ML18033B685

Annual Radiological Environ Operating Rept 1990. W/910424 Ltr

ML18033B685
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1990
From:	Carier P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9104300060
Download: ML18033B685 (237)

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ACCELERATED DIS UTION DEMONS TION SYSTEM a

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9104300060 DOC.DATE: 90/12/31 NOTARIZED: NO DOCKET g FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION CARIER, P. P. Tennessee Valley Authority R RECIP.NAME RECIPIENT AFFILIATION ~G @~-

SUBJECT:

"Annual Radiological Environ Operating Rept 1990." W/910424 ltr. D DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR TITLE: Environmental Monitoring Rept (per Tech ENCL pecs)

J SIZE: (

NOTES:1 Copy each to: B.Wilson,S. BLACK 05000259

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1 Copy each to: S.Black,B.WILSON 05000260 A 1 Copy each to: S. Black,B.WILSON 05000296 D

RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL KREBS,M. 3 3 HEBDON,F 1 1 ROSS,T. 1 1 INTERNAL: ACRS 1 1 1 1 NRR/DREP/PRPB11 2 2 FILE 1 1 RGN2 DRSS/RPB 1 1 RGN2 02 1 1 EXTERNAL EG&G S IMPSON i F 2 2 NRC PDR 1 1 NOTES: 5 5 D

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 20

Tennessee Valley Authority. Post Office Box 2000. Decatur, Afabama 35609 APR p4 III'.S.

Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) FOR 1990 In accordance with the requirements of BFN's Radiological Effluent Technical Specification Manual, enclosed is a copy of the BFN AREOR. The report includes the following information:

1. Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period,

2. Results of land use censuses,

3. Summarized and tabulated results of the radiological environmental samples taken during the reporting period, in the format of Regulatory Guide 4.8,

4. Summary description of the radiological monitoring program,

5. A map of sampling locations keyed to a table giving distances and directions from one reactor, and

6. Results of TVA's participation in the Interlaboratory Comparison

'Program.

There are no commitments made in this submittal or in the AREOR.

9104300060 901231 PDR ADOCK',05000259 R " '""" PDR

U.S. Regulatory Commission hPR p4 Nl If you have any questions, please telephone Patrick P. Carier, Site Licensing at (205) 729-3566.

Very truly yours, TE SEE VALLEY AUTHORITY Patrick P. Carier, Manager Site Licensing cc (Enclosure):

Ms. S. C. Black, Deputy Director Project Directorate II-4 U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike, Rockville, Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

TERIA'SSEE VALLEYAUTHORITY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT BROWNS FERRY NUCLEAR PLANT 1990 9104300060 CHEMISTRY AlVD RADIOLOGICALSERVICES

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT BRONNS FERRY NUCLEAR PLANT 1990 TENNESSEE VALLEY AUTHORITY NUCLEAR OPERATIONS SERVICES CHEMISTRY AND RADIOLOGICAL SERVICES

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TABLE OF CONTENTS Table of Contents .

List of Tables ~ ~ ~ iv List of Figures . ~ ~ ~, v Executive Summary . ~ ~ o 1 Introduction ~ ~ ~ 2 Naturally Occurring and Background Radioactivi ty . ~ ~ ~ 2 Electric Power Production ~ ~ ~ 5 Si te/Plant Descri ption ~ ~ ~ 8 Environmental Radiological Monitoring Program . 10 Direct Radiation Monitoring . 14 Measurement Techniques . ~ ~ . 14 Results 15 Atmospheric Monitoring 19 Sample Collection and Analys is . 19 Results ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 21 Terrestrial Monitoring 22 Sample Collection and Analysis ~ ~ ~ 22 Results 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 24 Aquatic Monitoring 26 Sample Collection and Analysis 26 Results 28 Assessment and Evaluation . 31 Results 32 Conclusions 34 References 35 Appendix A Environmental Radiolog ical Monitoring Program and Sa'mpling Locations 40 Appendix B 1990 Program Modifications ~ ~ 53

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Appendix C Missed Samples and Analyse's . 56 Appendix D Analytical Procedures . 59 Appendix E Nominal Lower Limits of Detection (LLD) 62 Appendix F Quality Control Program . 68 Appendix G Land Use Survey . 77 Appendix H Data Tables . 83"

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LIST OF TABLES Table l Haximum Permissible Concentrations for Nonoccupational Exposure . . . . . . . . . . . . . . . . 36 Table 2 Maximum Dose Due to Radioactive Effluent Releases . . . . . . . . . . . . . . . . . . . . . . . . 37

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LIST OF FIGURES Figure l Tennessee Valley Region . . . . . . . . . . . . . . . . . 38 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Material to the Atmosphere and Lake . . . 39

EXECUTIVE

SUMMARY

Thi.s report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant in 1990.

The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels . Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of. plant operations, The vast majority of the exposures calculated from environmental samples were contributed by naturally occurring radioactive materials or from materials commonly found in the environment as a result of atmospheric nuclear weapons fallout.

Small amounts of Co-60 were found in sediment samples downstream from the plant,. This activity in stream sediment 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 a large volume of data, the results of thousands of measurements and laboratory analyses. The measurements are made to comply with regulations and to determine potential effects on public health and safety. This report satisfies the annual reporting requirements of the BFN Radiolo ical Effluent Manual. In addition, estimates of the maximum potential doses to the surrounding population are made from radioactivity measured both in plant effluents and in environmental samples. Some of the data presented are prescribed by specific requirements while other data are included which may be useful or interesting to individuals who do not work with this material routinely.

Naturall Occurrin and Back round Radioactivit Most materials in our world 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'he major types of radioactive materials found naturally in, our environment. An individual weighing 150 pounds contains about 140 grams of potassium (Reference 1). This is equivalent to approximately 100,000 pCi of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body. Naturally occurring radioactive materials have always been in our environment. Other examples of naturally occurring radioactive materials are bismuth-212 and 214, lead 212 and 214, thallium-208, actinium-228, uranium -238, uranium-235, thorium-234, radium-226, radon-222, carbon-14, and hydrogen-3 (generally called tritium). These naturally occurring radioactive materials are in the soil, our food, our drinking water,

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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 1

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 from radiation from outer space (part of natural background radiation) is about 27 mrem/year. This essentially doubles with 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 from this radioactive material also depends upon the geographical location. Most of the remainder of the natural background radiation comes from the radioactive materials within each individual's body. We absorb these materials from the food we eat which contains naturally occurring radioactive materials from 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 if the 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

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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'y evaluating the amount of radiation the U.S. population receives from each general type of radiation source. The information below is primarily adapted from References 2 and 3.

U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source Millirem/Year Per Person Natural background dose equivalent Cosmic 27 Cosmogenic 1 Terrestrial 28 In the body 39 Radon 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)

I As 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.

Significant discussion recently has centered around exposures from radon.

Radon is an inert gas given off as a result of the decay of naturally occurring radium-226 in soil. Hhen 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 average annual effective dose equivalent from radon in the United States is approximately 200 mrem/year. This estimated dose is approximately twice the average dose equivalent from all other natural 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

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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.

All paths through which radioactivity is released are monitored. Liquid and gaseous effluent monitors record the radiation levels for each release. These monitors also provide alarming mechanisms to allow for 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 I

made in surrounding areas to verify that the population is not being ex'posed to significant levels of radiation or radioactive materials.

The BFN Offsite Oose Calculation Hanual (ODCM), which is required by the plant Technical Specifications, prescribes limits for the release of radioactive effluents, as well as doses to the general public from the release of these effluents. Additional limits are set by the Environmental Protection Agency (EPA) for doses to the public.

The offsite dose due to radioactive materials released to unrestricted areas, as given in the Technical Specifications, are limited to the following:

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'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 EPA limits for the total dose to the public in the vicinity of a nuclear power plant, established in the Environmental K

Dose Standard of 40 CFR 190, are as follows:

Total body 25 mrem/year Thyroid 75 mrem/year Any other organ 25 mrem/year In addition, 10 CFR 20.106 provides maximum permissible concentrations (MPCs) for radioactive materials released to unrestricted areas. HPCs for the principal radionuclides associated with nuclear power plant effluents are presented in table l.

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SITE/PLANT DESCRIPTION Browns Ferry Nuclear Plant (BFN) is located on the north shore of Wheeler Reservoir at Tennessee River Mile 294 in Limestone County in north Alabama.

Wheeler Reservoir averages 1 to l-l/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 the center of Decatur, Alabama (figure 1). 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 si'de of the river immediately surrounding the plant. The principal crop grown in the area is cotton. At least two dairy farms are located with)n a 10-mile radius of the plant.

Approximately 2000 people live within a 5-mile radius of the plant. Th'e town of Athens has a population of about 15,000, while approximately 40,000 people live in the city of Decatur. The largest city in the area with approximately 150,000 people is Huntsville, Alabama, located about 24 miles east of'he site.

Area recreation facilities are being developed along the Tennessee River. The nearest facilities are two county parks located about 8 miles west-northwest-of the site and a commercial boat dock across the river 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.

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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. Unit 2 began commercial operation oh Parch 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 January 1977. None of the units have operated since March 1985.

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM The unique environmental concern associated with a nuclear power plant is its production of radioactive materials and radiation. The vast majority of this radiation and radioactivity is contained within the reactor itself or one of the other plant systems designed to keep the material in the plant. The retention of the materials in each level of control is achieved by system engineering, design, construction, and operation. 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 will be maximized. The environmental'adiological, monitoring program is outlined in appendix A.

There are two primary pathways by which radioactivity can move through the environment to humans: air and water (see figure 2). The air pathway can be separated into two components: the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial pathway, radioactive materials may be, deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types of samples collected in this program are designed to monitor these pathways.

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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 lists the sampling stations and the types of samples collected from each. Modifications made to the program in 1990 are described in appendix B and exceptions to the sampling and analysis schedule are presented in .

appendix C.

To determine the amount of radioactivity in the environment prior to the operation of BFN, a preoperational environmental radiological 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 o the overall program. During the 1950s, 60s, and 70s, atmospheric -nuclear weapons testing released radioactive material to the environment causing fluctuations in the natural background radiation levels. This material is the same type as that produced in the BFN reactors. Preoperational knowledge of natural radionuclide patterns in the environment perm) ts a determination, through

comparison and trending analyses, of whether the operation of BFN is impacting the environment and thus the surrounding population.

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 I

plant) are compared with those from indicator stations (near the plant) to establish the extent of BFN influence.

All samples are analyzed by the radioanalytical laboratory of TVA's Environmental Radiological Monitoring and Instrumentation Department 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.

J The sophisticated radiation detection devices used to determine the radionuclide. content of samples collected in the environment are generally quite sensitive to small amounts of radioactivity. In the field of radiation measurement, the sensitivity of the measurement process is discussed 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 I

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 complex radiation detection devices are working properly and the analysis of special samples which are included alongside routine environmental samples. In addition, samples split with the Environmental Protection Agency and the State of Alabama provide an independent verification of the overall performance of the laboratory.. A complete description of the program is presented in appendix F.

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

Radiation levels measured in the area around the BFN site in 1990 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). Hhen certain materials are exposed to ionizin'g radiation, many of the electrons which become displaced are trapped in the crystalline structure of the material, They remain trapped for long periods of time as long as the material is not heated. Nhen heated (thermo-), the electrons are released, along with a pulse of light (-luminescence). The intensity of the light,pulse is directly proportional to the 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 f

bulb. In 1989, TVA began the process of changing from the Victoreen dosimeter to the Panasonic Model UD-814 dosimeter, and completely changed to the Panasonic dosimeter in 1990. This dosimeter contains four elements consisting of one lithium borate and three calcium sulfate phosphors. The calcium sulfate phosphors are shielded by approximately 1000 mg/cm'lastic and lead to compensate for the over-response of the detector to low energy radiation.

The TLDs are placed approximately 1 meter above the ground, with three TLDs at each station. Sixteen stations are located around the plant near the site boundary, one station in each of the 16 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 Panasoni.c Model UD-'710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system, Since the calcium sulfate phosphor is much more sensitive that the lithium borate, the measured exposure is taken as the median of the results obtained from the nine calcium sulfate phosphors in three detectors.

The values are corrected for gamma response, system variations, and transit exposure, with individual gamma response calibrations for each element. The system meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 f'r environmental applications of TLDs.

Results All results are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).

The 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 I

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lies between 1 and 2 miles, the third group between 2 and 4 miles, the fourth between 4 and 6 miles, and the fifth group is made up of all stations more than 6 miles from the plant. Past data have shown that the results from all stations greater than 2 miles from the plant are essentially the same.

Therefore, for purposes of this report, all stations 2 miles or 1;ess from the plant are identified as "onsite" stations and all others are considered "offsite."

Prior to 1976, direct radiation measurements in the environment were made with a

dosimeters that were not as precise at lower exposures. Consequently, the environmental radiation levels reported in 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 Watts Bar Nuclear Plant (WBN) environmental radiological monitoring program are referenced. The WBN is a non-operating plant under construction near Spring City, Tennessee.

The quarterly gamma radiation levels determined from the TLDs deployed around BFN in 1990 are given in table H-l. The rounded average annual exposures are shown below.

Annual Average Direct Radiation Levels mR/ ear BFN WBN Onsi te Stations 69 63 Offsite Stations 61 56

The data in table H-1 indicate that the average quarterly radiation levels at the BFN onsite stations are approximately 2-4 mR/quarter higher than levels at the offsite stations. This difference is also noted at the stations at HBN and other nonoperating nuclear power plant construction sites where the average levels onsite are generally 2-6 mR/quarter higher than 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 onsi te, and the mass of concrete employed in the construction of the plant. Other undetermined influences may also play a part. These conclusions are supported by the fact that similar differences between onsite and offsite stations were measured in the vicinity of the HBN construction site.

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 1990. To reduce the seasonal variations present in the data sets, a 4-quarter moving average was constructed for each data set.

Figure H-2 presents a trend plot of the direct radiation levels as defined by the moving averages. The data follow the same general trend as the raw data, but the curves are smoothed considerably. Figures H-3 and H-4 depict the environmental gamma radiation levels measured during the construction of TVA's HBN to the present. Note that the data follow a similar pattern to the BFN data and that, as discussed above, the levels reported at onsite stations are similarly higher than the levels at offsite stations, I

All results reported in 1990 are cons1stent with d1rect* radiation levels-identified at locations which are not 1nfluenced; by the operation of BFN.-

There is no indication that BFN acttv1ties increase the background radiation levels normally observed in the areas surrounding the plant.

ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as local, perimeter, and remote. In the current program, five local air monitoring stations are located on or adjacent to the plant site in the general directions of greatest wind frequency. One additional station 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 communi ties 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 from the analysis of samples in the atmospheric pathway are presented in tables H-2 and H-3. Radioactivity levels identified in this reporting period are, consistent with background and radionuclides 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 Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch Hollingsworth and Vose LB5211 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.

l 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 foi gross beta activity about 3 days after collection to allow time 'nalyzed for the radon daughters to decay. Every 4 weeks composites of the filters from each location are analyzed by gamma spectroscopy. On a quarterly basis, all of the filters from a location are composited and analyzed for Sr-89,90.

On March 27, 1989, two monitors, one local and one remote, were equipped with a second sampler. The filters from these samplers are analyzed weekly for gross alpha and composited quarterly for analysis of transuranic isotopes.

Gaseous radioiodine is collected using a commercially available cartridge containing TEOA-impregnated charcoal. This system is designed to collect iodine in both the elemental form and as organic compounds. The cartridge is located in the same sampling head as the air particulate filter and is downstream of the particulate filter. The cartridge is changed at the same time as the particulate filter and samples the same volume of air. Each is analyzed for I-131. If activi ty above a specified limit is 'artridge detected, a complete gamma spectroscopy analysis is performed.

Rainwater is collected by use of a collection tray attached to the monitor i building. The collection tray is protected from debris water drains from the tray, it is collected in one of by a screen two cover.

5-gallon )ugs inside As l the monitor buil'ding. A 1-gallon sample is removed from the container every 4

)0 weeks.

if 'the Any excess air particulate water is discarded.

samples Samples are he/d to be analyzed only indicate the presence of elevated activity 5

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levels or if fallout is expected. For example, rainwater samples were analyzed during the period of fallout following the accident at Chernobyl in 1986.

Results The results from the analysis of air particulate samples are summarized in table H-2. Gross beta activity in 1990 was consistent with levels reported in previous years. The average level at both indicator and control stations was 0.022 pCi/m'. The annual averages of the gross beta activity in air particulate filters at these stations for the years 1968-1990 are'presented in figure H-5. Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981.

Evidence of a small increase resulting from the Chernobyl accident can also be seen in 1986. These patterns are consistent with data from monitoring programs'onducted by TVA at nonoperating nuclear power plant construction sites.

Only natural radioacti ve materials were identified by the monthly gamma-spectral analysis of the air particulate samples. No fission or activation products were found at levels greater than the LLDs. As shown in table H-3, iodine-131 was detected in thirteen charcoal canister samples at levels slightly higher than the nominal LLD. Since the half-life of I-131 is only about 8 days and the plant has not operated in over 5 years, this activity could not be, from BFN.

rainwater samples from the vicinity of

)0 this No BFN were analyzed during reporting period.

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TERRESTRIAL MONITORING Terrestrial 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 I

where dairy cattle are grazing. Nhen the cow ingests the radioactive material, some of it may be transferred to the milk and consumed by humans who drink the milk. Therefore, samples of milk, vegetation, soil, and food crops are collected and analyzed to determine the potential impacts from exposure to this pathway. The results from the analysis of these samples are shown in tables H-4 through H-13, A land use survey,is conducted annually to locate milk producing animals and gardens within a 5-mile, radius of the plant, Only one dairy farm is located in this area; however, 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 3 miles of the plant. The results of the 1990 land use survey are presented in appendix G.

Sam le Collection and Anal sis Milk samples are purchased every two weeks from two dairies within 7 miles of the plant 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 performed on each sample and Sr-89,90-analysis is performed every 4 weeks.

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Samples of vegetation are collected every 4 weeks for I-131 analysis. The samples are collected from one farm which previously produced milk, from one control dairy farm, and from one control air monitor location. The samples are collected by cutting or breaking enough vegetation to provide between 100 and 200 grams of sample. Care is taken not to include any soil with the vegetation. The sample is placed in a container with 1650 ml of 0.5 N NaOH for transport back to the radioanalytical laboratory. A second sample of between 750 and 1000 grams is also collected from each location. After drying and grinding, this sample is analyzed by gamma spectroscopy. 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.

After drying and grinding, the sample is analyzed by gamma spectroscopy. Hhen the gamma analysis is complete, the sample is ashed and analyzed for Sr-89,90 'nalyses for transuranic isotopes are also performed on samples from the two monitoring stations with the second air samplers.

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 1990 samples of cabbage, corn, green beans, potatoes, and tomatoes were collected from local vegetable gardens. In addition, samples of apples and beef were also obtained from the area. The edible portion of each sample is prepared as if it were to be eaten and is analyzed by gamma spectroscopy.

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After drying, grinding, and ashing, the sample is analyzed for gross beta ac t i v i ty.

Results The results from the analysis of milk samples are presented in table H-4. No radioactivity which could be attributed to BFN was identified. All I-131 results were less than the established nominal LLD of 0.2 pCi/liter".

Strontium-90 was found in a little over half of the samples. These levels are consistent with concentrations measured in samples collected prior to plant operation and with concentrations reported in milk as a result of fallout from atmospheric nuclear weapons tests (reference 1). The average Sr-90 concentration reported from both indicator and control stations was approximately 2.6 pCI/liter. By far the predominant isotope reported in milk samples was the, naturally occurring K-40. An average of approximately 1300 pCi/liter of K-40 was identified in all milk samples.

I Similar results were reported for vegetation samples (table H-5). All I-131 values were less than the nominal LLD. Average Cs-137 concentrations were 33.4 and 25.7 pCi/kg for indicator and control stations, respectively.

Strontium-90 levels averaged 93.5 pCi/kg from indicator stations and 78.1 pCi/kg from control stations. Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7.

The only fission or activation product identifi ed in soil samples was Cs-137 .

The maximum concentration of this isotope was approximately 0.4 pCi/g which is consistent with levels previously reported from fallout. All Sr-89,90 values I

(g

were less than the nominal LLDs. All other radionuclides reported were naturally occurring isotopes (table H-6).

Analyses for transuranic isotopes (Am-241; Pu-238; Pu-239,240; and Cm-244) were performed for the first time in 1989. The procedures employed are still in the developmental stage. The analytical yields were very low and the values obtained imprecise. The results generally agreed with the concentrations reported by the Electric Power Research Institute (EPRI) in Reference 4. The EPRI report concludes that essentially all of the radionuclides in soils from around the nuclear power plants participating in the study (including BFN) were of fallout origin and that the variations in concentrations were a function of soil texture, soil permeability, and/or disturbances of the soil surface.

Only the naturally occurring K-40 was identified in food crops. 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. Gross beta concentrations for all indicator samples were consistent with the control values. Analysis of these samples indicated no contribution from plant activities. The results are reported in tables H-7 through H-13.

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A UATIC MONITORING Potential exposures from the liquid pathway can occur from drinking water, ingestion of f)sh and clams, or from 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, and bottom sediment. Samples from the reservoir are collected both upstream and downstream from the plant.

Results from the analysis of aquatic samples are presented in tables H-14 through H-20. Radioactivity levels in water, fish and clams were consistent with background and/or fallout levels previously reported. The presence of Co-60, Cs-134 and Sr-90 was identified in sediment samples; however, the projected exposure to the public from this medium is negligible.

Sam le Collection and Anal sis Samples of surface water are collected from the Tennessee River using automatic sampling pumps from two downstream stations arid one upstream station. A timer turns on the pump approximately once every hour. The line is flushed and a. sample collected into a composite jugs A 1-gallon sample is removed from the composite jug every four 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 Sr-89,90 and tritium.

Samples are also collected by an automatic sampling pump 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. At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source. These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity. A quarterly composite sample from each station is analyzed for Sr-89,90 and tritium. The sample collected by the automatic pumping device is taken 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 al,so considered as a control sample for drinking water.

I A groundwater well onsite is equipped with an automatic water sampler, however, power to this well was not available during 1990. Hater is also collected from a private well in an area unaffected by BFN. Samples from the private well are collected every 4 weeks and analyzed by gamma spectroscopy.

A quarterly composite sample is analyzed for tritium, Samples of commercial and game fish species are collected semiannually from each of two reservoirs: the reservoir on which the plant is located (Hheeler Reservoir) and the upstream reservoir (Guntersville Reservoir), The samples are collected using a combination of netting techniques and electrofishing.

Most of the fish are filleted, but one group is processed whole for analysis.

After drying and grinding, the samples are analyzed by gamma spectroscopy.'27-

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When the, gamma analysis is completed, the sample is ashed and analyzed for gross beta activity.

Bottom sediment is collected semiannually from selected Tennessee River Nile (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.

Samples of Asiatic clams are collected from one location below the plant and one location above the plant. The clams are usually collected in the dredging or diving process with the sediment. Enough clams are collected to produce approximately 50 grams of wet flesh. The flesh is separated from the shells, and the dried flesh samples are analyzed by gamma spectroscopy. Sufficient quantities of clams to provide a sample are becoming more and more difficult to find, Results All radioactivity in surface water samples was below the LLD except the gross beta activity and trace amounts of Sr-89 in one sample and tritium in one of the upstream control samples. With a half-life of approximately 60 days, Sr-89 cannot be present in the environment as a result of plant operations or previous nuclear weapons testing. The apparent identification of Sr-89 is an artifact of the calculational process and the low concentrations the laboratory is attempting to detect. These results are consistent with previously reported levels. trend plot of the gross beta activity in lo A

surface water samples from 1968 through 1990 is presented in figure H-6. A summary table of the results for this reporting period is shown in table H-14.

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ASSESSMENT AND EVALUATION Potential doses to the public are estimated from measured effluents using computer mode)s. 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 "maximum" 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 from the Tennessee river, eating fish caught in the Tennessee River, and direct exposure to radioactive material due to activities on the banks of the river (recreational activities). Oata 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.

Nhenever possible, data used in the dose calculation are based on specific conditions for the area.

Io BFN

For gaseous effluents, the public can be exposed to radiation from seve'ral sources: direct radiation from the radioactivity 1n the air, direct radiation from radioactivity deposited on the ground, inhalation of radioactivity in the air, ingestion of vegetation which contains radioactivity deposited from the atmosphere, and ingestion of milk or meat. from animals which=consumed vegetation containing deposited radioactivity. The concentrations of radioactivity in the air and the soil are estimated by computer models which use the actual meteorological conditions to determine the distribution of the effluents in the atmosphere. Again, as many of the parameters as possible are based on actual site-specific data.

Results The estimated doses to the maximum exposed individual due to radioactivity released from BFN in 1990 are presented in table 2. These estimates were made using the concentrations of the liquids and gases measured at the effluent monitoring points. Also shown are the technical specification 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 2 is 0.09 mrem/year, or 3 percent of the limit. The maximum organ dose equ1valent from gaseous effluents is 0.003 mrem/year. This represents less than O.l percent of the ODCM 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 "Semiannual Radioactive Effluent Release Reports."

As stated earlier in the report, the estimated increase in radiation dose l

equivalent to the genera1 public resulting from the operation of" BFN is trivial when compared to the dose from natural background radiation.

The results from each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences from the plant.

During this report period, Co-60, Cs-134, Cs-137, and Sr-90 were seen in aquatic media. The distribution of Cs-137 in sediment is consistent with fallout levels identified in samples both upstream and downstream from the plant during the preoperational phase of the monitoring program. Co-60, Cs-134, and Sr-90 were identified in sediment samples downstream from the plant in concentrations which would produce no measurable increase in the dose to the general public. No increases of radioactivity have'een seen in water samples.

Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media evaluated include, but are not limited to, air, milk, food products, drinking water, and fish. Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control stations. Greater than 95 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 from nuclear weapons testing. Concentrations of Sr-90 and Cs-137 are consistent with levels measured in TVA's preoperational environmental radiologic'al monitoring programs.

Conclusions It is concluded from the above analys.is of the environmental sampling results and from the trend plots presented in appendix that the exposure to members

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the genera1 public which may have been attributable to BFN is negligible The radioactivity reported herein is primarily the result of fallout or natural background radiation. Any activity which may be present as a result of plant operations does not represent a significant contribution to the exposure of members of the public.

I Radionuclides of the types produced by nuclear power plant operations were identified in sediment samples. The materials identified were Cs-137, Co-60, and Cs-134. The average levels of Cs-137 were 0.69 pCi/g in downstream samples and 0.21 pCi/g upstream. The Cs-137 concentration at downstream

'his stations is approximately triple the activity in upstream samples.

same relationship was reported from these stations during the preoperational phase of the monitoring at BFN, indicating that the levels reported herein are probably not the result of BFN operations.

Cobalt-60 concentrations in downstream samples averaged 0.06 pCi/g. Nhi le no Co-60 was identified in upstream samples, concentrations from upstream stations averaged 0.03 pCi/g in 1989. The maximum concentration downstream was 0.10 pCi/g. Cesium-134 concentrations in upstream samples were all below the LLO. Levels in downstream samples averaged 0.02 pCi/g, with a maximum of 0.03 pCi/g. A realistic assessment of the impact to the general public from this activity produces a negligible dose equivalent. Results from the analysis of sediment samples are shown in table H-19.

Only naturally occurring radioisotopes were identified in clam flesh samples.

The results are presented in table H-20.

I For public water, average gross beta activity was 3.0 pCi/liter at the downstream stations and 3.1 pCi/liter at the control stations. The results are shown in table H-15 and a trend plot of the gross beta activity in drinking Hater from 1968 to the present is presented in figure H-7.

As noted in appendix C, no indicator well water samples were collected in 1990. Concentrations of fission and activation products in control groundwater samples were all below the LLDs. Only naturally occurring radon decay products (Bi-214 and Pb-214) and trace indications of Sr-89 were identified in these samples. Bismuth-214 concentrations averaged 700 pCi/liter (range 215 to 1012 pCi/liter) and lead-214 concentrations averaged 684 pCi/li.ter (range 235 to 981 pCi/liter). As noted above, the identification of Sr-89 in environmental samples is an artifact of the calculational process.

Cesium-137 was identified in three fish samples. The downstream samples averaged 0.04 pCi/g while the upstream sample averaged 0.1 pCi/g. The only other radioisotope found in fish was the naturally occurring K-40. These values ranged from 5.2 pCi/g to 16.0 pCi/g. The maximum gross beta activity measured in downstream samples was 40.2 pCi/g, while the maximum value in upstream samples was 35.6 pCi/g. The results are summarized in tables H-16, H-17, and H-18. Since the concentrations downstream are essentially equivalent to the upstream levels, the Cs-137 activity is probably a result of fallout or other upstream effluents rather than activities at BFN.

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

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

September 1987.

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

4. Electric Power Research Institute, Report No. EPRI EA-2045, Project 1059, "Transuranium and Other Long-Lived Radionuclides in the Terrestrial Environs of Nuclear Power Plants," September 1981.

I Table 1 MAXIMUM PERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE MPC In Hater In Air

~C> gC> /m"

/1',000 Gross beta 100 3,000,000 200,000 Cs-137 20,000 500 Ru-103,106 10,000 200 Ce-144 10,000 100 2r-95 Nb-95 60,000 1,000 Ba-140 La-140 20,000 1,000 I-131 300 100 Zn-65 100,000 2,000 Mn-54 100,000 1,000 Co-60 30,000 300 Sr-89 3,000 300 Sr-90 30 300',000,000 Cr-51 80,000 Cs-134 9,000 400 Co-58 90,000 2,000

• 1 pCi '.7 x 10 'q..

Source: 10 CFR, Part 20, Appendix 8, Table II.

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Table 2 Maximum Dose due to Radioactive Effluent Releases Browns Ferry Nuclear Plant 1990 mrem/year Li uid Effluents 1990 NRC Percent of EPA Percent of

~Te Dose Limi t NRC Limit Limi t EPA Limit Total Body 0.09 3.0 25 0.4 Any Organ 0.14 10 1.4 25 0.6 Gaseous Effluents 1990 NRC Percent of EPA Percent of

~Te Dose Limit NRC Limit Limi t EPA Limit Noble Gas 0.0 10 N/A 25 N/A (Gamma)

Noble Gas 0.0 20 N/A 25 N/A (Beta)

Any Organ 0.003 0.020 25 0. 012 I'

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Figure 2 ENVIRQMNENTAL EXPOSURE PATH%/AYS QI" MAN KllJB TQ RHLISAHHH QF RAQIQAC TISH MATERIAI TQ THE ATMQBPHERE AND LAKE.

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Diluted By Atmosphere Airborne Releases Plume Exposure liquid Releases Diluted By l.ake AnImals Consumed By Man (Milk,Ileat) Shoreline Exposure Consumed By Animals Drinking Nater 8 0 Fish Vegetation Uptake From Soil I

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APPENDIX A ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM AND SAMPLING LOCATIONS 40

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Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Honitoring Program'xposure Pathway Number of Samples and Sampling and Type and Frequency n 1 1 AIRBORNE Particulates Five samples from locations Continuous sampler operation Parti cul ate sampler.

(in different sectors) at or with sample collection as Analyze for gross beta near boundary site (LH-1, LH-2 required by dust loading but radioactivity greater than LH-3, LH-4, LH-6 ~ and LH-7) at least once per 7 days or equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.

Two samples from control Perform galena isotopic locations greater than analysis on each sample 10 miles from the plant when gross beta activity (RH-1 and RH-6) is greater than 10 times the average of control Three samples from locations samples. Perform gamma in communities approximately isotopic analysis on 10 miles from the plant composite (by location)

PH-1, PH-2, and PH-3) sample at least once per 31 days. Analyze for Sr-89,90 content of quarterly composite (by location) at least once per 92 days.

Radioiodine Same loca:ions as air Continuous sampler operation I-131 every 7 days particulates wi th charcoal cani ster collection at least once per 7 days Rainwater Same location as air Composite sample at least Analyzed for gaama nuclides particulate once per 31 days only if radioactivity in other media indicates the presence of increased levels of fallout

I Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Honitoring Program'xposure Pathway Number of Samples and Sampling and Type and Frequency n m F f Soil Samples from same locations Once every year Galena scan, Sr-89, Sr-90 once as air particulates per year Direct Two or more dosimeters=placed At least once per 92 days Gamma dose once per 92 days at locations (in different sectors) at or near the site boundary in each of the 16 sectors Two or more dosimeters placed At least once per 92 days Gamna dose once per 92 days at 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 WATERBORNE Surface Water One sample upstream (TRH 305.0) Collected by automatic Gross beta and gamma scan on One sample immediately down- sequential-type sampler 4-week composite. Composite stream of discharge (TRH 293.5) with composite sample taken for Sr-89, Sr-90, and tritium One sample downstream from at least once per 7 days at least once per 92 days plant (TRH 285.2)

Drinking Water One sample at the first Collected by automatic Gross beta and gamma scan on potable surface water sequential-type sampler weekly composite. Composite supply downstream from the with composite sample taken for Sr-89, Sr-90, and tritium plant (TRH 282.6) at least once per 7 days at least once per 92 days

Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Honitoring Program'xposure Pathway Number of Samples and Sampling and Type and Frequency 1

Drinking Water Two additional samples of Grab sample taken at Gross beta and ganja scan on (Continued) potable surface water down- least once per 31 days each sample. Composite stream from the plant for Sr-89, Sr-90, and tritium (TRH 274.9 and TRH 259.5) at least once per 92 days One sample at a control location (TRH 306)

One additional sample at Collected by automatic a control location sequential-type sampler (TRH 305) with composite sample taken at least once per 7 days Ground Water One sample adjacent to the Collected by automatic Galena scan on each plant (Well No. 6) sequential-type sampler composite. Composite for with composite sample taken Sr-89, Sr-90, and tritium at least once per 31 days at least once per 92 days One sample at a control Grab sample taken at Gamma scan on each location upgradient from least once per 31 days sample. Composite for the plant, (Farm L) Sr-89, Sr-90, and tritium at least once per 92 days A/VATIC Sediment Two samples upstream from At least once per 184 days Ganja scan, Sr-89 and Sr-90 discharoe point (TRH 297.0 analyses and 307.52)

One sample in immediate At least once per 184 days Galena scan, Sr-89 and Sr-90 downstream area of discharge analyses point (TRH 293.7)

Two additional samples downstream from the p'lant (TRH 288.78 and 277.98)

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Table A-1 BROGANS FERRY NUCLEAR PLANT Environmental Radiological Honitoring Program~

Exposure Pathway Number of Samples and . Sampling and Type and Frequency n r 1 1 i 1 i INGESTION Hilh At least 2 samples from At least once per 15 days Gamma scan and I-131 on each dairy farms in the immediate whe'n animals are on pasture; sample. Sr-89 and Sr-90 at least vicinity of the plant (Farms at least once per 31 days once per 31 days B and Bn) at other times At least one sample from control location (Farm Be and/or GL)

Fish Three samples representing At least once per 184 days Gross beta and ganja scan at conmercial and game species least once per 184 days on in Guntersville Reservoir edible portions above the plant Three samples representing commercial and game species in Hheeler Reservoir near the plant.

Clams One sample downstream from At least once per 184 days Gamma scan on flesh only the discharge One sample upstream from the plant (No permanent stations established; depends on location of clams)

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Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Honitoring Program'xposure of Type and Frequency llSampling Pathway Number Samples and and

~r~mQe 1 i Fruits and Vegetables Samples of food crops such as At least once per year at Ganma scan on edible portion corn, green beans, tomatoes, time of harvest and potatoes grown at private gardens and/or farms in the immediate vicinity of the plant One sample of each of the same foods grown at greater than 10 miles distance from the plant Vegetation Samples from farms Once per 31 days I-131, gamaa scan once per 31 producing milk but not days providing a milk sample (Farm T)

Control samples from one remote air monitor station (RH-1) and one control dairy (Farm GL)

a. The sampling program outlined in this table is that which was in effect at the end of 1990.

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

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

d. The surface water control sample shall be considered a control for the drinking water sample.

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Table A-2 BROHNS FERRY NUCLEAR Pl.ANT Env/ronmental Radiological Monitoring Program Sampling Locations Map Approximate Indicator (I)

Location Distance ol Samples Number'tation Sector (mi 1 es) Control (C) Collected" 1 PM-1 NW 13.8 I AP,CF,R,S PM-2 NE 10.9 I AP,CF,R,S 3 PM-3 SSE 8.2 AP,CF,R,S 4 LM-7'M-1 W 2.1 I AP,CF,R,S, 5 W 31.3 C AP,CF,R,S,V'P,CF,R,S 6 RM-6 E 24.2 C 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 LM-4 NNH 1.7 I AP,CF,R;S, ll LM-6 SSW 3.0 I AP,CF,R;S, 12 Farm B NNH 6.8 I M, 13 Farm Bn N 5.0 I M, 14 Farm ENE 5.9 I H 18 L'arm GL WSH 35.0 C M,V

'22 Well No. 6 NH 0.02 I H 23 TRM'82.6 11.4~ I PH 24 TRM 306.0 12.0~ C PH 25 TRM 259.6 34.4 I PH 26 TRM 274.9 19.1~ I PH 27 TRM 2&5.2 8,8'.5g I SH 28 TRM 293.5 I SH 29 TRM 305.0 11.0~ Ch SH 30 TRM 307.52 13.52~ C CL,SD 31 TRM 293.7 0.3~ I CL,SD 32 TRM 288.78 5.22'6.029 I CL,SD 33 TRM 277.98 I CL,SD 34 Farm Be NH 28.8 C 36 Farm T HNW 3.2 I V 37 TRM 297.0 3.0 C SD 10 I

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Table A-2 BROHNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations (Continued)

Hap Approximate Indicator (I)

Location Distance or Samples Number'tation Sector (miles) Control (C)

Collected'heeler Reservoir'TRM F,CL 275-349)

Guntersville Reservoir'RM (349-424)

a. See figures'.A-l, A-2, and A-3.

b. Sample Codes:

AP - Air particulate filter R = Rainwater CF Charcoal filter (Iodine) S Soil CL = Clams SD = Sediment F - Fish SN = Surface water M = Milk- V = Vegetation PN Public drinking water N Nell water

c. Vegetation added March 26, 1990.

d. Dairy out of business. Last milk sample collected October 9, 1990.

e. 'TRM = Tennessee River Mile

f. Miles from plant discharge (TRH 294).

g. Also used as a control for public water.

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Table A-3 SROHNS FERRY NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) Locations Map Approximate Onsite (On)'r Location Distance Number' Station Sector (miles) Offsite (Off)

NH-3 NH 13.8 Off 2 NE-3 NE 10.9 Off 3 SSE-2 SSE 8.2 Off 5 H-3 31.3 Off 6 E-3 E 24.2 Off 7 N-1 N 0.97 On 8 NNE-1 NNE 0.88 On 9 ENE-1 ENE 0.92 On 10 NNH-2 NNH 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-1 NE 0.8 On 42 NE-2 NE 5.0 Off 43 ENE-2 ENE 6.2 Off 44 E-1 E 0.8 On 45 E-2 E 5.2 Off 46 ESE-1 ESE 0.9 On 47 ESE-2 ESE 3.0 Off 48 SE-1 SE 0.5 On 49 SE-2 SE 5.4 Off 50 SSE-1 SSE 5.1 Off 51 S-l S 3.1 Off 52 S-2 S 4.8 Off 53 SSH-1 SSW 3,0 Off 54 SSH-2 SSH 4,4 Off 55 SH-1 SW 1.9 On 56 SW-2 SW 4.7 Off 57 SH-3 SH 6.0 Off 58 HSH-1 HSH 2.7 Off 59 HSH-2 WSH 5.1 Off 60 HSH-3 HSH 10.5 Off 61 W-1 1.9 On 62 H-2 W 4.7 Off 63 H-4 H 32.1 Off 64 HNH-1 HNH 3.3 Off 65 HNH-2 HNW 4.4 Off 66 NH-1 NH 2.2 Off 67 NW-2 NW 5.3 Off

Table A-3 BROWNS FERRY NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) Locations (Continued)

Map Approximate Onsi te (On)'r Location Distance Number'8 Station Sector (miles) Offsite (Off)'n NNW-1 NNW 1.0 69 NNW-3 NNW 5.2 Off

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

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

TLDs designated offsi te are those located more than 2 miles from the plant.

49

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Figure A-I Environmental Radiological Sampling Locations Within 1 Mile of Plant 348.75 11.25 NNE 7 33.75 303.7 5 39 56.25 4 q%

WNW ENE 28m

( d,o~

281.25 3~ X-~ /~ 76.75

~

44 W

101.25 258.75 BROWNS FERRY NUCLEAR PLANT ~ 46 48 ESE WSW 123. 75 236. 25 SW lSE 213. 75 '146.25 SSW SSE S Scale 0 Mile l

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Figure A-2 Environmental Radiological Sampling Locations From 1 to. 5 Miles From The Plant 348.75 11.25 38 NNW NNE 13 326.25 33.75 NW NE, 42.

303,75 56.25 ENE WNW

~ 6 65 ~ 10 281.25 78.75 36,64

~1 .

~ 62 BROWNS PER Y NUCLEAR PLANT h1

'55.75 ~101.25 47 55

'ESE WSW 123.75 235.25 51 SW

~ 54 213.75 I 145.25 I

52 l SSW SSE SCALE 0 0.5 1 0.5 2 191.25 158.75 lA1LE5 IO k

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Figure A-3 Environmental Radiological Sampling Locations Greater Than 5 Miles From The Plant 348.76 11.26 NNW 328.25 33.75 NW AW ENCEBURO

.NE I'VLASKI 303.76 FAY TTEV LLE 8.25 WNW 34 ENE 281.25 F LORENC ATHENS 78.75

+E. TAN LAAT 8 A' SE I 2 2

SCM OAL 14, 45 NTSVILLE 67 258.75 0 CATUR 8 101.25 RUSS )VILLE il8 WS CWNI TOTAL 2 AN 328.25 ARAB HALEYVI LE 123.75 CVI LMAN SE 213.75 148.25 SCAM SSE 0 0 25 MIME 191.26 188.7S I

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APPENDIX B 1990 PROGRAM MODIFICATIONS I

APPENDIX B Environmental Radiolo ical Monitorin Pro ram Modifications During 1990, a small number of modifications were made in the environmental monitoring program.

One dairy farm went out of business. No other milk producing animals were identified within 10 miles of the plant, therefore, the number of indicator milk stations was reduced from three to two.

Fish range over the reservoirs, but do not generally pass from one reservoir to the other. Consequently. fish sampling from Wilson Reservoir, the reservoir downstream of Wheeler Reservoir, was discontinued in 1990.

The abundance of Asiatic Clams is steadily decreasing in the reservoirs of the Tennessee River. As a result, populations of the clams are becoming more and more difficult to find. In 1990, the monitoring program was revised to discontinue the collection of clams from specific Tennessee River Mile locations. Instead, samples are collected from two areas where clams are found, one area downstream from the plant and the other upstream.

Beginning in March, vegetation sampling was initiated at one additional control station.

The following table lists the changes in the monitoring program in 1990.

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Table B-1 Environmental Radiolo ical Monitorin Pro ram Modifications Date Station Location Remarks 1/1/90 Wilson 19 miles Fish sampling di sconti.nued.

Reservoir downstream 1/1/90 Wheeler Clam sampling from the general Reservoir areas in which clams are found rather than from specific river mile locations.

3/26/90 RM-1 31.2 miles W In)tiated vegetation sampling.

10/9/90 Farm L 5.9 miles ENE The dairy farm went out.of business. Sampling discontinued.

5 APPENDIX C MISSED SAMPLES AND ANALYSES I

Appendix C Missed Sam les and Anal ses During 1990, a small number of samples were not collected and several analyses were not completed on some collected samples. Those occurrences resulted in deviations from the scheduled program but not from the program required by the Radiological Effluent Manual. Table C-1 lists these occurrences. A general description follows.

Five milk samples were not collected because the dairy farm went out of business, one public water sample was not collected because of equipment malfunction, three clam samples were not collected because of scarcity of clams, and one air filter sample was destroyed during processing preventing complete analysis. Electrical power to the automatic well water sampler was out of service for the entire year. Because of the location of the well, a design change is required before power to the sampler can be restored.

Equipment malfunctions were corrected, additional care was taken to prevent recurrence of lost or destroyed samples during analysis, and a Design Change Request has been issued to restore power to the well sampler.

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Tab 1 e C-1 Environmental Radiolo ical Monitorin Pro ram Deviations Date Station Location Remarks 1/8/90 Champion 11.4 miles Public water sample not collected Paper Co. downstream as a result of a broken water 1 inc.

1/16/90 We 1 1 6 Onsi te The power to the automatic" well 12/22/90 sampler was out of service for the whole year. Consequently, no well water samples were taken from the indicator well.

5/16/90 Wheeler Plant site Sufficient quantities of clams and ll/19/90 Reservoir were not available to provide samples for three of the six samples scheduled.

6/11/90 LM-4 BF 1.7 miles NNW Air particulate filter (quarterly composite) lost or destroyed during analysis for strontium.

10/16/90 Farm L 5.9 miles ENE Farm L discontinued dairy 12/17/90 operations on October. The last milk sample was collected on October 9, 1990. This represents five samples that were not collected.

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APPENDIX D ANALYTICAL PROCEDURES I

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

The gross beta measurements are made with an automatic low background .counting system. Normal counting times are 50 minutes. Water samples are prepared by evaporating 500 ml of samples to near dryness, trans'ferring to a stainless steel planchet and completing the evaporation process. For solid samples, a specified amount of, the sample is packed into a deep stainless steel planchet. Air particulate 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 100 minutes. With the beta-gamma coincidence counting system, background counts are virtually eliminated and extremely low levels of detection can be obtained.

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

~l 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 mutlichannel analyzer system.

Spectral data reduction is performed by the computer program HYPERMET.

The charcoal cartridges used to sample gaseous radioiodine are analyzed with well-type NaI detectors interfaced with a single channel analyzer. .The system is calibrated to measure I-131. If activity above a specified limit is detected, the sample is analyzed by gamma spectroscopy.

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.

The analysis of transuranic isotopes in soil and air filters is performed by leaching the- sample with acid and then separating the isotopes of interest from the acid leach by an ion exchange technique. The ion exchange technique separates the samples into two fractions, one containing plutonium and the other containing both americium and curium. The Pu fraction and the Am/Cm lo fractions are each electroplated onto stainless steel discs, 1000 minutes on an alpha spectrometer employing a and counted surface barrier detector.

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APPENDIX E NOMINAL LONER LIMITS OF DETECTION (LLD)

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Appendix E Nominal Lower Limits of Detection Sensitive radiation detection devices can give a signal or reading even when I

no radioactivity is present in a sample being analyzed. This signal may come from trace amounts of radioactivity in the components of the device, from cosmic rays, from naturally occurring radon gas, or from machine noise. Thus, there is always some sort of signal on these sensitive devices. 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 some well-defined average reading, but any indi, vidual reading will vary from that average. In order to determine the activity present in a sample that will produce 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 act,ivity is calculated from a sample', the machine background must be subtracted from the sample signals For the very low levels I

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encountered in environmental monitoring, the sample signals are often 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 often happens, abo0t half the time its signal should fall below the average machine background and half the time it should be above the background. If a signal above the background is present, the calculated activity is compared to the calculated LLD to determine if there is really activity present or if the number is an artifact of the way radioactivity is measured.

A number of factors influence the LLD, including sample size, count time, counting 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

'resented in table E-1. The maximum values for the lower limits of detection specified in the ODCM are shown in table E-2.

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

Table E-1 Nominal LLO Values A. Radiochemical Procedures Charcoal Sediment Air Filters -

Filters Mater Milk Fish Flesh Whole Fish Soil

~im~~ ~m~g LB~i LRClL'wtEYl ~i Food Crops and Lull~& La&lasiul Gross Beta 0.002 1.7 Tritium 250 Iodine-131 .020 1.0 0.2 Strontium-89 O.OOoe 3.0 2.5 0.3 0.7 1.0 Strontium-90 0.0003 -1.4 2.0 0.04 0.09 0.3 Wet Vegetation Clam Flesh Heat Q)/Jib)~r LuCi&aH~

Gross Beta 0.2 15 Iodine-131 4 Strontium-89 140 Strontium-90 60

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

Air Water Vegetation Wet "

Soil and Foods, Tomatoes Heat and Particulates and Hilk and Grain Vegetation Sediment Fish Clam Flesh Potatoes, etc. Poultry

~Kilm3 wQLL aQL~~Lx aQLi~at; uCiL~~ uQl~tn Ce-141 .005 10 .07 28 .02 .07 .15 10 25 Ce-144 .01 33 .25 100 .06 .25 .50 33 50 Cr-51 .02 45 .45 180 .10 .45 .94 45 90 j-131 .005 10 .09 36 .02 .09 .18 10 20 Ru-103 .005 5 .05 20 .01 .05 .11 5 15 Ru-106 .02 40 .48 190 .09 .48 .95 40 95 Cs-134 .005 5 .07 28 .01 .07 .11 5 15 Cs-137 .005 5 .06 24 .01 .06 .10 5 15 Zr-95 .005 10 .11 44 .02 .11 .19 10 25 Nb-95 .005 5 .06 24 .01 .06 .11 5 15 Co-58 .005 5 .05 20 .01 .05 .10 5 15 Hn-54 .005 5 .05 20 .01 .05 .10 5 15 Zn-65 .005 10 .11 44 .01 .11 .21 10 25 Co-60 .005 5 .07 28 .01 .07 .11 5 15 K-40 .04 150 1.00 400 .20 1.00 2.00 150 300 Ba-140 .01 25 .23 92 ~ 05 .23 .47 25 50 La-140 .005 8 .11 44 .02 .11 .17 8 20 Fe-59 .005 5 .10 40 .01 .10 ~ 13 5 15 Be-7 .02 45 ~ 50 200 .10 .50 .90 45 100 Pb-212 .005 20 .10 40 .02 .10 .25 20 40 Pb-214 .005 20 .20 80 .02 .20 .25 20 40 Bi-214 .005 20 .12 48 .04 .12 .25 20 40 Bi-212 53 .40, 40 .25 .40 53 Tl-208 .001 7 .03 26 .02 .03 .35 7 Ra-224 ~ 30 Ra-226 .05 Ac-228 .014 25 .10 80 .10 .10 1.00 22 22 Pa-234m 700 3.00

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

Specified by the BFN Offsite Dose Calculation Manual Airborne Particulate Food Hater A~nal sl s or Gases pC//L ~Ci/m'ilk Fish

~C1/K wet Products

~C1/L Sediment

~ci /k wet ~Ci /K dr gross beta 1 N.A. N.A. N.A. N.A.

x10'.A.

H-3 2000 N.A. N.A. N.A. N.A.

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

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

Co-58,60 15 N.A, 130 N.A. N.A. N.A.

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

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

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

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

Cs-134 15 x 10-z 130 15 60 150 Cs-137 18 6x 150 18 80 180 10'.A.

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

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

LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L. If than 15 pCi/L are identified in surface water samples downstream from the levels greater plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for I-131..

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APPENDIX F QUALITY ASSURANCE/QUALITY CONTROL PROGRAM I

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Appendix F ualit Assurance/ ualit Control Pro ram 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 nonconfor'mance and corrective action tracking system, systematic internal aud1ts, a complete training and retraining system, 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 analys1s of special samples along with routine samples.

Radiation detection devices are complex and can be tested in a number of ways. There are two primary tests wh1ch are performed on all devices. In the first type, the device is operated without a sample on the detector to determine the background count rate. The background counts are usually low values and are due to machine noise, cosmic rays, or trace amounts of radioactivity in the materials used to construct the detector. Charts of background counts are kept and monitored to ensure that no unusually high or low values are encountered.

In the second test, the device is operated with a known amount of I

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radioactivity present. The number of counts registered from such a radioactive standard should be very reproducible. These reproduciblity checks are also monitored to ensure that they are neither higher nor lower than expected. Nken 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 dev1ce 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 answer questions about the performance of the 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 contam1nation of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference from isotopes other than the one being measured.

Duplicate samples are generated at random by the same computer program which schedules the collection of the routine samples. For example, if the routine program calls for four milk samples every week, on a random basis each farm I

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might provide an additional sample several times a year. These duplicate are analyzed along with the other routine samples. They provide,

'amples information about the variability of radioactive content in the various sample

, media.

There is another kind of replicate sample. From time to time, if enough sample is available for a particular analysis, the laboratory analyst can split it into two portions. Such a sample can provide information about the variability of the analytical process since two identical portions of material are analyzed side by side.

Analytical knowns are another category of quality control sample. A known amount of radioactivity is added to a sample medium by the quality control staff or by the analysts themselves. The analysts are told 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 analysts have immediate knowledge of the quality of the measurement process..

A portion of these samples are also blanks.

Blind spikes are samples containing radioactivity which are introduced into the analysis- process disguised as ordinary environmental samples. The analyst does not know they contain 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 they can be used to test the data review process. If an analysis routinely generates numerous zeroes for a I

particu,lar isotope, the presence of the isotope is brought to the attention of the laboratory supervisor in the daily rev1ew process. Blind spikes test this process since they contain radioactivity at levels high enough to be detected. FUrthermore, the activity can be put into such samples at the extreme limit of detection 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 analysts labeled as cross-check samples. This means that the quality control staff knows the radioactive content or "right answer" but the analysts do not. They are aware they are being tested. Such samples test the best performance of the laboratory by determining if the analysts can find the "right answer." These samples provide information about the accuracy of- the measurement process. Further information is available about the variability of the process if multiple analyses are requested on the same sample. Internal cross-checks can also tell if there is a I

difference in performance between two analysts. Like blind spikes or analytical know'ns, 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 I

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 are examined very closely by laboratory supervisory and quality control personnel. They 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-l.

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 TVA with L

yet another level of information about laboratory performance. These samples demonstrate performance on actualenvironmental 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. They are checked for trends, problem areas, or other indications that a portion of the analytical process needs I

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 couid be harmful to humans'

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Table F-1 RESULTS OBTAINED IN INTERLABORATORY COHPARISON PROGRAH A. Air Filter (pCi/Filter)

EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA K} ~v. +~i&} ~v. ~ji391k} ~v. ~~EiL}

3/90 . 5=9 7 31=9 32 10 2;6 11 10 9 9 8/90 10=9 14 62=9 64 20=9 20 20 9 20 B. &mrna}.

Radiochemical Analysis of Water (pCi/L) r n >

= EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA jgmm ~v Mammal kate. 6za. ~m~ ~~m 1/90 12=9 25=9 25 20=2.6 18 2/90 4976=863 4943 3/90 4/90'/90 10 9 10 10 2.6 5/90 15 9 15 7~9 7 9 6/90 2933=620 2830 7/90 8/90 39/10 36 9/90 10=9 10 10/90 7203 1247 7340 10/90u 20.9 21 15 9 13 11/90 12/90

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Table F-1 RESULTS OBTAINED IN INTERLABORATORY COHPARISON PROGRAH (Continued)

C. Ganma-Spectral Analysis of Mater (pCi/L)

Ba-133 or

-1 7 Value Value EPA TVA (LYQ EPA TVA L='&omni . hg:

EPA Value TVA

&mmes ha. h3 ~aal ~v.

EPA Value TVA

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EPA Value TVA EPA Value TVA 2/90 74=12 74 15=9 15 139 24 137 139 24 130 18 9 18 18=9 18 4/90~ 15 9 15 15 9 16 6/90 99=17 100 24=9 26 148 26 144 210=36 200 24=9 23 25 9 25 10/90~ 110=19 112 20=9 22 115 21 113 151 26 140 12=9 12 12=9 11 10/90 7=9 7 5 9 6 D. Nilk (pCi/L)

EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Bl 6YQ MzglQl 629 M19m& SY9. Mwi&+ IEK9. LQ 'ilgHl 4/90 23=9 23 23=9 21 99 17 100 24 9 24 1550=135 1577 9/90 16 9 14 20=9 16 58=10 59 20=9 20 1700 147 1790

a. Results invalid as a result of inaccuracies in sample weights.

b. Performance Evaluation Intercomparison Study.

c. Results were not received by EPA in time to be included in their report.

d. Units are milligrams of total potassium per liter rather than picocuries of K-40 per liter.

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APPENDIX G LAND USE SURVEY I

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

In order to identify the locations around BFN which have the greatest relative potential for i'mpact by the plant, radiation doses are projected for individuals living near BFN. These projections use the data obtained in the

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survey and historical meteorological data. They also assume that the plant is operating and 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).

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Doses from breathing air (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 same locations as in 1989, with the resulting values almost identical to those calculated in 1989. The calculated dose in one sector was reduced by about 40 percent as a result of the distance to the nearest resident increasing by a factor of almost 1.5.

Doses calculated for ingestion of home-grown foods changed in some sectors, reflecting shifts in the location of the nearest garden. The most notable changes occurred in the north, north-northeast, and northwest sectors where gardens were not identified or were identified at distances farther from the plant than in 1989.

For milk ingestion, projected annual doses decreased at two locations as a result of changes in the percentage of stored feed given to the cattle. At two locations, 5.9 miles east-northeast of the plant and 6.8 miles west-northwest from the plant, doses were not calculated because milk was no longer being produced at these locations. Vegetation only was being collected at the latter station. The other station, a dairy farm, was deleted from the milk sampling program. No other milk producing animals were identified within 10 miles of the plant, therefore the number of indicator milk sampling stations has been reduced from three to two.

Tables G-l, G-2, and G-3 show the comparative calculated doses for 1989 and 1990.

Table G-1 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident (Within 5 miles) mrem/year/reactor 1989 Surve 1990 Surve Approximate Approximate Sector Distance (Miles) Annual Dose Distance (Miles) Annual Dose N 1.04 0.43 1.51 0.26 NNE 1.68 0.11 2.27 0.12 NE 2.34 0.13 2.34 0.13 ENE 1.07 0.18 1.07 0.18 E 2.37 0.10 2.37 0.10 ESE 2.70 0.08 2.70 0.07 SE 5.03 0.08 5.03 0.08 SSE 4.40 0.08 4.40 0.08 S 2.82 0.12 2.82 0.12 SSH 2.60 3.15 0.16 2 '0 0. 16 SW ~

0.12 3.15 0,12 HSH 2.70 0.08 2.70 0.07 W 1 ~ 63 0.14 1.63 0.14 HNH 2.82 0.13 2.82 0.13

'NW 1.89 0,29 1.89 0.26 NNH 0.95 0.64 0.95 0.64

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Table G-2 BROHNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods (Nearest Garden Within 5 Miles) mrem/year/reactor 1989 Surve 1990 Surve Number of Approximate Approximate Gardens Within Sector Distance (Miles) Annual Dose Distance (Miles) Annual Dose 3 Miles (1990)

N 1.04 9.54 2.08 4.11 5 NNE 1.80 2.12 3.41 0.93 2 NE 2.75 1.22 2.75 1.22 1 ENE 1.68 2.47 1.51 2.76 1 E 2.37 2.38 2.37 2.3& 2 ESE a a 0 SE a a 0 SSE 4.40 1.08 4.17 1.18 4 S 2.82 2.15 2,82 2.15 3 SSW 2.60 2.74 2.84 2.42 13 SW 3.15 1.13 3.41 1.00 2 HSW 2.70 0.64 2.70 0.64 3 H 1.89 1.06 1.89 1.06 1 WNH 3.36 1.14 4.17 0.82 1 NH 2.20 5.12 a 0 NNH 1.14 9.89 1.14 9.89 5

a. Garden not identified in this sector.

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Table G-3 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Milk mrem/year/reactor Approximate Distance Annual Dose Location Sector (Miles) 1989 1990 Farm 5.0 0.02 0.01 L"

Bn'arm ENE 5.9 0.005 c Farm NNW 6.8 0.009 0.03 T'

8'arm WNW 3.2 0.09 c

a. Milk being sampled at these locations.

b. The dairy farm at this location went out of business in October, 1990.

c. Milk producing animals no longer at this location.

d. Vegetation being sampled at this location.

APPENDIX H DATA TABLES I

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Table H-1 DIRECT RADIATION LEVELS Averhgh External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter 1990 mR/Quarter'istance Avera e External Gamma Radiation Levels'th Miles 1st uarter 2nd uarter 3rd uarter uarter 0-1 15.9 a 1.4 18.9 a 1.5 19.4 a 1.8 16.6 a 1.5 1-2 15.0 a 1.2 17.3 a 1.6 16.9 R 1.3 15.2 a 1.1 2-4 14.4 x 1.2 16.9 a 1.3 16.3 a 1.3 14.5

• 1.4 14.1 2 0.9 17.0 R 1.0 16.8 x 1.3 14.5 a 1.1

. 13.6 a 1.3 15.8 a 1.2 15.7 a 1.2 13.4 x 1.3

Average, 0-2 miles (onsite) 15.7 ~ 1.4 18.5 x 1.6 18.8 a 2.0 16.3 a 1.5

Average, greater than 2 miles (offsite) 14.0 ~ 1.2 16.6 a 1.3 16.3 x 1.4 14.2 s 1.3

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

b. Averages of the individual measurements in the set ~ 1 standard deviation of the set.

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Table -2 TENNESSEE VALLEY AUtHORITY CHEHISTRY AND RADIOLOGICAL SERVICES ENVIRONHENTAL RADIOLOGICAL HONITORIHG AND IXSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONHENTAL HONITORING REPORTING SYSTEH RADIOACTIVITY IH AIR FILTER PCI/H3 - 0.037 BO/H3 HAKE OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAHA REPORTING PERIOD: 1990 TYPE AND LOMER LIHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION 'WITH HIGHEST. ANNUAL KEAN LOCATIONS NONROUT I NE OF ANALYSIS DETECT IOH HEAN (F) HAHE HEAR (F) HEAll (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS ALPHA 7.00E-04 1.06E-03( 29/ 52) LH.1 BF 1.06E.03( 29/ 52) 1.12E-03( 25/ 52)

?.'18E 2.00E-03 1.0 HILES N 7.18E 2.0QE-03  ?.57E 1.56E-03 GROSS BETA 2.00E-03 2.15E-02( 468/ 468) LH4 BF TRAILER P 2.26E.02( 52/ 52) 2.15E-02( 104/ 104) 8.49E 4.19E-02 1.7 HILES NNN 8.49E 4.19E-02 9.78E 4.54E-02 GAHHA SCAN (GELI) 143 BE-7 2.00E-02 8.70E-02( 117/ 117) PH-2 BF ATHENS AL 9.09E-02( 13/ 13) 8.91E-02( 26/ 26) 5 95E 1.14E-01 10.9 HILES NE 7.08E 1-14E-01 6.84E 1.16E-01 BI -214 5.00E-03 1.21E-02( 50/ 1'l7) LH-7BF LAKEVIEN 1.71E 02( 4/ 13) 1.43E-02( 10/ 26) 5.00E 3.78E-02 2.1 HILES llEST 6.40E 3.08E-02 6.20E 3.47E-02 PB-214 5.00E-03 '1.23E-02( 48/ 117) LH-7BF LAKEVIEM 1.56E.Q2( 5/ 13) 1.42E-02( 10/ 26) 5.40E 3.77E-02 2.1 HILES NEST '6.70E 2.77E-02 7.80E 3.43E-02 TL-208 1.00E-03 1.60E-03( 1/ 117) LH2 BF NORTH 1.60E.03( 1/ 13) 1.50E-03( 1/ 26) 1.60E 1.60E-03 0.9 NILE NNE 1.60E 1.60E-03 1.50E 1.50E-D3 SR 89 43 6.00E-04 35 VALUES < LLD 8 VALUES < LLD SR 90 43 3.00E-04 35 VALUES < LLD 8 VALUES < LLD AM 241 2.50E-05 3 VALUES < LLD 3 VALUES < LLD PU 239,240 2.50E-05 3 VALUES < LLD LH-1 BF 3 VALUES < LLD 3.90E-05( 2/ 3) 1.0 HILES N 3.90E 3.90E-05 6

2.50E-05 2.60E-05( 1/ 3) LH-1 BF 2.60E-05( 1/ 3) 3.50E.05( 1/ 3) 2.60E 2.60E-05 1.0 HILES H 2.60E 2.60E.05 3o50E.05- 3.50E-05 CH 244 6

2.50E-05 3 VALUES < LLD 3 VALUES < LLD NOTE- 1. NOHINAL LONER LIHIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2.-HEAN AND RANGE BASED UPON DEI'ECTABLE HEASUREHENTS ONLY. FRACTION OF DETECTABLE HEASUREHEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

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TENNESSEE VALLEY AUI'HORITY CHEMISTRY AND RADIOLOGICAL SERVICES EHVIROHNENTAL RADIOLOGICAL MONITORING AkD IHSTRLNENTATIOH NESTERM AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL HOHITORIXG REPORTlkG SYSTEII RADIOACTIVITY IH CHARCOAL FILTER PCI/H3 - 0.037 BO/N3 NAME OF FACILITY: BROMHS FERRY NUCLEAR PLANT DOCKET kO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORT IHG PERIOD: 1990 TYPE AND LOMER LIMIT ALL CONTROL NNBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION 'NITH HIGHEST ANNUAL MEAN LOCAT IONS NOMROUT I NE OF ANALYSIS DETECTION MEAN (F) MANE 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 IODINE-131 572 2.00E-02 2.52E-02( 13/ 468) LH-68F BAKER BOTTN 4.60E 02( 1/ 52) 2.90E-02( 1/ 104) 2.00E 4.60E-02 3.0 MILES SSM 4.60E 4.60E-02 2.90E 2.90E-02 NOTE: 1. NOMINAL USER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1 NOTE: 2. HEAM AHD RAkGE BASED UPON DETECTABLE MEASUREMENTS OILY. FRACTION OF DETECTABLE HEASURENEHTS AT SPECIFIED LOCATIOHS IS lkDICATED IN PARENTHESES (F).

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TEHNESSEE VALLEY AUTHORITY CHEHISTRY AHD RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MOHITORIHG AHD INSTRNIEHTATION NESTERH AREA RADIOLOGICAL LABORATORY EHVIROHXEHTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IN MILK PCI/L - 0.037 BQ/L NAME OF FACILITY: BROhlS FERRY NUCLEAR PLANT DOCKET XO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIG): 1990 TYPE AND LOMER LIMIT ALL CONTROL NIMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION illTH HIGHEST ANNUAL MEAN LOCAT I OHS NONROU TINE OF ANALYSIS DETECTIOH MEAN (F) NAME 'EAN (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 IODINE-131 125 2.00E-01 73 VALUES < LLD 52 VALUES < LLD GAMMA SCAN (GELI) 125 AC-228 2.50E+01 3.80E+01( 1/ 73) SMITH/BEHNETT FARM 3 80E+01( 1/ 26) 52 VALUES < LLD 3.80E+01- 3.80E+01 5.0 MILES N 3.80E+01- 3.80E+01 BI-214 2.DOE+01 4.65E+01( 9/ 73) SMITH/BEHHETT FARM 6.87E+01( 4/ 26) 2.27E+01( 7/ 52) 2.04E+01- '1.86E+02 5.0 MILES N 2.13E+01- 1.86E+02 2.01E+01- 3.32E+01 K-40 1.50E+02 1.29E+03( 74/ 73) SMITH/BENHETT FARM 1.33E+03( 27/ 26) 1.35E+03( 52/ 52) 9.96E+02- 1.64E+03 5.0 MILES H 1.05Et03- 1.64E+03 1.15E+03- 1.62E+03 PB-214 2.DOE+01 6.34E+01( 5/ 73) SMITH/BEHNETT FARM 1.10E+02( 2/ 26) 2.34E+01( 2/ 52) 2.06E+01- 1.83E+02 5.0 MILES N 3.64Et01- 1.83E+02 2.06E+01- 2.61E401 SR 89 62 2.50E+00 2.76E+00( 1/. 36) BROOKS FARM 6.8 MILE 2.76E+00( 1/ 13) 3.19EIOO( 1/ 26) 2.76E+00- 2.76E+00 S HNM 2.76E+00- 2.76E+00 3.19E+09- 3.19E+00 SR 90 62 2.00E+00 2.62E+00( 17/ 36) LOONEY FARM 5.9 MILE 2.85E>00( 9/ 10) 2.65E+00( 5/ 26) 2.04E+00- 4.25E+00 S EHE 2.04E+00- 4.25E+00 2-07E+00- 3.66E+00 NOTE: 1. NOMINAL LOMER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IH TABLE E-1 NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMEHTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

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Table H-5 TENNESSEE VALLEY AUTHORITY CHEHISTRY AND RADIOLOGICAL SERVICES ENVIROHHEHTAL RADIOLOGICAL HOHITORING AND INSTRUKENTATIOH MESTERH AREA RADIOLOGICAL LABORATORY ENVIROHHEHTAL HOHITORING REPORTING SYSTEH RADIOACTIVITY IH VEGETAT IOH PCI/KG - 0.037 BQ/KG (MET HEIGHT)

NAKE OF FACILITYI BROMHS FERRY NUCLEAR PLANT DOCKET HO.: 50 259,260,296 LOCATIOH OF FACILITYI LIHESTOHE ALABAHA REPORTING PERIMI 1990 TYPE AND LOMER L IHIT ALL CONTROL HUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL HEAH LOCAT IONS HOHROUT I NE OF ANALYSIS DETECTIOH KEAN (F) HAKE HEAN (F) KEAH (F) REPORTED PERFORKED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE KEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 IOD I NE-131 36 4.DOE+00 13 VALUES < LLD 23 VALUES < LLD GAHHA SCAN (GELI) 36 AC-228 1.16E+02( 1/ 13) TERRY FARH 1.16E+02( 1/ 13) 23 VALUES < LLD 1 ~ 16E+02- 1.16E+02 3.2 HILES MHM 1.16E+02- 1.16E+02 BE-7 2.DOE+02 1 ~ 57E+03( 13/ 13) TERRY FARH 1.57E+03( 13/ 13) 8.17E+02( 23/ 23) 2.30E+02- 6.36E+03 3.2 HILES MHM 2.30E+02- 6.36E+03 2.37E+02- 3.40E+03 81-214 4.80E+01 9.13E+Ol ( 3/ 13) TERRY FARH 9.13E+01( 3/ 13) 1.65E+02( 4/ 23) 5.04E+01- 1.16E+02 3.2 HILES QlM 5.04E+01- 1.16E+02 5.52E+01- 4.72E+02 K.40 4.DOE+02 4.95E+03( 13/ 13) TERRY FARH 4.95E+03( 13/ 13) 5.45E+03( 23/ 23) 1.44E+03- 9.58E+03 3.2 HILES MHM 1.44E+03- 9.58E+03 2.30E+03- 8.62E+03 PB-214 8.DOE+01 '.01E+02( 2/ 13) TERRY FARH 1.01E+02( 2/ 13) 4.48E+02( 1/ 23) 9.96E+01- 1.02E+02 3.2 HILES MNM 9.96E+01- 1.02E+02 4 48E+02- 4.48E+02 SR 89 1.40E+02 4 VALUES < LLD 7 VALUES < LLD SR 90 6.DOE+01 4 VALUES < LLD TERRY FARH 4 VALUES < LLO 8.10E+01( 1/ 7) 3.2 HILES MNM 8.10E+01- 8.10E+01 NOTE: 1. HOHINAL LOMER LIHIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1 .

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

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Table H-6 TENNESSEE VALLEY AUTHORITY CHEHISTRY AND RADIOLOGICAL SERVICES EHVIROHHEHTAL RADIOLOGICAL HOHITORING AMD INSTRUMENTATION MESTERN AREA RADIOLOGICAL LABORATORY ENVIROHKENTAL MONITORING REPORTIMG SYSTEH RADIOACTIVITY IH SOIL PCI/GH - 0.037 BQ/G (DRY MEIGKT)

HAKE OF FACILITY: BROMKS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIKESTONE ALABAMA REPORTING PERIOD: 1990 TYPE AKD LOMER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIOHS LOCATION MITH HIGHEST ANNUAL HEAH I LOCAT DMS KOHROUTINE OF ANALYSIS DETECTIOH KEAM (F) HAKE HEAN (F) KEAH (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND 0 I RECT I OH RANGE RANGE KEASUREKENTS SEE NOTE 1 SEE MOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS ALPHA NOT ESTAB 2.85E+00( 1/ 1) LH1 BF NOR'fHMEST 2.85E+00( 1/ 1) 1.39E+00( 1/ 1) 2.85E+00- 2.85E+00 1.0 NILE H 2.85E+00- 2.85E+00 1.39E+00- 1.39E+00 GAHHA SCAN (GELI )

11 AC-228 1.00E-01 1.12E+00( 9/ 9) LH4 BF TRAILER P 1.45E+00( 1/ 1) 6.89E-01( 2/ 2) 6.12E 1.45E+00 1.7 HILES NNM 1.45E+00- 1.45E+00 5.24E 8.54E-01 BI-212 2.50E-01 1. 21E+00( 9/ 9) LK4 BF TRAILER P 1.54E+00( 1/ 1) 7.74E-01( 2/ 2) 6.29E 1.54E+00 1.7 HILES HKM 1.54E+00- 1.54E+00 6.28E 9. 19E-01 BI-214 4.00E-02 1.03E+00( 9/ 9) LH1 BF NORTMMEST 1.35E+00( 1/ 1) 7.63E-01( 2/ 2) 6.60E 1.35E+00 1.0 HILE N 1.35E+00- 1.35E+00 5 '4E 9.62E-01 CS-137 1.00E-02 2.06E-Ol ( 9/ 9) PH-1 ROGERSVILLE AL 3.82E-01( 1/ 1) 2.28E-01( 2/ 2) 3.31E 3.82E-01 13.8 MILES HM 3.82E 3.82E-01 2.06E 2.49E-01 K-40 2.00E-01 5.01E+00( 9/ 9) LH1 BF NORTHMEST 7.?4E+00( 1/ 1) 3.54E+00( 2/ 2) 2.79E+00- 7.74E+00 1.0 HILE H 7.74E+00- 7.74E+00 2.22E+00- 4.8?E+00 PA-234H 3.00E+00 3.09E+00( 1/ 9) LH4 BF TRAILER P 3.09E+00( 1/ 1) 2 VALUES < LLD 3.09E+00- 3.09E+00 1.7 HILES NN'M 3.09E+00- 3.09E+00 PB-212 2.00E-02 1 ~ 11E+00( 9/ 9) LH4 BF TRAILER P 1.43E+00( 1/ 1) 7.05E.01( 2/ 2)

6. 11E 1.43E+00 1.7 HILES NN'M 1.43E+00- 1.43E+00 5.71E 8.39E-01 PB-214 2.00E-02 1.08E+00( 9/ 9) LK1 BF HORTMMEST 1.45E+00( 1/ 1) 8.03E-01( 2/ 2) 6.87E 1.45E+00 1.0 HILE N 1.45E+00- 1.45E+00 6.15E 9.90E-01 RA-224 3.00E-01 1.20E+00( 8/ 9) LH4 BF TRAILER P 1.50E+00( 1/ 1) 8.75E-01( 1/ 2) 6.25E 1.50E+00 1.7 MILES NMM 1.50E+00- 1.50E+DD 8.75E 8.75E-01 RA-226 5.00E-02 1.03E+00( 9/ 9) LH1 BF HORTMMEST 1.35E+00( 1/ 1) 9.62E 01( 1/ 2) 6.60E 1.35E+00 1.0 HILE H 1.35E+00- 1.35E+00 9.62E 9.62E-01

'L-208 2.00E-02 3.77E-O'I( 9/ 9) LH4 BF TRAILER P 4.90E-01( 1/ 1) 2.31E.01( 2/ 2)

2. 15E 4.90E-01 1.7 HILES NKM 4.90E 4.90E-01 1.81E.01- 2.81E-01 1.DOE+00 9 VALUES < LLD 2 VALUES < LLD SR 90 11 3.00E-01 9 VALUES < LLD 2 VALUES < LLD NOTE: 1. NOHIKAL LDMER LIHIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1 .

NOTE: 2. MEAN AMD RANGE BASED UPON DETECTABLE HEASUREHEHTS OHLY. FRACTION OF DETECTABLE KEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATEO IH PARENTHESES (F)

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Table 6 (Continued)

TEHNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MOHITORING AND INSTRUMEHTATIOH MESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADIOACT I VI'TY IN SOIL PCI/GH - 0.037 BO/G (DRY MEIGHT)

NAME OF FACILITY: BROMNS FERRY KUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTOHE ALABAMA REPORTING PERIOD: 1990 TYPE AND LONER LIMIT ALL CONTROL NQIBER OF TOTAL NUMBER OF INDICATOR LOCATIOHS LOCATION lJITK HIGHEST ANNUAL HEAM I LOCAT DMS MONRIJTI HE OF ANALYSIS DETECTIOM MEAN (F) NAME MEAN (F) JlEAM (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE MOTE 2 SEE NOTE 2 AM,241 2

NOT ESTAB 7.69E-03( 1/ 1) LM1 BF NORTKMEST 7.69E-03( 1/ 1) 2.22E-02(- 1/ 1) 7.69E 7.69E-03 1.0 MILE N 7.69E 7.69E-03 2.22E 2.22E-02 PU 239,240 HOT ESTAB 1.92E-02( 1/ 1) LH1 BF NORTKNEST 1.92E-02( 1/ 1) 2-17E-02( 1/ 1) 1.92E 1.92E-02 1.0 MILE N 1.92E 1.92E-02 2 '7E 2 '7E-02 NOT ESTAB 3.31E-02( 1/ 1) LM1 BF MORTHMEST 3.31E-02( 1/ 1) 3.45E-02( 1/ 1) 3.31E 3.31E-02 1.0 HILE N 3.31E 3.31E-02 3.45E 3.45E-02 CH 244 NOT ESTAB 6.15E-03( 1/ 1) LM1 BF KORTHIJEST 6.15E-03( 1/ 1) 2.18E-02( 1/ 1) 6.15E 6.15E-03 1.0 MILE H 6.15E 6.15E-03 2.18E 2.18E-02 NOTE: 1. NOMINAL LOMER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAN AMD RANGE BASED UPON DETECTABLE KEASUREMENI'S OHLY. FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS IKDICATED IN PAREHTKESES (F).

l TENNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL KONITORIKG AND INSTRUHEHTATIOK MESTERK AREA RADIOLOGICAL LABORATORY EHVIROMHEHTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IH APPLES PCI/KG - 0.037 BQ/KG (MET Ht)

NAKE OF FACILITY: BROILS FERRY NUCLEAR PLANT DOCKET KO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA ~

REPORTING PERIOD: 1990 TYPE AND LONER LIHIT ALL COHTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATIOH KITH HIGHESt ANNUAL MEAN LOCAT IONS HOMROUT INE OF ANALYSIS DETECT IOH MEAN (F) KAME MEAN (F) KEAH (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AMD DIRECT IOH RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 2

9.DOE+00 5.20E+03( 1/ 1) BROOKS FARM 6.8 NILE 5.20E+03( 1/ 1) 3A6E+03( 1/ 1) 5.20E+03- 5.20E+03 S NMll 5.20E+03- 5.20E+03 3.46E+03- 3A6E+03 GAMMA SCAM (GELI) 2 K-40 1.50E+02 '1.25E+03( 1/ 1) BROOKS FARM 6.8 NILE 1 ~ 25E+03( 1/ 1) 9.50E+02( 1/ 1) 1.25E+03- 1.25E+03 S NHM 1.25E+03- 1.25E+03 9.50E+02- 9.50E+02 NOTE: 1. NOHINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAN AHD RANGE BASED UPON DETECTABLE HEASUREHEHTS ONLY. FRACI'IOH OF DETECTABLE KEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F) ~

1 TENNESSEE VALLEY AUTHORITY CHEMISTRY AHD RADIOLOGICAL SERVICES ENVIROHMEkTAL RADIOLOGICAL MOHITORING AND IHSTRUMEHTATION NESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IH BEEF PCI/KG - 0.037 BQ/KG (lKT Mt)

NAME OF FACILITY: BR(MIS FERRY kUCLEAR PLAHT DOCKEt NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1990 TYPE AND LQlER LIMIT ALL CONTROL NUMBER OF TOTAL HUMBER OF INDICATOR LOCATIONS LOCATION MI TH HIGHEST ANNUAL MEAN LOCAT IOHS kONROUT I NE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAH (F) REPORTED PERFORMED (LLD) RAHGE DISTANCE AHD DIRECT IOH RANGE RANGE MEASUREMEHTS SEE NOTE 1 SEE NOTE 2 SEE HOTE 2 SEE NOTE 2 GROSS BETA 2

1.50E+01 3.50E+03( 1/ 1) SMITH/BENNETT FARM 3.50E+03( 1/ 1) 3.43E+03( 1/ 1) 3.50E+03- 3.50E+03 5.0 MILES N 3.50E+03- 3.50E+03 3.43E+03- 3.43E+03 GAMMA SCAN (GELI) 2 K-40 3-DOE+02 1.57E+03( 1/ 1) SMITH/BENNETT FARM 1.57E+03( 1/ 1) 'l.32E+03( 1/ 1) 1.57E+03- 1.57E+03 5.0 HILES H 1.57E+03- 1.57E+03 1.32Et03- 1.32E+03 kOI'E: '1. NOMINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1 NOTE: 2. MEAN AND RAHGE BASED UPON DETECTABLE MEASUREMENTS OHLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IH PAREHTHESES (F) ~

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TENNESSEE VALLEY AUTHORITY CHEMISTRY AMD RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MONITORING AHD INSTRUMENTATION MESTERH AREA RADIOLOGICAL LABORATORY EHVIRONXEHTAL XONITORIHG REPORTING SYSTEX RADIOACTIVITY IN CABBAGE PCI/KG - 0.037 BO/KG (MET MT)

NAME OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATIOH OF FACILITY: LIMESTONE ALABAMA REPORTIHG PERI(O: 1990 TYPE AND LOMER LIMIT ALL COHTROL NUMBER OF TOTAI. NUMBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL XEAH LOCATIONS MOHRIITINE 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 GROSS BETA 9.DOE+00 3.55E+03( 1/ 1) BROOKS FARM 6.8 MILE 3.55E+03( 1/ 1) 3.09E+03( 1/ 1) 3.55E+03- 3.55E+03 S NHM 3.55E+03- 3.55E+03 3.09E+03- 3.09E+03 GAMMA SCAN (GELI)

K-40 1.50E+02 1.86E+03( 1/ 1) BROOKS FARM 6.8 NILE 1.86E+03( 1/ 1) 1.51E+03( 1/ 1) 1.86E+03- 1.86E+03 S HMM 1.86E+03- 1.86E+03 1.51E+03- 1.51E+03 NOTE: 1. NOXIMAL LONER LIXIT OF DETECTIOH (LLD) AS DESCRIBED IH TABLE E-1 MOTE: 2. MEAN AND RANGE BASED UPO DETECTABLE MEASUREMENTS OHLY. FRACTIOH OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PAREHTHESES (F) ~

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TENNESSEE VALLEY AUTHORITY CHEHISTRY AHD RADIOLOGICAL SERVICES EHVIROHNENTAL RADIOLOGICAL HOHITORING AHD INSTRUNEHTATIOH MESTERN AREA RADIOLOGICAL LABORATORY ENVIRONNEHTAL NOHITORING REPORTING SYSTEN RADIOACTIVITY Ik CORH PCI/KG - 0.037 BO/KG (MET MT)

HANE OF FACILITY: BRDMHS FERRY NUCLEAR PLAHT DOCKET NO.: '0-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABANA REPORTIkG PERI&: 1990 TYPE AHD LOMER L INIT ALL COH'IROL NUNBER OF TOTAL kUNBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL NEAN LOCAT IOHS HOHROUT IN E OF ANALYSIS DETECT IOH HEAH (F) HAHE .NEAN (F) NEAN (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AHD DIRECTION =

RAkGE RANGE HEASURENENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 9.DOE+00 4.16E+03( 1/ 1) BROOKS FARN 6.8 NILE 4.16E+03( 1/ 1) 4.41E+03( 1/ 1) 4.16E+03- 4.16E+03 S HNM 4.16E+03- 4.16E+03 4.41E+03- 4.41E+03 GAHNA SCAN (GELI) 2 K-40 1.50E+02 2.03E+03( 1/ 1) BROOKS FARN 6.8 NILE 2.03E+03( 1/ 1) 2.16E+03( 1/ 1) 2.03E+03- 2.03E+03 S NHM 2.03E+03- 2.03E+03 2.16E+03- 2.16E+03 NOTE: 1. NOIIHAL LOMER LINIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. NEAH AND RANGE BASED UPON DETECTABLE NEASURENEHTS ONLY. FRACTIOH OF DE'IECTABLE NEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

I TEHHESSEE VALLEY AUTHORITY CHEMISTRY AJO RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MONITORING AMD INSTRQIENTATION MESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IH GREEk BEANS PCI/KG - 0.037 BQ/KG (llET NT)

HAHE OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET MO.. 50 259,260,296 LOCATION OF FACILITY: LINESTONE ALABAMA REPORTIHG PERIOD: 1990 TYPE AND LOUR LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION illTH HIGHEST ANNUAL MEAN LOCAT IOHS NONRQJ TINE OF ANALYSIS DETECT ION MEAN (F) MANE HEAM (F) NEAH (F) REPORTED PERFORMED (LLD) RAkGE DISTANCE AHD DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE MOTE 2 SEE NOTE 2 SEE MOTE 2 GROSS BETA 9.DOE+00 4.08E+03( 1/ 1) BROOKS FARM 6.8 MILE 4.08E+03( 1/ 1) 3.15E+03( 1/ 1) 4.08E+03- 4.08E+03 S HNM 4.08E+03- 4.08E+03 3.15E+03- 3.15E+03 GAJOIA SCAN (GELI) 2 BI-214 2.DOE+01 2.01E+01( 1/ 1) BROOKS FARH 6.8 NILE 2.01E+01( 1/ 1) 1 VALUES < LLD 2.01E+01- 2.01E+01 S NHQ 2.01E+01- 2.01E+01 K-40 1.50E+02 1.82E+03( 1/ 1) BROOKS FARM 6.8 NILE 1.82E+03( 1/ 1) 1.71E+03( 1/ 1) 1.82E+03- 1.82E+03 S HHM 1.82E+03- 1.82E+03 '1.71E+03- 1.71E+03 NOTE: 1. M(FINAL LONER LIMIT OF DETECTIOM (LLO) AS DESCRIBED IN TABLE E-1 .

MOTE: 2. KEAN AHD RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

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Table H-12 TENNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOI.OGICAL MOHITORIHG AND INSTRUNENTATIOH MESTERH AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IN POTATOES PCI/KG - 0.037 BO/KG (NET NT)

NAME OF FACILITY: BRSIHS FERRY NUCLEAR PLANT DOCKET HO.: 50 259,260,296 LOCATION OF FACILITY: LINESTONE ALABAMA REPORTING PERIII: 1990 TYPE AHD LOMER LINIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL MEAN LOCATIONS NOHROUT INE OF ANALYSIS DETECT IOH MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AHD DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE HOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 9.DOE+00 7.49E+03( 1/ 1) BROOKS FARM 6.8 MILE 7.49E+03( 1/ 1) 7.24E+03( 1/ 1) 7.49E+03- 7.49E+03 S NNM 7.49E+03- 7.49E+03 7.24E+03- 7.24E+03 GAMMA SCAN (GELI) 2 K-40 1.50E+02 3.59E+03( 1/ 1) BROOKS FARM 6.8 MILE 3.59E+03( 1/ 1) 3.49E+03( 'I/ 1) 3.59E+03- 3.59E+03 S HHN 3.59E+03- 3.59E+03 3.49E+03- 3.49E+03 NOTE: 1. NOMINAL LOMER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 .

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

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TENNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MONITORING AND IHSTRUHENTATION MESTERH AREA RADIOLOGICAL LABORATORY ENVIRONHEHTAL HOHITORING REPORTING SYSTEH RADIOACTIVITY IN TOMATOES PCI/KG - 0.037 BQ/KG (llET MT)-

NAME OF FACILITY: BROWS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERICO: 1990 TYPE AND TOTAL NUHBER OF ANALYSIS LOMER LIMIT OF DETECTION

'LL INDICATOR LOCATIONS MEAN (F)

LOCATION MITH HIGHEST ANNUAL HEAM HAHE HEAH (F)

CONTROL LOCATIONS MEAN (F)

MINBER OF NONROUT I NE REPORTED PERFORKED (LLD) RANGE D I STANCE AMD DIRECTION RANGE RANGE HEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 9.DOE+00 4.79E+03( 1/ 1) BROOKS FARH 6.8 MILE 4.79E+03( 1/ 1) 5.52E+03( 1/ 1) 4.79E+03- 4.79E+03 S NNM 4.79E+03- 4.79E+03 5.52E+03- 5.52E+03 GAMMA SCAM (GELI) 2 K-40 'l.50E+02 2.33E+03( 1/ 1) BROOKS FARM 6.8 HILE 2.33E+03( 1/ 1) 2.51E+03( 1/ 1) 2.33E+03- 2.33E+03 S MNM 2.33E+03- 2.33E+03 2.51E+03- 2.51E+03 NOTE: 1. NOMINAL LOWER LIHIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. HEAX AND RANGE BASED UPOM DETECTABLE HEASUREKENTS ONLY. FRACTIOM OF DETECTABLE HEASUREHEMTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

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Table H-14 TENNESSEE VALLEY AUTHORITY CHEHISTRY AKD RADIOLOGICAL SERVICES EHVIROKMEMTAL RADIOLOGICAL HOHITORING AND IHSTRQIENTATIOH MESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IH SURFACE MATER(Tote()

PCI/L - 0.037 BQ/L NAME OF FACILITY: BROMMS FERRY KUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA. REPORT IKG PERIOD t 1990 TYPE AHD LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST'ANNUAL MEAN LOCATIONS NON ROUT I HE OF ANALYSIS DETECT IOM = HEAN (F) NAME MEAN (F) HEAM (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AHD DIRECTION RANGE RANGE HEASUREHENTS SEE MOTE 1 SEE MOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 39 1.70E+00 2.80E+00( 26/ 26) TRH 293.5 2.80E+00( 13/ 13) 3.26E+00( 12/ 13) 1.79E+00- 4.35E+00 1.87E+00- 3.67E+00 2.40E+00- 4.87E+00 GAMMA SCAN (GELI) 39 81-214 2.DOE+01 2.72E+01( 2/ 26) TRM 285.2 3.33E+01( 1/ 13) 2.56E+01( 2/ 13) 2.12E+01- 3.33E+01 3.33E+01. 3.33E+01 2.21E+01- 2.92E+01 SR 89 12 3.DOE+00 3.39E+00( 1/ 8),TRH 285.2 3.39E+00( 1/ 4) 4 VALUES < LI.D 3.39E+00- 3.39E+00 3.39E+00- 3.39E+00 SR 90 12 1.40E+00 8 VALUES < LLD 4 VALUES < LLD

- TR IT IUH 12 2.50E+02 8 VALUES < LLD TRM 285.2 4 VALUES < LLD 2.59E+02( 1/ 4) 2.59E+02- 2.59E+02 NOTE: 1. NOMINAL LOMER LIMIT OF DETECTIOM (LLD) AS DESCRIBED IH TABLE E.1 .

NOTE: 2. HEAM AHD RANGE BASED UPON DETECTABLE MEASUREMEHTS ONLY. FRACTION OF DETECTABLE MEASUREHEKTS AT SPECIFIED LOCATIONS IS INDICATED Ik PARENTHESES (F).

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TENNESSEE VALLEY AUTHORITY CHEKISTRY AND RADIOLOGICAL SERVICES ENVIRONKENTAL RADIOLOGICAL KOHITORING AND INSTRUKENTATION i%STERN AREA RADIOLOGICAL LABORATORY ENVIRONKEHTAL KONITORIHG REPORTIHG SYSTEK RADIOACTIVITY IN PUBLIC MATER(TotaI)

PCI/L - 0.037 BQ/L NAKE OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET HO.: 50-259,260,296 LOCATIOH OF FACILITY: LIKESTONE ALABAKA REPORTING PERIOD: 1990 TYPE AND LOMER LIK IT ALL CONTROL QNBER OF TOTAL HUKBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST AXHUAL KEAN LOCATIONS NONROUT I HE OF ANALYSIS DETECTIOH . KEAN (F) NAKE .KEAH (F) KEAN (F) REPORTED PERFORKED (LLO) RANGE DISTANCE AND DIRECTION RANGE RANGE KEASUREKENTS SEE NOTE 1 SEE NOTE 2 SEE HOTE 2 SEE NOTE 2 GROSS BETA 103 1.70E+00 2.94E+00( 61/ 77) CHAMPION PAPER 2.96E+00( 42/ 51) 3.08E+00( 22/ 26) 1.79E+00- 5.DOE+00 TRK 282.6 1.79E+00- 4.80E+00 ,

1.98E+00- 4.87E+00 GAKKA SCAN (GELI) 103 AC-228 2.50E+01 3.03E+01( 1/ 77) CHAKP ION PAPER 3.03E+01( 1/ 51) 26 VALUES < LLD 3.03E+01- 3.03E+01 TRK 282.6 3.03E+01- 3.03E+01 BI-214 2.00E+01 3.30E+01( 7/ 77) CHAMPION PAPER 4.23E+01( 3/ 51) 3.47E+01( 3/ 26) 2.33E+01- 7.03E+Ol TRK 282.6 2 45E+01- 7.03E+01 2.21E+01- 5.27E+01 PB-214 2.DOE+01 2.92E+01( 3/ 77) CHAKP ION PAPER 3.20E+01( 2/ 51) 3.18E+01( 1/ 26) 2.14E+01- 4.27E+01 TRK 282.6 2.14E+01- 4.27E+01 3.18E+Ol- 3.18E+01 TL-208 7.DOE+00 8.90E+00( 1/ 77) KUSCLE SHOALS AREA 8.90E+00( 1/ 13) 26 VALUES < LLD 8.90E+00- 8.90E+00 TRK 259.5 8.90E+00- 8.90E+00 SR 89 20 3.DOE+00 12 VALUES < LLO 8 VALUES < LLD SR 90 20 1.40E+00 12 VALUES < LLD 8 VALUES < LLD TR IT IUK 2.50E+02 12 VALUES < LLD CHAKPIOH PAPER 4 VALUES < LLD 2.59E+02( 1/ 8)

TRK 282.6 2.59E+02- 2.59E+02 NOTE: 1. NOKIHAL LONER LIKIT OF DETECTIOH (LLD) AS DESCRIBED IH TABLE E-1 .

NO'TE: 2. KEAH AND RANGE BASED UPOH DETECTABLE KEASUREKENTS ONLY. FRACTION OF DETECTABLE KEASUREKEHTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY CHEHISTRY AND RADIOLOGICAL SERVICES ENVIROHHEHTAL RADIOLOGICAL HOHITORING AND INSTRUHENTATION MESTERN AREA RADIOLOGICAL LABORATORY ENVIRONHEHTAL NONITORING REPORTING S'YSTEH RADIOACTIVITY IN CRAPPIE FLESH PCI/GN - 0.037 BQ/G (DRY MEIGHT)

NAHE OF FACILITY: BROMHS FERRY NUCLEAR PLANT DOCKET HO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTOHE ALABAHA REPORT IHG PERIOD: 1990 LOMER LIHIT ALL CONTROL NUHBER OF TYPE AND TOTAL NIPIBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL HEAN LOCAT I OHS NOHROUT I HE OF ANALYSIS DETECTION HEAH (F) NAME . HEAN (F) HEAN (F) REPORTED PERFORKED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE KEASUREHEHTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 4

NOT ESTAB 3.49E+01( 2/ 2) MHEELER RES 3.49E+01( 2/ 2) 3.24E+01( 2/ 2) 2.96E+01- 4.02E+01 TRH 275-349 2.96E+01- 4.02E+01 3.05E+01- 3.42E+01 GAHHA SCAN (GELI) 4 CS-137 6.00E-02 2 VALUES < LLD MHEELER RES 2 VALUES < LLD 1.27E-01( 1/ 2)

TRH 275-349 1.27E.01- 1.27E-01 K-40 1.DOE+00 1.49E+01( 2/ 2) MHEELER RES 1.49E+01( 2/ 2) 1.46E+01( 2/ 2) 1.38E+01- 1.60E+01 'TRH 2?5-349 1.38E+01- 1.60E+01 1.42E+01- 1.50E+01 NOTE: 1. NONINAL LOMER LIHIT OF DETECTION (LLO) AS DESCRIBED IN TABLE E-1 NOTE: 2. HEAN AND RANGE BASED UPON DETECTABLE HEASUREHEHTS ONLY- FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).

I TENNESSEE VALLEY AUTHORITY CHEMISTRY AHD RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUKENTATIOH NESTERM AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL KOHITORIHG REPORTING SYSTEM RADIOACTIVITY IN SKALUNXJTH BUFFALO FLESH PCI/GK - 0.037 BO/G (DRY HEIGHT)

HAKE OF FACILITY: BROMHS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIKESTOHE ALABAMA REPORT IHG PERI(6: 1990 TYPE AHD LOMER LIKIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION ill TM HIGHEST ANNUAL MEAN LOCAT I ON S HOHROUTINE OF ANALYSIS DETECT I OH KEAH (F) MAKE KEAM (F) KEAH (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE MOTE 2 GROSS BETA 4

NOT ESTAB 2.25E+01( 2/ 2) MHEELER RES 2.25E+01( 2/ 2) 3.02E+01( 2/ 2) 1.87E+01- 2.64E+01 TRK 275-349 1.87E+01- 2.64E+01 2.48E+01- 3.56E+01 GAMMA SCAM (GELI)

X-40 1.DOE+00 1.DOE+01( 2/ 2) NHEELER RES 1.DOE+01( 2/ 2) 1.21E+01( 2/ 2) 8.37E+00- 1.17E+01 TRK 275-349 8.37E+00- 1.17E+01 9.DOE+00- 1.51E+01 NOTE: 1. HOMINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 MOTE: 2 KEAH AND RANGE BASED UPON DETECTABLE KEASUREKEHTS ONLY. FRACTION OF DETECTABLE KEASUREKEHTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).

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TENNESSEE VALLEY AUTHORITY CHEMISTRY AND,RADIOLOGICAL SERVICES EHVIROHHEHTAL RADIOLOGICAL MONITORING AND INSTR(M(ENTATION MESTERN AREA RADIOLOGICAL LABORATORY ENVIRONHEHTAL MONITORING REPORTIKG SYSTEM RADIOACTIVITY IM SHALLHOUTH BUFFALO KHOLE PCI/GH - 0.037 BQ/G (DRY HEIGHT)

NAHE OF FACILITY: BROKMS FERRY NUCLEAR PLANT DOCKET MO.: 50-259,260,296 LOCATIOH OF FACILITY: LIMESTONE ALABAMA REPORTING PERI(O: 1990 TYPE AND LOMER LIHIT ALL CONTROL NWBER OF TOTAL NINBER OF INDICATOR LOCATIONS, LOCATION KITH HIGHEST ANNUAL MEAN LOCAT IONS HONRQJT I ME OF ANALYSIS DETECTION HEAH (F) NAKE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE 0 I STANCE AND 01RECT ION RANGE RANGE HEASUREHEMTS SEE NOTE 1 SEE KOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA NOT ESTAB 1.68E+01( 2/ 2) KHEELER RES 1.68E+01( 2/ 2) 1.83E+01( 2/ 2) 1.48E+01- 1.88E+01 TRH 275-349 1.48E+01- 1.88E+01 1.65E+01- 2.02E+01 GONA SCAN (GELI) 4 Bl-214 1.20E-01 2 VALUES < LLD KHEELER RES 2 VALUES < LLD 1.76E-01( 1/ 2)

TRH 2?5-349 1.?6E 1.76E-01 K-40 1.DOE+00 5.94E+00( 2/ 2) KHEELER RES 5.94E+00( 2/ 2) 5.94E+00( 2/ 2) 5.16E+00- 6.71E+00 TRH 275-349 5.16E+00- 6.71E+00 5.77E+00- 6.10E+00 NOTE: 1. MOHINAL LOMER LIHIT OF DETECTIOH (LLD) AS DESCRIBED IM TABLE E-1 NOTE: 2. HEAH AND RANGE BASED UPON DETECTABLE HEASUREHEMTS ONLY. FRACTION OF DETECTABLE KEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IK PAREKTHESES (F).

Table H-19 TENNESSEE VALLEY AUTHORITY CHEHISTRY AMO RADIOLOGICAL SERVICES EHVIROMHEHTAL RADIOLOGICAL MONITORING AMD INSTRUHEHTATIOH MESTERN AREA RADIOLOGICAL LABORATORY EHVIRONNEMTAL HONITORIHG REPORTING SYSTEM RADIOACTIVITY IN SEDIHEHT PCI/GH - 0.037 BQ/G (DRY MEIGHT)

KAME OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET HO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAHA REPORT IHG PERIOD: 1990 TYPE AND LOIIER LIMIT ALL COHTROL NINBER OF TOTAL MINBER OF IKDICATOR LOCAT IOHS LOCATION KITH HIGHEST ANNUAL MEAN LOCATIONS KOMROUTIKE

-OF ANALYSIS DETECTION MEAN (F) NAHE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE . DISTANCE AHD DIRECTION RANGE RANGE HEASUREHENTS SEE NOTE 1 SEE MOTE 2 SEE KOTE 2 SEE NOTE 2 GAHHA SCAN (GELI) 10 AC-228 1 ~ OOE-01 1.42E+00( 6/ 6) TRH 288.78 1.46E+00( 2/ 2) 1.02E+00( 4/ 4) 1.27E+00- 1.51E+00 1.42E+00- 1.50E+00 9.23E 1.10E+00 81-212 2-50E-01 1.56E+00( 6/ 6) TRH 288.78 1.62E+00( 2/ 2) 1.12E+00( 4/ 4) 1.38E+00- 1.S5E+00 1.56E+00- 1.68E+00 1.08E+00- 1.16E+00 BI-214 4.00E-02 1.2SE+00( 6/ 6) TRH 288.78 1.35E+00( 2/ 2) 8.86E-01( 4/ 4) 1.11E+00- 1.48E+00 1.33E+00- 1.37E+00 8.38E 9.'19E-01 C0-60 1.00E-02 6.33E-02( 6/ 6) TRH 293.7 8.46E-02( 2/ 2) 4 VALUES < LLD 3.56E 1.05E-01 BFH DISCHARGE 6.42E 1.05E-01 CS-134 1.00E-02 2.46E-02( 5/ 6) TRH 293.7 2.60E-02( 2/ 2) 4 VALUES c LLD 2.02E 2.99E-02 BFH DISCHARGE 2.22E 2.99E-02 CS-137 1.00E-02 6.88E-01( 6/ 6) TRH 277.98 7.84E-01( 2/ 2) 2.10E-01( 4/ 4) 5.86E 8.44E-01 7.24E 8.44E-01 1.28E 2.70E-01 r-40 2.00E-01 1.23E+01( 6/ 6) TRH 288.78 1.31E+01( 2/ 2) 1.08E+01( 4/ 4) 1.13E+01- 1.35E+01 1.26E+01- 1.35E+01 9.50E+00. 1.22E+01 PB-212 2.00E-02 1.38E+00( 6/ 6) TRH 288.7S 1.42E+00( 2/ 2) 9.77E-01( 4/ 4) 1.23E+00- 1.49E+00 1.40E+00- 1 45E+00 8.95E 1.07E+00 PB-214 2.00E-02 1.37E+00( 6/ 6) TRH 28S.78 1.42E+00( 2/ 2) 9.40E-01( 4/ 4) 1.22E+00- 1.59E+00 1.41E+00- 1 43E+00 8.97E 9.97E-01 RA-224 3.00E-01 1.44E+00( 5/ 6) TRH 277.98 1.49E+00( 2/ 2) 1.12E+00( 3/ 4) 1.3&E+00- 1.53E+00 1.45E+00- 1.53E+00 1.08E+00- 1.16E+00 RA-226 5.00E-02 1.28E+00( 6/ 6) TRH 288.78 1.35E+00( 2/ 2) 8.86E-01( 4/ 4) 1.11E+00- 1.48E+00 1.33E+00- 1.37E+00 838E-OI- 9.19E.01 TL-208 2.00E-02 4.81E-01( 6/ 6) TRH 288.78 5.08E-01( 2/ 2) 3.41E-01( 4/ 4) 4.08E 01- 5.25E-01 5.04E 5.12E-01 3.13E 3.75E-01 SR 89 10 1.DOE+00 6 VALUES < LLD 4 VALUES < LLD SR 90 10 3.00E-OI 6 VALUES < LLD TRH 277.98 2 VALUES < LLD 3.32E-01( 1/ 4) 3.32E 3.32E-01 NOTE: 1. HOHINAL LONER LINIT OF DETECTION (LLD) AS DESCRIBED IH TASLE E 1 ~

MOTE: 2. MEAN AKD RANGE BASED UPON DETECTABLE HEASUREHEHTS ONLY. FRACTION OF DETECTABLE HEASURENEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

Table H-20 TENNESSEE VALLEY AUTHORITY CHEHISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATIOM VESTERH AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL HONITORING REPORTING SYSTEN RADIOACTIVITY IN CLAN FLESH Pcl/GH - 0.037 Ba/0 (DRY VEIGHT)

NAHE OF FACILITY: BROVHS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORT IHG PERIOD: 1990 TYPE AND LOVER LIHIT .ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATIOM 'llITH HIGHEST ANNUAL HEAH LOCAT I OH S KOHRQJT I HE OF ANAI.YSIS DETECT IOH KEAM (F) MANE HEAR (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE D I STANCE AND DIRECTION RANGE RANGE NEASURENENTS SEE MOTE 1 SEE NOTE 2 SEE NOTE 2 SEE MOTE 2 GANHA SCAN (GELI) 3 81-214 2.50E-01 7.63E-01( 1/ 1) DOVHSTREAH LOCATION 7.63E-01( 1/ 1) 5.23E+00( 1/ 2) 7..63E 7.63E-01 DOVHSTREAH 7.63E-Ol- 7.63E-01 5.23E+00- 5.23E+00 PB-214 2.50E-OI 7.60E-01( 1/ \) DOVMSTREAN LOCATION 7.60E-01( 1/ 1) 2.55E+00( 2/ 2) 7.60E 7.60E-01 DOVMSTREAH 7.60E 7.60E-O'I 3.53E 4.75E+00 NOTE: 1. NONINAL LOVER LIHIT OF DETECTIOM (LLD) AS DESCRIBEO IN TABLE E-1 NOTE: 2. HEAM AMD RANGE BASED UPON DETECTABLE HEASURENEHTS ONLY. FRACTIOH OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IK PAREHTKESES (F).

I' Figure H-1 Direct Radiation Levels Browns Fer r y Nuc ear 1 P1 ant 0 One) te X Offs5te QP 8B $9 88 S1 Year ~Quarter

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Figure H-2 Direct Radiation LeveIs Br owns Ferry Nuc t e ar P l ant 4-Quarter Moving Rverage 0 Overate X Offelte.

77 78 79 =

88 81 82 8s m 87 m 88 as 8I Year ~Quar ter

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Figure H-3 Direct Radiation Levels Natts Bar Nuclear Plant 0 Onetto X Offer to N 8!

Year/Quarter

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Figure H-4 Direct Radiation Leve l s Natts Bar Nuclear Pl ant 4-Quarter novi ng Rver age 0 Oneite X Offs)te 81 Year ~Quar ter

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Figure H-5 Annual Average Gross Beta Activity Air Filters (pCi/Cubic Meter)

Browns Ferry Nuclear Plant p

C R Indicator El Control I

0.25 Preoperational Operational Phase C Phase 0.2 u Preoperational 0.15 Average l

c 0 0.05 I'8 e

e 0

69 70 71 72 73 73 74 .75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 p 0

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Table H-6 Annual Average Gross Beta Activity Surface Water (pCi/Liter)

Browns Ferry Nuclear Plant R indicator Rl Control P Preoperational Phase Operational Phase Preoperational C 5 Average I

/

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2 t 5 e

I' 68 69 70 71 7273p73o 74 75 76 77 78 "79 80 81 82 83 84 85 86 87 88 89 90

• No gross beta measurements made in 1978

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Figure H-7 Annual Average Gross Beta Activity Drinking Water (pCi/Liter Browns Ferry Nuclear Plant

% Indicator I Control Preoperational Operational Phase c'

p Phase Preoperational Average 4

/

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2 e

I 0

68 69 70 71 7273p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90