ML18039A761

Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998.

ML18039A761
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Site:	Browns Ferry
Issue date:	12/31/1998
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Annual Radiological Environmental Operating Report Browns Ferry Nuclear Plant 1998 0

9'705040208 990427 PDR ADOCK 05000259 R PDR

ANNUALRADIOLOGICALENVIRONMENTALOPERATING REPORT BROWNS FERRY NUCLEAR PLANT 1998 TENNESSEE VALLEYAUTHORITY ENVIRONMENTALRADIOLOGICALMONITORINGAND INSTRUMENTATION

TABLE OF CONTENTS Table of Contents List of Tables lv List of Figures Executive Summary.

Introduction .. 2 Naturally Occurring and Background Radioactivity. 2 Electric Power Production.. 4 Site/Plant Description.

Radiological Environmental Monitoring Program....

t Direct Radiation Monitoring. 10 Measurement Techniques. 10 Results 11 Atmospheric Monitoring. 14 Sample Collection and Analysis 14 Results 15 Terrestrial Monitoring. 17 Sample Collection and Analysis . 17 Results 18 Liquid Pathway Monitoring.. 20 Sample Collection and Analysis.. 20 Results 22 Assessment and Evaluation. 25 Results 26 Conclusions 27 References 28

Appendix A Radiological Environmental Monitoring Program and Sampling Locations........... ~ ~ 34 Appendix B 1998 Program Modifications.... 45 C Program Deviations. 48 'ppendix Appendix D Analytical Procedures.. 51 Appendix E Nominal Lower Limits of Detection (LLD). 54 Appendix F Quality Assurance/Quality Control Program. 60 Appendix G Land Use Survey... 66 Appendix H Data Tables and Figures. 72

0 LIST OF TABLES Table 1 Comparison of Program Lower Limits of Detection with Regulatory Limits for Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas and Reporting Levels........... 29 Table 2 Results Rom the Intercomparison of Environmental Dosimeters 30 Table 3 Maximum Dose Due to Radioactive Effluent Releases......................... 31

LIST OF FIGURES Figure I Tennessee Valley Region. 32 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atmosphere and Lake. 33

EXECUTIVE

SUMMARY

This report describes the radiological environmental monitoring program conducted by TVA in the vicinity of the Browns Ferry Nuclear Plant (BFN) in 1998. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken &om stations in the general area of th' plant and &om areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Monitoring includes the sampling of air, water, milk, foods, vegetation, soil, fish, sediment, and the measurement of direct radiation levels. Results &om stations near the plant are compared with concentrations &om control stations and with preoperational measurements to determine potential impacts of plant operations.

The vast majority of the exposures'calculated from environmental samples were contributed by naturally occurring radioactive materials or from materials commonly found in the environment as a result of atmospheric nuclear weapons fallout.

Small amounts of Co-60, Cs-134, Cs-137, and Sr-90 were measured in a small number of samples collected during 1998. The level of activity measured in these samples would result in no measurable increase over background in the dose to the general public.

INTRODUCTION This report describes and summarizes results of radioactivity measurements made in the vicinity of BFN and laboratory analyses of samples collected in the area. The measurements are made to comply with the requirements of 10 CFR 50, Appendix A, Criterion 64 and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C and to determine potential effects on public heath 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.

In addition, estimates of the maximum potential doses to the surrounding population are made

&om radioactivity measured both in plant effluents and in environmental samples. The data presented in this report include results Rom 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.

Naturall Occurrin and Back ound Radioactivit Most materials in our world today contain trace amounts of naturally occurring radioactivity.

Approximately 0.01 percent of all potassium is radioactive potassium-40. Potassium-40 (K-40),

with a half-life of 1.3 billion years, is one of the major types of radioactive materials found naturally in our environment. An individual weighing 150 pounds contains about 140 grams of potassium (Reference 1). This is equivalent to approximately 100,000 pCi of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body. Naturally occurring radioactive materials have always been in our environment. Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-212, 214, lead (Pb)-

212,214, thallium (Tl)-208, actinium (Ac)-228, uranium (U)-238, 235, thorium (Th)-234, radium (Ra)-226, radon (Rn)-222, carbon (C)-14, and hydrogen (H)-3 (generally called tritium). These naturally occurring radioactive materials are in the soil, our food, our drinking water, and our bodies. 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. We are all exposed to this natural radiation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.

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 EQUIVALENTESTIMATES Source Millirem/Year Per Person Natural background dose equivalent Cosmic 27 Cosmogenic 1 Terrestrial 28 t

In the body 39 Radon-222 200 Total 295 Release of radioactive material in natural gas, mining, ore processing, etc.

Medical (effective dose equivalent) 53 Nuclear weapons fallout less than 1 Nuclear energy 0.28 Consumer products 0.03 Total 355 (approximately)

As can be seen from the table, the natural background radiation dose equivalent to the U.S.

population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background cosmic and 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. However, nuclear plants include many complex systems to control the nuclear fission process and to safeguard against the possibility of reactor malfunction, which could lead to the release of radioactive materials. 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 outlying areas around the plant. In this way, not only is the release of radioactive materials from the plant tightly controlled, but measurements are made in surrounding areas to verify that the population is not being exposed to significant levels of radiation or radioactive materials.

The BFN ODCM, which is required by the plant Technical Specifications, prescribes limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of these effluents. The dose to a member of the general public from radioactive materials released to unrestricted areas, as given in NRC guidelines and in the ODCM, is limited as follows:

Li uid Effluents Total body <3 mrem/year Any organ <10 mrem/year

Gaseous Effluents Noble gases:

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

Any organ <15 mrem/year The Environmental Protection Agency (EPA) limits for the total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are as follows:

Total body <25 mrem/year Thyroid <75 mrem/year Any other organ <25 mrem/year Appendix B to 10 CFR 20 presents the regulatory limits for the annual average concentrations of radioactive materials released in gaseous and liquid effluents at the boundary of the unrestricted area. Table 1 of this report compares the nominal lower limits of detection for the BFN monitoring program with the regulatory limits for maximum annual average effluent concentrations released to unrestricted areas and levels requiring special reports to the NRC. The data presented in this report indicate compliance with the regulations.

SITE/PLANT DESCRIPTION Browns Ferry Nuclear Plant (BFN) is located on the north shore of Wheeler Reservoir at Tennessee River Mile 294 in Limestone County in north Alabama (Figure 1). Wheeler Reservoir averages 1 to 1-1/2 miles in width in the vicinity of the plant. The site, containing approximately 840 acres, is approximately 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama. The dominant character of land use is small, scattered villages and homes in an agricultural area. A number of relatively large farming operations occupy much of the land on the north side of the river immediately surrounding the plant. The principal crop grown in the area is cotton. Only two dairy farms are located within a 10-mile radius of the plant.

Approximately 2500 people live within a 5-mile radius of the plant. The town of Athens has a population of about 17,000, while approximately 49,000 people live in the city of Decatur. The largest city in the area with approximately 160,000 people is Huntsville, Alabama, located about 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 &om the site.

The Tennessee River is also a popular sport fishing area.

BFN consists of three boiling water reactors. Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974. Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors. Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in March 1977.

t Allthree units were out of service from March 1991 and Unit 3 restarted on November 1985 to May 1991.

19, 1995.

Unit 2 was restarted May 24, Unit 1 remains in a non operating status.

RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within the reactor itself or one of the other plant systems. Plant effluent monitors are designed to detect the small amounts released to the environment. Environmental monitoring is a final verification that the systems are performing as planned. The monitoring program is designed to check the pathways between the plant and the people in the immediate vicinity and to most efficiently monitor these pathways. Sample types are chosen so that the potential for detection of radioactivity in the environment willbe maximized. The radiological environmental monitoring program is outlined in Appendix A.

There are two primary pathways by which radioactivity can move through the environment to humans: air and water (see Figure 2). The air pathway can be separated into two components:

the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types of samples collected in this program are designed to monitor these pathways.

A number of factors were considered in determining the locations for collecting environmental samples. The locations for the atmospheric monitoring stations were determined Rom 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 Modifications made to the program in 1998 are described in Appendix B and exceptions to the sampling and analysis schedule are presented in Appendix C.

To determine the amount of radioactivity in the environment prior to the operation of BFN, a preoperational radiological environmental monitoring program was initiated in 1968 and operated until the plant began operation in 1973. Measurements of the same types of radioactive materials that are measured currently were assessed during the preoperational phase to establish normal background levels for various radionuclides in the environment.

The preoperational monitoring program is a very important part of the overall program. During the 1950s, 60s, and 70s, atmospheric nuclear weapons testing released radioactive material to the environment causing fluctuations in background radiation levels. This radioactive material is the same type as that produced in the BFN reactors. Preoperational knowledge of pre-existing t radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of whether surrounding population.

The determination the operation of impact during the of BFN is impacting the environment and thus the operating phase also considers the presence of control stations that have been established in the monitoring program. Results of environmental samples taken at control stations (far &om the plant) are compared with those Rom indicator stations (near the plant) to establish the extent of BFN influence.

All samples are analyzed by the Radioanalytical Laboratory of TVA's Environmental Radiological Monitoring and Instrumentation group located at the Western Area Radiological Laboratory (WARL) in Muscle Shoals, Alabama. All analyses are conducted in accordance with written and approved procedures and are based on accepted methods. A summary of the analysis techniques and methodology is presented in Appendix D. Data tables summarizing the sample analysis results are presented in Appendix H.

The radiation detection devices and analysis methods used to determine the radionuclide content of samples collected in the environment are very sensitive to small amounts of radioactivity. The sensitivity of the measurement process is defined in terms of the lower limit of detection (LLD).

A description of the nominal LLDs for the Radioanalytical Laboratory is presented in Appendix The Radioanalytical Laboratory employs 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 equipment checks to ensure that the radiation detection instruments are working properly and the analysis of quality control samples which are included alongside routine environmental samples. The laboratory participated in the EPA Interlaboratory Comparison Program for 1998. In addition, samples split with the EPA National Air'and Radiation Environmental Laboratory and the State of Alabama provide an independent verification of the overall performance of the laboratory. A complete description of the quality control program is presented in Appendix F.

0 DIRECT RADIATIONMONITORING Direct radiation levels are measured at a number of stations around the plant site. These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout

&om atmospheric nuclear weapons tests conducted in the past, and radioactivity that may be present as a result of plant operations. Because of the relative large variations in background radiation as compared to the small levels from the plant, contributions from the plant may be difficultto distinguish.

Radiation levels measured in the area around the BFN site in 1998 were consistent with levels

&om previous years and with levels measured at other locations in the region.

Measurement Techni ues Direct radiation measurements are made with thermoluminescent dosimeters (TLDs). When certain materials are exposed to ionizing radiation, many of the electrons which become displaced are trapped in the crystalline structure of the material. They remain trapped for long periods of time as long as the material is not heated. When heated (thermo-), the electrons are released, producing a pulse of light (-luminescence). The intensity of the light pulse is proportional to the amount of radiation to which the material was exposed. Materials which display these characteristics are used in the manufacture of TLDs.

From 1968 through 1989, TVA used a Victoreen dosimeter consisting of a manganese activated calcium fluoride (Ca,F:Mn) TLD material encased in a glass bulb. In 1989, TVAbegan the process of changing &om the Victoreen dosimeter to the Panasonic,Model UD-814 dosimeter, and completely changed to the Panasonic dosimeter in 1990. This dosimeter contains four elements consisting of one lithium borate and three calcium sulfate phosphors. The calcium sulfate phosphors are shielded by approximately 1000 mg/cm'lastic and lead to compensate for the over-response of the detector to low energy radiation.

The TLDs are placed approximately 1 meter above the ground, with two or more TLDs at each monitoring location. Monitoring locations for TLDs are located in each of the sixteen compass sectors surrounding the site. One monitoring point is located in each sector near the site boundary and a second monitoring point is located at a distance of approximately five miles in each sector. Nine additional locations are distributed through the sectors out to a distance of approximately 32 miles. The TLDs are exchanged every 3 months and the accumulated exposure on the detectors is read with a Panasonic Model UD-710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system.

Since the calcium sulfate phosphor is much more sensitive than the lithium borate, the measured exposure is taken as the median of the results obtained Rom the calcium sulfate phosphors in all detectors from the monitoring location. The values are corrected for gamma response, system variations, and transit exposure, with individual gamma response calibrations for each element.

t The system meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 for environmental applications of TLDs.

Since 1974, TVAhas participated in the intercomparisons of environmental dosimeters conducted by the U.S. Department of Energy and other interested parties. The results, shown in Table 2, demonstrate that direct radiation levels determined by TVA are generally within ten percent of the calculated or known values.

Results All results are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />). The monitoring locations are grouped according to the distance from the plant. The first group consists of all locations within 1 mile of the plant. The second group lies between 1 and 2 miles, the third group between I

2 and 4 miles, the fourth between 4 and 6 miles, and the fiAh group is made up of all locations more than 6 miles from the plant. Past data have shown that the results from all monitoring points greater than 2 miles from the plant are essentially the same. Therefore, for

~ l purposes of this report, all locations 2 miles or less from the plant are identified as "onsite" stations and all others are considered "offsite." Prior to 1976, direct radiation measurements in the environment were made with dosimeters that were not as precise at lower exposures.

Consequently, the environmental radiation levels reported in the preoperational phase of the BFN monitoring program exceed current measurements of background radiation levels. For this reason, data collected prior to 1976 are not included in this report. For comparison purposes, direct radiation measurements made in the TVA Watts Bar Nuclear Plant (WBN) construction phase and preoperational radiological environmental monitoring program are referenced.

The quarterly gamma radiation levels determined from the TLDs deployed around BFN in 1998 are summarized in Table H-1. The results &om all measurements at individual locations are presented in Table H-2. The exposures are measured in milliroentgens. For purposes of this report, one milliroentgen (mR), one millirem (mrem), and one millirad are assumed to be numerically equivalent. The rounded average annual exposures are shown below.

Annual Average Direct Radiation Levels mR/Year BFN 1998 Onsite Stations 66 Offsite Stations 57 The data in Table H-l indicate that the average quarterly radiation levels at the BFN onsite locations are approximately 2.3 mR/quarter higher than levels at the offsite locations. This difference is consistent with levels measured for preoperation and construction phases of TVA nuclear plant sites where the average radiation levels on site were generally 2-6 mR/quarter higher than the levels offsite. The causes of these differences have not been isolated; however, it is postulated that the differences are probably attributable to combinations of influences such as natural variations in environmental radiation levels, earth-moving activities onsite, and the mass f

o concrete employed in the construction of the plant. Other undetermined influences may also play a part. These conclusions are supported by the fact that similar differences between onsite and offsite locations were measured in the vicinity of the WBN site during the construction and preoperational phase.

Figure H-l compares plots of the environmental gamma radiation levels from the onsite or site boundary locations with those from the offsite locations over the period from 1976 through 1998.

Figure H-2 depicts the environmental gamma radiation levels measured during the construction and preoperational phase of the WBN site. Note that the data follow a similar pattern to the BFN data and that, as discussed above, the levels reported at onsite locations are higher than the levels at offsite stations.

Allresults reported in 1998 are consistent with direct radiation levels identified at locations 1

which are not influenced by the operation of BFN. There is no indication that BFN activities increased the background direct radiation levels normally observed in the areas surrounding the plant.

ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as local, perimeter, and remote. In the current program, five local air monitoring stations are located on or adjacent to the plant site in the general direction of greatest wind frequency. Three of these stations (LM-1, LM-2, and LM-3) are located on the plant side of the Tennessee River and two stations (LM-6 and LM-7) are located immediately across the river from the plant site. One additional station (station LM-4) is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational 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.

l 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. There is no indication of an increase in atmospheric radioactivity as of BFN.

Sam le Collection and Anal sis a result Airparticulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch glass fiber filter. The sampling system consists of a pump, a magnehelic gauge for measuring the drop in pressure across the system, and a dry gas meter. This allows an accurate determination of the volume of air passing through the filter. The sampling system is housed in a metal building. The filter is contained in a sampling head mounted on the outside of the monitor building. The filter is replaced weekly. Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 weeks, composites of the filters from each location are analyzed by gamma spectroscopy.

4 Gaseous radioiodine is collected using a commercially available cartridge containing TEDA-impregnated charcoal. This system is designed to collect iodine in both the elemental form and as organic compounds. The cartridge is located in the same sampling head as the air particulate filter and is downstream of the particulate filter. The cartridge is changed at the same time as the particulate filter and samples the same volume of air. Each cartridge is analyzed for I-131 by gamma spectroscopy analysis.

Rainwater is sampled by use of a collection tray attached to the monitor building. The collection tray is protected &om debris by a screen cover. As water drains from the tray, it is collected in one of two 5-gallon jugs inside the monitor building. A 1-gallon sample is removed &om the container every 4 weeks. Any excess water is discarded. Rainwater samples are held to be analyzed only ifthe air particulate samples indicate the presence of elevated activity levels or if fallout is expected. For example, rainwater samples were analyzed during the period of fallout following the accident at Chernobyl in 1986. No rainwater samples from the vicinity of BFN were analyzed in 1998.

Results The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 1998 was consistent with levels reported in previous years. The average level at indicator stations was 0.021 pCi/m'hile the average at control stations was also 0.021 pCi/m'.

The annual averages of the gross beta activity in air particulate filters at these stations for the years 1968-1998 are presented in Figure H-3. Increased levels due to fallout &om 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 &om monitoring programs conducted by TVA at other nuclear power plant sites during construction and preoperational stages.

Only naturally occurring radionuclides radioactive materials were identified by the monthly gamma spectral analysis of the air particulate samples. No fission or activation products were found at levels greater than the LLDs. As shown in Table H-4, iodine-131 was not detected in any of the charcoal cartridge samples collected in 1998.

TERRESTRIAL MONITORING Terrestrial monitoring is accomplished by collecting samples of environmental media that may transport radioactive material &om the atmosphere to humans. For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass where dairy cattle are grazing. When the cow ingests the radioactive material, some of it may be transferred to the milk and consumed by humans who drink the milk.

Therefore, samples of milk, vegetation, 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-13.

A land use survey is conducted annually to locate milk producing animals and gardens within a 5-mile radius of the plant. Only one dairy farm is located in this area. One additional dairy farm t has been identified within 7 miles of the plant. These two dairies are considered indicator stations and routinely provide milk samples. No other milk-producing animals have been identified within 5 miles Appendix G.

Sam le Collection and Anal sis of the plant. The results of the 1998 land use survey are presented in Milksamples are collected every 2 weeks &om two dairies identified as indicator locations and

&om at least one of two control farms. These samples are placed on ice for transport to the radioanalytical laboratory. A specific analysis for I-131 and a gamma spectral analysis are performed on each sample and Sr-89,90 analysis is performed every 4 weeks.

Samples of vegetation are collected every 4 weeks for I-131 analysis. The vegetation samples are collected from one farm which previously produced milk and from one control dairy farm.

The samples are collected by cutting or breaking enough vegetation to provide between 100 and 200 grams of sample. Care is taken not to include any soil with the vegetation. The sample is placed in a container with 1650 ml of 0.5 N NaOH for transport back to the laboratory. A second sample of between 750 and 1000 grams is also collected from each location. After drying and grinding, this sample is analyzed by gamma spectroscopy.

Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cutter" or an auger type sampler. AAer drying and grinding, the sample is analyzed by gamma spectroscopy. When the gamma analysis is complete, the sample is ashed and analyzed for Sr-89,90.

Samples representative of food crops raised in the area near the plant are obtained from individual gardens, corner markets, or cooperatives. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. In 1998 samples of cabbage, corn, green beans, potatoes, and tomatoes were collected Rom local vegetable gardens. In addition, samples of apples were also obtained from the area. The edible portion of each sample is analyzed by Results The results from the analysis of milk samples are presented in Table H-S. No radioactivity which could be attributed to BFN was identified. All 1-131 results were less than the established nominal LLD of 0.4 pCi/liter. Strontium-90 was identified in two samples. The average Sr-90 concentration measured in the samples was approximately 2.02 pCi/liter. These levels are less than concentrations measured in samples collected prior to plant operation and are consistent with concentrations expected in milk as a result of fallout from atmospheric nuclear weapons tests (Reference 1). Figure H-4 displays the average Sr-90 concentrations measured in milk since 1968. The concentrations have steadily decreased as a result of the 28-year half-life of Sr-90 and the washout and transport of the element through the soil over the period.

The results for Strontium-89 analysis were less than the LLD of 3.5 pCi/liter. By far the predominant isotope reported in milk samples was the naturally occurring K-40. An average of approximately 1350 pCi/liter of K-40 was identified in all milk samples.

Similar results were found for vegetation samples as reported in Table H-6. AllI-131 values were less than nominal LLD. 'Gamma spectroscopy analysis identified only naturally occurring radionuclides. The largest concentrations identified were for the isotopes K-40 and Be-7.

The only fission or activation product identified in soil samples was Cs-137. The maximum concentration was approximately 0.8 pCi/g in a sample &om one of the control stations. This concentration is consistent with levels previously reported Rom fallout. All other radionuclides reported were naturally occurring isotopes. The results of the analysis of soil samples are reported in Table H-7. A plot of the annual average Cs-137 concentrations in soil is presented in t Figure H-5. Like the levels of Sr-90 in milk, concentrations of Cs-137 in soil are 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. As noted earlier, K-40 is one of the major radionuclides found naturally in the environment and is the predominant radioactive

.component in normal foods and human tissue. Analysis of these samples indicated no contribution from plant activities. The results are reported in Tables H-8 through H-13.

LI UID PATHWAYMONITORING Potential exposures from the liquid pathway can occur Rom drinking water, and ingestion of fish, and &om direct radiation exposure to radioactive materials deposited in the river sediment. The liquid pathway monitoring program conducted during 1998 included the collection of samples of surface (river/reservoir) water, groundwater, drinking water supplies, fish, Asiatic clams (not consumed by humans), bottom sediment, and shoreline sediment. Samples from the reservoir are

.collected both upstream and downstream &om the plant.

Results &om the analysis of aquatic samples are presented in Tables H-14 through H-20.

Radioactivity levels in water, fish, clams, and shoreline sediment were consistent with background and/or fallout produced levels previously reported. The presence of Co-60, Cs-134 and Cs-137 was identified in samples of bottom sediment.

Sam le Collection and Anal sis systems lrom one downstream station and one upstream station. A timer turns on the system at least once every two hours. The line is flushed and a sample collected into a collection container. A 1-gallon sample is removed &om the container every 4 weeks and the remaining water in the jug is discarded. The 4 week composite sample is analyzed by gamma spectroscopy and for gross beta activity. A quarterly composite sample is analyzed for tritium.

Samples are also collected by an automatic sampling system at the first downstream drinking water intake. These samples are collected in the same manner as the surface water samples. These monthly samples are analyzed by gamma spectroscopy and for gross beta activity. A quarterly composite is analyzed for tritium.

At other selected locations, grab samples are collected &om drinking water systems which use the Tennessee River as their source. These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity. A quarterly composite sample &om each station is analyzed for tritium. The sample collected at the first downstream public water supply is sampled by the automatic system directly from the river at the intake structure. Since the sample at this point is raw water, not water processed through the water treatment plant, the control sample should also be unprocessed water. Therefore, the upstream surface water sample is also considered as a control sample for drinking water. A program modification initiated in late 1997 and completed in January 1998 uses water sampled from the intake of the Decatur City Water Plant as the control location sample for surface and drinking water.

A groundwater well onsite is equipped with an automatic water sampler. Water is also collected

&om a private well in an area unaffected by BFN. Samples &om the wells are collected every 4 weeks and analyzed by gamma spectroscopy. A quarterly composite sample is analyzed for Samples of commercial and game fish species are collected semiannually from each of two reservoirs: the reservoir on which the plant is located (Wheeler Reservoir) and the upstream reservoir (Guntersville Reservoir). The samples are collected using a combination of netting techniques and electrofishing. To sample edible portions of the fish, the fish are filleted. After drying and grinding, the samples are analyzed by gamma spectroscopy.

During 1998 a program modification was implemented for sampling 'of sediment and clams. The sampling of bottom sediment was replaced by sampling of shoreline sediment during the second sampling period of the year and the sampling of clams was deleted after the Spring sampling period. The sampling of shoreline sediment &om areas of recreational use was evaluated as a better method of monitoring the potential exposure pathway to the public than the sampling of bottom sediment. The sampling of clams was deleted from the program since there is no human consumption of the Asiatic Clams &om the Tennessee River and no exposure pathway to man.

The samples of bottom sediment were collected from selected Tennessee River Mile (TRM) locations using a dredging apparatus or Scuba divers. The samples were dried and ground and analyzed by gamma spectroscopy. After this analysis was complete, the samples were ashed and analyzed for Sr-89,90.

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.

The samples of Asiatic clams were collected &om one location below the plant and one location t

above the plant. The clams were collected in the dredging or diving process with the sediment.

Enough clams were collected to produce approximately 50 grams of wet flesh. The flesh was separated from the shells, and the dried flesh samples were analyzed by gamma spectroscopy.

Results All radioactivity in surface water samples was below the detection limits except the gross beta activity and naturally occurring isotopes. These results are consistent with previously reported levels. A trend plot of the gross beta activity in surface water samples from 1968 through 1998 is presented in Figure H-6. A summary table of the results for this reporting period is shown in Table H-14.

For drinking water (public water), gross beta activity averaged 2.8 pCi/liter at the downstream stations and 2.7 pCi/liter at control stations. The results are shown in Table H-15 and a trend plot of the gross beta activity &om 1968 to the present is presented in Figure H-7.

e No fission or activation products were detected in groundwater samples. Only naturally occurring radon decay products (Pb-214 and Bi-214) were identified in these samples. Results from the analysis of groundwater samples are presented in Table H-16.

Cesium-137 was identified in samples of both game and commercial fish. The highest concentration of 0.12 pCi/g was measured in a game fish sample &om the indicator reservoir. A concentration of 0.05 pCi/g was measured in a sample fiom the control location sample. These concentrations are consistent with data from previous monitoring years. The only other isotopes found in fish were naturally occurring. Concentrations of K-40 ranged from 10.1 pCi/g to 16.9 pCi/g. The results are summarized in Tables H-17 and H-18. Plots of the annual average Cs-137 concentrations in fish are presented in Figures H-8 and H-9. Since the concentrations downstream are essentially equivalent to the upstream levels, the Cs-137 activity is most likely the results of fallout or other upstream effluents rather than activities at BFN.

Radionuclides of the types produced by nuclear power plant operations were identified in bottom sediment samples. The materials identified were Cs-137, Cs-134, and Co-60. The average levels of Cs-137 were 0.68 pCi/g in downstream samples and 0.34 pCi/g upstream. The Cs-137 concentrations at downstream stations have been historically higher than concentrations upstream. This relationship is graphically represented in Figure H-10 which presents a plot of the Cs-137 concentrations in sediment since 1968. The Co-60 concentrations in downstream samples averaged 0.09 pCi/g. Cobalt-60 was not identified in samples &om the upstream sampling point during 1998. Figure H-l 1 presents a graph of the Co-60 concentrations measured in sediment since 1968. Samples Rom the downstream sampling points contained Cs-134 at an average concentration of 0.05 pCi/g. There was not Cs-134 detected in the sample &om the upstream location. A realistic assessment of the impact to the general public from these radioisotopes produces a negligible dose equivalent. Results Rom the analysis of sediment samples are shown in Table H-19.

The data reported in Table H-19 for Sr-90 analyses indicates one result above the nominal LLD value of 0.4 pCi/g. The referenced result was below the actual LLD for the specific analysis and does not represent a positive identification of Sr-90 in the sample of bottom sediment. The analysis specific LLD was 0.57 pCi/g. The elevated LLD for this analysis was the result of a lower than normal chemical yield for the strontium analysis.

Only naturally occurring radionuclides were identified by the gamma spectral analyses of samples of shoreline sediment. The results &om the analysis of shoreline sediment are provided in Table H-20.

The gamma spectroscopy analyses of the samples of Asiatic clams collected during the Spring sampling period identified only the naturally occurring Bi-214 and Pb-214. The results from the analysis of clam samples are presented in Table H-21.

ASSESSMENT AND EVALUATION Potential doses to the public are estimated &om measured effluents using computer models.

These models were developed by TVA and are based on methodology provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living in the vicinity of a nuclear power plant. The doses calculated are a representation of the dose to a "maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates) are maximum expected values which willtend to overestimate the dose to this "hypothetical" person. In reality, the expected dose to actual individuals is significantly lower.

The area around the plant is analyzed to determine the pathways through which the public may receive an exposure. As indicated in Figure 2, the two major ways by which radioactivity is introduced into the environment are through liquid and gaseous effluents.

For liquid effluents, the public can be exposed to radiation from three sources: drinking water

&om the Tennessee river, eating fish caught in the Tennessee River, and direct exposure to radioactive material due to activities on the banks of the river (recreational activities). Data used to determine these doses are based on guidance given by the NRC for maximum ingestion rates, exposure times, and distribution of the material in the river. Whenever possible, data used in the dose calculation are based on specific conditions for the BFN area.

For gaseous effluents, the public can be exposed to radiation from several sources: direct radiation &om the radioactivity in the air, direct radiation &om radioactivity deposited on the ground, inhalation of radioactivity in the air, ingestion of vegetation which contains radioactivity deposited &om the atmosphere, and ingestion of milk &om animals which consumed vegetation containing deposited radioactivity. The concentrations of radioactivity in the air and the soil are estimated by computer models which use the actual meteorological conditions to determine the distribution of the effluents in the atmosphere. Again, as many of the parameters as possible are based on actual site specific data.

Results The estimated doses to the maximum exposed individual due to radioactivity released Rom BFN in 1998 are presented in Table 3. These estimates were made using the concentrations of the liquids and gases measured at the effluent monitoring points. Also shown are the ODCM limits for these doses and a comparison between the calculated dose and the corresponding limit. With the implementation of the process for zero liquid release during 1998, the maximum calculated dose equivalent &om measured liquid effluents as noted in Table 3 were insignificant. The maximum organ dose equivalent from gaseous effluents was 0.30 mrem/year which represents 2.0 percent of the NRC limit. A more complete description of the effluents released from BFN and the corresponding doses projected from these effluents can be found in the BFN Annual t Radioactive Effluent Release Reports.

As stated earlier in the report, the estimated increase in radiation dose equivalent to the general public resulting &om the operation of BFN is negligible when compared to the dose from natural background radiation. The results Rom 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, Co-60, Cs-134 and Cs-137 were identified in aquatic media. The distribution of Cs-137 in sediment and fish is consistent with fallout levels identified in samples both upstream and downstream from the plant during the preoperational phase of the monitoring program. Since there is no direct exposure pathway to humans, the Co-60 and Cs-134 identified in sediment samples would produce no measurable increase in the dose to the general public. No increases of radioactivity have been seen in water samples.

Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media evaluated include, but were not limited to, air, milk, food products, drinking water, fish, soil, and shoreline sediment. Inhalation, ingestion and direct doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control stations. More than 99 percent of those doses were contributed by the naturally occurring radionuclide K-40 and by Sr-90 and Cs-137, which are long-lived radioisotopes found in fallout &om nuclear weapons testing. Concentrations of Sr-90 and Cs-137 are consistent with levels measured in TVA's preoperational radiological environmental monitoring programs.

Conclusions It is concluded from the above analysis of the environmental sampling results and from the trend plots presented in Appendix H that the exposure to members of the general public which may have been attributable to BFN is negligible. The radioactivity reported herein is primarily the results of fallout or natural background radiation. Any activity which may be present as a result of plant operations does not represent a significant contribution to the exposure of Members of the Public.

REFERENCES

1. Merril Eisenbud, Environmental Radioactivit Academic Press, Inc., New York, NY, 1987.

2. National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing Radiation Exposure of the Population of the United States," September 1987.

3. United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instruction Concerning Risks &om Occupational Radiation Exposure," July 1981.

Table 1 COMPARISON OF PROGRAM LOWER LIMITS OF DETECTION WITH THE REGULATORY LIMITSFOR MAXIMUMANNUALAVERAGE EFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS AND REPORTING LEVELS Concentrations in Water Ci/Liter Concentrations in Air Ci/Cubic Meter Effluent Lower limit Lower limit Concentration'eporting LeveP of Detection'ffluent Concentration'eporting Level of Detection~

H-3 1,000,000 20,000 300 100,000 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 10 400 0.005 Sr-89 8,000 5 1,000 0.0011 Sr-90 500 2 6 0.0004 Nb-95 30,000 400 5 2,000 0.005 Zr-95 20,000 400 10 400 0.005 Ru-103 30,000 5 900 0.005 Ru-106 3,000 40 20 0.02 I-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 10 2,000 0.01 Note: 1 pCi ~ 3.7 x10'Bq.

Note: For those reporting levels that are blank, no value is given in the reference.

1 Source: Table 2 of Appendix B to 10 CFR 20.1001-20.2401 2 Source: BFN Offsite Dose Calculation Manual, Table 2.3-2 3 Source: Table E-1 of this report.

l 0 Intercomparison Table 2 Results from the of Environmental Dosimeters Calculated Average, all Exposure  % Difference % Difference TVA Results Respondents (See Note I) TVA: Respondents:

Year mrem mrem mrem Calculated Calculated Field Dosimeters 74 15.0 16.3 16.3 -8.0 0.0 77 30.4 31.5 34.9 -12.9 -9.7 79 13.8 16.0 14.1 -2.1 13.5 81 31.8 30.2 30.0 6.0 0.7 82 43.2 45.0 43.5 -0.7 3.4 84 73.0 75.1 75.8 -3.7 -0.9 86a 33.2 28.9 29.7 11.8 -2.7 86b 9.4 10.1 10.4 -9.6 -2.9 93a 24.4 26.4 27.0 -9.6 -2.2 93b 27.6 26.4 27.0 2.2 -2.2 96a 16.9 18.9 19.0 -11.1 -0.5 96b 17.6 18.9 19.0 -7.4 -0.5 Low Irradiated Dosimeters 74 27.9 28.5 30.0 -7.0 -5.0 79 12.1 12.1 12.2 -0.8 -0.8 86 18.2 16.2 17.2 5.8 -5.8 93a 24.9 25.0 25.9 -3.9 -3.5 93b 27.8 25.0 25.9 '.3 -3.5 High Irradiated Dosimeters 77 99.4 86.2 91.7 8.4 -6.0 79 46.1 43.9 45.8 0.7 4.1 81a 84.1 75.8 75.2 11.8 0.8 81b 102.0 90.7 88.4 15.4 2.6 82a 179.0 191.0 202.0 -11.4 -5.4 82b 136.0 149.0 158.0 -13.9 -5.7 84a 85.6 77.9 79.9 7.1 -2.5 84b 76.8 73.0 75.0 2.4 -2.7 93a 67.8 69.8 72.7 -6.7 -4.0 93b 80.2 69.8 72.7 10.3 -4.0 96a 60.7 55.2 58.1 4.5 -5.0 96b 59.4 55.2 58.1 2.2 -5.0 Notes: 1. The calculated exposure is the "known" exposure determined by the testing agency.

Table 3 Maximum Dose Due to Radioactive Effluent Releases Browns Ferry Nuclear Plant 1998 mrem/year Dose From Liquid Effluents 1998 NRC Percent of T~e Dose Limit NRC Limit Total Body 9.5E-IO <0.01 Any Organ 6.6E-09 10 <0.01 Doses From Gaseous Effluents 1998 NRC Percent of

~Te Dose Limit NRC Limit Noble Gas 1.5E-3 10 0.02 (Gamma)

Noble Gas 2.1E-3 20 0.01 (Beta)

Any Organ 3.0E-1 15 2.0 Total Cumulative Dose 1998 EPA Percent of

~Te Dose Limit EPA Limit Total Body or Any Other Organ 7.4E-2 25 0.3 Tllyrold 3.0E-1 75 0.4 LOUISVLLE TENNESSEE VALLEY REGION (TVA NUCLEAR PLANT SITES) i VOWENSeaRO W VA.

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APPENDIX A RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM AND SAMPLING LOCATIONS Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAM>

Exposure Pathway Number of Samples and Sampling and Type and Frequency

~and/or Sam ie Locationsb Collection Fre uenc ~a/Anal sis

1. AIRBORNE

a. Particulates Six samples from locations (in Continuous sampler operation with Analyze for gross beta radioactivity different sectors) at or near the site sample collection as required by dust greater than or equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> boundary (LM-I,LM-2, LM-3, LMA, loading but at least once per 7 days. following filter change. Perform LM-6, and LM-7). gamma isotopic analysis on each sample when gross beta activity is Two samples from control locations greater than 10 times the average of greater than 10 miles from the plant control samples. Perform gamma (RM-1 and RM-6). isotopic analysis on composite (by location) sample at least once per 31 Three samples from locations in days.

communities approximately 10 miles from the plant (PM-1, PM-2, and PM-3).

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

charcoal canister collection at least once per 7 days.

c. Rainwater 'ame locations as air particulates. Composite sample at least once per 31 Analyzed for gamma nuclides only if days. radioactivity in other media indicates the presence of increased levels of fallout

Table A-1 BROWNS FERRY NUCLEAR PLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAM*

Exposure Pathway Number of Samples and Sampling and Type and Frequency

~antSor Sam le Locationsb Collection Fre uenc ~of Anal sls

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

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

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

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

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

Two or more dosimeters in at least 9 additional locations of special interest.

2. WATERBORNE

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

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

Table A-1 BROWNS FERRY NUCLEAR PLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAM'xposure Pathway Number of Samples and Sampling and Type and Frequency

~anti/or Sam le Locationsb Collection Fre uenc ~of Anal sis

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

31 days.

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

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

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

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

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

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

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

recreational area (TRM 305).

Table A-1 BROWNS FERRY NUCLEAR PLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAM'xposure Pathway Number of Samples and Sampling and Type and Frequency

~antf/or Sam le Locationsb Collection Fre uenc ~of Anal sls

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

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

4. INGESTION

a. Milk At least 2 samples from dairy farms in At least once per 15 days when Gamma scan and I-131 on each the immediate vicinity of the plant animals are on pasture; at least once sample. Sr-89 and Sr-90 at least (Farms B and Bn). per 31 days at other times. once per 31 days.

At least one sample from control location (Farm Be and/or R).

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

Guntersville Reservoir above the plant.

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

Table A-1 BROWNS FERRY NUCLEAR PLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAM*

Exposure Pathway Number of Samples and Sampling and Type and Frequency

~and/or Sam le Locationsb Collection Fre uenc ~of Anal ala

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

Vegetables corn, green beans, tomatoes, and harvest.

potatoes grown at private gardens and/or farms in the immediate vicinity of the plant.

One sample of each of the same foods grown at greater than 10 miles distance from the plant.

e. Vegetation Samples from farms producing milk Once per 31 days. I-131, gamma scan once per 31 days.

but not providing a milk sample (Farm T).

Control samples from one control dairy (Farm R).

a. The sampling program outlined in this table is that which was in effect at the end of 1998.

b. Sample locations, sector and distance from plant, are described in Table A-2 and A-3 and shown in Figures A-l, A-2, and A-3.

c. Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

d. The sample location at the Decatur City Water Plant serves as a control sample for both surface water and drinking water.

e Table A-2 BROWNS FERRY NUCLEAR PLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicator (I)

Location Distance or Samples Numbera Station Sector ~iles Control C Collectedb I PM-I NW 13.8 I AP,CF,R,S 2 PM-2 NE 10.9 I AP,CF,R,S 3 PM-3 SSE 7.5 I AP,CF,R,S 4 LM-7 W 2.1 I AP,CF,R,S 5 RM-I W 31.3 C AP,CF,R,S 6 ~ RM-6 E 24.2 C AP,CF,R,S 7 LM-1 N 1.0 I AP,CF,R,S 8 LM-2 NNE 0.9 I AP,CF,R,S 9 LM-3 ENE 0.9 I AP,CF,R,S 10 LM4 NNW 1.7 I AP,CF,R,S 11 LM-6 SSW 3.0 I AP,CF,R,S 12 Farm B NNW 6.8 I M 13 Farm Bn N 5.0 I M,W 19 Farm R SW 12.5 C M,V 22 Well No.6 NW 0.02 I W 23 TRMc 282.6 11.4d I PW 24 TRM 306.0 12.0d C PW, SW 25 TRM 259.6 34.4d I PW 26 TRM 274.9 19.1d I PW 28 TRM 293.5 05d I SW 34 Farm Bc NW 28.8 C M 36 Farm T WNW 3.2 I V 70 TRM 259.8 34.2d I PW 71 TRM 286.5 7.5d I PW 72 TRM305 11.0d C SS 73 TRM293 I.od I SS 74 TRM 279.5 14.5d I SS Wheeler Reservoir (TRM 275-349) I F Guntersville Reservoir (TRM 349424) C F

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

b. Sample codes:

AP ~ Airparticulate filter CF Charcoal filter (Iodine) PW ~ Public drinking water F ~ Fish M ~ Milk SS ~ Shoreline sediment R Rainwater S ~ Soil W ~ Well water SW = Surface Water V Vegetation

c. TRM ~ Tcnncssee River Mile.

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

Table A-3 BROWNS FERRY NUCLEAR PLANT THERMOLUMINESCENTDOSIMETER (TLD) LOCATIONS Map Approximate Onsite (On)b Location Distance or NumbeR Station Sector ~miles ~Offside 0 I NW-3 NW 13.8 Off 2 NE-3 NE 10.9 Off SSE-2 SSE 7.5 Off W-3 W 31.3 Off E-3 E 24.2 Off N-I N 1.0 On NNE-I NNE 0.9 On 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-I E 0.8 On 45 E-2 E 5.2 Off 46 ESE-I ESE 0.9 On 47 ESE-2 ESE 3.0 Off 48 SE-I SE 0.5 On 49 SE-2 SE 5.4 Off 50 SSE-I SSE 5.1 Off 51 S-l S 3.1 Off 52 S-2 S 4.8 Off 53 SSW-I SSW 3.0 Off 54 SSW-2 SSW 4.4 Off 55 SW-I SW 1.9 On 5G SW-2 SW 4.7 Off 57 SW-3 SW 6.0 Off 58 WSW-I WSW 2.7 Off 59 WSW-2 WSW 5.1 Off 60 WSW-3 WSW 10.5 Off 61 W-I W 1.9 On 62 W-2 W 4.7 Off G3 WA W 32.1 Off G4 WNW-I WNW 3.3 Off 65 WNW-2 WNW 4.4 Off 66 NW-I NW 2.2 Off 67 NW-2 NW 5.3 Off 68 NNW-I NNW 1.0 On 69 NNW-3 NNW 5.2 Off

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

b. TLDs designated "onsitc" are those located 2 miles or less from the plant.

TLDS designated "offsitc" arc those located morc than 2 miles from the plant.

4 Figure A-1 Radiological Environmental Monitoring Locations Within 1 mile of Plant 326.2 7 33.75

~ 8 NE 303.75 56.25 WNW 28m 41'9 ENE 281.26 78.76 44 258.75 l

~ ~

BROWNS FERRY 101.25 4g NucLEAR PLANT 46 6p 48 WSW 236.25 123.75 SW SE 213.75 146.25 SSW SSE 191.26 168.75 S Scale Mile

Figure A-2 Radiological Environmental Monitoring Locations lead Between 1 and 5 miles from the Plant N

$ $ 4.2$ I NNW 23

$ 2$ .2$

NW NE 42

$ $ .2$

WNW er

~ 8 85 ~ 10 2$ I.2 38, 84 BI

~ 82 4 SIIOWHS TE T NUCLEAII PLANT 0

2$ ST 9 47 66 ~

. I WSW ree re I 22.2$

61 66 SE 2 IS.T$ 14$ >$

SSW SCALE I ~ Idd ~ 0 0$ l 0.$ 2 IM.TS ISLES

Figure A-3 Radiological Environmental Monitoring Locations More than 5 miles from the Plant 34S 7d 11.2S 328.2d 33.75 AW EHCESDRO HW HE RIILASKI 303.7S TAV TTEVILLE 8.25 34 281.26 FLOREHC AT S L

~ 2 0 43 SCLE HOAL 46 TSVILL 57 3

258.76 18 DECA IHISS LLVILLE WS <<Wn ~ AL ARAB 328.2 123.76 HALEVVI LE SE 213.76 148.25 SCALE SSW MILES 181.2d s 188.76

APPENDIX B 1998 PROGRAM MODIFICATIONS

APPENDIX B Radiolo ical Environmental Monitorin Pro am Modifications Modifications were made in the sampling of sediment and invertebrates (Asiatic Clams) during 1998. A change in the BFN monitoring program implemented for the Fall sampling period eliminated the collection of clams and replaced the collection of bottom sediment with the collection of shoreline sediment. These modifications were made based on the guidance provided in NUREG-1302, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors." The change in sediment sampling was implemented to provide for the monitoring of the direct exposure pathway &om radionuclides that may be deposited in the sediment. Sampling of shoreline sediment &om recreational use areas willprovide a better assessment of this potential exposure pathway. Since there is no human consumption of the Asiatic Clams &om the Tennessee River, it was concluded that sampling of these clams for monitoring of the ingestion pathway was not necessary. Table B-1 provides a detail summary of the 1998 modifications.

Table B-I Radiolo ical Environmental Monitorin Pro ram Modifications Date Station Location Remarks 11/98 TRM 305 Decatur Riverwalk Added location for the collection of shoreline Marina sediment.

11/98 TRM 293 Mallard Creek Added location for the collection of shoreline Recreational area sediment.

11/98 TRM 279.5 Joe Wheeler State Added location for the collection of shoreline Park Day Use Area sediment.

12/98 TRM 293.7 0.3 miles Deleted station and collection of bottom sediment.

downstream 12/98 TRM 288.8 5.2 miles Deleted station and collection of bottom sediment.

downstream 12/98 TRM 297.0 3.0 miles upstream Deleted station and collection of bottom sediment.

12/98 Control Upstream Deleted the collection of clams.

12/98 Indicator Downstream Deleted the collection of clams.

Appendix C, Pro am Deviations During 1998, seven samples were not collected as scheduled due to equipment problems or sample unavailability. Details of the missed samples are provided below and in Table C-l.

A total of four air particulate filter and charcoal cartridge samples were not collected from sampling location LM-3 due to equipment problems. Samples were not available Rom this location on July 27, 1998 or August 3, 1998 due to problems with the sampling pump. Repairs were made to the sampling pump and the pump operated correctly for the next four weeks.

Additional problems with the sampling system resulted in missed samples again on September 8, 1998 and September 14, 1998. Repairs were made and the sampling system operated normally for the remainder of the year.

t The continuous surface water sample scheduled for collection on January 20, 1998 &om the control location at TRM 306 was not available due to the relocation of the sampling equipment from the TRM 305. This sample also serves as the control for public water sampling. Grab samples were taken weekly at the location during the relocation of the equipment. The analysis of these grab samples identified only the normal natural background levels.

The milk sample scheduled for collection from the Richardson Dairy farm on February 23, 1998 was not available. This location is one of two control locations for milk sampling. A sample was collected on February 23, 1998 &om the other dairy farm used as a control location.

The continuous well water sample scheduled for collection on December 21, 1998 &om Well /f6 was not collected due to problems with the sampling pump. The electrical power for the pump was not available.

Table C-1 Radiolo ical Environmental Monitorin Pro ram Deviations Date Station Location Remarks 01/20/98 TRM 306 12.0 miles Continuous surface water sample was not available. The sampling equipment was out of service due to upstream relocation of the sampling point from TRM 305. Relocation was completed and the samples were collected as scheduled for the remainder of the year.

02/23/98 Farm R 12.5 miles SW Milkwas not available at the farm. A sample was collected as scheduled from the other control location dairy farm.

I 07/27/98 LM-3 0.9 miles ENE Air particulate filter and charcoal cartridge samples not collected due to equipment problems. Repairs initiated.

08/03/98 LM-3 0.9 miles ENE Sampling equipment still out of service. Repairs were completed and samples collected as scheduled for the next sampling period.

09/08/98 LM-3 0.9 miles ENE Airparticulate filter and charcoal cartridge samples not collected due to equipment problems. Repairs initiated.

09/14/98 LM-3 0.9 miles ENE Sampling equipment still out of service. Repairs were completed and samples collected as scheduled for the next sampling period.

12/21/98 Well //6 On site The continuous well water sample was not collected due to sampling pump power supply problems.

Power was restored to the sampling system.

Appendix D Anal ical Procedures Analyses of environmental samples are performed by the radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals. All analysis procedures are based on accepted methods. A summary of the analysis techniques and methodology follows.

The gross beta measurements are made with an automatic low background counting system.

Normal counting times are 50 minutes. Water samples are prepared by evaporating 500 ml of samples to near dryness, transferring to a stainless steel planchet and completing the evaporation process. Airparticulate filters are counted directly in a shallow planchet.

The specific analysis of I-131 in milk, water, or vegetation samples is performed by first isolating and purifying the iodine by radiochemical separation and then counting the final precipitate on a beta-gamma coincidence counting system. The normal count time is 50 minutes.

With the beta-gamma coincidence counting system, background counts are virtually eliminated and extremely low levels of detection can be obtained.

After a radiochemical separation, samples analyzed for Sr-89,90 are counted on a low background beta counting system. The sample is counted a second time after a 7-day ingrowth period. Prom the two counts the Sr-89 and Sr-90 concentrations can be determined.

Water samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintillation. A commercially available scintillation cocktail is used.

0 Gamma analyses are performed in various counting geometries depending on the sample type and volume. All gamma counts are obtained with germanium type detectors interfaced with a computer based multichannel analyzer system. Spectral data reduction is performed by the computer program HYPERMET.

The charcoal cartridges used to sample gaseous radioiodine were analyzed by gamma spectroscopy using a high resolution spectroscopy system germanium detector.

All of the necessary efficiency values, weight-efficiency curves, and geometry tables are established and maintained on each detector and counting system. A series of daily and periodic quality control checks are performed to monitor counting instrumentation. System logbooks and control charts are used to document the results of the quality control checks.

Appendix E Nominal Lower Limits of Detection Sensitive radiation detection devices can produce a signal even when no radioactivity is present in a sample being analyzed. This signal may come 6'om trace amounts of radioactivity in the components of the device, &om cosmic rays, from naturally occurring radon gas, or from electronic noise. The signal registered when no activity is present in the sample is called the background.

The point at which the signal is determined to represent radioactivity in the sample is called the critical level. This point is based on statistical analysis of the background readings Rom any particular device. However, any sample measured over and over in the same device will give different readings, some higher than others. The sample should have a well-defined average reading, but any individual reading willvary &om that average. In order to determine the activity present in a sample that willproduce a reading above the critical level, additional statistical analysis of the background readings is required. The hypothetical activity calculated

&om this analysis is called the lower limit of detection (LLD). A listing of typical LLD values that a laboratory publishes is a guide to the sensitivity of the analytical measurements performed by the laboratory.

Every time an activity is calculated from a sample, the background must be subtracted from the sample signal. For the very low levels encountered in environmental monitoring, the sample signals are oAen very close to the background. The measuring equipment is being used at the limit of its capability. For a sample with no measurable activity, which oAen happens, about half the time its signal should fall below the average machine background and half the time it should be above the background. Ifa signal above the background is present, the calculated activity is

compared to the calculated LLD to determine ifthere is really activity present or ifthe number is and artifact of the way radioactivity is measured.

A number of factors influence the LLD, including sample size, count time, count efficiency, chemical processes, radioactive decay factors, and interfering isotopes encountered in the sample. The most likely values for these factors have been evaluated for the various analyses performed in the environmental monitoring program. The nominal LLDs'calculated from these values, in accordance with the methodology prescribed in the ODCM, are presented in Table E-l.

The maximum values for the lower limits of detection specified in the ODCM are shown in Table E-2.

The nominal LLDs are also presented in the data tables. For analyses for which nominal LLDs have not been established, and LLD of zero is assumed in determining ifa measured activity is 4

TABLE E-1 Nominal LLD Values A. Radiochemical Procedures Sediment Air Filters Water Milk Wet Vegetation and Soil

~Ci/L ~Ci/L ~C//K wet ~Ci/ ~~

~Ci/m'.002 Gross Beta 1.9 Tritium 300 iodine-131 0.4 0.4 6.0 Strontium-89 5.0 3.5 31.0 1.6 Strontium-90 2.0 2.0 12.0 0.4

Table E-1 Nominal LLD Values B. Gamma Analyses (GeLi)

Foods Air Charcoal Water Vegetation Wet Soil and Tomatoes Particulates Filter and Milk and Grain Vegetation Sediment Fish Clam Flesh Potatoes, etc.

~C//m3 ttCi/m3 pCi/L ~Ci/ dD/ kCCi/k wet p~Ci/ ~d ~Ci/ d~ ~Ci/ dry ~Cilk wet Ce-141 .005 .02 10 .07 35 .10 .Q7 .35 20 Ce-144 .01 .07 30 .15 115 .20 .15 .85 60 Cr-51 .02 0.15 45 .30 200 .35 .30 2.4 95 1-131 .005 0.03 10 .20 60 .25 .20 1.7 20 Ru-103 .005 0.02 5 .03 25 .03 .03 .25 25 Ru-106 .02 0.12 40 .15 190 .20 .15 1.25 90 Cs-134 .005 0.02 5 .03 30 .03 .03 .14 10 Cs-137 .005 0.02 5 .03 25 .03 .03 .15 10 Zr-95 .005 0.03 10 .05 45 .05 .05 .45 45 Nb-95 .005 0.02 5 .25 30 .04 .25 .25 10 Co-58 .005 0.02 5 .03 20 .03 .03 .25 10 Mn-54 .005 0.02 5 .03 20 .03 .Q3 .20 10 Zn-65 .005 0.03 10 .05 45 .05 .05 .40 45 Co-60 .OQ5 0.02 5 .03 20 .03 .03 .20 10 K-40 .04 0.30 100 .40 400 75 .40 3.50 250 Ba-140 .015 0.07 25 .30 130 .30 .30 2.4 50 La-140 .01 0.04 10 .20 50 .20 .20 1.4 25 Fe-59 .005 0.04 10 .08 40 .05 .08 .45 25 Be-7 .02 0.15 45 .25 200 .25 .25 1.9 90 Pb-212 .005 0.03 15 .04 40 .10 .04 .30 40 Pb-214 .005 0.07 20 .50 80 .15 .50 .10 8Q Bi-214 .005 0.05 20 .10 55 .15 .10 .50 40 Bi-212 .02 0.20 50 .25 250 .45 .25 2.0 130 Tl-208 .002 0.02 10 .03 30 .06 .03 .25 30 Ra-224 .75 Ra-226 .15 Ac-228 .01 0.07 20 .10 70 .25 .10 .75 50

Table E-2 Maximum Values for the Lower Limits of Detection (LLD)

Specified by the BFN Offsite Dose Calculation Manual Airborne Particulate Food Water or Gases Milk Products Sediment A~ssl sis pCi/L ~C//m' 10'ish ~Ci/k wet ~C//L p~Ci/k wet ~Ci/k, dry gross beta x N.A. N.A.

H-3 2000'.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. N.A.

Zn-65 30 N.A. 260 N.A.

Zr-95 30 N.A. N.A. N.A. N.A. N.A.

Nb-95 15 N.A. N.A. N.A. N.A.

I-131 lb 7x 10' N.A. 60 N.A.

Cs-134 15 x10'x10'.A. 130 15 60 150 Cs-137 18 150 18 80 180 Ba-140 60 N.A. 60 N.A. N.A.

s La-140 15 N.A. N.A. 15 N.A.

a. Ifno drinking water pathway exists, a value of 3000 pCi/liter may be used

b. LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/liter. Iflevels greater than 15 pCi/liter are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples willbe analyzed at an LLD of 1.0 pCi/lite'r for I-131.

Appendix F uali Assurance/ uali Control Pro am A thorough quality assurance program is employed by the laboratory to ensure that the environmental monitoring data are reliable. This program includes the use of written, approved procedures in performing the work, a complete training and retraining system, 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.

Radiation detection devices can be tested in a number of ways. There are two primary tests which are performed on all devices. In the first type, the device is operated without a sample on the detector to determine the background count rate. The background counts are usually low values and are due to machine noise, cosmic rays, or trace amounts of radioactivity in the materials used to construct the detector. Charts of background counts are kept and monitored to ensure that no unusually high or low values are encountered.

In the second test, the device is operated with a known amount of radioactivity present. The number of counts registered &om such a radioactive standard should be very reproducible. These reproducibility checks are also monitored to ensure that they are neither higher nor lower than expected. When counts Rom either test fall outside the expected range, the device is inspected for malfunction or contamination. It is not placed into ser vice until it is operating properly.

t 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 may be blanks, replicate samples, blind samples or cross-checks.

Blanks are samples which contain no measurable radioactivity or no activity of the type being measured. Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference Rom isotopes other than the one being measured.

Duplicate samples are generated at random by the same computer program which schedules the collection of the routine samples. For example, ifthe 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 the other routine samples. The duplicate samples provide information about the variability of radioactive content in the various sample media.

Ifenough sample is available for a particular analysis, the laboratory staff can split a sample into two portions. Such a sample can provide 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 by the quality control staff or by the person performing the analyses. The staff member performing the analyses 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, the lab staff has immediate knowledge of the quality of the measurement process. A portion of these samples are also blanks.

Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples. The person performing the analysis does not know that 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 to test the data review process. Ifan 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 review process. Blind spikes test this process. Furthermore, the activity can be put into such samples at the extreme limit of detection (near the LLD) to determine whether or not the laboratory can find any unusual radioactivity whatsoever.

At present, 5 percent of the laboratory workload is in the category of internal cross-checks.

These samples have a known amount of radioactivity added and are presented to the person t performing the analysis labeled as cross-check samples.

laboratory by determining samples provide information about the accuracy This means that the quality control staff knows the radioactive content or "right answer" but the lab staff does not. Such samples test the best performance of the ifthe lab can find the "right answer."

of the measurement information is available about the variability of the process process. Further ifmultiple analyses These 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.

A series of cross-checks is produced by the EPA in Las Vegas. These interlaboratory comparison samples or "EPA cross-checks" are considered to be the primary indicator of laboratory performance. They provide an independent check of the entire measurement process that cannot be easily provided by the laboratory itself. That is, unlike internal cross-checks, EPA cross-checks test the calibration of the laboratory detection devices since different radioactive

standards produced'by individuals outside TVA are used in the cross-checks. The results of the analysis of these samples are reported back to EPA which then issues a report of all the results of all participants. These reports indicate how well the laboratory is doing compared to others across the nation. Like internal cross-checks, the EPA cross-checks provide information to the laboratory about the precision and accuracy of the radioanalytical work it does.

The results of TVA's participation in the EPA Interlaboratory Comparison Program are presented in Table F-1. For 1998, all EPA cross-check sample concentrations measured by TVA's laboratory were within+ 3-sigma of the EPA reported values.

TVA splits certain environmental samples with laboratories operated by the States of Alabama and Tennessee and the EPA National Air and Radiation Environmental Laboratory in Montgomery, Alabama. When radioactivity has been present in the environment in measurable quantities, such as following atmospheric nuclear weapons testing, following the Chernobyl incident, or as naturally occurring radionuclides, the split samples have provided TVAwith yet another level of information about laboratory performance. These samples demonstrate performance on actual environmental sample matrices rather than on the constructed matrices used in cross-check programs.

All the quality control data are routinely collected, examined, and reported to laboratory supervisory personnel. The data are checked for trends, problem areas, or other indications that a portion of the analytical process needs correction or improvement. The end result is a measurement process that provides reliable and verifiable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans.

Table F-I RESULTS OBTAINED IN INTERLABORATORYCOMPARISON PROGRAM A. Radiochemical Analysis of Water (pCi/L)

Gross Beta Strontium-89 Strontium-90 Tritium Iodine-131 EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Date (+3 ~si ma A~v. (+3 ~si ma ~Av .

(+3~si ma ~Av . (+3~si ma A~v. (+3 ~si ma ~Av .

01/98 4+9 8 8+9 10 32+9 30 02/98 105+18 03/98 2155+602 2199 04/98 6+9 8 18+9 18 07/98 13+9 16 21+9 21 7+9 8 08/98 17996+3118 17900 09/98 6+3 10/98 19+9 19 8+9 11/98 4+9 B. Gamma-Spectral Analysis of Water (pCi/L)

Barium-133 Cobalt-60 Zinc-65 Cesium-134 Cesium-137 EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Date (+3~si ma ~Av . (+3~si ma ~Av . (+3~si ma ~Av . (+3~si ma ~Av . (+3~si ma ~Av .

04/98 50+9 51 22+9 21 10+9 10 06/98 40+9 41 12+9 13 104+17 104 31+9 30 35+9 35

. 10/98 21+9 22 6+9 7 50+9 51 11/98 56+10 55 38+9 41 131+23 132 105+9 94 111+10 108

Appendix G Land Use Surve A land use survey was conducted to identify the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of 5 miles from the plant. The land use survey also identified the location of all milk animals and gardens of greater than 500 square feet producing fresh leafy vegetables within a distance of 3 miles Gom the plant.

The land use survey was conducted between April 1 and October 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from l

local agricultural authorities or other reliable sources.

In order to identify the locations around BFN which have the greatest relative potential for impact by the plant, radiation doses were projected for individuals living near BFN. These projections used the data obtained in the survey and historical meteorological data. The calculations also assumed that releases were equivalent to the design basis source terms. The dose projections are relative in nature and do not reflect actual exposures to individuals living near BFN. Calculated doses to individuals based on measured effluents from the plant were well below applicable dose limits (see Assessment and Evaluation Section and Table 3).

Dose projections &om air submersion were calculated for the nearest resident in each sector and dose projections from drinking milk or eating foods produced near the plant were calculated for the areas with milk producing animals and gardens, respectively.

Air submersion doses were calculated for the nearest resident in each sector, the resulting values were similar to those calculated for 1997. Any changes &om the 1997 results were small and

were due to differences in the distance values used for the nearest resident. These differences occurred from either slight changes in the distance value entered for the location or an actual change in the location. Doses calculated for ingestion of home-grown foods changed in some sectors, reflecting shifts in the location of the nearest garden. The changes were small and did not significantly impact the doses calculated for 1998. Gardens were identified in two sectors in 1998 that did not contain a garden in 1997.

For milk ingestion, projected annual doses were calculated for the same two locations reported in 1997. These were the only two locations where milk producing animals were identified.

Samples are collected &om both of these farms. There were no changes in relative projected doses calculated for these two locations compared to the results &om 1997 survey.

Tables G-1, G-2, and G-3 show the comparative calculated doses for 1997 and 1998.

Table G-1 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within Five Miles of Plant mrem/year 1997 Surve 1998 Surve Approximate Approximate Distance Annual Distance Annual Sector Miles Dose Miles Dose N 1.24 0.45 1.24 0.45 NNE 1.61 0.14 1.61 0.14 NE 2.54 0.12 2.54 0.12 ENE 1.52 0.17 1.52 0.17 E 1.00 0.33 1.00 0.33 ESE 1.15 0.22 1.15 0.22 SE a a SSE a a S 2.78 0.15 2.78 0.15 SSW 2.59 0.18 2.59 0.18 SW 2.76 0.10 2.76 0.10 WSW 2.47 0.08 2.47 0.08 1.57 0.19 1.57 0.19 3.39 0.10 3.39 0.10 2.09 0.30 2.09 0.30 1.02 0.76 1.02 0.76 note a None identified in this sector.

Table G-2 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods mrem/year 1997 Surve 1998 Surve Number of Approximate Approximate Gardens Within Distance Annual Distance Annual ~3milee 1993 Sector Miles Dose Miles Dose N 1.24 8.11 1.24 8.11 2 NNE 3.10 1.18 3.10 1.18 1 NE 2.67 1.27 2.67 1.27 1 ENE 1.85 2.24 2.68 1.33 1 E 2.70 1.75 2.70 1.75 1 ESE a 1.56 4.08 1 SE a a 0 SSE a a 0 S 2.78 2.28 2.78 2.28 1 SSW 2.59 2.68 2.59 2.68 1 SW a 2.77 1.15 1 WSW 2.67 0.60 2.84 0.56 1 1.69 1.27 1.85 1.15 1 a a 0 a a 0 1.10 10.10 1.10 10.10 5 note a Garden not found within 5 miles.

I Table G-3 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Milk mrem/year Approximate Consumer Age

• Location Sector Distance

{M~iles '997 Feeding Factor 1998 1997 1998 Annual Dose 1997 1998 s/m'arm Bn N 4.9 0.38 0.38 A A 0.029 0.029 1.28E-08 Farm B 6.8 0.01 0.01 A A 0.005 0.005 1.32E-08 NOTE: The feeding factor is an estimate of the percentage of the time the animals are feeding from pasture.

A feeding factor of 0.01 is used in the dose calculation when the estimated feeding factor is 0.

A = Adult, age 17+ years

APPENDIX H DATATABLES AND FIGURES

Table H-1 Average External Gamma Radiation Levels at Various Distances from BROWNS FERRY Nuclear Plant for Each Quarter -1998 mR / Quarter (a)

Distance per annum Miles Average External Gamma Radiation Levels (b) mR/yr 1st qtr 2nd qtr 3rd qtr 4th qtr 0-1 16.1 a 0.9 16.8 2 1.0 18.0 R 0.9 16.4 2 1.1 67 1 -2 14.4 2 1.3 15.4 2 1.5 16.2 2 1.5 14.9 R 1.2 61 2-4 13.4 2 1.0 14.2 k 1.0 15.2 k 1.4 13.8 R 0.9 57 14.1 k 1.4 15.3 2 1.7 14.0 R 1.4 56

>6 13.4 2 0.8 14.0 2 0.8 15.5 2 1.2 14.1 f 0.6 57 Average, 0 - 2 miles 15.6 t 1.2 16.4 k 1.3 17.5 R 1.3 16.0 k 1.3 66 (onsite)

Average,

>2miles 13.211.1 14.1 2 1.2 15.3 2 1.5 14.0 2 1.1 57 (offsite)

(a) Field periods normalized to one standard quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)

(b) Average of the individual measurements in the set s 1 standard deviation of the set TABLE H-2 DIRECT RADIATIONLEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels mR I q uarter Map TLD Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Location Station Direction, Distance, Jan - Mar Apr- Jun Jul - Sep Oct- Dec Exposure Hua~ Hua~ daarcaa 39K mHh car 7 N-1 348 1.0 17.2 18.2 19.2 17.3 71.9 38 N-2 1 5.0 12.6 13.3 14.4 13.0 53.3 8 NNE-1 12 9 15.4 16.2 . 18.1 16.5 66.2 39 NNE-2 31 .7 16.6 note 1 18.3 16.9 69.1 40 NNE-3 19 5.2 12.3 13.5 15.4 13.7 54.9 41 NE-1 51 .8 17.1 17.2 18.1 17.6 70.0 42 NE-2 49 5.0 14.9 15.9 18.3 16.1 65.2 2 NE-3 56 10.9 14.0 14.7 15.3 14.5 58.5 9 ENE-1 61 .9 16.1 17.4 18.2 16.4 68.1 43 ENE-2 62 6.2 13.8 note 1 18.1 14.6 62.0 44 E-1 85 .8 16.5 17.6 19.0 17.5 70.6 45 E-2 91 5.2 14.0 14.7 16.4 14.6 59.7 6 E-3 90 24.2 14.6 14.6 15.7 14.6 59.5 46 ~

ESE-1 110 9 14.3 15.0 16.2 14.3 59.8 47 ESE-2 112 3.0 13.7 14.1 15.9 13.8 57.5 48 SE-1 130 .5 15.5 15.9 16.8 14.7 62.9 49 SE-2 135 5.4 9.5 10.1 10.9 9.8 40.3 50 SSE-1 163 5.1 13.8 14.7 15.1 14.4 58.0 3 SSE-2 165 7.5 14.3 15.1 15.5 14.6 59.5 51 S-1 185 3.1 14.0 15.0 15.8 14.4 59.2 52 S-2 182 4.8 12.0 12.9 13.8 12.7 51.4 note 1 Sum of available quarterly data normalized to 1 year for the annual exposure value

TABLE H -2 continued DIRECT RADIATIONLEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels mR/ quarter Map TLD Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Location Station Direction, Distance, Jan - Mar Apr- Jun Jul - Sep Oct- Dec Exposure Humbler. Hua~ RQERR miha 2995 19K 1996 mBhesr 53 SSW-1 203 3.0 12.2 12.8 12.8 12.5 50.3 54 SSW-2 199 4.4 13.3 14.5 15.2 14.3 57.3 55 SW-1 228 1.9 12.9 13.5 14.4 13.7 54.5 56 SW-2 219 4.7 13.4 14.3 14.8 14.2 56.7 57 SW-3 224 6.0 12.3 13.0 note 1 13.2 51.3 58 WSW-1 244 2.7 12.3 13.2 14.0 12.9 52.4 59 WSW-2 251 5.1 13.8 15.9 15.5 14.9 60.1 60 WSW-3 257 10.5 12.5 13.2 14.7 13.3 53.7 61 W-1 275 1.9 14.3 15.4 16.1 14.5 60.3 62 W-2 268 4.7 12.3 13.7 14.6 13.3 53.9 5 W-3 275 31.3 12.8 13.0 13.8 13.3 52.9 63 WP 265 32.1 13.1 14.8 16.2 14.8 58.9 64 WNW-1 291 3.3 13.2 14.4 15.3 14.1 57.0 65 WNW-2 293 4.4 13.2 14.1 15.5 14.4 57.2 66 NW-1 326 2.2 15.2 15.7 17.3 15.3 63.5 67 NW-2 321 5.3 14.0 15.1 17.4 15.1 61.6 1 NW-3 310 13.8 13.7 13.8 14.5 13.9 55.9 68 NNW-1 331 1.0 15.8 16.8 18.0 16.2 66.8 10 NNW-2 331 1.7 16.0 17.2 18.2 16.5 67.9 69 NNW-3 339 5.2 13.5 14.8 16.8 15.0 60.1 note 1 Sum of available quarterly data normalized to 1 year for the annual exposure value

TENNESSEE VALLEY AUTHORITY ENVIRONMEHTAL RADIOLOGICAL HONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH AIR FILTER PCI/H3 - 0.037 BQ/M3 NAME OF FACILITY: BROWS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1998 TYPE AND LOWER LIHIT ALL COHTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUT I NE OF ANALYSIS DETECTION MEAN (F) NAHE MEAN (F) HEAN (F) REPORTED PERFORMED (LLD) RAHGE DISTANCE AND DIRECTION RANGE RANGE MEASUREHEN'fS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 2.00E-03 2.13E-02( 464/ 464) PH-2 BF ATHENS AL 2.26E-02( 52/ 52) 2.13E-02( 104/ 104) 6.56E 4.47E-02 10.9 MILES NE 9.78E 4.09E-02 8.01E 4.63E-02 GAMMA SCAN (GELI) 143 BE-7 2.00E-02 1 '5E-01( 117/ 117) PH-2 BF ATHENS AL 1.10E-01( 13/ 13) 1.04E-01( 26/ .26) 4.66E 1.50E-01 10.9 MILES NE 5.84E 1.50E-01 4.39E 1 '8E-01 BI -214 5.00E-03 1.19E-02( 68/ 117) LM-78F LAKEVIEW 1.42E-02( 5/ 13) 9.77E-03( 12/ 26) 5.00E 3.09E-02 2.1 MILES WEST 1.02E 2 '0E-02 5.60E 2.26E-02 PB-214 5.00E-03 1.29E-02( 58/ 117) LM4 BF TRAILER P 1.48E-02( 8/ 13) 8.45E-03( 13/ 26) 5 ~ OOE 3.35E-02 1.7 MILES NN'W 5 'OE 3.02E-02 5.00E 2.22E-02 NOTE: 1 ~ NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 ~

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY'RACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AHD INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CHARCOAL FILTER PCI/M3 - 0.037 BQ/M3 NAME OF FACILITY: BRDWNS FERRY NUCLEAR PLANT DOCKET HO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTIHG PERIOD: 1998 TYPE AHD LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NOHROUT INE OF ANALYSIS DETECT IOH MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AHD DIRECl'IOH RANGE RANGE MEASUREMENTS SEE HOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 568 81-214 5 'OE-02 6.80E-02( 21/ 464) PM-3 BF DECATUR AL 1.15E-01( 2/ 52) 6.68E-02( 4/ 104) 5.07E 1.78E-01 8.2 MILES SSE 5.14E 1.78E-01 5.26E 9.09E-02 K-40 3.00E-01 3.38E-01( 24/ 464) LM3 BF NORTHEAST 3.71E-01( 2/ 48) 3.54E-01( 5/ 104) 3.01E 4.12E-01 1.0 MILE EHE 3 '2E 3.90E-01 3.13E 4 ~ 11E-01 PB-214 7.00E-02 9.08E-02( 10/ 464) PM-3 BF DECATUR AL 1 ~ 51E-01( 1/ 52) 1.10E-01( 1/ 104) 7.28E 1.51E-01 8.2 MILES SSE 1.51E 1.51E-01 1.10E 1.10E-01 I-131 SEE NOTE 3.

NOTE: 1 ~ HOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE: 2. MEAN AHD RANGE BASED UPON DETECTABLE MEASUREMENTS OHLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)-

NOTE: 3. THE ANALYSIS OF CHARCOAL FILTERS WAS PERFORMED BY GAMMA SPECTROSCOPY. NO l-131 WAS DETECTED.

THE LLD FOR I-131 BY GAMMA SPECTROSCOPY WAS 0.03 pCi/cubic meter.

TEHHESSEE VALLEY AUTHORITY ENVIROHMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH MILK PCI/L - 0.037 BQ/L HAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTIHG PERIOD: 1998 TYPE AHD LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NOHROUTIHE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RAHGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 I OD IN E-131 103 4.00E-01 52 VALUES < LLD 51 VALUES < LLD GAMMA SCAN (GELI) 103 BI-214 2.00E+01 52 VALUES < LLD SHITH/BENNETT FARM 26 VALUES < LLD 2.04E+01( 1/ 51) 5.0 MILES H 2.04E+01- 2.04E+01 K-40 1.00E+02 1.35E+03( 52/ 52) SHITH/BENNETT FARM 1.37E+03( 26/ 26) 1.33E+03( 51/ 51) 1.24E+03- 1.49E+03 5.0 MILES N 1.26E+03- 1.49E+03 '1.18E+03- 1.48E+03 SR 89 51 3.50E+00 25 VALUES < LLD 26 VALUES < LLD SR 90 51 2.DOE+00 2.02E+00( 2/ 25) SMITH/BEHNETT FARM 2.02E+00( 2/ 12) 26 VALUES < LLD 2.01E+00- 2 '3E+00 5.0 MILES H 2.01E+00- 2.03E+00 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1.

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN VEGETATION PCI/KG - 0.037 BQ/KG (WET WEIGHT)

NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1998 TYPE AND LOWER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUtINE OF ANALYSIS DETECTION MEAN (F) NAHE MEAN (F) HEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREHEHTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 IODINE-131 GAMHA SCAN (GELI) 23 6.DOE+00 '1 VALUES < LLD 12 VALUES < LLD 26 BE-7 2.DOE+02 1.26E+03( 10/ 13) TERRY FARH 1 '6E+03( 10/ 13) 1.07E+03( 13/ 13) 4.28E+02- 2.99E+03 3.2 HILES WN'W 4 '8E+02- 2.99E+03 2.02E+02- 3.06E+03 BI-214 5.50E+01 7.70E+01( 2/ 13) TERRY FARH 7.70E+01( 2/ 13) 2.45E+02( 5/ 13) 7.47E+01- 7.92E+01 3.2 HILES WNW 7.47E+01- 7.92E+01 6.41E>01- 9.00E+02 K-40 4.DOE+02 4.93E+03( 13/ 13) TERRY FARH 4.93E+03( 13/ 13) 5.80E+03( 13/ 13) 2.26E+03- 7.01E+03 3.2 MILES WNW 2.26E+03- 7.01E+03 2.70E+03- 7.70E+03 PB-214 B.DOE+01 13 VALUES < LLD TERRY FARM 13 VALUES < LLD 1.30E+02( 1/ 13) 3.2 HILES WNW 1.30E+02- 1.30E+02 NOTE: 1. NOHINAL LOWER LIHIT OF DETECtION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE: 2. HEAN AND RANGE BASED UPON DE'tECTABLE MEASUREHENTS ONLY. FRACTION OF DETECTABLE HEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

0 TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SOIL PCI/GH - 0.037 BQ/G (DRY WEIGHT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAHA REPORTING PERIOD: 1998 TYPE AND LOWER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION 'WITH HIGHEST ANNUAL HEAN LOCAT I ONS NONROUT I NE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) HEAN (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 11 AC-228 2.50E-01 1.13E+00( 9/ 9) PH-3 BF DECATUR AL 1.40E+00( 1/ 1) 8.49E-01( 2/ 2) 6.31E 1.40E+00 8.2 MILES SSE 1 ~ 40E+00- 1.40E+00 6.61E 1.04E+00 BI -212 4.50E-01 1.22E+00( 9/ 9) LM4 BF TRAILER P 1.48E+00( 1/ 1) 8.47E-01( 2/ 2) 7.42E 1.48E+00 1.7 HILES NNW 1.48E+00- 1.48E+00 7.17E 9.77E-01 BI-214 1.50E-01 8.97E-01( 9/ 9) LH4 BF TRAILER P 1.16E+00( 1/ 1) 7-56E-01( 2/ 2)

I 5.78E 1.16E<00 1.7 HILES NNW 1.16E+00- 1.16E+00 7.31E 7.81E-01 CS-137 3.00E-02 2.51E-01( 8/ 9) LH-6BF BAKER BOTTOH 4.11E-01( 1/ 1) 5.42E-01( 2/ 2)

I 1.28E 4 ~ 11E-01 3 ' HILES SSW 4 ~ 11E 4.11E-01 2.51E 8.33E-O'I K-40 7.50E-01 5.34E+00( 9/ 9) LH2 BF NORTH 7.54E+00( 1/ 1) 4.22E+00( 2/ 2) 2.31E+00- 7.54E+00 0.9 HILE NNE 7.54E+00- 7.54E+00 3.93E+00- 4.50E+00 PB-212 1 ~ OOE-01 1.14E+00( 9/ 9) LH1 BF HORTNWEST 1.42E+00( 1/ 1) 9.00E-01( 2/ 2) 6.60E 1.42E+00 'I.O MILE N 1.42E+00- 1.42E+00 7.25E 1.08E+00 PB-214 1.50E-01 9.96E-01( 9/ 9) LH4 BF TRAILER P 1.26E+00( 1/ I) 8.30E-01( 2/ 2) 6.67E 1.26E+00 1.7 HILES NN'W 1 ~ 26E+00- 1.26E+00 8.03E 8.57E-01 RA-224 7.50E-01 'l.32E+00( 7/ 9) LM4 BF TRAILER P 1.60E+00( 1/ 1) 1.11E+00( 1/ 2) 1.01E+00- 1.60E+00 1.7 HILES NNW 1.60E+00- 1.60E<00 1.11E+00- 1.11E+00 RA-226 1.50E-01 8.97E-01( 9/ 9) LH4 BF TRAILER P 1.16E+00( 1/ 1) 7.56E-01( 2/ 2) 5.78E 1.16E+00 1.7 HILES NNW 1.16E+00- 1.16E+00 7.31E 7.81E-01 TL-208 6.00E-02 3.60E-01( 9/ 9) PH-3 BF DECATUR AL 4.35E-01( 1/ 1) 2.80E-01( 2/ 2) 2.08E 4.35E-01 8.2 HILES SSE 4.35E 4.35E-01 2.22E 3.37E-01 SR 89 11 1.60E+00 9 VALUES < LLD 2 VALUES < LLD SR 90 11 4.00E-01 9 VALUES < LLD 2 VALUES < LLD NOTE: 1. NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE: 2. HEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY- FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TEHHESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN APPLES PCI/KG - 0.037 BQ/KG (WET WT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1998 TYPE AND LOWER LIMIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUT INE OF ANALYSIS DETECTION HEAN (F) NAHE HEAN (F) HEAN (F) REPORTED PERFORMED (LLD) RAHGE DISTANCE AHD DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 2.50E+02 9.52E+02( 1/ 1) BFNP Paradise Shores 9.52E+02( 1/ 1) 8.49E+02( 1/ 1) 9.52E+02- 9.52E+02 1.5 Miles NNW 9.52E+02- 9.52E+02 8.49E+02- 8.49E+02 NOTE: 1. NOHINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1 ~

NOTE: 2. HEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY- FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION MESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CABBAGE PCI/KG - 0.037 BQ/KG (llET IIT)

HAME OF FACILITY: BRSINS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATIOH OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1998 TYPE AND LelER LIMIT ALI. CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION HITH HIGHEST ANNUAL MEAN LOCAT IONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) HEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 2.50E+02 1.76E+03( 1/ 1) 3 MILES SSM 1.76E+03( 1/ 1) 2.03E+03( 1/ 1) 1.76E+03- 1.76E+03 1.76E+03- 1.76E+03 2.03E+03- 2.03E+03 NOTE: 1. NOMINAL LOMER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABI.E E-1.

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL HONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CORN PCI/KG - 0.037 BQ/KG (WET WT)

NAHE OF-FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1998 TYPE AND LOWER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUT I NE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 'I SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 2.50E+02 1.69E+03( 1/ 1) BFNP Paradise Shores 1.69E+03( 1/ 1) 1.96E+03( 1/ 1) 1.69E+03- 1.69E+03 1.5 Miles NNW 1.69E+03- 1.69E>03 1.96E+03- 1.96E>03 NOTE: 1. HOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l.

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TEHNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH GREEN BEAHS PCI/KG - 0.037 BQ/KG (IIET MT)

NAME OF FACILITY: BROWS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1998 TYPE AND LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF IHDICATOR LOCATIOHS .

LOCATION IIITH HIGHEST AHNUAL MEAN LOCATIONS NOHROUT INE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 2.50E+02 3.05E+03( 1/ 1) BFNP Paradise Shores 3.05E+03( 1/ 1) 1.84E>03( 1/ 1) 3.05E+03- 3.05E+03 1.5 Miles NNM 3.05E+03- 3.05E+03 1.84E+03- 1.84E+03 NOTE: 1. HOMINAL LQIER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE: 2. MEAN AHD RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TENNESSEE VALLEY AUTHORITY ENVIRONHEHTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION llESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN POTATOES PCI/KG - 0.037 BQ/KG (llET MT)

NAHE OF FACILITY: BRONNS FERRY NUCLEAR PLANT DOCKET HO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAMA REPORTIHG PERIOD: 1998 TYPE AND LONER LIHIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL HEAN LOCATIONS NONROUT I NE OF ANALYSIS DETECTION MEAN (F) NAHE MEAN (F) HEAN (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 2.50E+02 2.86E+03( 1/ 1) 3.0 MILES NNE 2.86E+03( 1/ 1) 3.12E+03( 1/ 1) 2.86E+03- 2.86E+03 3.0 MILES NNE 2-86E+03- 2.86E+03 3.12E+03- 3.12E+03 NOTE: 1. NOMINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 ~

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AHD INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH TOMATOES PCI/KG - 0.037 BQ/KG (WET WT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTIHG PERIOD: 1998 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIOHS HOHROUT I HE OF ANALYSIS DETECTIOH MEAN (F) NAME (F)

MEAN MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI)

K-40 2.50E+02 1.85E+03( 1/ 1) BFHP Paradise Shores 1.85E>03( 1/ 1) 1.86E+03( 1/ 1) 1.85E+03- 1.85E+03 1.5 Miles NNW 1.85E+03- 1.85E+03 1.86E+03- 1.86E+03 NOTE: 1. HOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1.

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SURFACE MATER(Total)

PCI/L - 0.037 BQ/L NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAMA REPORTING PERIOD: 1998 TYPE AND LOWER LIMIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN LOCATIONS NONROUT I NE OF ANALYSIS DETECTION MEAN (F) NAHE HEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 25 I 1.90E+00 2.76E+00( 12/ 13) TRH 293.5 2.76E+00( 12/ 13) 2.74E+00( 12/ 12) 2.07E+00- 3.35E+00 2.07E+00- 3.35E+00 1.95E+00- 3.57E+00 GAMMA SCAN (GELI) 25 BI-214 2.DOE+01 2.85E+01( 1/ 13) TRH 293.5 2.85E+01( 1/ 13) 3.75E+01( 1/ 12) 2.85E+01- 2.85E+01 2.85E+01- 2.85E+01 3.75E+01- 3.75E+01 TR IT IUH 3.DOE+02 4 VALUES < LLD 4 VALUES < LLD NOTE: 1. NOHINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS OHL'Y. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORIHG AND INSTRUHEHTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN PUBLIC WATER(Total)

PCI/L - 0.037 BQ/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAHA REPORTING PERIOD: 1998 TYPE AND LOWER LIHIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH NIGHEST ANNUAL HEAN LOCATIONS NONROUT I NE OF ANALYSIS DETECTION HEAR (F) NAME HEAN (F) HEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AHD DIRECTION RANGE RANGE HEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 1.90E+00 2.82E+00( 56/ 65) W HOR-E LAWR WAT ATH 2.99E+00( 12/ 13) 2.74E+00( 12/ 12) 1.92E+00- 4 '2E+00 TRH 286.5 2.11E+00- 3.71E+00 1.95E+00- 3 ~ 57E+00 GAMMA SCAN (GELI) 77 BI -214 2.DOE+01 1.12E+02( 2/ 65) FLORENCE, AL 2.02E+02( 1/ 13) 3.75E+01( 1/ 12) 2.12E+01- 2.02E+02 TRM 259.8 2 '2E+02- 2.02E+02 3.75E+Ol- 3.75E+01 PB-214 2.DOE+01 2.09E+02( 1/ 65) FLORENCE, AL 2.09E+02( 1/ 13) 12 VALUES < LLD 2.09E+02- 2.09E+02 TRM 259.8 2.09E+02- 2.09E+02 TR I T I UH 3.DOE+02 20 VALUES < LLD 4 VALUES < LLD NOTE: 1. NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-'I.

NOTE: 2. HEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY. FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN WELL WATER(TotaI)

PCI/L - 0.037 BO/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAHA REPORTING PERIOD: 1998 TYPE AND LOWER LIMIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUT INE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) HEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 I GAHHA SCAN (GELI) co 25 I BI -214 2.00E+01 2.24E+01( 2/ 12) BFN WELL 45 2.24E+01( 2/ 'l2) 3.11E+02( 12/ 13) 2.21E+01- 2.27E+01 0.02 HILES W 2.21E+01- 2.27E+01 1.67E+02- 4.30E+02 PB-214 2.00E+01 2.26E+01( 1/ 12) BFN WELL 06 2.26E+01( 1/ 12) 3.13E+02( 12/ 13) 2.26E+01- 2.26E+01 0.02 HILES W 2.26E+01- 2.26E+01 1.69E+02- 4.36E+02 TRIT IUH 3.DOE+02 4 VALUES ( LLD 4 VALUES < LLD NOTE: 1 ~ NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 ~

NOTE: 2. HEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY. FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY EHVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH CQSERCIAL FISH PCI/GH - 0.037 BQ/G (DRY WEIGHT)

NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITYI LIHESTOHE ALABAMA REPORTING PERICOI 1998 TYPE AND LOWER LIHIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION HEAN (F) NAHE MEAN (F) HEAN (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREHEHI'S SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAHMA SCAN (GELI) 4 Bl-214 1.00E-01 3.36E-01( 1/ 2) WHEELER RES 3.36E-01( 1/ 2) 1.40E-01( 1/ 2) 3.36E 3.36E-01 TRH 275-349 3.36E 3.36E-01 1.40E 1.40E-01 CS-'137 3.00E-02 3.56E-02( 1/ 2) WHEELER RES 3.56E-02( 1/ 2) 2 VALUES ( LLD 3.56E 3.56E-02 TRH 275-349 3.56E 3.56E-02 K-40 4.00E-01 1.27E+01( 2/ 2) WHEELER RES 1.27E+01( 2/ 2) 1.21E+01( 2/ 2) 1.01E+0'I- 1.54E+01 TRM 275-349 1.01E+01- 1.54E+01 1.10E+01- 1.32E+01 NOTE: 1. NOHINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY'RACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH GAME FISH PCI/GM - 0.037 BQ/G (DRY WEIGHT)

NAME OF FACILITY: BROWHS FERRY NUCLEAR PLANT DOCKET HO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTOHE ALABAMA REPORTING PERIOD: 1998 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS HOHROUTIHE OF ANALYSIS DETECTION MEAN (F) NAME HEAN (F) MEAN (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 4 Bl-214 1.00E-01 1.63E-01( 1/ 2) WHEELER RES 1.63E-01( 1/ 2) 1.77E-O'I( 1/ 2) 1.63E 1.63E-01 TRM 275-349 1.63E 1.63E-01 1.77E 1.77E-01 CS-137 3.00E-02 7.47E-02( 2/ 2) WHEELER RES 7.47E-02( 2/ 2) 4.54E-02( 1/ 2) 3.41E 1 '5E-01 TRM 275-349 3.41E 1.15E-01 4.54E 4.54E-02 K-40 4 ~ OOE-01 1.56E+01( 2/ 2) WHEELER RES 1.56E+01( 2/ 2) 1.6BE+01( 2/ 2) 1.52E+01- 1.60E+01 TRM 275-349 1 ~ 52E+01- 1.60E+01 1.68E+01- 1.69E+01 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1.

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREHEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

0 TENNESSEE VALLE AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION IIESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SEDIMENT PCI/GM - 0.037 BQ/G (DRY MEIGHT)

NAHE OF FACILITY: BROWS FERRY NUCLEAR PLANT DOCKET NO.: 50 259g260g296 LOCATION OF FACILITY: LIHESTONE ALABAMA REPORTING PERIOD: 1998 TYPE AND LOWER LIMIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAHE MEAN (F) HEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 'EE NOTE 2 GAMMA SCAN (GELI)

AC-228 2.50E-01 2.00E+00( 2/ 2) TRM 293.7 2.47E+00( 1/ 1) 1 '5E+00( 1/ 1) 1 ~ 54E+00- 2.47E+00 BFN DISCHARGE 2.47E+00- 2.47E+00 1.25E+00- 1.25E+00 BE-7 2.50E-01 1.62E+00( 2/ 2) TRH 288.78 2.30E+00( 1/ 1) 4.53E-01( 1/ 1) 9.40E 2.30E+00 2.30E+00- 2.30E+00 4.53E 4.53E-01 BI-212 4.50E-01 2.18E+00( 2/ 2) TRH 293.7 2.89E+00( 1/ 1) 1.39E+00( 1/ 1) 1.47E+00- 2.89E+00 BFN DISCHARGE 2.89E+00- 2.89E+00 1.39E+00- 1.39E+00 81-214 1.50E-01 1.59E+00( 2/ 2) TRH 293.7 2.14E+00( 1/ 1) 9.26E-01( 1/ 1) 1.03E+00- 2.14E+00 BFN DISCHARGE 2.14E+00- 2.14E+00 9.26E 9.26E-01 C0.60 3.00E-02 8.56E-02( 2/ 2) TRH 293.7 8.86E-02( 1/ 1) 1 VALUES < LLD 8.26E 8.86E-02 BFN DISCHARGE 8.86E 8.86E-02 CS-134 3.00E.02 5 '0E-02( 2/ 2) TRH 293.7 5.79E-02( 1/ 1) 1 VALUES < LLD 4.61E 5.79E-02 BFN DISCHARGE 5.79E 5.79E-02 CS-137 3.00E-02 6.79E-01( 2/ 2) TRH 293.7 7.89E-01( 1/ 1) 3.36E-01( 1/ 1) 5.69E 7.89E-01 BFN DISCHARGE 7.89E 7.89E-01 3.36E 3.36E-01 K-40 7.50E-01 1.95E+01( 2/ 2) TRH 293.7 2.56E+01( 1/ 1.34E+01(

1) 1/ 1) 1.35E+01- 2.56E+01 BFN DISCHARGE 2.56E+01- 2.56E+01 1.34E+01- 1.34E+01 PB-212 1 OOE-01 2.14E+00( 2/ 2) TRM 293.7 2.78E+00( 1/ 1) 1.29E+00(

~

1/ 1) 1.49E+00- 2.78E+00 BFN DISCHARGE 2.78E+00- 2.78E+00 1.29E+00- 1.29E+00 PB-214 1 '0E-01 1.73E+00( 2/ 2) TRH 293.7 2.39E+00( 1/ 1) 1.03E+00( 1/ 1) 1.07E+00- 2.39E+00 BFN DISCHARGE 2.39E+00- 2.39E+00 1.03E+00- 1.03E+00 RA-224 7.50E-01 2.30E+00( 2/ 2) TRM 293.7 2.98E+00( 1/ 1) 1.29E+00( 1/ 1) 1.61E+00- 2.98E+00 BFN DISCHARGE 2.98E+00- 2.98E+00 1.29E+00- 1.29E+00 RA-226 1.50E-01 1.59E+00( 2/ 2) TRH 293.7 2.14E+00( 1/ 1) 9.26E-01( 1/ 1) 1.03E+00- 2 ~ 14E+00 BFN DISCHARGE 2.14E+00- 2.14E+00 9.26E 9.26E-01 TL-208 6.00E-02 6.58E-01( 2/ 2) TRM 293.7 8.58E-01( 1/ 1) 3.93E-01( 1/ 1) 4.59E 8.58E-01 BFN DISCHARGE 8.58E 8.58E-01 3.93E 3.93E-01 SR 89 1.60E+00 2 VALUES < LLD 1 VALUES < LLD SR 90 4.00E-01 4.08E-01( 1/ 2) TRH 293.7 4.08E-01( 1/ 1) 1 VALUES < LLD 4.08E 4.08E-01 BFN DISCHARGE 4.08E 4.08E-01 NOTE: 1 ~ NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE NOTE: 2. AND RANGE BASED UPON DETECTABLE MEASUREHENTS "HEAN LOCATIONS IS INDICATED IN PARENTHESES (F) ~

ONLY. FRACTION OF DETECTABLE HEASUREMENTS AT SPECIFIED

TENNESSEE VALLEY AUtHORITY EHVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SHORELINE SEDIMENT PCI/GH - 0.037 BQ/G (DRY WEIGHT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1998 TYPE AND LOWER LIMIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGKEST ANNUAL MEAN LOCATIONS NONROUTIHE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 3 AC-228 2.50E-01 2.78E-01( 1/ 2) JOE WHEELER ST PARK 2.78E-01( 1/ 'I) 1 VALUES < LLD 2.78E 2.78E-01 TRM 279.5 2.78E 2.78E-01 BI -214 1.50E-01 2.22E-01( 2/ 2) JOE WHEELER ST PARK 2.70E-01( 1/ 1) 1.66E-01( 1/ 1) 1.75E 2.70E-01 TRH 279.5 2.70E 2.70E-01 1.66E 1.66E-01 K-40 7.50E-01 2 VALUES < LLD MALLARD CREEK REC AR 1 VALUES < LLD 1 '2E+00( 1/ 1)

TRH 293.0 1.52E+00- 1.52E+00 PB-212 1.00E-01 2.07E-01( 2/ 2) JOE 'WHEELER ST PARK 2.51E-01( 1/ 1) 2.08E-01( 1/ 1) 1.63E 2.51E-01 TRH 279.5 2.51E 2.51E.01 2.08E 2.08E-01 PB-214 1.50E-01 2.37E-01( 2/ 2) JOE WHEELER ST PARK 3.03E-01( 1/ 1) 2.08E-01( 1/ 1) 1.70E 3.03E-01 TRH 279.5 3.03E 3.03E-01 2.08E 2.08E-01 RA-226 1.50E-01 2.22E-01( 2/ 2) JOE WHEELER ST PARK 2.70E-01( 1/ 1) 1.66E-01( 1/ 1) 1.75E 2.70E-01 TRH 279.5 2.70E 2.70E"01 1.66E 1.66E-01 TL-208 6.00E-02 7.61E-02( 1/ 2) JOE WHEELER ST PARK 7.61E-02( 1/ 1) 1 VALUES < LLD 7.61E 7.61E-02 TRH 279.5 7.61E 7.61E-02 NOTE: 1 ~ NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY. FRACTION OF DETECI'ABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMEHTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CLAM FLESH PCI/GM - 0.037 BQ/G (DRY WEIGHT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAMA REPORTING PERIOD: 1998 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN LOCATIONS NONROUT INE OF ANALYSIS DETECTION MEAN (F) NAME HEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMEN'TS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 BI-2'14 5.00E-01 1.57E+00( 1/ 1) DOWNSTREAM LOCATION 1.57E+00( 1/ 1) 3.75E+00( 1/ 1) 1 ~ 57E+00- 1.57E+00 DOWNSTREAM 1.57E+00- 1.57E+00 3.75E+00- 3.75E+00 PB-214 1.00E-01 1.83E+00( 1/ 1) DOWNSTREAM LOCATION 1.83E+00( 1/ 1) 3.79E+00( 1/ 1) 1.83E+00- 1.83E+00 DOWNSTREAM 1.83E+00- 1.83E+00 3.79E+00- 3.79E+00 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 ~

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY. FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

Direct Radiation Levels Browns Ferry Nuclear Plant 25 20 CO 15 E

10 1975 1980 1985 1990 1995 2000 Calendar Year

~ On-Site m Off-Site

Direct Radiation Levels by Thermoluminescence Dosimetry Watts Bar Nuclear Plant 25 Initial WBNP operation in January, 1996 20

~

~ on-site (within 2 miles) off-site (more than 2 miles)

M E

15 10 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 Calendar Year

Annual Average Gross Beta Activity in Air Filters - BFNP 0.25 Initial plant operaton in August, 1973 0.20 I

I I

I I

0.15 I O I Preoperational Average I

'7

> 010 O

0.05 W-OW 0.00 1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year e indicator ~ Control

Annual Average Sr-90 Activity in Milk - BFNP 20 15 initial plant operation in August, 1973 O

~ 10 Preoperational A~rage O

Nominal LLD 1965 1970 1975 1980 19S5 1990 1995 2000

~ ~ Calendar Year hdicator Control

Annual Average Cs-137 Activity in Soil - BFNP initial plant operation in August, 1973 I

I Q I

E I I

2 I Q)

I I

O I CL I 1

I I

Preoperational Average 1965 1970 1975 1980 1985 1990 1995 2000

~ ~ Calendar Year indicator control

Annual Average Gross Beta Activity in Surface Water - BFNP

- Preoperational Awrage c) 4 O

CL 2

I Initial Plant I Note: no gross beta Operation in measurements were August, 1973 I made in 1978 1965 1970 1975 1980 1985 1990 1995 2000

~ ~

Calendar Year dow nstream upstream

Annual Average Gross Beta Activity in Drinking Water - BFNP Initial plant operation in August, 1973, I

I 4 I I

O I Preoperational Amrage I

I Q 2 1965 1970 1975 1980 1985 1990 1995

~

Calendar Year dow nstream o upstream

Annual Average Cs-137 Activity in Fish Flesh Game Fish - BFNP 0.5 initial piant operation in August, 1973 0.4 E

0.3 Preoperational Average O

SL 0.2 0.1 0.0 1965 1970 1975 1980 1985 1990 1995

~ Calendar Year dow nstream o upstream

Annual Average Cs-137 Activity in Fish Flesh Commercial Fish - BFNP 0.25 initial plant operation in August, 1973 0.20 E

0.15 0

Preoperational Aerage 0.10 0.05 0.00 0 OW OW O-O-1965 1970 1975 1980 1985 1990 1995 2000

~ Catendar Year dow nstream ~ upstream

Annual Average Cs-137 Activity in Sediment - BFNP Initial plant operation in August, 1973 E

CQ 3

O CL Preoperational Average 2

1965 1970 1975 1980 1985 1990 1995 2000

~ Calendar Year dawnstream o upstream

Annual Average Co%0 Activity in Sediment - BFNP 0.8 Initial plant operation in August, 1973 0.6 E

CO O

a 0.4 Preoperational Aerage 02 0.0 1965 1970 1975 1980 1985 1990 1995 2000

~

~ Calendar Year dow nstream ~ upstream