E-I Nominal LLD Values A. Radiochemical Procedures Sediment Air Filters Water Milk Wet Vegetation and Soil (pCi/m 3) (pfllU (pfi/U (pCi/Kg wet) (pCi/g dry)Gross Beta 0.002 1.9 Tritium 300 Iodine-131 0.4 0.4 6.0 Strontium-89 5.0 3.5 31.0 1.6 Strontium-90 2.0 2.0 12.0 0.4 90 Table E-1 Nominal LLD Values B. Gamma Analyses (GeLi)Air Particulates pCi/m3 Ce-141 Ce-144 Cr-51 1-131 Ru-103 Ru-106 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Co-60 K-40 Ba-140 La-140 Fe-59 Be-7 Pb-212 Pb-214 Bi-214 Bi-212 TI-208 Ra-224 Ra-226 Ac-228.005.01.02.005.005.02.005.005.005.005.005.005.005.005.04.015.01.005.02.005.005.005.02.002 Charcoal Filter pCi/m3.02.07 0.15 0.03 0.02 0.12 0.02 0.02 0.03 0.02 0.02 0.02 0.03 0.02 0.30 0.07 0.04 0.04 0.15 0.03 0.07 0.05 0.20 0.02 0.07 Water And Milk pCi/L 10 30 45 10 5 40 5 5 10 5 5 5 10 5 100 25.10 10 45 15 20 20.50 10 20 Vegetation and Grain pCi/g, dry.07.15.30.20.03.15.03.03.05.25.03.03.05.03.40.30.20.08.25.04.50.10.25.03.10 Wet Vegetation pCi/kg, wet 35 115 200 60 25 190 30 25 45 30 20 20 45 20 400 130 50 40 200 40 80 55 250 30 Soil and Sediment pCi/g, dry.10.20.35.25.03.20.03.03.05.04.03.03.05.03.75.30.20.05.25.10.15.15.45.06.75.15.25 Fish Clam Flesh pCi/g, dry pCi/g, dry.07.15.30.20.03.15.03.03.05.25.03.03.05.03.40.30.20.08.25.04.50.10.25.03.10.35.85 2.4 1.7.25 1.25.14.15.45.25.25.20.40.20 3.50 2.4 1.4.45 1.9.30.10.50 2.0.25.75 Foods Tomatoes Potatoes, etc.pCi/kg, wet 20 60 95 20 25 90 10 10 45 10 10 10 45 10 250 50 25 25 90 40 80 40 130 30 50.01 70 Table E-2 Maximum Values for the Lower Limits of Detection (LLD)Specified by the BFN Offsite Dose Calculation Manual Airborne Particulate Food Water or Gases Fish Milk Products Sediment Analysis pCiiL pCi/rm 3 pCi/k wet _pf/L pCi/kg. wet pCi/k. dry gross beta 4 1 x 10-2 N.A. N.A. N.A. N.A.H-3 2000a N.A. N.A. N.A. N.A. N.A.Mn-54 15 N.A. 130 N.A. N.A. N.A.Fe-59 30 N.A. 260 N.A. N.A. N.A.Co-58, 60 15 N.A. 130 N.A. N.A. N.A.Zn-65 30 N.A. 260 N.A. N.A. N.A.Zr-95 30 N.A. N.A. N.A. N.A. N.A.Nb-95 15 N.A. N.A. N.A. N.A. N.A.1-131 1b 7 x 10-2 N.A. 1 60 N.A.Cs-134 15 5 x10-2 130 15 60 150 Cs-137 18 6 x 10-2 150 18 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A.La-140 15 N.A. N.A. 15 N.A. N.A.a. If no drinking water pathway exists, a value of 3000 pCi/liter may be used.b. LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCifliter.

If levels greater than 15 pCi/liter are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of 1-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/liter for 1-13 1.

APPENDIX F QUALITY ASSURANCE/QUALITY CONTROL PROGRAM Appendix F Quality Assurance/Quality Control Program A thorough quality assurance program is employed by the laboratory to ensure that the environmental monitoring data are reliable.

This program includes the use of written, approved procedures in performing the work, provisions for staff training and certification, internal self assessments of program performance, audits by various external organizations, and a laboratory quality control program.The quality control program employed by the radioanalytical laboratory is desigfied to ensure that the sampling and analysis process is working as intended.

The program includes equipment checks and the analysis of quality control samples along with routine samples. Instrument quality control checks include background count rate and counts reproducibility.

In addition to these two general checks, other quality control checks are performed on the variety of detectors used in the laboratory.

The exact nature of these checks depends on the type of device and the method it uses to detect radiation or store the information obtained.Quality control samples of a variety of types are used by the laboratory to verify the performance of different portions of the analytical process. These quality control samples include blanks, replicate samples, blind samples, or cross-checks.

Blanks are samples which contain no measurable radioactivity or no activity of the type being measured.

Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference from isotopes other than the one being measured.Duplicate samples are generated at random by the sample computer program which schedules the collection of the routine samples. For example, if the routine program calls for four public water samples every four weeks, on a random basis each location might provide an additional sample several times a year. These duplicate samples are analyzed along with other routine samples.They provide information about the variability of radioactive content in the various sample media.If enough sample is available for a particular analysis, the laboratory staff can split it into two portions.

Such a sample provides information about the variability of the analytical process since two identical portions of material are analyzed side by side.Analytical knowns are another category of quality control sample. A known amount of radioactivity is added to a sample medium. The lab staff knows the radioactive content of the sample. Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run. In this way, analytical knowns provide immediate data on the quality of the measurement process. A portion of these samples are also blanks.Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples. The lab staff does not know the sample contains radioactivity.

Since the bulk of the ordinary workload of the environmental laboratory contains no measurable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the laboratory or can be used to test the data review process. If an analysis routinely generates numerous zeroes for a particular isotope, the presence of the isotope is brought to the attention of the laboratory supervisor in the daily review process.Blind spikes test this process since the blind spikes contain radioactivity at levels high enough to be detected.

Furthermore, the activity can be put into such samples at the extreme limit of detection (near the LLD) to determine whether or not the laboratory can find any unusual radioactivity whatsoever.

Another category of quality control samples is internal cross-checks.

These samples have a known amount of radioactivity added and are presented to the lab staff labeled as cross-check samples. This means that the quality control staff knows the radioactive content or "right answer" but the lab personnel performing the analysis do not. Such samples test the best performance of the laboratory by determining if the lab can find the "right answer". These samples provide information about the accuracy of the measurement process. Further information is available about the variability of the process if multiple analyses are requested on the same sample. Like blind spikes or analytical knowns, these samples can also be spiked with low levels of activity to test detection limits. During 2006, all analysis results for internal cross-check samples were within agreement limits when compared to the known value.To provide for an independent verification of the laboratory's ability to make accurate measurements, the laboratory participated in an environmental level cross-check program available through Analytics, Inc., during 2006. The results of TVA's participation in this cross-check program are presented in Table F-1.The quality control data are routinely collected, examined and reported to laboratory supervisory personnel.

They are checked for trends, problem areas, or other indications that a portion of the analytical process needs correction or improvement.

The end result is a measurement process that provides reliable and verifiable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans.

Table F-I PResults For 2006 External Cross Checks Test Period First Quarter First Quarter First Quarter First Quarter Third Quarter Third Quarter Third Quarter Third Quarter Sample Type / Analysis Water (pCi/L)Gross Beta Milk (pCi/Liter) 9l 90Sr Water (pCiIL)1311 14 1 Ce SICr 1 3 4 Cs 17Cs soCo 3 4 Mn S 9 Fe 65 Z 6Zn 60Co Water (pCi/I.Results Known TVA 153 177 76.7 74.7")99 113 10.8 11.8 67.4 86.8 234 101 74.3 87.5 78.1 72.4 148 107 70.3 87.5 244 96.2 74 89.3 80.6 76.1 146 108 Aereement 1.15 0.97 1.14 1.09 1.04 1.01 1.04 0.95 1.00 1.02 1.03 1.05 0.97 1.01 1.10 3 H 4210 4630 Water (pCiIL)3 H Sand (pCi/gram) r41Ce 5 1 Cr 134Cs 117Cs SSCo 54Mn 59Fe 6SZn 0Co Air Filter (pCi/filter)

Gross Beta 11000 11121 0.121 0.398 0.120 0.247 0.154 0.159 0.062 0.204 0.189 0.125 0.387 0.139 0.235 0.155 0.172 0.053 0.198 0.189 1.01 1.03 0.97 1.16 0.95 1.00 1.08 0.86 0.97 1.00 0.95 0.95 1.01 0.84 0.94 0.96 1.05 0.88 1.01 0.96 86.0 81.4 Air Filter (pCi/filter) 14'Ce 5 1 Cr"34Cs'13Cs 58CO 54Mn 59 F sFe"sZn 60Co 79.1 259 78.2 161 101 104 40.2 133 123 74.8 260.9 66 152 96.9 108.4 35.4 135 117.8 (a) Activity was originally calculated using incorrect sample volume. The value reported here is the result of calculation with correct volume.

APPENDIX G LAND USE SURVEY Appendix G Land Use Survey A land use survey was conducted to identify the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of 5 miles from the plant. The land use survey also identifies all gardens of greater than 500 square feet producing fresh leafy vegetables within a distance of 3 miles from the plant.The land use survey was conducted between April 1 and October 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.In order to identify the locations around BFN which have the greatest relative potential for impact by the plant, radiation doses were projected for individuals living near BFN. These projections used the data obtained in the survey and historical meteorological data. The calculations also assumed that releases were equivalent to the design basis source terms. The dose projections are relative in nature and do not reflect actual exposures to individuals living near BFN.Dose projections from air submersion were calculated for the nearest resident in each sector and dose projections from eating foods produced near the plant were calculated for the areas with gardens.

There were no changes in the distance for the location of the nearest resident in 2006 as compared to 2005. The location of the nearest garden as identified in the 2006 survey changed in a total of three sectors.There were no locations identified within the five mile radius with milk production for human consumption.

Tables G-1 and G-2 show the comparative calculated doses for 2005 and 2006.

Table G-1 ROWNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within 8 km (5 Miles) of Plant mrem/year 2005 Survey Approximate Distance Annual 2006 Survey Sector N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Meters 2000 2590 4096 2458 1290 1860 a a 4482 4169 4458 3976 2530 5470 3373 1639 Dose 0.45 0.14 0.12 0.17 0.47 0.22 Approximate Distance Meters 2000 2590 4096 2458 1290 1860 a a 4482 4169 4458 3976 2530 5470 3373 1639 Annual Dose 0.45 0.14 0.12 0.17 0.47 0.22 0.15 0.18 0.10 0.08 0.19 0.10 0.30 0.76 0.15 0.18 0.10 0.08 0.19 0.10 0.30 0.76 Note a -There is no residence within the 8 km radius for this section Table G-2 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods mremlyear 2005 Survey 2006 Survey 0&Sector N NNE NE5 ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Approximate Distance Meters 4572 5940 4313 4319 2286 2125 a a 4482 4959 4458 4578 2995 a a 1791 Annual Dose Approximate Distance Meters Annual Dose 2.64 0.89 1.27 1.33 4.03 5.03 2.28 2.09 1.15 0.56 1.14 4572 5940 4313 4319 2286 2125 a a 5633 4959 7760 4578 2850 a a 1791 2.64 0.89 1.27 1.33 4.03 5.03 1.60 2.09 0.48 0.56 1.21 9.95 1 1 1 1 2 2 0 0 1 1 1 1 1 0 0 2 Number of Gardens Within 3 miles (2006)9.95 note a -Garden not found Within 8 km radius.

APPENDIX H DATA TABLES AND FIGURES Table H -I DIRECT RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from BROWNS FERRY Nuclear Plant for Each Quarter -2006 mR / Quarter (a)Distance per annum Miles Average External Gamma Radiation Levels (b) mR/yr 1st qtr 2nd qtr 3rd qtr 4th qtr 0-1 16.5+/-0.9 16.4+/-1.1 17.0 +/- 1.2 16.7+/-1.2 67 1-2 15.1 +/- 1.1 14.6 +/-1.2 15.3 +/-1.2 14.8+/-1.6 60 2-4 13.9 +/-0.8 13.4 +/-0.9 13.7 +/-0.8 13.5 +/-0.6 55 4-6 14.3 +/- 0.7 13.9 +/- 0.8 14.2 +/- 0.9 14.0 +/- 0.8 56> 6 .14.3 +/- 0.8 13.8 +/- 0.9 14.0 +/-0.8 13.7 +/- 1.4 56 Average, 0 -2 miles 16.1 +/- 1.1 16.0 +/- 1.4 16.6 +/- 1.4 16.3 +/- 1.5 65 (onsite)Average,> 2 miles 14.3 +/- 0.8 13.7 +/- 0.9 14.1 +/- 0.9 13.8 +/- 1.0 56 (offsite)(a) Field periods normalized to one standard quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)(b) Average of the individual measurements in the set +/- 1 standard deviation of the set TABLE H -2 DIRECT RADIATION LEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels mR / quarter!N Map Location Number 7 75 38 8 39 40 41 42 2 9 43 44 45 6 46 47 48 49 50 3 51 TLD Station Number N-1 N-1A N-2 NNE-1 NNE-2 NNE-3 NE-1 NE-2 NE-3 ENE-1 ENE-2 E-1 E-2 E-3 ESE-1 ESE-2 SE-i SE-2 SSE-1 SSE-2 S-1 Direction, degrees 348 355 1 12 31 19 51 49 56 61 62 85 91 90 110 112 130 135 163 165 185 Approx Distance, miles 1.0 1.0 5.0.9.7 5.2.8 5.0 10.9.9 6.2.8 5.2 24.2.9 3.0.5 5.4 5.1 7.5 3.1 1st Qtr Jan -Mar 2006 17.2 17.6 13.2 15.7 16.9 13.8 17.0 16.0 15.1 16.7 15.1 17.1 13.8 15.1 14.8 14.7 15.9 14.9 14.8 15.5 14.9 2nd Qtr Apr -Jun 2006 17.4 17.6 13.0 15.3 16.6 13.2 17.1 15.6 14.4 16.8 15.1 17.7 13.9 14.8 14.1 14.2 16.0 14.1 14.2 14.6 14.2 3rd Qtr Jul -Sep 2006 18.0 18.5 13.2 16.2 17.4 13.7 18.1 16.3 14.3 16.9 14.9 18.1 13.5 14.9 15.0 14.3 15.5 14.7 14.5 14.8.14.7 4th Qtr Oct- Dec 2006 18.4 18.3 13.1 16.7 16.8 13.0 17.5 15.4 14.6 16.2 14.8 17.3 13.2 15.3 14.8 13.8 15.2 15.0 14.4 15.5 14.4 Annual Exposure mR/vear 71.0 72.0 52.4 63.9 67.7 53.7 69.8 63.2 58.4 66.7 59.8 70.2 54.5 60.1 58.7 56.9 62.6 58.7 57.9 60.4 58.2-'3 TABLE H -2 continued DIRECT RADIATION LEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels mR / quarter&Map Location Number 52 53 54 55 56 57 58 59 60 61 62 5 63 64 65 66 67 1 68 10 69 TLD Station Number S-2 SSW-1 SSW-2 SW-1 SW-2 SW-3 WSW-1 WSW-2 WSW-3 W-1 W-2 W-3 W-4 WNW-1 WNW-2 NW-1 NW-2 NW-3 NNW-1 NNW-2 NNW-3 Direction, degrees 182 203 199 228 219 224 244 251 257 275 268 275 265 291 293 326 321 310 331 331 339 Approx Distance, miles 4.8 3.0 4.4 1.9 4.7 6.0 2.7 5.1.10.5 1.9 4.7 31.3 32.1 3.3 4.4 2.2 5.3 13.8 1.0 1.7 5.2 1st Qtr Jan -Mar 2006 13.5 13.0 14.2 14.0 14.2 13.6 13.0 15.1 13.7 14.8 13.7 14.1 13.8 14.1 14.2 (1)14.8 13.1 15.5 16.5 14.8 2nd Qtr Apr -Jun 2006 12.3 11.8 13.6 13.3 13.6 13.0 12.5 14.3 12.8 14.3 13.2 13.2 13.7 13.8 13.6 13.8 14.5 12.5 15.7 16.3 14.8 3rd Qtr Jul -Sep 2006 12.8 12.4 14.3 14.1 14.2 13.9 12.8 14.9 13.2 14.9 13.2 13.5 14.2 14.0 14.3 13.9 15.3 12.5 15.8 16.9 14.8 4th Qtr Oct- Dec 2006 13.2 12.7 14.2 13.2 14.2 12.9 12.6 14.7 13.1 14.3 13.2 13.5 10.8 13.9 13.6 13.7 14.6 12.7 15.8 17.0 14.4 Annual Exposure mR/year 51.8 49.9 56.3 54.5 56.1 53.3 50.9 59.0 52.8 58.2 53.3 54.2 52.5 55.9 55.6 55.2 59.2 50.8 62.8 66.7 58.8 0 0 CD HA CD note (1) Sum of available quarterly data normalized to 1 year for the annual exposure value Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN AIR FILTER PCI/M3 -0.037 BQ/M3 Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Docket Number. 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed GROSS BETA Lower Limit of Detection (LLD)See Note 1 568 2.OOE-03 143 1.00E-02 Indicator Locations Mean (F)Range See Note 2 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements GAMMA SCAN (GELI)AC-228 BE-7 BI-214 K-40 2.OOE-02 5.00E-03 4.0012-02 5.OOE-03 5.OOE-03 2.OOE-03 2.21E-02 (466/466)8.72E-03 -4.88E-02 117 VALUES < LLD 1.17E-01 (116/117)7.35E-02 -1.70E-01 1.39E-02 (91/117)5.00E-03 -5.44E-02 4.14E-02 (1/117)4.14E-02 -4.14E-02 117 VALUES < LLD 1.40E-02 (97/117)5.OOE-03 -6.33E-02 117 VALUES < LLD LM2 BF NORTH 0.9 MILE NNE LM-6BF BAKER BOTTOM 3.0 MILES SSW LM3 BF NORTHEAST 1.0 MILE ENE LM-6BF BAKER BOTTOM 3.0 MILES SSW PM-3 BF DECATUR AL 8.2 MILES SSE LM-6BF BAKER BOTTOM 3.0 MILES SSW LM-6BF BAKER BOTTOM 3.0 MILES SSW LM-6BF BAKER BOTTOM 3.0 MILES SSW 2.33E-02 (51 /51)1.13E-02 -3.72E-02 13 VALUES < LLD 1.22E-01 (13/ 13)8.76E-02 -1.57E-01 1.99E-02 (7113)5.60E-03 -5.44E-02 4.14E-02 (1 / 13)4.14E-02 -4.14E-02 13 VALUES < LLD 1.64E-02 (10/13)5.00E-03 -6.33E-02 13 VALUES < LLD 2.15E-02 (102/102)9.34E-03 -3.09E-02 26 VALUES < LLD 1.12E-01 (26/26)4.27E-02 -1.54E-01 1.59E-02 (18126)5.OOE-03 -2.78E-02 26 VALUES < LLD 26 VALUES < LLD 1.61E-02 (18126)5.OOE-03 -3.26E-02 26 VALUES < LLD-3 PB-212 PB-214 TL-208 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is Indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN CHARCOAL FILTER PCIIM3 -0.037 BQIM3 Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Docket Number: 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)See Note 1 568 5.OOE-02 Indicator Locations Mean (F)Range See Note 2 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements GAMMA SCAN (GELI)BI-214 1-131 K-40 PB-212 PB-214 TL-208 3.00E-02 3.OOE-01 3.OOE-02 7.OOE-02 2.OOE-02 8.05E-02 (23 /466)5.21E-02 -1.89E-01 SEE NOTE 3 3.55E-01 (371466)3.OOE-01 -4.56E-01 466 VALUES < LLD 9.68E-02 (19 /466)7.10E-02 -1.71E-01 466 VALUES < LLD LM-6BF BAKER BOTTOM 3.0 MILES SSW PM-2 BF ATHENS AL 10.9 MILES NE LM-6BF BAKER BOTTOM 3.0 MILES SSW LM1 BF NORTHWEST 1.0 MILE N LM-7BF LAKEVIEW 2.1 MILES WEST 1.30E-01 (2 i 52)7.06E 1.89E-01 4.28E-01 (1 52)4.28E 4.28E-01 52 VALUES < LLD 1.61E-01 (1152)1.61E-01 -1.61E-01 52 VALUES < LLD 8.65E-02 (4 1102)5.90E-02 -1.49E-01 3.73E-01 (111 102)3.04E-01 -4.92E-01 102 VALUES < LLD 9.86E-02 (4 102)7.16E-02 -1.41E-01 102 VALUES < LLD CD Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -I Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location Is Indicated In parentheses (F).Note: 3. The analysis of Charcoal Filters was performed by Gamma Spectroscopy.

No 1-131 was detected.

The LLD for 1-131.by Gamma Spectroscopy was 0.03 pCi/cubic meter.

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN SOIL PCrIGM -0.037 BQ/G (DRY WEIGHT)Name of Facility: Location of Facility: Type and Total Number of Analysis Performed GAMMA SCAN (GELI)AC-228 BE-7 BI-212 BI-214 CS-137 K-40 PB-212 PB-214 RA-224 RA-226 TL-208 SR 89 BROWNS FERRY NUCLEAR PLANT LIMESTONE ALABAMA Lower Limit Indicator Locations of Detection Mean (F)(LLD) Range See Note 1 See Note 2 Docket Number: 50-259.260,296 Reporting Period: 2006 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements 11 2.50E-01 2.50E-01 4.50E-01 1.50E-01 3.OOE-02 7.50E-01 1.00E-01 1.50E-01 7.50E-01 1.50E-01 6.00E-02 1.60E+00 1.20E+00 (919)6.96E-01 -. 1.45E+00 9 VALUES < LLD 1.24E+00 (9 /9)8.18E-01 -1.60E+00 9.59E-01 (9 9)7.45E-01 -1.14E+00 2.03E-01 (9/9)5.57E-02 -4.79E-01 5.47E+00 (919)2.77E+00 -7.48E+00 1.13E+00 (919)6.63E-01 -1.49E+00 1.05E+00 (9/9)8.33E-01 -1.26E+00 1.29E+00 (4 19)8.47E-O1 -1.60E+00 9.59E-01 (9/ 9)7.45E-01 -1.14E+00 3.73E-01 (9 /9)2.43E-01 -4.58E-01 LM-7BF LAKEVIEW 2.1 MILES WEST LM2 BF NORTH 0.9 MILE NNE LM-7BF LAKEVIEW 2.1 MILES WEST LM4 BF TRAILER P 1.7 MILES NNW LM-6BF BAKER BOTTOM 3.0 MILES SSW LMI BF NORTHWEST 1.0 MILE N LM-7BF LAKEVIEW 2.1 MILES WEST LM4 BF TRAILER P 1.7 MILES NNW LM-7BF LAKEVIEW 2.1 MILES WEST LM4 BF TRAILER P 1.7 MILES NNW LM-7BF LAKEVIEW 2.1 MILES WEST 1.45E+00 (1 I1)1.45E+00 1.45E+00 1 VALUES < LLD 1.60E+00 (1 /1)1.60E+00-1.60E+00 1.14E+00 (1 1)1.14E+00-1.14E+00 4.79E-01 (111)4.79E 4.79E-01 7.48E+00 (1 1)7.48E+00-7.48E+00 1.49E+00 (I 11)1.49E+00-1.49E+00 1.26E+00 (1 1)1.26E+00-1.26E+00 1.60E+00 (1 1)1.60E+00-1.60E+00 1.14E+00 (1 1)1.14E+00 -- 1.14E+00 4.58E-01 (1 1)4.58E 4.58E-01 8.21E-01 (2/2)7.52E-01 -8.91E-01 2 VALUES < LLD 8.85E-01 (2 2)8.06E-01 -9.64E-01 8.22E-01 (2 2)7.34E-01 -9.10E-01 2.05E-01 (2 /2)1.27E-01 -2.83E-01 4.62E+00 (2/2)3.81E+00 -5.42E+00 8.07E-01 (212)7.14E-01 -9.OOE-01 9.03E-01 (2 2)7.87E-01 " 1.02E+00 2 VALUES < LLD 8.22E-01 (212)7.34E-01 9.10E-01 2.78E-01 (2/2)2.57E-01 -3.00E-01 CD z'61i 11 11 9 VALUES < LLD 2 VALUES < LLD SR 90 4.00E-01 9 VALUES < LLD 2 VALUES < LLD Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN APPLES PCI/KG -0.037 BQ/KG (WET WT)Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Docket Number 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed GAMMA SCAN (GELI)BI-214 2 Lower Limit of Detection (LLD)See Note 1 4.OOE+01 2.50E+02 8.00E+01 Indicator Locations Mean (F)Range See Note 2 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements K-40 1 VALUES < LLD 1.19E+03 (1 1)1.19E+03-1.19E+03 1 VALUES < LLD 1 VALUES < LLD BFNP Paradise Shores 1.5 Miles NNW BFNP Paradise Shores 1.5 Miles NNW BFNP Paradise Shores 1.5 Miles NNW BFNP Paradise Shores 1.5 Miles NNW 1 VALUES < LLD 1.19E+03 (1 I1)1.19E+03-1.19E+03 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD 1.02E+03 (1 1)1.02E+03 -1.02E+03 I VALUES < LLD 1 VALUES < LLD PB-214 TL-208 3.00E+01 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN CABBAGE PCIIKG -0.037 BQ1KG (WET WT)Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Docket Number 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed GAMMA SCAN (GELI)BI-214 2 Lower Limit of Detection (LLD)See Note 1 4.00E+01 2.50E+02 8.0OE+01 Indicator Locations Mean (F)Range See Note 2 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements K-40 1 VALUES < LLD 1.29E+03 (1 1)1.29E+03-1.29E+03 1 VALUES < LLD LM-6BF BAKER BOTTOM 3.0 MILES SSW LM-6BF BAKER BOTTOM 3.0 MILES SSW LM-6BF BAKER BOTTOM 3.0 MILES SSW 1 VALUES < LLD 1.29E+03 (1 1)1.29E+03-1.29E+03 1 VALUES < LLD 1 VALUES < LLD 1.43E+03 (1 1)1.43E+03 -1.43E+03 1 VALUES < LLD PB-214 CD Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is Indicated In parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory

• RADIOACTIVITY IN CORN PCIIKG -0.037 BQIKG (WET WT)Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Docket Number 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)See Note 1 4.OOE+01 2.50E+02 Indicator Locations Mean (F)Range See Note 2 GAMMA SCAN (GELI)BI-214 K-40 2.1 VALUES < LLD 2.05E+03 (I/1)2.05E+03 -2.05E+03 I VALUES < LLD 1 VALUES < LLD Location with Highest Name Distance and Direction LM-6BF BAKER BOTTOM 3.0 MILES SSW LM-6BF BAKER BOTTOM 3.0 MILES SSW LM-6BF BAKER BOTTOM 3.0 MILES SSW LM-6BF BAKER BOTTOM 3.0 MILES SSW Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements I VALUES <LLD 2.05E+03 (1i1)2.05E+03-2.05E+03 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD 2.03E+03 (111)2.03E+03 -2.03E+03 1 VALUES < LLD 1 VALUES < LLD PB-212 PB-214 4.OOE+01 8.OOE+01 60 Note: 1. Nominal Lower Level of Detection (LLD) as described In Table E I : Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location Is Indicated In parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN GREEN BEANS PCI/KG -0.037 BQ/KG (WET WT)Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Type and Lower Limit Indicator Locations Total Number of Detection Mean (F)of Analysis (LLD) Range Performed See Note 1 See Note 2 Docket Number 50-259,260,296 Reporting Period: 2006 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements GAMMA SCAN (GELI)AC-228 BI-214 K-40 PB-214 2 5.0012+01 4.OOE+01 2.50E+02 8.0012+01 1 VALUES < LLD 1 VALUES < LLD 1.83E+03 (1 1)1.83E+03-1.83E+03 1 VALUES < LLD LM-6BF BAKER BOTTOM 3.0 MILES SSW LM-6BF BAKER BOTTOM 3.0 MILES SSW LM-6BF BAKER BOTTOM 3.0 MILES SSW LM-6BF BAKER BOTTOM 3.0 MILES SSW I VALUES < LLD 1 VALUES < LLD 1.83E+03 (111)1.83E+03 -1.83E+03 I VALUES < LLD 1 VALUES < LLD I VALUES < LLD.1.07E+03 (1 1)1.07E+03 -1.07E+03 1 VALUES < LLD CD Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN POTATOES PCIIKG -0.037 BQ/KG (WET WT)Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Docket Number. 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)See Note 1 4.00E+01 2.50E+02 Indicator Locations Mean (F)Range See Note 2 1 VALUES < LLD Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 1 VALUES < LLD Number of Nonroutine Reported Measurements GAMMA SCAN (GELI)BI-214 2 K-40 3.92E+03 (11 1)3.92E+03-3.92E+03 1 VALUES < LLD 3 MILES ENE 3 MILES ENE 3 MILES ENE I VALUES < LLD 3.92E+03 (1/ 1)3.92E+03 -3.92E+03 1 VALUES < LLD 2.95E+03 (1/1)2.95E+03 -2.95E+03 1 VALUES < LLD PB-214 8.OOE+01 CD C0 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -.1 Note: 2. Mean and Range based upon detectable mdasurements only. Fraction of detectable measurements at specified location Is Indicated In parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN TOMATOES PCI/KG -0.037 BQ1KG (WET WT)Name of Facility:

BROWNS FERRY NUCLEAR PLANT*Location of Facility:

LIMESTONE ALABAMA Docket Number 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)See Note 1 4.OOE+01 2.50E+02 Indicator Locations Mean (F)Range See Note 2 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations.

Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements GAMMA SCAN (GELI)BI-214 2 K-40 PB-212 PB-214 TL-208 4.0OE+01 8.OO11+01 3.OaE+01 1 VALUES < LLD 1.99E+03 (11 1)1.99E+03 -1.99E+03 1 VALUES< LLD 1 VALUES < LLD 1 VALUES < LLD LM4 BF TRAILER P 1.7 MILES NNW LM4 BF TRAILER P, 1.7 MILES NNW LM4 BF TRAILER P 1.7 MILES NNW LM4 BF TRAILER P 1.7 MILES NNW LM4 BF TRAILER P 1.7 MILES NNW 1 VALUES < LLD 1.99E+03 (1 1)1.99E+03-1.99E+03 I VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD I VALUES < LLD 1.68E+03 (1 1)1.68E+03 -1.68E+03 1 VALUES < LLD I VALUES < LLD I VALUES < LLD ,D iH,=Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -I Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location Is Indicated In parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN SURFACE WATER(Total)

PCI/L -0.037 BQ/L Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Docket Number: 50-259,260,296 Reporting Period: 2006* Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)See Note 1 Indicator Locations Mean (F)Range See Note 2 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements GROSS BETA-26 26 GAMMA SCAN (GELI)AC-228 BI-214 K-40 1.90E+00 2.OOE+01 2.00E+01 1.OOE+02 1.50E+0 l 2.00E+01 1.00E+01 3.00E+02 2.70E+00 (10/13)1.96E+00-3.98E+00 13 VALUES < LLD 2.40E+01 (1 13)2.40E+01 -2.40E+01 13 VALUES < LLD 13 VALUES < LLD 13 VALUES < LLD 13 VALUES < LLD TRM 293.5 TRM 293.5 TRM 293.5 TRM 293.5 TRM 293.5 TRM 293.5 TRM 293.5 2.70E+00 (10/13)1.96E+00 -3.98E+00 2.40E+01 (1 13)2.40E+01-2.40E+01 13 VALUES < LLD 13 VALUES < LLD 2.72E+00 (12/13)2.09E+00 -3.70E+00 13 VALUES < LLD 2.41E+01 (3/13)2.02E+01 -2.83E+01 13 VALUES < LLD 13 VALUES < LLD 2.19E+01 (1 /13)2.19E+01 -2.19E+01 13 VALUES < LLD PB-212 PB-214 TL-208 13 VALUES < LLD 13 VALUES < LLD 13 VALUES < LLD ,D TRITIUM 8 4 VALUES < LLD 4 VALUES < LLD Note: 1. Nominal Lower Level of Detection (LLD) as described In Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN PUBLIC WATER(Total)

PCI/L -0.037 BO/L Name of Facility: Location of Facility: BROWNS FERRY NUCLEAR PLANT LIMESTONE ALABAMA Docket Number 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)See Note 1 Indicator Locations Mean (F)Range See Note 2 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements GROSS BETA 78 78 GAMMA SCAN (GELI)AC-228 BI-214 K-40 PB-212 PB-214 TL-208 1.90E+00 2.0011+01 2.OOE+01 1 .OOE+02 1 .50E+01 2.OOE+01 1 .0OE+01 3.OOE+02 2.58E+00 (52165)1.91E+00 -4.54E+00 65 VALUES < LLD 2.27E+01 (4 65)2.04E+01 -2.41E+01 65 VALUES < LLD 65 VALUES < LLD 65 VALUES < LLD 65 VALUES < LLD CHAMPION PAPER TRM 282.6 CHAMPION PAPER TRM 282.6 CHAMPION PAPER TRM 282.6 CHAMPION PAPER TRM 282.6 CHAMPION PAPER TRM 282.6 CHAMPION PAPER TRM 282.6 CHAMPION PAPER TRM 282.6 2.77E+00 (10/ 13)2.10E+00 -4.54E+00 13 VALUES < LLD 2.35E+01 (3/13)2.23E+01 -2.41E+01 13 VALUES < LLD 13 VALUES < LLD 13 VALUES < LLD 13 VALUES < LLD 2.72E+00 (12/ 13)2.09E+00 -3.70E+00 13 VALUES < LLD 2.41E+01 (3/13)2.02E+01 -2.83E+01 13 VALUES < LLD 13 VA,,LUES < LLD 2.19E+01 (1113)2.19E+01 -2.19E+01 13 VALUES < LLD 0 TRITIUM 24 20 VALUES < LLD 4 VALUES < LLD Note: 1. Nominal Lower Level of Detection (LLD) as described In Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN WELL WATER(Total)

PCIIL -0.037 BQ/L Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Docket Number 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)See Note 1 Indicator Locations Mean (F)Range See Note 2 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements GAMMA SCAN (GELI)AC-228 26 BI-214 K-40 PB-212 PB-214 TL-208 2.00E+01 2.OOE+01 1.OOE+02 1 .50E+01 2.0011+01 1 .OOE+01 3.0011+02 13 VALUES < LLD 2.87E+01 (1/13)2.87E+01 -2.87E+01 13 VALUES < LLD 13 VALUES < LLD 2.16E+01 (1 113)2.16E+01 -2.16E+01 13 VALUES < LLD BFN WELL #6 0.02 MILES W BFN WELL #6 0.02 MILES W BFN WELL #6 0.02 MILES W BFN WELL #6 0.02 MILES W BFN WELL #6 0.02 MILES W BFN WELL #6 0.02 MILES W 13 VALUES < LLD 2.87E+01 (1113)2.87E+01 -2.87E+01 13 VALUES < LLD 13 VALUES < LLD 2.16E+01 (1 13)2.16E+01-2.16E+01 i3 VALUES < LLD 13 VALUES < LLD 1.62E+02 (12/ 13)2.21E+01 -5.40E+02 13 VALUES < LLD 13 VALUES < LLD 1.53E+02 (12/13)2.01E+01 -5.12E+02 13 VALUES < LLD CD TRITIUM 8 4 VALUES < LLD 4 VALUES < LLD Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN COMMERCIAL FISH PCI/GM -0.037 BQIG (DRY WEIGHT)Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Docket Number 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed GAMMA SCAN (GELI)BI-214 CS-137 K-40 PB-212 PB-214 TL-208 4 Lower Limit of Detection (LLD)See Note 1 1.00E-01 3.OOE-02 4.OOE-01 4.00E-02 5.00E-01 3.00E-02 Indicator Locations Mean (F)Range See Note 2 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements 2.04E-01 (112)2.04E-01 " 2.04E-01 2 VALUES < LLD 1.26E+01 (212)1.26E+01 -1.27E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD WHEELER RES TRM 275-349 WHEELER RES TRM 275-349 WHEELER RES TRM 275-349 WHEELER RES TRM 275-349 WHEELER RES TRM 275-349 WHEELER RES TRM 275-349 2.04E-01 (1 12)2.04E-01 -2.04E-01 2 VALUES < LLD 1.26E+01 (2/2)1.26E+01 -1.27E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD 4.62E-02 (212)4.41E-02 -4.82E-02 1.49E+01 (212)1.42E+01 -1.56E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD CD t-I Note: 1. Nominal Lower Level of Detection (LLD) as described In Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated In parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory

RADIOACTIVITY IN GAME FISH PC IGM -0.037 BQIG (DRY WEIGHT)Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE ALABAMA Docket Number 50-259,260,296 Reporting Period: 2006 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)See Note I Indicator Locations Mean (F)Range See Note 2 Location with Highest Name Distance and Direction Annual Mean Mean (F)Range See Note 2 Control Locations Mean (F)Range See Note 2 Number of Nonroutine Reported Measurements GAMMA SCAN (GELI)BI-214 CS-137 4 K-40 1.00E-01 3.OOE-02 4.OOE-01 5.OOE-01 3.00E-02 1.56E-01 (1 12)1.56E-01 -1.56E-01.4.05E-02 (11 2)4.05E-02 -4.05E-02 1.40E+01 (2 2)1.39E+01 -1.41E+01 2 VALUES < LLD 2 VALUES < LLD WHEELER RES TRM 275-349 WHEELER RES TRM 275-349 WHEELER RES TRM 275-349 WHEELER RES TRM 275-349 WHEELER RES TRM 275-349 1.56E-01 (1 /2)1.56E-01!-

1.56E-01 4.05E-02 (1 12)4.05E 4.05E-02 1.40E+01 (212)1.39E+01-1.41E+01 2 VALUES < LLD 2 VALUES < LLD 1.25E-01 (1 2)1.25E-01 -1.25E-01 2 VALUES < LLD 1.38E+01 (2 /2)1.37E+01 -1.38E+01 2 VALUES < LLD 2 VALUES < LLD PB-214 TL-208 CD I Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN SHORELINE SEDIMENT PCI/GM -0.037 BQIG (DRY WEIGHT)Name of Facility: Location of Facility: Type and Total Number of Analysis Performed GAMMA SCAN (GELI)AC-228 BE-7 BI-212 BI-214 K-40 P1-3-212 PB-214 RA-226 TL-208 BROWNS FERRY NUCLEAR PLANT LIMESTONE ALABAMA Lower Limit Indicator Locations of Detection Mean (F)(LLD) Range See Note 1 See Note 2 Location with Highest Name Distance and Direction Docket Number. 50-259,260,296 Reporting Period: 2006 Annual Mean Control Locations Mean (F) Mean (F)Range Range See Note 2 See Note 2 Number of Nonroutine Reported Measurements 6 2.50E-01 2.50E-01 4.50E-01 1.50E-01 7.50E-01 1.00E-01 1 .50E-01 1 .50E-01 6.OOE-02 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD 1.97E-01 (1 4)1.97E-01 -1.97E-01 4 VALUES < LLD 1.41E-01 (114)1.41E-01 -1.41E-01 2.11E-01 (1/4)2.11E-01 -2.11E-01 1.97E-01 (1/4)1.97E-01 -1.97E-01 4 VALUES < LLD MALLARD CREEK REC AR TRM 293.0 JOE WHEELER ST PARK TRM 279.5 MALLARD CREEK REC AR TRM 293.0 MALLARD CREEK REC AR TRM 293.0 MALLARD CREEK REC AR TRM 293.0 MALLARD CREEK REC AR TRM 293.0 MALLARD CREEK REC AR TRM 293.0 MALLARD CREEK REC AR TRM 293.0 MALLARD CREEK REC AR TRM 293.0 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD 1.97E-01 (1 12)1.97E 1.97E-01 2 VALUES < LLD 1.41E-01 (112)1.41E-01 -1.41E-01 2.11E-01 (1/2)2.11E-01 -2.11E-01 1.97E-01 (112)1.97E-01 -1.97E-01 2 VALUES < LLD 7.58E-01 (212)5.54E-01 -9.62E-01 4.08E-01 (112)4.08E-01 -4.08E-01 8.36E-01 (2 /2)6.04E-01 -1.07E+00 5.94E-01 (2 1 2)5.10E-01 -6.78E-01 8.75E+00 (2 2)6.64E+00 -1.09E+01 7.55E-01 (2/2)6.20E-01 -8.91E-01 6.25E-01 (2 2)5.89E-01 -6.62E-01 5.94E-01 (2/2)5.10E-01 -6.78E-01 2.48E-01 (2 2)1.72E-01 -3.24E-01-3 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Direct Radiation Levels Browns Ferry Nuclear Plant 25 20 ' " C)a (15 9-E 10 5 1980 1 1990 105 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year I A On-Site --o- Off-SiteI Annual Average Gross Beta Activity in Air Filters -BFNP 0.25 Initial plant operation 0.20 ,in August, 1973 E, 0.15 , Preoperational Average C00.~0.10 0.05 0.00 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year[ --Indicator

-Control -------------

00 C)

Annual Average Gross Beta Activity in Surface Water -BFNP 6 I I I I I I I 00 I~4 C2<2 Preoperational Average................................................................

Initial Plant Operation in August, 1973 Note: no gross beta measurements were made in 1978 0o 1965 1970 1975 1980 1985 1990 Calendar Year 1995 2000 2005 2010[ downstream -e- upstream I Annual Average Gross Beta Activity in Drinking Water -BFNP 6 Initial plant operation in August, 197 4 Preoperational Average-~ -----------

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Z 2I 0I 1965 1970 1975 1980 1985 1990 1995 2000 2005 20`10 Calendar Year 1 0 -downstream upstream Annual Average Cs-137 Activity in Fish Flesh Game Fish -BFNP 0.5 Initial plant operation in August, 1973 0.4 E 000.3 Propraioa Average> 0.2 0.1 0.0 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010.Calendar Year----downstream o upstream