ML18033B285

Annual Radiological Environ Operating Rept,Browns Ferry Nuclear Plant 1989. W/900501 Ltr

ML18033B285
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1989
From:	Wallace E TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9005070279
Download: ML18033B285 (241)

Text

ACCELERATED DI%lDBUTION DEMONSHRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9005070279 DOC.DATE: ~i~~

FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee NOTARIZED: NO DOCKET 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 WALLACE,E.G. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Annual Radiological~nviron Operating Rept,Browns Ferry Nuclear Plant 1989."( W/900501 ltr.

DISTRIBUTION CODE: IEZSD COPIES RECEIVED:LTR TITLE: Environmental Monitoring Rept (per Tech Specs)

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/i 4 TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 37401 I

5N 157B Lookout Place MAY 01 t890 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 1989 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 radiological environmental samples taken during the reporting period, in the format of Regulatory Guide 4.8,

4. Summary description of the radiological monitoring program,

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

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

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

If you have any questions,, please telephone Patrick P. Carier, BFN, Site Licensing, at (205) 729-3570.

Very truly yours, TENNESSEE VALLEY AUTHORITY

. G. Wallace, Manager Nuclear Licensing and Regulatory Affairs Enclosure cc: See page 2 9005070279 o259 R

An Equal Opportunity Employer

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U.S. Nuclear Regulatory Commission MAY 0 i 1980 cc (Enclosure):

Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One Hhite Flint, North 11555 Rockvi lie Pike Rockville, Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. B. A. Hi lson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NH, Suite 2900 Atlanta, Georgia 30323

TENlMSSEE VALLEYAUTHGRITY ANNUALRADIOLOGICALENVIRONMENTALOPERATING REPORT BROWNS FERRY NUCLEAR PLANT 1989 9QQ5Q70279 CHEMISTRY 3263 HA33IOLOGICAL SERVICES

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT BROWNS FERRY NUCLEAR PL'ANT 1989 I

TENNESSEE VALLEY AUTHORITY NUCLEAR ASSURANCE AND SERVICES CHEMISTRY AND RADIOLOGICAL SERVICES E

April 1990 f~

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TABLE OF CONTENTS Table of Contents ~ 11 List of Tables ~ ~ ~ ~ ~ ~ ~

iv List of Figures ~ ' ~ ~ ~ ~ ~ v Execut1ve Summary ~ ~ ~ ~ ~ 1 Introduction ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2 Naturally Occurring and Background Radioactivi ty ~ 2 Electric Power Production ~ 5 Site/Plant Description ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 Environmental Radiological Monitoring Program . . . . . . . . . . . 10 Direct Radiation Monitoring . 13 Measurement Techniques 13 Results ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 15 Atmospheric Monitoring 18 Sample Collection and Analysis ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 18 Results 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 20 Terrestrial Monitoring 21 Sample Collection and Analysis 21 Results 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ f ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 23 Aquatic Monitoring ~ ~ ~ ~ 26 Sample Collection and Analysis 26 "Results 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 28 Assessment and Evaluation 31 Results ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 32 Conclusions ~ ~ ~ ~ ~ ~ ~ ~ ~ 34 References ~ ~ ~ ~ ~ 35 Appendix A Environmental Radiological Monitoring Program and Sampling Locations ~ ~ ~ ~ ~ ~ ~ ~ 40 Appendix B 1989 Program Modifications ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ ~ ~ 52 11

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Appendix C Missed Samples and.Analyses . . . . . . . . . . . . . . 55 Appendix D Analytical Procedures . . . . . . . . . . . . . . . . . 58 Appendix E Nominal Lower Limits of Detection (LLD) . . . . . . . . 61 Appendix F Quality Control Program . ~ ~ ~ 66 Appendix G Land Use Survey . ~ ~ ~ 76 Appendix H Data Tables ~ ~ ~ ~ ~ ~ ~ o 82

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

Releases . . . . . . . . . . . . . . . . . . . . . . . . 37

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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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EXECUTIVE SUt NARY This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant (BFN) in 1989. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations.

Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations.

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

Small amounts of Co-60 were found in sediment samples downstream from the plant. This activity in river sediment would result in no measurable increase over background in the dose to the general public.

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

Most materials in our world contain trace amounts of naturally occurring radioactivity. Approximately 0.01 percent of all P otassium is radioacti ve potassium-40. Potassium-40 (K-40), with a half-life of 1.3 billion years, is one of the major types of radioactive materials found naturally in our environment. An individual weighing 150 pounds contains about 140 grams of potassium (Reference 1). This is equivalent to approximately 100,000 pCi of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body. Naturally occurring radioactive materials have always been in our environment. Other examples of naturally occurring radioactive materials are bismuth-212 and 214, lead-212 and 214, thallium 208, actinium-228, uranium-38, uranium-235, thorium-234, radium-226, radon-222, carbon-l4, and hydrogen-3 (generally called tritium).

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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 hours per day.

The avezage 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 geography'cai location, the part of the natural background radiation coming from this l~ radioactive material also depends upon the geographical location.

remainder of the natural background radiation comes from the radioactive Most of the materials within each individual s body. We absorb these materials from the food we eat which contains naturally occurring radioactive materials from the soil. An example of this is K-40 as described above. Even building materials affect the natural background radiation levels in the environment. Living or working in a,building which, is largely made of earthen material, such as concrete or brick, will generally result in a higher natural background radiation level than would exist if the same structure were made of wood.

This is due to the naturally occurring radioisotopes in the concrete or brick, such as trace amounts of uranium, radium, thorium, etc.

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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, lke people of Denver receive around 350 mrem/year total natural background i radiation average.

dose People equivalent compared to about in some 295 mrem/year for the national 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

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U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source Millirem/Year Per Person Natural background dose equivalent Cosmic 27 Cosmogenic 1 Terrestrial 28 In the body 39 Radon 200 Total 295 Release of radioactive material in natural gas, mining, milling, etc.

Medical (effective dose equivalent) 53 fallout N

Nuclear weapons less than 1 Nuclear energy 0.28

)0 Consumer products Total 0.03 355 (approximately)

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

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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 i that which results from natural background radiation.

the use of radiation and radioactive materials for It should be noted medical uses has resulted that

'in a similar effective dose equivalent to the U.S. population as that caused by natural background radiation.

'ignificant 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 t '

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 mremlyear. 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 (o'r 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.

I However, nuclear plants require many complex systems to control the nuclear fission process and to safeguard against the possibility of reactor malfunction, which could lead to the release of radioactive materials.

i small amounts of these fission and activation products are released into the Very plant systems. This radioactive material can be transported throughout plant systems and some of it released to the environment.

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

Releases are monitored at the onsite points of release and through an environmental monitoring program which measures the environmental radiation in outlying areas around the plant.

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h In this way, not only is the release of radioactive materials from the plant tightly controlled, but measurements are

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made in surrounding areas to ensure that the population is not being exposed to significant levels of radiation or radioactive materials.

Plant Technical Specifications limit 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.

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

Li uid Effluents Total body <3 mrem/year Any organ <10 mrem/year Gaseous Effluents Noble gases:

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

'Particulates:

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

Total body 25 mrem/year Thyroid 75 mrem/year Any other organ 25 mrem/year I

In addition, 10 CFR 20.106 provides maximum permissible concentrations (MPCs) for, radioactive materials'eleased to unrestricted areas. MPCs for the principal radionuclides associated with nuclear power plant effluents are presented in table l.

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t L SITE/PLANT DESCRIPTION s

The BFN is located on the north shore of Wheeler Reservoir at Tennessee River i Mile (TRM) 294 in Limestone County in north Alabama. Wheeler Reservoir averages 1 to l-l/2 miles in width in the vicinity of the plant. The site, r 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 the land is small, scattered villages and homes in an agricultural area. A number of relatively large fa'rming 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 three dairy farms are located within a 10-mile radius of the plant~

I Approximately 2000 people of Athens has a live within a 5-mile radius of the plant.

population of about 15,000, while approximately 40,000 people The town live in the city of Decatur. The largest city in the area with approximately 150,000 people is Huntsville, Alabama, located about 24 miles east of the site.

Area recreation facilities ar'e being developed. along the Tennessee River. The nearest facility is a commercial boat dock across the river from the site and.

I, two county parks located about 8 miles west-northwest of the site. The city of Decatur has developed a large municipal recreation area, Point Mallard Park, approximately 15 miles upstream from the site. The Tennessee River is also a popular sport fishing area.

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The BFN consists of three boiling water reactors; each unit is rated at 1098 megawatts (electrical). Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974. Unit 2 began commercial operation 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'". None of the units have operated since March 1985.

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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 1

a final 'verification that the systems are performing as planned. The monitoring program is designed to check the pathways between the plant and the people in the immediate vicinity and to most efficiently monitor these pathways. Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized. The environmental There are two primary pathways by which radioactivity can move through the environment to humans: air and water (see figure 2). The air pathway can be separated into two components: the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types of samples collected in this program are designed to monitor these pathways.

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

Terrestrial sampling stations were selected after reviewing such things as the locations of dairy 'animals and gardens in conjuction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and,sediment.

Table A-2-lists the sampling stations and the types of samples collected from each. Modifications made to the program in 1989 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 I monitoring program operation in 1973.

was initiated in Measurements 1968 and operated of the same until the plant began types of radioactive materials establish normal background levels for various radionuclides in the environment. This is very important in that during the 1950s, 60s, and 70s, atmospheric nuclear weapons testing occurred which released radioactive material to the environment causing fluctuations in the natural background radiation levels. This radioactive material is the same type as that produce'd in the BFN reactors. Preoperational knowledge of natural radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of whether the operation of BFN is impacting the environment and thus the surrounding population. The determination of impact during the operating phase also considers the presence of control stations

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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 I influence.

All samples are analyzed by the radioanalytical laboratory of TVA's Environmental Radiological Monitoring and Instrumentation Department located at the Western Area Radiological Laboratory (WARL) in Muscle Shoals, Alabama.

All analyses are conducted in accordance with written and approved procedures and are based on accepted methods. A summary of the analysis techniques and methodology is presented in appendix D. Data tables summarizing the sample analysis results are presented in appendix H.

I The sophisticated radiation detection devices used to determine the i radionuclide content of samples collected in the environment are generally quite sensitive to small amounts of radioactivity. In the field of radiation measurement, the sensitivity of the measurement process is discussed in terms of the lower limit of detection (LLD). A description of the nominal LLDs for the radioanalytical laboratory is presented in appendix E.

The radioanalytical laboratory employs a comprehensive quality assurance/

quality control program to monitor laboratory performance throughout the 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. A complete description of the program is presented in appendix F.

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DIRECT RADIATION MONITORING Direct radiation levels are measured at a number of stations around the plant site. These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and any radioactivity that may be present as a result of plant operations. Because of the relatively 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 'QFN site in 1989 were consistent with levels from previous years and with levels measured at other locations in the region.

Measurement Techni ues Direct radiation measurements are made with thermoluminescent dosimeters (TLDs). When certain materials are exposed to ionizing radiation, many of the electrons which become displaced are trapped in the crystalline structure of the material. They remain trapped for long periods of time as long as the material is not heated. When heated, the electrons are released, h

along with a pulse of light. A measurement of the intensity of the light is directly proportional to the radiation to which the material was exposed. Materials which display these characteristics are used in the manufacture of TLDs.

Since 1968 TVA has used a manganese activated calcium fluoride (Ca~F:Mn) TLD material encased in a glass bulb. The bulb is placed in an energy compens'ating shield to correct for energy dependence of the material.

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The TLDs are placed approximately 1 meter above the ground, with three TLDs at each station. Sixteen stations are located around the plant near the site boundary, one station in each of the 16 sectors. Dosimeters are also placed at the perimeter and remote air monitoring sites and at 19 additional stations out to approximately 32 miles from the site. The TLDs are exchanged every 3 months and read with a Victoreen Model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD. The .system meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 for environmental applications of TLDs.

In 1989, TVA began the process of changing from the Victoreen dosimeter to the Panasonic Model UD-814 dosimeter. This dosimeter contains four elements I consisting of one lithium borate and three calcium calcium sulfate phosphors are shielded by approximately 1000 mg/cm sulfate phosphors. The plastic radiation. These dosimeters are deployed in the same manner as the bulb detectors described above. 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

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three detectors. The values are corrected for gamma response, system variations, and transit exposure, with individual gamma response calibrations for each element. This system also meets or exceeds the performance

.specifications outlined in Regulatory Guide 4.13 for environmental

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yj Results For 1989, the results obtained with both the Victoreen and'he Panasonic dosimeters are included in this report. All results are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />). The stations are grouped according to the distance from the plant. The first group consists of all stations within 1 mile of the plant'. The 'second group 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 greater than 6 miles from the plant. Past data have shown that the results from all stations greater than 2 miles from the plant are essentially the same. Therefore, for purposes of this report, all stations 2 miles or less from the plant are identified as "onsite" stations and all others are considered "offsite."

Prior to 1976, direct radiation measurements in the environment were made with less sensitive dosimeters. 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'amma radiation levels determined from the TLDs deployed around BFN in 1989 are given in table H-1. The rounded average annual exposures are shown below.

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Annual Average Direct Radiation Levels mR/ ear WBN Victoreen Panasonic Victoreen Panasonic Onsite Stations 68 59 75 67 Offsite Stations 60 51 67 59 The data in table H-1 indicate that the average quarterly radiation levels at the BFN onsite stations are approximately 2-4 mR/quarter higher than levels at the offsite stations. This difference is also noted at the stations at WBN and other nonoperating nuclear power plant construction sites where the average levels onsite are generally 2-6 mR/quarter higher than levels offsite. The causes of these differences have not been isolated; however, it is postulated that the differences are probably attributable to combinations of influences such as natural variations in environmental radiation levels, l earth-moving activities onsite, construction of the plant.

and the mass of concrete employed in the Other undetermined influences may also play a part. These conclusions are supported by the fact that similar differences between onsite and offsite stations were measured in the vicinity of the WBN construction site Figure H-1 compares plots of the environmental gamma radiation levels from the onsite or site boundary stations with those from the offsite stations over 'the period from 1976 through 1989. To reduce the variations present in the data sets, a 4-quarter moving average I 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

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the curves are smoothed considerably. Figures H-3 and H-4 depict the environmental gamma radiation levels measured during the construction of TVA's WBN 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.

The procedures for the handling and readout of the Panasonic dosimeters and calculating the exposure from the raw data generated by the dosimeters were being developed during the year. The procedures were not finalized until the middle of the year, consequently, the data from the first two quarters were not generated in accordance with the finalized procedures. The data from the last two quarters of the year are within approximately 10 percent of the exposures calculated from the Victoreen dosimeters.

I All results reported in 1989 are consistent with direct radiation levels identified at locations which are not influenced by the operation of BFN.

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

~I l~ ATMOSPHERIC MONITORING L

The atmospheric monitoring network is divided into, three groups identified as L 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 areas 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.

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 i Vose LB5211 glass magnehelic gauge fiber for filter. The sampling system measuring the drop consists of a in pressure across the system, pump, a and a C

dry gas meter. This allows an accurate determination of the volume of air gO passing through the filter.

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

The filter is contained in a sampling head mounted on the outside of the monitor building. The filter is replaced every 7 days. Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 weeks composites of the filters from each location are analyzed by gamma spectroscopy. On a quarterly basis, all of the filters from a location are composited and analyzed for Sr-89,90.

On March 27, 1989, two of the stations were equipped with a second sampler.

The'filter from this sampler is analyzed weekly for gross alpha and composited quarterly for analysis of transuranic isotopes.

Gaseous radioiodine is collected using a commercially available cartridge L containing TEDA-impregnated char'coal. This system is designed to collect iodine in both the elemental form and as organic compounds. The cartridge is located in the same sampling head as the air particulate filter and is downstream of the particulate filter. The cartridge is changed at the same time as the particulate filter and samples the same volume of air. Each cartridge is analyzed for I-131. 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 from the tray, it is collected in one of two 5-gallon jugs inside the monitor building. A 1-gallon sample is removed from the container every 4 weeks. Any excess water is discarded.

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Samples are held to be analyzed only 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.

Results The results from the analysis of air particulate samples are summarized in table H-2. Gross beta activity in 1989 was consistent with levels reported in previous years. The average level at both indicator and control stations was 0.019 pCi/m . The annual averages of the gross beta activity in air particulate filters at these stations for the years 1968-1989 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.

i Evidence of a small increase seen in 1986. These resulting from the Chernobyl accident patterns are consistent with data from monitoring can also be L programs conducted by TVA at nonoperating nuclear 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. Likewise, concentrations measured in transuranic isotopes were all below the respective LLD. As shown in table H-3, iodine-131 was not detected at any of the indicator stations and was detected"'at one control station at a level slightly higher than the nominal LLD.

No rainwater samples from the vicinity of BFN were analyzed during this reporting period.

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

For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass where dairy cattle are grazing. When the cow ingests the radioactive material, some of it may be transferred to the milk and consumed by humans who drink the milk. Therefore, samples of milk, vegetation, soil, and food crops are collected and analyzed to determine the potential impacts from exposure to this pathway. The results from the analysis of these samples are shown in tables H-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, two dairy farms have been identified within 7 miles of the plant. These three dairies are considered indicator stations 'and routinely provide milk samples. In addition, the 1988 land use survey identified one farm producing milk for private consumption. Since insufficient quantities of milk are available for sampling, samples of vegetation are taken at this farm. The results of the 1989 land use survey are presented in appendix G.

Sam le Collection and Anal sis Milk samples are purchased every two weeks from three dairies within 7 miles of the plant and from at least one of two control farms. These samples are placed on ice for'ransport to the radioanalytical laboratory.

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A specific analysis for I-131 is performed on each sample and a gamma spectroscopy analysis and Sr-89,90 analysis are performed every 4 weeks.

Samples of vegetation are collected every 4 weeks for I-131 analysis. The samples are collected from the farm producing milk but unable to provide a milk sample, and from one control station. 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.

For the first 7 months of the year, vegetation samples were also taken from the dairy farms from which milk samples were obtained and from selected air monitoring stations. Effective August 23, 1989, the collection of these samples was dis'continued. The collection of other samples from these stations (for example, air, soil, or milk) was continued, as was the collection of vegetation from the two stations described above and the collection of food products from the area.

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 fo'r Sr-89,90 and transuranic isotopes.

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Samples representative of food crops raised in the area near the plant are obtained from individual gardens, corner markets, or cooperatives. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. In 1989 samples of corn, green beans, potatoes, tomatoes, and turnip greens were collected from local vegetable gardens. In addition, samples of apples and beef were also obtained from the area. The edible portion of each sample is prepared as if it were to be eaten and is analyzed by gamma spectroscopy. 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 IO results were bless Strontium-90 than the, established was found in little over nominal LLD of 0.2 half of the pCi/liter.

a samples. These levels are consistent with concentrations measured in samples collected prior to plant operation and with concentrations reported in milk as a result of fallout from atmospheric nuclear weapons tests (reference 1). The average Sr-90 concentration reported from indicator stations was approximately 3.4 pCi/liter. An average of 2.6 pCi/liter was identified in samples from control stations. By far the predominent 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.

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Similar results were reported for vegetation samples (table H-5}. An average of 5.8 pCi/kg of I-131 was identified in samples from indicator stations while 4.2 pCi/kg was measured at control stations. Average Cs-137 concentrations were 24.7 and 28.7 pCi/kg for indicator and control stations, respectively.

Strontium-90 levels averaged 96.7 pCi/kg from indicator stations and 104.0 pCi/kg from control stations. Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7.

The only fission or activation product identified in soil samples was Cs-137, with traces of Sr-89 identified. With a half-life of approximately 60 days, Sr-89 cannot be present in the environment as a result of plant operations or Previous nuclear weapons testing. The positive identification of Sr-89 is an artifact of the calculational process and the low concentrations the laboratory is attempting to detect. The maximum concentration of Cs-137 was 1

approximately 0.6 pCi/g which is consistent with levels previously reported from fallout. All Sr-90 values were less than the nominal LLDs. All other radionuclides identified in the gamma spectral analysis were naturally occurring isotopes (table H-6).

Transuranic analyses were performed for the first time in 1989. The procedures employed are still in the developmental stage. The analytical.

yields were very low and the values obtained imprecise. The results generally agreed with the concentrations reported by the Electric Power Research Institute (EPRI) in Reference 4.

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The EPRI report concludes that essentially all of the radionuclides in soils from around the nuclear power plants participating in the study (including BFN) were of fallout origin and that the variations in concentrations were a function 'of soil texture, soil permeability, and/or disturbances of 'the soil surface.

Only the naturally occurring K-40 was. identified in food crops. As noted earlier, K-40 is one of the major radionuclides found naturally in the environment and is the predominant radioactive component in normal foods and human tissue. Gross beta concentrations for all indicator samples were consistent with the control values. Analysis of these samples indicated no contribution from plant activities. The results are reported in tables H-7 through H-13; i

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A UATIC MONITORING Potential exposures from. the liquid pathway can occur from drinking water, ingestio'n 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-21. Radioactivity levels in water, fish, and clams were consistent with background and/or fallout levelspreviously reported. The presence of Co-60,- Cs-134, and Sr-90 was identified in sediment samples; however, the projected exposure to the public from this medium is negligible.

Sam le Collection, and Anal sis Samples of surface water are collected from the Tennessee River using automatic sampling pumps from two downstream stations and one upstream station. A timer turns on the pump at least once every 2 hours. The line is flushed and a sample collected into a composite jug. A 1-gallon sample is removed from the composite jug weekly and the remaining water in the jug is discarded. A 4-week composite'ample is prepared from the weekly samples and analyzed by gamma spectroscopy and for gross beta activity. A quarterly composite sample is analyzed for Sr-89,90 and tritium.

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Samples are also collected, by an automatic sampling pump at the first downstream,.drinking water intake. These samples are collected in the same manner as the surface water samples. These weekly samples are analyzed by gamma spectroscopy and for gross beta activity. At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source. These samples are analyzed every 4 weeks by gamma spectroscopy and .for gross beta activity. A quarterly composite sample from each station is analyzed for Sr-89,90 and tritium. The sample collected by the automatic pumping device is taken directly from the river at the intake P

structure. Since the sample at this point is raw water, not water processed through the* water treatment plant, the control sample should also be unprocessed water. Therefore, the upstream surface water sample is also considered as a control sample for drinking water.

Groundwater is sampled from an onsite well and from a private well in an area unaffected by BFN. The samples are collected every 4 weeks and analyzed by I

gamma spectroscopy. A quarterly composite sample is analyzed for tritium.

Samples of commercial and game fish species are collected semiannually from each of three reservoirs: the reservoir on which the plant is located (Wheeler Reservoir), the upstream reservoir (Guntersville Reservoir), and the downstream reservoir (Wilson Reservoir). The samples are collected using a combination of netting techniques and electrofishing. Most of the fish are filleted, but one group is processed whole for analysis. After drying and grinding, the samples are 'analyzed by gamma spectroscopy. When the gamma analysis is completed, the sample is ashed and analyzed for gross beta activity.

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L I Bottom sediment is collected semiannually from selected locations using

,e a TRM dredging apparatus. The samples are dried and ground and analyzed by gamma spectroscopy. After this analysis is complete, the samples are ashed and r analyzed for Sr-89,90.

r Samples of Asiatic clams are 'collected from the same locations as the bottom

'sediment. The clams are usually collected in the dredging process with the sediment. 'owever, at times the clams are difficult to find and divers must be used. 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.

Re'suits I All radioactivity in surface water samples was below the LLD except the gross beta activity and trace amounts of Sr-89 in one sample. As noted earlier, the positive identification of Sr-89 is an artifact of the calculational process and the low concentrations the laboratory are attempting to detect. These results are consistent with previously reported levels. A trend plot of the gross beta activity in surface water samples from 1968 through 1989 is presented=in figure H-6. A summary table of the results for this reporting period is shown in table H-14.

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For public water, average gross beta activity was 2.7 pCi/liter at the downstream stations and 2.6 pCi/liter at the control stations. Sr-89 was identified in one downstream sample and one upstream sample. As noted above, .

the identification of Sr-89 in environmental samples is an artifact of the calculational process. 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-7.

Concentrations of fission and activation products in groundwater were all below the LLDs. Only naturally occurring radionuclides and trace amounts of Sr-89 were identified in these samples. The results are presented in table identification of Sr-89 in environmental r H-16.

an As noted above, the artifact of the calculational process.

samples is Iy Cesium-137,was identified in four fish samples. The downstream samples averaged 0.08 pCi/g while the upstream sample averaged 0.13 pCi/g. The only I other radioisotope found in fish was values ranged from 3.6 pCi/g to 18.9 pCi/g.

the naturally occurring K-40.

The maximum gross beta These activity I measured in downstream samples was 36.2 pCi/g, while the maximum value in upstream samples was 31.9 pCi/g. These results, which are summarized in tables H-17, H-18, and H-19, indicate that the Cs-137 activity is probably a result of fallout or other upstream effluents rather than activities at BFN.

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.0 Radionuclides 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-90. The average levels of Cs-137 were 0.58 pCi/g in downstream samples and 0.22 pCi/g upstream. The Cs-137 concentration at downstream stations is approximately double the activity in upstream samples. This same relationship was reported from these stations during the preoperational phase C

of the monitoring at BFN, indicating that the levels reported herein are probably not the result of BFN operations.

Cobalt-60 concentrations in downstream samples averaged 0.18 pCi/g, while concentrations upstream averaged 0.02 pCi/g. The maximum concentrations were 0.50 and 0.04 pCi/g, respectively. Cesium-134 concentrations in upstream samples were all below the LLD. Levels in downstream samples averaged 0.04 pCi/g, with a maximum of 0.05 pCi/g. A concentration of 0.7 pCi/g .of Sr-90 was identified in one downstream sample, while the concentrations in upstream samples were all less than the LLD. Sr-89 was identified in two samples, but as noted earlier, the identification of Sr-89 in environmental samples is an artifact of the calculational process. A realistic assessment of the impact to the general public from this activity produces a negligible dose equivalent. Results from the analysis of sediment samples are shown in table H-20.

Only naturally occurring radioisotopes were identified in clam flesh samples.

The K-40 concentrations, presented in table H-21, ranged from 2.02 to 4.95 pCi/g.

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-0 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 provided by the NRC in Regulatory Guide 1.109 for determining the 'ethodology potential dose to individuals and populations living in the vicinity of a I nuclear power plant.

a "maximum exposed The doses individual."

calculated are Some a representation of the dose to 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 I~ the public may receive an exposure. As indicated in figure 2, the two ma)or ways by which radioactivity is introduced into the environment are through liquid and gaseous effluents.

For liquid effluents, the public can be exposed to radiation from three'ources:

drinking water from the Tennessee River, eating fish caught .in the Tennessee River, and direct exposure to radioactive material due to activities on the banks of the river (recreational activities). Data used to determine these doses are based on guidance given by the NRC for maximum ingestion rates, exposure times, and distribution of the material in the river.

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

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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 meteorological conditions to determine the distribution of- the effluents in the atmosphere. Again, as many of the parameters as possible are based on actual site-specific data.

Results The estimated doses to the maximum exposed individual due to radioactivity released from BFN in 1989 are presented in table 2. These estimates were made using the measured concentrations of the liquid and gaseous effluents. Also shown are the technical specification limits for these doses and a comparison between the calculated dose and the corresponding limit. The maximum calculated whole body dose equivalent from measured liquid effluents as presented in table 2 is 0.026 mrem/year, or 0.9 percent of the limit. The maximum organ dose equivalent from gaseous effluents is 0.001 mrem per year.

This represents less than 0.1 percent of the technical specification limit. A more complete description of the effluents released from BFN and the corresponding doses projected from these effluents can be found in the BFN "Semiannual Radioactive Effluent I Release Reports."

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

During this report period, Co-60, Cs-134, Cs-137, and Sr-90 were seen in aquatic media. The distribution of Cs-137 in sediment is consistent with fallout levels identified in samples both upstream and downstream from the plant during the preoperational phase of the monitoring program. Co-60, Cs-134, and Sr-90 were identified in sediment samples downstream from the plant in,concentrations which would produce no measurable increase in the dose l 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 Sr-90 and Cs-137 are consistent with levels measured in TVA's preoperational environmental radiological monitoring programs.

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Conclusions It is .concluded from the above analysis of the environmental sampling r'esults 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.

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REFERENCES

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

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

September 1987.

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

4. Electric Power Research Institute, Report No. EPRI EA-2045, Project 1059,

'Transuranium and Other Long-Lived Radionuclides in the Terrestrial Environs of Nuclear Power Plants," September 1981.

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

~Ci /1* gCI/m'*

Gross beta 3,000 100 H-3 3,000,000 200,000 Cs-137 20,000 500 Ru-103,106 10,000 200 Ce-144 10,000 100 Zr-95 Nb-95 60,000 1,000 Ba-140 La-140 20,000 1,000 I-131 300 100 Zn-65 100,000 2,000 Mn-54 100,000 1,000

'o-,60 30,000 300 Sr-89 Co-58'n 3,000 300 Sr-90 . 300 30 Cr-51 2,000,000 80,000 Cs-134 9,000 400 90,000 2,000

• 1 pCi = 3.7 x 10 'q.

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

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Table 2 Maximum Dose due to Radioactive Effluent Releases Browns Ferry Nuclear Plant 1989 mrem/year Li uid Effluents 1989 NRC Percent of EPA Percent of

~Te Dose Lim/t NRC Limit Limit EPA Limit Total Body 0.026 0.9 25 0.1 Any Organ 0.038 10 0.4 25 0.15 Gaseous Effluents 1989 NRC Percent of EPA Percent of

~Te Dose Limit NRC Limit Limit EPA Limit .

Noble Gas 0.0 10 N/A 25 N/A (Gamma)

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

Any Organ 0.001 15 0.007

• 25 0.004 I

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Figure 2 ENVIRONMENTALEXPOSURE PATHWA'lt'S OF MAN DUE TO RELEASES OF RADIOACTIVE MATERIAL TO THE ATMOSPHERE ANO LAKE.

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Diluted- By Atmosphere Airborne Releases Plume Exposure

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Liquid Releases By Lake:'iluted IVIA,M Animals Consumed By Man (Milk,Meat) Shoreline Exposure I'ish Consumed By Animals Drinking Water 'L 8 rt Vegetation .

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~I APPENDIX A .

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM AND SAMPLING LOCATIONS I

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BROMNS FERRY NUCLEAR PLANT Environmental Radiological Honitoring Program'xposure Pathway Number of Samples and Sampling and Type and Frequency AIRBORNE Particulates Six samples from locations Continuous sampler operation Particulate sampler.

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

Two samples from control Perform gamna 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 ganna in coamunities approximately isotopic analysis on 10 miles from the plant composite (by location)

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

Radioiodine Same 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 gaama nuclides particulate once per 31 days only if radioactivity in other media indicates the presence of increased levels of fallout 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 Ganma dose once per 92 days at locations (in different sectors) at or near the site boundary in each of the 16 sectors

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

Exposure Pathway Number of Samples and Sampling and Type and Frequency Two or more dosimeters placed At least once per 92 days Gamma dose once per 92 days at stations located greater than 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 One sample upstream (TRH 305.0) Collected by automatic Gross beta and gamma scan on One sample immediately down- sequential-type sampler 4-week composite. Composite stream of discharge (TRH 293.5) with composite sample taken for Sr-89, Sr-90, and tritium One sample downstream from at least once per 7 at least once per 92 days plant (TRH 285.2) days'ollected Orinking One sample at the first by automatic Gross beta and gamma scan on potable surface water sequential-type sampler weekly composite. Composite supply downstream from the with composite sample taken for Sr-89, Sr-90, and tritium plant (TRH 282.6) at least once per 7 days at least once per 92 days Two additional samples of Grab sample taken at Gross beta and gamma scan on potable surface water down- least once per 31 days 4-week composite. Composite stream from the plant for Sr-89, Sr-90, and tritium (TRH 274.9 and TRH 259.5) at least once per 92 days One sample at a control location (TRH 306)

One additional sample at Collected by automatic a control location 4 sequential-type sampler (TRH 305) with composite sample taken at least once per 7 days Ground One sample adjacent to the-- Collected by automatic Ganja 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

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Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program'xposure Pathway Number of Samples and Sampling and Type and Frequency 1 r n One sample at a control Grab sample taken at Ganma scan on each location upgradient from least once per 31 days composite. Composite for the plant (Farm L) Sr89, Sr-90, and tritium at least once per 92 days A(VATIC Sediment Two samples upstream from At least once per 184 days Gamma scan, Sr-89 and Sr-90 discharge point (TRM 297.0 analyses and 307.52)

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

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

INGESTION Milk At least 3 samples from At least once per 15 days I-131 on each sample. Gaama dairy farms in the immediate when animals are on pasture; scan, Sr-89 and Sr-90 at least vicinity of the plant (Farms at least once per 31 days once per 31 days 8, Bn, and L) at other times At least one sample from control loction (Farm Be and/or Gl)

Fish Three samples representing At least once per 184 days Gross beta and galena scan at coaeercial and game species least once per 184 days on in Guntersville Reservoir edible portions above the plant Three samples representing comnercial and game species in Wheeler Reservoir near the plant and in Wilson Reservoir downstream from plant.

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Table A-1 BROMNS FERRY NUCLEAR PLANT Environmental Radiological Honi toring Program'xposure Pathway Number of Samples and Sampling and Type and Frequency Cl ams Samples from same locations Same as sediment Galena scan on flesh only as sediment (if available)

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

Control samples from one one control dairy (Farm 0)

a. The sampling program outlined in this table is that which was in effect at the end of 1989.

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

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

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

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Table A-2 BRONNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Map Approximate Indicator (I) r Location Number' Station Sector Distance (miles) or Control (C) les Collected'P,CF,R,S PM-1 NW 13.8 2 PM-2 NE 10.9 AP,CF,R,S 3 PM-3 SSE 7.5 AP,CF,R,S 4 LM-7 N 2.1 AP,CF,R,S 5 RM-1 N 31.3 AP,CF,R,S 6 RM-6 E 24.2 AP,CF,,R,S

'7 LM-1 N 0.97 AP,CF,R,S 8 LM-2 NNE 0.88 AP,CF,R,S 9 LM-3 ENE 0.92 AP,CF,R,S 10 LM-4 LM-6 Farm B NNN SSN NNN 1.7 3.0 6.8 C'am AP,CF,R,S AP,CF,R,S M

Farm Bn N 5.0 M farm L ENE 5.9 M,W Farm WSN 35.0 M,V Gl'arm NE 6.8 V 22 No, 6 N'ell NW 0.02 N 23 TRH'82.6 PW 24 'TRH 306 ' 11.4'2.O'1.3 PW 25 Muscle Shoals, AL PN 26 TRH 274.9 PN 27 TRH 285.2 SN 28 TRH 293.5 19.1'.S'.5'1.0'3.52' SN 29 TRM 305.0 SN 30 TRH 307.52 'L,SD 31 TRM 293.7 CL,SD 32 TRM 288.78 CL,SD 33 TRM 277.98 3'.22'6.02'8.8 CL,SD 34 Farm Be NW H 35 Farm 0" E 26.2 M,V 36 Farm T WNN 3.3 V 37 TRH 297.0 3.0 CL,SD Wilson Reservoir'TRH F

259-275)

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

I Map Approximate Indicator (I)

Location Distance or

. Numb'er'tation Sector (miles) Control (C) Sam les Wheeler Reservoir'TRM 275-349)

Guntersville Collected'ee Reservoir'RM (349-424) figures A-l, A-2, and A-3.

Sample Codes:

AP Air particulate filter R Rainwater CF = Charcoal filter (Iodine) S = Soil GL Clams SD Sediment F = Fish SW = Surface water M = Milk V = Vegetation PW Public drinking water W Well water Sampling begun May 15, 1989.

Sampling discontinued August 14, 1989.

TRM - Tennessee River Mile Miles from plant discharge (TRM 294).

Also used as a control for public water, Dairy out of business. Last sample collected April 4, 1989.

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i Table A-3 BROHNS FERRY NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) Locations i

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

NW-3 NW 13.8 Off 2 NE-3 NE 10. 9 Off 3 SSE-2 SSE 7.5 Off 5 H-3 W 31. 3 Off 6 E-3 E 24.2 Off 7 N-1 N 1.0 On 8 NNE-1 NNE 0.9 On 9 ENE-1 ENE 0.9 On 10 NNW-2 NNH 1.7 On 38 N-2 N 5.0 Off 39 NNE-2 NNE 0.7 On 40 NNE-3 NNE 5.2 Off NE-1 NE 0.8 On I",', NE-2 ENE-2 E-1 NE ENE E

5.0 6.2 0.8 Off Off On E-2 5.2 Off I

E ESE-1 ESE 0.9 On ESE-2 ESE 3.0 Off 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 SSW-1 SSW 3.0 Off 54 SSW-2 SSW 4.4 Off 55 SW-1 SW 1.9 On 56 SW-2 SW 4.7 Off 57 SW-3 SW 6.0 Off 58 WSW-1 WSW 2.7 Off 59 WSW-2 WSW 5.1 Off 60 WSW-3 WSH 10.5 Off W-1 W 1.9 On i 65 H-2 W-4 WNH-1 WNW-2 W

W WNW WNW 4.7 32.1 3.3 4.4 Off Off Off Off 66 NH-1 NH 2.2 Off 67 NW-2 NW 5.3 Off i0 I

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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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Figure A-1 Environmental Radiological Sampling Locations

. Within 1 Mile of Plant 348.75 NNW 326.2 7 33.75

~ 8 303.75 39 56.25 9 ENE WNW 28 I

81.25 w

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258.75 I r BROWNS FERRY IIIIIII 101.25 NUCLEAR PLANT. ~ 46 48 ESE wsw 123.75 236.25

.. Sw SE 213.75 146.25 ssw 675 SSE S Scale I Mile

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Figure A-2 Environmental Radiological Sampling Locations From 1 to 5 Miles From The Plant 348.75 11.25 NNW 36 NNE 326.25 33.75 Nw I NE 42 ~

303,75 56.25 P

WNW 48. ENE

~ 6 65 ~ 10 78.75 36,64

~ 62 BROWNS FERI1Y NUCI.EAR PLANT I

258.75 I 47 NN P

WSW ESE 46

/I, 236.25 53 123.75 51 SW 56 ~SE

~ 54 213.75 I 146.25 I

52j SSE SSW SCALE 0 0.5 I 05 191.25 168.75 MILES IJ 4

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iguge Locations SarAPGng Radlologlcal Thee Plant Envlronroenta tal a Frotn bNles Than 6 G ate>

11.25 348.7 5 33.75 326.25 AeHEHCEBVBB 56.25 FASSttS'PILLS PVLASKI SHE 78.75 AtH'SHS VHtSVILLE

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,2 SSSY sHoAL tAvscLS Oo 3

Baht VB N.LE OS'IAV All AQAB 123.75

<a.LE BVSSS 18 CVLtJhAH LE HAL6'(VI 326.2

%Ilail 146.25 than.KS 0

SSS 168.75 SSVf ~

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APPENDIX B 1989 PROGRAM MODIFICATIONS gt

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APPENDIX B Environmental Radiolo ical Monitorin Pro ram Modifications During 1989, a small number of modifications were made in the environmental monitoring program.

In addition to the air and milk samples collected from the vicinity of the plant, vegetation (grass) samples have been collected for several years. The results produced during this time indicate that the air and milk samples provide an earlier indication of changes in environmental concentrations than do the vegetation samples. Therefore, vegetation sampling has been discontinued at all but two stations. Collection of the other scheduled samples from these stations continues.

In an effort to track the concentrations of transuranic isotopes in the vicinity of BFN, analysis for these isotopes was initiated in air and soil samples during the period. Air particulate filters are also screened weekl'y by a gross alpha an'alysis.

One of the control dairy farms went out of business and was replaced by another farm. In addition, since the Technical Specifications only require the collection of milk samples every two weeks, milk sampling was reduced from weekly to once every two,weeks.

The following table lists the changes in the monitoring program in 1989.

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1~ Table B-1 l Environmental Radiolo ical Monitorin Pro ram Modifications L

Date Station Location Remarks 3/27/89 LM-1 1.0 miles N Add analysis for transuranic isotopes 1 RM-6 23.0 miles E in air and soil samples and gross alpha activity in air filters.

) 4/24/89 Farm 0 26.2 miles E Deleted from the program when the farm went out of the dairy business.

5/15/89 Farm Gl 35 miles WSW Added to the sampling program to replace'arm 0.

8/14/89 Farm W 6.8 miles NE Sampling discontinued after the owner di continued milking operations.

LM-1 1.0 miles N Vegetation (grass) sampling L'M-2 0.9 miles NNE discontinued at all but two stations.

LM-3 0.9 miles ENE LM-4 1.7 miles NNW LM-6 3.0 miles SSW LM-7 2.1 miles W RM-1 31.3 miles W Farm B 6.8 miles NNW Farm Bn 5.0 miles N Farm L 5.9 miles ENE Farm W 6.8 miles NE 8/28/89 Farm B 6.8 miles NNW The collection of milk samples was Farm Bn 5.0 miles N changed from weekly to once every Farm L 5.9 'miles ENE two weeks.

Farm T 3.3 miles WNW Farm Gl 35 miles WSW Farm Be 28.8 miles NW L

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APPENDIX C MISSED SAMPLES AND ANALYSES

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Appendix C Missed Sam les and Anal ses During 1989, a small number of samples were not collected and analyses were 4

not completed on some collected samples. Those occurrences resulted in deviations from the scheduled program but not from the program required by the Technical Specifications. Table C-1 lists these occurrences. A general description follows.

Two milk samples were missed because the farm providing the samples went out of the dairy business and one milk sample was lost during analysis. Three samples (two air and one well water) were not collected because of equipment malfunction, and two samples (one milk and one vegetation) were destroyed during processing, preventing complete analysis. Two well water samples were not available for collection as a result of damage to the electrical power supply cable. Missed milk samples were from extra sampling locations, equipment malfunctions were corrected, and the analyst responsible for the destroyed samples received additional training to prevent recurrence.

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Table C-1 Environmental Radiolo ical Monitorin Pro ram Deviations Date Station Location Remarks 3/6/89 LM-1 1.0 miles N Air particulate and charcoal (iodine) sample not collected as t

a result of sampler malfunction.

3/20/89 Farm Be 28.8 miles NW Milk sample lost or destroyed before analysis for I-131 done.

4/17/89 Well 6 Onsite Hell water not available because of electrical malfunction.

5/1/89, Farm 0 26.2 miles E Milk sample not available Farm out of business.

5/8/89 Farm 0 26.2 miles E Milk sample not available - Farm out of business.

5/22/89 PM-3 7.5 miles SSE Air particulate and charcoal (iodine) sample not collected as a result of sampler malfunction.

11/6/89 Farm T 3.3 miles WNW Vegetation sample lost during iodine analysis.

ll/20/89 ,Well 6 Onsite Well water not available as a result of damage to the electrical supply system.

12/18/89 Hell 6 Onsite Hell water not available as a result of damage to the electrical supply system.

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APPENDIX D ANALYTICALPROCEDURES

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APPENDIX D Anal tical Procedures All analyses 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.

r 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, transfering to a stainless steel planchet and completing the evaporation process. For solid samples, a specified amount of the sample is packed into a deep stainless steel planchet. Air particulate filters are counted directly in a shallow planchet.

The specific analysis of 1-131 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 h

concentrations can be determined.

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Water samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintillation. A commerically 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 HYPERNET.

The gaseous radioiodine analyses are performed with well-type NaI detectors interfaced with a single channel analyzer. The system is calibrated to measure 1-131. 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 performe'd 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 fraction are each electroplated onto stainless steel discs, and counted for 1000 minutes on an alpha spectrometer employing a surface barrier detector.

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APPENDIX E NOMINAL LOWER LIMITS OF DETECTION (LLD)

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Appendix E Nominal Lower Limits of Detection Sensitive radiation detection devices can give a signal or reading even when 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, 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,'ny 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.

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Every time an activity is calculated fro'm 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 of its capability. For a sample with no measureable activity, which often happens, about half the time its signal should fall below the average machine background and half the time it should be above the background. If a signal above the background is present, the calculated activity is compared to the calculated LLD to determine if there is really activity present or if the number is an artifact of the way radioactivity is measured.

A number of factors influence the LLD, including sample size, count time, counting efficiency, chemical processes, radioactive decay factors, and k interfering isotopes encountered in the sample. The most likely values for these factors have been evaluated for the various analyses performed in the envir'onmental monitoring program. The nominal LLDs calculated from these values, in accordance with the methodology prescribed in the Technical Specifications, are presented i'n the following table.

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 that the LLD.

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Table E-1 Hominal LLD Values A. Radiochemical Procedures Charcoal Sediment Air Filters Filters Hater Hi lk Fi sh Fl esh Hhole Fish Food Crops and Soil

~(Ci /I'> ~(Ci /m') ~(Ci /L> ~(Ci /L> (Ci/ dr)

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 S tronii um-90 0.0003 1.4 2.0 0.04 0.09 0.3 Het Vegetation Clam Flesh Heat

( Ci/k Het) ( Ci/ Dr ) ( Ci/k Het)

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

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

Air Water Vegetation Wet Soil and. Foods, Tomatoes Meat and Parti cul ates and Milk and Grain Vegetation Sediment Fish Clam Flesh Potatoes, etc. Poultry m&m3 zQLL uQL~in uCiLk~& uCiQ~in uUL~ Q lb Ce-141 .005 10 .07 28 .02 .07 .15 10 25 Ce-144 .01 33 .25 100 .06 .25 .50 33 50 Cr-51 .02 45 .45 180 .10 .45 .94 45 90 I-131 .005 10 .09 36 .02 .09 .18 10 20 Ru-103 .005 5 .05 20 .01 .05 .11 5 15 Ru-106 .02 40 .48 190 .09 .48 .95 40 95 Cs-134 .005 5 .07 28 .01 .07 .11 5 15 I Cs-137 .005 5 .06 24 .01 .06 .10 5 15 col Zr-95 .005 10 .11 44 .02 .11 .19 10 25 I Nb-95 .005 5 .06 24 .01 .06 .11 5 15 Co-58 .005 5 .05 20 .01 .05 .10 5 15 Mn-54 .005 5 .05 20 .01 .05 .10 5 15 Zn-65 .005 10 .11 44 .01 .11 .21 10 25 Co-60 .005 5 .07 28 .01 .07 .11 . 5 15 K-40 .04 150 1.00 400 .20 1.00 2.00 150 300 Ba-140 .01 25 .23 92 .05 .23 .47 25 50 La-140 .005 8 .11 44 .02 .11 .17 8 20 Fe-59 .005 5 .10 40 .01 .10 .13 5 15 Be-7 .02 45 .50 200 .10 .50 .90 45 100 Pb-212 .005 20 .10 40 .02 .10 .25 20 40 Pb-214 .005 20 .20 80 .02 .20 .25 20 40 Bi-214 .005 20 .12 48 .04 ~ 12 .25 20 40 Bi-212 53 .40 40 .25 .40 53 Tl-208 .001 7 .03 26 .02 .03 .35 7 Ra-224 .30 Ra-226 .05 Ac-228 ~ 014 25 .10 80 .10 .10 1.00 22 22 Pa-234m 700 3.00

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APPENDIX 'F QUALITY ASSURANCE/QUALITY CONTROL PROGRAN el I

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Appendix F ualit Assurance/ ualit Control Pro ram A thorough quality assurance program is employed by the laboratory to ensure that the environmental monitoring data are reliable. This program includes the use of written, approved procedures in performing the work, a 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 samples along with routine samples.

Radiation detection devices are complex and can be tested in a number of ways. There are two primary tests which are performed I

on all devi'ces. In the first type, the device is operated without a sample on the detector to determine the background count. rate. The background counts are usually low values and are due to machine noise, cosmic rays, or trace amounts of radioactivity in the materials used to construct the detector. Charts of background counts are kept and monitored to ensure that no unusually high or low values are encountered.

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

C 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.

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

Blanks are samples which contain no measureable 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.

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Duplicate samples are generated at random by the same computer program which schedules the collection of the routine samples. For example, if the routine program calls for four milk samples every week, on a random basis each farm might provide an additional sample several times a year. These duplicate samples are a'nalyzed along with the other routine samples. They provide information about the variability of radioactive content in the various sample media.

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

Analytical knowns are another category of quality control sample. A known amount of radioactivity is added to a sample medium by the quality control staff or by the analysts themselves. The analysts are told the radioactive content of the sample. Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run. In this way, the analysts have immediate knowledge of the quality of the measurement process.

A portion of these samples are also blanks.

Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples. The analyst does not know they contain radioactivity. Since the bulk of the ordinary workload of the environmental laboratory contains no measureable activity or I

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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 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 1 any unusual radioactivity whatsoever.

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

added and are presented These samples have a known amount of radioactivity to the analysts labeled as cross-check samples. This I means that the quality control staff answer" but the analysts. do not.

knows the radioactive content or "right They are aware they are being tested. Such 1 samples test the best performance of the laboratory by determining if the i analysts can find the "right answer."

the accuracy of the measurement process.

These samples provide information about 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 NO I

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the primary indicator of laboratory performance. They provide an independent check of the entire measurement process that cannot be easily provided by the laboratory itself. That is, unlike internal cross-checks, EPA cross-checks test the calibration of the laboratory detection devices since different radioactive standards produced by individuals outside TVA are used in the cross-checks. The results of the analysis of these samples are reported back to EPA which then issues a report of all the results of all participants.

These reports are examined very closely by laboratory supervisory and quality control personnel. They indicate how well the laboratory is doing compared to others across the nation. Like internal cross-checks, the EPA cross-checks information to the laboratory about the precision and accuracy of the'rovide radioanalytical work it does. The results of TVA's participation in the EPA Interlaboratory Compariso'n 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 Eastern Environmental Radiation Facility in Montgomery, Alabama. When radioactivity has been present in the environment in measureable quantities, such as following atmospheric nuclear weapons testing, 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.

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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 L help or improvement. The end result is a measurement process that provides accurate data and is sensitiveenough to measure the presence of radioactivity I~

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

Gross Al ha Gross Beta Strontium-90 Cesium-137 EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Date ~33 a A~v. ~+3 a A~v ~33 a A~v ~A3 a A~v 3/89 21+9 23 62+9 65 20+2.6 20+9 20 8/89 6+9 9 10+9 10 B. Radiochemical Analysis of Water (pCi/L)

Gross Beta Strontium-89 Strontium-90 Tritium Iodine-131 EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Date ~33 a A~v. ~+3 a A~v ~A3 a A~v. ~33 a A~v ~+3 a A~v.

1/89 4+9 40+9 30b 25+2.6 23 2/89 2754+617 2690 106+19 98 3/89 4/89c 8+9 8+2.6 4/89 5/89 50+9 47 6+9 (5 6+2.6 6/89 4503+779 4100 7/89 8/89 83+14 77 9/89 6+9 10/89 3496+630 3353 10/89c 15+9 15 7+2.6 11/89 12/89

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Table F-1 RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM (Continued)

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

Barium-133 or Chromium-51 Cobalt-60 Zine-65 Ruthenium-106 Cesium-134 Cesium-137 EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Date ~33 a A~v ~+3 a A~v. ~33 a A~v. ~33 a A~v ~A3a A~v ~33 a A~v 2/89 4/89c 235+42 235 10+9 ll 159+28 159 178+31 166 10+9 20+9 10 19 10+9 20+9 ll 20 6/89 49+ 9 49 31+9 31 165+29 171 128+23 124 39+9 38 20+9 21 10/89 59+10 58 30+9 30 129+23 129 161+28 150 29+9 26 59+9 59 I 10/89c 5+9 5 5+9 6 D. Mi.lk (pCi/L)

Strontium-89 Strontium-90 Iodine-131 Cesium-137 Potassium-40d EPA Value .TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Date ~+3 a A~v ~33 a A~v. ~+3 a A~v ~33 a A~v ~+3 a A~v 4/88 39+9 24b 55+5 53 50+9 49 1600+139 1633

Footnotes for Table F-1 Results Obtained in Interlaboratory Comparison Program

a. Change in sample matrix resulted in lost analysis Procedure revision in progress to accomodate new matrix.

b. The low strontium result was investigated. A definitive cause for the low result could not be identified. Further evaluation of the strontium radioanalytical procedure continues.

c. Laboratory Performance Evaluation Study.

d. Units are milligram of total potassium per liter'ather than picrocuries of K-40 per liter.

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APPENDIX G LAND USE SURVEY

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

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

From these data, radiation doses are projected for individuals living near the plant. 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. These doses are calculated using design basis source terms and historical meteorological data.

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Air submersion doses were calculated for the same locations as in 1988, with the resulting values almost identical to those calculated in 1988.

Doses for ingestion of home-grown foods were also calculated for the same locations as 1988, resulting in values only slightly different from the previous doses.

For milk ingestion, projected annual doses decreased slightly at three locations as a result of a change in the age of the receptors. In all three cases, the milk was consumed by teens in 1989 as opposed to children in 1988.

One farm was dropped from the sampling schedule in 1989 as a result of the disposal of all milk-producing animals in 1988.

Tables G-l, G-2, and G-3 show the comparative calculated doses for 1987 and 1988.

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Table G-1 BROWNS FERRY NUCLEAR PLANT Projected Annual Air Submersion Dose to the Nearest Resident (Within 5 miles) mrem/year/reactor 1988 Surve 1989 Surve Approximate Approximate Sector Distance (Miles) Annual Dose Distance (Miles) Annual Dose N 1.04 0.45 1.04 0.43 NNE 1-. 68 0.11 1.68 0.11 NE 2.34 0.14 2.34 0.13 ENE 1.07 0.19 1.07 0.18 E 2.37 0.11 2.37 0.10 ESE 2.70 0.09 2.70 0.08 SE 5.03 0.08 5.03 0.08 SSE 4.40 0.08 4.40 0.08 S 2.82 0.13 2.82 0.12 SSH 2,60 0.17 2.60 0.16 SW 3.15 0.13 3.15 0.12 WSW 2.70 0.08 2.70 0.08 W 1.63 0.15 1.63 0.14 HNH 2.82 0.13 2.82 0.13 NH = 1.89 0.31 1.89 0.29 NNW 0.95 0.68 0.95 0.64

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Table G-2 BROHNS FERRY NUCLEAR PLANT Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods (Nearest Garden Within 5 Miles) mrem/year/reactor 1988 Surve 1989 Surve Number of Approximate Approximate Gardens Wi.thin Sector Distance (Miles) Annual Dose Distance (Miles) Annual Dose 3 Miles ( 1989)

N 1.04 9.75 1.04 9.54 4 NNE 1.80 2.16 1,80 2.12 0 NE 2,75 1.25 2.75 1.22 3' ENE 1.68 2.52 1.68 2.47

'3 I ESE 2.37 a

a 4.40 2

1.10 2.37 a

a 4.40 2.38 1.08 5

0 0

I SSE 1 2.82 2.19 2.82 2.15 1 2.60 2.79 2.60 2.74 4 SH 3.15 1.15 3.15 1.13 1 WSH 2.70 0.65 2.70 0.64 4 H 1.89 1.08 1.89 1.06 2 HNH 3.36 1:16 3.36 1.14 0 5.02 I NW vow 2,20 1.14 5.13 10.10 2.20 1.14 9.89 2

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a. Garden not identified in this sector.

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Table G-3 BROWNS FERRY NUCLEAR PLANT Projected Annual Dose to Receptor Thyroid from Ingestion of Milk mrem/year/reactor Approximate Distance Annual Dose Location Sector (Miles) 1988 1989 Farm 5.0 0.04 0.02 Bn'arm ENE 5.9 0.01 0.005 L'arm NNW 6.8 0.02 0.009 T

B'arm WNW 3.3 0.09 0.09

a. Milk being sampled at these locations.

b. Vegetation being sampled at these locations.

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APPENDIX H DATA TABLES

< 6 15.2 + 1.6 11.5 + 1.0 13.3 + 1.2 11.5 + 1.1 14.3 + 1.2 12.7 + 1.4 15.0 + 0.9 13.5 + 1.3

Average, 0-2 miles (onsite) 17.3 + 1.1 13.9 + 1.1 17.1 + 2.7 13.9 + 2 ' 16.6 + 1.3 15.1 + 1.5 17.4 + 1.7 16.1 + 1.4

Average, greater than 2 miles (offsite) 15.6 + 1.2 12.0 0.9 14.1 + 1.9 12.0 + 1.1 14.9 + 1.3 13.3 + 1.3 15.6 + l.l 14.0 + 1.2

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

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

Table H-2 ENNES EE V 'ET'J HO-,

RADI OLOG I GAL CONTROa ENV IRONt1ENTAL RADIOLOGICAL MONITOR INC AND It(STRUt(ENTA1'IOti !iEP T WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL NONITOR It(G REPORT INC SYSTEt1 RADIOACTIVITY IN AIR F ILT R PCI/H3 0.037 BQ/H3 NAt)E OF FACILITY- BROMNS FERRY NUCLEAR PLANT DOCKET tiO.: 50 259,260,296 LOCATION OF FACILITY: Lit(ESTONE ALABA)(A PFPORTING PERIOD- 1989 TYPE AND LOMER L It(IT ALL CONTROL NUi)SER OF TOTAL NUNBER OF INDICATOR LOCATIONS LOCATION MITH HI CHEST ANNUAL tlEAN LOCATIOtiS NONROUTINE OF ANALYSIS DETECT ION . )(EAN (F ) NAt(E t(EAN (F ) t(EAN (F l REPORTED PERFORNED (LLD) RANCE DISTANCE AND DIRECTION RANCE RAtiCE HEASUREHEt'TS SEE NOTE SEE NOTE SEc t(OTE ScE NOTE CROSS ALPHA 80

7. OOE-04 1.2GE-03( 22/ 40) Ltt-) BF 1.26E "03( 22/ 40) 1.20E-03( 24/ 40) 7.44E 2.32E-03 1.0 HILES N 7.44E 2.32E-03 7.04E 2.27E-03 GROSS BETA 570 2.00E-03 1.95E-02( 46G/ 466) Lt)) BF NORTHWEST 2.01E-OR( 51/ 51) 1.87E-02( 104/ 104) 7.15E 6.05E-02 1.0 NILE N 9.5SE G.05E-OR 8.4SE 4.37E-OR GAt(MA SCAN (GELI )

143 BE-7 R.OOE-OR 8.51E-OR( 1 17/ 117) LH'1 BF NORTHWEST 8.79E-OR( 13/ 13) 8.29E-02( 26/ 26)

5. 14E 1.36E-01 1.0 NILE N 6.29E-OR- 1.24E-O) 5.7SE 1.30E-01 BI-214 5.00E-03 7.59E-03( 10/ 117) LN-6BF BAKER BOTTOt( 1.01E-OR(, 2/ 13) 8.90E-03( 3/ 26) 5.10E 1.46E-02 3.0 HILES SSW 5.GOE 1.46E-02 5.90E 1.33E-02 PB-214 5.00E-03 7.86E-03( 8/ 117) Lt(R BF NORTH 5.40E 1.40E-02 0.9 NILE NNE 9.60E-03( 1 9.60E-03" 9.60E-03

/ 13) 8.10E-03( 4/ 26)

G.OOE 1.09E-02 SR 89 6.00E-04 35 VALUES < LLD 8 VALUES < LLD SR 90 43 3.00E-04 35 VALUES < LLD 8 VALUES < LLD A)1 241 2.50E-05 3 VALUES < LLD 3 VALUES < LLD CH 244 6

2.50E-05 3 VALUES < LLD 3 VALUES < LLD PU 239,240 5

2.50E-05 3 VALUES < LLD VALUES < LLD PU 238 2.50E-05 3 VALUE < LLD 2 VALUES < LLD CN 2.50E-05 3 VALUES < LLD 3 VALUES < LLD NOTE: I . Ill NOt) INAL LOMER L i T OF DETECTION (LLO ) AS DESCR ISED IN TABLE E- 1 NOTE: 2. tlEAN AND RANCE BASED UPON 'DETECTABLE NEASUREtlENTS ONLY. FRACTION OF DETECTABLE tlEASUREHENTS AT SPECIFIED, 1 OCATIONS IS INDICATED IN PAREtiTHESES (F) .

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~ TENNESSEE e H-3 VALLEY AUTHORITY RAC'OLOGICAL CONTROL Et)VIRONMENTAL RADIOLOGICAL t)Ot)ITORING AND It(STRVt)E(((ATION DEPT MESTERN AREA RADIOLOG!CAL LABORATORY ENV IRONHEt)TAL t)ONITOR ING PEPORT ING SYSTEt)

RADIOACTIVITY IN CHARCOAL FILTER PCI/H3 - 0. 037 BQ/H3 NAHE OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOC)(KT NO.: 50 c59icG0,29c LOCATION OF FACILITY: Llt(ESTQNE ALABAHA REPORTING PERIOD: (980 TYPE AND LOMKR Llt(IT ALL CONTROL t(UNBKR OF TOTAL NUt)BER OF INDICATOR-LOCATIONS LOCATION MITH HIGHEST ANNUAL t1EAN LOCATIONS NOt)POUT INE OF ANALYSIS DETECTION HEAN (F) NANE t(EAN (F) HEAN (F) REPORTED PERFORt)ED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE ~EASUREt)Et)TS SEE NOTE 1 SEE NOTE SKE t(OTE c. SEE NOTE 2 I OD INK-131 570 2.00E-02 460 VALUES < LLD LH) BF NORTH'MEST 5) VAl.UES ( LLD 2. 0)E-02( 1/ 104) 1.0 NILE N 2.0')E-Oc,- c. ~ 01E-02 NOTE: 1 ~ NONINAL LOMER Llt)IT OF DETECTION (1 LD) AS DESCRIBED IN TABLE E-1 NOTE: 2, 11EAN AND RANGE BASED UPON DETECTABLE t(EASUREt(KNTS ONLY. NLY. FRACTION OF DETECTABLE t(EASUREHEt(TS AT SPECIFIEO LOCATIONS IS INDICATED IN PARENTHESES (F).

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m m m w m m m m m m m m m m m m m m 0 ~ Table H-4 TEI4t ESSEE VALLEY AUIHOPITY RAD I OLOG I CAL = CONTROL ENVIRONNENTAL RADIOLOGICAL tlONITORING AtID INSTRUt!ct(TATION DEPT.

(IESTERN AREA RADIOLOGICAL LABORATOR~Y ENVIPONtlEtITAL tlONITORING REPORTING SYSTFH RADIOACTIVITY IN NILK PCI/L - 0. 037 BQ/L NAIIE OF FACILITY: BROIJNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259 260,296 LOCATION OF FACILITY: LIHESTONE ALABAHA REPORTING PERIOD: 1989 T YP E At4D LOLJER LINIT ALL COt4TROL t4UHBER OF TOTAL NUNBER OF INDICATOR LOCATIONS LOCATION UITH HIGHEST ANNUAL HEAN LOCATIONS OF ANALYSIS NONROUTINE DETECTION HEAN (F) NANE NEAN (F) HEAN (F) REPORTED PERFORNED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEAcURENEWTS SEE NOTE I SEE NOTE c. SEE NOTE 2 SEE NOTE 2 IODINE 131 212 2.00E-OI 129 VALUES < LLD S3 VALUES < LLD GANNA SCAN (GELI) 84 AC-228 2.50E+01 2.89E+01( I / 51 ) LOONEY FARH 5. 9 NILE 2.89E+01( I/ (7) 33 VALVES < LLD 2.89E+01- 2.89E+01 S ENE 2.89E+0) 2.89E+0)

BI-21 4 2.00E+01 3.51E+01(

2.03E~OI-7/ 51) StlITH/BENNETT 6.8)E+0$ 5. 0 HILES N FARH 6.81E+01 ( I/

6.81E+01- 6.8)E+0$

17) 33 VALUES < LLD K-40 1.50E+02 1.27E+03( 51/ 51) SHITH/BENNETT FARH 1.32E+03( 17/ 17) 1.37E+03( 33/ 33) 9.81E+02- 1.57E+03 5. 0 tlILES N I . I E+ 03- 1.57E+03

'I 1.2$ E+03- .54E+03 I

OO Cll PB-214 c..OOE+01 3.66E+01(

2.'$6E+01-4/ 5'I) 7.04E+0)

St(ITH/BENNETT FARtl

5. 0 HILES N 7.04E+01(

7.04E+0$ - I/ 17) 33 VALVES

< LLD I 7.04E+0$

SR 89 65 2.50E+00 40 VALUES < LLD SHITH/BENNETT FARN 13 VALUES < LLD 3.30E+00( 2/ 25)

5. 0 HILES N 3.11E+00- 3.4SE+00 SR 90 65

2. 00E+00 3.35E+00( 29/ 40) LOONEY FARN 5.9 NILE 4.60E+00( 8/ 14) 2.55E+00( 10/ 25)

2. I OE+00- I . 83E+0 I S ENE 2.21E+00- 1.83E+01 2.17E+00- 3.03E+00 NOTE: I . NONINAL LOLlER LItlIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l NOTE: . HEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY. FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) .

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Table H-5 T &444ESSEc. VALLEY AVlHOR I TY RADIO'C ICAL COt4TROL Et(VIROWt(EWTAL RADIOLO ICAL tlOWITORING AWD It(STRUttEtt AT ION DEPT AREA RA IOLOG ICAL LABORATORY "'ESTERtt ENVIPONtlENTAL tlONITOR ING REPORTING SYSTEM RADIOACTIVITY IN l)ET VEGETATION PCI/KG - 0. 037 BQ/KG il)ET UT)

WANE OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET WO.: 50-259,260,296 LOCATION OF FACILITY: LIMESTONE Al.ABANA PEPORT INC PERIOD: 1989 TYPE AND LOI)ER LIMIT ALL CONTROL t(VtlBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL MEAN LOCATIONS- ttONROVTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) NEA)4 (F ) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RAt4GE t4EASURENE)4TS SEE NOTE I SEE NOTE SEE NOTE SEE NOTE 2 IODINE-131 128 4.00E+00 5.79E+00( 6/ 102) MISER FARM 4.34E+00" 7.77E+00 6.S MILE 7.28E+00( I/ 9) 4.15E+00( I/ 26)

S NE 7.28E+00- 7.28E+00 4. 15E+00- 4.)5E+00 CANNA SCAN (GELI)

'I 29 AC-228 8.00E+01 1.21E+02(

8.44E+01-G/ 103) 1.78E+02 LM-6BF BAKER BOTTOM 3.0 MILES SSM 1.78E+02( I/

1.78E+02- 1.78E+OR

9) 1.29E+0 1.29E+02-( I/ 2G) 1.29E+02 BF-7 2.00E+02 2.31E+03( 00/ 103) LM-6BF BAKER BOTTOM 3.72E+03( 9/ 9) 1.97E+03( 25/ 2G)

R. 11E+02- 8.72E+03 3. 0 N ILES SSM 1.08E+03- 8.72E+03 3.73E+02- G.GIE+03 BI-214 4.80E+01 9. 31E+01 ( 10/ 103) LOONEY FARtl 5.9 tlILE 1.33E+02( 1/ 9) 1.00E+02( 3/ 26) 5.23E+01- 1.61E+02 8 ENE 1.33E+02- 1.33E+02 6.69E+01- 1.21E+02 CS-137 2.40E+01 2.47E+01( I/ 103) MISER FARtl 6.8 NILE 2.47E+01( I/ 9) R.S7E+01( I/ 26) 2.47E+01- 2.47E+01 S NE 2.47E+01- R.47E+01 c..87E+01- 2.87E+01 K-40 4.00E+02 5.17E+03( 02/ 103) LN3 BF- NORTHEAST 6.00E+03( ~ 9/ 9) 6.41E+03( 26/ 26)

5. 37& 02- R.13E+04 1.0 tlILE ENE 5.37E+02- 1.17E+04 2.652~03- 1.43E+04 PB-212 4.00E+01 7. 32Ee01 4.64E+01-( 5/ 103) 9.52E+01 LOONEY FARM 5. 9 NILE 9.52E+01(

8 ENE I/ 9) 9.5'RE+01- 9.52E+01 6.55E+01( 4/ ?6) 4.20E+01- 8.43E+01 PB-214 8,00E+01 I.'IOE+02(

8.64E+01-5/ 103) 1.40E+02 LOONEY FARM 5.9 MILE I.40i+02( I/

1.40E+02- 1.40E+02

9) 1.0SE+02( 4/ 26)

S ENE 9.092+01- 1.3'lE+Oc.

TL-20S 2.60E+0) 4.00E+01( 4/ 103) 3.08E+01- 5 '7E+01 TERRY FARM 3.2 NILES 5.07E+01( I/

5.07E+01- 5.07Ey01

13) 2.SIE+01( 1/ 2G)

MNM R.SIE~01- 2. 81E+01 SR 89 43 1.40E+02 34 VALVES < LLD 9 VALUES < LLD SR 90 6.00E+01 9.67E+01( 8/ 34) 6.45E+01- 1.71E+02 LOONEY FARM 5.9 NILE 1.71E+02( I/ 3) 1.7IE+02- 1.71E+02 1.04E+02( I/ 9)

S ENE 1.04E+02- 1.04E+02 t40 TE ."

1 . tlI ttOtll WAL LOVER L'I T OF DETECT ION (LLD ) AS DES CR I BEO IN TABLE 2 1 NOTE: -

2. MEAN AND RANGE BasED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE M asURENEt4TS AT SPECIFIED LOCATIONS I 8 INDICATED IN PARENTHESES (F) .

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Table H-6 TKHthKSSKK VA> LKY AUTHOR)i ~

RADIOLOGICAL CONTROL KNVIRONttKHTAL RADIOLOGICAL tlOHITOR IHG AHO ltlSTRUNKHTATIOti DEPT MESTERN AREA RADIOLOGICAL LABORATORY ENV IRONtlENTAL tlOHITOR IHG REPORTING SYSTEN RADI OACT I V I TY IN SOIL PCI/GN 0.037 BQ/G (DRY MEIGHT)

HAtlK OF FACILITY- BROGANS FERR'Y NUCLEAR PLANT DOCKET HO.: 50-259,260.296 LOCATION OF FACILITY- LINESTONE ALABANA REPORTING PERIOD'- l989 TYPE AHD LOMER LINIT ALL CONTROL NUNBER OF TOTAL NUNBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL NEAN LOCATIONS NONROUTINE OF AtlALYSIS DETECTION NEAN (F ) NANE NEAN (F ) tIKAN (F) REPORTED PERFORNED (LLD) RANGE DISTANCE AND DIRECTION RANGE P.ANGE NEASURENENTS SEE NOTE SEE NOTE 2 SEE NOTE SEE NOTE 2 GROSS ALPHA 2

NOT ESTAB 2.75E+00( I/ I) LNI BF NORTHMEST 2.7SE+00t I/ I ) 2.74E+00( I/ I )

2.75E+00- 2.75E+00 1.0 NILE N 2.75E+00- 2.75E+00 2.74E+00- 2.74K+00 GANNA SCAN (GELI) ll AC"228 1.00E-01 1.14E+00( 9/ 9) LN4 BF TRAILER P I . 41E+00( I/ I) 9,98E-Olt 0- 1.41E+00 2/ 2) 7.40E 1.41K+00 I .7 N ILES NNM I . 4 'I E+ 0 9.97E 9.99E-O'I BE-7 1.00E-OI 2.32E-OI( 'I/ 9) ATHENS AL > 2.32E-01( I/ I) 3.6IE-01( I/ 2) 2.32E-01 2.32E-OI I 0. 9 NILES NE 2.32E-OI- 2.32E-OI 3.61E-OI- 3.6IE-OI 8 I-212 2.50E-01 1.16E+00( 9/ 9) LN4 BF TRAILER P 1.56E+00( I/ I) 8.97E-01( 2/ 2) 7.25E-OI 1.56E+00 1.7 NILES NNM 1.56E+00- 1.56E+00 8.95E-OI- 8.99E-01 CX>

CO I

81-214 4.00E-OR 9.37E-OI( 9/ 9) LN4 BF TRAILER P 7.15E 1.22E+00 I.RRE+00( I/ I) 7.34E-01( 2/ 2) 6.79E-OI- 7.88E-OI 1.7 NILES NNM 1.22E+00- 1.22E+00 CS-137 '1.00E-OR 3.23E-OI( 9/ 9) ROGERSV ILLE, AL 6.1IE-O'I( I/ I) 2.43E-01( 2/ 2) 1.11E-0'I- 3.75E-01 5.87E-OR- 6.11E-OI 13.8 NILES NM 6.11E 6.11E-01 K-40 2.00E-01 5.27E+00( 9/ 9) LN4 BF TRAILER P 7.87E+00( I/ I) 3.23E+00( 2/ 2) 3.3SE+00- 7.87E+00 I . 7 NILES NNM 7.87E+00- 7.S7E+00 Z.SSE+00- 3.61K+00 PA-234N 3.00E+00 3.55E+00( 2/ 9) LNI BF NORTHWEST 3.50E+00- 3.59E+00 1.0 NILE N 3.59E+00(

3.59E+00-I/ I) 3.5IE+00(

3.59E+00 Il 3.51E+00- 3.51E+00 2)

PB ~~12 2.00E-02 1.06E+00( 9/ 9) LN4 BF TRAILER P 1.40E+00( 'I/ I) 8.75E-01( 2/ 2) 6.51E 1.40E+00 1.7 tlILES NNM 1.40E+00- 1.40E+00 8.05E 9.45E-01 PB-214 2.00E-02 I.OIE+00( 9/ 9) LN4 BF TRAILER P 1.26E+00( I/ I) 7.82E-Olt 2/ 2) 7.60E 1.26E+00 '1.7 NILES NNM 1.26E+00- 1.26E+00 7.37E 8.27E-01 RA-224 3.00E-01 I.)2E+00(

5.96E 7/ 9) 1.51E+00 Ltl4 BF TRAILER P 1.7 NILES NNM 1.51E+00(

1.51E+00-

'I/ I) 1.51E+00 I. IOE+00l Il 1.10E+00- 1.10K+00 2)

RA-226 5.00E-02 9.37E-OI( 9/ 9) LN4 BF TRAILER P 1.22E+00( I/ I) 7.34E-01( 2/ 2) 7.15E I.RRE+00 I . 7 NILES NNM 1.22E+00- 1.2RE+00 6.79E 7.88E-OI TL-208 R.OOE-02 3.58E"O'I( 9/ 9) LN4 BF TRAILER P 4. S IE-01 ( I/ I) 2.87E-01( 2/ 2)

R.RSE 4.81E-01 I . 7 NILES NNM 4. 81 E 4.81E-01 2.60E 3.I5E-01 SR 89

1. 00E+00 1.13E+00( 2/ 9) LN4 BF TRAILER P 1.23E+00( I/ I) 2 VALUES ( LLD

1. 03E+00- 1.23E+00 1.7 NILES NNM 1.23E+00- 1.23E+00 NOTE: I . NONItlAL LOMKR LINIT OF DETECTION (LLD) AS DESCRIBED IN TABLE K-l NOTE: R. NEAN *AND RANGE BASED UPON DETECTABLE NEASURENENTS ONLY. FRACTION OF DETECTABLE NEASURENENTS AT SPECIcIED LOCATIONS IS INDICATED IN PARENTHESES (F).

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Table H-6 (Continued)

TENNESSEE V*i LEY AUTHOR I ) Y RADIO'GICAL CONTROL ENVIRONtlENTAL RADIOLOGICAL NONITORING At4D It(STRUtlE)4TAT ION DEPT.

WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONNEt4TAL MONITORING REPORTING SYSTEN RADIOACTIVITY IN SOIL PCI/GN - 0.037 BQ/G (DRY WEIGHT) t4Rt(E OF FACILITY: BROIJt(S FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,-96 LOCATION OF FACILITY: LINESTONE Al ABANA REPORTING PERIOD: 1989 TYPE A)4D LOWER LINIT ALL CONTROL NUNBER OF TOTAL NUNBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL NEAN LOCATIONS NONROUTINE OF ANALYSIS DETECT ION NEAN (F) NANE NEAN (F) NEAN (F) REPORTED PERFORtlED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE NEASURENENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE SEE NOTE 2 SR 90 3.00E-01

'U 239.240 9 VALUES < LLD 2 VALUES < LLD NOT ESTAB 8.18E-03( 1/ 1) LN1 BF NORTHWEST 8. 18E-03( 1/ 1) 2.65E-03( 1/ 1 )

8.18E 8.)SE-03 ).0 NILE N S. )SE S. )SE-03 2.65E 2.65E-03 PU 238 t(OT ESTAB 6.92E-04( 1/ 1) Ltll BF NORTHWEST 6.92E-04( 1/ 1) 9.58E-04(

6.92E 6.92E-04 1.0 NILE N 6.92E 6.92E-04 9.58E 9.582-04 AN 241 I

NOT ESTAB 3.47E-04( 1/ 1) LN1 BF NORTHWEST 3.47E-04( 1/ 1) 1. 78E-03( 1/ 1 )

3.47E 3.47E-04 1.0 NILE N 3.47E 3.47E-04 1.78E '1.7SE-03 Ctl 244 NOT ESTAB 1.27E-03( 1/ 1) LN1 BF NORTHWEST 1.27E-03( 1/ 1) 2.97E-04( 1/ 1) 1.27E 1.27E-03 1.0 NILE N ).27E 1.27E-03 2.97E 2.97E-04 CN 242 NOT ESTAB 2.80E-03( 1/ 1) LNl BF NORTHWEST 2.80E-03( 1/ 1) 3.60E-03( 1/ 1) 2.80E 2.80E-03 1.0 NILE N 2.80E 2.SOE-03 3.60E 3.602-03 t(OTE: l. NOtlINAL LOWER LItliT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l NOTE: 2. NEAN AND RANGE BASED UPON DETECTABLE NEASURENENTS ONLY. FRACTION OF DETECTABLE NEASURENENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

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Table H-T TENt(ESSES VA'EY AUTHOR I Y ~

RADIOLOGICAL CONTROL ENVIRONtlENTAL RADIOLOGICAL NOt(ITOR It(G AND INSTRUMENTATION DEPT, 1'ESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTIHG SYSTEM ~

RADIOACTIVITY IN APPLES PCI/KG 0. 037 BQ/KG (UET (IT)

NA!1E OF FACILITY- BROWNS FERRY NUCLEAR PLANT DOCKET NO.- 50-259, 2 '-

C . 29 6 LOCATION OF FACILITY: LIMESTONE ALABAMA PEPORTING PERIOD: 19S9 TYPE At(D LOLlER L I(1I T ALL CONTROL NUMBER OF TOTAL NUMBER OF INDI GATOR LOCATIONS LOCATION UITH HIGHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NANE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE t(OTE GROSS BETA 9 . DOE+00 S.39E+02( 1 / 1 ) BROOKS FARM 6 .S NILE 8.39E+02( 1/ 1) 2. 03E+03( 1/ 1 )

8.39E+02- 8.39E+02 S NNQ 8.39E+02- 8.39E+02 2.03E+03- 2.035+03 GAMMA SCAN (GELI)

K-40 1.50E+02 G.55E+02( 1/ 1) BROOKS FARM 6.S NILE 6.55E+02( 1/ 1) 1. 1)E+03( 1/ 1) 6.55&'02- 6.55E+02 S NNU 6. 55& 02- 6. 55& 02 1 . 1 1E+03- 1 . 1 .5+03 NOTE: 1 . NOMINAL LOUER LItlIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAN AND RANCE BASED UPON DETECTABLE MEASUREMENTS OtlLY. FRACTION OF DETECTABLE tlEASURENENTS AT SPECI=IED LOCATIONS IS INDICATED IN PARENTHESES (F) .

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Table H-8 TENNESSEF VALLEY A()THORITY RADIOLOGICAL CONTROL ENVIRONt(ENTAL RADIOLOGICAL'tOt(ITORING AND It(STJ(VttENTATIOtt DEPT.

(JESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL tlONITOR INC REPORTING SYSTEM RADIOACTIVITY IN BEEF PCI/KG - 0.037 BQ/KG (lJET (JT)

NAME OF FACILITY: BROVNS FERRY NUCLEAR PLANT DOCKET NO.t 50-259>260,296 LOCATION OF FACILITY- LIMESTONE ALABAMA REPORTING PERIOD: 1989 I

TYPE Af(D LOVER LIMIT ALl CONTROL f(UMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION VITH HIGHEST At(NVAL MEAN LOCATIONS NONROVTINE OF ANALYSIS DETECTION . MEAN (F l NAME tlEAN (F ) MEAN (Ff REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREtlEt(TS SEE NOTE SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 CROSS BETA 1.50E+01 4.06E+03( 1/ 1) SMITH/BENNETT FARM 4.06E+03( 1/ 1) 2.65E+03( 1/ 1) 4.06E+03- 4.06E+03 5.0 MILES N 4.06E+03- 4.06E+03 2.6SE+03- 2.6SE+03 GAMMA SCAN (CELI)

3. OOE+02 2.38E+03( 1/ 1) StlITH/BENNETT FARM 2.38E+03( 1/ 1) 2.48E+03( 1/ 1) 2.38E+03- 2.38E+03 5.0 MILES N 2.38E+03- 2.38E+03 2.48E+03- 2.48E+03 NOTE: 1 . NOMINAL LOVER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l NOTE( 2. tlEAN AND RANGE BASED UPON DETECTABLE tlEASVREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

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Table H-9 TENt(ESSEE VALLEY AU.HOP. I TY RAD)OLOGICAL CONTROL ENV? ROJJt(EtJTAL RAO I OLOG ICAL t)ON I TOR JNG At(D JN TRUtle tJT*T IOJJ DEPT .

LIESTERN AREA RADIOLOGICAL LABORATORY ENVIRONtlENTAL MONITORING REPORTING SYSTEtl RADIOACTIVITY IN CORN PCI/KG - 0.037 BQ/KG (MET UT)

NAME OF FACILITY: BROIJNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259 260,296

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LOCATION OF FAC ILITY: L itlESTONE. ALABAMA REPORTING PERIOD: 1989 TYPE AND LOIJER LIMIT ALL CONTROL JJUMBER OF TOTAL tJUMBER OF INDICATOR LOCATIONS LOCATION UITH HIGHEST ANNUAL t(EAN LOCATIONS tJONROU T INE OF ANALYSIS DETECTION tlEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORtlED (LLD) RANGE DISTANCE At(D DIRECTION RANGE RANGE tlEASUREtlENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS SETA 9.00E+00 4.18E+03( 1/ 1) SMITH/BENNETT FARM 4.18E+03( 1/ 1) 3.92E+03( 1/

4. 1SE+03- 4.1SE+03 5.0 MILES N 4.18E+03- 4.18E+03 3.92E+03- 3.92E+03 GAllMA SCAN (GELI )

2 K-40 1 . 50E+02 2. 38E+03( 1/ 1 ) St(I TH/BENNETT FARtl 2 38E+03(

~ 1/ 1 ) 2. 17E+03( 1/ 1 )

2.3SE+03- 2.3SE+03 5. 0 MILES N 2.3SE+03- 2.3SE+03 2.17E+03- 2.17E+03 NOTE: 1. NOtlINAL LO(JER LI(1IT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l NOTE: 2. tlEAN AND RANGE BASED UPON DFTECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREtlENTS AT SPFCIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) .

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Table H-10 TEtlt(ESSEE VALLEY AUTHOP. i TY RADIOLOGICAL CONTROL ENVIRONNENTAL RADIOLOGICAL NONITORINC AND IN TRUNENTATION DEPT, MESTERN AREA RADIOLOGICAL LABORATORY ENVIRONNENTAL NOWITORING REPORTING SYSTEN RADIOACTIVITY IN GREEN BEANS PCI/KC - 0.037 BQ/KG (MET MT)

WANE OF FACILITY: BROMWS FERRY NUCLEAR PLANT DOCKET NO.: 50 259,260,296 LOCATIOtt OF FACILITY: LINESTONE ALABANA PFPORTING PERIOD: 19S9 TYPE At(D LOMER L It1 IT ALL CONTROL NUNBER OF TOTAL NUNBER OF INDICATOR LOCATIONS I.OCATION MITH HICHEST ANNUAL NEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION, MEAN (F ) NANE NEAN (F) NEAN (F) REPORTED PERFORNED (LLD) RANCE DISTANCE AND DIRECTION RANGE RANGE tlEASURENENTS SEE NOTE I SEE NOTE SEE NOTE 2 SEE NOTE 2 GROSS BETA 9.00E+00 3.61E+03( I/

3.61E+03- 3.61E~03 I) BROOKS FARN 6.8 NILE 3.61E+03( I/ I) 3.00E+03( I/ I)

S NNM 3.61E+03- 3.61E+03 3.00E+03- 3.00E+03 CA)1NA SCAN (GELI) 2 K-40 1.50E+02 2.35E+03( I/

2.35Ew03- 2.35E+03 I ) BROOKS FARN 6.S NILE 2.35E+03( I/ I ) 1.49E+03( I/ I )

S t(NM 2.35E+03- 2.35E+03 1.49E+03- 1.49E+03 NOTE: I. NONINAL LOMER LItlIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l NOTE: ., 2. NEAN AND RANGE BASED UPON DETECTABLE NEASUREtIENTS ONLY. FRACTION OF DETECTABLE NEASURENENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

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Table H-11 TENtlESSEE VALLEY AUTHORITY RAO I OLOG I CAL COt(TROL ENVIRONHEtlTAL RADIOLOGICAL t(Ot(ITORING ANO It)STPUMEt(TAT ION DEPT.

LJESTERN APEA RADIOLOGICAL LABORATOFY ENVIRONHEtlTAL t(ONITOR ING REPORTING SYSTEM RADIOACTIVITY IN POTATOES PCI/KG 0.037 BQ/KG (UET MT)

NAHE OF FACILITY: BROGANS FERRY NUCLEAR PLANT DOCKET NO.: 50 259,260 296 LOCATION OF FACILITY: LIHESTONE ALABAHA REPORTING PERIOD: 19S9 TYPE At(O LOLlER L I NIT ALL COt)TROL NUt)SER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION UITH HIGHEST ANNUAL HEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION - NEAN (F ) NA)1E HEAN (F ) t)EAN (F) REPORTED PERFORNED (LLD) RANGE DISTANCE AND DIRECTION RAtlGE RANGE t)EASURENENTS SEE NOTE SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS SETA 9 . 00E+00 6,44E+03( 1 / 1 ) BROOKS FARt1 6 8 NILE 6 4 lE+03( 1 / 1 ) 4 58E+03( '1/

4.58E+03- 4.5SE 03

'1 )

6.44E+03- 6.44E+03 S NNU 6.44E+03- 6.44E+03 GANHA SCAN (GELI)

I K-40 1. 50E+02 4.09E+03( 1/ 1 ) BROOKS FARH 6.8 NILE 4. 09E+03( 1/ 1 ) 3. 01E+03( 1/

4. 09E+03- 4. 09E+03 S NNM 4.09E+03- 4.09E+03 3.0)E+03- 3.0)E-O3 NOTE: 1. WONINAL LOLJER LItlIT OF DETECTION (LLO) AS OESCRIBEO IN- TABLE E-1 ~

I CO NOTE: 2. NEAN AND RANGE BASED UPON DETECTABLE t)EASUREt1ENTS ONLY. FRACTION OF DETECTABLE t)EASUREt)ENTS AT SPECIF I D IO I LOCATIONS IS INDICATED IN PARENTHESES (F) .

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Table H-12 I ENt(ESSEE VALLEY AUTHORITY RADIOLOGICAL CONTROL ENVIRONt(ENTAL RADIOLOGICAL MONITORING AND INSTRUtlENTATION DEPT.

MESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITOR ING REPORTING SYSTEtl RADIOACTIVITY IN TOMATOES PCI/KG - 0.03? BO/KG (MET MT)

NAtlE OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET f40.: 50 259,260,296 LOCAT ION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1989 TYPE AWO LOMER L Itl IT ALL CONTROL NUtlBER OF TOTAL NUMBER OF INDICATOR 1.0CATIONS LOCATION M I TH HIGHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION . MEAN (F ) NAME tlEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECT!ON RANGE RANGE tlEASUREMENTS SEE NOTE 1 SEE t(OTE 2 SEE NOTE SEE NOTE 2 GROSS BETA

9. 00E+00 3.45E+03( 1/ 1) BROOKS FARM G.S MILE 3.45E+03( 1/ 1) 3.83E+03( 1/ 1")

3.45E+03- 3.45E+03 S NNW 3.45E+03- 3.45E+03 3.83E+03- 3.83E+03 GAMtlA SCAN (GELI )

K-40 1.50E+02 2.14E+03( 1/ 1) BROOKS FARM G.B MILE 2.14E+03( 1/ 1) 2.32E+03( 1/ 1)

2. 14E+03- 2. 14E+03 S NNM 2. 14E+03- 2. 14E+03 2.32E+03- 2 .32E+03 NOTE: 1 . NOMINAL LOMER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F ) .

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Table H-I3 EE VALLEY AUTHORITY 0

RADIOLOGICAL CONTROL ENVIRONHENTAL RADIOLOGICAL HOWITOR ING AND INSTRUHEt(TAT ION DEPT.

MESTERN AREA RAD10LOGICAL LABORATORY ENVIRON(1ENTAL t10t(ITOR ING REPORTING SYSTEH RADIOACTIVITY IN TURNIP GREENS PCI/VG - 0.03? BO/KG (MET MT)

NA)1E OF FACILITY- BROMNS FERRY NUCLEAR PLANT DOCKET NO.: S0-2S9,260,296 LOCATION OF FACILITY- LIHESTONE ALABAHA REPORTING PERIOD: 1989 TYPE AND LOMER L IH IT ALL CONTROL NU(18ER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL HEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION HEAN (F) NAHE t(EAN (F) HEAN (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASUREtlENTS SEE NOTE SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS BETA

9. 00E+00 3.51E+03( 1/ 1) LHS BF DAVIS F 3.S)E+03( 1/ 1) 4.52E+03( 1/ 1) 3.51E+03- 3.51E+03 P..5 HILES MSM 3.51E+03- 3.51E+03 4.52E+03- 4.52E+03 GAH)1A SCAN (GELI )

2 K-40 '1.50E+02 ).54Ei03( 1/ 1) LHS BF DAVIS F 1.54E+03( 1/ 1) 1.90E+03( 1/ 1) 1.54E+03- 1.54E+03 2.5 HILES MSM 1.54E+03- 1.54E+03 1.90E+03- 1.90E+03 PB-212 2.00E+01 4.)BE+01( 1/ 1) LHS BF DAVIS F 4.18E+01( 1/ 1) 1 VAI UES < LLD

4. 18E+01- 4.18E+01 2.5 HILES MSM 4. 18E+01- 4.18E+01 TL-208 7.00E+00 1 .40E+01 ( '1

/ \ ) LI15 BF DAVIS F 1 .40E+01 ( 1/ 1 ) 1 VALUES < LLD 1.40E+01- 1 . 4 0E+ 01 2. 5 H ILES MSM 1.40E+01- 1.40E+01 NOTE: 1. NOHINAl. LOMER LItlIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: . HEAN AND RANGE BASED UPON DETECTABLE t1EASUREHENTS ONLY. FRACTION OF DETECTABLE HEASURD(ENTS AT SPECIFIED LOCATIONS IS INDICATED IN PAREt(THESES (F) .

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Table H-14 TENNESSEE VALLEY AUTHORITY RADIOLOGICAL CONTROL Et(VIRONr(EHTAL PADIOLOG ICAL ttOril TOR ING ANO INSTRUNENTAT ION DEPT.

WESTERN AREA RADIOLOGICAL LABORATORY ENVIROHNENTAL t(ONITORING REPORTIt(G SYSTEtl RADIOACTIVITY IN SURFACE WATER(Tora))

PCI/L - 0.037 BQ/L HArlE OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50 259,ZGO,ZSG LOCATION OF FACILITY: LINESTONE ALABANA REPORTING PERIOD'- 19S9 TYPE AND LOWER L INIT ALL CONTROL HVNBER OF TOTAL NUNBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL NEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION NEAN (F) NANE NEAN (F) NEAN (F) REPORTED PERFORNED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE tlEASURENENTS SEE NOTE I SEE NOTE SEE NOTE SEE NOTE 2 GROSS BETA 1.TOE+00 2.55E+00( 25/ 26) TRtl 285.2 2.56E+00( 12/ 13) 2.62E+00( 10/ 13) 1.TTE+00- 3.91E+00 1.79E+00 3.91E+00 1.93E+00- 3.34E+00 CANNA SCAN (GELI) 39 AC-228 2.50E+O'I 3.0SE+01( I/ 26) TRN 293.5 3.08E+01( I/ 13) 13 VALUES < LLD 3.08E+01- 3.08E+01 3.08E+01- 3.08E+01 SR S9

3. 00E+00 3.45E+00( 2/ 8) TRN 285.2 3.4SE+00( 2/ 4) 3.54E+00( I/ 4) 3.06E+00- 3.84E+00 3.06E+00- 3.84E+00 3.54E+00- 3.54E+00 SR 90 12 1.40E+00 8 VALUES < LLD 4 VALUES < LLD TRITIUN 12 2.50E+02 8 VALUES < LLD 4 VALUES < LLD t(OTE: 1 ~ NONIt(AL LOWER LINIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l NOTE- 2. tlEAN AND RANGE BASED UPON DETECTABLE NEASUREtlENTS ONLY. FRACTION OF DETECTABLE NEASURENENTS AT SPECIFIED LOCATIONS IS IHDICATED IN PAREHTKESES (F) .

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Table H-15 TENNESSEE VALLEY AVTHOP.ITY RADIOLOC ICAL CONTROL ENVIRONtlEt(TAL RADIOLOCICA'ONITORIt(G AND INSTRVMEt(TATION DEPT.

WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONt(ENTAL MONITORING REPORTING SYSTEtl RADIOACTIVITY IN PUBLIC WATER(Total)

PC I/L 0. 037 BQ/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.- 50-259,260,296 LOCATIOtl OF FACILITY: LIMESTONE ALABAMA REPORTIt(G PERIOD'- 1989 TYPE AND LOWER LItlIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS, LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUT INE OF ANALYSIS DETECTION - MEAN (F) NAME MEAN (F) MEAN (F l REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RAt(GE MEASVREtlENTS SEE NOTE 1 SEE NOTE SEE NOTE SEE NOTE 2 CROSS BETA 104 1.TOE+00 2.70E+00( 65/ 7S) CHAMPION PAPER 2.S3E+00( . 49/ 52) 2.61E+00l 23/ 26) 1.7(E+00- 4.50E+00 TRtl 282.6 1.71E+00- 4.50E+00 1.93E+00- 3.35E+00 GAMtlA SCAN (GELI) 104 BI-214 2. 00E+01 3.41E+01( 2/ 7S) CHAMPION PAPER 3.41E+01( 2/ 52) 26 VALUES < LLD 3.12E+01- 3.69E+01 TRtl 282.6 3. 12E+01- 3. 69E+01 SR 89

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3. 00E+00 4.34E+00( 1/ 1 ) CHAMPION PAPER 4.34E+00( 1/ 4) 3. 91E+00( 2/ 8) 4.34E+00- 4.34E+00 TRM 282.6 4.34E+00- 4.34E+00 3.54E+00- 4.29E+00 SR 90 20 1.40E+00 12 VALUES < LLD S VALVES < LLD TR I T I Vtl 20 2.50E+02 12 VALUES < 1.LD 8 VALUES < LLD NOTE: 1 . NOMINAL LOWER LItlIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l t(OTE: 2. MEAN AND RANGE BASED UPON DETECTABLE t(EASVREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED l OCATIONS IS INDICATED IN PARENTHESES (F).

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Table N-16 TENtJESSEE VALLEY AUTHORITY RAG IOLOG ICAL COtJTROL ENVIRONt1ENTAL RAD I OLD ICAL t)O)J I TOR ING AND INSTRUt)ENTAT ION Dc PT .

WESTER)) AREA RADIOLOGICAl. LABORATORY ENVIRON))ENTAL NONITOR ING REPORTING SYSTEN RADIOACTIVITY IN MELL WATER(Total)

PCI/L 0. 037 BQ/L t)At)E OF FACILITY: BROMNS FERRY NUCLEAR PLANT DOCKET tJO 50 259,260,296 LOCATION OF FACILITY: Llt(ESTONE ALABANA REPORTING PERIOD'989 TJPE AND LOWER L IN IT ALL CONTROL Nl"1BER OF TOTAL tlUNBLR OF INDICATOR LOCATIONS LOCATIOtl lJITH HIGHEST ANNUAL NEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION NEAN (F) NANE NEAN (F) NEAN (F) RFPORTED PERFOR)(ED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE t(EASUREt(ENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAt)t)A SCAN (GELI )

23 B 1-214 2.00E+0'1 6.62E+01( 7/ 10) BFN l)ELL N6 6.62E+01( 7/ 10) 5.91E+02( 13/ 13) 3.40E+0)- 1.23E+02 0.02 t)ILES M 3.40E+0)- 1.23E+02 4. 12E+02- 8.56E+02 PB-214 2.00E+01 6.13E+01( 7/ 10) BFN (JELL J)6 6. 13E+01( 7/ 10) 5.89E+02( 13/ 13) 2.30E+0)- 1.22E+02 0.02 t(ILES lJ 2.30E+01- 1.22E+02 3.92E+02- 8.3)E+02 SR 89 3.00E+00 4 VALUES < LLD BFN MELL ()6 4 VALUES < LLD 4. 74E+00( 1/ 4) 0.02 tlILES M 4 .74E+00- 4 .74E+00 SR 90 1.40E+00 4 VALUES < LLD 4 VALUES < LLD TR I TI UN 2.50E+02 4 VALUES < LLD 4 VALUES < LLD NOTE: 1. NONINAL LOIJER LINIT OF DETECTION (Ll.D) AS DESCRIBED IN TABLE E-1 NOTE: 2. tlEAN AND RANGE BASED UPON DETECTABLE NEASUREtlENTS ONLY. FRACTION OF DETECTABLE t)EASURE)(ENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) .

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Table H-17 TE(JWE-SEE VAi LE: AUTHORITl

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RADIO'GICAL CONTROL ENVIROtitlEtJTAL RADIOLOGICAL NOtJITORING AND INSTRUtlENTATION DEPT.

(JESTERN AREA RADIOLOGICAL LABORATORY ENVIRONNENTAL t(ONITOR ING REPORTING SYSTEtl RADIOACTIVITY IN FISH-FLESH-WC PCI/GN - 0. 03 BQ/G (DRY UEIGHT) tJAt(E OF FACILITY- BROGANS FERRY NUCLEAR PLANT DOCKET NO.: 50-259>260,296 LOCATION OF FACILITY: Llt(ESTONE ALABAl1A REPORTING PERIOD: 1989 TYPE AND LOlJER L I NIT ALL CONTROL NUNBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION (JITH HIGHEST ANNUAL t(EAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION l1EAN (F) NANE NEAN (F) NEAN (F) REPORTED PERFORt(ED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE ttEASUREt(E)JTS SEE NOTE 1 SEE NOTE 2 SEE tJOTE 2 SEE NOTE 2 GROSS BETA NOT ESTAB 3.37E+01( 4/ 4) (JILSON RESERVOIR 3.42E+Ol (. 2/ 2) 3.1(E+01( 2/ 2) 3.18E+01 3.6PE+01 TRtl 259-275 3.23E+01- 3.62E+01 3.03E+01- 3.19E+01 GAt)t(A SCAN (GELI )

CS-1 37 6. OOE-02 9.33E-02( 1/ 4) MHEELER RES 9.33E-02( 1/ 2) 1.34E-OI( 2/ 2) 9.33E 9.33E-02 TRtl 275-349 9.33E-'02- 9.33E-02 1.30E-O(- 1.38E-01 K-40 1.00E+00 1 . 66E+01 ( 4/ 4) WILSON RESERVOIR 1:67E+01( 2/ 2) 1.78E+0I( 2/ 2) 1.51E+01- 1.82E+01 TRH 259-275 1.51E+01- 1.82E+01 1.67E+01- 1.89E+01 I

Ct C) NOTE - 1 . NOtlINAL LOMER LItlIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 I

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

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Table H-18 1KNhESSEE VA KY AUTHORITY PADIOLOGICAL CONTROL ENVIRONt(ENTAL RADIOLOGICAL- t(ON( TORING AND INSTRU)(ENTAT ION DEPT.

'MESTERN AREA RADIOLOGICAL LABORATORY ENVIRON)(ENTAL t(ONITORING REPORTING SYSTEt(

RADIOACTIVITY IN FISH-FLESH-SB PCI/Gt( - 0. 037 BQ/G (DRY MEIGHT)

NAt(K OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50 259,260,296 LOCATION OF FACILITY: LiMESTONE ALABAHA REPORTING PERIOD: 1909 TYPE AND LOWER LItlIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCAT I Ot(S LOCATION MITH HIGHEST ANNUAL t)EAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION ~

t(EAN (F ) NAHE t(EAN (F) tlEAN (F)

PERFORHED REPORTED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE tlEASURENKNTS SEE NOTE 1 SEE NOTE SEE NOTE 2 SEE NOTE 2 GROSS BETA 6

NOT ESTAB 1.90E+01( 4/ 4) MHEELER RES 2 35E+01( 2/ 2) 2 31E+O'I ( 2/ 2) 1.08E+01- 2.36E+01 TR)( 275-349 2.35E+01 2.36E+01 2.28E+01- 2.33E+01 GANHA SCAN (GELI)

CS-)37 6.00E-02 7.36E-02( 1/ 4) WHEELER RES 7.36E-02( 1/ 2) 2 VALUES ( LLD 7.36E 7.36K-02 TRN 275-349 7.36E -7.36E-02 K-40 1.00E+00 9.72K+00( 4/ 4) 2/ 2) 6.06E+00- ).42E+0)

MHEELER RES 1.29E+01( 1.26E+01( 2/ 2)

TRH 275-349 1.16E+0'1- 1.42E+0) 1.'l)E+01- 1.42E+01 NOTE: 1: NONINAL l.OMKR Lit(IT OF DETECTION (LLD ) AS DESCRIBED IN TABLE K- 1 NOTE: 2. NEAN AND RANGE BASED UPON DETECTABLE NEASUREHENTS Ot(LY. FRACTION OF DETECTABLE NEASUREtlENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) .

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Table H-19 TEt(NESSEE VALLEY AUTHORITY RADIOLOGICAL CONTROL ENVIRONt)ENTAL RADIOLOGICAL MONITORING AND INSTRUMEt(TATIOtt DEPT, WESTERN AREA RADIOLOGICAL LABORATORY FNVIRONMENTAL MONITORING REPORTIt(G SYSTEM RADIOACTIVITY It( FISH-WHOLE-SB PCI/G)1 - 0. 037 BQ/G (DRY WEIGHT)

NAME OF FACILITY: BROWt(S FERRY NUCLEAR PLANT DOCKET NO.: 50-259.ZG0,296 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1989 TYPE AND LOWER L IMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN ( F ) NAME t)EAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE t(EASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE tkOTE 2 SEE NOTE 2 GROSS BETA 6

NOT ESTAB 1.11E+01( 4/ 4) 1)HEELER RES 1 . 17E+O'I ( 2/ 2) 1 . 06E+01 ( 2/ 2) 6.81E+00- 1.60E+01 TRM 275-349 7.39E~00- 1.60E+01 8.35E+00- 1.29E+01 GAMMA SCAN (GELI)

R-40 1.00E+00 4.41E+00( 4/ 4) WHEELER RES 4.56E+00( 2/ 2) 5. 14E+00( 2/ 2) 3.62E+00- 4.90E+00 TRM 275-349 4.27E+00- 4.85E+00 5.10E+00- 5.18E+00 NOTE: 1 . NOt)INAL LOWER LIt(IT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. t1EAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS r IS INDICATED IN PARENTHESES (F).

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Table H-20 TEt(t(ESSEE VA'EY AUTHOP I T Y RADIOLOG ICAL COt(TPOL StlV IRONMKNTAL RADIOLOGICAL MONITORING AtlD Itk - ttVMKt(TATION CE'PT

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WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONtlENTAL MOt(I TOR It(G REPORTING SYSTEM RADIOACTIVITY IN SEDIMENT PCI/GH 0.037 BQ/G (DRY WEIGHT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT COCKET NO 50-259,260i296 LOCATION OF FACIL ITY: LIHESTONE ALABAt(A REPORTING PERIOD: 1989 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (Fl NAME . MEAN (F ) MEAN (Fl REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE t(EASVREHENT' SEE NOTE SEE NOTE 2 SEE t(OTE 2 SEE NOTE 2 GAtltlh SCAN (GELI )

'I 0 AC-22S 1. 00E-01 1.29E+00( 6/ 6) TRH 2SS.78 'l.5SE+00( 2/ 2) 1.24E+00( 4/ 4) 8.75E-01 1.59E+00 1.58E+00- 1.59E+00 1.08E+00- 1.65E+00 BE-7 ~ 1. 00E-01 3.16E-01( 2/ G) TRH RSS.7S 4.48E-01( 1/ 2) R.SGE-01( 1/ 4) 1.83E 4.48E-01 4.48E-OI- 4.48E-O'I 2.56E 2.56E-01 BI-R12 2.50E-01 1.35E+00( 6/ 6) TRH RSS.78 1.76E+00( 2/ 2) 1.36E+00l 4/ 4) 8.63E-01 1.84E+00 1.67E+00- 1.84E+00 1.05E+00- 1.89E+00 Bi-214 4.00E-OR 9.70E-O(( G/ 6) TRH 2SS.7S l. 13E+00( 2/ 2) 1.00E+00,( a/

5.92E 1.ROE+00 1.06E+00- 1.ROE+00 7.27E"0(- 1.44E+00 CO-GO 1.00E-02 1.7GE-01( 6/ 6) TRH 293.7 3. 91E-01 ( 2/ 2) 2.32E-02( 3/ 4) 1.43E-OR- 4.97E-01 BFN DISCHARGE 2.85E 4.97E-01 1.27E-OR- 3.65E-OR C>

CS-134 1. 00E-02 3.7SE-02( 3/ 6) TRH 293.7 4.61E-OR( 1/ 2) VALUES LLD C4 I

1.75E-OP- 4.88E-02 BFN DISCHARGE 4.61E 4.61E-OR CS-137 l. 00E-02 5.75E"01( 6/ 6) TRH 2S8.78 8.46E-01( 2/ 2) 2. 16E-01 ( 4/ 4) 1.64E 8.73E-01 8.18E-O(- 8.73E-01 '1

. 68E 2.76E-01 K-40 2.00E-01 1.02E+Ol( 6/ 6) TRtl 28S.78 1.33E+01( 2/ 2) 1 . 31E+01 ( 4/ 4) 4.34E+00- 1.34E+01 1.33E+01- 1.34E+01 1 . 21E+01- 1.49E+01 PB-212 2.00E-OR '1.18E+00( 6/ 6) TRtl 28S.78 1.44E+00( 2/ 2) l.20E+00( 4/ 4) 7.94E 1.50E+00 1.37E+00- 1.50E+00 9.7RE 1.63E+00 PB-214 2.00E-02 1.05E+00( G/ 6) TRH RS8.78 1.22E+00( 2/ 2) 1.08E+00( a/

6.60E 1.29E+00 1.14E+00- 1.29E+00 7.94E 1.59E+00 P.A-224 3.00E-01 1.38E+00( 5/ 6) TRH 2SS.78 1.66E+00( 2/ 2) 1.2SE+00l 4/ 4) 9.55E-01 1,81E+00 1.51E+00- 1.81E+00 1.08E+00- 1.78E+00 RA"22G 5 00E-02 9.70E-01( 6/ 6) TRH RSS.7S 1.13E+00( 2/ 2) 1.00E+00( 4/ 4>

5.92E 1.ROE+00 1,06E+00- 1.ROE+00 7.27E I.44E+00 SB NOT ESTAB 6. 91E-02( 1/ 6) TRH 293.7 6. 91E-02( 1/ . 2) 4 VALUES ( LLD 6.91E-OR- 6.9(E-OR BFN DISCHARGE 6.91E 6.91E-OR TL- 08 2.00E-02 3.92E-01( 6/ 6) TRH 288.78 4.86E-01( 2/ 2) 4. 01E-01 ( 4/ 4)

R.SOE-01 5.04E-01 4.69E 5.04E-01 3.23E-O(- 5,22E-01 SR S9 10

1. 00E+00 1.43E+00( 1/ 6) TRH 293.7 1 . 43E+00( 1/ 2) 1. 9SE+00( 1/ 4)

1. 43E+00- 1 . 43E+00 BFN DISCHARGE 1.43E+00- 1.43E+00 1.98E+00- 1.98E+00 NOTE: 'l. NOtlINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l NOTE-'. MEAN AND RANGE BASED UPON DETECTABLE t(EASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIOt(S IS INDICATED IN PARENTHESES (F).

Table H-20 (Continued)

TEt(tIESSEE VALLEY AUTHORITY RADIOLOGICAL CONTROL ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION DEPT.

LIESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL t)ONITOR ING REPORTING SYSTEM RADIOACTIVITY IN SEDIt(ENT PC i/GM 0. 037 BQ/G ( DRY ()EIGHT )

-'I 989 '60,296 NAME OF FACILITY: BROIINS FERRY NUCLEAR PLANT DOCRET NO.: 50-259 LOCATION OF FACILITY: LIMESTONE ALABAMA REPORT It(G PER I OD TYPE A(ID LOuER L ItlIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION LJITH HIGHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) tIAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE t(EASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 .SEE NOTE 2 SR 90 10 3.00E-01 6.65E-01( 1/ 6) TRM 288.78 6 . 65E-01 ( 1/ '2) 0 VALVES < LLD 6.GSE-O)- 6.65E-O'1 6.65E 6.GSE-Ol NOTE: 1 . t(011INAL LO'VER LI11IT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE: 2. t1EAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE t)EASUREt1ENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) .

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Table H-21 TENNESSEE VA'EY AUTHORITY RADIOLOGICAL CONTROL Et(VIRONMENTAL RADIOLOGICAL MOt(ITORIt(G AND INS RVMENTATIOt( DEPT.

WESTERN AREA RADIOLOGICA( LABORATORY ENVIRONt(ENTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IN CLAM FLESH PCI/GM - 0. 037 BQ/G (DRY WEIGHT)

NAt1E OF FACILITY: BROWNS FERRY NUCLEAR PLANT DOCKET NO.: 50-259,260,296 LOCATIOtl OF FACILITY: LIMESTONE ALABAMA REPORTING PERIOD: 1989 TYPE ANO LOWER Llt1IT ALL CONTROL l(VMBER TOTAL NVtlBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL tlEAN LOCATIONS OF'ONROVTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED

'PERFORt(ED (LLD) RANGE DISTANCE AND DIRECTIOt( RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAt(MA SCAN (GELI) 10 AC-22S 1.00E+00 l.07E+00( 1/ 6) TRM 277.98 1.07E+00( 1/ 2) 4 VALUES < i LD

'l.07E+00- 1.07E+00 1.07E+00- 1.07E+00 Bi-214 2.50E-OI 9.63E-01( 5/ 6) TRtl 2S8.7S 1.10E+00( 2/ 2) 4.04E-01( 4/ 4) 3.14E 1.20E+00 'l.01E+00- 1.19E+00 3.59E-O(- 4.4ZE-01 Y.-40 2.00E+00 3.55E+00( 3/ 6) TRM 2SS.7S 4.95E+00( '1/ 2) 2.37E+00( 2/ 4) 2.6SE+00- 4.95E+00 4.95E+00- 4.95E+00 2.02E+00- 2.71E+00 PB-212 2.50E-01 3.33E-01( 2/ 6) TRM 2SS.7S 3.5)E-01( 1/ 2) 4 VALUES < LLD 3.15E 3.51E-01 3.51E 3.51E-01 PB-214 2.50E-01 9.19E-01( 5/ 6) TRM 277.9S 1.24E+00( 1/ 2) 3.60E-01( 3/ 4) 3.8(E 1.24E+00 1.24E+00- 1.24E+00 2.83E"01- 5.00E-O(

NOTE: 1. NOtlINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-I NOTE: 2. tlEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASVREMEt(TS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) .

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Di r ect Rad i at, i on Leve, s1 Browns Fer r y Nuc1ear P ant, 1 25 15 18 0 Ons 1 tc X Offs1tc 79 88 81 82 83 85 Year /Qu art,er

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Direct Radi ation Levels Brogans Fer ry Nuc l ear Pl ant 0 Quarter Moving Rver age 25 CO cz5

(

CO I g 15 i'oal CX3 18 0 Ons(te X Offs(te 77 78 88 81 82 85 86 87 88 89 98

~ It ~ v Year ~Quarter

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F H-3 Di rect Racl i at i on Leve s 1 t ~at ts Bar," Iuc I e ar P ) ant 38.

g S

Q3 h~8~ g s f ~

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0 OIIs f te

>< Offs ate g

77 I l~I.~ 79L..X 78

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- 82 I i I 83 LJ I. l 84 J.J-A 3 85 I J.J. I 86 AIJ t 87 I I I.. I 88 I ~ l..~~

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98 Year/Quar ter

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Di rect Radiation Levels

-Natts Bar Huc ear Pl ant 1

4-Quarter Moving Rver age 25I--

28I 15 18,'

0 Ons I to X OFfs1te

~mw.>.L x.s P7 78 '- '8

.( .J .( ( 1.L c..wx L ~i 88 81

( L( x 82

( J 83 mL> I 84

( ( ( t .(...1..

85 (2BG i 1.&amxt 87 88 w( x Bgl..az.. ( 3 88 Ye arr'Qu ar te1

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

Browns Ferry Nuclear Plant p R Indicator H Control C

i 0.25 Preoperational Operational Phase Phase

/

C 02 u Preoperational b 0 15 0

~

Average I

c 0.1 M 0.05 I'8 e

t 0 e 69 70 71 7273p73o74 75 76 77 78 79-80 81 82 83 84 85 86 87 88 89

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Figure H-6 Annual Average Gross Beta Activity Drinking Water (pCi/liter)

Browns Ferry Nuclear Plant

~ Indicator H Control Preoperational Operational Phase p Phase C Preoperational Average I

4

/

I 3 2

e 1 I'

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

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m m m m m w w w w w w w &w w m m

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Figure H-7 Annual Average Gross Beta Activity Surface Water (pCi/liter)

Browns Ferry Nuclear Plant R Indicator H Control p Preoperational Phase Operational Phase Preoperational C 5 Average I

4

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l 3 I

2 C+

e I'

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

• No gross beta measurements made in 1978

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