ML101330496

Submittal of Annual Radiological Environmental Operating Report - 2009

ML101330496
Person / Time
Site:	Browns Ferry
Issue date:	05/10/2010
From:	Krich R Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML101330496 (92)

Text

Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing May 10, 2010 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1, 2, and 3 Facility Operating License No. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Browns Ferry Nuclear Plant - Units 1, 2, And 3 - Annual Radiological Environmental Operating Report - 2009 In accordance with the Browns Ferry Nuclear Plant (BFN) Technical Specifications Section 5.6.2 and Offsite Dose Calculation Manual Administrative Control Section 5.1, the Tennessee Valley Authority is submitting the Annual Radiological Environmental Operating Report for BFN Units 1, 2, and 3. Enclosed is the subject report for the period of January 1 through December 31, 2009. This report is required to be submitted by May 15 of each year. Since May 15 falls on a Saturday, this report is required to be submitted by May 17, 2010.

There are no regulatory commitments contained within this letter. If you have any questions, please contact Terry Cribbe at (423) 751-3850.

Sincerely, R. M. Krich

Enclosure:

Annual Radiological Environmental Operating Report, Browns Ferry Nuclear Plant, 2009 cc: See page 2 printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 May 10, 2010 cc (w/Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

Enclosure Browns Ferry Nuclear Plant Annual Radiological Environmental Operating Report 2009 (See Attached)

Annual Radiological Environmental Operating Report Browns Ferry Nuclear Plant 2009

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT BROWNS FERRY NUCLEAR PLANT 2009 TENNESSEE VALLEY AUTHORITY April 2010

TABLE OF CONTENTS Table of Contents ............................................. ii List of Tables ................................................. iv List of Figures ................................................ v Executive Summary ........................................... 1 Introduction ................................................. 2 Naturally Occurring and Background Radioactivity ................. 2 Electric Power Production ..................................... 4 Site/Plant Description .......................................... 6 Radiological Environmental Monitoring Program .................... 7 Direct Radiation Monitoring ..................................... 10 Measurement Techniques ...................................... 10 R esults .................................................... 11 Atmospheric Monitoring ....................................... 13 Sample Collection and Analysis ................................ 13 Results ................................................... 14 Terrestrial Monitoring ......................................... 15 Sample Collection and Analysis ................................ 15 R esults .................................................... 15 Liquid Pathway Monitoring ..................................... 17 Sample Collection and Analysis ................................ 17 Results .................................................... 18 Assessment and Evaluation ..................................... 20 Results .................................................... 20 Conclusions ................................................. 21 References ................................................... 22

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Appendix A Radiological Environmental Monitoring Program and Sampling Locations ............................................ 26 Appendix B 2009 Program Modifications ........................... 37 Appendix C Program Deviations .................................. 39 Appendix D Analytical Procedures ................................ 41 Appendix E Nominal Lower Limits of Detection (LLD)................ 44 Appendix F Quality Assurance/Quality Control Program ............... 49 Appendix G Land Use Survey .................................... 54 Appendix H Data Tables and Figures .............................. 59

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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 ............. 23

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LIST OF FIGURES Figure 1 Tennessee Valley Region ................................. 24 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atmosphere and Lake .................................... 25

EXECUTIVE

SUMMARY

This report describes the radiological environmental monitoring program conducted by TVA in the vicinity of the Browns Ferry Nuclear Plant (BFN) in 2009. 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. Small amounts of Cs-137 were measured in a limited number of soil and fish samples collected during 2009. 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)-I 4, 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 Millirem/Year Per Person Natural background dose equivalent Cosmic 27 Cosmogenic I 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 I 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 operitions 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:

Liguid Effluents Total body <3 rnrem/year Any organ <I0 mrem/year Gaseous Effluents Noble gases:

Gamma radiation <10 mrad/year Beta radiation <20 mrad/year Particulates:

Any organ < 15 torero/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 <25 mreni/year Thyroid <75 mrem/year Any other organ <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 I 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 BFN site contains approximately 840 acres. 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, and is approximately 10 miles northeast of BFN. Approximately 49,000 people live in the city of Decatur 10 miles southeast. The cities of Madison and Huntsville have a combined population of approximately 200,000 starting 20 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 I 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 was completed and the unit was restarted on May 22, 2007.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within the reactor 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. There were no program modifications or deviations from the sampling and analysis schedules. Appendix B and Appendix C are included in this report as place keepers to maintain the format of the report.

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 conducted 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, with exception of the SR-89, 90 analyses of soil samples which were performed by a contracted laboratory. 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. 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 Eckert & Ziegler Analytics. A complete description of the quality control program is presented in Appendix F.

DIRECT RADIATION MONITORING Direct radiation levels are measured at various monitoring points 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 any radioactivity that may be present as a result of plant operations. Because of the relatively large variations in background radiation as compared to the small levels from the plant, contributions from the plant may be difficult to distinguish.

Measurement Techniques The Landauer InLight environmental dosimeter is used in the radiological environmental monitoring program for the measurement of direct radiation. This dosimeter contains four elements consisting of aluminum oxide detectors with varying plastic and copper filtrations to provide qualitative information about conditions during the exposure.

The dosimeters are placed approximately I meter above the ground, with two at each monitoring location. Sixteen monitoring points are located around the plant near the site boundary, one location in each of the 16 compass sectors. One monitoring point is also located in each of the 16 compass sectors at a distance of approximately four to five miles from the plant.

Dosimeters are also placed at additional monitoring locations out to approximately 32 miles from the site. The dosimeters are exchanged every 3 months. The dosimeters are sent to Landauer for processing and results reporting. The values are corrected for transit and shielded background exposure. An average of the two dosimeter results is calculated for each monitoring point. The system meets or exceeds the performance specifications outlined in ANSI N545-1975 and HPS Draft Standard N13.29 for environmental applications of dosimeters.

Results The results for environmental dosimeter measurements 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 monitoring points within 2 miles of the plant. The second group is made up of all locations greater than 2 miles from the plant. Past data have shown that the average results from the locations more than 2 miles from the plant are essentially the same. Therefore, for purposes of this report, monitoring points 2 miles or less from the plant are identified as "onsite" stations and locations greater than 2 miles are considered "offsite."

The quarterly gamma radiation levels determined from the dosimeters deployed around BFN in 2009 are summarized in Table H-1. The exposures are measured in milliroentgens (mR). For purposes of this report, one milliroentgen, one millirem (mrem) and one millirad (mrad) are assumed to be numerically equivalent.

The rounded average annual exposures, as measured in 2009, are shown below.

Annual Average Direct Radiation Levels mR/Year BFN 2009 Onsite Stations 56 Offsite Stations 44 The data in Table H-I indicate that the average quarterly direct radiation levels at the BFN onsite stations are approximately 3.0 mR/quarter higher than levels at the offsite stations. This difference is consistent with levels measured for the preoperation and construction phases of TVA nuclear power plant sites where the average levels onsite were slightly higher than levels offsite. Figure H-I compares plots of the data from the onsite stations with those from the offsite

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stations over the period from 1977 through 2009. The results from the Landauer InLight dosimeters are lower across all locations when compared to the results previously obtained using the Panasonic UD-814 dosimeters. This difference is most likely due to the manner in how background badge data was applied for the in house processing of Panasonic dosimeters as compared to the method used by the vendor.

The data in Table H-2 contains the results of the individual monitoring stations. The results reported in 2009 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 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 (cfm) 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.

Results The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 2009 was consistent with levels reported in previous years. The average gross beta concentrations in samples collected at indicator locations was 0.021 pCi/m 3 and the average for control locations was 0.020/pCi/m 3 . The annual averages of the gross beta activity in air particulate filters at these stations for the years 1968-2009 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 2009. 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- i1.

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 2009 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 2009, samples of apples, cabbage, corn, green beans, potatoes, and tomatoes were collected from local gardens. Samples of these same food crops were purchased from area produce markets to serve as control samples. 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 0.12 pCi/g. The average concentration for control locations was 0.09 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-i 37 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-11.

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 2009 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.

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 1-gallon sample is removed from the container every 4 weeks and the remaining water in the jug is discarded. The 4-weekcomposite 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 The gross beta activity in surface water samples was consistent with previously reported levels.

Only naturally occurring isotopes were identified by gamma spectral analysis. No tritium was detected in surface water samples above the LLD of 270 pCi/L. A trend plot of the gross beta activity in surface water samples from 1968 through 2009 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 2.4 pCi/liter at the downstream stations and 2.6 pCi/liter at control stations. These results are consistent with previous monitoring results. No fission or activation products were detected by the gamma analysis of drinking water and no tritium was detected above the LLD. The results are shown in Table H- 13 and a trend plot of the gross beta activity from 1968 to 2009 is presented in Figure H-5.

No fission or activation products were detected in groundwater samples from BFN REMP monitoring locations. Results from the analysis of groundwater samples are presented in Table H-14.

Trace levels of Cs-137 were identified in fish samples collected from the control location. 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 detected by the gamma analysis of shoreline sediment samples. 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 using computer models.

These models were developed by TVA and are based on methodology provided by the NRC in Regulatory Guide 1.109 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 2009 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 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 I COMPARISON OF PROGRAM LOWER LIMITS OF DETECTION WITH THE REGULATORY LIMITS FOR MAXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS AND REPORTING LEVELS Concent rations in Water, pCi/Liter Concentrations in Air, pCi/Cubic Meter Effluent Reporting Lower limit Effluent Reporting Lower limit 3 Concentration' Level 2 of Detection 3 Concentration Level2 of Detection H-3 1,000,000 20,000 270 100,000 Cr-5 i 500,000 45 30,000 0.02 Mn-54 30,000 1,000 5 1,000 0.005 Co-58 20,000 1,000 5 1,000 0.005 Co-60 3,000 300 5 50 0.005 Zn-65 5,000 300 10 400 0.005 Sr-89 8,000 5 1,000 0.0011 Sr-90 500 2 6 0.0004 Nb-95 30,000 400 5 2,000 0.005 Zr-95 20,000 400 10 400 0.005 Ru- 103 30,000 5 900 0.005 Ru- 106 3,000 40 20 0.02 1-131 1,000 2 0.4 200 0.9 0.63 Cs- 134 900 30 5 200 10 0.005 Cs-137 1,000 50 5 200 20 0.005 Ce-144 3,000 30 40 0.01 Ba-140 8,000 200 25 2,000 0.015 La-140 9,000 200 10 2,000 0.01 Note: 1pCi = 3.7 x10"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-I of this report.

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Figure 2 ENVIRONMENTAL EXPOSURE PATHWAYS OF MAN DUE: TO RELEASES OF RAIDICACTIVE MATERIAL TO THE ATMOSPHERE AND LAKE.

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Plume Exposure Liquid Releases Diluted By Lake I

LIlL MAN n wBn Consumed By .Man Shoreline.

Exposure Consumed Drinkin By Animals Water JFish Uptake From Soil w25-

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND SAMPLING LOCATIONS Table A- I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMW Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locations' Collection Frequency of Analysis

1. AIRBORNE

a. Particulates Six samples from locations (in Continuous sampler operation with Analyze for gross beta radioactivity different sectors) at or near the site sample collection as required by dust 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 /> boundary (LM-I, LM-2, LM-3, LM-4, loading but at least once per 7 days. following filter change. Perform LM-6, and LM-7). gamma isotopic analysis on each sample when gross beta activity is Two samples from control locations greater than 10 times the average of greater than 10 miles from the plant control samples. Perform gamma (RM-! and RM-6). isotopic analysis on composite (by location) sample at least once per 31

!Three samples from locations in days.

communities approximately 10 miles from the plant (PM- i, PM-2, and PM-3).

b. Radioiodine Same locations as air particulates. Continuous sampler operation with 1-131 by gamma scan on each sample.

charcoal canister collection at least once per 7 days.

c. Soil Samples from same locations as air Once every year. Gamma scan, Sr-89, Sr-90 once per particulates. year.

Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM8 Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

d. Direct Two or more dosimeters placed at At least once per 92 days. Gamma dose once per 92 days.

locations (in different sectors) at or near the site boundary in each of the 16 sectors.

Two or more dosimeters placed at At least once per 92 days. Gamma dose once per 92 days.

stations located approximately 5 miles from the plant in each of the 16 sectors.

Two or more dosimeters in at least 9

,00 additional locations of special interest.

2. WATERBORNE

a. Surface Water One sample upstream (TRM 306.0). Collected by automatic sequential- Gross beta and gamma scan on 4-One sample immediately downstream type sampler with composite sample week composite. Composite for of discharge (TRM 293.5). taken at least once per 31 dayse. tritium at least once per 92 days.

b. Drinking water One sample at the first potable Collected by automatic sequential- Gross beta and gamma scan on 4-surface water supply downstream type sampler with composite sample week composite. Composite for from the plant (TRM 286.5). taken at least once per 31 dayse. tritium analysis at least once per 92 days.

Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

c. Drinking Water Four additional samples of potable Grab sample taken from water supply Gross beta and gamma scan on 4-(Continued) surface water downstream from the at a facility using water from the week composite. Composite for plant (TRM 282.6, TRM 274.9, public supply being monitored. tritium analysis at least once per 92 TRM 259.8 and TRM 259.6). Sample collected at least once per days.

31 days.

One sample at a control locationd Collected by automatic sequential- Same as downstream location.

(TRM 306). type sampler with composite sample taken at least once per 31 daysc.

d. Ground water One sample adjacent to the plant Collected by automatic sequential- Gamma scan on each composite.

tza (Well No. 6). type sampler with composite sample Composite for tritium analysis at taken at least once per 31 days. least once per 92 days.

One sample at a control location Grab sample taken at least once per Gamma scan on each sample.

up gradient from the plant. 31 days. Composite for tritium analysis at least once per 92 days.

e. Shoreline Sediment One sample upstream from a At least once per 184 days. Gamma scan of each sample.

recreational area (TRM 305).

Table A- I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locations" Collection Frequency of Analysis

e. Shoreline Sediment One sample from each of at least two At least once per 184 days. Gamma scan of each sample.

(Continued) downstream locations with recreational use (TRM 293 and 279.5).

4. INGESTION

a. Fish Two samples representing At least once per 184 days. Gamma scan at least once per 184 commercial and game species in days on edible portions.

0, Guntersville Reservoir above the plant.

Two samples representing commercial and game species in Wheeler Reservoir near the plant.

Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

b. Fruits and Samples of food crops such as greens, At least once per year at time of Gamma scan on edible portion.

Vegetables corn, green bsans, tomatoes, and harvest.

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.

7'

a. The sampling program outlined in this table is the program conducted during 2009.

b. Sample locations, sector and distance from plant, are described in Table A-2 and A-3 and shown in Figures A-I, 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 Approximate Indicator (1)

Location Distance or Samples Numbera Station Sector (Miles) Control (C) Collectedb PM-I NW 13.8 AP,CF,S 2 PM-2 NE 10.9 AP,CF,S 3 PM-3 SSE 7.5 C C AP,CF,S 4 LM-7 W 2.1 C I AP,CF,S 5 RM-I W 31.0 C AP,CF,S 6 RM-6 E 23.4 C AP,CF,S 7 LM-I NNW 1.0 I AP,CF,S 8 LM-2 NNE 0.9 I AP,CF,S 9 LM-3 ENE 0.9 I AP,CF,S 10 LM-4 NNW 1.7 I AP,CF,S 11 LM-6 SSW 3.0 I AP,CF,S 12 Farm B NNW 6.8 I W 22 Well No.6 NW 0.02 I W 23 TRM 282.6 - 11.4' I PW 24 TRM 306.0 - 12.0' C PW, SW 25 TRM 259.6 - 34.4d I' PW 26 TRM 274.9 - 19.1I I .PW 28 TRM 293.5 - 0.5d I SW 70 TRM 259.8 - 34.2' I PW 71 TRM 286.5 7.5d PW 72 TRM 305 I1.05 1.0d C SS 73 TRM 293 I SS 74 TRM 279.5 -

14.5 d I SS Wheeler Reservoir (TRM 275-349) I F Guntersville Reservoir (TRM 349-424) C F

a. See Figures A-I, A-2, and A-3

b. Sample codes:

AP = Air particulate filter CF = Charcoal filter (Iodine) PW = Public drinking water F = Fish S =Soil SS = Shoreline sediment R = Rainwater W = Well water SW = Surface Water

c. TRM = Tennessee River Mile.

d. Miles from plant discharge at (TRM 294);

Table A-3 BROWNS FERRY NUCLEAR PLANT ENVIRONMENTAL DOSIMETER LOCATIONS Map Approximate Onsite (On)b Location Distance or Number Station Sector (miles) Offsite (Off0 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-1 NNW 1.0 On 8 NNE-I NNE 0.9 On 9 ENE-] 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-1 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-I S 3.1 Off 52 S-2 S 4.8 Off 53 SSW-I SSW 3.0 Off 54 SSW-2 SSW 4.4 Off 55 SW-I 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-I 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-I, A-2, and A-3,

b. Dosimeters designated "onsite" are those located 2 miles or less from the plant.

Dosimeters designated "offsite" are those located more than 2 miles from the plant.

Figure A-1 Radiological Environmental Monitoring Locations Within I mile of the Plant 5

NW348.75 N NNE2 11NN

32. 68 7 750NE .6N 378.75 7544 NE Scale Mile Figure A-2 Radiological Environmental Monitoring Locations Between 1 and 5 miles from the Plant Figure A-3 Radiological Environmental Monitoring Locations More than 5 miles from the Plant SCALE

'I 1 It 20 26 APPENDIX B 2009 PROGRAM MODIFICATIONS APPENDIX B Radiological Environmental Monitoring Program Modifications There were no modifications to the BFN REMP during 2009.

APPENDIX C PROGRAM DEVIATIONS APPENDIX C Progrm Deviations There were deviations from the sampling and analysis schedule during 2009.

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 with the exception of the Sr-89, 90 analysis of soil samples which are performed by a commercial lab. 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.

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 the 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-1 Nominal LLD Values A. Radiochemical Procedures Sediment Air Filters Water Milk and Soil (Rim)(RO/ (C(/* (p-Ci/2 dry)

Gross Beta 0.002 1.9 Tritium 270 Iodine-13I OA 0.4 Strontium-89 3.5 1.6 Strontium-90 2.0 0.4

?I

Table E- I Nominal LLD Values B. Gamma Analyses Foods Air Charcoal Water Vegetation Wet Soil and Tomatoes Particulates Filter And Milk and Grain Vegetation Sediment Fish Potatoes, etc.

pCi/m3 pCi/rmn pCi/L pCig. dry pCi/kg. wet pCj/p. dry oCi/2. dry pCi/kg, wet Ce-141 .005 .02 10 .07 35 .10 .07 20 Ce-144 .01 .07 30 .15 115 .20 .15 60 Cr-51 .02 0.15 45 .30 200 .35 .30 95 1-131 .005 0.03 10 .20 60 .25 .20 20 Ru-103 .005 0.02 5 .03 25 .03 .03 25 Ru-106 .02 0.12 40 .15 190 .20 .15 90 Cs-134 .005 0.02 5 .03 30 .03 .03 10 Cs-137 .005 0.02 5 .03 25 .03 .03 10 Zr-95 .005 0.03 10 .05 45 .05 .05 45 Nb-95 .005 0.02 5 .25 30 .04 .25 10 Co-58 .005 0.02 5 .03 20 .03 .03 10 Mn-54 .005 0.02 5 .03 20 .03 .03 10 Zn-65 .005 0.03 10 .05 45 .05 .05 45 Co-60 .005 0.02 5 .03 20 .03 .03 10 K-40 .04 0.30 100 .40 400 .75 .40 250 Ba-140 .015 0.07 25 .30 130 .30 .30 50 La-140 .01 0.04 10 .20 50 .20 .20 25 Fe-59 .005 0.04 10 .08 40 .05 .08 25 Be-7 .02 0.15 45 .25 200 .25 .25 90 Pb-212 .005 0.03 15 .04 40 .10 .04 40 Pb-214 .005 0.07 20 .50 80 .15 .50 80 Bi-214 .005 0.05 20 .10 55 .15 .10 40 Bi-212 .02 0.20 50 .25 250 .45 .25 130 TI-208 .002 0.02 10 .03 30 .06 .03 30 Ra-224 - --.- .75 -- --

Ra-226 -- -- - - -- .15 - --

Ac-228 .01 0.07 20 .10 70 .25 .10 50

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 Gases3 Fish Milk Products Sediment Analysis pCi/L pCi/m p "/k wet pCi/L pCi/ka. wet pCi/k.* dry gross beta 4 I x 10.2 N.A. N.A. N.A. N.A.

H-3 2000" 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.

ib 1-131 7x 10.2 N.A. 1 60 N.A.

2 Cs-134 15 5 X10" 130 15 60 150 Cs-137 18 6x 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 pCi/liter. 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 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 designed 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 milk samples every week, on a random basis each farm 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.

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 verify that the laboratory can detect very low levels of activity.

Another category of quality control samples is the 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 2009, 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 Eckert and Ziegler Analytics, during 2009. The results of TVA's participation in this cross-check program are presented in Table F-1. As shown in Table F-I, the result for the Cs-1 34 reported for the third quarter gamma in air filter cross check was too low. A review of the lab results of other gamma cross checks containing Cs-134 analyzed during 2009 verified that all other Cs-134 results for QC samples were within the applicable agreement limits. This data included two cross checks analyzed after the sample with the low result. Corrective action program problem evaluation report (PER) 222670 was initiated to document the investigation of this Cs-134 measurement.

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 Results For 2009 External Cross Checks Results Test Period Sample Type / Analysis Known TVA Agreement First Quarter Water (pCi/L)

Gross Beta 2.35E+02 2.37E+02 1.01 Water (pCi/Filter) 3H 4.48E+03 5.78E+03 1.29 First Quarter Water (pCi/L) 1'1 6.90E+01 6.91E+01 1.00

'41Ce 1.20E+02 1.18E+02 0.98 5"Cr 3.87E+02 3.91E+02 1.01

'34Cs 1.19E+02 I.IOE+02 0.92

'"Cs 1.41 E+02 1.45E+02 1.03 59Co 1.51 E+02 1.501E+02 0.99 34Mn 1.62E+02 1.69E+02 1.04 "9Fe 1.27E+02 1.22E+02 0.96 63Zn 1.97E+02 2.06E+02 1.05

'Co 1.80E+02 1.89E+02 1.05 First Quarter Milk (pCiIL)

"3'1 7.95E+01 7.91E+01 0.99

'9Sr 8.35E+01 8.84E+01 1.06 9"Sr 1.33E+01 1.52E+01 1.14 Third Quarter Water (pCi/L) 3H 1.41E+04 1.44E+04 1.02 Third Quarter Sand (pCi/gram)

"4'Ce 0.640 0.613 0.96 S'Cr 0.515 0.513 1.00

"'Cs 0.287 0.269 0.94 137Cs 0.431 0.442 1.03 "sCo 0.232 0.233 1.00

.4Mn 0.480 0.502 1.05 "9Fe 0.343 0.350 1.02 6"Zn 0.474 0.503 1.06 "Co 0.373 0.389 1.04 Third Quarter Air Filter (pCi/filter)

Gross Beta 80.1 69.3 0.87 Third Quarter Air Filter (pCi/filter)

"11Ce 228.0 198.0 0.87 5tCr 183.0 168.0 0.92 "34Cs 102.0 78.7 0.77

'MCs 153.0 139.0 0.91 58Co 82.3 80.9 0.98 "Mn 171.0 167.0 0.98 "9Fe 122.0 121.0 0.99 6sZn 169.0 170.0 1.01 "Co 133.0 120.0 0.90 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.

The location of the nearest resident changed in one sector in 2009. The location of the nearest garden as identified in the 2009 survey changed in six 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 2008 and 2009.

Table G- I BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within 8 km (5 Miles) of Plant mrem/year 2008 Survey 2009 Survey r

Approximate Approximate Distance Annual Distance Annual Sector Meters Dose Meters Dose N 2000 0.45 2000 0.45 NNE 2590 0.14 2590 0.14 NE 4096 0.12 2879 0.13 ENE 2458 0.17 2458 0.17 E 1290 0.47 1290 0.47 ESE 1860 0.22 1860 0.22 SE a a SSE a a S 4482 0.15 4482 0.15 SSW 4169 0.18 4169 0.18 SW 4458 0.10 4458 0.10 WSW 3976 0.08 3976 0.08 W 2530 0.19 2530 0.19 WNW 5470 0.10 5470 0.10 NW 3373 0.30 3373 0.30 NNW 1639 0.76 1639 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 mrem/year 2008 Survey 2009 Survey Approximate Approximate Number of Distance Annual Distance Annual Gardens Within Sector Meters Dose Meters Dose 3 miles (2009)

N 2000 8.11 5394 2.04 0 NNE 4345 1.42 2834 2.54 1 NE 4313 1.27 2979 2.08 3 ENE 4319 1.33 4319 1.33 1 E 1689 5.68 1689 5.68 3 ESE 2125 5.03 1812 6.18 2

,! SE a a 0 SSE a a 0 S 4482 2.28 4482 2.28 0 SSW 4959 2.09 4959 2.09 0 SW 4859 1.03 4859 1.03 0 WSW 4578 0.56 4578 0.56 W 3120 1.08 2850 1.21 WNW a a 0 NW a a 0 NNW 1791 9.95 1802 9.89 6 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 Onsite and Offsite BROWNS FERRY Nuclear Plant for Each Quarter - 2009 mR / Quarter (a)

Average External Gamma Radiation Levels (b) 1st qtr 2nd qtr 3rd qtr 4th qtr mR/yr Average, 0 - 2 miles 11.5 15.1 16.1 13.1 56 (onsite)

Average,

> 2 miles 9.3 12.4 12.5 9.9 44 (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 TABLE H - 2 DIRECT RADIATION LEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels=

mR / quarter Map TLD Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Location Station Direction, Distance, Jan - Mar Apr - Jun Jul - Sep Oct - Dec Exposure Number Number degrees miles 2009 2009 2009 2009 mR/Year 7 N-1 348 1.0 12.5 16.9 17.6 13.2 60.2 75 N-1A 355 1.0 13.0 15.4 18.1 15.7 62.2 38 N-2 I 5.0 11.0 11.4 12.1 8.6 43.1 8 NNE-1 12 .9 9.0 14.4 14.1 (1) 50.0 39 NNE-2 31 .7 12.0 17.4 16.1 15.7 61.2

$, 40 NNE-3 19 5.2 7.0 12.9 11.6 10.1 41.6

! 41 NE-1 51 .8 14.0 15.9 15.1 14.2 59.2 42 NE-2 49 5.0 12.5 15.4 13.6 11.2 52.7 2 NE-3 56 10.9 6.5 14.9 12.1 8.6 42.1 9 ENE-1 61 .9 15.0 17.4 18.1 14.2 64.7 43 ENE-2 62 6.2 11.0 14A 15.1 10.1 50.6 44 E-1 85 .8 13.0 16.9 17.6 15.2 62.7 45 E-2 91 5.2 9.0 12.9 11.1 9.1 42.1 6 E-3 90 23.1 12.5 14.9 11.6 12.7 51.7 46 ESE-1 110 .9 6.5 11.9 14.6 11.7 44.7 47 ESE-2 112 3.0 9.5 12.9 12.1 11.7 46.2 48 SE-1 130 .5 11.0 16.9 18.1 13.2 59.2 49 SE-2 135 5.4 9.0 10.4 13.1 12.7 45.2 50 SSE-1 163 5.1 10.5 14.4 13.1 11.7 49.7 3 SSE-2 165 7.5 13.0 9.9 15.1 9.1 47.1 51 S-1 185 3.1 10.0 11.9 14.6 10.6 47.1 note (1) Sum of available quarterly data normalized to 1 year for the annual exposure value

TABLE H - 2 continued DIRECT RADIATION LEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels mR / quarter Map TLD Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Location Station Direction, Distance, Jan - Mar Apr - Jun Jul - Sep Oct - Dec Exposure Number Number d2rees miles 2009 2009 2009 2009 mR/year 52 S-2 182 4.8 6.5 11.4 12.1 8.6 38.6 53 SSW-1 203 3.0 6.5 10.4 12.1 6.6 35.6 54 SSW-2 199 4.4 10.0 12.4 14.1 8.1 44.6 55 SW-1 228 1.9 10.5 12.4 12.1 9.1 44.1 56 SW-2 219 4.7 10.5 10.4 12.6 9.1 42.6 57 SW-3 224 6.0 7.5 13.9 12.6 7.1 41.1

'* 58 WSW-1 244 2.7 6.0 10.9 11.1 8.1 36.1 59 WSW-2 251 5.1 9.0 11.9 13.1 12.7 46.7 60 WSW-3 257 10.5 7.0 11.4 11.1 10.6 40.1 61 W-1 275 1.9 9.0 9.9 15.6 10.6 45.1 62 W-2 268 4.7 14.0 10.9 12.1 10.6 47.6 5 W-3 275 31.0 9.0 9.9 10.1 9.6 38.6 64 WNW-1 291 3.3 9.5 14.4 12.1 11.2 47.2 65 WNW-2 293 4.4 8.0 12.9 14.6 9.1 44.6 66 NW-1 326 2.2 6.0 9.9 9.6 7.6 33.1 67 NW-2 321 5.3 13.0 13.9 14.6 12.7 54.2 1 NW-3 310 13.8 8.0 10.4 9.6 8.1 36.1 68 NNW-1 331 1.0 11.5 15.9 15.1 10.6 53.1 10 NNW-2 331 1.7 11.5 15.4 17.6 13.2 57.7 69 NNW-3 339 5.2 9.0 15.4 13.6 11.2 49.2

RADIOACTIVITY IN AIR FILTER PCI/M3 - 0.037 BQ/M3 Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported J Measurements Performed See Note 1 See Note 2 See Note 2 See Note 2 GROSS BETA 572 2.00E-03 2.06E-02 (4681468) LM-6BF BAKER BOTrOM 2.14E-02 (52 / 52) 2.02E-02 (104 /104) 8.99E 3.31E-02 3.0 MILES SSW 1.13E 3.14E-02 9.21E 3.1OE-02 GAMMA SCAN (GELI) 143 AC-228 1.00E-02 117 VALUES < LLD LM-6BF BAKER BOTTOM 13 VALUES < LLD 26 VALUES < LLD 3.0 MILES SSW 1.19E-01 (13/13) 1.12E-01 (26/26)

BE-7 2.OOE-02 1.13E-01 (117/117) LM-6BF BAKER BOTTOM 3.71E 1.63E-01 3.0 MILES SSW 9.20E 1.61E-01 8.02E 1.50E-01 BI-214 5.OOE-03 1.52E-02 (1161117) LM-7BF LAKEVIEW 2.06E-02 (12/13) 1.43E-02 (26/ 26) 5.10E 5.45E-02 2.1 MILES WEST 6.OOE 5.45E-02 5.40E 5.06E-02 -"

,:hK-40 4.OOE-02 4.21E-02 (1/117) LM1 BF NORTHWEST 4.21 E-02 (1 /13) 4.48E-02 (1/26) 4.21E 4.21E-02 1.0 MILE N 4.21E 4.21 E-02 4.48E 4.48E-02 PB-212 5.OOE-03 117 VALUES < LLD LM-6BF BAKER BOTTOM 13 VALUES < LLD 26 VALUES < LLD 3.0 MILES SSW 1.53E-02 (114/117) 1.93E-02 (13/ 13) 1.42E-02 (25 / 26)

PB-214 5.OOE-03 LM4 BF TRAILER P 5.40E 5.09E-02 1.7 MILES NNW 6.90E 4.58E-02 5.50E 4.63E-02 TL-208 2.OOE.03 117 VALUES < LLD LM-6BF BAKER BOTTOM 13 VALUES < LLD 26 VALUES < LLD 3.0 MILES SSW 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).

RADIOACTIVITY IN CHARCOAL FILTER PCIIM3 - 0.037 BQJM3 Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 572 BI-214 5.00E-02 8.02E-02 (156/468) PM-3 BF DECATUR AL 1.10E (8152) 8.13E-02 (26 / 104) 5.01E 2.07E-01 8.2 MILES SSE 5.55E 2.07E-01 5.04E 1.58E-01 1-131 3.OOE-02 SEE NOTE 3 K-40 3.00E-01 3.88E-01 (103/468) PM-1 ROGERSVILLE AL 4.09E-01 (12/52) 3.42E-01 (23/104) 3.01E 7.28E-01 13.8 MILES NW 3.01E 6.14E-01 3.00E 4.68E-01 PB-212 3.00E-02 468 VALUES < LLD PM-3 BF DECATUR AL 52 VALUES < LLD 104 VALUES < LLD 8.2 MILES SSE 1.05E-01 (961468) PM-3 BF DECATUR AL 1.24E-01 (5 / 52) 9.85E-02 (12/ 104)

PB-214 7.00E-02 7.00E 2.52E-01, 8.2 MILES SSE 7.09E 2.20E-01 7.24E 1.34E-01 0~

61 t~ TL-208 2.OOE-02 468 VALUES < LLD LM-7BF LAKEVIEW 52 VALUES < LLD 104 VALUES < LLD 2.1 MILES WEST TL-209 -1.00E+00 3.30E-03 (1 /468) LM2 BF NORTH 3.30E-03 (1/ 52) 104 VALUES < LLD 3.30E 3.30E-03 0.9 MILE NNE 3.30E 3.30E-03 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 (F).

Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses 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.

Note: 3. The analysis of Charcoal

RADIOACTIVITY IN SOIL PCIIGM - 0.037 BQIG (DRY WEIGHT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Perfonmed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GEU) 11 AC-228 2.50E-01 1.23E+00 (919) PM-3 BF DECATUR AL 1.51E+00 (1/1) 8.35E-01 (2/2) 7.00E 1.51E+00 8.2 MILES SSE 1.51E+00 - 1.51E+00 6.63E-01 - 1.01E+00 BE-7 2.50E-01 3,55E-01 (219) LM1 BF NORTHWEST 3.79E-01 (1/ 1) 2.95E-01 (1/2) 3.30E 3.79E-01 1.0 MILE N 3.79E 3.79E-01 2.95E-01 - 2.95E-01 BI-212 4.50E-01 1.22E+00 (919) LM4 BF TRAILER P 1.60E+00 (1 1) 8.32E-01 (2/2) 5.02E 1.60E+00 1.7 MILES NNW 1.60E+00 - 1.60E+00 5.76E 1.09E+00 BI-214 1.50E-01 1.04E+00 (9/9) PM-1 ROGERSVILLE AL 1.23E+00 (1 1) 8.53E-01 (2/2) 6.62E 1.23E+00 13.8 MILES NW 1.23E+00 - 1.23E+00 7.26E 9.79E-01 CS-137 3.00E-02 1.15E-01 (9/9) PM-2 BF ATHENS AL 2.93E-01 (1 1) 9.18E-02 (2/2) 3.25E 2.93E-01 10.9 MILES NE 2.93E 2.93E-01 8.19E 1.02E-01

,=:

K-40 7.50E-01 5.47E+00 (9/9) LM2 BF NORTH 9.40E+00 (1 1) 3.99E+00 (2/2) 2.86E+00 - 9.40E+00 0.9 MILE NNE 9.40E+00 - 9.40E+00 3.59E+00 - 4.40E+00 PA-234M 4.00E+00 4.30E+00 (119) LM1 BF NORTHWEST 4.30E+00 (1 1 1) 2 VALUES < LLD 4.30E+00 - 4.30E+00 1.0 MILE N 4.30E+00 - 4.30E+00 PB-212 1.001E-01 1.15E+00 (9/9) LM2 BF NORTH 1.43E+00 (1 / 1) 8.22E-01 (2/2) 6.24E 1.43E+00 0.9 MILE NNE 1.43E+00 - 1.43E+00 6.52E-01 - 9.91E-01 PB-214 1.50E-01 1.12E+00 (9/9) LM2 BF NORTH 1.32E+00 (1 / 1) 9.26E-01 (2 / 2) 7.46E 1.32E+00 0.9 MILE NNE 1.32E+00 - 1.32E+00 8.27E 1.02E+00 RA-226 1.50E-01 1.04E+00 (9/9) PM-1 ROGERSVILLE AL 1.23E+00 (1 / 1) 8.53E-01 (2/2) 6.62E 1.23E+00 13.8 MILES NW 1.23E+00 - 1.23E+00 7.26E-01 - 9.79E-01 TL-208 6.00E-02 3.75E-01 (9 / 9) PM-3 BF DECATUR AL 4.70E-01 (1 / 1) 2.80E-01 (2/2) 2.12E 4.70E-01 8.2 MILES SSE 4.70E 4.70E-01 2.26E-01 - 3.34E-01 SR 89 11 1.60E+00 9 VALUES < LLD 2 VALUES < LLD SR 90 11 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).

RADIOACTIVITY IN APPLES PCI/KG - 0.037 BQ/KG (WET WT)

Name of Fadlity. BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GEU) 2 BI-214 4.OOE+01 5.14E+01 (111) LM-6BF BAKER BOTTOM 5.14E+01 (1I1) 6.29E+01 (111) 5.14E+01 - 5.14E+01 3.0 MILES SSW 5.14E+01 - 5.14E+01 6.29E+01 .- 6.29E+01 K-40 2.50E+02 9.97E+02 (1 / 1) LM-6BF BAKER BOTTOM 9.97E+02 (1 /1) 8.98E+02 (1 /1) 9.97E+02 - 9.97E+02 3.0 MILES SSW 9.97E+02 - 9.97E+02 8.96E+02 - 8.96E+02 PB-212 4.00E+01 1 VALUES < LLD LM-6BF BAKER BOTTOM 1 VALUES < LLD I VALUES < LLD 3.0 MILES SSW PB-214 8.00E÷01 1 VALUES < LLD LM-6BF BAKER BOTTOM 1 VALUES < LLD 1 VALUES < LLD 3.0 MILES SSW a,.

0" 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).

RADIOACTIVITY IN CABBAGE PCI/KG - 0.037 BQ/KG (WET WT)

Name of Faclity: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 BI-214 4.00E+01 6.93E+01 (1 / 1) LM4 BF TRAILER P 6.93E+01 (I / 1) 5.75E+01 (111) 6.93E+01 - 6.93E+01 1.7 MILES NNW 6.93E+01 - 6.93E+01 5.75E+01 - 5.75E+01 K-40 2.50E+02 1.52E+03 (1 / 1) LM4 BF TRAILER P 1.52E+03 (I1/1) 1.55E+03 (I /I) 1.52E+03 - 1.52E+03 1.7 MILES NNW 1.52E+03 - 1.52E+03 1.55E+03 - 1.55E+03 PB-214 8.OOE+01 1 VALUES < LLD LM4 BF TRAILER P 1 VALUES < LLD 1 VALUES < LLD 1.7 MILES NNW TL-208 3.OOE+01 1 VALUES < LLD LM4 BF TRAILER P I VALUES < LLD 1 VALUES < LLD 1.7 MILES NNW

-3

-J 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).

RADIOACTMTY IN CORN PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 BI-214 4.00E+01 1.23E+02 (1 1) LM-6BF BAKER BOTTOM 1.23E+02 (I / 1) 1 VALUES < LLD 1.23E+02 - 1.23E+02 3.0 MILES SSW 1.23E+02 - 1.23E+02 K-40 2.50E+02 2.17E+03 (1 I1) LM-6BF BAKER BOTTOM 2.17E+03 (1/1) 1 VALUES < LLD 2.17E+03 - 2.17E+03 3.0 MILES SSW 2.17E+03 - 2.17E+03 PB-214 8.00E+01 1.27E+02 (1 /1) LM-6BF BAKER BOTTOM 1.27E+02 (I / 1) 1 VALUES < LLD 1.27E+02 - 1.27E+02 3.0 MILES SSW 1.27E+02 - 1.27E+02 H

00 CD x0 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).

RADIOACTIVITY IN GREEN BEANS PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 AC-228 5.OOE+01 1 VALUES < LLD 2 MILES NE 1 VALUES < LLD 1-VALUES < LLD BI-214 4.OOE+01 1.49E+02 (111) 2 MILES NE 1.49E+02 (1 / 1) 9.75E+01 (111) 1.49E+02 - 1.49E+02 1.49E+02 - 1.49E+02 9.76E+01 - 9.75E+01 K-40 2.50E+02 2.45E+03 (I /1) 2 MILES NE 2.45E+03 (111) 2.13E+03 (1/ 1) 2.45E+03 - 2.45E+03 2.45E÷03 - 2.45E+03 2.13E+03 - 2.13E+03 PB-214 8.00E+01 1.21E+02 (1/1) 2 MILES NE 1.21E+02 (I/1) 8.84E+01 (1/ 1) 1.21E+02 - 1.21E+02 1.21E+02 - 1.21E+02 8.84E+01 - 8.84E+01

-i

61. 0D 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).

RADIOACTIVITY IN POTATOES PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility, BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GEU) 2 BI-214 4.OOE+01 7.24E+01 (I /1) LM4 BF TRAILER P 7.24E+01 (11 / 1) 7.74E+01 (1 /1) 7.24E+01 - 7.24E+01 1.7 MILES NNW 7.24E+01 - 7.24E+01 7.74E+01 - 7.74E+01 K-40 2.50E+02 4.01 E+03 (1111) LM4 BF TRAILER P 4.01E+03 (I 11) 3.98E+03 (1 /1) 4.01 E+03 - 4.01 E+03 1.7 MILES NNW 4.01E+03 - 4.01E+03 3.98E+03 - 3.98E+03 PB-214 8.OOE+01 1 VALUES < LLD LM4 BF TRAILER P 1 VALUES < LLD 8.24E+01 (1 / 1) 1.7 MILES NNW 8.24E+01 - 8.24E+01 0~

Cs 0

0 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).

RADIOACTIVITY IN TOMATOES PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number. 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Umit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note I See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GEU) 2 BI-214 4.OOE+01 5.93E+01 (1 /1) LM4 BF TRAILER P 5.93E+01 (I /1) 7.86E+01 (1 /1) 5.93E+01 - 5.93E+01 1.7 MILES NNW 5.93E+01 - 5.93E+01 7.86E+01 - 7.86E+01 K-40 2.50E+02 2.06E+03 (1 /1) LM4 BF TRAILER P 2.06E+03 (111) 1.89E+03 (I / 1) 2.06E+03 - 2.06E+03 1.7 MILES NNW 2.06E+03 - 2.06E+03 1.89E+03 - 1,89E+03 PB-214 8.OOE+01 1 VALUES < LLD LM4 BF TRAILER P I VALUES < LLD 1 VALUES < LLD 1.7 MILES NNW TL-208 3.OOE+01 1 VALUES < LLD LM4 BF TRAILER P 1 VALUES < LLD 1 VALUES < LLD 1.7 MILES NNW

-3 T"

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).

RADIOACTIVITY INSURFACE WATER(Total)

PCI/L - 0.037 BO/L Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number. 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note I See Note 2 See Note 2 See Note 2 Measurements GROSS BETA 26 1.90Ee00 2.60E+00 (10 /13) TRM 293.5 2.60E+00 (10/13) 2.63E+00 (9/13) 2.04E+00 - 3.08E+00 2.04E+00 - 3.08E+00 2.11E+00 - 3.33E+00 GAMMA SCAN (GELI) 26 AC-228 2.OOE+01 13 VALUES < LLD TRM 293.5 13 VALUES < LWD 13 VALUES < LLD BI-214 2.OOE+01 3.81E+01 (4 113) TRM 293.5 3.81E+01 (4/13) 3.28E+01 (6 / 13) 2.39E+01 - 4.59E+01 2.39E+01 - 4.59E+01 2.33E+01 - 4.92E+01 K-40 1.OOE+02 13 VALUES < LID TRM 293.5 13 VALUES < LLD 13 VALUES < LWD

- PB-212 1.5OE+01 13 VALUES < LLD TRM 293.5 13 VALUES < LLD 13 VALUES < LLD to PB-214 2.00E+011 2.79E+01 (2/13) TRM 293.5 2.79E+01 (2 / 13) 2.77E+01 (3/13) 2.69E+01 - 2.89E+01 2.69E+01 - 2.89E+01 2.35E+01 - 3.26E+01 TL-208 I .00E+01 13 VALUES < LLD TRM 293.5 13 VALUES < LLD 13 VALUES < LLD TRITIUM 8 2.70E+02 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).

RADIOACTIVITY IN PUBLIC WATER(Total)

PCIIL - 0.037 BQ/L Name of Facility. BROWNS FERRY NUCLEAR PLANT Docket Number. 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GROSS BETA 78 1.90E+00 2.40E+00 (40/65) CHAMPION PAPER 2.62E+00 (7/13) 2.63E+00 (9/13) 1.91E+00 - 3.71E+00 TRM 282.6 1.97E+00 - 3.08E+00 2.11E+00 - 3.33E+00 GAMMA SCAN (GEU) 78 AC-228 2.00E2+01 2.69E+01 (2/65) W MOR-E LAWR WAT ATH 3.15E+01 (1113) 13 VALUES < LLD 2.23E+01 - 3.15E+01 TRM 286.5 3.15E+01 - 3.15E+01 BI-214 2.OOE+O1 4.03E+01 (24/65) CHAMPION PAPER 5.65E+01 (5/13) 3.28E+01 (6113) 2.01E+01 - 1.12E+02 TRM 282.6 2.08E+01 - 1.03E+02 2.33E+01 - 4.92E+01 K-40 1.0OE+02 65 VALUES < LLD MUSCLE SHOALS AREA 13 VALUES < LLD 13 VALUES < LLD

--]

TRM 259.5 o"

-!j PB-212 1.50E+01 65 VALUES < LLD MUSCLE SHOALS AREA TRM 259.5 13 VALUES < LLD 13 VALUES < LLD ,=

PB-214 2.00E+011 4.07E÷01 (12/65) MUSCLE SHOALS AREA 9.39E+01 (1 /13) 2.77E+01 (3/13) L*J 2.35E+01 - 9.39E+01 TRM 259.5 9.39E+01 - 9.39E+01 2.35E+01 - 3.26E+01 TH-234 -1.OOE+00 1.43E+01 (1 /65) W MOR-E LAWR WAT ATH 1.43E+01 (1 113) 13 VALUES < LLD 1.43E+01 - 1.43E+01 TRM 286.5 .1.43E+01 - 1.43E+01 TL-208 1 .OOE+01 65 VALUES < LLD FLORENCE, AL 13 VALUES < LLD - 13 VALUES < LLD TRM 259.8 TRITIUM 24 2.70E+02 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).

RADIOACTIVITY INWELL WATER(Total)

PCI/L - 0.037 BO/L Name of Fadility: BROWNS FERRY NUCLEAR PLANT Docket Number. 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 26 AC-228 2.00E+011 13 VALUES < LLD BFN WELL #6 13 VALUES < LLD 13 VALUES < LLD 0.02 MILES W BI-212 5.OOE+01 13 VALUES < LLD BFN WELL #6 13 VALUES < LLD 13 VALUES < LLD 0.02 MILES W BI-214 2.OOE+01 3.47E+01 (7/13) BFN WELL #6 3.47E+01 (7 /13) 1.19E+02 (13/13) 2.13E+01 - 5.32E+01 0.02 MILES W 2.13E+01 - 5.32E+01 2.84E+01 - 1.96E+02 K-40 1.00E+02 13 VALUES < LLD BFN WELL #6 13 VALUES < LLD 13 VALUES < LLD 0.02 MILES W PB-212 1.50E+01 13 VALUES < LLD BFN WELL #6 13 VALUES < LLD 13 VALUES < LLD -i to 0.02 MILES W Cr

,=

PB-214 2.00E+011 3.04E+01 (7/13) BFN WELL #6 3.04E+01 (7/ 13) 1.14E+02 (13/13) 2.28E+01 - 4.56E+01 0.02 MILES W 2.28E+01 - 4.56E+01 3.93E+01. - 1.98E+02 TL-208 I.00E401 13 VALUES < LLD BFN WELL #6 13 VALUES < LLD 13 VALUES < LLD 0.02 MILES W TRITIUM a 2.70E+02 4 VALUES < LLD 4 VALUES < LLD 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).

RADIOACTIVITY IN COMMERCIAL FISH PCI/GM - 0.037 BQ/G (DRY WEIGHT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number. 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Umit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 4 BI-214 11.0012-01 1.48E-01 (2 /2) WHEELER RES I.48E-01 (2/2) 1.82E-01 (2/2) 1.45E 1.52E-01 TRM 275-349 1.45E 1.52E-01 1.26E 2.37E-01 CS-137 3.OOE-02 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 4.08E-02 (2/2)

TRM 275-349 3.41 E 4.75E-02 K-40 4.00E-01 1.50E+01 (2 / 2) WHEELER RES 1.50E+01 (2 / 2) 1.78E+01 (2/2) 1.36E+01 - 1.63E+01 TRM 275-349 1.36E+01 - 1.63E+01 1.76E+01 - 1.80E+01 PB-212 4.OO12-02 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 2 VALUES < LLD TRM 275-349 PB-214 5.00E-01 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 2 VALUES < LLD TRM 275-349 co LA 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).

RADIOACTIVITY IN GAME FISH PCI/GM - 0.037 BQ/G (DRY WEIGHT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 4 BI-214 I .OOE-01 1.22E-01 (212) WHEELER RES 1.22E-01 (212) 1.74E-01 (2/2) 1.06E 1.39E-01 TRM 275-349 1.06E 1.39E-01 1.56E 1.92E-01 CS-137 3.OOE-02 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 3.72E-02 (2 / 2)

TRM 275-349 3.38E 4.06E-02 K-40 4.0OE-01 1.60E+01 (2 /2) WHEELER RES 1.60E+01 (212) 1.53E+01 (2/2) 1.58E+01- 1.62E+01 TRM 275-349 1.58E+01 - 1.62E+01 1.41E+01 - 1.66E+01 PB-212 4.00E-02 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 2 VALUES < LLD TRM 275-349 PB-214 5.OOE-01 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 2 VALUES < LLD CD TRM 275-349 9'TL-208 3.OOE-02 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 2 VALUES < LLD TRM 275-349 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).

RADIOACTIVITY IN SHORELINE SEDIMENT PCIIGM - 0.037 BQ/G (DRY WEIGHT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number. 50-259,260.296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note I See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 6 AC-228 2.50E-01 3.23E-01 (1/14) MALLARD CREEK REC AR 3.23E-01 (1 / 2) 4.94E-01 (2 / 2) 3.23E 3.23E-01 TRM 293.0 3.23E 3.23E-01 4.24E 5.64E-01 BE-7 2.50E-01 4 VALUES < LLD JOE WHEELER ST PARK 2 VALUES < LLD 2 VALUES < LLD TRM 279.5 BI-212 4.60E-01 4 VALUES < LLD MALLARD CREEK REC AR 2 VALUES < LLD 5.66E-01 (2 / 2)

TRM 293.0 5.22E 6.11E-01 BI-214 1.50E-01 3.18E-01 (2/4) MALLARD CREEK REC AR 3.18E-01 (2/2) 4.04E-01 (2/2) 1.52E 4.84E-01 TRM 293.0 1.52E 4.84E-01 3.65E 4.43E-01 K-40 7.50E-01 4 VALUES < LLD JOE WHEELER ST PARK 2 VALUES < LLD 4.03E+00 (2/2)

TRM 279.5 3.94E+00 - 4.11E+00 CD

, PB-212 1.00E-01 2.12E-01 (2/4) MALLARD CREEK REC AR 2.12E-01 (2/2) 4.85E-01 (2/2) 1.17E-01 - 3.07E-01 TRM 293.0 1.17E 3.07E-01 4.36E 5.35E-01 PB-214 1.50E-01 5.34E-01 (1/4) MALLARD CREEK REC AR 5.34E-01 (1 /2) 4.19E-01 (2 /2) 5.34E 5.34E-01 TRM 293.0 5.34E 5.34E-01 3.70E 4.68E-01 RA-226 1.50E-01 3.18E-01 (2 /4) MALLARD CREEK REC AR 3.18E-01 (212) 4.04E-01 (2/2) 1.52E 4.84E-01 TRM 293.0 1.52E 4.84E-01 3.65E 4.43E-01 TL-208 6.00E-02 9.99E-02 (1/4) MALLARD CREEK REC AR 9.99E-02 (112) 1.74E-01 (2/2) 9.99E 9.99E-02 TRM 293.0 9.99E 9.99E-02 1.46E 2.03E-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).

Direct Radiation Levels BROWNS FERRY NUCLEAR PLANT Four Quarter Moving Average 25 20 00 CO) 15 E 10 5 1 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year

-I - On-Site .o-- Off-SiteI

Annual Average Gross Beta Activity in Air Filters - BFNP 0.25 Initial plant operation in August, 1973 E

0.20 0.ILI

,* 0.15 43 Preoperational Awerage 0.10 0.05 0.00 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year 1 -0Indicator - Control ---- -I

Annual Average Cs-137 Activity in Soil - BFNP 3

Initial plant operation in August, 1973 Ee2 19 1970"19Preoperational 9erage 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year

Annual Average Gross Beta Activity in Surface Water - BFNP 6

Preoperational Axerage COC 4 2 Initial Plant Operation in Note: no gross beta August, 1973 measurements were made in 1978 0

1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year

-dowstream upstream

Annual Average Gross Beta Activity in Drinking Water - BFNP 6

Initial plant operation in August, 1973 4

00J I!, Preoperational Average Z,

2 0

1965 1970 1975 1980. 1985 1990 1995 2000 2005 2010 2015 Calendar Year I @- dowitream -- Upstiew.m

Annual Average Cs-137 Activity in Fish Flesh Game Fish - BFNP 0.5 Initial plant operation in August, 1973 0.4 0.3 Preoperational Aerage 0.2 0.1 0.0 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year I--i--dovistream -G-- upstream