ML16137A249

Transmittal of 2015 Annual Radiological Environmental Operating Report

ML16137A249
Person / Time
Site:	Browns Ferry
Issue date:	05/15/2016
From:	Bono S M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML16137A249 (88)

Text

Te nne s s ee V alley A uth o ri ty , Post Office Box 2000 , Decatu r , A l a b a m a 35609-2000 May 1 5 , 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Browns Ferry Nuclear Plant , Units 1 , 2 , and 3 10 CFR 50.4 Renewed Facility Operating License Nos. DPR-33 , DPR-52 , and DPR-68 NRC Docket Nos. 50-259 , 50-260 , and 50-296

Subject:

2015 Annual Radiological Environmental Operating Report I n accordance with the Browns Ferry Nuclear Plant Technical Specification 5.6.2 and Offsi t e Dose Calculation Manual Administrative Control Section 5.1 , the Tennessee Valley Authority is submitting the 2015 Annual Radiological Environmental Operating Report for Browns Ferry Nuclea r Plant , Units 1 , 2 , and 3. Enclosed is the subject report for the pe ri od of January 1 , 2015 , through December 31 , 2015. There are no new regulatory commitments contained within this letter. If you have any questions , please contact J. L. Paul at (256) 729-2636. E nclosur e: 20 15 Annual Radiological Environmenta l Oper a ting Report cc (w/Enclosure): NRC Regional Administrator

-Region II NRC Senior Resident Inspector

-Browns Ferry Nuclea r Plant Enclosure Browns Ferry Nuclear Plant Units 1, 2, and 3 2015 Annual Radiological Environmental Operating Repor t See Enclosed 2015 Annual Radiological Environmental Operating Report Browns Ferry Nuclear Plant ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT BROWNS FERRY NUCLEAR PLANT 2015 TENNESSEE VALLEY AUTHORITY TABLE OF CONTENTS Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i 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 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

11 Atmospheric Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

13 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

14 Terrestrial Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

15 Sample Collection and Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

15 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

15 Liquid Pathway Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

17 Sample Collection and Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

17 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

18 Assessment and Evaluation........ . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

20 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

20 Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

21 References. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

22 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 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 -i-TABLE OF CONTENTS (continued)

Appendix A Radiological Environmental Monitoring Program and Sampling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

26 Appendix B Program Modifications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7 Appendix C Program Deviations.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

39 Appendix D Analytical Procedures................................

42 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. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

58 -ii-EXECUTIVE

SUMMARY

This report describes the Radiological Environmental Monitoring Program (REMP) conducted by the Tennessee Valley Authority (TVA) in the vicinity of the Browns Ferry Nuclear Plant (BFN) during the monitoring period of2015. The program is conducted in accordance with regulatory requirements to monitor the environment per 10 CFR 20, 10 CFR 50, and TV A procedures.

The REMP includes the collection and subsequent determination of radioactive material content in environmental samples. Various types of samples are collected within the vicinity of the plant, including air, water, food crops, soil, fish, shoreline sediment, and the measurement of direct radiation levels. The radiation levels of these samples are measured and then compared with results at control stations located outside the plant's vicinity and data collected at Browns Ferry Nuclear Plant prior to operations (preoperational data). This report contains an evaluation of the potential impact of BFN operations on the environment and general public. The vast majority of radioactivity measured in environmental samples from the BFN program can be contributed to naturally occurring radioactive materials.

In 2015, trace quantities of cesium (Cs)-137 were measured in soil and shoreline sediment.

The concentrations were typical of the levels expected to be present in the environment from past nuclear weapons testing or operation of other nuclear facilities in the region. The fallout from accidents at the Chernobyl plant in the Ukraine in 1986 and the Fukushima plant in Japan in 2011 may have also contributed to the low levels of Cs-137 measured in environmental samples. Tritium at concentrations slightly above the analytical detection limit was detected in water samples collected from Wheeler Reservoir and in one sample of groundwater collected from the onsite REMP well. These* levels of radioactive elements detected do not represent a significant contribution to the radiation exposure to members of the public. -I-INTRODUCTION This report describes and summarizes results of radioactivity measurements made in the vicinity of Browns Ferry Nuclear Plant (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 (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 ). 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)-235, 238, thorium (Th)-234, radium (Ra)-226, radon (Rn)-222 and 220, 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 Natural background dose equivalent Cosmic Terrestrial In the body Radon Total Medical (effective dose equivalent)

Nuclear energy Consumer products Total millirem (mrem)/Y ear Per Person 33 21 29 228 311 300 0.28 13 624 (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.

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 Nuclear Regulatory Commission (NRC) guidelines and in the ODCM, is limited as follows:

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

Any organ mrem/Y ear mrem/Y ear millirad (mrad)/Y ear go mrad/Year mrem/Y ear The Environmental Protection Agency 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 mrem/Year mrem/Y ear gs mrem/Y ear 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 e:ffluent 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 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 1 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 5200 people live within a 5-mile radius of the plant. The town of Athens has a population of about 24,000, and is approximately 10 miles northeast of BFN. Approximately 56,000 people live in the city of Decatur 10 miles southeast.

The cities of Madison and Huntsville have a combined population of approximately 230,000 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 11, 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 1and2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation on March 1, 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 effiuent 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 (REMP) and sampling locations are 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.

Program modifications made to the REMP are described in Appendix B. Program 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 ofBFN, a preoperational REMP 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, 1960s, and 1970s, 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 the Tennessee Valley Authority's (TV A's) Environmental Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area Radiological Laboratory in Muscle Shoals, Alabama, with exception of the strontium (Sr)-89, 90 analyses of soil samples which is performed by Teledyne Brown Engineering (TBE), Knoxville, TN. 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 AppendixH.

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 AppendixE.

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 REMP for the measurement of direct radiation.

This dosimeter contains four elements consisting of aluminum oxide detectors with open windows as well as plastic and copper filters. The dosimeter is processed using optical stimulated luminescence (OSL) technology to determine the amount of radiation exposure.

The dosimeters are placed approximately one 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 three months. The dosimeters are sent to Landauer InLight 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 American National Standards Institute (ANSI) N545-l 975 and Health Physics Society (HPS) Draft Standard N 13 .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 "off site." The quarterly gamma radiation levels determined from the dosimeters deployed around BFN in 2015 are summarized in Table H-1. The exposures are measured in milliroentgens (mR). For purposes of this report, one mR, one mrem, and one mrad are assumed to be numerically equivalent.

The rounded average annual exposures, as measured in 2015, are shown below: Onsite Stations Offsite Stations Annual Average Direct Radiation Levels mR/Year BFN 2015 69 55 The data in Table H-1 indicates that the average quarterly direct radiation levels at the BFN onsite stations are approximately 3 .6 mR/quarter higher than levels at the offsite stations.

This equates to 14.4 mR/year detected at the onsite locations.

This value falls below the EPA limit of 25 mrem/year total body. The difference in onsite and off site averages is consistent with levels measured for the preoperational and construction phases of TV A nuclear power plant sites where the average levels onsite were slightly higher than levels offsite. Figure H-1 compares plots of the data from the onsite stations with those from the offsite stations over the period from 1977 through 2015. The new Landauer lnLight Optically Stimulated Luminescence (OSL) dosimeters have been deployed since 2007 replacing the Panasonic UD-814 dosimeters used during the previous years. The data in Table H-2 contains the results of the individual monitoring stations.

The results reported in 2015 are consistent with direct radiation levels identified at locations which are not influenced by the operation ofBFN. 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 monitoring 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 Triethylenediamine (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 iodine (l)-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 2015 was consistent with levels reported in previous years. The annual average gross beta concentrations was 0.018 pCi/m 3* The annual averages of the gross beta activity in air particulate filters for the years 1968-2015 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 TV A 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 2015. 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-11. 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 2015 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. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. Samples of apples, cabbage, com, peas, potatoes, and tomatoes were collected from local gardens in 2015. Samples of these same food crops were purchased from area produce markets or private gardens 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-13 7. The average concentration measured in samples from indicator locations was 0.15 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-137 concentrations in soil is presented in Figure H-3. The concentration of Cs-13 7 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 2015 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 a 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 one 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 for gamma isotopic and 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 of raw untreated water is collected at the intake for the water plant. These samples are collected in the same manner as the surface water samples. These monthly samples are analyzed for gamma isotopic and 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 for gamma isotopic and 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 the 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 Only naturally occurring isotopes were identified by gamma spectral analysis of surface water. Tritium was detected in one downstream (indicator) sample and one upstream (control) sample. Tritium was measured at a concentration of 290 pCi/liter in the indicator sample and 295 p<;i/liter for the control sample. This tritium concentration represented only a small fraction of the Environmental Protection Agency (EPA) drinking water limit of20,000 pCi/liter.

The gross beta activity for surface water samples was consistent with the results from previous years. The average gross beta concentration measured in surface water samples was 2.5 pCi/liter.

A trend plot of the gross beta activity in surface water samples from 1968 through 2015 is presented in Figure H-4. A summary table of the results for this reporting period is shown in Table H-12. No fission or activation products were detected by the gamma analysis of drinking water. Gross beta activity averaged 2.4 pCi/liter at the downstream stations and 2.6 pCi/liter at upstream stations.

These results are consistent with previous monitoring results. Tritium was measured in drinking water samples at a maximum concentration of 337 pCi/liter.

This tritium concentration represented only a small fraction of the EPA drinking water limit of 20,000 pCi/liter.

The results are shown in Table H-13 and a trend plot of the gross beta activity from 1968 to 2015 is presented in Figure H-5. No fission or activation products were detected in groundwater samples from BFN REMP monitoring locations.

Tritium was detected, above the nominal LLD, in one sample collected from the indicator location at a concentration of 454 pCi/liter.

Results from the analysis of groundwater samples are presented in Table H-14. The only 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. The gamma spectroscopy analysis of shoreline sediment samples identified trace levels of Cs-137 in one sample collected from the upstream sampling location.

The concentration was 0.04 pCi/gram.

There was no Cs-137 detected in samples from the downstream locations.

The Cs-13 7 levels were consistent with levels present in the environment as the result of past nuclear weapons testing. The results of 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 TV A 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 calculated doses 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 BFN 2015 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, above the nominal LLD, in soil and shoreline sediment samples. The Cs-137 detected in these samples 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 (Figures H-1 through H-6) 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 result 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 I. Merril Eisenbud, Environmental Radioactivity, Academic Press, Inc., New York, NY, 1987. 2. National Council on Radiation Protection and Measurements, Report No. 160, "Ionizing Radiation Exposure of the Population of the United States," March 2009. 3. United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instruction Concerning Risks from Occupational Radiation Exposure," February 1996.

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

gCi/Liter Concentrations in gCi/Cubic Meter Eftluent Reporting Lower limit Eftluent Reporting Lower limit Analysis Concentration 1 Level 2 of Detection 3 Concentration*

Level 2 of Detection 3 H-3 1,000,000 20,000 270 I00,000 3.0 Cr-51 500,000 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 IO 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 0.03 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 IO 2,000 0.01 Note: l pCi = 3.7 xI0*2 Bq. Note: For those reporting levels that are blank, no value is given in the reference.

1. Table 2 of Appendix B to 10 CFR 20. 2. BFN Offsite Dose Calculation Manual, Table 2.3-3. 3. Table E-1 of this report.

LOUISVll.L£ L L. M \ I M I SS. c I< y GEORGIA V A. s C A R. lmfl -WATTS BAA NUCLEAR PLANT ---SEQUOYAH NUCL£AR PLANT llJI -8ELLEFONTE NUCLEAR PUWT J!I[ -BROWNS FERRY NUCLEAR PLANT ......

Figure 2 ENVIRONMENTAL EXPOSURE PATHWAYS OF MAN CUE TD RELEASES OF RADIOACTIVE MA TE RIAL TD THE ATMOSPHERE AND LAKE.

!fT:iftJ!!>----iii.;;;

-Diluted By Atmosphere Airborne Releases Exposure u MAN Animals By Man Liquid Releases Diluted By Lake (Milk.Meat)

.._ ___ __...., Shoreline 6 Exposure Consumed U By Animals c::::J Vegetation Uptake From Soil .___ ____ ___.. Drinking Water APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND SAMPLING LOCATIONS Exposure Pathway and/or Sample 1. AIRBORNE a. Particulates

b. Radioiodine

c. Soil Table A-1 (1of5) BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8 Number of Samples and Sampling and Locationsb Collection Frequency Six samples from locations (in Continuous sampler operation with different sectors) at or near the site sample collection as required by dust boundary(LM-1, LM-2, LM-3, LM-4, loading but at least once per 7 days. LM-6, and LM-7). Two samples from control locations greater than 10 miles from the plant (RM-I and RM-6). Three samples from locations in communities approximately I 0 miles from the plant (PM-I, PM-2, and PM-3). Same locations as air particulates.

Continuous sampler operation with charcoal canister collection at least once per 7 days. Samples from same locations as air Once every year. particulates. Type and Frequency of Analysis Analyze for gross beta radioactivity following filter change. Perform gamma isotopic analysis on each sample when gross beta activity is greater than 10 times the yearly mean activity for control samples. Perform gamma isotopic analysis on composite (by location) sample at least once per 31 days. 1-131 by gamma scan on each sample. Gamma scan, Sr-89, Sr-90 once per year.

Exposure Pathway and/or Sample 2. DIRECT RADIATION

3. WATERBORNE

a. Surface Water b. Drinking Water Table A-1 (2 of 5) BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8 Number of Samples and Sampling and Type and Frequency Locationsb Collection Frequency of Analysis 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 8 additional locations of special interest.

One sample upstream (TRM 306.0). Collected by automatic sequential-Gross beta and gamma isotopic on One sample immediately downstream type sampler with composite sample 4-week composite.

Composite for of discharge (TRM 293 .5). taken at least once per 31 daysc. tritium at least once per 92 days. One sample at the first potable Collected by automatic sequential-Gross beta and gamma isotopic on surface water supply downstream type sampler with composite sample 4-week composite.

Composite for from the plant (TRM 286.5). taken at least once per 31 daysc. tritium analysis at least once per 92 days.

Exposure Pathway and/or Sample b. Drinking Water (Continued)

c. Ground Water d. Shoreline Sediment Table A-1 (3 of 5) BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 0 Number of Samples and Sampling and Type and Frequency Locationsb Collection Frequency of Analysis Three additional samples of potable Grab sample taken from water supply Gross beta and gamma scan on surface water downstream from the at a facility using water from the 4-week composite.

Composite for plant (TRM 274.9, TRM 259.8, public supply being monitored.

tritium analysis at least once per 92 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. One sample adjacent to the plant Collected by automatic sequential-Gamma scan on each 4-week (Well No. 6R). type sampler with composite sample composite.

Composite for tritium taken at least once per 31 days. analysis at 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. (Farm B) 31 days. Composite for tritium analysis at least once per 92 days. One sample upstream from a At least once per 184 days. Gamma scan of each sample. recreational area {TRM 305).

Exposure Pathway and/or Sample d. Shoreline Sediment (Continued)

4. INGESTION

a. Fish Table A-1 (4 of 5) BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENT AL MONITORING PROGRAM 8 Number of Samples and Locationsb One sample from each of at least two downstream locations with recreational use (TRM 293 and TRM279.5).

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. Sampling and Collection Frequency At least once per 184 days. At least once per 184 days. Type and Frequency of Analysis Gamma scan of each sample. Gamma scan at least once per 184 days on edible portions.

Exposure Pathway and/or Sample b. Fruits and Vegetables Table A-1 (5 of 5) BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8 Number of Samples and Locationsb Samples of food crops such as greens, com, 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 a. The sampling program outlined in this table is that which was in effect at the end of 2015. 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 />. Type and Frequency of Analysis Gamma scan on edible portion. d. The sample location at the Decatur City Water Plant serves as a control sample for both surface water and drinking water.

Map Location Number.B 1 2 3 4 5 6 7 8 9 10 11 12 24 25 26 28 70 71 72 73 74 76 TableA-2 BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Approximate Indicator (I) Distance or Station Sector (Miles) Control CC) PM-1 NW 13.8 I PM-2 NE 10.9 I PM-3 SSE 7.5 I LM-7 w 2.1 I RM-1 w 31.0 c RM-6 E 23.4 c LM-1 NNW 1.0 I LM-2 NNE 0.9 I LM-3 ENE 0.9 I LM-4 NNW 1.7 I LM-6 SSW 3.0 I FannB NNW 6.8 c TRM306.0 12.0d c TRM259.6 34.4d I TRM274.9 19.ld I TRM293.5 o.5d I TRM259.8 34.2d I TRM286.5 7.5d I TRM305 11.0d c TRM293 1.0d I TRM279.5 14.5d I WellNo.6R NW 0.1 I Wheeler Reservoir (TRM 275-349) I Guntersville Reservoir (TRM 349-424) c a. See Figures A-1, A-2, and A-3 b. Sample codes: AP =Air Particulate Filter CF = Charcoal Filter (Iodine) PW = Public Water Samples Collectedb AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S w PW,SW PW PW SW PW PW SS SS SS w F F F =Fish S = Soil SW = Surface Water SS = Shoreline Sediment W = Well Water c. TRM = Tennessee River Mile d. Miles from plant discharge at (TRM 294)

TableA-3 BROWNS FERRY NUCLEAR PLANT ENVIRONMENTAL DOSIMETER LOCATIONS Map Approximate Onsite (On)b Location Distance or Numbe(l Station Sector (Miles) Offsite(Oft)

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-1 NNE 0.9 On 9 ENE-I 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-1 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 SS SW-I SW 1.9 On 56 SW-2 SW 4.7 Off S8 WSW-I 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-1 NW 2.2 Off 67 NW-2 NW 5.3 Off 68 NNW-1 NNW 1.0 On 69 NNW-3 NNW S.2 Off 75 N-IA N 1.0 On a See Figures A-1, 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 281.25 w 268.75 Figure A-1 Radiological Environmental Sampling Locations Within 1 mile of the Plant 5 348.75 N 191.25 s 168.75 Scale 0 Mlle E 1 w Figure A-2 Radiological Environmental Sampling Locations 1 to 5 miles from the Plant

• 0 tt i OJI I 1111.11 7U5 I Figure A-3 Radiological Environmental Sampling Locations Greater than 5 miles from the Plant w £ OU!5 o '"1 16 48 26 d& ta.CO APPENDIXB PROGRAM MODIFICATIONS APPENDIXB Radiological Environmental Monitoring Program Modifications Well 6, the site's indicator groundwater well, was located beneath the maintenance building, which was demolished.

Due to the construction of the new maintenance building and the loss of power to Well 6, the well was removed from the REMP program. A new well, Well 6R, was installed adjacent to the site to replace Well 6. This change was documented in CR1025091.

The location known as Champion Paper Co. at TRM 282.6 was removed from the REMP program due to the fact the location no longer produces its own potable water. The change was documented in CRI 031206.

APPENDIXC PROGRAM DEVIATIONS APPENDIXC Program Deviations Issues with sampling equipment resulted in missed air monitoring samples for one sampling period from one of eleven monitoring locations.

One water sample was not obtained during 2015 due to sampling equipment issues. Environmental dosimeters were missing at four locations during the year. Table C-1 provides details of these program deviations.

Table C-1 Radiological Environmental Monitoring Program Deviations Date Station Location SamnleTvne Descrintion 03/23/2015 LM-4 I. 7 Miles NNW Air Monitor During the weekly REMP filter change, the (AF/CF) technician found station LM-4 not working and contacted EPFS personnel.

An issue with the power switch was discovered and fixed. The monitor was returned to service the same day but the sample volume was not sufficient for analysis.

This issue was identified in CR 1004454. 07/06/2015 Well 6R 0.12 Miles NW Water The automatic sampler for Well 6R was being repaired by the vendor during this sampling period after an issue was discovered during the mid-cycle check. The composite sample was unable to be collected for analysis.

The problem was documented with CR 1045871 and CR 1051963. 2nc1 QTR2015 19-BF-N-lA

1.0 MilesN

Dosimeter The environmental dosimeters from station 19 were missing during the quarterly change out The issue was documented with CR 1053364. 2nc:t QTR2015 15-BF-NNE-2

0. 7 Miles NNE Dosimeter The environmental dosimeters from station 15 were missing during the quarterly change out. The issue was documented with CR 1053362. 3n:1QTR2015 25-BF-SSE-2

7.5 Miles

SSE Dosimeter The environmental dosimeters from station 25 were missing during the quarterly change out. The issue was documented with CR 1090948. 3n:IQTR2015 26-BF-SE-2 5.4Miles SE Dosimeter The environmental dosimeters from station 26 were missing during the quarterly change out The issue was documented with CR 1090958.

APPENDIXD ANALYTICAL PROCEDURES AppendixD Analytical Procedures Analyses of environmental samples are performed by the radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals with the exception of the Sr-89, 90 analysis of soil samples which are performed by Teledyne Brown Engineering, Knoxville, 1N. 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 milliliters 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. The charcoal cartridges used to sample gaseous radioiodine are 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.

APPENDIXE NOMINAL LOWER LIMITS OF DETECTION AppendixE 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 Radiological Environmental Monitoring Program (REMP). The nominal LLD values are calculated using the methodology prescribed in the Offsite Dose Calculation Manual (ODCM). These nominal LLD values are presented in Table E-1. The maximum LLD values specified in the ODCM are shown in Table E-2. Mille samples are not currently collected and analyzed for the Browns Ferry Nuclear Plant REMP, but the nominal LLD values for the analysis of millc are included in the tables to maintain the historical record of the laboratory's measurement capabilities.

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

Analysis Gross Beta Tritium Iodine-131 Strontium-89 Strontium-90 Air Filters (pCi/m 3) 0.002 TABLEE-1 Nominal LLD Values A. Radiochemical Water (pCi/Ll 1.9 270 0.4 Milk (pCi/L) 0.4 3.5 2.0 Sediment and Soil (pCi/g dtyl 1.6 0.4 Table E-1 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. Analysis pCi/m 3 pCi/m 3 pCi/L pCi/g. dry pCilkg. wet pCi/g. dry pCi/g. dry pCi/kg. wet Ce-141 0.005 0.02 IO 0.07 35 O.IO 0.07 20 Ce-144 0.01 0.07 30 0.15 115 0.20 0.15 60 Cr-51 0.02 0.15 45 0.30 200 0.35 0.30 95 I-131 0.005 0.03 IO 0.20 60 0.25 0.20 20 Ru-103 0.005 0.02 5 0.03 25 0.03 0.03 25 Ru-106 0.02 0.12 40 0.15 190 0.20 0.15 90 Cs-134 0.005 0.02 5 0.03 30 0.03 0.03 IO Cs-137 0.005 0.02 5 0.03 25 0.03 0.03 IO Zr-95 0.005 0.03 IO 0.05 45 0.05 0.05 45 Nb-95 0.005 0.02 5 0.25 30 0.04 0.25 IO Co-58 0.005 0.02 5 0.03 20 0.03 0.03 10 Mn-54 0.005 0.02 5 0.03 20 0.03 0.03 10 Zn-65 0.005 0.03 10 0.05 45 0.05 0.05 45 Co-60 0.005 0.02 5 0.03 20 0.03 0.03 IO K-40 0.04 0.30 100 0.40 400 0.75 0.40 250 Ba-140 0.015 0.07 25 0.30 130 0.30 0.30 50 La-140 0.01 0.04 10 0.20 50 0.20 0.20 25 Fe-59 0.005 0.04 10 0.08 40 0.05 0.08 25 Be-7 0.02 0.15 45 0.25 200 0.25 0.25 90 Pb-212 0.005 0.03 15 0.04 40 0.10 0.04 40 Pb-214 0.005 0.07 20 0.50 80 0.15 0.50 80 Bi-214 0.005 0.05 20 O.IO 55 0.15 O.IO 40 Bi-212 0.02 0.20 50 0.25 250 0.45 0.25 130 Tl-208 0.002 0.02 10 0.03 30 0.06 0.03 30 Ra-224 0.75 Ra-226 0.15 Ac-228 0.01 0.07 20 0.10 70 0.25 0.10 so Pa-234m 800 4.00 Table E-2 Maximum LLD Values Specified by the BFN ODCM Airborne Particulate Food Water or Gases Fish Mille Products Sediment Analysis pCi/L pCi/m 3 pCi/kg. wet pCi/L pCi/kg. wet pCi/kg. dry gross beta 4 0.01 N.A. N.A. N.A. H-3 2oooa N.A. N.A. N.A. N.A. Mn-54 15 N.A. 130 N.A. N.A. Fe-59 30 N.A. 260 N.A. N.A. Co-58, 60 15 N.A. 130 N.A. N.A. Zn-65 30 N.A. 260 N.A. N.A. Zr-95 30 N.A. N.A.

N.A. N.A. Nb-95 15 N.A. N.A. N.A. N.A. I-131 lb 0.07 N.A. I 60 Cs-134 15 0.05 130 15 60 Cs-137 18 0.06 150 18 80 Ba-140 60 N.A. N.A. 60 N.A. La-140 15 N.A. N.A. 15 N.A. a. If no drinking water pathway exists, a value of 3000 pCi/L may be used. b. LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L. If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for 1-131. N.A. N.A. N.A. N.A. N.A. N.A. N.A. N.A. N.A. 150 180 N.A. N.A.

APPENDIXF QUALITY ASSURANCE/QUALITY CONTROL PROGRAM AppendixF Quality Assurance/Quality Control Program A quality assurance program is employed by the ERM&I 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, field and lab duplicates, analytical knowns, blind spikes, and 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.

Duplicates are samples 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. The analysis results for internal cross-check samples met the program performance goals for 2015. 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 2015. The results for these cross-check samples, as shown in Table F-1, were all within the program agreement limits with the exception of the Sr-90 in Milk result for the first quarter cross-checks.

The disagreement was documented in CR 1106899. All other Sr-90 results were in agreement.

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-1 Results For 2015 External Cross Checks &mill Test Period Saronle Tvne I Analysis K!!mm IYA First Quarter Water (pCi/L) Gross Beta 2.80E+o2 2.83E+o2 Yes First Quarter Water (pCi/L) JH l.26E+04 l.36E+04 Yes First Quarter Water (pCi/L) ml 9.67E+ol 9.83E+ol Yes 51 Cr 3.66E+o2 3.76E+o2 Yes iucs 1.26E+o2 l.23E+o2 Yes in cs l.67E+o2 l.69E+o2 Yes SICo l.80E+o2 l.81E+o2 Yes S4Mn l.S9E+o2 l.67E+o2 Yes 59 Fe l.9SE+o2 J.92E+o2 Yes 6'ZD 2.99E+o2 3.09E+o2 Yes 60 Co 3.28E+o2 3.2SE+o2 Yes 141Ce l.39E+o2 l.49E+o2 Yes First Quarter Synthetic Urine (pCi/L) ,H l.43E+04 1.46E+04 Yes First Quarter Millc(pCi/L) ml 9.90E+ol 9.0SE+ol Yes "Sr 9.68E+ol 8.61E+ol Yes 90 Sr l.32E+o1 8.90E+oo No First Quarter Air Filter (pCi/Filter)

Gross Beta l.OOE+o2 9.46E+o1 Yes Third Quarter Water (pCi/L) JH l.32E+04 1.36E+04 Yes Third Quarter S811d (pCi/gram) aoCe 3.38E-01 3.IOE-01 Yes Sier 8.54.E-Ol 8.20E-01 Yes iucs 3.36E-01 2.82E-Ol Yes 137 Cs 4.05.E-01 3.78E-Ol Yes "co 4.ISE-01 4.0IE-01 Yes S4Mn 4.61.E-01 4.70E-01 Yes 59 Fe 3.SS.E-01 3.39E-01 Yes 6SZD S.61E-OI 5.7SE-01 Yes 60 Co S.24.E-01 5.13.E-01 Yes Third Quarter Air Filter (pCi/Filter)

Gross Beta 9.21E+ol 7.70E+o1 Yes Third Quarter Air Filter (pCi/Filter) 141Ce 8.34E+ol 8.36E+ol Yes Sier 2.11E+o2 2.0lE+o2 Yes iucs 8.29E+ol 6.60E+ol Yes 137 Cs 9.98E+OI 9.55E+ol Yes "co l.03E+o2 9.96E+OI Yes S4Mn l.14E+o2 1.19E+o2 Yes 59 Fe 8.84E+ol 9.05E+ol Yes 6'ZD 1.38E+o2 l.SOE+02 Yes 60 Co 1.29E+o2 l.32E+02 Yes Third Quarter Synthetic Urine (pCi/L) ,H l.39E+04 l.40E+04 Yes Fourth Quarter Mille (pCi/L) ml 8.97E+ol 9.38E+ol Yes "sr 9.00E+ol 8.28E+ol Yes 90 Sr 1.57E+ol l.27E+ol Yes APPENDIXG 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 (8 km) 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 (5 km) from the plant. The land use survey was conducted between April 1, 2015, and October 1, 2015, 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 Browns Ferry Nuclear Plant (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 location of the nearest resident in 2015 as compared to 2014. The location of the nearest garden as identified in the 2015 survey did not change. However, no garden was identified in the west sector in 2015. 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 2014 and 2015.

Sector N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Table G-1 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within 8 km (5 Miles) of the Plant (mrem/Y ear) 2014 Survey 2015 Survey Approximate Approximate Distance Annual Distance Meters Dose Meters 2,440 0.34 2,440 2,620 0.14 2,620 2,020 0.17 2,020 2,460 0.17 2,460 1,410 0.40 1,410 1,750 0.24 1,750 a a a a 4,540 0.15 4,540 4,610 0.16 4,610 4,650 0.10 4,650 4,200 0.07 4,200 2,660 0.17 2,660 5,280 0.10 5,280 3,150 0.33 3,150 1,650 0.75 1,650 a. There is no residence within the 8 km radius for this sector. Annual Dose 0.34 0.14 0.17 0.17 0.40 0.24 0.15 0.16 0.10 0.07 0.17 0.10 0.33 0.75 Table G-2 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods (mrem/Y ear) 2014 2015 Number of Approximate Approximate Gardens Within Distance Annual Distance Annual 5 km (3 Miles) Sector Meters Dose Meters Dose for 2015 N 2,540 5.99 2,540 5.99 1 NNE 5,980 0.88 5,980 0.88 1 NE 3,790 1.50 3,790 1.50 2 ENE 5,070 1.06 5,070 1.06 1 E 1,410 6.70 1,410 6.70 3 ESE 1,830 6.10 1,830 6.10 2 SE a a 0 SSE a a 0 s 4,540 2.24 4,540 2.24 1 SSW 4,880 2.14 4,880 2.14 I SW 4,940 1.00 4,940 1.00 I WSW 4,330 0.60 4,330 0.60 I w 2,860 1.20 a 0 WNW a a 0 NW a a 0 NNW 2,290 7.30 2,290 7.30 5 a. No garden was found within 8 km radius for this sector.

APPENDIXH DATA TABLES AND FIGURES Average, 0-2 miles (onsite) Average, >2 miles (offsite)

Table H-1 DIRECT RADIATION LEVELS 2015 Average External Gamma Radiation Levels On-site and Off-site for Browns Ferry Nuclear Plant for Each Quarter (mR I Quarter) a. Average External Gamma Radiation Levels b. 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr mRNrc. 16.1 16.4 20 16.9 69 12.8 13.2 15.5 13.6 55 (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. (c). The 14.4 mR/yr for onsite locations falls below the 25 mrem total body limit in 1 O CFR 190.

Table H-2 (1 of 2) DIRECT RADIATION LEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels mR I Quarter Map Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual 1 Jan -Apr-Jul-Oct-Location Station Direction, Distance, Mar Jun Sep Dec Exposure Number Number Degrees Miles 2015 2015 2015 2015 mRNear 7 N-1 348 1.0 15.5 18.7 24.2 17.7 76.1 75 N-1A 355 1.0 20.9 (1) 20.6 17.7 78.9 38 N-2 1 5.0 9.6 12.6 14.6 12.3 49.1 8 NNE-1 12 0.9 14.4 15.9 17.6 17.7 65.6 39 NNE-2 31 0.7 22.5 (1) 22.2 15.3 80.0 40 NNE-3 19 5.2 11.7 13.6 15.6 12.3 53.2 41 NE-1 51 0.8 15.5 17.3 20.6 19.7 73.1 42 NE-2 49 5.0 18.7 15.0 17.1 16.3 67.1 2 NE-3 56 10.9 14.4 15.9 14.6 13.3 58.2 9 ENE-1 61 0.9 18.2 15.9 21.1 17.2 72.4 43 ENE-2 62 6.2 12.8 15.4 18.1 16.7 63.0 44 E-1 85 0.8 16.6 16.8 21.1 16.7 71.2 45 E-2 91 5.2 11.7 13.1 17.6 13.8 56.2 6 E-3 90 23.1 12.3 15.9 15.6 14.8 58.6 46 ESE-1 110 0.9 11.7 15.0 18.6 15.8 61.1 47 ESE-2 112 3.0 17.6 15.9 13.5 12.8 59.8 48 SE-1 130 0.5 15.5 18.2 20.6 16.7 71.0 49 SE-2 135 5.4 15.0 13.1 (1) 17.7 61.1 50 SSE-1 163 5.1 13.4 14.0 16.1 15.8 59.3 3 SSE-2 165 7.5 15 15.9 (1) 14.3 60.3 51 S-1 185 3.1 17.1 13.1 19.1 14.3 63.6 (1) Sum of available quarterly data normalized to 1 year for the annual exposure value.

Table H-2 (2 of 2) DIRECT RADIATION LEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels mR I Quarter Map Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual 1 Jan-Apr-Jul-Oct-Location Station Direction, Distance, Mar Jun Sep Dec Exposure Number Number Degrees Miles 2015 2015 2015 2015 mRNear 52 S-2 182 4.8 10.7 15.0 18.1 12.8 56.6 53 SSW-1 203 3.0 11.7 9.4 15.6 12.8 49.5 54 SSW-2 199 4.4 12.3 13.6 13.0 14.8 53.7 55 SW-1 228 1.9 15.5 13.6 19.1 17.2 65.4 56 SW-2 219 4.7 15.5 15.0 15.1 14.3 59.9 58 WSW-1 244 2.7 13.4 10.3 13.5 10.9 48.1 59 WSW-2 251 5.1 14.4 14.5 19.6 15.8 64.3 60 WSW-3 257 10.5 12.8 11.7 15.6 12.8 52.9 61 W-1 275 1.9 12.8 16.4 15.6 14.3 59.1 62 W-2 268 4.7 9.1 12.6 14 13.3 46.7 5 W-3 275 31.0 13.4 11.7 14.0 11.4 50.5 64 WNW-1 291 3.3 11.2 10.3 19.1 13.8 54.4 65 WNW-2 293 4.4 13.4 12.2 15.6 11.8 53.0 66 NW-1 326 2.2 11.7 13.1 15.1 12.8 52.7 67 NW-2 321 5.3 11.7 14.5 16.1 15.3 57.6 1 NW-3 310 13.8 11.2 12.2 12.0 11.4 46.8 68 NNW-1 331 1.0 15.0 15.9 18.1 17.2 66.2 10 NNW-2 331 1.7 15.5 16.7 20.8 16.7 69.7 69 NNW-3 339 5.2 10.7 13.1 17.1 14.3 55.2 (1) Sum of available quarterly data normalized to 1 year for the annual exposure value.

I OI N I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Lower Limit Total Number of Detection of Analysis (LLD) Performed See Note 1 GROSS BETA -571 2.00E-03 GAMMA SCAN (GELi) -143 AC-228 1.00E-02 BE-7 2.00E-02 Bl-214 5.00E-03 K-40 4.00E-02 PB-212 5.00E-03 PB-214 5.00E-03 TL-208 2.00E-03 Indicator Locations Mean (F) Range See Note 2 1.90E-02 (467 I 467) 4.60E-03 -3.41E-02 117VALUES

<LLD 9.80E-02 (117/117) 7 .1 OE-02 -1.23E-01 1.91E-02 (1151117) 5.1 OE-03 -4.83E-02 117 VALUES < LLD 117 VALUES< LLD 1.88E-02 (110/117) 5.00E-03 -4.89E-02 2.40E-03 (3 / 117) 2.1 OE-03 -2.SOE-03 Tennessee Valley Authority RADIOACTIVITY IN AIR FILTER pCilm"3 = 0.037 Bq/m"3 Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 PM-3 BF DECATUR AL 2.00E-02 (52 / 52) 8.2 MILES SSE 5.58E-03 -3.07E-02 LM3 BF NORTHEAST 13 VALUES< LLD 1.0 MILE ENE PM-3 BF DECATUR AL 1.05E-01 (13/13) 8.2 MILES SSE 8.58E-02 -1.23E-01 PM-3 BF DECATUR AL 2.91E-02 (13113) 8.2 MILES SSE 1.66E-02 -4.17E-02 LM2 BF NORTH 13 VALUES< LLD 0.9 MILE NNE LM2 BF NORTH 13 VALUES< LLD 0.9 MILE NNE PM-3 BF DECATUR AL 2.90E-02 (13113) 8.2 MILES SSE 1.69E-02 -4.64E-02 LM2BF NORTH 2.45E-03 (2 / 13) 0.9 MILE NNE 2.1 OE-03 -2.SOE-03 Control Locations Mean (F) Range See Note 2 1.73E-02 (1041104) 2.68E-03 -3.14E-02 26 VALUES < LLD 9.29E-02 (26 I 26) 6.26E-02 -1.36E-01 1.57E-02 (24 I 26) 5.30E-03 -3.22E-02 26 VALUES < LLD 26 VALUES < LLD 1.45E-02 (22 / 26) 5.SOE-03 -3.31E-02 2.00E-03 (1 I 26) 2.00E-03 -2.00E-03 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements onty. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 -Cl) ::c: I w I °' w I 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 GAMMA SCAN (GELi) -571 BE-7 1.50E-01 1.72E-01 (1/467) 1. 72E-01 -1. 72E-01 Bl-214 5.00E-02 9.37E-02 (251/467) 5.03E-02 -3.03E-01 1-131 3.00E-02 SEE NOTE4 K-40 3.00E-01 3.44E-01 (101/467) 3.01E-01 -5.26E-01 PB-212 3.00E-02 3.37E-02 (1 I 467) 3.37E-02 -3.37E-02 PB-214 7.00E-02 1.19E-01 (150 / 467) 7.02E-02 -3.57E-01 TL-208 2.00E-02 467 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN CHARCOAL FILTER pCilm"3 = 0.037 Bq/m"3 Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 LM-7BF LAKEVIEW 2.1 MILES WEST LM3 BF NORTHEAST 1.0 MILE ENE LM3 BF NORTHEAST 1.0 MILE ENE LM1 BF NORTHWEST 1.0 MILE N PM-1 ROGERSVILLE AL 13.8 MILES NW PM-2 BF ATHENS AL 10.9 MILES NE 1. 72E-01 (1 I 52) 1.72E-01 -1.72E-01 1.19E-01 (30 I 52) 5.25E-02 -2.90E-01 3.72E-01 (13 / 52) 3.06E-01 -5.26E-01 3.37E-02 (1 I 52) 3.37E-02 -3.37E-02 1.44E-01 (19 / 52) 7.18E-02 -3.53E-01 52 VALUES< LLD Control Locations Mean (F) Range See Note2 104 VALUES < LLD 1.12E-01 (46/104) 5.19E-02 -4.54E-01 3.38E-01 (14 / 104) 3.05E-01 -4.21E-01 3.80E-02 (1 / 104) 3.80E-02 -3.80E-02 1.33E-01 (33 / 104) 7.05E-02 -5.07E-01 104 VALUES< LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 4. 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.

I °' I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Lower Limit Total Number of Detection of Analysis (LLD) Performed See Note 1 GAMMA SCAN (GELi) -11 AC-228 2.50E-01 BE-7 2.50E-01 Bl-212 4.50E-01 Bl-214 1.50E-01 CS-137 3.00E-02 K-40 7.50E-01 PA-234M 4.00E+OO PB-212 1.00E-01 PB-214 1.50E-01 RA-226 1.50E-01 TL-208 6.00E-02 SR 89 -11 1.60E+OO SR 90 -11 4.00E-01 Indicator Locations Mean (F) Range See Note 2 1.15E+OO (9 I 9) 5.93E-01 -1.40E+OO 5.68E-01 (4/9) 3.03E-01 -1.25E+OO 1.24E+OO (9 I 9) 6.12E-01 -1.52E+OO 1.02E+OO (9 / 9) 6.60E-01 -1.30E+OO 1.50E-01 (8 / 9) 3.98E-02 -3.0SE-01 5.24E+OO (9 I 9) 2.58E+OO -8.23E+OO 4.13E+OO (119) 4.13E+OO -4.13E+OO 1.13E+OO (9 / 9) 5.61E-01 -1.38E+OO 1.10E+OO (919) 6.74E-01 -1.40E+OO 1.02E+OO (9 / 9) 6.60E-01 -1.30E+OO 3.78E-01 (9 / 9) 1.84E-01 -4.61 E-01 9 VALUES < LLD 9 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN SOIL pCi/g = 0.037 Bq/g (DRY WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 LM1 BF NORTHWEST 1.40E+OO (1/1) 1.0 MILE N 1.40E+OO -1.40E+OO PM-1 ROGERSVILLE AL 1.25E+OO (111) 13.8 MILES NW 1.25E+OO -1.25E+OO LM1 BF NORTHWEST 1.52E+OO (1/1) 1.0 MILE N 1.52E+OO -1.52E+OO LM2BFNORTH 1.30E+OO (1/1) 0.9MILE NNE 1.30E+OO -1.30E+OO LM-6BF BAKER BOTTOM 3.08E-01 (1 / 1) 3.0 MILES SSW 3.08E-01 -3.08E-01 LM2BF NORTH 8.23E+OO (1 / 1) 0.9MILENNE 8.23E+OO -8.23E+OO LM2BFNORTH 4.13E+OO (1 / 1) 0.9 MILE NNE 4.13E+OO -4.13E+OO LM2 BF NORTH 1.38E+OO (1 / 1) 0.9MILE NNE 1.38E+OO -1.38E+OO LM2BFNORTH 1.40E+OO (1/1) 0.9MILE NNE 1.40E+OO -1.40E+OO LM2BF NORTH 1.30E+OO (1/1) 0.9MILE NNE 1.30E+OO -1.30E+OO LM2BFNORTH 4.61E-01 (1 / 1) 0.9MILENNE 4.61 E-01 -4.61 E-01 Control Locations Mean (F) Range See Note 2 9.12E-01 (2 / 2) 8.37E-01 -9.87E-01 2 VALUES < LLD 1.01 E+OO (2 / 2) 9.45E-01 -1.07E+OO 8.43E-01 (212) 8.16E-01 -8.70E-01 9.1 OE-02 (2 I 2) 7.33E-02 -1.09E-01 3.35E+OO (2 I 2) 2.00E+OO -4.71E+OO 2 VALUES < LLD 9.43E-01 (2 / 2) 8.64E-01 -1.02E+OO 9.38E-01 (2 / 2) 8.57E-01 -1.02E+OO 8.43E-01 (2 / 2) 8.16E-01 -8.70E-01 3.01E-01 (2 / 2) 2.81E-01 -3.20E-01 2 VALUES< LLD 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutlne Reported Measurements See Note 3 a" -Vl Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -2 81-214 K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD) See Note 1 4.00E+01 2.50E+02 4.00E+01 8.00E+01 3.00E+01 Indicator Locations Mean (F) Range See Note 2 6.66E+01 (1 / 1) 6.66E+01 -6.66E+01 1.07E+03 (1 / 1) 1.07E+03 -1.07E+03 1 VALUES < LLD 1 VALUES < LLD 1 VALUES< LLD Tennessee Valley Authority RADIOACTIVITY IN APPLES pCl/Kg = 0.037 Bq/Kg (WET WEIGHn Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 1 MILENNW 6.66E+01 (1 / 1) 6.66E+01 -6.66E+01 1 MILENNW 1.07E+03 (1/1) 1.07E+03 -1.07E+03 1 MILENNW 1 VALUES < LLD 1 MILENNW 1 VALUES < LLD 1 MILENNW 1 VALUES < LLD Control Locations Mean (F) Range See Note 2 1 VALUES < LLD 1.14E+03 (1/1) 1.14E+03 -1.14E+03 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F}. 3. Blanks in this column Indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 -CD ::z:: I °'

I °' °' I Name of Facility:

BROWNS FERRY NUCLEAR PLA.NT Location of Facility:

LIMESTONE, ALA.SAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -2 Bl-214 K-40 PB-212 PB-214 Lower Limit of Detection (LLD) See Note 1 4.00E+01 2.50E+02 4.00E+01 8.00E+01 Indicator Locations Mean (F) Range See Note 2 5.18E+01 (1 / 1) 5.18E+01 -5.18E+01 1.36E+03 (1/1) 1.36E+03 -1.36E+03 1 VALUES < LLD 1 VALUES< LLD Tennessee Valley Authority RADIOACTIVITY IN CABBAGE pCi/Kg = 0.037 Bq/Kg (WET WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 C.MOSLEY FARM 5.18E+01 (1 / 1) 1.58 MILES N 5.18E+01 -5.18E+01 C.MOSLEY FARM 1.36E+03 (1/1) 1.58 MILES N 1.36E+03 -1.36E+03 C.MOSLEY FARM 1 VALUES < LLD 1.58 MILES N C.MOSLEY FARM 1 VALUES < LLD 1.58MILESN Control Locations Mean (F) Range See Note2 5.85E+01 (1 / 1) 5.85E+01 -5.85E+01 1.46E+03 (1 / 1) 1.46E+03 -1.46E+03 1 VALUES < LLD 1 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note3 I °' .....J I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -2 Bl-214 K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD) See Note 1 4.00E+01 2.50E+02 4.00E+01 8.00E+01 3.00E+01 Indicator Locations Mean (F) Range See Note 2 6.32E+01 (111) 6.32E+01 -6.32E+01 2.05E+03 (1/1) 2.05E+03 -2.05E+03 1 VALUES < LLD 1 VALUES< LLD 1 VALUES< LLD Tennessee Valley Authority RADIOACTIVITY IN CORN pCi/Kg = 0.037 Bq/Kg {WET WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 LM-6BF BAKER BOTIOM 6.32E+01 (1 11) 3.0 MILES SSW 6.32E+01 -6.32E+01 LM-6BF BAKER BOTIOM 2.05E+03 (111) 3.0 MILES SSW 2.05E+03 -2.05E+03 LM-6BF BAKER BOTIOM 1 VALUES < LLD 3.0 MILES SSW LM-6BF BAKER BOTIOM 1 VALUES < LLD 3.0 MILES SSW LM-6BF BAKER BOTIOM 1 VALUES < LLD 3.0 MILES SSW Control Locations Mean (F) Range See Note 2 6.04E+01 (1 / 1) 6.04E+01 -6.04E+01 2.02E+03 (1 11) 2.02E+03 -2.02E+03 1 VALUES< LLD 1 VALUES< LLD 1 VALUES< LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column Indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note3 ...., -CD ::c: I 00 I °' Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN {GELi) -2 AC-228 81-214 K-40 PB-212 PB-214 Lower Limit of Detection

{LLD) See Note 1 5.00E+01 4.00E+01 2.50E+02 4.00E+01 8.00E+01 Indicator Locations Mean {F) Range See Note 2 5.53E+01 (1 / 1) 5.53E+01 -5.53E+01 1.86E+02 (1/1) 1.86E+02 -1.86E+02 3.51 E+03 (1 / 1) 3.51E+03 -3.51E+03 1 VALUES < LLD 1 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN POTATOES pCi/Kg = 0.037 Bq/Kg (WET WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 2.3 MILES NNW 5.53E+01 {1 / 1) 5.53E+01 -5.53E+01 2.3 MILES NNW 1.86E+02 (1 / 1) 1.86E+02 -1.86E+02 2.3 MILES NNW 3.51E+03 (1 / 1) 3.51 E+03 -3.51 E+03 2.3 MILES NNW 1 VALUES < LLD 2.3 MILES NNW 1 VALUES < LLD Control Locations Mean (F) Range See Note2 1 VALUES < LLD 5.06E+01 (1 / 1) 5.06E+01 -5.06E+01 3.49E+03 (1 / 1) 3.49E+03 -3.49E+03 1 VALUES< LLD 1 VALUES< LLD TL-208 3.00E+01 1 VALUES < LLD 2.3 MILES NNW 1 VALUES < LLD 1 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is Indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 1--3 g. -R ::c: I \0 Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -2 Bl-214 K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD) See Note 1 4.00E+01 2.50E+02 4.00E+01 8.00E+01 3.00E+01 Indicator Locations Mean (F) Range See Note 2 5.63E+01 (1 / 1) 5.63E+01 -5.63E+01 2.58E+03 (1 / 1) 2.58E+03 -2.58E+03 1 VALUES< LLD 1 VALUES < LLD 1 VALUES< LLD Tennessee Valley Authority RADIOACTIVITY IN TOMATOES pCi/Kg = 0.037 Bq/Kg (WET WEIGHn Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 1.4 MILES NNW 5.63E+01 (1 / 1) 5.63E+01 -5.63E+01 1.4 MILES NNW 2.58E+03 (1 / 1) 2.58E+03 -2.58E+03 1.4 MILES NNW 1 VALUES < LLD 1.4 MILES NNW 1 VALUES< LLD 1.4 MILES NNW 1 VALUES < LLD Control Locations Mean (F) Range See Note 2 1 VALUES < LLD 1.62E+03 (1/1) 1.62E+03 -1.62E+03 1 VALUES < LLD 1 VALUES< LLD 1 VALUES< LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 t-3 Ci" ,__. 0 I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -2 Bl-214 K-40 PB-214 Lower Limit of Detection (LLD) See Note 1 4.00E+01 2.50E+02 8.00E+01 Indicator Locations Mean (F) Range See Note 2 9.56E+01 (1 / 1) 9.56E+01 -9.56E+01 3.50E+03 (1 / 1) 3.50E+03 -3.50E+03 8.43E+01 (1 / 1) 8.43E+01 -8.43E+01 Tennessee Valley Authority RADIOACTIVITY IN PEAS pCl/Kg = 0.037 Bq/Kg (WET WEIGHn Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 LM-6BF BAKER BOTIOM 9.56E+01 (1 / 1) 3.0 MILES SSW 9.56E+01 -9.56E+01 LM-6BF BAKER BOTIOM 3.50E+03 (1 / 1) 3.0 MILES SSW 3.50E+03 -3.50E+03 LM-6BF BAKER BOTIOM 8.43E+01 (1 / 1) 3.0 MILES SSW 8.43E+01 -8.43E+01 Control Locations Mean (F) Range See Note 2 8.94E+01 (1 / 1) 8.94E+01 -8.94E+01 5.06E+03 (1 / 1) 5.06E+03 -5.06E+03 1 VALUES< LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 ...., -n --

I -...J -I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Lower limit Total Number of Detection of Analysis (LLD) Performed See Note 1 GROSS BETA -26 1.90E+OO GAMMA SCAN (GELi) -26 Bl-214 2.00E+01 K-40 1.00E+02 PB-212 1.50E+01 PB-214 2.00E+01 TL-208 1.00E+01 TRITIUM -8 2.70E+02 Indicator Locations Mean (F) Range See Note2 2.44E+OO (7 / 13) 1.91 E+OO -3.26E+OO 4.49E+01 (5 / 13) 2.50E+01 -6.99E+01 13 VALUES< LLD 13 VALUES< LLD 3.53E+01 (5 / 13) 2.36E+01 -5.17E+01 13 VALUES< LLD 2.90E+02 (1 I 4) 2.90E+02 -2.90E+02 Tennessee Valley Authority RADIOACTIVITY IN SURFACE WATER (Total) pCi/L = 0.037 Bq/L Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 TRM 293.5 TRM293.5 TRM 293.5 TRM 293.5 TRM 293.5 TRM 293.5 TRM 293.5 2.44E+OO (7 / 13) 1.91 E+OO -3.26E+OO 4.49E+01 (5 / 13) 2.50E+01 -6.99E+01 13 VALUES< LLD 13 VALUES< LLD 3.53E+01 (5 / 13) 2.36E+01 -5.17E+01 13 VALUES< LLD 2.90E+02 (1 I 4) 2.90E+02 -2.90E+02 Control Locations Mean (F) Range See Note 2 2.55E+OO (8 / 13) 1.95E+OO -3. 77E+OO 3.32E+01 (7 / 13) 2.14E+01 -6.06E+01 13 VALUES< LLD 13 VALUES< LLD 3.62E+01 (4 / 13) 2.46E+01 -5.14E+01 13 VALUES < LLD 2.95E+02 (1 I 4) 2.95E+02 -2.95E+02 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 c::T -..._. N I ........ t-.J I Tennessee Valley Authority RADIOACTIVITY IN PUBLIC (DRINKING)

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: 2015 Type and Lower limit Indicator Locations Total Number of Detection Mean (F) of Analysis (LLD) Range Performed See Note 1 See Note 2 GROSS BETA -72 1.90E+OO 2.35E+OO (34 I 59) 1.91E+OO -3.18E+OO GAMMA SCAN (GELi) -72 AC-228 2.00E+01 2.04E+01 (1 / 59) 2.04E+01 -2.04E+01 Bl-214 2.00E+01 3.86E+01 (28 / 59) 2.32E+01 -9.21E+01 K-40 1.00E+02 3.21 E+02 (1 I 59) 3.21E+02 -3.21E+02 PB-212 1.50E+01 1.55E+01 (1 / 59) 1.55E+01 -1.55E+01 PB-214 2.00E+01 3.41E+01 (23 / 59) 2.04E+01 -7.54E+01 Tl-208 1.00E+01 59 VALUES< LLD TRITIUM -22 2.70E+02 3.08E+02 (10 I 18) 2.70E+02 -3.37E+02 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 CHAMPION PAPER TRM 282.6 WHEELER DAM, Al TRM 274.9 WHEELER DAM, Al TRM274.9 WHEELER DAM, Al TRM 274.9 WHEELER DAM, Al TRM274.9 FLORENCE, Al TRM259.8 FLORENCE, Al TRM259.8 CHAMPION PAPER TRM 282.6 2.42E+OO (4 I 7) 1.97E+OO -2.86E+OO 2.04E+01 (1 / 13) 2.04E+01 -2.04E+01 4.75E+01 (8 / 13) 2.97E+01 -8.50E+01 3.21 E+02 (1 I 13) 3.21 E+02 -3.21 E+02 1.55E+01 (1 / 13) 1.55E+01 -1.55E+01 3.96E+01 (5 / 13) 2.25E+01 -6.97E+01 13 VALUES< LLD 3.19E+02 (1 I 2) 3.19E+02 -3.19E+02 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 Control Locations Mean (F) Range See Note 2 2.55E+OO (8 / 13) 1.95E+OO -3. 77E+OO 13 VALUES< LLD 3.32E+01 (7 / 13) 2.14E+01 -6.06E+01 13 VALUES< LLD 13 VALUES< LLD 3.62E+01 (4 / 13) 2.46E+01 -5.14E+01 13 VALUES< LLD 2.95E+02 (1 I 4) 2.95E+02 -2.95E+02 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 tr ::c I ...... w I ....:i w I Tennessee Valley Authority RADIOACTIVITY IN WELL (GROUND) 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: 2015 Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -25 AC-228 Bl-214 K-40 PB-212 PB-214 TL-208 TRITIUM -8 Lower Limit of Detection (LLD) See Note 1 2.00E+01 2.00E+01 1.00E+02 1.50E+01 2.00E+01 1.00E+01 2.70E+02 Indicator Locations Mean (F) Range See Note 2 2.63E+01 (1 / 12) 2.63E+01 -2.63E+01 4.07E+01 (10 / 12) 2.40E+01 -8.84E+01 12 VALUES< LLD 12 VALUES< LLD 3.48E+01 (10 / 12) 2.22E+01 -7.56E+01 12 VALUES< LLD 4.54E+02 (1/4) 4.54E+02 -4.54E+02 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 BFN WELL#6R 2.63E+01 (1 / 6) 0.12 MILES NW 2.63E+01 -2.63E+01 BFN WELL#6 4.60E+01 (6 / 6) 0.02 MILESW 2. 73E+01 -8.84E+01 BFN WELL#6R 6 VALUES< LLD 0.12 MILES NW BFN WELL#6 6 VALUES < LLD 0.02MILESW BFN WELL#6 3.78E+01 (6 / 6) 0.02MILESW 2.22E+01 -7.56E+01 BFN WELL#6 6 VALUES < LLD 0.02MILESW BFN WELL#6 4.54E+02 (1 I 2) 0.02 MILESW 4.54E+02 -4.54E+02 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1 Control Locations Mean (F) Range See Note2 1.16E+02 (1/13) 1.16E+02 -1.16E+02 3.04E+02 (13/13) 1.00E+02 -4.84E+02 13 VALUES< LLD 13 VALUES< LLD 3.06E+02 (13 / 13) 8.90E+01 -4.96E+02 13 VALUES< LLD 4 VALUES< LLD 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column Indicate no nonrountlne measurements Number of Nonroutine Reported Measurements See Note 3 ..., -CTI ::c: I .......

I ....,) .i::. I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -4 Bl-214 K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD) See Note 1 1.00E-01 4.00E-01 4.00E-02 5.00E-01 3.00E-02 Indicator Locations Mean (F) Range See Note 2 1.83E-01 (1 I 2) 1.83E-01 -1.83E-01 1.26E+01 (2 / 2) 1.14E+01 -1.38E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN COMMERCIAL FISH pCi/g = 0.037 Bq/g (ORY WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 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 1.83E-01 (1 / 2) 1.83E-01 -1.83E-01 1.26E+01 (2 / 2) 1.14E+01 -1.38E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD Control Locations Mean (F) Range See Note 2 1.87E-01 (2 / 2) 1.45E-01 -2.30E-01 1.19E+01 (2 / 2) 1.18E+01 -1.20E+01 2 VALUES < LLD 2 VALUES< LLD 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 I " VI I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -4 81-214 CS-137 K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD) See Note 1 1.00E-01 3.00E-02 4.00E-01 4.00E-02 5.00E-01 3.00E-02 Indicator Locations Mean (F) Range See Note 2 1.95E-01 (1 / 2) 1.95E-01 -1.95E-01 2VALUES*<

LLD 1.31 E+01 (2 / 2) 1.25E+01 -1.38E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN GAME FISH pCi/g = 0.037 Bq/g (DRY WEIGHn Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 WHEELER RES 1.95E-01 (1/2) TRM 275-349 1.95E-01 -1.95E-01 WHEELER RES 2 VALUES < LLD TRM 275-349 WHEELER RES 1.31E+01 (2 / 2) TRM 275-349 1.25E+01 -1.38E+01 WHEELER RES 2 VALUES < LLD TRM 275-349 WHEELER RES 2 VALUES < LLD TRM 275-349 WHEELER RES 2 VALUES< LLD TRM 275-349 Control Locations Mean (F) Range See Note 2 2.70E-01 (1/2) 2.70E-01 -2.70E-01 2 VALUES < LLD *b 1.23E+01 (2 / 2) 1.19E+01 -1.28E+01 2 VALUES< LLD 2 VALUES< LLD 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 -Cl> :I: I °'

I -...J °' I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Lower limit Total Number of Detection of Analysis (LLD) Perfonned See Note 1 GAMMA SCAN (GELi) -6 AC-228 2.50E-01 BE-7 2.50E-01 81-212 4.50E-01 Bl-214 1.50E-01 CS-137 3.00E-02 K-40 7.50E-01 PB-212 1.00E-01 PB-214 1.50E-01 RA-226 1.50E-01 TL-208 6.00E-02 Indicator Locations Mean (F) Range See Note 2 4.92E-01 (2 / 4) 3.73E-01 -6.11E-01 4 VALUES < LLD 6.95E-01 (1/4) 6. 95E-01 -6.95E-01 3.47E-01 (4/4) 1.67E-01 -6.40E-01 4 VALUES < LLD 8.61E-01 (1/4) 8.61 E-01 -8.61 E-01 3.07E-01 (4 / 4) 1.27E-01 -5.81E-01 3.73E-01 (4/4) 1. 70E-01 -7.11 E-01 3.47E-01 (4 / 4) 1.67E-01 -6.40E-01 1.66E-01 (2 / 4) 1.23E-01 -2.0SE-01 Tennessee Valley Authority RADIOACTIVllY IN SHORELINE SEDIMENT pCi/g ::: 0.037 Bq/g (DRY WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 JOE WHEELER ST PARK 4.92E-01 (2/ 2) TRM279.5 3. 73E-01 -6.11 E-01 JOE WHEELER ST PARK 2 VALUES< LLD TRM 279.5 JOE WHEELER ST PARK 6.95E-01 (1/2) TRM279.5 6.95E-01 -6.95E-01 JOE WHEELER ST PARK 5.08E-01 (2/ 2) TRM279.5 3.76E-01 -6.40E-01 JOE WHEELER ST PARK 2 VALUES < LLD TRM279.5 JOE WHEELER ST PARK 8.61E-01 (1/2) TRM 279.5 8.61E-01 -8.61E-01 JOE WHEELER ST PARK 4.83E-01 (2 / 2) TRM279.5 3.85E-01 -5.81E-01 JOE WHEELER ST PARK 5.58E-01 (2/ 2) TRM 279.5 4.05E-01 -7.11E-01 JOE WHEELER ST PARK 5.08E-01 (2 / 2) TRM279.5 3. 76E-01 -6.40E-01 JOE WHEELER ST PARK 1.66E-01 (2 / 2) TRM 279.5 1.23E-01 -2.0SE-01 Control Locations Mean (F) Range See Note 2 5.20E-01 (2 / 2) 4.41E-01 -6.00E-01 2 VALUES< LLD 5.63E-01 (2 / 2) 4.73E-01 -6.52E-01 5.05E-01 (2 / 2) 4.32E-01 -5.79E-01 3.78E-02 (1 / 2) 3.78E-02 -3.78E-02 4.08E+OO (2 I 2) 3.18E+OO -4.98E+OO 5.26E-01 (2 / 2) 4.36E-01 -6.17E-01 5.25E-01 (2 / 2) 4.83E-01 -5.67E-01 5.05E-01 (2 / 2) 4.32E-01 -5. 79E-01 1.70E-01 (2 / 2) 1.42E-01 -1.98E-01 Notes: 1. Nominal Lower Level of Detection (LLD) as described In Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks In this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 ...., -('11 ::I: I ...... -...J 25 20 .... m :J 0 "E15 lU "O c: .!!! CJ) -0::10 E 5 1975 1980 Figure H-1 Direct Radiation Direct Radiation Levels Browns Ferry Nuclear Plant Four Quarter Moving Average lnlight Dosimeter Deployment January, 2007 1985 1990 1995 2000 2005 2010 Calendar Year _....,...

On-Site -o-Off-Site 2015 2020 Dosimeters are processed quarterly.

This chart shows trends in the average measurement for all dosimeters grouped as "on-site" or "off-site".

The data from preoperational phase and construction phases of TV A nuclear power plant sites, prior to 1980, show the same trend of "on-site" measurements higher than "off-site" measurements that is observed in current data indicating that the slightly higher "on-site" direct radiation levels are not related to plant operations.

.., E -0 c. i::' *;;: tJ c( Figure H-2 Radioactivity in Air Filters Annual Average Gross Beta Activity in Air Filters -BFN 0.25 0.2 0 0.1 5 0.10 0.05 0.00 Initial Plant Operation in August , 1 973 Pr eope ratio na l Average 1965 1 97 0 1975 1980 1 985 1990 1 995 2000 2005 20 1 0 2015 2020 Calendar Year -+-Ind i cato r -e-Cont r ol As can b e seen in the trend plot of gross beta activity , th e gross b eta l eve l s in a ir part i culates ha ve r e m a in ed r e l a ti ve ly constan t with t h e exception of years when th e beta act i vity was e l evate d due to fa ll out from nuclear weapons testing. The data a l so shows that th e r e is no difference in th e l eve l s for sa mplin g conducted at t h e indic ator stat i o n s as compared to the control stat ion s. -7 8 -

3 E. Cl -u c. 0 1965 Figure H-3 Cs-1 37 in So il Annual Average Cs-137 Activity in Soil -BFN In i tia l P lan t Operation in August , 1973 Preope rat i ona l Average 1970 1975 1 980 1985 1990 1995 2000 2005 20 10 Ca le ndar Year ---+---I nd i cator -o-Co n t rol 2015 2020 Cesium-13 7 was produced by pa s t nuclear weapons testing and is pre s ent in almost every environmental sample exposed to the atmosphere.

The "control" and "indicator" l ocat ion s h a ve generally trended downward with year-t o-year variation, s in ce the end of atmospheric nuclear weapons testing in 1980.

..J -u c. *;; .. u < 6 4 2 Figure H-4 Gross Beta Activity in Surface Water Annual Average Gross Beta Activity in Surface Water -BFN Initial Plant Operation in I August, 1973 Note: No gross beta measurements were made in 1978 Preoperational Average 0 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year --.-Ind i cator (Downstream) -e-Contro l (Upst r eam) 2015 2020 A s shown in the graph , the gross beta activity in samples from the downstream indicator locations has been essentially the same as the activity in samples from the upstream control locations.

The average gross beta activity in these samples has been trending down since the early 1980's.

...J 4 -C3 c. 2 Initial Plant Operation in August, 1973 Figure H-5 Gross Beta Activity in Drinking Water Annual Average Gross Beta Activity in Drinking Water -BFN 0 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 2020 Calendar Year -+-Indicator (Downstream) -e-Con trol (Upst ream) The average gross beta activity in drinking water samples from the upstream control locations has typically been slightly higher than activity level measured in samples from the downstream indicator locations. The annual average gross beta activity has been relatively constant since the start of plant operations in 1980 and is slightly lower than preoperational levels.

0.5 0.4 Cl -u c. 0.1 Figure H-6 Radioactivity in Fish Annual Average Cs-137 Activity in Fish Flesh Game Fish -BFN Initial Plant Operation in August, 1973 Preoperational Average 0.0 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 2020 Calendar Year I -+-I n dicator -e-Co n trol I The concentrations of Cs-13 7 found in fish are consistent with level s present in the Tennessee River due to past atmospheric nuclear weapons te sting. As s hown in the gra ph , the level s of Cs-13 7 have been decreasing consistent with the overall level s of Cs-13 7 in the environment.

Te nne s s ee V alley A uth o ri ty , Post Office Box 2000 , Decatu r , A l a b a m a 35609-2000 May 1 5 , 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Browns Ferry Nuclear Plant , Units 1 , 2 , and 3 10 CFR 50.4 Renewed Facility Operating License Nos. DPR-33 , DPR-52 , and DPR-68 NRC Docket Nos. 50-259 , 50-260 , and 50-296

Subject:

2015 Annual Radiological Environmental Operating Report I n accordance with the Browns Ferry Nuclear Plant Technical Specification 5.6.2 and Offsi t e Dose Calculation Manual Administrative Control Section 5.1 , the Tennessee Valley Authority is submitting the 2015 Annual Radiological Environmental Operating Report for Browns Ferry Nuclea r Plant , Units 1 , 2 , and 3. Enclosed is the subject report for the pe ri od of January 1 , 2015 , through December 31 , 2015. There are no new regulatory commitments contained within this letter. If you have any questions , please contact J. L. Paul at (256) 729-2636. E nclosur e: 20 15 Annual Radiological Environmenta l Oper a ting Report cc (w/Enclosure): NRC Regional Administrator

-Region II NRC Senior Resident Inspector

-Browns Ferry Nuclea r Plant Enclosure Browns Ferry Nuclear Plant Units 1, 2, and 3 2015 Annual Radiological Environmental Operating Repor t See Enclosed 2015 Annual Radiological Environmental Operating Report Browns Ferry Nuclear Plant ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT BROWNS FERRY NUCLEAR PLANT 2015 TENNESSEE VALLEY AUTHORITY TABLE OF CONTENTS Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i 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 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

11 Atmospheric Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

13 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

14 Terrestrial Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

15 Sample Collection and Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

15 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

15 Liquid Pathway Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

17 Sample Collection and Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

17 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

18 Assessment and Evaluation........ . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

20 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

20 Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

21 References. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

22 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 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 -i-TABLE OF CONTENTS (continued)

Appendix A Radiological Environmental Monitoring Program and Sampling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

26 Appendix B Program Modifications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7 Appendix C Program Deviations.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

39 Appendix D Analytical Procedures................................

42 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. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

58 -ii-EXECUTIVE

SUMMARY

This report describes the Radiological Environmental Monitoring Program (REMP) conducted by the Tennessee Valley Authority (TVA) in the vicinity of the Browns Ferry Nuclear Plant (BFN) during the monitoring period of2015. The program is conducted in accordance with regulatory requirements to monitor the environment per 10 CFR 20, 10 CFR 50, and TV A procedures.

The REMP includes the collection and subsequent determination of radioactive material content in environmental samples. Various types of samples are collected within the vicinity of the plant, including air, water, food crops, soil, fish, shoreline sediment, and the measurement of direct radiation levels. The radiation levels of these samples are measured and then compared with results at control stations located outside the plant's vicinity and data collected at Browns Ferry Nuclear Plant prior to operations (preoperational data). This report contains an evaluation of the potential impact of BFN operations on the environment and general public. The vast majority of radioactivity measured in environmental samples from the BFN program can be contributed to naturally occurring radioactive materials.

In 2015, trace quantities of cesium (Cs)-137 were measured in soil and shoreline sediment.

The concentrations were typical of the levels expected to be present in the environment from past nuclear weapons testing or operation of other nuclear facilities in the region. The fallout from accidents at the Chernobyl plant in the Ukraine in 1986 and the Fukushima plant in Japan in 2011 may have also contributed to the low levels of Cs-137 measured in environmental samples. Tritium at concentrations slightly above the analytical detection limit was detected in water samples collected from Wheeler Reservoir and in one sample of groundwater collected from the onsite REMP well. These* levels of radioactive elements detected do not represent a significant contribution to the radiation exposure to members of the public. -I-INTRODUCTION This report describes and summarizes results of radioactivity measurements made in the vicinity of Browns Ferry Nuclear Plant (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 (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 ). 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)-235, 238, thorium (Th)-234, radium (Ra)-226, radon (Rn)-222 and 220, 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 Natural background dose equivalent Cosmic Terrestrial In the body Radon Total Medical (effective dose equivalent)

Nuclear energy Consumer products Total millirem (mrem)/Y ear Per Person 33 21 29 228 311 300 0.28 13 624 (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.

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 Nuclear Regulatory Commission (NRC) guidelines and in the ODCM, is limited as follows:

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

Any organ mrem/Y ear mrem/Y ear millirad (mrad)/Y ear go mrad/Year mrem/Y ear The Environmental Protection Agency 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 mrem/Year mrem/Y ear gs mrem/Y ear 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 e:ffluent 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 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 1 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 5200 people live within a 5-mile radius of the plant. The town of Athens has a population of about 24,000, and is approximately 10 miles northeast of BFN. Approximately 56,000 people live in the city of Decatur 10 miles southeast.

The cities of Madison and Huntsville have a combined population of approximately 230,000 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 11, 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 1and2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation on March 1, 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 effiuent 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 (REMP) and sampling locations are 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.

Program modifications made to the REMP are described in Appendix B. Program 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 ofBFN, a preoperational REMP 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, 1960s, and 1970s, 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 the Tennessee Valley Authority's (TV A's) Environmental Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area Radiological Laboratory in Muscle Shoals, Alabama, with exception of the strontium (Sr)-89, 90 analyses of soil samples which is performed by Teledyne Brown Engineering (TBE), Knoxville, TN. 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 AppendixH.

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 AppendixE.

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 REMP for the measurement of direct radiation.

This dosimeter contains four elements consisting of aluminum oxide detectors with open windows as well as plastic and copper filters. The dosimeter is processed using optical stimulated luminescence (OSL) technology to determine the amount of radiation exposure.

The dosimeters are placed approximately one 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 three months. The dosimeters are sent to Landauer InLight 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 American National Standards Institute (ANSI) N545-l 975 and Health Physics Society (HPS) Draft Standard N 13 .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 "off site." The quarterly gamma radiation levels determined from the dosimeters deployed around BFN in 2015 are summarized in Table H-1. The exposures are measured in milliroentgens (mR). For purposes of this report, one mR, one mrem, and one mrad are assumed to be numerically equivalent.

The rounded average annual exposures, as measured in 2015, are shown below: Onsite Stations Offsite Stations Annual Average Direct Radiation Levels mR/Year BFN 2015 69 55 The data in Table H-1 indicates that the average quarterly direct radiation levels at the BFN onsite stations are approximately 3 .6 mR/quarter higher than levels at the offsite stations.

This equates to 14.4 mR/year detected at the onsite locations.

This value falls below the EPA limit of 25 mrem/year total body. The difference in onsite and off site averages is consistent with levels measured for the preoperational and construction phases of TV A nuclear power plant sites where the average levels onsite were slightly higher than levels offsite. Figure H-1 compares plots of the data from the onsite stations with those from the offsite stations over the period from 1977 through 2015. The new Landauer lnLight Optically Stimulated Luminescence (OSL) dosimeters have been deployed since 2007 replacing the Panasonic UD-814 dosimeters used during the previous years. The data in Table H-2 contains the results of the individual monitoring stations.

The results reported in 2015 are consistent with direct radiation levels identified at locations which are not influenced by the operation ofBFN. 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 monitoring 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 Triethylenediamine (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 iodine (l)-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 2015 was consistent with levels reported in previous years. The annual average gross beta concentrations was 0.018 pCi/m 3* The annual averages of the gross beta activity in air particulate filters for the years 1968-2015 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 TV A 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 2015. 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-11. 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 2015 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. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. Samples of apples, cabbage, com, peas, potatoes, and tomatoes were collected from local gardens in 2015. Samples of these same food crops were purchased from area produce markets or private gardens 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-13 7. The average concentration measured in samples from indicator locations was 0.15 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-137 concentrations in soil is presented in Figure H-3. The concentration of Cs-13 7 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 2015 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 a 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 one 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 for gamma isotopic and 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 of raw untreated water is collected at the intake for the water plant. These samples are collected in the same manner as the surface water samples. These monthly samples are analyzed for gamma isotopic and 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 for gamma isotopic and 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 the 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 Only naturally occurring isotopes were identified by gamma spectral analysis of surface water. Tritium was detected in one downstream (indicator) sample and one upstream (control) sample. Tritium was measured at a concentration of 290 pCi/liter in the indicator sample and 295 p<;i/liter for the control sample. This tritium concentration represented only a small fraction of the Environmental Protection Agency (EPA) drinking water limit of20,000 pCi/liter.

The gross beta activity for surface water samples was consistent with the results from previous years. The average gross beta concentration measured in surface water samples was 2.5 pCi/liter.

A trend plot of the gross beta activity in surface water samples from 1968 through 2015 is presented in Figure H-4. A summary table of the results for this reporting period is shown in Table H-12. No fission or activation products were detected by the gamma analysis of drinking water. Gross beta activity averaged 2.4 pCi/liter at the downstream stations and 2.6 pCi/liter at upstream stations.

These results are consistent with previous monitoring results. Tritium was measured in drinking water samples at a maximum concentration of 337 pCi/liter.

This tritium concentration represented only a small fraction of the EPA drinking water limit of 20,000 pCi/liter.

The results are shown in Table H-13 and a trend plot of the gross beta activity from 1968 to 2015 is presented in Figure H-5. No fission or activation products were detected in groundwater samples from BFN REMP monitoring locations.

Tritium was detected, above the nominal LLD, in one sample collected from the indicator location at a concentration of 454 pCi/liter.

Results from the analysis of groundwater samples are presented in Table H-14. The only 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. The gamma spectroscopy analysis of shoreline sediment samples identified trace levels of Cs-137 in one sample collected from the upstream sampling location.

The concentration was 0.04 pCi/gram.

There was no Cs-137 detected in samples from the downstream locations.

The Cs-13 7 levels were consistent with levels present in the environment as the result of past nuclear weapons testing. The results of 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 TV A 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 calculated doses 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 BFN 2015 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, above the nominal LLD, in soil and shoreline sediment samples. The Cs-137 detected in these samples 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 (Figures H-1 through H-6) 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 result 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 I. Merril Eisenbud, Environmental Radioactivity, Academic Press, Inc., New York, NY, 1987. 2. National Council on Radiation Protection and Measurements, Report No. 160, "Ionizing Radiation Exposure of the Population of the United States," March 2009. 3. United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instruction Concerning Risks from Occupational Radiation Exposure," February 1996.

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

gCi/Liter Concentrations in gCi/Cubic Meter Eftluent Reporting Lower limit Eftluent Reporting Lower limit Analysis Concentration 1 Level 2 of Detection 3 Concentration*

Level 2 of Detection 3 H-3 1,000,000 20,000 270 I00,000 3.0 Cr-51 500,000 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 IO 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 0.03 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 IO 2,000 0.01 Note: l pCi = 3.7 xI0*2 Bq. Note: For those reporting levels that are blank, no value is given in the reference.

1. Table 2 of Appendix B to 10 CFR 20. 2. BFN Offsite Dose Calculation Manual, Table 2.3-3. 3. Table E-1 of this report.

LOUISVll.L£ L L. M \ I M I SS. c I< y GEORGIA V A. s C A R. lmfl -WATTS BAA NUCLEAR PLANT ---SEQUOYAH NUCL£AR PLANT llJI -8ELLEFONTE NUCLEAR PUWT J!I[ -BROWNS FERRY NUCLEAR PLANT ......

Figure 2 ENVIRONMENTAL EXPOSURE PATHWAYS OF MAN CUE TD RELEASES OF RADIOACTIVE MA TE RIAL TD THE ATMOSPHERE AND LAKE.

!fT:iftJ!!>----iii.;;;

-Diluted By Atmosphere Airborne Releases Exposure u MAN Animals By Man Liquid Releases Diluted By Lake (Milk.Meat)

.._ ___ __...., Shoreline 6 Exposure Consumed U By Animals c::::J Vegetation Uptake From Soil .___ ____ ___.. Drinking Water APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND SAMPLING LOCATIONS Exposure Pathway and/or Sample 1. AIRBORNE a. Particulates

b. Radioiodine

c. Soil Table A-1 (1of5) BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8 Number of Samples and Sampling and Locationsb Collection Frequency Six samples from locations (in Continuous sampler operation with different sectors) at or near the site sample collection as required by dust boundary(LM-1, LM-2, LM-3, LM-4, loading but at least once per 7 days. LM-6, and LM-7). Two samples from control locations greater than 10 miles from the plant (RM-I and RM-6). Three samples from locations in communities approximately I 0 miles from the plant (PM-I, PM-2, and PM-3). Same locations as air particulates.

Continuous sampler operation with charcoal canister collection at least once per 7 days. Samples from same locations as air Once every year. particulates. Type and Frequency of Analysis Analyze for gross beta radioactivity following filter change. Perform gamma isotopic analysis on each sample when gross beta activity is greater than 10 times the yearly mean activity for control samples. Perform gamma isotopic analysis on composite (by location) sample at least once per 31 days. 1-131 by gamma scan on each sample. Gamma scan, Sr-89, Sr-90 once per year.

Exposure Pathway and/or Sample 2. DIRECT RADIATION

3. WATERBORNE

a. Surface Water b. Drinking Water Table A-1 (2 of 5) BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8 Number of Samples and Sampling and Type and Frequency Locationsb Collection Frequency of Analysis 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 8 additional locations of special interest.

One sample upstream (TRM 306.0). Collected by automatic sequential-Gross beta and gamma isotopic on One sample immediately downstream type sampler with composite sample 4-week composite.

Composite for of discharge (TRM 293 .5). taken at least once per 31 daysc. tritium at least once per 92 days. One sample at the first potable Collected by automatic sequential-Gross beta and gamma isotopic on surface water supply downstream type sampler with composite sample 4-week composite.

Composite for from the plant (TRM 286.5). taken at least once per 31 daysc. tritium analysis at least once per 92 days.

Exposure Pathway and/or Sample b. Drinking Water (Continued)

c. Ground Water d. Shoreline Sediment Table A-1 (3 of 5) BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 0 Number of Samples and Sampling and Type and Frequency Locationsb Collection Frequency of Analysis Three additional samples of potable Grab sample taken from water supply Gross beta and gamma scan on surface water downstream from the at a facility using water from the 4-week composite.

Composite for plant (TRM 274.9, TRM 259.8, public supply being monitored.

tritium analysis at least once per 92 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. One sample adjacent to the plant Collected by automatic sequential-Gamma scan on each 4-week (Well No. 6R). type sampler with composite sample composite.

Composite for tritium taken at least once per 31 days. analysis at 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. (Farm B) 31 days. Composite for tritium analysis at least once per 92 days. One sample upstream from a At least once per 184 days. Gamma scan of each sample. recreational area {TRM 305).

Exposure Pathway and/or Sample d. Shoreline Sediment (Continued)

4. INGESTION

a. Fish Table A-1 (4 of 5) BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENT AL MONITORING PROGRAM 8 Number of Samples and Locationsb One sample from each of at least two downstream locations with recreational use (TRM 293 and TRM279.5).

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. Sampling and Collection Frequency At least once per 184 days. At least once per 184 days. Type and Frequency of Analysis Gamma scan of each sample. Gamma scan at least once per 184 days on edible portions.

Exposure Pathway and/or Sample b. Fruits and Vegetables Table A-1 (5 of 5) BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8 Number of Samples and Locationsb Samples of food crops such as greens, com, 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 a. The sampling program outlined in this table is that which was in effect at the end of 2015. 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 />. Type and Frequency of Analysis Gamma scan on edible portion. d. The sample location at the Decatur City Water Plant serves as a control sample for both surface water and drinking water.

Map Location Number.B 1 2 3 4 5 6 7 8 9 10 11 12 24 25 26 28 70 71 72 73 74 76 TableA-2 BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Approximate Indicator (I) Distance or Station Sector (Miles) Control CC) PM-1 NW 13.8 I PM-2 NE 10.9 I PM-3 SSE 7.5 I LM-7 w 2.1 I RM-1 w 31.0 c RM-6 E 23.4 c LM-1 NNW 1.0 I LM-2 NNE 0.9 I LM-3 ENE 0.9 I LM-4 NNW 1.7 I LM-6 SSW 3.0 I FannB NNW 6.8 c TRM306.0 12.0d c TRM259.6 34.4d I TRM274.9 19.ld I TRM293.5 o.5d I TRM259.8 34.2d I TRM286.5 7.5d I TRM305 11.0d c TRM293 1.0d I TRM279.5 14.5d I WellNo.6R NW 0.1 I Wheeler Reservoir (TRM 275-349) I Guntersville Reservoir (TRM 349-424) c a. See Figures A-1, A-2, and A-3 b. Sample codes: AP =Air Particulate Filter CF = Charcoal Filter (Iodine) PW = Public Water Samples Collectedb AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S w PW,SW PW PW SW PW PW SS SS SS w F F F =Fish S = Soil SW = Surface Water SS = Shoreline Sediment W = Well Water c. TRM = Tennessee River Mile d. Miles from plant discharge at (TRM 294)

TableA-3 BROWNS FERRY NUCLEAR PLANT ENVIRONMENTAL DOSIMETER LOCATIONS Map Approximate Onsite (On)b Location Distance or Numbe(l Station Sector (Miles) Offsite(Oft)

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-1 NNE 0.9 On 9 ENE-I 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-1 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 SS SW-I SW 1.9 On 56 SW-2 SW 4.7 Off S8 WSW-I 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-1 NW 2.2 Off 67 NW-2 NW 5.3 Off 68 NNW-1 NNW 1.0 On 69 NNW-3 NNW S.2 Off 75 N-IA N 1.0 On a See Figures A-1, 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 281.25 w 268.75 Figure A-1 Radiological Environmental Sampling Locations Within 1 mile of the Plant 5 348.75 N 191.25 s 168.75 Scale 0 Mlle E 1 w Figure A-2 Radiological Environmental Sampling Locations 1 to 5 miles from the Plant

• 0 tt i OJI I 1111.11 7U5 I Figure A-3 Radiological Environmental Sampling Locations Greater than 5 miles from the Plant w £ OU!5 o '"1 16 48 26 d& ta.CO APPENDIXB PROGRAM MODIFICATIONS APPENDIXB Radiological Environmental Monitoring Program Modifications Well 6, the site's indicator groundwater well, was located beneath the maintenance building, which was demolished.

Due to the construction of the new maintenance building and the loss of power to Well 6, the well was removed from the REMP program. A new well, Well 6R, was installed adjacent to the site to replace Well 6. This change was documented in CR1025091.

The location known as Champion Paper Co. at TRM 282.6 was removed from the REMP program due to the fact the location no longer produces its own potable water. The change was documented in CRI 031206.

APPENDIXC PROGRAM DEVIATIONS APPENDIXC Program Deviations Issues with sampling equipment resulted in missed air monitoring samples for one sampling period from one of eleven monitoring locations.

One water sample was not obtained during 2015 due to sampling equipment issues. Environmental dosimeters were missing at four locations during the year. Table C-1 provides details of these program deviations.

Table C-1 Radiological Environmental Monitoring Program Deviations Date Station Location SamnleTvne Descrintion 03/23/2015 LM-4 I. 7 Miles NNW Air Monitor During the weekly REMP filter change, the (AF/CF) technician found station LM-4 not working and contacted EPFS personnel.

An issue with the power switch was discovered and fixed. The monitor was returned to service the same day but the sample volume was not sufficient for analysis.

This issue was identified in CR 1004454. 07/06/2015 Well 6R 0.12 Miles NW Water The automatic sampler for Well 6R was being repaired by the vendor during this sampling period after an issue was discovered during the mid-cycle check. The composite sample was unable to be collected for analysis.

The problem was documented with CR 1045871 and CR 1051963. 2nc1 QTR2015 19-BF-N-lA

1.0 MilesN

Dosimeter The environmental dosimeters from station 19 were missing during the quarterly change out The issue was documented with CR 1053364. 2nc:t QTR2015 15-BF-NNE-2

0. 7 Miles NNE Dosimeter The environmental dosimeters from station 15 were missing during the quarterly change out. The issue was documented with CR 1053362. 3n:1QTR2015 25-BF-SSE-2

7.5 Miles

SSE Dosimeter The environmental dosimeters from station 25 were missing during the quarterly change out. The issue was documented with CR 1090948. 3n:IQTR2015 26-BF-SE-2 5.4Miles SE Dosimeter The environmental dosimeters from station 26 were missing during the quarterly change out The issue was documented with CR 1090958.

APPENDIXD ANALYTICAL PROCEDURES AppendixD Analytical Procedures Analyses of environmental samples are performed by the radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals with the exception of the Sr-89, 90 analysis of soil samples which are performed by Teledyne Brown Engineering, Knoxville, 1N. 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 milliliters 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. The charcoal cartridges used to sample gaseous radioiodine are 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.

APPENDIXE NOMINAL LOWER LIMITS OF DETECTION AppendixE 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 Radiological Environmental Monitoring Program (REMP). The nominal LLD values are calculated using the methodology prescribed in the Offsite Dose Calculation Manual (ODCM). These nominal LLD values are presented in Table E-1. The maximum LLD values specified in the ODCM are shown in Table E-2. Mille samples are not currently collected and analyzed for the Browns Ferry Nuclear Plant REMP, but the nominal LLD values for the analysis of millc are included in the tables to maintain the historical record of the laboratory's measurement capabilities.

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

Analysis Gross Beta Tritium Iodine-131 Strontium-89 Strontium-90 Air Filters (pCi/m 3) 0.002 TABLEE-1 Nominal LLD Values A. Radiochemical Water (pCi/Ll 1.9 270 0.4 Milk (pCi/L) 0.4 3.5 2.0 Sediment and Soil (pCi/g dtyl 1.6 0.4 Table E-1 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. Analysis pCi/m 3 pCi/m 3 pCi/L pCi/g. dry pCilkg. wet pCi/g. dry pCi/g. dry pCi/kg. wet Ce-141 0.005 0.02 IO 0.07 35 O.IO 0.07 20 Ce-144 0.01 0.07 30 0.15 115 0.20 0.15 60 Cr-51 0.02 0.15 45 0.30 200 0.35 0.30 95 I-131 0.005 0.03 IO 0.20 60 0.25 0.20 20 Ru-103 0.005 0.02 5 0.03 25 0.03 0.03 25 Ru-106 0.02 0.12 40 0.15 190 0.20 0.15 90 Cs-134 0.005 0.02 5 0.03 30 0.03 0.03 IO Cs-137 0.005 0.02 5 0.03 25 0.03 0.03 IO Zr-95 0.005 0.03 IO 0.05 45 0.05 0.05 45 Nb-95 0.005 0.02 5 0.25 30 0.04 0.25 IO Co-58 0.005 0.02 5 0.03 20 0.03 0.03 10 Mn-54 0.005 0.02 5 0.03 20 0.03 0.03 10 Zn-65 0.005 0.03 10 0.05 45 0.05 0.05 45 Co-60 0.005 0.02 5 0.03 20 0.03 0.03 IO K-40 0.04 0.30 100 0.40 400 0.75 0.40 250 Ba-140 0.015 0.07 25 0.30 130 0.30 0.30 50 La-140 0.01 0.04 10 0.20 50 0.20 0.20 25 Fe-59 0.005 0.04 10 0.08 40 0.05 0.08 25 Be-7 0.02 0.15 45 0.25 200 0.25 0.25 90 Pb-212 0.005 0.03 15 0.04 40 0.10 0.04 40 Pb-214 0.005 0.07 20 0.50 80 0.15 0.50 80 Bi-214 0.005 0.05 20 O.IO 55 0.15 O.IO 40 Bi-212 0.02 0.20 50 0.25 250 0.45 0.25 130 Tl-208 0.002 0.02 10 0.03 30 0.06 0.03 30 Ra-224 0.75 Ra-226 0.15 Ac-228 0.01 0.07 20 0.10 70 0.25 0.10 so Pa-234m 800 4.00 Table E-2 Maximum LLD Values Specified by the BFN ODCM Airborne Particulate Food Water or Gases Fish Mille Products Sediment Analysis pCi/L pCi/m 3 pCi/kg. wet pCi/L pCi/kg. wet pCi/kg. dry gross beta 4 0.01 N.A. N.A. N.A. H-3 2oooa N.A. N.A. N.A. N.A. Mn-54 15 N.A. 130 N.A. N.A. Fe-59 30 N.A. 260 N.A. N.A. Co-58, 60 15 N.A. 130 N.A. N.A. Zn-65 30 N.A. 260 N.A. N.A. Zr-95 30 N.A. N.A.

N.A. N.A. Nb-95 15 N.A. N.A. N.A. N.A. I-131 lb 0.07 N.A. I 60 Cs-134 15 0.05 130 15 60 Cs-137 18 0.06 150 18 80 Ba-140 60 N.A. N.A. 60 N.A. La-140 15 N.A. N.A. 15 N.A. a. If no drinking water pathway exists, a value of 3000 pCi/L may be used. b. LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L. If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for 1-131. N.A. N.A. N.A. N.A. N.A. N.A. N.A. N.A. N.A. 150 180 N.A. N.A.

APPENDIXF QUALITY ASSURANCE/QUALITY CONTROL PROGRAM AppendixF Quality Assurance/Quality Control Program A quality assurance program is employed by the ERM&I 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, field and lab duplicates, analytical knowns, blind spikes, and 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.

Duplicates are samples 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. The analysis results for internal cross-check samples met the program performance goals for 2015. 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 2015. The results for these cross-check samples, as shown in Table F-1, were all within the program agreement limits with the exception of the Sr-90 in Milk result for the first quarter cross-checks.

The disagreement was documented in CR 1106899. All other Sr-90 results were in agreement.

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-1 Results For 2015 External Cross Checks &mill Test Period Saronle Tvne I Analysis K!!mm IYA First Quarter Water (pCi/L) Gross Beta 2.80E+o2 2.83E+o2 Yes First Quarter Water (pCi/L) JH l.26E+04 l.36E+04 Yes First Quarter Water (pCi/L) ml 9.67E+ol 9.83E+ol Yes 51 Cr 3.66E+o2 3.76E+o2 Yes iucs 1.26E+o2 l.23E+o2 Yes in cs l.67E+o2 l.69E+o2 Yes SICo l.80E+o2 l.81E+o2 Yes S4Mn l.S9E+o2 l.67E+o2 Yes 59 Fe l.9SE+o2 J.92E+o2 Yes 6'ZD 2.99E+o2 3.09E+o2 Yes 60 Co 3.28E+o2 3.2SE+o2 Yes 141Ce l.39E+o2 l.49E+o2 Yes First Quarter Synthetic Urine (pCi/L) ,H l.43E+04 1.46E+04 Yes First Quarter Millc(pCi/L) ml 9.90E+ol 9.0SE+ol Yes "Sr 9.68E+ol 8.61E+ol Yes 90 Sr l.32E+o1 8.90E+oo No First Quarter Air Filter (pCi/Filter)

Gross Beta l.OOE+o2 9.46E+o1 Yes Third Quarter Water (pCi/L) JH l.32E+04 1.36E+04 Yes Third Quarter S811d (pCi/gram) aoCe 3.38E-01 3.IOE-01 Yes Sier 8.54.E-Ol 8.20E-01 Yes iucs 3.36E-01 2.82E-Ol Yes 137 Cs 4.05.E-01 3.78E-Ol Yes "co 4.ISE-01 4.0IE-01 Yes S4Mn 4.61.E-01 4.70E-01 Yes 59 Fe 3.SS.E-01 3.39E-01 Yes 6SZD S.61E-OI 5.7SE-01 Yes 60 Co S.24.E-01 5.13.E-01 Yes Third Quarter Air Filter (pCi/Filter)

Gross Beta 9.21E+ol 7.70E+o1 Yes Third Quarter Air Filter (pCi/Filter) 141Ce 8.34E+ol 8.36E+ol Yes Sier 2.11E+o2 2.0lE+o2 Yes iucs 8.29E+ol 6.60E+ol Yes 137 Cs 9.98E+OI 9.55E+ol Yes "co l.03E+o2 9.96E+OI Yes S4Mn l.14E+o2 1.19E+o2 Yes 59 Fe 8.84E+ol 9.05E+ol Yes 6'ZD 1.38E+o2 l.SOE+02 Yes 60 Co 1.29E+o2 l.32E+02 Yes Third Quarter Synthetic Urine (pCi/L) ,H l.39E+04 l.40E+04 Yes Fourth Quarter Mille (pCi/L) ml 8.97E+ol 9.38E+ol Yes "sr 9.00E+ol 8.28E+ol Yes 90 Sr 1.57E+ol l.27E+ol Yes APPENDIXG 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 (8 km) 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 (5 km) from the plant. The land use survey was conducted between April 1, 2015, and October 1, 2015, 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 Browns Ferry Nuclear Plant (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 location of the nearest resident in 2015 as compared to 2014. The location of the nearest garden as identified in the 2015 survey did not change. However, no garden was identified in the west sector in 2015. 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 2014 and 2015.

Sector N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Table G-1 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within 8 km (5 Miles) of the Plant (mrem/Y ear) 2014 Survey 2015 Survey Approximate Approximate Distance Annual Distance Meters Dose Meters 2,440 0.34 2,440 2,620 0.14 2,620 2,020 0.17 2,020 2,460 0.17 2,460 1,410 0.40 1,410 1,750 0.24 1,750 a a a a 4,540 0.15 4,540 4,610 0.16 4,610 4,650 0.10 4,650 4,200 0.07 4,200 2,660 0.17 2,660 5,280 0.10 5,280 3,150 0.33 3,150 1,650 0.75 1,650 a. There is no residence within the 8 km radius for this sector. Annual Dose 0.34 0.14 0.17 0.17 0.40 0.24 0.15 0.16 0.10 0.07 0.17 0.10 0.33 0.75 Table G-2 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods (mrem/Y ear) 2014 2015 Number of Approximate Approximate Gardens Within Distance Annual Distance Annual 5 km (3 Miles) Sector Meters Dose Meters Dose for 2015 N 2,540 5.99 2,540 5.99 1 NNE 5,980 0.88 5,980 0.88 1 NE 3,790 1.50 3,790 1.50 2 ENE 5,070 1.06 5,070 1.06 1 E 1,410 6.70 1,410 6.70 3 ESE 1,830 6.10 1,830 6.10 2 SE a a 0 SSE a a 0 s 4,540 2.24 4,540 2.24 1 SSW 4,880 2.14 4,880 2.14 I SW 4,940 1.00 4,940 1.00 I WSW 4,330 0.60 4,330 0.60 I w 2,860 1.20 a 0 WNW a a 0 NW a a 0 NNW 2,290 7.30 2,290 7.30 5 a. No garden was found within 8 km radius for this sector.

APPENDIXH DATA TABLES AND FIGURES Average, 0-2 miles (onsite) Average, >2 miles (offsite)

Table H-1 DIRECT RADIATION LEVELS 2015 Average External Gamma Radiation Levels On-site and Off-site for Browns Ferry Nuclear Plant for Each Quarter (mR I Quarter) a. Average External Gamma Radiation Levels b. 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr mRNrc. 16.1 16.4 20 16.9 69 12.8 13.2 15.5 13.6 55 (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. (c). The 14.4 mR/yr for onsite locations falls below the 25 mrem total body limit in 1 O CFR 190.

Table H-2 (1 of 2) DIRECT RADIATION LEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels mR I Quarter Map Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual 1 Jan -Apr-Jul-Oct-Location Station Direction, Distance, Mar Jun Sep Dec Exposure Number Number Degrees Miles 2015 2015 2015 2015 mRNear 7 N-1 348 1.0 15.5 18.7 24.2 17.7 76.1 75 N-1A 355 1.0 20.9 (1) 20.6 17.7 78.9 38 N-2 1 5.0 9.6 12.6 14.6 12.3 49.1 8 NNE-1 12 0.9 14.4 15.9 17.6 17.7 65.6 39 NNE-2 31 0.7 22.5 (1) 22.2 15.3 80.0 40 NNE-3 19 5.2 11.7 13.6 15.6 12.3 53.2 41 NE-1 51 0.8 15.5 17.3 20.6 19.7 73.1 42 NE-2 49 5.0 18.7 15.0 17.1 16.3 67.1 2 NE-3 56 10.9 14.4 15.9 14.6 13.3 58.2 9 ENE-1 61 0.9 18.2 15.9 21.1 17.2 72.4 43 ENE-2 62 6.2 12.8 15.4 18.1 16.7 63.0 44 E-1 85 0.8 16.6 16.8 21.1 16.7 71.2 45 E-2 91 5.2 11.7 13.1 17.6 13.8 56.2 6 E-3 90 23.1 12.3 15.9 15.6 14.8 58.6 46 ESE-1 110 0.9 11.7 15.0 18.6 15.8 61.1 47 ESE-2 112 3.0 17.6 15.9 13.5 12.8 59.8 48 SE-1 130 0.5 15.5 18.2 20.6 16.7 71.0 49 SE-2 135 5.4 15.0 13.1 (1) 17.7 61.1 50 SSE-1 163 5.1 13.4 14.0 16.1 15.8 59.3 3 SSE-2 165 7.5 15 15.9 (1) 14.3 60.3 51 S-1 185 3.1 17.1 13.1 19.1 14.3 63.6 (1) Sum of available quarterly data normalized to 1 year for the annual exposure value.

Table H-2 (2 of 2) DIRECT RADIATION LEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels mR I Quarter Map Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual 1 Jan-Apr-Jul-Oct-Location Station Direction, Distance, Mar Jun Sep Dec Exposure Number Number Degrees Miles 2015 2015 2015 2015 mRNear 52 S-2 182 4.8 10.7 15.0 18.1 12.8 56.6 53 SSW-1 203 3.0 11.7 9.4 15.6 12.8 49.5 54 SSW-2 199 4.4 12.3 13.6 13.0 14.8 53.7 55 SW-1 228 1.9 15.5 13.6 19.1 17.2 65.4 56 SW-2 219 4.7 15.5 15.0 15.1 14.3 59.9 58 WSW-1 244 2.7 13.4 10.3 13.5 10.9 48.1 59 WSW-2 251 5.1 14.4 14.5 19.6 15.8 64.3 60 WSW-3 257 10.5 12.8 11.7 15.6 12.8 52.9 61 W-1 275 1.9 12.8 16.4 15.6 14.3 59.1 62 W-2 268 4.7 9.1 12.6 14 13.3 46.7 5 W-3 275 31.0 13.4 11.7 14.0 11.4 50.5 64 WNW-1 291 3.3 11.2 10.3 19.1 13.8 54.4 65 WNW-2 293 4.4 13.4 12.2 15.6 11.8 53.0 66 NW-1 326 2.2 11.7 13.1 15.1 12.8 52.7 67 NW-2 321 5.3 11.7 14.5 16.1 15.3 57.6 1 NW-3 310 13.8 11.2 12.2 12.0 11.4 46.8 68 NNW-1 331 1.0 15.0 15.9 18.1 17.2 66.2 10 NNW-2 331 1.7 15.5 16.7 20.8 16.7 69.7 69 NNW-3 339 5.2 10.7 13.1 17.1 14.3 55.2 (1) Sum of available quarterly data normalized to 1 year for the annual exposure value.

I OI N I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Lower Limit Total Number of Detection of Analysis (LLD) Performed See Note 1 GROSS BETA -571 2.00E-03 GAMMA SCAN (GELi) -143 AC-228 1.00E-02 BE-7 2.00E-02 Bl-214 5.00E-03 K-40 4.00E-02 PB-212 5.00E-03 PB-214 5.00E-03 TL-208 2.00E-03 Indicator Locations Mean (F) Range See Note 2 1.90E-02 (467 I 467) 4.60E-03 -3.41E-02 117VALUES

<LLD 9.80E-02 (117/117) 7 .1 OE-02 -1.23E-01 1.91E-02 (1151117) 5.1 OE-03 -4.83E-02 117 VALUES < LLD 117 VALUES< LLD 1.88E-02 (110/117) 5.00E-03 -4.89E-02 2.40E-03 (3 / 117) 2.1 OE-03 -2.SOE-03 Tennessee Valley Authority RADIOACTIVITY IN AIR FILTER pCilm"3 = 0.037 Bq/m"3 Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 PM-3 BF DECATUR AL 2.00E-02 (52 / 52) 8.2 MILES SSE 5.58E-03 -3.07E-02 LM3 BF NORTHEAST 13 VALUES< LLD 1.0 MILE ENE PM-3 BF DECATUR AL 1.05E-01 (13/13) 8.2 MILES SSE 8.58E-02 -1.23E-01 PM-3 BF DECATUR AL 2.91E-02 (13113) 8.2 MILES SSE 1.66E-02 -4.17E-02 LM2 BF NORTH 13 VALUES< LLD 0.9 MILE NNE LM2 BF NORTH 13 VALUES< LLD 0.9 MILE NNE PM-3 BF DECATUR AL 2.90E-02 (13113) 8.2 MILES SSE 1.69E-02 -4.64E-02 LM2BF NORTH 2.45E-03 (2 / 13) 0.9 MILE NNE 2.1 OE-03 -2.SOE-03 Control Locations Mean (F) Range See Note 2 1.73E-02 (1041104) 2.68E-03 -3.14E-02 26 VALUES < LLD 9.29E-02 (26 I 26) 6.26E-02 -1.36E-01 1.57E-02 (24 I 26) 5.30E-03 -3.22E-02 26 VALUES < LLD 26 VALUES < LLD 1.45E-02 (22 / 26) 5.SOE-03 -3.31E-02 2.00E-03 (1 I 26) 2.00E-03 -2.00E-03 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements onty. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 -Cl) ::c: I w I °' w I 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 GAMMA SCAN (GELi) -571 BE-7 1.50E-01 1.72E-01 (1/467) 1. 72E-01 -1. 72E-01 Bl-214 5.00E-02 9.37E-02 (251/467) 5.03E-02 -3.03E-01 1-131 3.00E-02 SEE NOTE4 K-40 3.00E-01 3.44E-01 (101/467) 3.01E-01 -5.26E-01 PB-212 3.00E-02 3.37E-02 (1 I 467) 3.37E-02 -3.37E-02 PB-214 7.00E-02 1.19E-01 (150 / 467) 7.02E-02 -3.57E-01 TL-208 2.00E-02 467 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN CHARCOAL FILTER pCilm"3 = 0.037 Bq/m"3 Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 LM-7BF LAKEVIEW 2.1 MILES WEST LM3 BF NORTHEAST 1.0 MILE ENE LM3 BF NORTHEAST 1.0 MILE ENE LM1 BF NORTHWEST 1.0 MILE N PM-1 ROGERSVILLE AL 13.8 MILES NW PM-2 BF ATHENS AL 10.9 MILES NE 1. 72E-01 (1 I 52) 1.72E-01 -1.72E-01 1.19E-01 (30 I 52) 5.25E-02 -2.90E-01 3.72E-01 (13 / 52) 3.06E-01 -5.26E-01 3.37E-02 (1 I 52) 3.37E-02 -3.37E-02 1.44E-01 (19 / 52) 7.18E-02 -3.53E-01 52 VALUES< LLD Control Locations Mean (F) Range See Note2 104 VALUES < LLD 1.12E-01 (46/104) 5.19E-02 -4.54E-01 3.38E-01 (14 / 104) 3.05E-01 -4.21E-01 3.80E-02 (1 / 104) 3.80E-02 -3.80E-02 1.33E-01 (33 / 104) 7.05E-02 -5.07E-01 104 VALUES< LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 4. 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.

I °' I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Lower Limit Total Number of Detection of Analysis (LLD) Performed See Note 1 GAMMA SCAN (GELi) -11 AC-228 2.50E-01 BE-7 2.50E-01 Bl-212 4.50E-01 Bl-214 1.50E-01 CS-137 3.00E-02 K-40 7.50E-01 PA-234M 4.00E+OO PB-212 1.00E-01 PB-214 1.50E-01 RA-226 1.50E-01 TL-208 6.00E-02 SR 89 -11 1.60E+OO SR 90 -11 4.00E-01 Indicator Locations Mean (F) Range See Note 2 1.15E+OO (9 I 9) 5.93E-01 -1.40E+OO 5.68E-01 (4/9) 3.03E-01 -1.25E+OO 1.24E+OO (9 I 9) 6.12E-01 -1.52E+OO 1.02E+OO (9 / 9) 6.60E-01 -1.30E+OO 1.50E-01 (8 / 9) 3.98E-02 -3.0SE-01 5.24E+OO (9 I 9) 2.58E+OO -8.23E+OO 4.13E+OO (119) 4.13E+OO -4.13E+OO 1.13E+OO (9 / 9) 5.61E-01 -1.38E+OO 1.10E+OO (919) 6.74E-01 -1.40E+OO 1.02E+OO (9 / 9) 6.60E-01 -1.30E+OO 3.78E-01 (9 / 9) 1.84E-01 -4.61 E-01 9 VALUES < LLD 9 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN SOIL pCi/g = 0.037 Bq/g (DRY WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 LM1 BF NORTHWEST 1.40E+OO (1/1) 1.0 MILE N 1.40E+OO -1.40E+OO PM-1 ROGERSVILLE AL 1.25E+OO (111) 13.8 MILES NW 1.25E+OO -1.25E+OO LM1 BF NORTHWEST 1.52E+OO (1/1) 1.0 MILE N 1.52E+OO -1.52E+OO LM2BFNORTH 1.30E+OO (1/1) 0.9MILE NNE 1.30E+OO -1.30E+OO LM-6BF BAKER BOTTOM 3.08E-01 (1 / 1) 3.0 MILES SSW 3.08E-01 -3.08E-01 LM2BF NORTH 8.23E+OO (1 / 1) 0.9MILENNE 8.23E+OO -8.23E+OO LM2BFNORTH 4.13E+OO (1 / 1) 0.9 MILE NNE 4.13E+OO -4.13E+OO LM2 BF NORTH 1.38E+OO (1 / 1) 0.9MILE NNE 1.38E+OO -1.38E+OO LM2BFNORTH 1.40E+OO (1/1) 0.9MILE NNE 1.40E+OO -1.40E+OO LM2BF NORTH 1.30E+OO (1/1) 0.9MILE NNE 1.30E+OO -1.30E+OO LM2BFNORTH 4.61E-01 (1 / 1) 0.9MILENNE 4.61 E-01 -4.61 E-01 Control Locations Mean (F) Range See Note 2 9.12E-01 (2 / 2) 8.37E-01 -9.87E-01 2 VALUES < LLD 1.01 E+OO (2 / 2) 9.45E-01 -1.07E+OO 8.43E-01 (212) 8.16E-01 -8.70E-01 9.1 OE-02 (2 I 2) 7.33E-02 -1.09E-01 3.35E+OO (2 I 2) 2.00E+OO -4.71E+OO 2 VALUES < LLD 9.43E-01 (2 / 2) 8.64E-01 -1.02E+OO 9.38E-01 (2 / 2) 8.57E-01 -1.02E+OO 8.43E-01 (2 / 2) 8.16E-01 -8.70E-01 3.01E-01 (2 / 2) 2.81E-01 -3.20E-01 2 VALUES< LLD 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutlne Reported Measurements See Note 3 a" -Vl Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -2 81-214 K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD) See Note 1 4.00E+01 2.50E+02 4.00E+01 8.00E+01 3.00E+01 Indicator Locations Mean (F) Range See Note 2 6.66E+01 (1 / 1) 6.66E+01 -6.66E+01 1.07E+03 (1 / 1) 1.07E+03 -1.07E+03 1 VALUES < LLD 1 VALUES < LLD 1 VALUES< LLD Tennessee Valley Authority RADIOACTIVITY IN APPLES pCl/Kg = 0.037 Bq/Kg (WET WEIGHn Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 1 MILENNW 6.66E+01 (1 / 1) 6.66E+01 -6.66E+01 1 MILENNW 1.07E+03 (1/1) 1.07E+03 -1.07E+03 1 MILENNW 1 VALUES < LLD 1 MILENNW 1 VALUES < LLD 1 MILENNW 1 VALUES < LLD Control Locations Mean (F) Range See Note 2 1 VALUES < LLD 1.14E+03 (1/1) 1.14E+03 -1.14E+03 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F}. 3. Blanks in this column Indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 -CD ::z:: I °'

I °' °' I Name of Facility:

BROWNS FERRY NUCLEAR PLA.NT Location of Facility:

LIMESTONE, ALA.SAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -2 Bl-214 K-40 PB-212 PB-214 Lower Limit of Detection (LLD) See Note 1 4.00E+01 2.50E+02 4.00E+01 8.00E+01 Indicator Locations Mean (F) Range See Note 2 5.18E+01 (1 / 1) 5.18E+01 -5.18E+01 1.36E+03 (1/1) 1.36E+03 -1.36E+03 1 VALUES < LLD 1 VALUES< LLD Tennessee Valley Authority RADIOACTIVITY IN CABBAGE pCi/Kg = 0.037 Bq/Kg (WET WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 C.MOSLEY FARM 5.18E+01 (1 / 1) 1.58 MILES N 5.18E+01 -5.18E+01 C.MOSLEY FARM 1.36E+03 (1/1) 1.58 MILES N 1.36E+03 -1.36E+03 C.MOSLEY FARM 1 VALUES < LLD 1.58 MILES N C.MOSLEY FARM 1 VALUES < LLD 1.58MILESN Control Locations Mean (F) Range See Note2 5.85E+01 (1 / 1) 5.85E+01 -5.85E+01 1.46E+03 (1 / 1) 1.46E+03 -1.46E+03 1 VALUES < LLD 1 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note3 I °' .....J I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -2 Bl-214 K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD) See Note 1 4.00E+01 2.50E+02 4.00E+01 8.00E+01 3.00E+01 Indicator Locations Mean (F) Range See Note 2 6.32E+01 (111) 6.32E+01 -6.32E+01 2.05E+03 (1/1) 2.05E+03 -2.05E+03 1 VALUES < LLD 1 VALUES< LLD 1 VALUES< LLD Tennessee Valley Authority RADIOACTIVITY IN CORN pCi/Kg = 0.037 Bq/Kg {WET WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 LM-6BF BAKER BOTIOM 6.32E+01 (1 11) 3.0 MILES SSW 6.32E+01 -6.32E+01 LM-6BF BAKER BOTIOM 2.05E+03 (111) 3.0 MILES SSW 2.05E+03 -2.05E+03 LM-6BF BAKER BOTIOM 1 VALUES < LLD 3.0 MILES SSW LM-6BF BAKER BOTIOM 1 VALUES < LLD 3.0 MILES SSW LM-6BF BAKER BOTIOM 1 VALUES < LLD 3.0 MILES SSW Control Locations Mean (F) Range See Note 2 6.04E+01 (1 / 1) 6.04E+01 -6.04E+01 2.02E+03 (1 11) 2.02E+03 -2.02E+03 1 VALUES< LLD 1 VALUES< LLD 1 VALUES< LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column Indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note3 ...., -CD ::c: I 00 I °' Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN {GELi) -2 AC-228 81-214 K-40 PB-212 PB-214 Lower Limit of Detection

{LLD) See Note 1 5.00E+01 4.00E+01 2.50E+02 4.00E+01 8.00E+01 Indicator Locations Mean {F) Range See Note 2 5.53E+01 (1 / 1) 5.53E+01 -5.53E+01 1.86E+02 (1/1) 1.86E+02 -1.86E+02 3.51 E+03 (1 / 1) 3.51E+03 -3.51E+03 1 VALUES < LLD 1 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN POTATOES pCi/Kg = 0.037 Bq/Kg (WET WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 2.3 MILES NNW 5.53E+01 {1 / 1) 5.53E+01 -5.53E+01 2.3 MILES NNW 1.86E+02 (1 / 1) 1.86E+02 -1.86E+02 2.3 MILES NNW 3.51E+03 (1 / 1) 3.51 E+03 -3.51 E+03 2.3 MILES NNW 1 VALUES < LLD 2.3 MILES NNW 1 VALUES < LLD Control Locations Mean (F) Range See Note2 1 VALUES < LLD 5.06E+01 (1 / 1) 5.06E+01 -5.06E+01 3.49E+03 (1 / 1) 3.49E+03 -3.49E+03 1 VALUES< LLD 1 VALUES< LLD TL-208 3.00E+01 1 VALUES < LLD 2.3 MILES NNW 1 VALUES < LLD 1 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is Indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 1--3 g. -R ::c: I \0 Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -2 Bl-214 K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD) See Note 1 4.00E+01 2.50E+02 4.00E+01 8.00E+01 3.00E+01 Indicator Locations Mean (F) Range See Note 2 5.63E+01 (1 / 1) 5.63E+01 -5.63E+01 2.58E+03 (1 / 1) 2.58E+03 -2.58E+03 1 VALUES< LLD 1 VALUES < LLD 1 VALUES< LLD Tennessee Valley Authority RADIOACTIVITY IN TOMATOES pCi/Kg = 0.037 Bq/Kg (WET WEIGHn Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 1.4 MILES NNW 5.63E+01 (1 / 1) 5.63E+01 -5.63E+01 1.4 MILES NNW 2.58E+03 (1 / 1) 2.58E+03 -2.58E+03 1.4 MILES NNW 1 VALUES < LLD 1.4 MILES NNW 1 VALUES< LLD 1.4 MILES NNW 1 VALUES < LLD Control Locations Mean (F) Range See Note 2 1 VALUES < LLD 1.62E+03 (1/1) 1.62E+03 -1.62E+03 1 VALUES < LLD 1 VALUES< LLD 1 VALUES< LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 t-3 Ci" ,__. 0 I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -2 Bl-214 K-40 PB-214 Lower Limit of Detection (LLD) See Note 1 4.00E+01 2.50E+02 8.00E+01 Indicator Locations Mean (F) Range See Note 2 9.56E+01 (1 / 1) 9.56E+01 -9.56E+01 3.50E+03 (1 / 1) 3.50E+03 -3.50E+03 8.43E+01 (1 / 1) 8.43E+01 -8.43E+01 Tennessee Valley Authority RADIOACTIVITY IN PEAS pCl/Kg = 0.037 Bq/Kg (WET WEIGHn Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 LM-6BF BAKER BOTIOM 9.56E+01 (1 / 1) 3.0 MILES SSW 9.56E+01 -9.56E+01 LM-6BF BAKER BOTIOM 3.50E+03 (1 / 1) 3.0 MILES SSW 3.50E+03 -3.50E+03 LM-6BF BAKER BOTIOM 8.43E+01 (1 / 1) 3.0 MILES SSW 8.43E+01 -8.43E+01 Control Locations Mean (F) Range See Note 2 8.94E+01 (1 / 1) 8.94E+01 -8.94E+01 5.06E+03 (1 / 1) 5.06E+03 -5.06E+03 1 VALUES< LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 ...., -n --

I -...J -I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Lower limit Total Number of Detection of Analysis (LLD) Performed See Note 1 GROSS BETA -26 1.90E+OO GAMMA SCAN (GELi) -26 Bl-214 2.00E+01 K-40 1.00E+02 PB-212 1.50E+01 PB-214 2.00E+01 TL-208 1.00E+01 TRITIUM -8 2.70E+02 Indicator Locations Mean (F) Range See Note2 2.44E+OO (7 / 13) 1.91 E+OO -3.26E+OO 4.49E+01 (5 / 13) 2.50E+01 -6.99E+01 13 VALUES< LLD 13 VALUES< LLD 3.53E+01 (5 / 13) 2.36E+01 -5.17E+01 13 VALUES< LLD 2.90E+02 (1 I 4) 2.90E+02 -2.90E+02 Tennessee Valley Authority RADIOACTIVITY IN SURFACE WATER (Total) pCi/L = 0.037 Bq/L Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 TRM 293.5 TRM293.5 TRM 293.5 TRM 293.5 TRM 293.5 TRM 293.5 TRM 293.5 2.44E+OO (7 / 13) 1.91 E+OO -3.26E+OO 4.49E+01 (5 / 13) 2.50E+01 -6.99E+01 13 VALUES< LLD 13 VALUES< LLD 3.53E+01 (5 / 13) 2.36E+01 -5.17E+01 13 VALUES< LLD 2.90E+02 (1 I 4) 2.90E+02 -2.90E+02 Control Locations Mean (F) Range See Note 2 2.55E+OO (8 / 13) 1.95E+OO -3. 77E+OO 3.32E+01 (7 / 13) 2.14E+01 -6.06E+01 13 VALUES< LLD 13 VALUES< LLD 3.62E+01 (4 / 13) 2.46E+01 -5.14E+01 13 VALUES < LLD 2.95E+02 (1 I 4) 2.95E+02 -2.95E+02 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 c::T -..._. N I ........ t-.J I Tennessee Valley Authority RADIOACTIVITY IN PUBLIC (DRINKING)

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: 2015 Type and Lower limit Indicator Locations Total Number of Detection Mean (F) of Analysis (LLD) Range Performed See Note 1 See Note 2 GROSS BETA -72 1.90E+OO 2.35E+OO (34 I 59) 1.91E+OO -3.18E+OO GAMMA SCAN (GELi) -72 AC-228 2.00E+01 2.04E+01 (1 / 59) 2.04E+01 -2.04E+01 Bl-214 2.00E+01 3.86E+01 (28 / 59) 2.32E+01 -9.21E+01 K-40 1.00E+02 3.21 E+02 (1 I 59) 3.21E+02 -3.21E+02 PB-212 1.50E+01 1.55E+01 (1 / 59) 1.55E+01 -1.55E+01 PB-214 2.00E+01 3.41E+01 (23 / 59) 2.04E+01 -7.54E+01 Tl-208 1.00E+01 59 VALUES< LLD TRITIUM -22 2.70E+02 3.08E+02 (10 I 18) 2.70E+02 -3.37E+02 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 CHAMPION PAPER TRM 282.6 WHEELER DAM, Al TRM 274.9 WHEELER DAM, Al TRM274.9 WHEELER DAM, Al TRM 274.9 WHEELER DAM, Al TRM274.9 FLORENCE, Al TRM259.8 FLORENCE, Al TRM259.8 CHAMPION PAPER TRM 282.6 2.42E+OO (4 I 7) 1.97E+OO -2.86E+OO 2.04E+01 (1 / 13) 2.04E+01 -2.04E+01 4.75E+01 (8 / 13) 2.97E+01 -8.50E+01 3.21 E+02 (1 I 13) 3.21 E+02 -3.21 E+02 1.55E+01 (1 / 13) 1.55E+01 -1.55E+01 3.96E+01 (5 / 13) 2.25E+01 -6.97E+01 13 VALUES< LLD 3.19E+02 (1 I 2) 3.19E+02 -3.19E+02 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 Control Locations Mean (F) Range See Note 2 2.55E+OO (8 / 13) 1.95E+OO -3. 77E+OO 13 VALUES< LLD 3.32E+01 (7 / 13) 2.14E+01 -6.06E+01 13 VALUES< LLD 13 VALUES< LLD 3.62E+01 (4 / 13) 2.46E+01 -5.14E+01 13 VALUES< LLD 2.95E+02 (1 I 4) 2.95E+02 -2.95E+02 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 tr ::c I ...... w I ....:i w I Tennessee Valley Authority RADIOACTIVITY IN WELL (GROUND) 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: 2015 Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -25 AC-228 Bl-214 K-40 PB-212 PB-214 TL-208 TRITIUM -8 Lower Limit of Detection (LLD) See Note 1 2.00E+01 2.00E+01 1.00E+02 1.50E+01 2.00E+01 1.00E+01 2.70E+02 Indicator Locations Mean (F) Range See Note 2 2.63E+01 (1 / 12) 2.63E+01 -2.63E+01 4.07E+01 (10 / 12) 2.40E+01 -8.84E+01 12 VALUES< LLD 12 VALUES< LLD 3.48E+01 (10 / 12) 2.22E+01 -7.56E+01 12 VALUES< LLD 4.54E+02 (1/4) 4.54E+02 -4.54E+02 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 BFN WELL#6R 2.63E+01 (1 / 6) 0.12 MILES NW 2.63E+01 -2.63E+01 BFN WELL#6 4.60E+01 (6 / 6) 0.02 MILESW 2. 73E+01 -8.84E+01 BFN WELL#6R 6 VALUES< LLD 0.12 MILES NW BFN WELL#6 6 VALUES < LLD 0.02MILESW BFN WELL#6 3.78E+01 (6 / 6) 0.02MILESW 2.22E+01 -7.56E+01 BFN WELL#6 6 VALUES < LLD 0.02MILESW BFN WELL#6 4.54E+02 (1 I 2) 0.02 MILESW 4.54E+02 -4.54E+02 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1 Control Locations Mean (F) Range See Note2 1.16E+02 (1/13) 1.16E+02 -1.16E+02 3.04E+02 (13/13) 1.00E+02 -4.84E+02 13 VALUES< LLD 13 VALUES< LLD 3.06E+02 (13 / 13) 8.90E+01 -4.96E+02 13 VALUES< LLD 4 VALUES< LLD 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column Indicate no nonrountlne measurements Number of Nonroutine Reported Measurements See Note 3 ..., -CTI ::c: I .......

I ....,) .i::. I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -4 Bl-214 K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD) See Note 1 1.00E-01 4.00E-01 4.00E-02 5.00E-01 3.00E-02 Indicator Locations Mean (F) Range See Note 2 1.83E-01 (1 I 2) 1.83E-01 -1.83E-01 1.26E+01 (2 / 2) 1.14E+01 -1.38E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN COMMERCIAL FISH pCi/g = 0.037 Bq/g (ORY WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 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 1.83E-01 (1 / 2) 1.83E-01 -1.83E-01 1.26E+01 (2 / 2) 1.14E+01 -1.38E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD Control Locations Mean (F) Range See Note 2 1.87E-01 (2 / 2) 1.45E-01 -2.30E-01 1.19E+01 (2 / 2) 1.18E+01 -1.20E+01 2 VALUES < LLD 2 VALUES< LLD 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 I " VI I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Total Number of Analysis Performed GAMMA SCAN (GELi) -4 81-214 CS-137 K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD) See Note 1 1.00E-01 3.00E-02 4.00E-01 4.00E-02 5.00E-01 3.00E-02 Indicator Locations Mean (F) Range See Note 2 1.95E-01 (1 / 2) 1.95E-01 -1.95E-01 2VALUES*<

LLD 1.31 E+01 (2 / 2) 1.25E+01 -1.38E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN GAME FISH pCi/g = 0.037 Bq/g (DRY WEIGHn Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 WHEELER RES 1.95E-01 (1/2) TRM 275-349 1.95E-01 -1.95E-01 WHEELER RES 2 VALUES < LLD TRM 275-349 WHEELER RES 1.31E+01 (2 / 2) TRM 275-349 1.25E+01 -1.38E+01 WHEELER RES 2 VALUES < LLD TRM 275-349 WHEELER RES 2 VALUES < LLD TRM 275-349 WHEELER RES 2 VALUES< LLD TRM 275-349 Control Locations Mean (F) Range See Note 2 2.70E-01 (1/2) 2.70E-01 -2.70E-01 2 VALUES < LLD *b 1.23E+01 (2 / 2) 1.19E+01 -1.28E+01 2 VALUES< LLD 2 VALUES< LLD 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 -Cl> :I: I °'

I -...J °' I Name of Facility:

BROWNS FERRY NUCLEAR PLANT Location of Facility:

LIMESTONE, ALABAMA Type and Lower limit Total Number of Detection of Analysis (LLD) Perfonned See Note 1 GAMMA SCAN (GELi) -6 AC-228 2.50E-01 BE-7 2.50E-01 81-212 4.50E-01 Bl-214 1.50E-01 CS-137 3.00E-02 K-40 7.50E-01 PB-212 1.00E-01 PB-214 1.50E-01 RA-226 1.50E-01 TL-208 6.00E-02 Indicator Locations Mean (F) Range See Note 2 4.92E-01 (2 / 4) 3.73E-01 -6.11E-01 4 VALUES < LLD 6.95E-01 (1/4) 6. 95E-01 -6.95E-01 3.47E-01 (4/4) 1.67E-01 -6.40E-01 4 VALUES < LLD 8.61E-01 (1/4) 8.61 E-01 -8.61 E-01 3.07E-01 (4 / 4) 1.27E-01 -5.81E-01 3.73E-01 (4/4) 1. 70E-01 -7.11 E-01 3.47E-01 (4 / 4) 1.67E-01 -6.40E-01 1.66E-01 (2 / 4) 1.23E-01 -2.0SE-01 Tennessee Valley Authority RADIOACTIVllY IN SHORELINE SEDIMENT pCi/g ::: 0.037 Bq/g (DRY WEIGHT) Docket Number: 50-259,260,296 Reporting Period: 2015 Location with Highest Annual Mean Mean (F) Location Description with Range Distance and Direction See Note 2 JOE WHEELER ST PARK 4.92E-01 (2/ 2) TRM279.5 3. 73E-01 -6.11 E-01 JOE WHEELER ST PARK 2 VALUES< LLD TRM 279.5 JOE WHEELER ST PARK 6.95E-01 (1/2) TRM279.5 6.95E-01 -6.95E-01 JOE WHEELER ST PARK 5.08E-01 (2/ 2) TRM279.5 3.76E-01 -6.40E-01 JOE WHEELER ST PARK 2 VALUES < LLD TRM279.5 JOE WHEELER ST PARK 8.61E-01 (1/2) TRM 279.5 8.61E-01 -8.61E-01 JOE WHEELER ST PARK 4.83E-01 (2 / 2) TRM279.5 3.85E-01 -5.81E-01 JOE WHEELER ST PARK 5.58E-01 (2/ 2) TRM 279.5 4.05E-01 -7.11E-01 JOE WHEELER ST PARK 5.08E-01 (2 / 2) TRM279.5 3. 76E-01 -6.40E-01 JOE WHEELER ST PARK 1.66E-01 (2 / 2) TRM 279.5 1.23E-01 -2.0SE-01 Control Locations Mean (F) Range See Note 2 5.20E-01 (2 / 2) 4.41E-01 -6.00E-01 2 VALUES< LLD 5.63E-01 (2 / 2) 4.73E-01 -6.52E-01 5.05E-01 (2 / 2) 4.32E-01 -5.79E-01 3.78E-02 (1 / 2) 3.78E-02 -3.78E-02 4.08E+OO (2 I 2) 3.18E+OO -4.98E+OO 5.26E-01 (2 / 2) 4.36E-01 -6.17E-01 5.25E-01 (2 / 2) 4.83E-01 -5.67E-01 5.05E-01 (2 / 2) 4.32E-01 -5. 79E-01 1.70E-01 (2 / 2) 1.42E-01 -1.98E-01 Notes: 1. Nominal Lower Level of Detection (LLD) as described In Table E -1 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F). 3. Blanks In this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 ...., -('11 ::I: I ...... -...J 25 20 .... m :J 0 "E15 lU "O c: .!!! CJ) -0::10 E 5 1975 1980 Figure H-1 Direct Radiation Direct Radiation Levels Browns Ferry Nuclear Plant Four Quarter Moving Average lnlight Dosimeter Deployment January, 2007 1985 1990 1995 2000 2005 2010 Calendar Year _....,...

On-Site -o-Off-Site 2015 2020 Dosimeters are processed quarterly.

This chart shows trends in the average measurement for all dosimeters grouped as "on-site" or "off-site".

The data from preoperational phase and construction phases of TV A nuclear power plant sites, prior to 1980, show the same trend of "on-site" measurements higher than "off-site" measurements that is observed in current data indicating that the slightly higher "on-site" direct radiation levels are not related to plant operations.

.., E -0 c. i::' *;;: tJ c( Figure H-2 Radioactivity in Air Filters Annual Average Gross Beta Activity in Air Filters -BFN 0.25 0.2 0 0.1 5 0.10 0.05 0.00 Initial Plant Operation in August , 1 973 Pr eope ratio na l Average 1965 1 97 0 1975 1980 1 985 1990 1 995 2000 2005 20 1 0 2015 2020 Calendar Year -+-Ind i cato r -e-Cont r ol As can b e seen in the trend plot of gross beta activity , th e gross b eta l eve l s in a ir part i culates ha ve r e m a in ed r e l a ti ve ly constan t with t h e exception of years when th e beta act i vity was e l evate d due to fa ll out from nuclear weapons testing. The data a l so shows that th e r e is no difference in th e l eve l s for sa mplin g conducted at t h e indic ator stat i o n s as compared to the control stat ion s. -7 8 -

3 E. Cl -u c. 0 1965 Figure H-3 Cs-1 37 in So il Annual Average Cs-137 Activity in Soil -BFN In i tia l P lan t Operation in August , 1973 Preope rat i ona l Average 1970 1975 1 980 1985 1990 1995 2000 2005 20 10 Ca le ndar Year ---+---I nd i cator -o-Co n t rol 2015 2020 Cesium-13 7 was produced by pa s t nuclear weapons testing and is pre s ent in almost every environmental sample exposed to the atmosphere.

The "control" and "indicator" l ocat ion s h a ve generally trended downward with year-t o-year variation, s in ce the end of atmospheric nuclear weapons testing in 1980.

..J -u c. *;; .. u < 6 4 2 Figure H-4 Gross Beta Activity in Surface Water Annual Average Gross Beta Activity in Surface Water -BFN Initial Plant Operation in I August, 1973 Note: No gross beta measurements were made in 1978 Preoperational Average 0 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year --.-Ind i cator (Downstream) -e-Contro l (Upst r eam) 2015 2020 A s shown in the graph , the gross beta activity in samples from the downstream indicator locations has been essentially the same as the activity in samples from the upstream control locations.

The average gross beta activity in these samples has been trending down since the early 1980's.

...J 4 -C3 c. 2 Initial Plant Operation in August, 1973 Figure H-5 Gross Beta Activity in Drinking Water Annual Average Gross Beta Activity in Drinking Water -BFN 0 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 2020 Calendar Year -+-Indicator (Downstream) -e-Con trol (Upst ream) The average gross beta activity in drinking water samples from the upstream control locations has typically been slightly higher than activity level measured in samples from the downstream indicator locations. The annual average gross beta activity has been relatively constant since the start of plant operations in 1980 and is slightly lower than preoperational levels.

0.5 0.4 Cl -u c. 0.1 Figure H-6 Radioactivity in Fish Annual Average Cs-137 Activity in Fish Flesh Game Fish -BFN Initial Plant Operation in August, 1973 Preoperational Average 0.0 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 2020 Calendar Year I -+-I n dicator -e-Co n trol I The concentrations of Cs-13 7 found in fish are consistent with level s present in the Tennessee River due to past atmospheric nuclear weapons te sting. As s hown in the gra ph , the level s of Cs-13 7 have been decreasing consistent with the overall level s of Cs-13 7 in the environment.