ML18036B025

Annual Radiological Environ Operating Rept,Browns Ferry Nuclear Plant 1991. W/920424 Ltr

ML18036B025
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1991
From:	Baron R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9204290402
Download: ML18036B025 (167)

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ACCELERATED DI 7RIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 9204290402 DOC. DATE: 91/12/31 NOTARIZED: NO DOCKET 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 BARON,R.R. Tennessee Valley Authority

.RECIP.NAME RECIPIENT AFFILIATION t

SUBJECT:

"Annual Radiological Environ Operating Rept,Browns Ferry Nuclear Plant 1991." W/920424 ltr. D DISTRIBUTION CODE: IEZSD COPIES RECEIVED:LTR TITLE: Environmental Monitoring Rept (per Tech Specs)

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RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D SANDERS,M. 3 3 HEBDON,F 1 1 ROSS,T. 1 1 WILLIAMS,J. 1 1 D

INTERNAL: ACRS 1 1 NRR/DREP/PRPB11 2 2 I G 01 1 1 RGN2 DRSS/RPB 1 1 2 FILE 02 1 1 EXTERNAL I EGGG S MPSON g F 2 2 NRC PDR D

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D NOTE TO ALL "RIDS" RECIPIENTS:

S PLEASE HELP US TO REDUCE KVASTE! 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 15 ENCL 15

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Tennessee Valley Autferfty, Post Office Box 2000. Decatur, Alabama 35609 APR 84 lggz U.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 1991 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, following the guidance 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 the plant, and

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

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

moOZ90zoa 9<laSS PDR ADOCK 05000259 R PDR

U.S. Regulatory Commission APR 24 1992 If you have any questions, please telephone Raul R. Baron, Site Licensing at (205) 729-7566.

R. R. Baron Manager of Site Licensing PAB 1C-BFN cc (Enclosure):

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 American Nuclear lnsurers Town Center, Suite 3005 29 South Main Street West Hartford, Connecticut 06107-2445

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Nuclear Operations/Technical Programs Annual Radiological Environmental Operating Report Browns Ferry Nuclear Plant 1991

.9204290402

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT BROWNS FERRY NUCLEAR PLANT 0 1991 TENNESSEE VALLEY AUTHORITY NUCLEAR OPERATIONS TECHNICAL PROGRAMS Apr 1 1 1992

TABLE OF CONTENTS Table of Contents .

Li st of Tables iv List of Figures . v Executive Summary .

Introduction ~ ~ ~ ~ ~ ~ 2 Naturally Occurring and Background Rad ioactivity . 2 Electric Power Production 5 Site/Plant Description 8 Environmental Radiological Monitoring Program . 10 Direct Radiation Monitoring . 14 Measurement Techniques . 14 Results 16 Q Atmospheric Monitoring Sample Results Collection and Analysis

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19 19 21 Terrestrial Monitoring ~ ~ 22 Sample Collection and Analysis 22 Results 24 Aquatic Monitoring ~ 26 Sample Collect on and Analysis 26 Results ~ ~ 28 Assessment and Evaluation . 31 Results 32 Conclusions 34 References 35 Appendix A Environmental Radiolog ical Monitoring Program and Sampling Locations 40 Aopendix B 1991 Program Modificat ions 53

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

LIST OF TABLES Table 1 Maximum Permissible Concentrations for Nonoccupational Exposure . . . . . . . . . . . . . . . . 36 Table 2 Maximum Dose Due to Radioactive Effluent Releases . 37

LIST OF FIGURES Figure 1 Tennessee Valley Region . . . . . . . . . . . . . . . . . 38 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Material to the Atmosphere and Lake . . . 39

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'XECUTIVE

SUMMARY

This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant in 1991.

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 I

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.

4 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 and Cs-134 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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0 INTRODUCTION This report describes and summarizes a large volume of data, the results of thousands of measurements and laboratory analyses. The measurements are thawed to comply with regulations and to determine potential effects on public health and safety. This report satisfies the annual reporting requirements of the BFN,Offsite Dose Calculation 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 includ d 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 the major types of radioactive materials found naturally in our environment. An individual weighing 150 pounds contains about 140 grams of potassium (Reference 1). This is equivalent to approximately 100,000 pCi of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body. Naturally occurring radioactive materials have always been in our environment. Other'examples of naturally occurring radioactive material's are bismuth-212 and 214, lead 212 and 214, thallium-208, II actinium-228, uranium -238, uranium-235, thorium-234, radium-226, radon-222, carbon-l4, (generally called tritium).

O and hydrogen-3 These naturally occurring radioactive materials are in the'soil, our food, our drinking water,

and our bodies. The radiation from these materials makes up a part of the low-level natural background radiation. The remainder of the natural background radiation comes from outer space. We are all exposed to this natural radiation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per,day.

4 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 Q remainder of the natural background radiation comes from the radioactive materials within each individual's body, We absorb these materials from the food we'at 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 .i:han 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

radiation dose equivalent compared to about 295 mrem/year for the national, average. PK>ople in some locations of the world receive over 1000 mrem/year natural background radiation dose equivalent, primarily because of the greater quantity of radioactive materials in the soil and rocks in those locations.

Scientists have never been able to show that these levels of radiation have caused physical harm to anyone.

It is possible to get an idea of the relative hazard of different types of radiation sources by evaluating the amount of radiation the U.S. population receives from each general type of radiation source. The information below is primarily adapted from References 2 and 3.

0 Source U.S, GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES 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 5 natural gas, mining, ore. processing, etc.

Medical (effective dose equivalent) 53 Nuclear weapons fallout less than 1 Nuclear enerqy 0.28 Consumer products 0,03 Total 355 (approximately)

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, When dispersed in the atmosphere, radon concentrations are relatively low, However, when the gas is trapped in, closed O 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.

fission process and to safeguard against the possibility of reactor malfunction, which could lead to the release of radioactive materials. Yery small amounts of these fission and activation products are released into the plant systems. This radioactive material can be transported throughout plakt 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 made in surrounding areas to verify that the population is not being'xposed to significant le'vels of radiation or radioactive materials.

The BFN Offsite Dose Calculation Manual (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,

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 l,imits for the total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are as follows:

0 . Total body Thyroid Any other organ 25 mrem/year 75 mrem/year 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.

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

Hheeler Reservoir averages 1 to 1-1/2 miles in width in the vicinity of the plant. The site, containing approximately 840 acres, is approximately 10 miles southwest of Athens, Alabama, and 10 miles northwest of 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 1'arge farming operations occupy much of the land on the north side of the river immediately surrounding the plant. The principal crop grown in the area is cotton. At least two dairy farms are located within a 10-mile radius of the plant.

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

BFN consists of three boiling water reactors; each unit is rated at 1098 megawatts (electrical) . Unit 1 achieved criticality on August 17, 1 973, and began commercial operation on August 1, 1974. Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975', forced the shutdown of both reactors. Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in January 1977. All three units were taken out of service in March 1985. Unit 2 was restarted May 24, 1991.

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 pr'ogram 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 maximized.

Q be radiological monitoring program is outlined in appendix A.

The environmental 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, rad'ioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types of'amples coll.ected in this program are designed to monitor these pathways.

A number of factors were considered in determining the locations for collecting environmental samples. The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weathe

- patterns, dose projections, population distribution, and land use.

Terrestrial sampling stations were selected after reviewing such things as the locations of'airy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, water use information,'nd 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 1991 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 of the overall program. During the 1950s, 60s, and 70s, atmospheric nuclear weapons testing r leased radioactive material to the environment causing fluctuations in the natural background radiation levels. Th s radioactive material is the same type as thai produced in the BFN reactors. Preoperational knowledge of r atural. radionuclide patterns in the environment permits a determination, O

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 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 techniqu'e's and methodology is presented in appendix D. Data tables summarizing the sample analysis results are presented in appendix H.

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/

O quality control program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement process as soon as possible so they can be corrected. This program includes equipment checks to ensure that the 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.

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 1991 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 ionizing radiation, many of the electrons which become displaced are trapped in the crystalline structure of the material. They remain trapped for long periods of time as long as the material is not heated. Hhen 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 TLQs.

From 1968 through 1989, TVA used a Victoreen dosimeter consisting of a

manganese activated calcium fluoride (Ca~F:Mn) TLD material encased in a glass bulb. In 1989, TVA began the process of changing from the Victoreen dosimeter to the Panasonic Model UD-814 dosimeter, and completely chang'ed 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 th'e perimeter and remote air monitoring sites and at 19 additional stations out to approximately 32 miles from the site. The TLDs are exchanged every 3 months and the accumulated exposure on the detectors is read with a Panasonic Model UD-710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system.

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 for

, environmental applications of TLDs.

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

The stations are grouped according to the distance from the plant. The first group consists of all stations within 1 mile of the plant. The second groUP lies between 1 and 2 miles, the third group between .2 and 4 miles, the fourth between 4 and 6 miles, and the 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.

r Therefore, for purposes of this report, all stations 2 miles or less from the plant >re identified as "onsite" stations and all others are considered "offsi te."

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

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 1991 are given in table H-1. The rounded average annual exposures are shown below Annual Average Direct Radiation Levels mR/ ear BFN WBN Onsite Stations 64 Offsite Stations 56 The data in table H-1 indicate that the average quarterly radiation levels at

.the BFN onsite stations are approximately 2 mR/quarter higher than levels at the offsite stations. This difference is also noted at the stations at WBN and other nonoperating nuclear power plant construction sites where the average levels onsite are generally 2-6 mR/quarter higher than levels offsit>>. 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, O earth-moving activities onsite, and the mass of concrete employed in the construction of the plant. Other undetermined influences may also play a part. Thes'e conclusions are supported by the fact that similar differences between onsite and offsite stations were measured in the vicin'ity of the WBN construction site.

Figure H-1 compares plots of the environmental gamma radiation ldVels ft'om the onsite or site boundary stations with those from the offsite stations-over the period from 1976 through 1991. 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 NBN 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.

All results reported in 1991 are consistent with direct radiation levels identified at locations which are not influenced by the operation of BFN.

There is no indication that BFN activities i'ncrease 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 communities out to about 13 miles from the plant, and two remote air monitors are located out to 32 miles. The monitoring program and the locations of monitoring stations are identified in the tables and figures of appendix A. The remote stations are used. as control or baseline stations.

Results 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 tl e filter.

This'ystem is housed in a building approximately 2 feet by 3 feet by 4 feet.

The filter is contained in a sampling head mounted on the outside of the monitor building. The filter is replaced every 7 days. Each filter is analyzed for gross beta activity about 3 days after collection to allow title 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 TEDA-impregnated charcoal. This system is designed to collect iodine in both the elemental form and as organic compounds. The cartridge is located in the same sampling head as'he air particulate filter and is downstream of the particulate filter. The cartridge is changed at the same time as the particulate filter and samples the same volume of air. Each cartridge is analyzed for I-131. If activity above a specified limit is detected, a complete gamma spectroscopy analysis is performed.

Rainwater is collected by use of a collection tray attached to the monitor building. The collection tray is protected from debris by a screen cover. As water drains fJom the tray, it is collected in one of two 5-gallon jugs inside the monitor building. A 1-gallon sample is removed from the container every 4 weeks. Any excess water is discarded. Samples are held to be analyzed only O if the air particulate samples indicate the presence of elevated activity levels or if fallout is expected. For example, rainwater samples were analyzed during the period of fallout following the accident at Chernobyl in 1986.

Results The results from the analysis of air particulate samples are summarized in table H-2. Gross beta activity in 1991 was consistent with levels reported in previous years. The average level at both indicator and control stations was 0.020 pCi/m'. The annual averages of the gross beta activity in air particulate filters at these stations for the years 1968-1991 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 conducted by TVA at nonoperating n'uclear power plant construction sites.

Only natural radioactive materials were identified by the monthly gamma spectral analysis of the air particulate samples. No fission or activation products were found at levels greater than the LLDs. As shown in table H-3, iodine-131 was detected in twelve charcoal canister samples at levels slightly higher than the nominal LLD. This is consistent with the number of samples reporting positive results during the period while the plant was not operating. Gamma spectral analyses of these samples indicated the positive values were a result of interference from radon daughters in the sample.

No rain vater samples from the vicinity of BFN were analyzed during this report)ng period.

TERRESTRIAL MONITORING Terrestrial monitoring is accomplished by collecting samples of environmental media ihat may transport radioactive material from the atmosphere to humans.

For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass where dairy cattle are grazing. 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 cf the plant. These two dairies are considered indicator stations and routinely provide milk samples. No other milk producing animals have been identii led within 3 miles of the plant. The results of the 1 991 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 Q and Sr- 89,90 analysis is performed every 4 weeks.

Samples of vegetation are collected every 4 weeks for I-131 analysis. The samples are co)lected from one farm which previous'ly 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. When the gamma analysis is complete, the sample is ashed and analyzed for Sr-89,90. Analyses for transuranic isotopes are also performed on samples from the two monitoring stations with the second air samplers.

f 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 gf changes in the local vegetable gardens. In 1991 samples of cabbage, corn, green beans, potatoes, and tomatoes wer>> coll.ected 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 O

gamma spectroscopy.

After drying, grinding, and ashing, the sample is analyzed for gross beta activity.

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 almost half of the samples. These levels are consistent with concentrations measured in samples collected prior to plaht operation and with concentrations reported in milk as a result of fallout from atmospheric nuclear weapons tests (reference 1). Figure H-6 displays the average Sr-90 concentrations measured in milk since 1968. The concentrations have steadily decreased as a result of the 28 year half-life of Sr-90 and the washout and transport of the element through the soil over the period. The average Sr-90 concentration reported from both indicator and control stations was approximately 2.5 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.

Similar results were reported for vegetation samples (table H-5). All I-131 and Cs-137 values were less than the nominal LLD. Strontium-90 was identified in one control station sample at a concentration of 72.4 pCi/kg. Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7.

0 The only fission or activation products identified in soil samples were Cs-137, Sr-90 and Sr-89. The maximum concentration of Cs-137 was approximately 0.4 pCi/g and the maximum Sr-90 concentration was 0.9 pCi/g.

These concentrations are consistent with levels previously reported from fallout. The positive identification of Sr-89 at levels near the LLD is typically a result of artifacts in the calculational proess ~ All other radionuclides reported were naturally occurring isotopes (table H-6).

'A plot of the annual average Cs-137 concentrations in soil is presented in

'figure H-7. Like the levels of Sr-90 in milk, concentrations of Cs-137 in

'soil are steadily decreasing as a result of the 30 year half-life of Cs-137 and transport through the environment.

Analyses for transuranic isotopes (Am-241; Pu-238; Pu-239,240; Cm-242; and Cm-244) were performed for the first time in 1989. 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 t

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 ontribution from plant activities. The results are reported in tables H-7 hrough H-13.

0 A UATIC MONITORING Potential exposures from the liquid pathway can occur from drinking water, ingestion of fish 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. Radioactivi,ty levels in water, fish and clams were consistent with background and/or fallout levels previously reported. The presence of Co-60, Cs-134 and Cs-137 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 and one upstream station. A timer turns on the pump approximately once every hour. The line is flushed and a sample collected into a collection container. A 1-gallon sample Is removed from the container every four weeks=and the remaining water in the jug i.'iscarded. 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 al.so collected by an automatic sampling pump at the first downstream dl.inking 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, arab 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 also A groundwater well onsite -is equipped with an automatic water sampler, however, permanent power to this well was not available during 1991-.

Beginning in July, temporary power was made available to the sampler so that grab samples could be taken each month. Water is also collected from a well in an area unaffected by BFN. Samples from the wells are 'rivate collec ed every 4 weeks and analyzed by gamma spectroscopy. A quarterly composite sample is analyzed for Sr-89,90 and tritium.

Samples of commercial and game fish species are collected semiannually from each of two reservoirs: the reservoir on which the plant is located (Wheeler Reservoir) and the upstream reservoir (Guntersville Reservoir). The samples are collected using a combination of netting techniques and electrofishing.

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

After drying and grinding, the samples are analyzed by gamma speCtroscopy.

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

8ottom sediment is collected semiannually from selected Tennessee River Mile

<TRH) 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 diff'icult to find.

RasU1hs All radioactivity in surface water samples was below the LLD except tile gross beta activity and naturally occurring isotopes. These results are consistent with previous1y r'eported levels. A trend plot of the gross beta activity in su.face water samples'from~1968 through 1991 is presented in figure H-8. A sgamary tabls of the results for this reporting period is shown in table H-14.

For drinking water, average gross beta activity was 3.0 pCi/liter at the downstream stations and 2.8 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 water from 1968 to the present is presented in figure H-9.

Concentrations of fission and activation products in groundwater samples were all below the LLDs. Only naturally occurring radon decay products <Bi-214 and Pb-214) were identified in these samples. Results from the analysis of groundwater samples are presented in table H-16.

Cesium-137 was identified in two fish samples. The downstream sample had a concentration of 0.08 pCi/g while the concentration in the upstream sample was, 0.10 pCi/g, The only other radioisotope found in fish were naturally occurring. Concentrations in K-40 ranged from 5.3 pCi/g to 15.8 pCi/g. The maximum gross beta activity measured in downstream sampleswas 25.7 pCi/g. No gross beta measurements were made in upstream samples. The results are summarized in tables H-17, H-18, and H-19. Plots of the annual average Cs-137 concentrations in fish are presented in figures H-10, H-ll, and H-12. 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.

Aadionuclides of the types, produced by nuclear power plant operations were identified in sediment .samples. The materials identified were Cs-137, Co-60, Cs-134, and Sr'-,89. The average levels of Cs-137 were 0.64 pCi/g in downstream e

U

amples and 0.21 pCi/g upstream. The Cs-137 concentration at downstream stations is approximately triple the activity in upstream samples.

0 This same relationship was reported from these stations during the preoperatiohai p}lase of the monitoring at BFN, indicating that the levels reported herein are probably not the result of BFN operations. This relationship is graphically represented in figure H-13 which presents 5 'p/ot of the Cs-137 concentrations in sediment since 1968.

Cobalt-60 concentrations in downstream samples averaged 0.06 pCi/g, while concentrations in upstream samples averaged 0.02 pCi/g. The maximum concentration downstream was 0.08 pCi/g. Figure H-14 presents a graph of the Co-60 concentrations measured in sediment since 1968.

Cesium-134 concentrations in upstream samples were all below the. LLD. Levels in downstream samples averaged 0.02 pCi/g, with a maximum of 0.03 pCi/g. The apparent identification of Sr-89 is an artifact of the calculational process and the low concentrations the laboratory is attempting to detect. A realistic assessment of the impact to the general public from these radioisotopes produces a negligible dose equivalent. Results from the analysis of sediment samples are shown in table H-20.

Only naturally occurring radioisotopes were identified in clam flesh samples.

The results are presented in table H-21.

ASSESSMENT AND EVALUATION Potential doses to the public are estimated from measured effluents using computer models. These models were developed by TVA and are based on methodology provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living in the vicinity of a nuclear power plant. The 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 Qthe public may receive an exposure. As indicated in figure 2, the two major ways by which radioactivity is introduced into the environment are through'iquid end gaseous effluents.

For liqi id 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 i anks of the river (recreational activities). Data used to determine these dc ses are based on guidance given by the NRC for maximum ingestion P

rates, <xposure times, and-distribution of the material in the river.

C Whenever possible, data used in the dose calculation are based on specific conditi< ns for the BFN area.

For gaseous effluents, the public can be exposed to radiation from several sources: dIrect radiation from the radioactivity in the air, direct radiation from radioactivity deposited on the ground, inhalation of radioactivity in the air, ingestion of vegetation which contains radioactivity deposited 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'eteorological 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 1991 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 ODCM limits for these doses and a comparison between the calculated dose and the corresponding limit, The maximum calculated whole body dose equivalent from measured liqu.id efflUehts as presented in table 2 is 0.08 mrem/year, or 2.7 percent of the limit. The oaximum organ dose equivalent from gaseous effluents is 0.2 harem/years This represents 1.33 percent of the ODCM limit. A more complete description of the effluents released from BFN and the corresponding doses projected from these iffluents can be found in the BFhl "Semiannual Radioactive Effluent Release Reports."

equivalent to the general 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.

Durin'g 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.'o-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 been 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'r-90 and Cs-137 are consistent with levels measured in TVA's preoperational environmental radiological monitoring programs.

Conclusions It is concluded from the above analysis of the environmental sampling results and from the trend plots presented in appendix H that the exposure to members of the general public which may have been attributable to BFN is negligible.

The radioactivity reported herein is primarily the 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.

0 REFERENCES

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

2. National Council on Radiation Protection and Measly'rements, Report 8o. 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.

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

~CI/I* gCi/m'*

Gross beta 3,000 100 H-3 3,000,000 200,000 Cs-132 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 2n-65 100,000 2,000 Mn-54 100,000 1,000 Co-60 30,000 300 Sr-89 . 3,000 . 300 Sr-90 300 30 Cr-51 2,000,000 80,000 Cs-134 ,9,000 400 Co-58 90,000 2,000

'1 pCi = 3.1 x 10 'q.

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

Table 2 Maximum Dose due to Radioactive Effluent Releases Browns Ferry Nuclear Plant 1991 mrem/year Li uid Effluents 1991 NRC Percent of EPA Percent of Dose Limit NRC Limit Limit EPA Limit Total Body 0.08 2.7 25 0.3 Any Organ 0.12 10 1.2 25 0.5 Gaseous Effluents 1991 NRC Percent of EPA Percent of Dose Limit NRC Limit Limit EPA Limit Noble Gas 0.011 10 0.11 25 0.04 (Gamma)

Noble Gas 0.018 20 0.09 25 0.07 (Beta)

Any Organ 0.16 15 1.07 25 0.64 D

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APPENDIX A ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM AND SAMPLING LOCATIONS 40

Table A-1 BROMNS FERRY NUCLEAR PLANT Environmental Radiological Honi toring Program'xposure Pathway Number of Samples and Sampling and Type and Frequency 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-l, 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 gamma 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 ganja 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-B9,90 content of quarterly composite (by location). at least-once per 92 days.

Radioiodine Same locations as air Continuous sampler operation I-131 every 7 days particulates with charcoal canister collection at least once per 7 days Rainwater Same location as air Composite sample at least Analyzed for gambia nuclides particulate once per 31 days only if radioactivity in other media indicates the presence of increased levels of fallout

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

Soil Samples from same locations Once every year Gamma scan, Sr-89, Sr-90 once as air particulates per year Direct Two or more dosimeters placed At least once per 92 days Gaarna 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 Ganja 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 beta and gamma scan on One sample imnediately down- sequential-type sampler 4-week composite. Composite stream of discharge (TRN 293.5) with composite sample taken for Sr-89, Sr-90, and tritium One sample downstream from at least once per 7 at least once per 92 days plant (TRH 285.2)

Drinking Water One sample at the first by automatic days'ross days'ollected Gross beta and gamna 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 at least once per 92 days

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

Exposure Pathway Number of Samples and Sampling and Type and Frequency 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 (TRN 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 4 sequential-type sampler (TRN 305) with composite sample taken at least once per 7 days~

Ground Water One sample adjacent to the Collected by automatic Gamma 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 Galena scan on each location upgradient from least once per 31 days sample. Composite for the plant (Farm L) Sr89, Sr-90, and tritium at least once per 92 days AQUATIC Sediment Two samples upstream from At least once per .184 days Gamma scan, Sr-89 and Sr-90 discharge point (TRN 297.0 analyses and 307.52)

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

Two additional samples downstream from the plant (TRH 288.78 and 277.98)

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

INGESTION Nil k At least 2 samples from At least once per 15 days Gamma scan and I-131 on each dairy farms in the immediate. when 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 8 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 Ganma scan at least commercial and game species once per 184 days on in Guntersville Reservoir edible portions above the plant Three samples representing conmerciai and game species in Wheeler 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)

Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program'~pnsure nathway Number of Samples and'ampling and Type and Frequency Fruits and Vegetables Samples of food crops such as At least once per year at Gaama scan on edible portion corn, green beans, tomatoes, time of harvest potatoes grown at private 'nd gardens and/or farms in the inmediate 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, gamna scan once per 31 producing milk but not days providing a milk sample (Farm T)

Control samples from one remote air monitor station (RN-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 1991.

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.

0 Table A-2 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Hap Approximate Indicator (I)

Location Distance or Samples Number'tation Sector (miles) Control (C) Collected' PM-'i NN 13.8 AP,CF,R,S PM-2 NE 10. 9 AP,CF,R,S 3 PM-3 SSE 8.2 AP,CF,R,S LH-7 W 2.1 AP,CF,R,S, 5 RM-1 N 31. 3 AP,CF,R,S,V 6 RM-6 E 24.2 AP,CF,R,S 7 LM-1 N 1.0 AP,CF,R,S, 8 LH-2 NNE 0.9 AP,CF,R,S, 9 LM-3 ENE 0.9 AP,CF,R,S, 10 LM-4 NNH 1.7 AP,CF,R,S, ll LM-6 SSN 3.0 AP,CF,R,S, 12 Farm B NNN 6.8 M, 13 Farm Bn N 5.0 M, 14 Farm L ENE 5.9 W 18 Farm GL NSH 35.0 M,V 22 Well No. 6 NN 0.02 23 TRM'82.6 PW 24 TRM 306.0 11.4'2.0'4 PN 25 TRH 259.6 4 PN 26 TRM 274.9 PH 27 TRH 285.2 SN 28 TRM 293.5 19.1'.8'.5'1.0'3.52'.34 SN 29 TRM 305.0 SW 30 TRH 307.52 SD 31 TRH 293.7 SD 32 TRM 288.78, 5.22'6.02 SD 33 TRM 277.98 SD 34 Farm Be 28.8 36 Farm T 3.2 V 37 TRM 297.0 3.0 SD Table A-2 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations (Continued)

Map 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 SW = Surface water M = Milk V = Vegetation PW Public drinking water W = Well water

c. TRM = Tennessee River Mile

d. Miles fr )m plant discharge (TRM 294).

e. Also use as a control for public water.

1 0

Table A-3 BROWNS FERRY NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) Locations Hap Approximate Onsite (On)'r Location Distance Number'tation Sector (miles) Offsite (Off) 1 NN-3 NN 13.8 Off 2 NE-3 NE 10.9 Off 3 SSE-2 SSE 8.2 Off 5 H-3 N 31.3 Off 6 E-3 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 NNN 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 SSN-1 SSN 3.0 Off 54 SSN-2 SSW :4,4 Off 55 SH-1 SN 1.9 On 56 SN-2 SH 4.7 Off 57 SH-3 SW 6.0 Off 58 NSW-1 NSN 2' Off -.

59 WSN-2 WSN 5.1 Off 60 WSH-3 HSN 10.5 ~ 'Off 61 N-1 N 1.9 On 62 N-'2 W 4.7 Off 63 H-4 32.1 Off 64 HNH-1 NNN 3.3 Off 65 WNH-2 WNW 4.4 Off NH-1 2.2 Off 0

I66 67 NW-2 NN 5.3 Off

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

Map Approximate Onsite (On)'r Location Distance Number'8 Station Sector ,(miles) Offsite (Off)

NNW-1 NNW 1.0 On 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 offsite are those located more than 2 miles from the plant.

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s APPENDIX B 1991 PROGRAM MODIFICATIONS APPENDIX 8 Environmental Radi ol o ical Moni tori n f Pro ram Modi i cati ons During 1991, only one slight modification was made in the environmental monitoring program. Because they are of little use in the evaluation of plant impacts and they require extensive sample preparation, gross beta analyses of fish samples were discontinued. Gamma spectral analysis of these samples continues.

The following table lists the changes in the monitoring program in 1991.

O Table B-l Environmental Radiolo ical Monitorin'ro ram Modifications Date Station Location Remarks 6/26/91 Wilson 19 miles Gross beta analyses of fish samples Reservoir downstream discontinUed.

and Wheeler Plant site Reservoir APPENDIX C HISSED SAHPLES AND ANALYSES Appendix C Missed Sam les and Anal ses During 1991, a small number of samples were not collected. Those occurrences resulted in deviations from the scheduled program but not from the minimum program required in the Offsite Dose Calculation Manual. Table C-1 lists these occurrences. A general description follows.

Permanent 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. A Design Change Request has been issued to restore power to the well sampler. In the mean time, temporary power permits the collection of monthly grab samples from

'he well.

One surface water sample was not collected because of the malfunction of the pump motor and one was missed as a result of the misalignment of the sampling line. The pump motor was replaced and the misalignment was corrected tbe week after the problems were identified. Two samples from the drinking water,,

supply 11.4 miles downstream from the plant were missed dur'ing the installation of a new sampling system.

One set of air particulate and charcoal filter samples was* missed when the pump motor malfunctioned. The motor was replaced during the same week.

Table C-1 Environmental Radiolo ical Monitorin Pro ram Deviations Date Station Location Remarks 1/14/91 We 1 1 6 Ons i te Permanent power to the automatic 12/18/91 well sampler was out of service for the whole no year.'onsequently, well water samples were taken by automatic sampler from the indicator well.

Grab samples were taken monthly beginning 7/12/91.

2I19/91 TRM 305.0 11.0 miles The surface water/drinking water upstream sample was not taken'ecause the motor on the sampler had burned out. The motor was replaced.

8/5/91 TRM 285.2 8.8 miles The surface water sample was not downstream collected as a result of the misalignment of the collection line. The line was reinstalled.

9/30/91 and Champion 11.4 miles Public water samples not collected 10/28/91 Paper Co. downstream during the period while the sampler was being replaced.

10/21/91 PM-1 BF 13.8 miles NW Air particulate filter a'nl charcoal filter samples were not collected as a result of the malfunction of the pump motor.

The motor was replaced.

APPENDIX D ANALYTICAL PROCEDURES

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

The gross beta measurements are made with an automatic low background counting system. Normal counting times are 50 minutes. Water samples are prepared by evaporating 500 ml of samples to near dryness, transferring to a stainless steel planchet and completing the evaporation process. 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 analys'is 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 O concentrations can be determined.

Hater samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintillation' 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 fractions are each electroplated onto stainless steel discs, and counted for Q 1000 minutes on an alpha spectrometer employing a surface barrier detector.

APPENDIX E NOMINAL LONER LIMITS OF DETECTION (LLD) h Appendix E Nominal Lower Limits of Detection Serlsitive radiation detection devices can give a signal or reading even when no radioactivity is present in a sample being analyzed. This signal may come from trace amounts of radioactivity in the components of the device, 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 individual 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.

Fvery time an activity is calculated from a sample, the machine background must: be subtracted from the sample signal. For the very low levels 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, about half the time its signal should fall below the average machih4 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' 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 e these factors have been evaluated environmental monitoring program.

for the'arious analyses performed in The nominal, LLDs values, in accordance with the methodology prescribed in the calculated from these ODCM, are the presented 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 if a result is greater than the LLD.

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

~i m~j Mater Hil k Lull~

Fish Flesh Whole Fish KJ~ ~ill Food Crops we+

and Soil Gross Beta 0.002 1.7 Tritium 250 Iodine-131 .020 1.0 0.2, Strontium-89 0.0006 3.0 2.5 0.3 0.7 1.0 Strontium-90 0.0003 1.4 2.0 0.04 0.09 0.3 Met Vegetation Clam Flesh Heat

~ilier ~i~gfJ Gross Beta 0.2 15 Iodine-131 4 Strontium-89 140 Strontium-90 60

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

Air Water Vegetation Wet Soil and Foods, Tomatoes Heat and Particulates in ~i~

and Hilk and Grain

<~/ZAN Vegetation RQjlLg ~w Sediment Fish Clam Flesh Potatoes, etc. Poultry Ce-141 .005 10 .07 28 .02 .07 .15 10 25 Ce-144 n01 33 .25 100 .06 .25 .50 33 50 Cr-51 .02 45 .45 180 n 10 .45 '94 45 90 I-131I .005 10 .09 36 .02 .09 .18 10 20 Ru-103 .005 5 .05 20 .01 .05 .11 5 15 Ru-106 .02 4Q .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 .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 .Q4 .12 .25 20 4Q 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 Anal~sis Hater gC1/L or Gases

~C) /m'i Particulate, sh

~Ci/K wet Mi lk

~Ci/t "Food Products Sediment

~ci /k wet ~Ci /K dr gr'oss beta 4 1 N.A. N.A. N.A. N.A.

x10'.A.

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

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

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

Cs-134 15 x 10 130 15 60 150 Cs-137 18 6 x 10 150 18 80 180 Ba-140

'.A.

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.

APPENDIX F QUALITY ASSURANCE/QUALITY CONTROL PROGRAM

-68.

Q Appendix F ualit Assurance/ uali t 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 nonconformance and corrective action tracking system, systematic internal audits, 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 analysis of special

",amples along with routine samples.

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

radioactivity present. The number of counts registered from such a f

radioactive standard should be very reproducible. These reproducibility checks are also monitored to ensure that they are neither higher nor lower than expected. When counts from either test fall outside the expected'ange, 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 device and the method it uses to detect radiation-or store the information obtained.

Quality control samples of a variety of types are used by the laboratory to answer questions about the performance of the different portions of the analytical process. These quality control samples may be blanks, replicate

'I samples, blind samples, or cross-checks.

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

Ouplicate samples are generated at random by the same computer program which schedules the collection of the routine samples. For example, if the routine ,

~ i might provide an additional sample several times a year. These duplicate

'I samples are analyzed along with the other routine samples. They provide information about the variability of radioactive content in the various sample media.

There's 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. Nhenever 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 .;pikes 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

-71

particular isotope, the presence of the isotope is brought to the attention of the laboratory supervisor in the daily review process. Blind spikes test this process since 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 difference in performance between two analysts. Like blind spikes or analytical knowns, these samples can also be spiked with low levels of activity to test detection limits.

A series of cross-checks is produced by the EPA in Las Vegas. These interlaboratory comparison samples or "EPA cross-checks" are considered to be the primary indicator of laboratory performance.. They provide an independent check of the entire measurement process that cannot be easily provided by the 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.'ike 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. Hhen radioactivity has been present in the environment in measurable quantities, such as fo'llowing atmospheric nuclear weapons t'esting, following the Chernobyl incident, or as naturally occurring radionuclides, the split samples have provided TVA with yet another level of information about laboratory performance, These samples demonstrate performance on actual environmental sample matrices rather than on the constructed matrices used in cross-check programs.

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

Table F-1 RESULTS OBTAINEO IN INTERLABORATORY CONPARISON PROGRAM A. Air Filter (pCi/Filter)

~r~~h EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA aL hm. ~v aL hm.

3/91 25 10 28 124 10 133 40 9 37 40=9 39 8/91 25 10 28 92 17 97 30=9 33 30=9 29 B. Radiochemical Analysis of Mater (pCi/L)

EPA Value

~qm~

TVA

~v EPA Value m~

TVA

~v. ~~m~'v.

EPA Value TVA EPA

~<<~m Value TVA

~v.

EPA

~~m~

Value TVA

~v 1/91 5 9 5=9 6 5 9 4 2/91 4418 766 4658 75 14 63 4/914 28 9 25 26 9 23 5/91 46 9 48 39=9 38 24 9 24 6/91 12480 2162 11886 8/91 20 10 18 9/91 20.9 24 10/91 2454=610 2409 10/918 10 9 10 10 9 10

0

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

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

EPA Value

~irwin TVA

~v EPA Value TVA EPA Value m~ ~v TVA

~ ~~i~

EPA Value TVA EPA Value Bl TVA BKQ.

EPA

&MRS Value TVA BZQ ~-

2/91 75 14 77 40 9 41 149 26 148 186 33 184 89 9 8 9 9 4/91a 24 9 24 25=9 24 6/91 62=10 64 10 9 11 . 108 19 105 149 20 143 15 9 15 14 9 14 10/91 98 17 98 29=9 29 73 12 73 199 35 184 10 9 11 10=9 10 10/91~ 20 9 20 109 9 11 9 12 D. Hilk (pCi/L)

Value Value Value Value Value EPA

~~im TVA

~v.

EPA

~~im~

TVA

~v. Q~Q EPA TVA

~v.

EPA

~~i@ TVA EPA Q~m~

TVA 4/91 32=9 22 32 9 29 60~10 60 49i9 51 1650 144 1697 9/91 25=9 18 25=9 26 108=19 107 30 9 29 1740 150 1698

a. Performance Evaluation Intercomparison Study.

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

c. Negative bias resulted from unusually high chemical yield.

APPENDIX G LAND USE SURVEY 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 us'e 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 impact by the plant, radiation doses are projected for individuals living near BFN. These projections use the data obtained in the survey and historical meteorological data. They also assume that 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).

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 1990, with the resulting values almost identical to those calculated in 1990. 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 northwest sector where gardens were not identified in 1990.

For milk ingestion, projected annual doses were identical to those calcua'Ited in 1990. Only two locations with milk producing animals were identified.

Samples are being taken from both of these farms.

Tables G-l, G-2, and G-3 show the comparative calculated doses for 1990 and Table G-1 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident (Within 5 miles) mrem/year/reactor 1990 Surve 1991 Surve Approximate Approximate Sector Distance (Miles) Annual Dose Distance (Miles) Annual Dose

1. 51 0.2 1.51 0.19 NNE 2.27 0.1 2.27 0.11 NE 2.34 0.1. 2.34 0.13 ENE 1.07 0.18 1.07 0,11 2.37 0.10 2.37 0.10 ESE 5.03 0.07 2.08 0.07 SE 5.03 0.08 5.03 0.07 I,". 4.17 2.82 2.60 3.15 0.08 0.12 0.16 0.12 4.17 2.82 2.60 3.15 0.08 0.11 0.14 SW 0.12 WSW 2.70 0.07 2.70 0.07 W 1.63 0.14 1.63 0.09 2.84 0.13 2.75, 0.12 NW 2.27 0.26 2.27 0.22 NNW 0.95 0.64 1.03 0.33 Table G-2 BROWNS 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 1990 Surve 1991 Surve Number of Approximate Approximate Gardens Within Sector Distance (Miles') Annual Dose Distance (Miles) Annual Dose 3 Miles ( 1990) 2,08 4.11 2.08 '.11 5 NNE 3.41 0.93 3.41 0.93 1 NE 2.75 1.22 2.75 1.22 1 ENE 1.51 2.76 1.51 2.76 1 E 2.37 2.38 2.37 2.38 2 ESE a a 0 SE, a a 0 SSE 4.17 1.18 4 17 1.18 2 0,',.

~

2.82 2.15 2.82 2.15 2 2.84 2.42 2.84 2.43 9.

SN 3.41 1.00 3.41 1.00 1 WSN 2.70 0.64 2.70 0.60 2 1.89 1.06 1.89 1.06 WNW 4 '7 0.82 4.64 0.69 1

1 NW a 2.72 10.10 1 NNW 1.14 9.89 1.14 9.90 4

a. Garden not identified in this sector.

-81

Table G-3 BRONNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Milk mrem/year/reactor Approximate Distance Annual Dose Location Sector (Miles) 1990 1991 Farm 4.9 0.01 0.01 B'

Bn'arm NNW 6.8 0.03 0.03

a. Milk being sampled at these locations.

0 APPENDIX H DATA TABLES Table H-1

,DIRECT RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Brogans Ferry Nuclear Plant for Each Quarter 1991 mR/Quarter'istance Avera e External Gamma Radiation 1st uarter Levels'nd Mi 1 es uarter 3rd uarter 4th uarter f

0-1 15.1 a 1.4 14.6 a 1.5 16.3 R 1.5 1.61 a 1.4 1-2 14.2 t 1.3 13.0 2 1.4 15.0 a 1.6 14.6 2 0.7 2-4 13.3" ~ 1.2 12.4 x 1.2 15.3 a 2.4 13.9 a 1.1 4-6 13.3 2 0.9 12.5 x 0.8 15.0 a 2.2 14.0 2 0.8

> 6 12.3 a 1.1 11.7 a 1.0 13.6 a 1.7 13.1 a 1.3 Average, 0-2 miles (onsite) 14.9 x 1.4 14.2 x 1.6 16.0 a 1.6 15.7 a 1.4 Average,

> 2 miles (offsi te) 13.0 2 1.1 12.3 a 1.0 14.6 a 2.2 13.7 a 1.1

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 ind.ividual measurements in the set ~ 1 standard deviation of the set.

0 e

TENNESSEE VALLEY AUTHORITY CNEHISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MONITORIHG AND INSTRUMENTATION NESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MOHITORIKG REPORTING SYSTEM RADIOACTIVITY IN AIR FILTER PCI/M3 - 0.037 BQ/M3 NAME OF FACILITY: BROMIS FERRY NUCLEAR PLANT DOC<ET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1991 TYPE AND L(WER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION IIITH NIGHEST ANNUAL HEAN LOCATIONS NONROUT I HE OF ANALYSIS DETECTION MEAN (F) HAME 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 ALPHA 7.00E-04 9.87E-04( 13/ 52) LH-1 BF 9.87E.04( 13/ 52) 8.76E-04( 23/ 52) 7.15E 1.91E-03 1.0 MILES N 7.15E.04- 1.91E-03 7.01E-04. 1.22E-03 GROSS BETA 571 2.00E-03 2.00E-02( 467/ 467) PH-2 BF ATHENS AL 2.06E-02( 52/ 52) 1.96E-02( 104/ 104) 3.84E 5 ~ 15E-02 10.9 HILES NE 8.48E.03- 4.80E-02 6.43E 4.59E-02 I GAMMA SCAN (GELI) 143 BE-7 2.00E-02 7.76E-02( 116/ 117) LM4 BF TRAILER P 8.02E.02( 13/ 13) 7.62E-02( 26/ 26) 5.18E 1.05E-01 1.7 MILES NHH 6.23E 9.81E-02 5.68E 9.71E 02 BI -214 5.00E.03 1.13E-02( 80/ 117) PH.1 ROGERSVILLE AL 1.49E.02( 10/ 13) 1.13E-02( 12/ 26) 5.00E 4.47E-02 13.8 HILES Nll 5.20E.03. 4.47E-02 5.20E-03-'2.58E-02 PB-214 5.00E-03 'l.12E-02( 73/ 117) PM-1 ROGERSVILLE AL 1.60E-02( 8/ 13) 1.00E.02( 12/ 26) 5.00E.03- 4.68E-02 . 13.8 MILES NM 5.30E 4.68E-02 5.10E 2.20E-02 SR 89 44 6.00E-04 36 VALUES < LLD 8 VALUES < LLD SR 90 44 3.00E-04 36 VALUES < LLD 8 VALUES < LLO AM 241 2.50E-05 4 VALUES < LLO 4 VALUES < LLD PU 238 2.50E-05 4 VALUES < LLD 4 VALUES < LLD PU 239,240 2.50E-05 4 VALUES < LLD 4 VALUES < LLD CM 244 8

2.50E-05 4 VALUES < LLD 4 VALUES < LLD CH 242 2.50E-05 4 VALUES < LLD 4 VALUES < LLD NOTE: 1. NOMINAL LOUR LIMIT OF OETECI'ION (LLD) AS DESCRIBED IN TABLE E-1 .

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

TENNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IN CHARCOAL FILTER PCI/M3 - 0.037 BO/M3 HAKE OF FACILITY: BRONNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PER ICO: 1991 TYPE AND LOVER L IHIT ALL CONTROL NUMBER OF TOTAL HUMBER OF INDICATOR LOCATIOHS LOCATION KITH HIGHEST ANNUAL MEAN LOCAT IOKS NOKROUT IKE OF AHALYSIS DETECTIOH MEAN (F) NAHE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE OISI'ANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE KOTE 2 SEE NOTE 2 I CO INE-131 571 2.00E-02 2.60E-02( 10/ 467) LM3 BF NORTHEAST 2.97E.02( 2/ 52) 2.42E-02( 2/ 104) 2.03E 3.15E-02 1.0 MILE ENE 2.79E 3.15E-02 2.00E 2.85E-02 NOTE: 1. NOMINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAK AND RANGE BASE UPOH DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS iNDICATED IN PARENTHESES (F).

TEKNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVICE EKVIROKHEHTAL RADIOLOGICAL HOKITORIKG AMD INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATOR'Y EHVIROKHENTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IN MILK PCI/L - 0.037 BQ/L NAME OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET KO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTOME ALABAMA REPORT IKG PERIOD: 1991 TYPE AND LONER L IHIT ALL CONTROL NQIBER OF TOTAL NUMBER OF INDICATOR LOCATIOMS LOCATION KITH HIGHEST ANNUAL MEAN LOCAT I ON S XOMROUT I NE OF ANALYSIS DETECT IOM MEAN (F) MEAN (F)

KAME 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-131 104 2.00E-01 52 VALUES < LLD 52 VALUES < LLD GAMMA SCAN (GELI) 104 Bl -214 2.00E+01 6.72E+01( 12/ 52) SMITH/BEKKETT 7.93E+01( 9/ 26) 3.08E+01( 11/

FARH 52) 2.01E+01- 1.88E+02 5.0 MILES N 2.01E+01- 1.88E+02 2.15E+01- 4.91E+01 K.40 1.50E+02 1.32E+03( 52/ 52) BROOKS FARM 6.8 HILE 1.34E+03( 26/ 26) 1.34E+03( 52/ 52) 9.67E+02- 1.63E+03 S NNH 1.15E+03- 1.48E+03 1.19E+03- 1.57E+03 PB-214 2.DOE+01 7.96E+01( 9/ 52) 9.47E+01( 7/ 26)

SMITH/BENHETT FARM 2.99E+01( 8/ 52) 2.09E+01- 2,DOE+02 5.0 HILES H 2.09E+01- 2.DOE+02 2.01E+01- 4.82E+01 I SR 89 52 2.50E+00 26 VALUES < LLD 26 VALUES < LLD SR 90 52 2.DOE+00 2.44E+00( 12/ 26) SMITH/BEMNETT FARM 2.44E+00( 6/ 13) 2.54E+00( 6/ 26) 2.11E+00- 2.92E+00 5.0 MILES N 2.14E+00- 2.83E+00 2.03E+00- 3.33E+00 NOTE: 1. NOHINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE KEASUREHENTS ONLY. FRACTION OF DETECTABLE KEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IH PAREHTHESES (F).

TENNESSEE VALLEY AUTHORITY CHEHISTR'Y AHD RADIOLOGICAL SERVIC ENVIRONMENTAL RADIOLOGICAL HOHITORING AND IHSTRUHENTATIOM NESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTIKG SYSTEM RADIOACTIVITY IN VEGETATION PCI/KG - 0.037 BO/KG (NET QEIGHT)

MANE OF FACILITY: BROGANS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1991 TYPE AMD L(QER LIMIT ALL CONTROL NQIBER OF TOTAL NUMBER OF INDICATOR LOCATIOHS LOCATIOH MITH HIGHEST AKKUAL MEAN LOCATIONS NON RQJT I NE OF ANALYSIS DETECTION MEAN (F) MANE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AMD DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE KOTE 2 SEE KOTE 2 SEE NOTE 2 IODINE-131 39 4.00E+00 13 VALUES < LLD 26 VALUES < LLD GAMMA SCAM (GELI) 39 BE-7 2.DOE+02 2.21E+03( 10/ 13) TERRY FARM 2.21E+03( 10/ 13) 1.60E+03( 24/ 26) 2.29E+02- 4.77E+03 3.2 MILES 2.29E+02- 4.77E+03 3.30E+02- 4.55E+03 Bl -214 4.80E+01 1.70E+02( 11/ 13) FARM 1'ERRY 1.70E+02( 11/ 13) '1.22E+02( 25/ 26)

I 6.81E+01- 2.98E+02 3.2 MILES NHN 6.81E+01- 2.98E+02 5.DOE+01- 2.29E+02 K.40 4.DOE+02 4.26E+03( 13/ 13) TERRY FARM 4.26E+03( 13/ 13) 4.78E+03( 26/ 26)

CO 3.10E+03- 6.02E+03 3.2 MILES NNN 3. 10E+03- 6.02E+03 1.99E+03- 8.59E+03 PB.214 8.00E+01 1.67E+02( 10/ 13) TERRY FARM 1.67E+02( 10/ 13) 1.27E+02( 19/ 26) 8.92E+01- 2.79E+02 3.2 NILES QN 8.92E+01- 2.79E+02 8.25E+01- 2.12E+02 SR 89 12 1.40E+02 4 VALUES <.LLD 8 VALUES < LLD SR 90 12 6.DOE+01 4 VALUES < LLD TERRY FARM 4 VALUES < LLD 7.24E+01( 1/ 8) 3.2 HILES WN 7.24E+01- 7.24E+01 KOTE: 1. N(FINAL LONER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. KEAN AND RANGE BASED UPOH DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE HEASUREHEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

0 TENNESSEE VALLEY AUTHORITY CHEHISTRY AHD RADIOLOGICAL SERVICE ~J ~ D. 4 P 1 I I ENVIRONMENTAL RADIOLOGICAL HOHITORIXG AKD INSTRUHEKTATIOH WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL HOHITORIHG REPORTING SYS'IEH RADIOACTIVITY IN SOIL FCI/GH - a.037 ea/G (ORV WEIGHT)

NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET KO.:. 50-259,260,296 LOCATIOH OF FACILITY: LIHES'TONE ALABAMA REPORTING PERICO: 1991 TYPE AND LOWER LIMIT ALL CONTROL MQIBER OF TOTAL NUMBER OF INDICATOR LOCATIOKS LOCAT IOH WITH HIGHEST ANNUAL MEAN LOCAT IOHS HOHROUT IN E OF ANALYSIS DETECTIOM MEAN (F) NAME HEAN (F) HEAH (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREHENTS SEE NOTE 1 SEE MOTE 2 SEE KOTE 2 SEE NOTE 2 GROSS ALPHA 2

NOT ESTAB 3.40E+00( 1/ 1) LH1 BF NORTHWEST 3.40E+00( 1/ 1) 1.34E+00( 1/ 1) 3.40E+00- 3.40E+00 1.0 HILE H 3.40E+00- 3.40E+00 1.34E+00- 1.34E+00 GAMMA SCAN (GELI) 11 AC-228 1.00E-01 9.33E-01( 9/ 9) LM4 BF TRAILER P 1.46E+00( 1/ 1) 7.48E-01( 2/ 2) 6.33E 1.46E+00 1.7 HILES HHW 1.46E+00- 1 '6E+00 6.69E 8.27E-01 I

BE-7 1.00E-01 2 '5E-01( 2/ 9) LH4 BF TRAILER P 2.80E-01( 1/ 1) 1.84E-01( 2/ 2) 2.29E 2.80E-01 1.7 HILES MNW 2.80E 2.80E-01 1.52E 2.16E-01 Bl -212 2.50E-01 9.93E-01( 9/ 9) LH2 BF NORTH 1.49E+00( 1/ 1) 8.01E-01( 2/ 2)

I 5.85E 1.49E+00 0.9 HILE HHE 1.49E+00- 1.49E+00 6.96E 9.06E-01 Bl -214 4.00E-02 9.98E-01( 9/ 9) LH2 BF NORTH 1.45E+00( 1/ 1) 8.38E-01( 2/ 2) 7.12E 1.45E+00 0.9 HILE HHE 1.45E+00- 1 ~ 45E+00 7.05E 9.70E-01 CS-137 1 ~ OOE-02 2.08E-01( 9/ 9) PM-1 ROGERSVILLE AL 4.34E-01( 1/ 1) 2.12E-01( 2/ 2) 1.46E 4.34E-01 13.8 HILES NW 4.34E 4.34E-01 1.74E 2.51E-01 K-40 2.00E-01 4.74E+00( 9/ 9) LHC BF TRAILER P 7.60E+00( 1/ 1) 3.88E+00( 2/ 2) 2.79E+00- 7.60E+00 1.7 HILES NHW 7.60E+00- 7.60E+00 3.05E+00- 4.72E+00

-PA-234H 3.DOE+00 3.69E+00( 3/ 9) LH4 BF TRAILER P 4.71E+00( 1/ 1) 2 VALUES < LLD 3.02E+00- 4.71E+00 1.7 HILES NHW 4.71E+00- 4.71E+00 PB-212 2.00E-02 9.04E-01( 9/ 9) LM2 BF NORTH 1.40E+00( 1/ 1) 7.38E-01( 2/ 2) 6.04E 1.40E+00 0.9 HILE NHE 1.40E+00- 1 '0E+00 6.60E 8.17E.01 PB-214 2.00E-02 1.03E+00( 9/ 9) LM2 BF NORTH 1.50E+00( 1/ 1) 8.82E-01( 2/ 2) 7.26E 1 '0E+00 0.9 HILE NNE 1.50E+00- 1 ~ 50E+00 7.52E 1.01E+00 RA-224 3 ~ OOE-01 1.00E+00( 8/ 9) LH2 BF NORTH 1.50E+00( 1/ 1) 7.15E-01( 2/ 2)

RA-226 5.00E:02 5.96E 1.50E+00 9.98E-01(

9/ 9) 0.9 HILE HHE LH2 BF NORTH 1.50E+00- 1.50E+00 1.45E+00( 1/ 1) 6.22E 8.38E-01(

8.07E-01 2/ 2) 7.12E 1.45E+00 0.9 HILE HHE 1.45E+00- 1 '5E+00 7.05E 9.70E-01 TL-208 2.00E-02 3.22E-01( 9/ 9) LMK BF NORTH 5.05E-01( 1/ 1) 2.51E-01( 2/ 2) 2.18E 5.05E-01 0 9 NILE KNE 5.05E 5.05E-01 2.29E 2.74E-01 SR 89 11 1.00E+00 1.30E+00( 2/ 9) PM-2 BF ATNEHS AL 1.47E+00( 1/ 1) 1.91E+00( 1/ 2) 1.12E+00- 1.C7E+00 10.9 HILES NE 1.47E+00- 1.47E+00 1.91E+00- 1-91E+00 I!OTE: 1. NOMINAL LOWER LIHIT OF DETECTIOH (LLD) AS DESCRIBED IH TABLE E-1 NOTE: 2. HEAM AHD RANGE BASED UPON DETECTABLE MEASUREMENTS OHLY- FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IK PARENTHESES (F).

0 0

TEKNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVIC ENVIRONMENTAL RADIOLOGICAL MONITORING AHD IH ix ENTATIOH WESTERH AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IN 'SOIL PCI/GM - 0.037 BO/G (DRY WEIGHT)

NAME OF FACILITY: BROWKS FERRY NUCLEAR PLANT DOCKET KO.: 50-259,260,296 LOCATIOH OF FACILITY: LIMESTOHE ALABAMA REPORTIHG PERIOD: 1991 TYPE AHD LOWER LIMIT ALL COHTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAH LOCATIONS HOKROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE.AND DIRECTION RANGE RANGE MEASUREMEHTS SEE HOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 SR 90 3.00E-01 5.64E-01( 5/ 9) PM-1 ROGERSVILLE AL 8.63E-01( 1/ 1) 2 VALUES < LLD 3.80E 8.63E-01 13.8 MILES KW 8.63E-OI- 8.63E-01 AM 241 HOT ESTAB 1 VALUES < LLD LM1 BF NORTHWEST 1 VALUES < LLD 1 VAI.UES < LLD

'1.0 MILE K PU 238 NOT ESTAB 3.29E-03( 1/ 1) LM1 BF HORTKWEST 3.29E-03( 1/ 1) 1 VALUES < LLD I

3.29E 3.29E-03 1.0 MILE N 3.29E.03- 3.29E-03 PU 239,240 NOT ESTAB 4.70E-03( 1/ 1) LM1 BF KORTHWEST 4.70E-03( 1/ 1) 3.63E-03( 1/ 1) 4.70E 4 .70E-03 1.0 MILE H 4.70E 4.70E-03 3.63E 3.63E-03 CM 244 HOT ESTAB 1 VALUES < LLD LM1 BF HORTHWEST 1 VALUES < LLD 7.16E-03( 1/ 1) 1.0 MILE H 7.16E 7.16E-03 CM 242 NOT ESTAB 1 VALUES < LLD LM1 BF NORTHWEST 1 VALUES < LI.D 5.23E-03( 1/ 1) 1.0 MILE N 5.?3E 5-23E.03 NOTE: 1. KOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1 ~

NOI'E: 2. MEAN AND RANGE BASED UPOH DETECTABLE MEASUREMEHTS ONLY. FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

0 TEHHESSEE VALLEY AU'IKORITY CHEMIS'IRY AND RADIOLOGICAL SERVIC ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMEHTATIOH WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORIKG REPORTIKG SYSTEM RADIOACTIVITY IH APPLES PCI/KG - 0.037 BQ/KG (WET WT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERICO: 1991 TYPE AND LOWER LIMIT ALL COHTROL NUMBER OF TOTAL NUMBER OF ANALYSIS PERFORMED OF DETECTION (LLD)

INDICATOR LOCATIONS MEAN (F)

RANGE NAME "'EAN (F)

LOCATION WITH HIGHEST ANNUAL MEAN DISTANCE AHD DIRECTION RANGE LOCATIONS MEAN (F)

KON ROUT I KE REPORTED RANGE MEASUREMEHTS SEE NOTE 1 SEE KOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 9.DOE+00 2.51E+03( 1/ 1) 7 MILES HHW 2.51E+03( 1/ 1) 2.07E+03( 1/ 1) 2.51E+03- 2.51E+03 2.51E+03- 2.51E+03 2.07E+03- 2.07E+03 GAMMA SCAN (GELI) 2 K-40 1;50E+02 1.11E+03( . 1/ 1) 7 MILES 1.11E+03( 1/ 1) 1.11E+03(

NNW 1/ 1) 1.11E+03- 1.11E+03 1.11E+03- 1.11E+03 1 ~ 11E+03- 1.11E+03 I

NOTE: 1. HOMIHAL LOWER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-'I NOTE: 2. MEAN AND RANGE BASED UPOH DETECTABLE MEASUREMEHTS ONLY. FRACTIOH OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TEHHESSEE VALLEY AUTHORITY CHEHISTRY AND RADIOLOGICAL SERVICE ENVIRONMENTAL RADIOLOGICAL MONITORING AND INS>RUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTIHG SYSTEM RADIOACTIVITY IN BEEF PCI/KG - 0.037 BO/KG (NET llT)

NAME OF FACILITY: BRSINS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTIHG PERIM: 1991 TYPE AND LONER LIMIT ALL COHTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION HITH HIGHEST ANNUAL HEAN LOCATIONS NONROUT I HE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORHED (LLD) RANGE DISTAHCE AND DIRECTION RANGE RANGE HEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 1.50E+01 3.95E+03( 1/ . 1) BROOKS FARM 6.8 MILE 3.95E+03( 1/ 1) 3.98&03( 1/ 1) 3.95E+03- 3.95E+03 S NNH 3.95E+03- 3.95E+03 3.98E+03- 3.98E+03 GAMMA SCAN (GELI) 2 BI-214 4.DOE+01 1 VALUES < LLD BROOKS FARM 6.8 MILE 1 VALUES < LLD 6.75E+01( 1/ 1)

S NNII 6.75E+01- 6.75E+01 K-40 3.DOE+02 1.62E+03( 1/ 1) BROOKS FARM 6.8 HILE 1.62E+03( 1/ 1) 2.13E+03( 1/ 1)

I 1.62E+03- 1.62E+03 S HNH 1.62E+03- 1.62E+03 2.13E+03- 2.13E+03 PB-214 4.DOE+01 1 VALUES c LLD 'ROOKS FARM 6.8 MILE 1 VALUES < LLD 6.27E+01( 1/ 1)

I S NNH 6.27E+01- 6.27E+01 NOTE: 1. NOMINAL LOMER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

I'EHNESSEE VALLEY AUTHORITY CHEHISTRY AND RADIOLOGiCAL SERVICES EHVIRONHEHTAL RADIOLOGICAL MONITORING AND IHSTRUHEHTATIOH WESTERN AREA RADIOLOGICAL LABORATORY ENVIROMHEHTAL HOMITORING REPORTING SYSTEM RADIOACTIVITY IN CABBAGE PCI/KG - 0.037 BO/KG (NET llT)

NAME OF FACILITY: BROlINS FERRY NUCLEAR PLANT DOCKET NOi I 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAHA REPORTING PERICO: 1991 TYPE AND LONER LIMIT ALL CONTROL NUMBER OF TOTAL HUHBER OF INDICATOR LOCATIOHS LOCATION lIITH HIGHEST ANNUAL HEAH LOCAI'ONS NONROUT I HE OF AHALYSIS DETECTIOH MEAN (F) MAHE HEAN (F) HEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREHEHTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 9.DOE+00 3.55E+03( 1/ 1) 7 MILES NNM 3.55E+03( 1/ 1) 2.19E+03( 1/ 1) 3.55E+03- 3.55E+03 3.55E+03- 3.55E+03 2.19E+03- 2.19E+03 GAHHA SCAN (GELI) 2 K-40 1.50E+02 1.71E+03( 1/ 1) 7 MILES NHH 1.71E+03( 1/ 1) 1.17E+03( ~ 1/ 1) 1.71E+03- 1.71E+03 1.71E+03- 1.71E+03 1.17E+03- 1.17E+03 I

NOTE: 1. HOHIHAL LQtER LIHIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1 NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY. FRACTION OF DETECTABLE HEASUREHEHTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).

0 TENNESSEE VALLEY AUTHORITY CNEHISTRZ AND RADIOLOGICAL SERVICES ENVIRONHENTAL RADIOLOGICAL HONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL HOMITORING REPORTING SYSTEH RADIOACTIVITY IN CORN PCI/KG . 0.037 BQ/KG (MET MT)

NAHE OF FACILITY: BRSSS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTONE ALABAHA REPORTING PERIOD: 1991 TYPE AMD LONER LIHIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION NITH HIGHEST ANNUAL HEAR LOCAT I ONS NONROUT I NE OF AMALYSIS DETECTION MEAN (F) NAHE HEAN (F) HEAR (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREHEMTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 9.DOE+00 3.99E+03( 1/ 1) 7 HI LES NNN 3.99E+03( 1/ 1) 2.96E+03( 1/ 1) 3.99E+03- 3.99E+03 3 99E+03- 3.99E+03 2.96E+03- 2 96E+03 GAHHA SCAN (GELI)

K-<0 1.50E+02 2.23E+03( 1/ 1) 7 HILES NNll 2.23E+03( 1/ 1) 1.63E+03( 1/ 1) 2.23E+03- 2.23E+03 2.23E+03- 2.23E+03 1.63E+03- 1.63E+03 I

o E: 1. NOHINAL LONER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. HEAR AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY. FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TEHNESSEE VALLEY AUTHORITY CMEHISTRY AND RADIOLOGICAL SERVICE ENVIROHHEHTAL RADIOLOGICAL MONITORING AND IHSTRUHENTATIDN i%STERN AREA RADIOLOGICAL LABORATORY ENVIRONHEHTAL MONITORING REPORTING SYSTEH RADIOACTIVITY IN GREEN BEAHS PCI/KG - 0.037 BQ/KG (NET N')

MAHE OF FACILITY: BROOMS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTOME ALABAMA REPORTIHG PERIOD: 1991 TYPE AND LONER 'L IHIT ALL CONTROL NUMBER OF

'fOTAL NUMBER OF INDICATOR LOCATIONS LOCATION 'llITH HIGHEST AHMUAL HEAM LOCATIONS HONROUI' NE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) HEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECT IOM RANGE RANGE MEASUREMENTS SEE NOTE I SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 9.00E+00 4.07E+03( 1/ 1) 7 HILES HNII 4.07E+03( 1/ 1) 3.67E+03( 1/ 1) 4.07E+03- 4.07E+03 4.07E+03- 4.07E+03 3.67E+03- 3.67E+03 GAMMA SCAN (GELI) 2 K-40 1.50E+02 2.08E+03( 1/ 1) 7 MILES NNll 2.08E+03( 1/ 1) 1.85E+03( 1/ 1) 2.08E+03- 2.08E+03 2 '8E+03- 2.08E+03 1.85E+03- 1.85E+03 I

NOTE: 1. NOHINAL LONER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAN AHD RANGE BASED UPON DETECTABLE HEASUREHEHTS ONLY. FRAC'fIOM OF DETECTABLE HEASUREHEN'fS AT SPECIFIED LOCATIOMS IS INDICATED IH PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY CNEMIS'IRY AND RADIOLOGICAL SERVICE ENVIRONHENTAL RADIOLOGICAL NOHITORING AND IHSTRUNEHTATION MESTERH AREA RADIOLOGICAL LABORATORY ENVIRONHEHTAL HONITORIHG REPORTIHG SYSTEH RADIOACTIVI'IY IN POTATOES PCI/KG - 0.037 BQ/KG (MEI MT)

NAHE OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET HO.: 50-259,260,296 LOCATIOH OF FACILITY: LIHESTOHE ALABAHA REPORTIHG PERICO: 1991 TYPE AND LOMER LIHIT ALL CONTROL HWBER OF TOTAL NUNBER OF INDICATOR LOCATIONS LOCATION MITN HIGHEST AHNUAL HEAH LOCATIONS NONROUT I NE OF ANALYSIS DETECTIOH HEAH (F) HAHE HEAH (F) HEAH (F) REPORTED PERFORNED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREHENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 2

9.DOE+00 6.52E+03( 1/ 1) 7 NILES NHM 6.52E+03( 1/ 1) 6.52E+03( 1/ 1) 6.52E+03- 6.52E+03 6.52E+03- 6.52E+03 6.52E+03- 6.52E+03 GAS SCAN (GELI) 2 K-40 1.50E+02 3.05E+03( 1/ 1) 7 HILES NNM 3.05E+03( 1/ 1) 3.19E+03( 1/ 1) 3.05E+03- 3.05E+03 3.05E+03- 3.05E+03 3.19E+03- 3.19E+03 I

NOTE: 1. NOHIHAL LOMER LINIT OF DE'IECTION (LLD) AS DESCRIBED IH TABLE E-1 HOTE: 2. HEAN AHD RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY. FRACTION OF DETECTABLE HEASUREHEN'TS A'I SPECIFIED I.OCATIOHS IS INDICATED IN PARENTHESES (F).

TEHNESSEE VALLEY AUTHORITY CHEMISTRY AHD RADIOLOGICAL SERVICES ENVIROHHENI'AL RADIOLOGICAL HOHITORING AHD INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY-ENVIRONNENTAL NONITORIHG REPORTIHG SYSTEN RADIOACTIVITY IH TOMATOES PCI/KG - 0.037 BQ/KG (NET NT)

MANE OF FACILITY: BROWS FERRY NUCLEAR PLANT DOCKET XO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTIMG PERIOD: 1991 TYPE AMD LONER LIHIT ALL CONTROL HIWBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION IIITH HIGHEST ANNUAL MEAN LOCATIONS HONROUT I NE OF AMALYSIS DETECTIOH MEAN (F) MANE HEAM (F) MEAN (F) REPORTED PERFORMED . (LLD) RANGE 0 I STAHCE AND D IRECI'ION RANGE RANGE NEASURENENTS SEE NOTE 1 SEE HOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 9.DOE+00 5.03E+03( 1/ 1) 7 NILES NNN 5.03E+03( 1/ 1) 5.22E+03( 1/ 1) 5.03E+03- 5 '3E+03 5.03E+03- 5.03E+03 5.22E+03- 5.22E+03 GAMMA SCAM (GELI) 2 K-40 1.50E+02 2.44E+03( 1/ 1) 7 MILES NMM 2.44E+03( 1/ 1) 2.68E+03( 1/ 1) 2.44E+03. 2.44E+03 2.44E+03- 2.44E+03 2.68E+03- 2.68E+03 I

NOTE: 1 ~ NONIHAL LONER LIKIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. KEAN AND RANGE BASED UPON DETECTABLE NEASURENEHTS ONLY. FRACTION OF DETECTABLE HEASUREHEH'IS AT SPECIFIED LOCATIONS IS IHDICATED IH PARENTHESES (F).

TEHKESSEE VALLEY AUTHORITY CHEHISTRY AND RADIOLOGICAL SERVICE ENVIRONHENTAL RADIOLOGICAL MOKITORIKG AND INSTRUMENTATION MESTERH AREA RADIOLOGICAL LABORATORY EHVIRONMEHTAL MONITORING REPORTING SYSTEH RADIOACTIVITY IN SURFACE MATER(Total)

PCI/L - 0.037 BQ/L KAME OF FACILITY: BRONNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1991 TYPE AND LONER LIMIT ALL CONTROL KUMBER OF TOTAL KUHBER OF IKDICATOR LOCATIONS LOCATION MITM HiGHEST ANNUAL MEAN LOCAT ION S NONROUT I HE OF ANALYSIS DETECTIOH MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE . DISTANCE AND DIRECTION, RANGE RANGE MEASUREMENTS SEE KOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 37 1.70E+00 3.07E+00( 23/ 25) TRH 285.2 3.36E+00( 10/ 12) 3.01E+00( 11/ 12) 1.71E+00- 5.38E+00 1.94E+00- 5.38E+00 1.89E+00- 4.56E+00 GAMMA SCAN (GELI) 37 Bl -214 2.DOE+01 3.04E+01( 4/ 25) TRM 293.5 3.09E+01( 3/ 13) 3.TOE+01( 2/ 12) 2.36E+01- 4.47E+01 2.36E+01- 4.47E+01 2.84E+01- 4.56E+01 I

PB-214 2.DOE+01 2.23E+01( 3/ 25) TRM 293.5 2.32E+01( 2/ 13) 3.06E+01( 1/ 12) 2.03E+01- 2.47E+01 2.18E+01- 2.47E+01 3.06E+01- 3.06E+01 co SR 89 I

12 3.DOE+00 8 VALUES < LLD 4 VALUES < LLD SR 90 12 1.40E+00 8 VALUES < LLD 4 VALUES < LLD TRITIUM 12 2.50E+02 8 VALUES < LLD 4 VALUES < LLD NOTE: 1. HOHIHAL LSJER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAN AHD RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY CHEMISTRY AHD RADIOLOGICAL SERVIC ENVIRONHENTAL RADIOLOGICAL HOMITORING AND IHSTRUHENTATION MESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL, HOHITORING REPORTING SYSTEM RADIOACTIVITY IN PUBLIC llATER(total)

PCI/L - 0.037 BQ/L NAME OF FACILITY. BROWS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1991 TYPE AND LOMER LIMIT ALL CONTROL NUMBER OF .

TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUT INE OF ANALYSIS DETECTIOH MEAN (F) NAME HEAN (F) KEAN (F) REPORtED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREHEHTS SEE NOTE 1 SEE NOTE 2 SEE MOTE 2 SEE HOTE 2 GROSS BETA 65 1.70E+00 2.95E+00( 36/ 40) CHANPIOI PAPER 3-72E+00( 13l 14) 2.83E+00( 23/ 25) 1 ~ 73E+00- 7.47E+00 TRH 282.6 1.95E+00- 7.47E+00 1.89E+00- 4.56E+00 GAMMA SCAN (GELI) 65 BI-214 2.DOE+01 3.43E+01( 7/ 40) CHAMP IOM PAPER 3.98E+01( 3/ 14) 3.31E+01( 3/ 25) 2.22E+01- 4.87E+01 TRH 282.6 3.18E+01- 4.87E+01 2.53E+01- 4.56E+01 I

PB-214 2.DOE+01 4.32E+01( 2/ 40) CHAMPION PAPER 4.32E+01( 2l 14), 3.06E+0'I( 1/ 25) 3.69E+01- 4.95E+01 TRH 282.6 3.69E+01- 4.95E+Ol 3.06E+01- 3.06E+01 SR 89 I 20 3.DOE+00 12 VALUES < LLD 8 VALUES < LLD SR 90 20 1.40E+00 12 VALUES < LLD 8 VALUES < LLD TRITIUH 20 2.50E+02 12 VALUES < LLD 8 VALUES < LLD HOTE: 1. NOMINAL LOWER LIHIT OF DETECTIOH (LLD) AS DESCRIBED IH TABLE E-1 NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS OHLY. FRACtlOH OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY CHEMISTRY AHD RADIOLOGICAL SERVICE EHVIROHHEHTAL RADIOLOGICAL MONITORING AHD INSTRUMENTATION MESTERN AREA RADIOLOGICAL LABORATORY EHVIROKHEHTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IM MELL MATER(Total)

PCI/L - 0.037 BQ/L MANE OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET XO.: 50-259,260,296 LOCATION OF FACILITY: LIKESTOKE ALABAMA REPORTING PERIOD: 1991 TYPE AHD TOTAL NUMBER LONER LIMIT'LL INDICATOR LOCATIONS CONTROL NUKBER OF OF LOCATION KITH HIGHEST AHHUAL MEAN LOCATIONS KONROUT INE OF ANALYSIS DETECTIOH MEAN (F) NAKE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RAKGE RANGE MEASUREMENTS SEE KOTE 1 SEE NOTE 2 SEE HOTE 2 SEE NOTE 2 GAMMA SCAM (GELI) 19 BI -214 2.DOE+01 3.25E+01( 3/ 6) BFH . llELL ¹6 3.25E+01( 3/ 6) 4.14E+02( 13/ 13) 2.11E+01- 5.51E+01 0.02 K ILES II 2.11E+01- 5.51E+01 4.28E+01- 8.65E+02 PB-214 2.DOE+01 2.21E+01( 1/ 6) BFH MELL ¹6 2.21E+01( 1/ 6) 3.94E+02( 13/ 13) 2.21E+01- 2.21E+01 0.02 KILES U 2.21E+01- 2.21E+01 3.60E+01- 8.37E+02 SR 89 I

3.DOE+00 2 VALUES < LLD 4 VALUES < LLD SR 90 CO 6 I

1.40E+00 2 VALUES < LLD 4 VALUES < LLD TRITIUM 2.50E+02 2 VALUES < LLD 4 VALUES < LLD NOTE: 1. NOMINAL LONER LIMIT OF DEI'ECTIOH (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTIOH OF DETECTABLE HEASUREHEHTS AT SPECIFIED LOCATIOHS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUI'HORITY CHEMISTRY AND RADIOLOGICAL SERVICE E At L C D N W ENVIRONHEHTAL RADIOLOGICAL MONITORING AMD INSTRUMENTATION NESTERN AREA RADIOLOGICAL LABORATORY ENVIROMNEHTAL MONITORING REPORTING SYSTEH RADIOACTIVITY IN CRAPPIE FLESH PCI/GH - 0.037 BQ/G (DRY INSIGHT)

MAHE OF FACILITY- BRONMS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: I.IMESTONE ALABAMA REPORTING PERIOD: 1991 TYPE AND LONER LIMIT ALL CONTROL HUHBER OF TOTAL NUMBER, OF INDICATOR LOCATIONS LOCATIOH MITH HIGHEST ANNUAL HEAX LOCAT I OHS NONROUT I KE OF ANALYSIS -DETEC1'ION MEAN (F) NAHE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE HOTE 2 SEE NOTE 2 SEE MOTE 2 GAMMA SCAM (GELI)

BI -214 1.20E-01 1.69E-01( 2/ 2) MNEELER RES 1.69E-01( 2/ 2) 1.88E-01( 1/ 2) 1.63E 1.75E-01 TRH 275-349 1.63E 1 '5E-01 1.88E 1.88E-01 CS-137 6.00E-02 7.61E-02( 1/ 2) NNEELER RES 7.61E-02( 1/ 2) 1.01E-01( 1/ 2) 7.61E 7.61E-02 TRH 275-349 7.61E 7.61E-02 1.01E 1.01E-01 K-40 1.DOE+00 . 1.50E+01( 2/ 2) MHEELER RES 1 '0E+01( 2/ 2) 1.48E+01( 2/ 2) 1.42E+01- 1.58E+01 TRH 275-349 1.42E+01- 1.58E+01 1 . 4 2E +01- 1.55E+01 I

CO MOTE: 1. XOHIHAL LOLIER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IH TABLE E-1 NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE HEASUREHEHI'S AT SPECIFIED LOCATIOHS IS INDICATED IH PAREHTHESES (F).

TENNESSEE VALLEY AUTHORI'TY CHEMISTRY AND RADIOLOGICAL SERVICE ENVIROHMEHTAL RADIOLOGICAL MONITORING AHD INS ENTATIOH WESTERH AREA RADIOLOGICAL LABORATORY EHVIRONMENTAL MOHITORIHG REPORTING SYSTEN RADIOACTIVITY IN SMALI.MOU'IM BUFFALO FLESH PCI/GM - 0.037 BQ/G (DRY WEIGHT)

HAME OF FACILITY: BROWNS FERRY HUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATIOH OF FACILIT'Y: LIMESTONE ALABAMA REPORT IHG PERIOD: 1991 TYPE AHD LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIOHS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUT I HE OF ANALYSIS DETECTIOH MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AHD DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA 2

NOT ESTAB 2.48E+01( 2/ 2) WHEELER RES 2.48E+01( 2/ 2) 0 VALUES < LLD 2.38E+01- 2.57E+01 TRM 275-349 2.38E+01- 2.57E+01 GAMMA SCAN (GELI)

BI -214 1.20E-01 2.78E-01( 2/ 2) WHEELER RES 2. 78E-01( 2/ 2) 3.01E-01( 1/ 2) 2.09E 3.47E-01 TRM 275-349 2. 09E 3.47E-01 3.01E.01- 3.01E-01 K-40 1.DOE+00 1. 16E+01( 2/ 2) WHEELER RES 1. 16E+01( 2/ 2) 1.12E+01( 2/ 2)

C7 1. 15E+01- 1.17E+01 TRN 275-349 1. 15E+01- 1.17E+Ol 9.09E+00- 1.32E+01 PB-214 2.00E-01 3.00E-01( 1/ 2) WHEELER RES 3.00E-01( 1/ 2) 2.85'-01( 1/ 2)

I 3.00E 3.00E-01 TRM 275-349 3.00E 3.00E-01 2.85E 2.85E-01 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IH TABLE E-1 NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIOHS IS IHDICATED IH PAREH'THESES (F).

TEHNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVICE ENVIRONMENTAL RADIOLOGICAL HOMITORIHG AND IHS UHENTATIOM WESTERN AREA RADIOLOGICAL LABORATORY EHVIRONHENTAL HONITORIHG REPORTIMG SYSTEM RADIOACTIVITY IN SHALLMOUTH BUFFALO MHOLE PCI/GH - 0.037 BQ/G (ORY HEIGHT)

MANE OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTIHG PERIOD: 1991 TYPE AND L(VER LIHIT ALL CONTROL NUMBER OF TOTAL NUHBFR OF INDICATOR LOCATIOHS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS HOHROUI' NE OF ANALYSIS OETECTIOM MEAN (F) NAME HEAH (F) HEAH (F) REPORTED PERFORMED (LLD) RANGE DIS'TAHCE AHD DIRECTION RANGE RANGE HEASUREHEHTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 .SEE NOTE 2 GAMMA SCAN (GELI) 4 BI -214 1.20E-01 2.23E-01( 1/ 2) MHEELER RES 2.23E-01( 1/ 2) 1.95E.01( 1/ 2) 2.23E 2.23E-01 TRN 275-349 2.23E 2.23E-01 1.95E-01. '1.95E-01 K.40 1.DOE+00 6.07E+00( 2/ 2) NHEELER RES 6.0?E+00( 2/ 2) 5.65E+00( 2/ 2) 6.05E+00- 6.09E+00 TRH 275-349 6.05E+00- 6.09E+00 5.33E+00- 5.97E+00 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTIOM (LLD),AS DESCRIBED IM TABLE E-1 HOTE: 2. MEAN AND RANGE BASED UPOH DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED I

LOCATIONS IS INDICATED IH PARENTHESES (F).

0 TENNESSEE VALLEY AUTHORITY CHEHISTRY AND RADIOLOGICAL SERVICE ENVIRONMEHTAL RADIOLOGICAI. MONITORING AND IN i uMENIATIOM HESIERH AREA RADIOLOGICAL LABORATORY ENVIRONHENIAL HONITORING REPORTING SYSTEM RADIOACTIVITY IN SEDIHEHT PCI/GH - 0.037 BQ/G (DRY HEIGHT)

NAHE OF FACILITY: BROMHS FERRY NUCLEAR PLAHI DOCKET HO.: 50-259,260,296 LOCATION OF FACILITY: LIHESTOME ALABAHA REPORTING PERIOD: 1991 tYPE AND LONER LIMIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATIOM llITH HIGHEST AHHUAL HEAH LOCATIONS HOHROUTINE OF ANALYSiS DETECTION HEAN (F) NAHE HEAM (F) MEAM (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREHENtS SEE NOTE 1 SEE NOTE 2 SEE NOIE 2 SEE HOTE 2 GAMMA SCAN (GELI) 10 AC-228 1.00E-01 1.42E+00( 6/ 6) TRM 277.98 1.49E+00( 2/ 2) 1.05E+00( 4/ 4) 1.27E+00- 1.61Ei00 1.37E+00- 1.61E+00 9.39E 1.16E+00 BE-7 1.00E-01 2.74E-01( 3/ 6) TRM 277.98 3.09E-01( 1/ 2) 4.73E-01( 1/ 4) 2.19E 3.09E-01 3.09E 3.09E-01 4.73E C.73E.01 8 I -212 2.50E-01 1.44E+00( 6/ 6) TRM 277.98 1.52E+00( 2/ 2) 1.07E+00( 4/ 4) 1.34E+00- 1.64E+00 1.39E+00 1.64E+00 8.53E 1.31E+00 I

8 I -21C 4.00E-02 1.21E+00( 6/ 6) TRM 277.98 1.26E+00( 2/ 2) 8.98E-01( 4/ 4)

CO 1.01E+00- 1.50E+00 1.01E+00- 1.50E+00 7.67E 1.05E+00 C0.60 1.00E-02 5.71E-02( 6/ 6) TRH 293.7 7.67E-02( 2/ 2) 2.15E-02( 2/ 4)

I 3.09E 8.14E-02 BFN DISCHARGE 7.19E 8.14E-02 2.03E 2.27E.02 CS-134 1.00E-02 2.16E-02( 4/ 6) TRH 293.7 2.58E-02( 2/ 2) 4 VALUES < LLD 1.38E.02- 3.00E-02 BFN DISCHARGE 2.17E 3.00E-02 CS-137 1.00E.02 6.37E.01( 6/ 6) TRM 277.98 6.97E-01( 2/ 2) 2.14E-01( 4/ 4) 5.40E.01. 7.34E-01 6.60E-01 7.34E-01 1.72E-01. 2.74E-01 K-40 2.00E-01 1. 24E+01( 6/ 6) IRH 288.78 1.28E+01( 2/ 2) 1.18E+01( 4/ 4) 1.12E+01- 1.33E+01 1.24E+01. 1.33E+01 1.01E+01- 1.29E+01 PA-234M 3.DOE+00 3.51E+00( 2/ 6) TRH 277.98 3.51E+00( 2/ 2) 4 20E+00( 1/ 4) 3.50E+00- 3.53E+00 3.50E+00- 3.53E+00 4.20E+00. 4.20E+00 PB-212 2.00E-02 1.33E+00( 6/ 6) TRH 277.98 1.37E+00( 2/ 2) 1.02E+00( 4/ 4) 1.21E+00- 1.52E+00 1. 21E+00- 1.52E+00 8.92E-01. 1.10E+00 PB-214 2.00E-.02 1.30E+00( 6/ 6) TRH 277.98 1.36E+00( 2/ 2) 9.34E-01( 4/ 4) 1.08E+00- 1.63E+00 1.08E+00- 1.63E+00 7.49E 1.08E+00 RA-224 3.00E.01 1.53E+00( 6/ 6) TRH 288.78 1.57E+00( 2/ 2) 1.14E+00( 3/ 4) 1.36E+00- 1.73E+00 1.54E+00- 1.60E+00 1.03E+00- 1.23E+00 RA-226 5.00E-02 1.21E+00( 6/ 6) TRH 277.98 1.26E+00( 2/ 2) 8.98E-01( 4/ 4) 1.01E+00. 1.50E+00 1.01E+00- 1.50E+00 7.67E 1.05E+00 TL-208 2.00E-02 4.65E.01( 6/ 6) TRH 277.98 4.84E-01( 2/ 2) 3.37E-01( 4/ 4) 4.38E 5.30E-01 4.38E.01- 5.30E-01 2.87E 3.81E-01 SR 89 10 1.DOE+00 1.C1E+00( 3/ 6) TRH 277.98 1.51E+00( 1/ 2) 1.21E+00( 1/ 4) 1.33E+00- 1.51E+00 1.51E+00- 1.51E+00 1.21E+00- 1.21E+00 NOTE: 1. NOHINAL LONER LIHIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1 ~

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

TENNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVICE ENVIRONMENTAL RADIOLOGICAL MONITORING AHD IHS ENTATIOH WESTERN AREA RADIOLOGICAL LABORATORY ENVIROHNENTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IH

- 0.037 SEDINEHI'CI/GN BQ/G (DRY WEIGHT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET MO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1991 TYPE AHD LOWER LIMIT ALL CONTROL NIWBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATIOH WITH HIGHEST ANNUAL MEAN LOCATIONS HOHROUT I HE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) NEAH (F) REPORTED PERFORMED (LLD) RAHGE DISTANCE AHD DIRECTION RANGE RANGE NEASURENEHTS SEE HOTE 1 SEE NOTE 2 SEE NOTE '2 SEE NOTE 2 10 3.00E-01' VALUES < LLD 4 VALUES < LLD NOTE: 1. HOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE NEASURENEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

I CO I

0 TEHNESSEE VALLEY AUTHORITY CHENISTRY AND RADIOLOGICAL SERVICE EHVIROHHEHTAL RADIOLOGICAL NONITORIHG AND INSTRUHENTATION

'WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEN RADIOACT'IVITY IN CLAH FLESH PCI/GH - 0.037 BO/G (DRY llEIGHT)

NANE OF FACILITY: BRONNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATION OF FACILITY: LIKESTOHE ALABAMA REPORTING PERIOD: 1991 TYPE AHD LOMER LINIT ALL CONTROL NUHBER OF TOTAL HUHBER OF IHDICATOR LOCATIOHS LOCATION MITH HIGHEST ANNUAL NEAN LOCAT I OHS NONROUT I HE OF AHALYSIS DEI'ECTION NEAN (F) HAHE NEAH (F) HEAN (F) REPORTED PERFCRNED (LLD) RAHGE DISTANCE AND DIRECTION RANGE RANGE NEASUREHEHTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAHNA SCAN (GELI) 4 BI -214 2.50E-01 3.98E+00( 2/ 2) DONHSTREAN LOCATION 3.98E+00( 2/ 2) 5.44E+00( 1/ 2) 1.81E+00- 6.16E+00 DDMHSTREAN 1.81E+00- 6.16E+00 5.44E+00- 5.44E+00 K-40 2.00E+00 3.30E+00( I/ 2) DOMNSTREAH LOCATIOH 3.30E+00( 1/ 2) 4.05E+00( 1/ 2) 3.30E+00- 3.30E+00 DONHSTREAH 3.30E+00- 3.30E+00 4.05E+00- 4.05E+00 PB-214 2.50E-01 3.89E+00( 2/ 2) DONNSTREAH LOCATION 3.89E+00( 2/ 2) 5.02E+00( 1/ 2) 1 ~ 48E+00- 6.31E+00 DOMHSTREAH 1 '8E+00- 6.31E+00 5.02E+00- 5.02E+00 I

CO NOTE: 1. NONINAL LOMER LINIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. NEAN AHD RANGE BASED UPON DETECTABLE NEASUREHEHTS ONLY. FRACTION OF DETECTABLE NEASURENEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

0 c . Ra ~ion Levels Brogans F erry. Nuclear Pl ani 15' Onstte X Offsite 6 77 78 79 88 81 88 83 84 85 86 87 88 89 98 91 92 Year~Quar ter

~,

0

Direct Raa. ion Levels Br owns, F er ry Nuc ear Pl ant 1

0-Quar ter Moving Rver age 0 Ons1te X Offskte 6 77 78 - 7S 88 81 82 83 &f 85 66 8? 88 89 SB 91 92 Ye ar~Quam ter

Direct Rad ion Levels watts Bar Nucl.ear. Pl ant 0 Qnstte X Offsfte 78 78 88 81 82 83 &4 85 88 87 88 88 88 81 82 Year/Quarter

Direct Radar .ion LeveIs Natts Bar NucIear PI ant 0-Qu ar t,e r No v i ng Rve." age-L 63 A5 C3 o Q fO D-C rd E

0 (bsfte X Offs1te 78 7S 88 81 82 85 86 87 88 BS SB 91 SB Year ~Quar'+ er

Annual Avera ross Beta Activity Air Filters (pCi/Cubic Meter)

Browns Ferry Nuclear Plant p

C R Indicator Rl Control I

0 25 Preoperational Operational Phase Phase 0.2 u

b 0.15 Preoperational Average l

c o-l t

M 005 68 69 70 71 72 73 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 e 0 p

r Year

Annual Avera Sr-90 in Milk Browns Ferry uclear Plant

- Indicator .~ Control 20 y 18~

p Preoperational Operational Phase C 16 Phase I 14

/ 12 L 10 Preoperational Average 8

6 e ~a0 Q g p 4

2 0

68 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 Year

Annual Avera Cs-137 in Soil Browns Fer i uclear Plant

- Indicator '~ Control 2.5 Preoperational ase Operational Phase p

C 1.5 Preoperational Average g

r

'05o ~

tA a 0

+Y +o~ +s 8

~ Q o o s g ~~o 68 69 70 71 72 73p 73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 Year Note: Detector system changed from Nal to GeLi in 1977.

Annual Average s Beta Activity Surface Wa (pCi/Liter)

Browns Ferry Nuclear Plant

- Downstream ~ Upstream p

Preoperational Phase Operational Phase Preoperational Average 5

I 4

I L 3 e M Q I

2 e

68 69 70 71 72 73p73o 74 75 76 77 79 80 81 82 83 84 85 86 87 88 89 90 91 Year

• No gross beta measurements made in 1978

Annual Average ss Beta Activity Drinking Vla er (pCilLiter}

Browns Ferry Nuclear, Plant

- Indicator ~ Control Preoperational Operational Phase p Phase C 5 Preoperational Average I

4

/

L 3 6 o e~ 0 o=~~ o OQ I

0 t

e r

0 68 69 70 71 ?2-?Sp?3o?4 ?5 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 Year

~

Annu verage Cs-137 in h: Crappie Browns Ferry Nuclear Plant

- Downstream 0- Upstream 0.4 p 0.35 C 0.3 Preoperational Average 0.25 0.2 g Q r

a 0.15 0.1 Preoperational

~e o~ ~9 Operational phase 0

~~ o ~Mee O o ~

O e

e m 005 Phase 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 Year Note: Detector system changed from Nal to GeLi in 1978.

Ann verage Cs-137 in Fish: Smallmouth Buffalo, Flesh Browns Ferry Nuclear Plant 4- Downstream '~ Upstream 0.2 P reoperational Operational Phase p Phase C 015 I

Preoperational Average 0.1 g

0. 05 0 m

Q Q 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 Year Note: Detector system changed from Nal to GeLi in 1978.

0 Annu erage Cs-137 in Fish: Sm cmouth Buffalo, Whole Browns Ferry Nucelar Plant

~- Downstream '~ Upstream 0.18 P reoperational Operational Phase 0.16 p Phase 0.34 0.12 l 01 g 008 Preoperational Average 0.06 0.04 ~p 0.02 0 0 @~~0 0 69 70 71. 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 0 0 0 Year Note: Detector system changed from Nal to GeLi in 1978.

Annual Averag s-i37 in Sediment Browns Fe Nuclear Plant .

.- Downstream ~ Upstream 5T P reoperational Operational Phase 4.5 Phase p 4 35 3

2.5 Preoperational Average g

i.5

@~o~ow ~G~ o 0.5 0

o o o ~~ ~o o e

~o oo 69 70 7i 72 73 74 75 76 77 78 79 80 8i 82 83 84 85 86 87 88 89 90 9i Year Note: Detector system changed from Nal to GeLi in i977.

Annual Avera Co-60 in Sediment Browns Fe Nuclear Plant 4- Downstream .~ Upstream 0.7 ~

P reoperational Operational Phase 0.6 Phase p

0.5 I

0.4 Preoperational Average 0.3 o a 0 O~y m 01 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 Year Note: Detector system changed from Nal to GeLi in 1977.