ML18039A322

Annual Radiological Environ Operating Rept for Browns Ferry Nuclear Plant Units 1 & 2 for 970101-1231.

ML18039A322
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Site:	Browns Ferry
Issue date:	12/31/1997
From:	TENNESSEE VALLEY AUTHORITY
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Annual Radiological Environmental Operating Report Browns Ferry Nuclear Plant 1997 9'804240350 980420 PDR ADQCK 05000259 PDR

TABLE OF CONTENTS able of Contents List of Tables lv List of Figures.

Executive Summary.

Introduction . 2 Naturally Occurring and Background Radioactivity. 2 Electric Power Production.. 5 Site/Plant Description.

Radiological Environmental Monitoring Program......

Direct Radiation Monitoring. 11 Measurement Techniques......... 11 Results............

~ ~ ~ ~ ~ 12 tmospheric Monitoring. 15 Sample Collection and Analysis... ~ .. '15 Results 16 Terrestrial Monitoring......... 18 Sample Collection and Analysis 18 Results........... ~............ 19 Aquatic Monitoring.... 21 Sample Collection and Analysis 21 R esults......... ~............. 23 Assessment and Evaluation. 25 Resul'ts ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 26 Conclusions . 27 References. 28 Appendix A Radiological Environmental Monitoring Program and Sampling Locations....

~ ~ 34 ppendix B 1997 Program Modifications. 45 Appendix C Program Deviations..... 48 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

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V LIST OF TABLES le 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 Results &om the Intercomparison of

'able'2 Environmental Dosimeters.............. 30 Table 3 Maximum Dose Due to Radioactive Effluent Releases 31'

LIST OF FIGURES

. gure 1 Tennessee Valley Region. 32 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atmosphere and Lake. 33

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EXECUTIVE

SUMMARY

is report describes the radiological environmental monitoring program conducted by TVA in the vicinity of the Browns Ferry Nuclear Plant (BFN) in 1997. The program includes the collection of samples Rom the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and Rom 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 from 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 ult of atmospheric nuclear weapons fallout.

Small amounts of Co-60, Cs-134, Cs-137, and Zn-65 were found in sediment and clam flesh samples downstream from the plant. The level of activity measured in these samples would result in no measurable increase over background in the dose to the general public.

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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 eFects on public heath and safety.

This report satisfies the annual reporting requirements of BFN Technical Specification 6.9.1.5 and Oft'site Dose Calculation Manual (ODCM) Administrative Control 5.1. In addition, estimates of the maximum potential doses to the surrounding population are made from radioactivity measured both in plant eBluents and in environmental samples. The data presented in this report include results from the prescribed program and other useful or interesting information for individuals who do not work with this material routinely.

Naturall Occurrin and Back round Radioactivit st 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 so& 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, uranium-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 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. The average dose equivalent at sea level resulting Rom radiation Rom ter space (part of natural background radiation) is about 27 mrem/year. This essentially doubles th each 6600-foot increase in altitude in the lower atmosphere. Another part of natural background radiation comes from naturally occurring radioactive materials in the soil and rocks.

Because the quantity of naturally occurring radioactive material varies according to geographical location, the part of the natural background radiation coming &om this radioactive material also depends upon the geographical location. Most of the remainder of the natural background radiation comes &om the radioactive materials within each individual's body. We absorb these materials

&om the food we eat which contains naturally occurring radioactive materials &om the soil. An example of this is K-40 as described above. Even building materials affect the natural background radiation levels in the environment. Living or working in a building which is largely made of earthen material, such as concrete or brick, will generally result in a higher natural background radiation level than would exist ifthe same structure were made of wood. This is due to the naturally occurring radioisotopes in the concrete or brick, such as trace amounts of uranium, radium, thorium, etc.

Because the city of Denver, Colorado, is over 5000 feet in altitude and the soil and rocks there contain more radioactive material than the U.S. average, the people of Denver receive around 350 mrem/year total natural background radiation dose equivalent compared to about 295 mrem/year for-the national average. People in some locations of the world receive over 1000 mrem/year natural background radiation dose equivalent, primarily because of the greater quantity of radioactive materials in the soil and rocks in those locations. Scientists have never been able to show that these levels of radiation have caused physical harm to anyone.

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.

e U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENTESTIMATES urce Millirem/Year Per Person Natural background dose equivalent Cosmic 27 Cosmo genic 1 Terrestrial 28 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) can be seen from the table, natural background radiation dose equivalent to the U.S. population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background cosmic and terrestrial radiation.

t Significant discussion recently has centered around exposures from radon. Radon-222 (radon) is an inert gas given off as a result of the decay of naturally occurring radium-226 in soil. When dispersed in the atmosphere, radon concentrations are relatively low. However, when the gas is trapped in closed spaces, it can build up until concentrations become significant. The National Council of Radiation Protection and Measurements (Reference 2) has estimated that the 4

~ r average annual effective dose equivalent from radon in the United States is approximately 200 em/year. This estimated dose is approximately twice the average dose equivalent from all other tural background sources.

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.

Allpaths through which radioactivity is released are monitored. Liquid and gaseous effluent nitors 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 an 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.

~ r The dose to a member of the general public from radioactive materials released to unrestricted areas, 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 clear power plant, established in the Environmental Dose Standard of 40 CFR 190, are as ollows:

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 owns 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. At least 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 24 miles east of the site.

O 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 from the site. The Tennessee River is also a popular sport fishing area.

BFN consists of three boiling water reactors; each unit is rated at 1098 megawatts (electrical). Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974.

C 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. 4 All three units were out of service &om March 1985 to May 1991. Unit 2 was restarted May 24, 1991 and Unit 3 restarted on November 19, 1995. Unit 1 remains in a non operating status.

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

A number of factors were considered in determining the locations for collecting environmental samples. The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weather patterns, dose projections, population distribution, and land use.

Terrestrial sampling stations were selected after reviewing such things as the locations of dairy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections,'water use information, and availability of media such as fish and sediment. Table A-2 (Appendix A, Table 2: This method of notation is used for all tables and figures given in the appendices.) lists the sampling stations and the types of samples collected &om each.

Modifications made to the program in 1997 are described in Appendix B and exceptions to the pling 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 radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of whether the operation of BFN is impacting the environment and thus the surrounding ulation.

The determination of impact during the operating phase also considers the presence of control stations that have been established in the environment. Results of environmental samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to establish the extent of BFN influence.

Allsamples 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 used to determine the radionuclide content of samples collected in

~ environment are very sensitive to small amounts of radioactivity. The sensitivity of the Measurement process is defined in terms of the lower limit of detection (LLD). A description of the nominal LLDs for the Radioanalytical Laboratory is presented in Appendix E.

The 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 participates in the EPA Interlaboratory Comparison Program. 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 A pendix F.

DIRECT RADIATIONMONITORING rect radiation levels are measured at a number of stations around the plant site. These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and radioactivity that may be present as a result of plant operations. Because of the relative large variations in background radiation as compared to the small levels Rom the plant, contributions from the plant may be difficultto distinguish.

Radiation levels measured in the area around the BFN site in 1997 were consistent with levels from 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 ped 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.

f The TLDs are placed approximately 1 meter above the ground, with two or more TLDs at each tion. Sixteen stations are located around the plant near the site boundary, one station in each of sixteen compass sectors. Dosimeters are also placed at the perimeter and remote air monitoring sites and at 19 additional stations out to approximately 32 miles from the site. 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.

Nine of the locations also have TLD devices processed by the NRC. The results from the NRC measurements are reported in NUREG 0837.

Since the calcium sulfate phosphor is much more sensitive than the lithium borate, the measured exposure is taken as the median of the results obtained from the calcium sulfate phosphors in all detectors from the monitoring station. The values are corrected for gamma response, system variations, and transit exposure, with individual gamma response calibrations for each element. The s ystem meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 for environmental applications of TLDs.

Since 1974, TVAhas participated in nine of the eleven 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 Allresults 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 stations are grouped according to the distance from the plant. The first group consists of all stations within 1 mile of the plant. The second group lies between 1 and 2 miles, the third group between 2 and 4 miles, the fourth between 4 and 6 miles, and the fiAh group is made up of all stations more than 6 miles from the plant. Past data have shown that the results from all stations greater than 2 miles

&om the plant are essentially the same. Therefore, for purposes of this report, all stations 2 miles or lessIfrom 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

'I re not as precise at lower exposures. Consequently, the environmental radiation levels reported the preoperational phase of the 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 &om the TLDs deployed around BFN in 1997 are summarized in Table H-1. The results from all measurements at individual stations 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 1997 Onsite Stations Offsite Stations 55 The data in Table H-l indicate that the average quarterly radiation levels at the BFN onsite stations are approximately 2.5 mR/quarter higher than levels at the offsite stations. This difference is t

consistent with levels measured for preoperation and construction phases of TVAnuclear 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 of concrete employed in the construction of the plant. Other undetermined influences may also play a part. These

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conclusions are supported by the fact that similar differences between onsite and offsite stations re measured in the vicinity of the WBN site during the construction and preoperational phase.

Figure H-1 compares plots of the environmental gamma radiation levels from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1997.

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 stations are higher than the levels at offsite stations.

All results reported in 1997 are consistent with direct radiation levels identified at locations which are not influenced by the operation of BFN. There is no indication that BFN activities increase the background direct radiation levels normally observed in the areas surrounding the plant.

ATMOSPHERIC MONITORING e 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 remote air monitors 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. The remote stations are used as control or baseline stations.

Results Rom 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 and onuclides produced as a result of fallout from previous nuclear weapons tests. There is no indication of an increase in atmospheric radioactivity as a result of BFN.

Sam le Collection and Anal sis Airparticulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfin) 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. This system is housed in a building approximately 2 feet by 3 feet by 4 feet. The filter is contained in a sampling head mounted on the outside of the monitor building. The filter is replaced every 7 days. Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 weeks, composites of the filters from each location are analyzed by gamma spectroscopy.

Gaseous radioiodine is collected using a commercially available cartridge containing TEDA-regnated charcoal. This system is designed to collect iodine in both the elemental form and as ganic 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 a complete 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 from the container every 4 weeks. Any excess water is discarded. Samples are held to be analyzed only ifthe air particulate samples indicate the presence of elevated activity levels or iffallout 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 1997.

ults The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 1997 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 1968-1997 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 Rom the Chernobyl accident can also be seen in 1986. These patterns are consistent with data from monitoring programs conducted by TVA at other nuclear power plant sites during construction and preoperational stages.

Only natural radioactive materials were identified by the monthly gamma spectral analysis of the air rticulate samples. No fission or activation products were found at levels greater than the LLDs.

shown in Table H-4, iodine-131 was not detected in any of the charcoal canister samples collected in 1997.

Since no plant-related air activity was detected, no rainwater samples from the vicinity of BFN were analyzed during this reporting period.

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TERRESTRIAL MONITORING rrestrial monitoring is accomplished by collecting samples of environmental media that may transport radioactive material from 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 &om exposure to this pathway. The results from the analysis of these samples are shown in Tables H-5 through H-13.

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 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 es of the plant. The results of the 1997 land use survey are presented in Appendix G.

Sam le Collection andAnal sis Milksamples are purchased every 2 weeks from two dairies identified as indicator locations and from 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 II performed on each sample and Sr-89,90 analysis is performed every' weeks. Samples of vegetation are collected every 4 weeks for I-131 analysis. The samples are collected &om one farm which previously produced milk and &om 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

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container with 1650 ml of 0.5 N NaOH for transport back to the radioanalytical laboratory. A ond sample of between 750 and 1000 grams is also collected from each location. After drying d grinding, this sample is analyzed by gamma spectroscopy. Once each quarter, the sample is ashed after the gamma analysis is completed and analyzed for Sr-89,90.

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 1997 samples of cabbage, corn, green beans, potatoes, and tomatoes were collected from local vegetable gardens. In addition, samples of apples were also obtained &om the area. The edible portion of each sample is analyzed by gamma spectroscopy.

Results The results from the analysis of milk samples are presented in Table H-5. No radioactivity which could be attributed to BFN was identified. All1-131 results were less than the established nominal LLD of 0.4 pCi/liter. Strontium-90 was identified in a total of four samples. The average Sr-90 concentration measured in samples from both indicator and control locations was approximately 2.1 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 I). 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.

Y I The results for Strontium-89 analysis were less than the LLD of 3.5 pCi/liter. By far the dominant isotope reported in milk samples was the naturally occurring K-40. An average of proximately 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. All I-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 0.6 pCi/g in a sample from one of the control stations. This concentration is consistent with levels previously reported from fallout. All other radionuclides reported were naturally occurring isotopes. The results of the analysis of soil samples are reported in Table H-7. A plot of the annual average Cs-137 concentrations in soil is presented in 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 ugh 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.

A UATIC MONITORING tential exposures from the liquid pathway can occur from drinking water, ingestion of fish and invertebrates, or &om direct radiation exposure to radioactive materials deposited in the river sediment. The aquatic monitoring program includes the collection of samples of surface (river/reservoir) water, groundwater, drinking water supplies, fish, Asiatic clams (not consumed by humans), and bottom sediment. Samples Rom the reservoir are collected both upstream and downstream &om the plant.

Results lrom the an'alysis of aquatic samples are presented in Tables H-14 through H-20.

Radioactivity levels in water and fish were consistent with background and/or fallout produced levels previously reported. The presence of Co-60, Zn-65, Cs-134 and Cs-137 was identified in samples of bottom sediment and Zn-65 was identified in one sample of clams collected &om downstream monitoring location.

le Collection and Anal sis Samples of surface water are collected &om the Tennessee River using automatic sampling systems from 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 from drinking water systems which use the nnessee River as their source. These samples are analyzed every 4 weeks by gamma ectroscopy and for gross beta activity. A quarterly composite sample from 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. During the last month of 1997, a program modification was initiated to relocate the upstream sampling point used as surface water and drinking water control to the intake k

of the Decatur City Water Plant. Sampling from this new location was started in January 1998.

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 tritium.

ples 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.

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

f ~

Samples of Asiatic clams are collected &om one location below the plant and one location above the

t. The clams are usually collected in the dredging or diving process with the sediment. Enough ams are collected to produce approximately 50 grams of wet flesh. The flesh is separated &om the shells, and the dried flesh samples are analyzed by gamma spectroscopy.

Results Allradioactivity 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 1997 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, average gross beta activity was 2.9 pCi/liter at the downstream stations and control stations. The results are shown in Table H-15 and a trend plot of the gross beta activity from 1968 to the present is presented in Figure H-7.

O No concentrations of 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 two fish samples (game fish). A concentration of 0.06 pCi/g was measured &om one indicator location sample while the concentration in the control location sample was 0.05 pCi/g. These concentrations are consistent with data &om previous monitoring years. The only other isotopes found in fish were naturally occurring. Concentrations of K-40 ranged from 7.1 pCi/g to 14.8 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 sediment mples. The materials identified were Cs-137, Cs-134, Zn-65 and Co-60. The average levels of

-137 were 0.40 pCi/g in downstream samples and 0.20 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.

Cobalt-60 concentrations in downstream samples averaged 0.08 pCi/g. Cobalt-60 was measured in one sample from the upstream sampling point. The concentration measured from this sample was 0.03 pCi/g. The maximum concentration measured in downstream samples was 0.12 pCi/g. Figure H-11 presents a graph of the Co-60 concentrations measured in sediment since 1968. One sediment sample from the downstream sampling point closest to the plant discharge contained measurable I

levels of Zn-65 and Cs-134. The Zn-65 concentration was 0.07 pCi/g and the Cs-134 concentration was 0.06 pCi/g. A realistic assessment of the impact to the general public from these radioisotopes roduces a negligible dose equivalent. Results Rom the analysis of sediment samples are shown in le H-19.

Zinc-65 was measured at a concentration of 0.78 pCi/g in one sample of clam flesh collected at the downstream sampling point. There is no human consumption of the Asiatic clams sampled in BFN program, therefore, the presence of Zn;65 in the sample does not present an exposure potential to humans. The results for the analysis of clam flesh samples are presented in Table H-20.

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ASSESSMENT AND EVALUATION tential 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 will tend to overestimate the dose to this "hypothetical" person.

In reality, the expected dose to actual individuals is 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 fr'om O 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 Rom the radioactivity in the air, direct radiation from 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

fthe effluents in the atmosphere. Again, as many of the parameters as possible are based on actual e specific data.

Results The estimated doses to the maximum exposed individual due to radioactivity released from BFN in 1997 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. The maximum calculated whole body dose equivalent from measured liquid effluents as presented in Table 3 is 0.25 mrem/year, or 8.4 percent of the limit. The maximum organ dose equivalent Rom gaseous effluents is 0.11 mrem/year. This represents 0.7 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 Radioactive Effluent Release Reports.

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

The results from each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences Rom the plant. During this report period, Co-60, Zn-65, Cs-134 and Cs-137 were seen in aquatic media. The distribution of Cs-137 in sediment and fish is consistent with fallout levels identified in samples both upstream and downstream &om the plant during the preoperational phase of the monitoring program. Since there is no direct exposure pathway to humans, the Co-60, Zn-65 and Cs-134 identified in sediment samples and the Zn-65 in the one clam sample downstream &om the plant would produce no measurable increase in the dose to the general public. No increases of radioactivity have been seen in water samples.

ose estimates were made from concentrations of radioactivity found in samples of environmental dia. Media evaluated include, but are not limited to, air, milk, food products, drinking water, fish d soil. 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 Rom.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 &om 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 o erations does not represent a significant contribution to the exposure of Members of the Public.

REFERENCES Merril Eisenbud, Environmental Radioactivi 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 Rom 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 Effluent Lower limit Concentration'eporting Level~ of Detection~ Concentration'eporting Level~ of Detection3 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 30,000 300 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 O Ru-106 I-131 Cs-134 3,000 1,000 900 2

30 40

,5 0.4 20 200 200 0.9 10 0.02 0.03 0.005 Cs-137 1,000 50 5 200 20 0.005 Ce-144 3,000 30 40 0.011 Ba-140 8,000 ~

200 25 2,000 0.015 La-140 9,000 200 10 2,000 0.01 Note: lpCi=3.7xl0'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.

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Table 2 Results from the Intercomparison of Environmental Dosimeters'ear Calculated Average, all Exposure o/o Difference '/o Difference TVA Results Respondents (See Note I) TVA: Respondents:

mrem 'rem 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 SGa 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 -10.9 -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 93a'4.9 86 93b 18.2 27.8 16.2 25.0 25.0 17.2 25.9 25.9 5.8

-3.9 7.3

-5.8

-3.5

-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

'79.0 0.8 81b 102.0 90.7 88.4 15.4 2.6 82a 191.0 202.0 -11.4 -5.4 82b 136.0 149.0 158.0 -13.9 -5.7 S4a 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 C.O 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 1997 mrem/year Dose From Liquid Effluents 1997 NRC Percent of T~e Dose Limit NRC Limit Total Body 2.5E-1 8.4 Any Organ 3.7E-1 10 3.7 Doses From Gaseous EfHuents 1997 NRC Percent of

~Te Dose Limit NRC Limit Noble Gas 1.2E-3 10 0.01 (Gamma)

Noble Gas 1.9E-3 20 0.01 (Beta)

Any Organ 1.1E-1 15 0.7 Total Cumulative Dose 1997 EPA Percent of

~Te Dose Limit EPA Limit Total Body or Any Other Organ 6.9E-1 25 2.8 Thyroid 4.1E-1 75

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Figure 2 ENVIRONMENTALEXPOSURE PATHWAYS OF MAN DUE TO RELEASES OF RADIOACTIVE MATERIAL TO THE ATMOSPHERE AND LAKE.

~ P..q.

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Diluted By Atmosphere Airborne Releases Plume Exposure Liquid Releases Diluted By Lake Consumed By Man Animals (Milk,Meat) Shoreline Exposure Consumed By Animals Drinking Water Fish Vegetation Uptake From Soil

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)I

APPENDIX A RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM AND SAMPLING LOCATIONS Table A-I 0

BROWNS FERRY NUCLEAR PLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency

~and/or Sam ie Locations~ Collection Fre uenc ~of 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-I and RM-6). isotopic analysis on composite (by location) sample at least once per 31 Three samples from locations in days.

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

b. Radioiodine 5ame 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 Same 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 8

BROWNS FERRY NUCLEAR PLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAM*

Exposure Pathway Number of Samples and Sampling and Type and Frequency

~and/or Sam /e Locationsb Collection Fre uenc ~of Anal sis

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 8 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 0

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 sis

c. Drinking Water Four additional samples of potable Collected by automatic sequential- beta and gamma scan on 4-(Continued) surface water downstream from the days.'ross type sampler with composite sample week composite. Composite for plant (TRM 282.6, TRM 274.9, taken at least once per 31 tritium analysis at least once per 92 TRM 259.8 and TRM 259.6) days; One sample at a control location4 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.

3. AQUATIC

a. Sediment One sample upstream from discharge At least once per 184 days. Gamma scan, Sr-89 and Sr-90 point (TRM 297.0) analyses.

Table A-1 0

BROWNS FERRY NUCLEAR PLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAM*

Exposure Pathway Number of Samples and Sampling and Type and Frequency

~and/or Sam le Locations~ Collection Fre uenc ~of Anal aia

a. Sediment One sample in immediate (Continued) downstream area of discharge point (TRM 293.7)

One additional sample downstream from the plant (TRM 288.8)

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 I (Farms B and Bn). per 31 days at other times. once per 31 days.

co I

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.

c. Clams One sample downstream from the At least once per 184 days: Gamma scan on flesh only.

discharge.

One sample upstream from the plant.

(No permanent stations established; depends on location of clams)

Table A-1 0

BROWNS FERRY NUCLEAR PLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM*

Exposure Pathway Number of Samples and Sampling and Type and Frequency

~and/or Sam le Locationsb Collection Fre uenc ~of Ana1 sis

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 1997.

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

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

Location Distance or Samples Numbera Station Sector ~ilbs Control C Collcctedb 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 ll 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 >>.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 ld I PW 28 TRM 293.5 0.5d I SW 31 TRM 293.7 03d I SD TRM 288.8 5.2d I SD Farm Be NW 28.8 C M Farm T WNW 3.2 I V 37 TRM 297.0 3.0 C SD 70 TRM 259.8 34 2d I PW 71 TRM 286.5 75d I PW Wheeler Reservoir (TRM 275-349) I F,CL 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) CL ~ Clams F ~ Fish M ~ Milk PW ~ Public drinking water R ~ Rainwater S ~ Soil SD ~ Sediment SW Surface Water V ~ Vegetation W Well water

c. TRM ~ Tennessee 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 Numbera Station Sector ~miles ~Offsile 0 I NW-3 NW 13.'8 Off 2 NE-3 NE 10.9 Off 3 SSE-2 SSE 8.2 Off 5 W-3 W 31.3 Off 6 E-3 E 24.2 Off 7 N-I N 0.97 On 8 NNE-I NNE 0.88 On 9 ENE-I ENE 0.92 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 0.8 On 45 E-2 E 5.2 Off 46 ESE-I ESE 0.9 On 47 ESE-2 ESE 3.0 Off 48 SE-I SE 0.5 On 49 SE-2 SE 5.4 Off 50 SSE-I SSE 5.1 Off 51 S-I S 3.1 Off 52 S-2 S 4.8 Off 53 SSW-I SSW 3.0 Off 54 SSW-2 SSW 4.4 Off 55 SW-I SW 1.9 On 56 SW-2 SW 4.7 Off 57 SW-3 SW 6.0 Off 58 WSW-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 63 W-4 W 32.1 Off 64 WNW-I WNW 3.3 Off 65 WNW-2 WNW 4,4 Off 66 NW-I NW 2.2 Off 67 NW-2 NW 5.3 Off 68 NNW-I NNW 1.0 On 69 NNW-3 NNW 5.2 Off

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

b. TLDs designated "onsitc" arc those located 2 miles or less from thc plant.

TLDS designated "offsite" are those located more than 2 miles from thc plant.

Figure A-1 Radiological Environmental Monitoring Locations Within 1 Mile of Plant 348.75 1 1.25 NNE

'7 33.75 68

~ 8 NE WNW 303.75 28'9~ 41 9 56.25 ENE 0 3>

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44 78.75 258.75 BROWNS FERRY 101.25

+g NUCLEAR PLANT 8@

46 48 WSW ESE ri.

236.25 1 23.75 SW 213.75 146.25 SSW SSE 19125 168 75 S

Scale Mile Figure A-2 Radiological Environmental Monitoring Locations From 1 to 5 Miles from the Plant 355.75 11.25 NNW ~ 8 NNE 13 325.25 33.75 NW 303.75 55.25 Pg

+~

WNW .ENE

~ 8

/P 85 ~ 10 251.2 38,84 75.7$

81

~ 62 4 SROWNS FE Y IAICLEAR PLANT 0

2$ 5.7$ ~ 101,25 0 47 55 ~

PS. 37+

44, WSW ESE

/P 235.2d 63 123.75 51 SW 68 SE 64 213.'Td 145.25 52 SSW SCALE 0.5 1 0.5 2 101.2$ 3 155.75 LSLES

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Figure A-3 Radiological Environmental Monitoring Locations Greater than 5 Miles from the Plant 348.76 " 11 26 326.26 33.75 AW ENCESUSO NW Nf FULASKI 303.76 FAV TTEVILLe 8.25 WNW 34 ENE FLOIIENC AT ENS 78.75 A

++ LMT 8 ON SE ~ 2 9 7 43 SOLE HOAL 45 NTSVILL 83 57 3

2S8.75 O CATUA 101.25 IIUSS LLVILLE OUWWesvAL Esf AIIAS 328.2 HALEVVI LE 123.76 CULLMAN SE 213.7 146.25 SCALE 0

55E MlLES 191.25 5 188.76 APPENDIX B 1997 PROGRAM MODIFICATIONS APPENDIX B Environmental Radiolo ical Monitorin Pro am Modifications Only two modifications were made in the BFN monitoring program in 1997. The fish sampling was modified to add an alternative species for both game and commercial fish. Historically crappie have been collected as representing game fish and smallmouth buffalo have been collected as the commercial species. During some sampling periods it has been difficult to find an adequate number of fish for a sample. To address this problem, largemouth bass was added as an alternative game fish and channel catfish was added as an alternative commercial species.

These changes are consistent with fishing practices in the region. The modification allows collection of either crappie or largemouth bass as representative of game fish and,either smallmouth buffalo or channel catfish as the commercial fish. The species collected for a sampling period may be varied based on availability but the same species must be collected from the indicator and control location. This consistency is maintained by first sampling the indicator c'ation. For example, iflargemouth bass is more abundant than crappie it willbe collected as the game species from both the indicator and control location. This change was implemented during the fall sampling period.

In November 1997, the automatic sampler at the location used as a control (TRM 305) for surface and drinking water had to be moved. The sampler was located on a bridge in Decatur, Alabama. The construction of a new bridge had been completed and the old bridge was scheduled to be removed. The decision was made to relocate the sampling point to the intake for Decatur City Water Plant located at TRM 306. This move was started in late November and completed in January 1998. Table B-1 provides a detail summary of the 1997 notifications.

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Table B-I Environmental Radiolo ical Monitorin Pro ram Modifications Date Station Location Remarks 11/97 Control Guntersville Added largemouth bass as alternative game fish Reservoir species and added channel catfish as alternative commercial fish species.

11/97 Indicator Wheeler Reservoir Same modification as control location.

12/9/97 TRM 305 11 miles upstream Deleted automatic water sampler at this location.

12/9/97 TRM 306 12 miles upstream Added automatic water sampler at this location to replace sampling performed at TRM 305.

~ ~ r Appendix C Pro am Deviations During 1997, one milk sample was not collected due to unavailability of the sample. A sample was not available from the Richardson dairy on October 6, 1997. This farm is one of two control locations. A sample was collected as scheduled from the other control location.

As noted in the program modifications discussed in Appendix B, the automatic surface water sampler located at TRM 305 was relocated to TRM 306 during the last month of the 1997. The sampler was removed from TRM 305 during the last monthly sampling period of the year. The sample available in the sampler was collected and analyzed. The results were consistent with the data from the other samples collected from this location during the year and are included in the data used for this report. In addition, grab sampling was performed weekly at the TRM 306 until the automatic sampler was returned to service. Each weekly grab sample was analyzed for gross beta and gamma isotopic. The results were consistent with the normal data from the control location. Since a sample was available from TRM 305 for part of the sampling period and the additional weekly grab sampling was performed during the period of relocation of the sampler, no samples are considered to be missing &om this location for,1997.

Table C-1 lists the missed milk sample. All other samples were collected as scheduled.

~ ~

Table C-1 Environmental Radiolo ical Monitorin Pro ram Deviations Date Station Location Remarks 10f06/97 Farm R 12.5 miles SW Milkwas not available from the Richardson Dairy. Samples were collected from the other control dairy.

I

J 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.'ormal 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.

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

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

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 germanium detector system.

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 from 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 from 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 eading, 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 from 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 &om 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 LLDs have not been established, and LLD of zero is assumed in determining ifa measured activity is greater than the LLD.

TABLE E-1 Nominal LLD Values A. Radiochemical Procedures Sediment

~Ci/m'ater Air Filters

~Ci/L Milk

~Ci/L Fish

~Ci/ ~

d+

Wet Vegetation

~C//K we/

and Soil

~Ci/~ d+

Gross Beta 0.002 1.9 Tritium 300 Iodine-131 0.4 0.4 6.0 Strontium-89 5.0 3.5 31.0 1.6 Strontium-90 2.0 2.0 12.0 0.4

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.

~Ci/m3 itCi/nD 1ICi/L 1ICi/g dry ~Ci/k wet ~Ci/ dry ~~dry

'Ci/

i/ r~Q ~Ci/k wet Ce-141 .005 .02 10 .07 35 .10 .07 .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 .Q2 Q.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 2Q .Q3 .03 .25 10 Mn-54 .005 0.02 5 .03 20 .03 .03 .20 10 Zn-65 .005 0.03 10 .05 45 .05 .05 .40 45 Co-60 .005 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 80 Bi-214 .005 0.05 20 .10 55 .15 .10 .50 40 Bi-212 .02 0.20 50 .25 250 .45 .25 2.0 30 TI-208 .002 0.02 10 '.03 30 .06 .03 .25 130 Ra-224 .75 Ra-226 .15 Ac-228 .01 0.07 20 .10 70 .25 .10 .75 50

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

Specified by the BFN Offsite Dose Calculation Manual Airborne Particulate Food Rater or Gases Fish Milk Products Sediment

~Anet eie pCi/L ~C//mt ~Cilk wet ~Ci/L ~Ci/k ~~ wet ~Ci/k dry gross beta x10~ N.A. N.A. N.A. N.A.

e H-3 2000' N.A. N.A. N.A. N.A. N.A.

Mn-54 15 N.A. 130 N.A. N.A.

Fe-59 30 N.A. 260 N.A.

'o-58,60 15 130 N.A. N.A.

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

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

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

I-131 lb 7x10' N.A. 60 N.A.

Cs-134 15 130 15 60 150 x10'x102 Cs-137 18 18 80 180 150'.A.

Ba-140 60 N.A. 60 N.A. N.A.

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/liter for I-131.

~ ~

Appendix F ualit Assurance/ ualit 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. Three are two primary tests which are performed on all devices, In the first type, the device is operated without a sample on he 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 from either test fall outside the expected range, the device is inspected for malfunction or contamination. It is not placed into service until it is operating properly.

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 vice 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 &om 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 analyst can split a sample into two portions.'uch a sample can provide information about the variability of the analytical process since two identical portions of material are analyzed side by side.

staff 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 ha immediate knowledge of the quality of the measurement pro'cess. 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 performing the analysis labeled as cross-check samples. This means that the quality control staff knows the radioactive content or "right answer" but the lab staff does not. Such samples test the est performance of the laboratory by determining ifthe lab can find the "right answer." These samples provide information about the accuracy of the measurement process. Further information is available about the variability of the process ifmultiple analyses are requested on the same sample. Like blind spikes or analytical knowns, these samples can also be spiked with low levels of activity to test detection limits.

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 1997, 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 other 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 ~Av . (+3~si ma ~Av . (+3~si ma ~Av . (+3~si ma ~Av . (+3~si ma, ~Av .

01/97 15+9 17 02/97 86+16 75 03/97 7900+1368 7770 04/97 24+9 25 13+9 12 07/97 15+9 16 44+9 43 16+9 17 08/97 11010+1907 11106 09/97 10+10 10 10/97 49+9 10/97 36+9 33 22+9 24 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 s~ima ~Av . (+3 ~si ma ~Av . (+3~si ma ~Av . (+3~si ma ~Av .

04/97 21+9 21 31+9 29 22+9 2Q 06/97 25+9 25 18+9 21 100+17 99 22+9 20 49+9 48 1Q/97 10+9 10 41+9 39 34+9 33 11/97 99+17 95 27+9 27 75+16 74 10+9 10 .74+9 74

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

The land use survey is conducted between April 1 and October 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.

t In order to identify the locations around BFN which have the greatest relative potential for a 'mpact by the plant, radiation doses are projected for individuals living near BFN. These projections use the data obtained in the survey and historical meteorological data. They also assume that releases are equivalent to the design basis source terms. The calculated doses 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 are well below applicable dose limits (see Assessment and Evaluation Section and Table 3).

Doses from air submersion are calculated for the nearest resident in each sector, while doses from drinking milk or eating foods produced near the plant are 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 1996. Any changes from the 1996 results were small and were due to differences in the distance values used for the nearest resident. These differences occurred &om 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 1997.

For milk ingestion, projected annual doses were calculated for the same two locations reported in 1996. These were the only two locations where milk producing animals were identified.

Samples are collected from both of these farms. The location Farm Bn indicated a decrease in the annual dose compared to the 1996 results. This change resulted from the change to only adult consumer in 1997 compared to an infant as a consumer of milk at this location in 1996. A small decrease in annual dose was also indicated at Farm B due to change in the feeding factor.

ables G-1, G-2, and G-3 show the comparative calculated doses for 1996 and 1997.

Table G-1 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within Five Miles of Plant mrem/year

'1996 Surve 1997 Surve Approximate Approximate Distance Annual Distance Annual Sector Miles Dose Miles Dose N 1.24 0.45 1.24 0.45 NNE 1.58 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 4.60 0.08 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 0.18 1.57 0.18 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 1996 Surve 1997 Surve Number of Approximate Approximate Gardens Within Distance Annual Distance Annual ~3miiee 1997 Sector Miles Dose Miles Dose

.N 1.24 8.11 1.24 8.11 2 NNE 2.57 1.52 3.10 1.18 1 NE 2.67 1.27 2.67 1.27 1 ENE 2.63 1.37 1.85 2.24 1 E 2.41 2.05 2.70 1.75 1 ESE a a 0 SE a a 0 SSE 4.60 0.88 a 0 S 2.78 2.28 2.78 2.28 1 SSW 2.59 2.68 2.59 2.68 2 SW a a 0 WSW 2.67 0.60 2.67 0.60 2 1.69 1.27 1.69 1.27 1 a 0 2.09 4.93 a 4.93 0 1.03 10.70 1.10 10.10 6 note a Garden not found within 5 miles.

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

• Annual Dose Location Sector fMMiles 1996 1997 1996 1997 1996 1997

'.9 s/m'.28E-08 Farm Bn N 0.38 0.38 I A 0.224 0.029 Farm B 6.8 0.33 0.01 A A 0.016 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.

I = Infant, age 0- 1 years A = Adult, age 17+ years

APPENDIX H DATATABLES AND FIGURES Table H-1 DIRECT RADIATIONLEVELS Average External Gamma Radiation Levels at Various Distances from BROWNS FERRY Nuclear Plant for Each Quarter -1997 mR / Quarter (a)

Distance yearly Miles Average External Gamma Radiation Levels (b) mR/yr 1st qtr 2nd qtr 3rd qtr 4th qtr 0-1 16.5 2 1.1 16.4 2 1.0 17.5 2 0.9 16.5 R 1.0 67 1-2 14.811.4 14.3 2 1.5 15.2 k'1.5 14.5 2 1.3 59 2-4 13.6 k 1.2, 13.1 k 1.2 14.2 k 1.1 13.7 2 1.1 55 4-6 13.8 2 1.4 13.3 2 1.3 14.2 0 1.4 13.7 k 1.4 55

>6 13.9 2 1.0 14.0 R 0.7 14.5 2 0.9 14.2 2 1.5 56

Average, 0-2 miles 16.1 a1.4 15.9 2 1.4 16.8 k 1.5 16.0 k 1.4 65 (onsite)

Average,

>2miles 13.8a1.2 13.5 2 1.2 14.3 0 1.2 13.8 2 1.4 55 (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 a 1 standard deviation of the set

TABLE H-2 DIRECT RADIATIONLEVELS Individual Stations Environmental Radiation Levels mR I quarter Map TLD Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Location Station (1) NRC Direction, Distance, Jan- Mar Apr- Jun Jul - Sep Oct- Dec Exposure Number Number Station No ~de race miles 1997 1997 1997 1997 ~mRI ear 7 N-1 348 1.0 18.0 17.9 18.7 17.8 72A 38 N-2 1 5.0 (2) 12.1 13.2 12.7 50.7 8 NNE-1 12 .9 15.7 16.1 17.0 15.5 64.3 39 NNE-2 31 .7 16.7 16.3 (2) 16.9 66.5 40 NNE-3 19 5.2 13.7 12.8 13.9 13.5 53.9 41 NE-1 51 .8 16.9 17.5 17.9 17.0 69.3 42 NE-2 49 5.0 15.5 15.1 16.4 15.7 62.7 2 NE-3 56 10.9 14.7 14.3 15.0 14.2 58.2 9 ENE-1 22 61 .9 17.1 16.5 17.9 16.9 68.4 43 ENE-2 62 6.2 14.7 14.7 15.1 18.0 62.5 44 E-1 85 .8 17.4 16.3 18.1 17.9 69.7 45 E-2 91 5.2 14.6 14.0 (2) 14.7 57.7 6 E-3 90 24.2 14.6 14.6 15.2 14.5 58.9 46 ESE-1 110 9 14.4 14.5 15.8 15.0 59.7 47 ESE-2 21 112 3.0 14.2 13.2 14.7 14.5 56.6 48 SE-1 130 .5 15.6 15.7 16.5 15.8 63.6 49 SE-2 2 135 5.4 10.1 9.8 10.8 9.9 40.6 50 SSE-1 163 5.1 14.3 14.2 15.1 14.2 57.8 3 SSE-2 37 165 7.5 14.8 14.8 15.3 14.3 59.2 51 S-1 185 3.1 13.8 13.7 14.8 14.1 56.4 52 S-2 182 4.8 12.5 12.4 13.2 12.5 50.6 (1) Locations with TVA and NRC stations co-located (2) Sum of available quarterly data normalized to 1 year for the annual exposure value

TABLE H -2 (continued)

DIRECT RADIATIONLEVELS Individual Stations Environmental Radiation Levels mR/ quarter Map TLD Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual.

Location Station (1) NRC Direction, Distance, Jan- Mar Apr- Jun Jul - Sep Oct- Dec Exposure Number Number Station No ~de race miles 1997 1997 1997 1997 ~mRI ear 53 SSW-1 15 203 3.0 12.0 11.5 12.7 12.1 48.3 54 SSW-2 199 4.4 13.7 13.3 14.4 13.9 55.3 55 SW-1 13 228 1.9 - 13.1 12.7 13.8 12.9 52.5 56 SW-2 219 4.7 13.6 13.6 14.4 13.7 55.3 57 SW-3 224 6.0 12.3 14.3 13.5 13.1 53.2 58 WSW-1 12 244 2.7 12.2 11.9 13.3 12.3 49.7 59 WSW-2 251 5.1 14.4 14.1 15.1 13.8 57.4 60 WSW-3 257 10.5 12.6 13.0 12.7 12.9 51.2 61 W-1 275 1.9 14.7 14.0 14.7 14.6 58.0 62 W-2 268 4.7 13.1 12.5 13.3 13.1 52.0 5 W-3 275 31.3 12.6 12.8 13.7 12.8 51.9 63 WP 265 32.1 14.8 13.7 15.3 14.5 58.3 64 WNW-1 291 3.3 14.0 13.6 13.9 13.9 55.4 65 WNW-2 10 293 4.4 14.2 13.2 14.4 13.6 55.4 66 NW-1 326 2.2 15.6 14.9 16.1 15.1 61.7 67 NW-2 321 5.3 15.6 14.7 15.7 15.1 61.1 1 NW-3 310 13.8 13.7 13.5 14.3 13.6 55.1 68 NNW-1 331 1.0 17.1 16.8 17.8 16.1 67.8 10 NNW-2 331 1.7 16.5 16.3 17.2 16.1 66.1 69 NNW-3 339 5.2 15.0 14.5 15.4 15.2 60.1 (1) Locations with fVAand NRC stations co-located (2) Sum of availabIe quarterly data normalized to 1 year for the annual exposure value

85 TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN AIR FILTER PCI/H3 - 0.037 BQ/M3 NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260(296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1997 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUT INE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECI'ION RANGE RANGE MEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 572 2.00E-03 2.06E-02( 468/ 468) PM-2 BF ATHEHS AL 2.14E-02( 52/ 52) 2.10E-02( 104/ 104) 7.59E 3.91E-02 10.9 MILES NE 8.43E 3.91E-02 8.25E 3.80E-02 GAMMA SCAN (GELI) 143 BE-7 2.00E-02 1 ~ 11E-01( 117/ 117) PM-3 BF DECATUR AL ~ 15E-01( 13/ 13) 1.11E-01(

1 26/ 26) 6.94E 1.68E-01 8.2 MILES SSE 7.83E 1.51E.01 7.03E 1.58E-01 BI-214 5.00E-03 1.18E-02( 95/ 117) PM-1 ROGERSVILLE AL 1.37E-02( 9/ 13) 1.13E-02( 18/ 26) 5.00E 3.50E-02 13.8 HILES NW 5.20E 2.41E-02 5.90E 2.32E-02 PB-214 5.00E-03 1 10E-02( 94/ 117) PH-1 ROGERSVILLE AL 1.28E-02( 9/ 13) 1.19E-02(

~

17/ 26) 5.00E 3.37E-02 13.8 MILES NW 5.20E.03- 2.33E-02 6.10E 2.33E-02 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

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

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RAD10LOGICAL LABORATORY RADIOACTIVITY IN CHARCOAL FILTER PCI/H3 - 0.037 BQ/M3 NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAHA REPORTING PERIOD: 1997 TYPE AND LOWER LIHI7 ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAHE HEAN (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) 572 BI-214 5.00E-02 6.22E-02( 23/ 468) LM4 BF TRAILER P 8.88E-02( 1/ 52) 7.63E-02( 5/ 104) 5.00E 8.88E-02 1.7 HILES NNW 8.88E 8.88E.02 5.08E 1.45E-01 K-40 3.00E-01 3.57E-01( 34/ 468) LM.6BF BAKER BOTTOM 3.97E-01( 2/ 52) 3.48E-01( 5/ 104) 3.01E 5.34E-01 3.0 HILES SSW 3.70E 4.24E-01 3.05E 4.40E-01 PB-214 7.00E-02 8.80E-02( 11/ 468) LM4 BF TRAILER P 1. 14E-01( 1/ 52) 9.88E-02( 3/ 104) 7.42E 1.14E-01 1.7 MILES,NN'W 1:14E 1.14E-01 7.07E 1.51E-01 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l.

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

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

THE LLD FOR I-131 BY GAMMA SPECTROSCOPY 'WAS 0.03 pCi/m 3.

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN HILK PCI/L - 0.037 BO/L NAME OF FACILITY: BROWNS FERRY NUCLEAR DOCKET NO.: 50-259,260,296 FACILITY: LIHESTONE ALABAMA REPORTING PERIOD: 1997 PLANI'OCATION OF TYPE AND LOWER L IHIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUT INE OF ANALYSIS DETECTION HEAN (F) NAHE MEAN (F) MEAH (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NDTE 2 SEE NOTE 2 IODINE-131 103 4.00E-01 52 VALUES < LLD 51 VALUES < LLD GAMMA SCAN (GELI) 103 AC-228 2.00E+01 . 52 VALUES < LLD SHITH/BENNETT FARH 26 VALUES < LLD 2.01E+Ol ( 1/ 51) 5.0 MILES N 2.01E+01- 2 ~ 01E+01 Bl -214 2.00E+01 2.87E+01( 4/ 52) SHITH/BENNETT FARH 3.67E+01( 2/ 26) 2.54E+01( 8/ 51) 2.02E+01- 3.91E+01 5.0 MILES H 3.43E+01- 3.91E+01 2.18E+01. 3.2ZE+01 K-40 1.DOE+02 1.34E+03( 52/ 52) SMITH/BENNETT FARH 1 '5E+03( 26/ 26) 1.35E+03( 51/ 51) 1.19E+03- 1.64E+03 5.0 MILES N 1.19E+03- 1.64E+03 1 ~ 19Ei03- 1.50E+03 PB-214 2.DOE+01 2.44E+01( 2/ 52) SMITH/BENNETT FARM 2.44E+01( 2/ 26) 2.58E+01( 1/ 5'I) 2.14E+01- 2.74E+01 5 ~ 0 MILES N 2.14E+01- 2.74E+01 2.58E+01- 2.58E+01 SR 89 52 3.50E+00 26 VALUES < LLD 26 VALUES < LLD SR 90 52 2.DOE+00 2.12E+00( 2/ 26) SHITH/BENNETT FARH 2.12E+00( 2/ 13) 2.15E+00( 2/ 26) 2.06E+00- 2.17E+00 5.0 MILES N 2.06E+00- 2.17E+00 2.11E+00- 2.19E+00 NOTE: 1 ~ NOHINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

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

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL HONITORING AND IHSTRUMENTATION MESTERN AREA RADIOLOGICAL LABORATORY RADIOACI'IVITY IN VEGETATION PCI/KG - 0.037 BQ/KG (NET HEIGHT)

NAME OF FACILITY: BR(W FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATIOH OF FACILITY- LIMESTONE ALABAMA REPORTING PERIOD: 1997 TYPE AND LOVER LIHIT ALL CONTROI. NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION NTH HIGHESI'NNUAL MEAN LOCATIONS NONROUT I NE OF AHALYSIS DETECTION HEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RAHGE HEASUREMENTS SEE NOTE 'I SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 IODINE-131 26 6.DOE+00 13 VALUES < LLD VALUES < LLD GAMMA SCAN (GELI) 26 BE-7 2.DOE+02 1.51E+03( 13/ 13) TERRY FARM 1.51E+03( 13/ 13) 1.51E+03( 13/ 13) 2.44E+02- 6.35E+03 3.2 MILES NNQ 2.44E+02- 6.35E003 3.45E+02- 4.60E+03 BI-214 5 '0E+01 1.50E+02( 4/ 13) TERRY FARM 1 ~ 50E+02( 4/ 13) 8.55E+01( 5/ 13) 6.31E+01- 2.85EtOZ 3.2 MILES llNM 6.31E401- 2.85E+02 5.87E<01- 1.24E+02 K-40 4.DOE+02 5.47E+03( 13/ 13) TERRY FARM 5.47E+03( 13/ 13) 6.46E+03( 13/ 13) 3.74E+03- 6.66E+03 3.2 MILES NNM 3.74Ei03- 6.66E+03 3.58E+03- 7.82E+03 PB-2'I2 4 'OE+01 1 '0E+02( 1/ 13) TERRY FARM 1.10E+02('.10E+02-1/ 13) " 13 VALUES < LLD 1.10E+02- 1.10E402 3.2 MILES NNM 1.10E+02 PB-214 8.DOE+01 1.33E+02( 3/ 13) TERRY FARH 1.33E+02( 3/ 13) 1.01E+02( 3/ 13) 1.03E>02- 1.48E+02 3.2 MILES HNH 1.03E+02- 1.48E+02 8.13E+01- 1.14E+02 TL-208 3.DOE+0'I 3.74E+01( 1/ 13) TERRY FARM 3.74E+01( 3.74E+01'3 1/ 13) 13 VALUES < LLD 3.74E+01- 3.74EtOI 3.2 MILES HNW 3.74E+01-NOTE: 1. HOMINAL LONER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE: 2. MEAN AND RANGE BASED UPON DETECTABI.E MEASUREMENTS ONLY. FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFiED LOCATIONS IS INDICATED IN PARENTHESES (F).

W .

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

NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAHA REPORTING PERIOD: 1997 TYPE AND LOWER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATIOH WITH HIGHEST ANNUAL HEAN LOCATIONS NONROUT I NE OF ANALYSIS DETECTION HEAN (F) NAHE 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 GAHHA SCAN (GELI)

'l1 AC-228 2.50E-01 1 ~ 10E+00( 9/ 9) PH-3 BF DECATUR AL 1.33E+00( 1/ 1) 6.91E-01( 2/ 2) 5.40E-01. 1.33E+00 8.2 MILES SSE 1.33E+00- 1 '3E+00 5.56E 8.25E-01 BI -212 4.50E-01 1. OBE+00( 9/ 9) LM2 BF NORTH 1.34E+00( 1/ 'I) 8.38E-01( 2/ 2) 5.77E-01. 1 '4E+00 0.9 MILE NNE 1.34E+00- 1.34E+00 6.07E 1.07E+00 BI-214 1.50E-01 8.19E-01( 9/ 9) LH2 BF NORTH 9.66E-01( 1/ 1) 7.35E-01( 2/ 2) 5.23E 9.66E-01 0.9 MILE NNE 9.66E 9.66E-01 6.30E 8.39E-01 CS-137 3.00E-02 2.48E-01( 9/ 9) LH.6BF BAKER BOT'TOM 4.52E-01( 1/ 1) 3.96E-01( 2/ 2) 4.81E 4.52E-01 3.0 HILES SSW 4.52E 4.52E-01 1.74E 6 17E 0'I K-40 7.50E-01 4.63E+00( 9/ 9) LM1 BF NORTHWEST 6.82E+00( 1I 1) 3.82E+00( 2/ 2) 1.87E+00- 6.82E+00 1.0 HILE N 6.82E+00- 6.82E+00 3.28E+00- 4.37E+00 PB-212 1.00E-01 1.01E+00( 9/ 9) PM-3 BF DECATUR AL 1.24E+00( 1/ I) 7.03E-01( 2/ 2) 4.93E-01 1.24E+00 8.2 HILES SSE 1.24E+00- 1.24E+00 5.97E 8.09E-01 PB-214 1.50E-01 9.20E-01( 9/ 9) LH2 BF NORTH 1. 12E+00( 1/ 1) 8.53E-01( 2/ 2) 5.74E 1 '2E+00 0.9 HILE NNE 1.12E+00- 1 '2E+00 7.38E 9.69E-01 RA-224 7.50E-01 1.20E+00( 8/ 9) LM2 BF NORTH 1.49E+00( 1/ 1) 2 VALUES < LLD 9.43E 1.49E+00 0.9 HILE NNE 1.49E+00- 1.49E+00 RA-226 1.50E-01 8.19E 01( 9/ 9) LH2 BF NORTH 9.66E-01( 1/ 1) 7.35E-01( 2/ 2) 5.23E 9.66E-01 0.9 HILE NNE 9.66E 9.66E-01 6.30E 8.39E-01 TL-208 6.00E-02 3 '2E-01( 9/ 9) PH-3 BF DECATUR AL 3.95E-01( 1I 1) 2.31E-01( 2/ 2) 1.58E 3.95E-01 8.2 MILES SSE 3.95E 3.95E.01 1.88E 2.73E-01 SR 89 1.60E+00 9 VALUES < LLD 2 VALUES < LLD SR 90 4.00E-01 9 VALUES < LLD 2 VALUES < LLD NOTE: 1. NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

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

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND -INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN APPLES PCI/KG - 0.037 BO/KG (WET WT)

NAME OF FACILITY: BROWS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1997 TYPE AND LOWER LIMIT 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) HEAN (F) REPORTED PERFORMED (LLD) RANGE DISTAHCE AND. DIRECTION RANGE RANGE MEASUREHEN'IS SEE NOTE 1 SEE NOTE 2 SEE NO'IE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 BI-214 4.DOE+01 6.57E+01( 1/ 1) BF AREA 6.57E+01( 1/ 1) 1 VALUES < LLD 6.57E+01- 6.57E+01 6.57E+01- 6.57E+01 K-40 2.50E+02 1 ~ 02E+03( 1/ 1) BF AREA 1.02E+03( 1/ 1) 9.58E+02( 1/ 1) 1.02E+03- 1.02E+03 1.02E+03- 1.02E+03 9.58E+02- 9.5BE+02 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1.

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

~ ~

TENNESSEE VALLEY AUTHORITY ENVIRONMEHI'AL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CABBAGE PCI/KG - 0.037 BQ/KG (WET Wl')

NAME OF FACILITY: BRSIHS FERRY NUCLEAR PLANT DOCKEI'O.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTIHG PERIOD: 1997 TYPE AND LOWER LIMIT ALL CON'IROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCAT IONS NONROUT I HE OF ANALYSIS DETECTION MEAN (F) NAME MEAH (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTAHCE AND DIRECI'ION RANGE RANGE MEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 2.50E+02 1.58E+03( 1/ 1) BF AREA 1.58E+03( 1/ 1) 2.36E+03( 1/ 1) 1.58E+03- 1.58E+03 1.58E+03- 1-58E+03 2.36E+03- 2.36E+03 NOTE: 1. HOMINAL LOWER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IH TABLE E-1.

NOTE: 2. MEAN AHD RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRAG'IION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIOHS IS INDICATED IH PAREHTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND IHSTRUMEHTATION MESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CORN PCI/KG - 0.03/ BQ/KG (WET MT)

NAHE OF FACILITY: BRSSS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1997 TYPE AND LONER LIHIT AI.L CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION HITH NIGHEST ANNUAL MEAN LOCATIONS NONROUT INE OF ANALYSIS DETECTION MEAN (F) NAHE MEAN (F) MEAN (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 81-214 4.DOE+0'I 1 VAl.UES < LLD BF AREA 1 VALUES < LLD 4.30E+01( 1/ 'I) 4.30E+01. 4.30E+01 K-40 2.50E+02 2.18E+03( 1/ 1) BF AREA 2.18E+03( 1/ 1) 2.77E+03( 1/ 1) 2.18E+03- 2.18E+03 2.18E+03- 2. 18E+03 2.77E+03- 2.77E+03 NOTE: 1. NOMINAL LOLIER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

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

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

NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAMA REPORTING PERIOD:

1997'YPE AND LOWER LIHIT ALL CONTROL NUHBER OF TOTAL HUHBER OF INDICATOR LOCATIONS .LOCATION WITH HIGHEST ANNUAL MEAN LOCAT I ONS NONROUT INE OF ANALYSIS DETECTION MEAN (F) NAHE 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) 2 BI-214- 4.DOE+01 5.57E+01( 1/ 1) BF AREA 5.57E+01( 1/ 1) 1 VALUES < LLD 5.57E+01- 5.57E+01 5.57E+D1- 5.57E+01 K-40 2.50E+02 2.37E+03( 1/ 1) BF AREA 2.37E+03( 1/ 1) 2.38E+03( 1/ 1) 2.37E+03- 2.37E+03 2.37E+03- 2.37E+03 2.3BE+03- 2.3BE+03 NOTE: 1. NOHINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE: 2 ~ HEAH AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY- FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS IHDICATED IN PARENTHESES (F).

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

NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50.259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAMA REPORTING PERIOD: 1997 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORHEO (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI)

BI-214 4.00E+01 6.33E+01( 1/ 1) BFNP Paradise Shores 6.33E+01( 1/ 1) 1 VALUES < LLD 6.33E+01- 6.33E+01 1.5 Hi les NNW 6.33E+0'I- 6.33E+01 I K-40 2 '0E+02 4 '0E+03( 1/ 1) BFHP Paradise Shores 4.10E+03( 1/ 1) 3.88E+03( 1/ 1) co 4.10E+03- 4.10E+03 1.5 Miles.NNW 4.10E+03- 4.10E+03 3.88E+03- 3.88E+03 I

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

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

TENNESSEE ALLEY AUTHORITY EHVIROHMENTAL RADIOI.OGICAL MOHITORING AHD IHSTRUMENTATIOH 0

WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN 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 REPORTING PERIOD: 1997 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST AHNUAL MEAN LOCATIONS HONROUT I HE OF AHALYSIS DETECTIOH MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LI.D) RANGE DISTANCE AHD DIRECTION RANGE RANGE MEASUREMEHTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE HO'IE 2 GAMMA SCAN (GELI) 2 K-40 2.50E+02 2.15E+03( 1/ 1) BF AREA 2 ~ 15E+03( 1/ 1) 2.54E+03( 1/ 1) 2.15E+03- 2.15E+03 2.15E+03- 2.15E+03 2.54E+03- 2.54E+03 NOTE: 1 ~ HOMINAL LOWER LIMIT OF DETECTION (LI.D) AS DESCRIBED IH TABLE E 1.

NOTE: 2. MEAN AHD 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 0

MES'IERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SURFACE llATER(Total)

PCI/L - 0.037 BQ/L NAME OF FACILITY: BRONNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAHA REPORTING PERIOD: 1997 TYPE AND LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION MITN HIGHEST ANNUAL MEAN LOCATIONS NONROUT I HE OF ANALYSIS DETECTION MEAN (F) NAME (F)

MEAN HEAN (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 26 1.90E+00 3.21E+00( 12/ 13) TRH 293.5 3.21E+00( 12/ 13) 2.75E+00( 11/ 13) 2.16E+00- 4.55E+00 2.16E+00- 4.55E+00 2.04E+00- 3.71E+00 GAMMA SCAN (GELI)

I 26 oo Bl-214 2.DOE+01 2.43E+01( 1/ 13) TRM 293.5 2.43E+01( 1/ 13) 2.73E+01( 6/ 13)

I 2.43E+01- 2.43E+01 2.43E+01- 2.43E+01 2.22E+01- 3.37E+01 PB-214 2.DOE+01 3.02E+01( 1/ 13) TRH 293.5 3.02E+01( 1/ 13) 0.19E+01( 1/ 13) 3.02E+01- 3.02E+01 3.02E+O'I- 3.02E+01 2.19E+01- 2:19E+01 TRITIUM 8

3.DOE+02 4 VALUES < LLD 4 VALUES < LLD NOTE: 1. NOMINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NO'IE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY 0

ENVIRONMENTAL RADIOLOGICAL MONITORING AND IHSTRUHENTATION 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: LIHES'IONE ALABAMA REPORTING PERIOD: 1997 TYPE AND LOWER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN LOCATIONS NONROUT INE OF ANALYSIS DETECTION HEAN (F) NAME HEAN (F) MEAN (F) REPORTED PERFORMED (LLO) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 91 1.90E+00 2.94E+00( 56/ 65) W MOR-E LAIR WAT ATH 3.12E+00( 11/ 13) 2.88E+00( 23/ 26) 1.91E+00- 5.56E<00 TRH 286.5 2.19E+00- 4 '3E+00 1.94E+00- 4.98E+00 GAMMA SCAN (GELI) oo 91 I BI-214 2.DOE+01 3.22E+01( 8/ 65) W MOR-E LAWR WAT ATH 4.98E+01( 1/ 13) 2.84E+01( 9/ 26) 2.28E+01- 4.98E+01 TRM 286.5 4.98E401 4.98E+01 2.01E+01- 4.36E+01 PB-214 2.DOE+01 2.65E+01( 4/ 65) W HOR-E LAWR WAT ATH 3.50E+01( 1/ 13) 2.99E+01( 3/ 26) 2.15E+01- 3.50E+01 TRH 286.5 3.50E+01- 3.50f+01 2.19E+01- 4.21E+01 TRITIUM 28 3.DOE+02 20 VALUES < LLD 8 VALUES < LLD NOTE: 1. NOMINAL LOWER LIHIT OF DETECTION (LLO) AS DESCRIBED IN TABLE E-1.

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

TENNESSEE LLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN WELL MATER(Total)

PCI/L - 0.037 BQ/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET <<O.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE Al.ABAMA REPORTING PERIOD: 1997 TYPE AND LOWER LIHIT ALL CONTROL NUHBER OF TOTAL NUMBER OF . INDICATOR LOCATIONS LOCATION WITH. HIGHEST ANNUAL MEAN LOCATIONS NONROUI'INE OF ANALYSIS DETECTION MEAN (F) NAHE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE . DISTANCE AND DIRECT ION RANGE RANGE HEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAHHA SCAN (GELI) 26 BI-214 2.DOE+01 2.65E+01( 3/ 13) BFN WELL ¹6 2.65E+01( 3/ 13) 3.08E+02( 13/ 13) 2.12E+0'I- 3.03E+01 0.02 HILES W 2.12E+01- 3.03E+01 2.10E+02- 4.06E+02 PB-214 2.DOE+01 2.36E+01( 1/ 13) BFN WELL ¹6 2.36E+01( 1/ 13) 3.13E+02( 13/ 13) 2.36E+01- 2.36E+01 0.02 HILES W 2.36E+01- 2.36E+01 2.12E+02- 4.28E+02 TRITIUM 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 HEASUREHEN'IS ONLY. FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TENNESSEE VALLEY AUTHORITY EHVIRONMENTAL RADIOLOGICAL MONITORING AND IHSTRUMEH'IATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN GAME FISH (CRAPPIE OR LARGEHOUTH BASS)

PCI/GH - 0.037 BQ/G (DRY WEIGHT)

NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1997 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST AHHUAL MEAN LOCATIOHS NONROUT INE 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 HOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 4 BI-214 1.00E-01 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 1 ~ 19E-O'I( 1/ 2)

TRM 275-349 1.19E-01. 1.19E-D'1 cs-137 3.00E-02 6.19E-02( 1/ 2) WHEELER RES 6.19E-02( 1/ 2) 4.70E-02( 1/ 2) 6.19E-02. 6.19E-02 TRM 275-349 6.19E 6.19E-02 4.70E 4.70E-02 K-40 4.00E-01 1.41E+01( 2/ 2) WHEELER RES 1.41E+01( 2/ 2) 1.48E+01( 2/ 2) 1.40E+01- 1.41E+01 TRH 275-349 1.40E+01- 1.41E+01 1.41E+01- 1.55E+01 NOTE: 1. NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

HOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE, MEASUREMENTS AT SPECIFIED LOCATIONS IS IHDICATED IN PARENTHESES (F).

TENNESSEE LLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATION MESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH COMMERCIAL FISH (SMALLMOUTH BUFFALO OF CHANNEL CATFISH FLESH)

PCI/GM - 0.037 BQ/G (DRY HEIGHT)

NAME OF FACILITY: BROWS FERRY NUCLEAR PLANT DOCKET NO.: 50.259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAMA REPORTIHG PERIOD: 1997 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL MEAN LOCATIONS NONRGUT INE OF ANALYSIS DETECTIOH MEAN (F) NAME HEAN (F) HEAN (F) REPORTED PERFORHED (LLD) RANGE D IS'TANCE AND DIRECTION RANGE RANGE HEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAHHA SCAN (GELI)

BI-214 1.00E-01 1.86E-01( 2/ 2) WHEELER RES 1.86E-01( 2/ 2) 1.30E-01( 1/ 2)

'1.68E 2.04E-01 TRH 275-349 1.68E 2.04E.01 1.30'E 1.30E-01 K-40 4-OOE 01 8.02E+00( 2/ 2) MHEELER RES 8.02E+00( 2/ 2) 1.19E+01( 2/ 2) 7.14E+00- 8.90E+00 TRM 275-349 7.14E+00- 8.90E+00 9.59E+00- 1.42E+Ol NOTE: 1. NOMIHAL L(S LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1.

HOTE: 2 ~ MEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY. FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PAREHTHESES (F).

TENNESSE~EY AUTHORITY ENVIRONHENTAL RADIOLOG~<ONITORING AND INSTRUHENTATION MESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SEDIHENT PCI/GH - 0.037 BQ/G (DRY HEIGHT)

HAHE OF FACILITY: BRSINS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAMA REPORTING PERIOD: 1997 TYPE AND LONER LIHIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION llITH HIGHEST ANNUAL HEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAHE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAHMA SCAN (GELI)

AC-228 2.50E-01 1.24E+00( 4/ 4) TRM 293.7 'I.35E+00( 2/ 2) 1 '9E+00( 2/ 2) 8.61E 1.40E+00 BFH DISCHARGE 1.31E+00- 1.40E+00 9.91E 1.20E+00 BE-7 2.50E-01 4.48E-01( 3/ 4) TRH 293.7 4.77E-01( 2/ 2) 4.02E-01( 2/ 2) 2.66E 6.89E-01 BFN DISCHARGE 2.66E 6.89E-01 3.94E 4.10E-01 81-212 4.50E-01 1.25E+00( 4/ 4) TRH 293.7 1.34E+00( 2/ 2) 1.09E+00( 2/ 2) 8.43E 1.48E+00 BFN DISCHARGE 1.28E+00- 1.40E+00 9.08E 1.28E+00 81-214 1.50E-01 8.89E-01( 4/ 4) TRH 293.7 9.65E-01( 2/ 2) 8.00E-01( 2/ 2) 7.03E 1.08E+00 BFN DISCHARGE 8.45E 1.08E+00 7.34E 8.65E-01 C0.60 3.00E-02 8.28E-02( 3/ 4) TRH 288.78 1 ~ 16E-01( 1/ 2) 3.02E-02( 'I/ 2) 5.90E 1.16E-01 1.16E 1.16E-01 3.02E 3.02E-02 CS-134 3.00E-02 6.00E-02( 1/ 4) TRM 293.7 6.00E-02( 1/ 2) 2 VALUES < LLD 6.00E 6.00E-02 BFN DISCHARGE 6.00E 6.00E-02 CS-137 3.00E-02 4.04E-01( 4/ 4) TRH 293.7 4.58E-01( 2/ 2) 2.05E-01( 2/ 2) 1.37E 5.62E-01 BFN DISCMARGE 4.'14E 5.02E-01 1.08E 3.03E-01 K-40 7.50E-01 1.22E+01( 4/ 4) TRH 288.78 1.29E+01( 2/ 2) 9.76E+00( 2/ 2) 1.06E+0'I- 1.39E+01 1.19E+01- 1.39E+01 7.96E+00- 1 ~ 16E+01 PB-212 1.00E-01 1.21E+00( 4/ 4) TRH 293.7 1.34E+00( 2/ 2) 1.11E+00( 2/ 2) 7.92E 1.40E+00 BFN DISCHARGE 1.28E+00- 1.40E+00 9.87E 1.23E+00 PB-214 1.50E-01 9.93E-01( 4/ 4) TRM 293.7 1.09E+00( 2/ 2) 8.43E-01( 2/ 2) 7.41E 1.21E+00 BFN DISCHARGE 9.66E 1.21E+00 7.83E 9.04E-O'I RA-224 7.50E-01 1.41E+00( 2/ 4) TRM 293.7 1.45E+00( 1/ 2) 1.34E+00( 2/ 2) 1.38E+00- 1.45E+00 BFN DISCHARGE 1.45E+00- 1.45E+00 1.15E+00- 1.52E+00 RA-226 1.50E-01 8.89E-01( 4/ 4) TRM 293.7 9.65E-01( 2/ 2) 8.00E-01( 2/ 2) 7.03E 1.08E+00 BFN DISCHARGE 8.45E 1.08E+00 7.34E 8.65E-01 TL-208 6.00E-02 3.94E-01( 4/ 4) TRH 293.7 4.38E-01( 2/ 2) 3.49E-01( 2/ 2) 2.83E 4.45E-01 BFN DISCHARGE 4.31E 4.45E-01 3.03E 3.95E-01 ZH-65 5.00E-02 6.63E-02( 1/ 4) TRH 293.7 6.63E-02( 1/ 2) 2 VALUES < LLD 6.63E 6.63E-02 BFN DISCHARGE 6.63E 6.63E-02 SR 89 1.60E+00 4 VALUES < LLD 2 VALUES < LLD SR 90 4.00E.01 4 VALUES < LLD 2 VALUES < LLD NOTE: 1. NOHINAL LSIER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

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

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

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET HO.: 50-259,260,296 LOCATION OF FACILITY: I.IMESTOHE ALABAMA REPORTING PERIOD: l997 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCAT IOHS HONROUT I HE 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) 4 BI -214 5.00E-01 2.43E+00$ 2/ 2) DOWNSTREAM LOCATION 2.43E+00( 2/ 2) 5 52E+00( 2/ 2) 1.12E+00- 3.75E+00 DOWNSTREAM 1.12E+00- 3.75E+00 1.87E+00- 9.17E+00 PB-214 1.00E-01 2.24E+00( 2/ 2) DOWNSTREAM LOCATION 2.24E+00( 2/ 2) 5.40E+00( 2/ 2) 9.47E 3.54E+00 DOWHSTREAM 9.47E-Oi" 3.54E+00 1.81E+00- 8.98E+00 ZN-65 4.00E-01 7.84E-01( 1/ 2) DOWNSTREAM LOCATION 7.84E-01( 1/ 2) 2. VALUES < LLD 7.84E 7.84E-01 DOWNSTREAM 7.84E 7.84E-01 NOTE: 1. NOHINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

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

Direct Radiation Levels Browns Ferry Nuclear Plant 20 0

15 E

10 1975 1980 1985 1990 1995 2000 Calendar Year

~On-Site ~OffZite

Direct Radiation levels by Thermoluminescence Dosimetry Watts Bar Nuclear Plant 25 Initial WBNP operation in

~on-site (within 2 miles) January, 1996 m 20 Q

~off-site (more than 2 miles)

~ 15 E

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 0.15 O Preoperational Average 0.10 I

I I

I I

I 0.05 I I

I I

o-o-0+~+-H-o-e-e-o-0-e-e 0.00 1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year

~ Indicator 8 Control

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

~ 10 Preoperational Average 0

1965 1970 1975 1980 1985 1990 1995 2000

~ Calendar Year Indicator o Control

Annual Average Cs-1 37 Activity in Soil - BFNP Initial plant operation in August, 1973 0

L 2 D)

O 0

Q.

0 1 Preoperational Average 1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year

~ Indicator ~ Control

Annual Average Gross Beta Activity in Surface Water - BFNP o 4 Preoperational Average O

tL I

I I I Initial Plant I Note: no gross beta Operation in measurements were August, i 973,'

made in 1978 I

I 1965 1970 1975 1980 1985 1990 1995 2000

~ Calendar Year Indicator o Control

Annual Average Gross Beta Activity in Drinking Water -BFNP Initial plant operation in August, 1973 4

I CD O I Preoperational Aerage CD Q. I I I I

I I

1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year

~ Indicator o Control

Annual Average Cs-137 Activity Crappie or Largemouth Bass - BFNP 0.5 initial plant operation in August, 1973 I

0.4 IQ I

I E I I

I 0.3 Preoperational Aerage O

Q.

0.2 0.1 0.0 1965 1970 1975 1980 1985 1990 1995 2000

~ Calendar Year Dow nstream o Upstream

Annual Average Cs-137 Activity in Fish Smallmouth Buffalo or Channel Catfish Flesh-BFNP 0.25 Initial plant operation in August, 1973 0.20 E

tlat 0.15 O

Preoperational Average 0.10 0

+ 0.05 0.00 0- 0-0-0-~-

1965 1970 1975 1980 1985 1990 1995 2000

~ Calendar Year Dow nstream ~ Upstream

0 Annual Average Cs-1 37 Activity in Sediment - BFNP Initial plant operation in August, 1973 E

C$

Ul 3 O

Q.

Preoperational Average 0

. - -- -0%-0~A)~~

1965 1970 1975 1980 1985 1990 1995 2000

~ Calendar Year Dow nstream ~ Upstream

v Annual Average Co-60 Activity in Sediment - BFNP 0.8 Initial plant operation in August, 1973 0.6 I

E I I

I I

I O

a 0.4 I Preoperational Average I

I I

0.2 0.0 1965 1970 CD-1975 0- . ~

1980 1985

'~

1990 O~ o o s 1995 2000

~ Calendar Year Dow nstream ~ Upstream

r