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Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1994
	ML18038B263
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Site:	Browns Ferry
Issue date:	12/31/1994
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT BRONNS FERRY NUCLEAR PLANT 1994 TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION Apri 1 1995 e505030l57 PDR ADOCK R

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TABLE OF CONTENTS Table of Contents List of Tables iv List of Figures Executive Summary Introduction Naturally Occurring and Background Radioactivi Electric Power Production ty v

2 2

5 Site/Plant Description Environmental Radiological Monitoring Program Direct Radiation Monitoring Measurement Techniques

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Results 8

10 14 14 16 Atmospheric Monitoring Sample Collection and Analysis Results

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19 19 21 Terrestrial Monitoring Sample Collection and Analysis Results 22 22 24 Aquatic Monitoring Sample Collection and Analysis Results Assessment and Evaluation Resul ts Conclusions 26 26 28 31 32 34 References Appendix A

Environmental Radiological Sampling Locations Appendix B

1994 Program Modifications Monitoring Program and 35 40 53

Appendix C

Program Deviations.

Appendix D

Analytical Procedures Appendix E

Nominal Lower Limits of Detection '(LLD) 55 58 61 Appendix F

Quality Assurance/Quality Control Program 67 Appendix G

Appendix H

Land Use Survey Data Tables 77 83

LIST OF TABLES Table 1

Table 2

Comparison of Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas Hith Reporting Levels and Lower Limits of Detection 36 Maximum Dose Due to Radioactive Effluent Releases 37

LIST OF FIGURES Figure 1

Tennessee Valley Region 38 Figure 2

Environmental Exposure Pathways of Man Oue to Releases of Radioactive Haterial to the Atmosphere and Lake 39

EXECUTIVE

SUMMARY

This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant (BFN) in 1994.

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,

'oil, fish, sediment, and direct radiation levels.

Results from stations near the plant are compared wi.th concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations.

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

Small amounts of Co-60 and Cs-134 were found in sediment samples downstream from the plant.

This activity in stream sediment would result in no measurable increase over background in the dose to the general public.

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 the requirements of 10 CFR 50, Appendix A, Criterion 64 and 10 CFR 50, Appendix I, Section IV.B, and to determine potential effects on public health and safety.

This report satisfies the annual reporting requirements of BFN Technical Specification 6..9.1.5 and Offsite Dose Calculation Manual (ODCM) Administrative Control 5.1.

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

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radioactivity measured both in plant effluents and in environmental samples.

Some of the data presented are prescribed by specific requirements while other data are included which may be useful or interesting to individuals who do not work with this material routinely.

Naturall Occurrin and Back round Radioactivi t Most materials in our world contain trace amounts of naturally occurring radioactivi,ty.

Approximately 0.01 percent of all potassium is radioactive potassium-40.

Potassium-40 (K-40), with a half-life of 1.3 billion years, is one of the major types of radioactive materials found naturally in our environment.

An individual weighing 150 pounds contains about 140 grams of potassium (Reference 1).

This is equivalent to approximately 100,000 pCi of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body.

Naturally occurring radioactive materials have always been in our environment.

Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-212 and 214, lead (Pb)-212

and, 214, thallium (Tl)-208, actinium (Ac)-228, uranium (U)-238, uranium-235,

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thorium (Th)-234, radium (Ra)-226, radon (Rn)-222, carbon (C)-14, and hydrogen (H)-3 (generally called tritium).

These naturally occurring radioactive materials are in the soil, our food, our drinking water, and our bodies.

The radiation from these materials makes up a part of'he low-level natural background radiation.

The remainder of the natural background radiation comes from outer space.

We are all exposed to this natural radiation 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day.

The average dose equivalent at sea level resulting from radiation from outer space (part of natural background radiation) is about 27 mrem/year.

This essentially doubles with each 6600-foot increase in altitude in the lower atmosphere.

Another part of natural background radiation comes from naturally occurring radioactive materials in the soil and rocks.

Because the quantity of naturally occurring radioactive material varies according to geographical

location, the part of the natural background radiation coming from this radioactive material also depends upon the geographical location.

Most of the remainder of the natural background radiation comes from the radioactive

.materials within each individual's body, We absorb these materials from the food we eat which contains naturally occurring radioactive materials from the soil.

An example of this is K-40 as described above.

Even building materials affect the natural background radiation levels in the environment.

Living or working in a building which is largely made of earthen material, such as concrete or brick, will generally result in a higher natural background radiation level than would exist if the same structure were made of wood.

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

Because the city of Denver,

Colorado, is over 5000 feet in elevation and the soil and rocks there contain more radioactive material than the U.S.

average, the people of Denver receive around 350 mrem/year total natural background

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radiation dose equivalent compared to about 295 mrem/year for the national average.

People in some locations of the world receive over 1000 mrem/year natural background radiation dose equivalent, primarily because of the greater quantity of radioactive materials in the soi 1 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 t

primarily adapted from References 2 and 3.

U.S.

GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source Hi 1 1 irem/Year Per Person Natural background dose equivalent Cosmic Cosmogenic Terrestrial In the body-Radon Total 27 1

28 39 200 295 Release of radioactive material in natural

gas, mining, ore processing, etc.

Medical (effective dose equivalent)

Nuclear weapons fallout Nuclear energy Consumer products Total 53 less than 1

0.28 0.03 355 (approximately)

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As can be seen from the table on the preceeding

page, natural background radiation dose equivalent to the U.S. population normally exceeds that from nuclear plants by several hundred times.

This indicates that nuclear plant operations normally result in a population radiation dose equi'valent which is insignificant compared to that which results from natural background radiation.

It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background cosmic and terrestrial radiation.

Significant discussion recently has centered around exposures from radon.

Radon is an inert gas given off as a result of the decay of naturally occurring radium-226 in soil.

Nhen dispersed in the atmosphere, radon

'I concentrations are relatively low.

However, when the gas is trapped in closed spaces, it can build up unti 1 concentrations become significant.

The National Council of Radiation Protection and Measurements (Reference 2) has estimated that the average annual effective dose equivalent from radon in the United States is approximately 200 mrem/year.

This estimated dose is approximately twice, the average dose. equivalent from all other natural background sources.

Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electrical generating plants.

The basic process behind electrical power production in both types of plants is that fuel is used to heat water to produce steam which provides the force to turn turbines and generators.

However, nuclear plants include many complex systems 'to control

the nuclear fission process and to safeguard against the possibility of reactor malfunctio'n, which could lead to the release of radioactive materials.

Very small amounts of these fission and activation products are released into the plant systems.

This radioactive material can be transported throughout plant systems and some of it released to the environment..

All paths, through which radioactivity is released are monitored.

Liquid and gaseous effluent monitors record the radiation levels for each release.

These monitors also provide alarm mechanisms to prompt termination of any release above limits.

Releases are monitored at the onsi te points of release and through an environmental monitoring program which measures the environmental radiation in outl'ying areas around the plant.

In this way, not only is.the release of

'radioactive materials from the plant tightly controlled, but measurements are made in surrounding areas to verify that the population is not being exposed to significant levels of radiation or radioactive materials.

The BFN ODCM, which is required by the plant Technical Specifications, prescribes limits-for the 'release of radioactive effluents, as well as limits for doses to the general public from the release of these effluents.

The dose to a member of the general public from radioactive materials released to unrestricted

areas, as given in NRC guidelines and in the ODCM, is limited as follows:

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Li uid Effluents Total body Any organ Gaseous Effluents

<3 mrem/year

<10 mrem/year Noble gases:

Gamma radiation Beta radiation

<10 mrad/year

<20 mrad/year Particulates:

Any organ

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

Total body Thyroid Any other organ 25 mrem/year 75 mrem/year 25 mrem/year 10 CFR 20.1302(b) presents annual average limits for the concentrations of radioactive materials released in gaseous and liquid effluents at the boundary of the unrestricted areas.

Table 1 of this report presents the annual average concentration limits for the principal radionuclides associated with nuclear power plant effluents.

This table also presents (1) the concentrations of radioactive materials in the environment which would require a special report to the NRC and (2) the detection limits for. the listed radionuclides.

It should be noted that the levels of radioactive materials measured in the environment are typically below or only slightly above the lower limit of detection.

The data presented in this report indicate compliance wi th the regulation.

SITE/PLANT DESCRIPTION Browns Ferry Nuclear Plant (BFN) is located on the north shore of Wheeler,

'eservoir at Tennessee River Mile 294 in Limestone County in north Alabama.

Wheeler Reservoir averages 1 to 1-1/2 miles in width in the vicinity of the plant.

The site, containing approximately 840 acres, is approximately 10 miles southwest of Athens,

Alabama, and 10 miles northwest of the center "of

Decatur, Alabama (Figure 1).

The dominant character of land use is small, scattered villages and homes in an agricultural area.

A number of relatively large farming operations occupy much of the land on the north side of the river immediately surrounding the plant.

The principal crop grown in the area is cotton.

At least two dairy farms are located within a 10-mile radius of the plant.

Approximately 2500 people live within a 5-mile radius of the plant.

The town of Athens has a population of about 15,000, while approximately 45,000 people li've in the city of Decatur.

The largest city in the area with approximately 145,000 people is Huntsville, Alabama, located about 24 miles east of the site.

Area recreation facilities are being developed along the Tennessee River.

The nearest facilities are two county parks located about 8 miles west-northwest of the site and a commercial boat dock across the river from the site.

The city of Decatur has developed'a large municipal recreation area.,

Point Mallard Park, approximately 15 miles upstream from the site.

The Tennessee River is also a popular sport fishing area.

BFN consists of three boiling water reactors; each unit is =rated at 1098 megawatts (electricai).

Unit 1 achieved criticality on August 17,

1973, and began commercial operation on August 1,

1974.

Unit 2 began commercial operation on March 1, 1975.

However, a fire in the cable trays 'on March 22, 1975, forced the shutdown of both reactors.

Units 1

and 2 resumed operation and Unit 3 began testing in August"1976.

Unit 3 began commercial operation in March 1977.

All three units were taken out of service in March 1985.

Unit 2 was restarted May 24, 1991 '

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM The unique environmental concern associated with a nuclear power plant is its production of radioactive materials and radiation.

The vast majority'of this radiation and radioactivity is contained within the reactor itself or one of the other plant systems designed to keep the material in the plant.

The retention of the materials in each level of control is achieved by system engineering,

design, construction, and operation.

Environmental monitoring is a final verification that the systems are performing as planned.

The

'monitoring 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 radiological monitoring program is outlined in Appendix A.

There are two primary pathways by which radioactivity can move through the environment to humans'.

air and water (see Figure 2).

The air pathway can be separated into two components:

the direct (airborne) pathway and the indirect (ground or terrestrial) pathway.

The direct airborne pathway consists of direct radiation and inhalation by humans.

In the terrestrial

pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans.

Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline.

The types of samples collected in this program are designed to monitor these pathways.

A number of factors were considered in determining the locations for collecting environmental samples.

The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weather patterns, dose projections, population distribution, and land use.

Terrestrial sampling stations were selected after reviewing such things as the locations of dairy animals and gardens in coqjunction with the air pathway analysis.

Liguid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and sediment.

Table A-2 (Appendix A, Table 2:

This identification system is used for all tables and figures given in the appendices.)

lists the sampling stations and the types of samples collected from each.

Modifications made to the program in 1994 are described in Appendix B and exceptions to the sampling and analysis schedule are presented in Appendix.C.

To determine the amount of radioactivity in the environment prior to the operation of BFN, a preoperational environmental radiological monitoring program was initiated in 1968 and operated until the plant began operation in 1973.

Measurements of the same types of radioactive materials that are measured currently were assessed during the preoperational phase to establish normal background levels for various radionuclides in the environment.

The preoperational monitoring program is a very important part of the overall program.

During the

1950s, 60s, and 70s, atmospheric nuclear weapons testing

'eleased radioactive material to the environment causing fluctuations in background radiation levels.

This radioactive material is the same type as that produced in the BFN reactors.

Preoperational knowledge of preexisting radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of whether the operation of BFN is impacting the environment arid thus the surrounding population.

The determination of impact during the operating phase also considers the presence of control stations that have been established in the environment.

Results of environmental samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to establish the extent, of BFN influence.

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

All analyses are conducted in accordance with written and approved procedures and are based on accepted methods.

A summary of the analysis techniques and methodology is presented in Appendix D.

Data tables summarizing the sample analysis results are presented in Appendix H.

The sophisticated radiation detection devices used to determine the radionuclide content of samples collected in the environment are generally quite sensitive to small amounts of radioactivity.

In the field of radiation measurement, the sensitivity of the measurement process is discussed in terms of the lower limit of detection (LLD).

A description of the nominal LLDs for the Radioanalytical Laboratory is presented in Appendix E.

The Radioanalytical Laboratory employs a comprehensive quality assurance/

year.

The program is intended to detect any problems in the measurement process as soon as'ossible 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.

The laboratory participates in the EPA Interlaboratory Comparison Program.

In addition, samples split with the EPA and the State of Alabama provide an independent verification of the overall performance of the laboratory.

A complete description of the program is presented in Appendix F.

DIRECT RADIATION MONITORING Direct radiation levels are measured at a number of stations around the plant site.

These measurements include contributions from cosmic radiation',

radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and radioactivity that may be present as a result of plant operations.

Because of the relative large variations in background radiation as compared to the small levels from the plant, contributions from the plant may be difficult to distinguish.

Radiation levels measured in the area around the BFN site in 1994 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 (thermo-), the electrons are released, producing a pulse of light (-luminescence).

The intensity of the light pulse is proportional to the amount of radiation to which the material was exposed.

Materials which display these characteristics are used in the manufacture of TLDs.

from 1968 through

1989, TVA used a Victoreen dosimeter consisting of a

manganese activated calcium fluoride (Ca>F:Mn)

TLD material encased in a glass bulb.

In 1989.,

TVA began the process of changing from the Victoreen dosimeter to the Panasonic Model UD-814 dosimeter, and completely changed to the Panasonic dosimeter in 1990.

This dosimeter contains four elements consisting of one lithium borate and three calcium sulfate phosphors.

The calcium sulfate phosphors are shielded by approximately 1000 mg/cm'lastic and lead to compensate for the over-response of the detector to low energy radiation.

The TLDs are placed approximately 1 meter above the ground, with three TLDs at each station.

Sixteen stations are located around the plant near the site

boundary, one station in each of the sixteen compass sectors.

Dosimeters are also placed at the perimeter and remote air monitoring sites and at 19 additional stations out to approximately 32 miles from the site.

The TLDs are exchanged every 3 months and the accumulated exposure on the detectors is read with a Panasonic Model UD-710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system.

Seven of the locations also have TLD devices processed by the NRC.

The results from the NRC measurements are reported in NUREG 0837.,

Since the calcium sulfate phosphor is much more sensitive than the lithium

borate, the measured exposure is taken as the median of the results obtained from the nine calcium sulfate phosphors in three detectors.

The values are corrected for gamma response, system variations, and transit exposure, with individual gamma response calibrations for each element.

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

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

The stations are grouped according to the distance from the plant.

The first group consists of all stations within 1 mile of the plant.

The second group lies between 1

and 2 miles, the third group between 2 and 4 miles, the fourth between 4 and 6 miles, and the fifth group is made up of all stations more than 6 miles from the plant.

Past data 'have shown that the average results from all. groups 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 t

dosimeters that were not as precise at lower exposures.

Consequently, the environmental radiation levels reported in th'e 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 Hatts Bar Nuclear Plant (NBN) environmental radiological monitoring program are referenced.

The NBN is a non-operating plant under construction near Spring City, Tennessee.

The quarterly gamma radiation levels determined from the TLDs deployed around BFN in 1994 are summarized in Table H-1.

The results from all measurements at individual stations are presented in Table H-2.

The exposures are measured in mi lliroentgens and reported in millirem per standard quarter.

For purposes of this report, one milliroentgen and one millirem (mrem) are assumed to be equivalent.

The rounded average annual exposures are shown below.

Annual Average Direct Radiation Levels mrem/ ear BFN WBN Onsite Stations Offsite Stations 68 60 65 58 The data in Table H-1 indicate that the average quarterly radiation levels at the BFN onsite stations are approximately 2 mrem/quarter higher than levels at the offsite stations.

This difference is also not'ed at the stations at WBN and other nonoperating nuclear power plant construction sites where the average levels onsite are generally 2-6 mrem/quarter higher than levels offsite.

The causes of these differences have not been isolated; however, it is postulated that the differences are probably attributable'o combinations of influences such as natural variations in e'nvironmental radiation levels, earth-moving activities onsite, and the mass of concrete employed in the construction of the plant.

Other undetermined influences m'ay also play a part.

These conclusions are supported by the fact that similar differences between onsite and offsite stations are currently observed in the vicinity of the WBN construction si te.

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 1994.

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

Figure H-2 presents a trend plot of the direct radiation levels as defined by the moving averages.

The data follow the same general trend as the raw data, but the curves are much smoother.

Figures H-3 and H-4 depict the environmental gamma radiation levels measured during the construction of TVA's HBN to the present.

Note that the data follow a similar pattern to the BFN data and that, as discussed

above, the levels reported at onsite stations are similarly higher than the levels at offsite stations.

All results reported in 1994 are consistent with direct radiation levels identified at locations which are not influenced by the operation of BFN.

" There is no indication that BFN.activities increase the background radiation N

levels normally observed in the areas surrounding the plant.

ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as local, perimeter, and remote.

In the current program, five local air monitoring stations are located on or adjacent to the plant site in the general directions of greatest wind frequency.

One additional station (station LM-4) is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data.

Three perimeter air monitoring stations are located in communities out to about 13 miles from the plant, and two remote air monitors are located out to 32 miles.

The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appendix A.

The remote stations are used as control or baseline stations.

Results from the analysis of samples in the atmospheric pathway are presented in Tables H-3 and H-4.

Radioactivity levels identified in this reporting period are consistent with background and radionuclides produced as a result of fallout from previous nuclear weapons tests.

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

Sam le Collection and Anal sis Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch Hollingsworth and Vose LB5211 glass fiber filter.

The sampling system consists of a pump, a

magnehelic gauge for measuring the drop in pressure across the system, and a

dry gas meter.

This allows an accurate determination of the volume of air passing through the filter.

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

The filter is cont'ained 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'o allow time for the radon daughters to decay.

Every 4 weeks composites of the filters from each location are analyzed by gamma spectroscopy.

On March. 27,

1989, two monitors, one local and one remote, were equipped with a second sampler.

The filters from these samplers are analyzed weekly for gross alpha and composited quarterly for analysis of transuranic isotopes and for Sr-89,90.

Gaseous radioiodine is collected using a commercially available cartridge containing TEDA-impregnated charcoal.

This system is designed to collect iodine in both the elemental form and as organic compounds.

The cartridge is located in the same sampling head as the air particulate filter and is downstream of the particulate filter.

The cartridge is changed at the same time as the particulate filter and samples the same volume of air.

Each cartridge is analyzed for I-131 by a complete gamma spectroscopy analysis.

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 conta'incr every 4

weeks.

Any excess water is discarded.

Samples are held to be analyzed only if the air particulate samples indicate the presence of elevated activity III

I levels or if fallout is expected.

For example, rainwater samples were analyzed during the period of fallout following the accident at Chernobyl in 1986.

Results The results from the analysis of air particulate samples are summarized in Table H-3.

Gross beta activity in 1994 was consistent with levels reported in previous years'he average level at indicator stations was 0.019 pCi/m'hile the average at control stations was 0.020 pCi/m'.

The annual averages of the gross beta activity in air particulate filters at these stations for the years 1968-1994 are presented in Figure H-5.

Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in

1969, 1970,

1971, 1977,

1978, and 1981.

Evidence of a small increase resulting from the Chernobyl accident can also be seen in 1986.

These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating 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 or transuranic isotopes were found at levels greater than the LLDs.

As shown in Table H-4, iodine-131 was not detected in any of the charcoal canister samples collected in 1994.

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

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TERRESTRIAL MONITORING 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 gr'azing.

When the cow ingests the radioactive

material, some of it may be transferred to the milk and consumed by humans who drink the milk.

Therefore, samples of milk, vegetation, soil, and food crops are collected and analyzed to determine the potential impacts from exposure to this pathway.

The results

.from the analysis of these samples are shown in Tables H-5 through H-14.

t A land use survey is conducted annually to locate milk, producing animals and gardens within a 5-mile radius of the plant.

Only one dairy farm is located in this area;

however, one additional dairy farm has been identified within 7 miles of the plant.

These two dairies are considered indicator stations and routinely provide milk samples.

No other milk-producing animals have been identified within 3 miles of the plant.

The results of the 1994 land use survey are presented in Appendix G.

Sam le Collection and Anal sis Milk samples are purchased every 2 weeks from two dairies within 7 miles of the plant and from at least one of two control farms.

These samples are placed on ice for transport to the radioanalytical laboratory.

A specific analysis for I-131 and a

gamma spectral analysis are performed on each sample and Sr-89,90 analysis is performed every 4 weeks.

Samples of vegetation are collected every 4 weeks for I-131 analysis.

The II samples are collected from one farm which previously produced milk and from one control dairy farm.

The samples are collected by cutting or breaking enough vegetation to provide between 100 and 200 grams of sample.

Care is taken not to include any soil with the vegetation.

The sample is placed in a container with 1650 ml of 0.5 N NaOH for transport back to the radioanalytical laboratory.

A second sample of between 750 and 1000 grams is also collected from each location.

After drying and grinding, this sample is analyzed by gamma spectroscopy.

Once each quarter, the sample is ashed after the gamma analysis is completed and analyzed for Sr-89,90.

Soil samples are collected annually from the air monitoring locations.

The samples are collected with either a "cookie cutter" or an auger type sampler.

After drying and grinding, the sample is analyzed by gamma spectroscopy.

Hhen the gamma analysis is complete, the sample is ashed and analyzed for Sr-89,90.

Analyses for transuranic isotopes are also performed on samples from the two monitoring stations with the second air samplers.

1 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 1994 samples of cabbage,

corn, peas,

potatoes, and tomatoes were collected from local vegetable gardens'n

addition, samples of apples and beef were also obtained from the area.

The edible portion of each sample is analyzed by gamma spectroscopy.

Results The results from the analysis of milk samples are presented in Table H-5.

No radioactivity which could be attributed to BFN was identified.

All I-131 results were less than the established nominal LLD of 0.4 pCi/liter.

Strontium-90 was found in seven of the samples.

These levels are consistent with concentrations measured in samples collected prior to plant operation and with concentrations repor'ted in milk as a result of fallout from atmospheric nuclear weapons tests (Reference 1).

Figure H-6 displays the average Sr-90 concentrations measured in milk since 1968.

The concentrations

'have steadily decreased as a result of the 28-year half-life of Sr-90 and the washout and transport of the element through the soil over the period.

The average Sr-90 concentration reported from indicator locations in 1994 was 2.5 pCi/liter; the concentration from control stations was also approximately 2.5 pCi/liter.

By far the predominant isotope reported in milk samples was the naturally occurring K-40.

An average of approximately 1300 pCi/liter of K-40 was 4

identified in all milk samples.

Similar results were reported for vegetation samples (Table H-6).

All I-131 and Cs-137 values were less than the nominal LLD.

Strontium-90 was identified in four of the eight samples.

The maximum concentration at the indicator station was approximately 29 pCi/Kg while the maximum concentration at the control station was 14 pCi/Kg.

Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7.

The only fission or activation products identified in soil samples was Cs-137.

The maximum concentration was approximately 0.6 pCi/g.

These

concentrations are consistent with levels previously reported from fallout.

All other radionuclides reported were naturally occurring isotopes (Table H-7).

A plot of the annual average Cs-137 concentrations in soil is presented in Figure H-7.

Like the levels of Sr-90 in milk, concentrations of Cs-137 in soil are steadily decreasing as a result of the cessation of weapons testing in the atmosphere, the 30-year half-life of Cs-137 and transport through the environment.

Analyses for transuranic isotopes (Am-241; Pu-238; Pu-239,240; Cm-242; and Cm-244) in soil have been performed since 1989.

The results have generally agreed with the concentrations reported by the Electric Power Research Institute (EPRI) in Reference 4.

The EPRI report concludes that essentially all of the radionuclides in soils from around the nuclear power plants participating in the study (including BFN) were of fallout origin and that the variations in concentrations were a function of soil texture, soil permeability, and/or disturbances of the soil surface The concentrations measured in 1994 are included in Table H-7.

Only naturally occurring radioactivity 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.

Analysis of these samples indicated no contribution from plant activities.

The results are reported in Tables H-8 through H-14.

t

~ (

I

A VATIC MONITORING Potential exposures from the liquid pathway can occur from drinking water, ingestion of fish and clams, or from direct radiation exposure to radioactive materials deposited in the river sediment.

The aquatic monitoring program includes the collection of samples of surface (river/reservoir) water, groundwater, drinking water supplies, fish, Asiatic clams, and bottom sediment.

Samples from the reservoir are collected both upstream and downstream from the plant.

Results from the analysis of aquatic samples are presented in Tables H-15 through H-22.

Radioactivity levels in water, fish and clams were consistent with background and/or fallout levels previously reported.

The presence, of Co-60, Cs-137 and Sr-90 was identified in sediment samples;

however, the projected exposure to the public from this medium is significantly less than 0.1 mrem/year.

Sam le Collection and Anal sis Samples of surface water are collected from the Tennessee River using automatic sampling pumps from two downstream stations and one upstream station.

A timer turns on the pump approximately once every hour.

The line is flushed and a sample collected into a collection container.

A 1-gallon sample is removed from the container every 4 weeks and the remaining water in the jug is discarded, The 4-week composite sample is analyzed. by gamma spectroscopy and for gross beta activity.

A quarterly composite sample is

Samples are also collected by an automatic sampling pump at the first A

downstream drinking water intake.

These samples are collected in the same manner as the surface water samples.

These monthly samples are analyzed by gamma spectroscopy and for gross beta activity.

At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source.

These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity.

A quarterly composite sample from each station is analyzed for Sr-89,90 and tritium.

The sample collected by the automatic pumping device is taken directly from the river at the intake structure.

Since the sample at this point is raw water, not water processed through the water treatment plant, the control sample should also be unprocessed water.

Therefore, the upstream surface water sample is also considered as a control sample for drinking water.

A groundwater well onsite is equipped with'an automatic water sampler.

Hater is also collected from a private well in an area unaffected by BFN.

Samples from the wells are collected every 4 weeks and analyzed by gamma spectroscopy.

A quarterly composite sample is analyzed for Sr-89,90 and tritium.

Samples of commercial and game fish species are collected semiannually from each of two reservoirs:

the reservoir on which the plant is located (Hheeler Reservoir) and the upstream reservoir (Guntersville Reservoir).

The samples are collected using a combination of netting techniques and electrofishing.

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

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

Bottom sediment is collected semiannually from selected Tennessee River Mile (TRM) locations using a dredging apparatus or divers.

The samples are dried and ground and analyzed by gamma spectroscopy.

After this analysis is

complete, the samples are ashed and analyzed for Sr-89,90.

Samples of Asiatic clams are collected from one location below the plant and one location above the plant.

The clams are usually collected in the dredging or diving process with the sediment.

Enough clams are collected to produce approximately 50 grams of wet flesh.

The flesh is separated from the shells, and the dried flesh samples are analyzed by gamma spectroscopy.

Sufficient quantities of clams to provide a sample are becoming more and more difficult to find.

Resu1ts All radioactivity in surface water samples was below the LLD except the gross beta activity and naturally occurring isotopes.

These results are consistent with previously reported levels.

A trend plot of the gross beta activity in surface water samples from 1968 through 1994 is presented in Figure H-8.

A summary table of the results for this reporting period is shown in Table H-15.

(

e

For drinking water, average gross beta activity was 2.4 pCi/1'iter at the downstream stations and 2.4 pCi/liter at the control stations.

The results are shown in Table H-16 and a trend plot of the gross beta activity in drinking water from 1968 to the present is presented in Figure H-9.

Concentrations of fission and activation products in groundwater samples were all below the LLDs.

Only naturally occurring radon decay products (Bi-214 and Pb-214) were identified in these samples.

Results from the analysis of groundwater samples are presented in Table H-17.

Cesium-137 was identified in two fish samples.

The downstream sample had a

concentration of 0.07 pCi/g while the concentration in the upstream sample was also 0.07 pCi/g.

The only other radioisotopes found in fish were naturally occurring.

Concentrations of K-40 ranged from 4.9 pCi/g to 16.3 pCi/g.

The results are summarized in Tables H-18, H-19, and H-20.

Plots of the annual average Cs-137 concentrations in fish are presented in Figures H-10, H-ll, and H-12.

Since the concentrations downstream are essentially equivalent to the upstream

levels, the Cs-137 activity is probably a result of fallout or other upstream effluents rather than activities at BFN.

Radionuclides of the types produced by nuclear power plant operations were identified in sediment samples.

The materials identified were Cs-137, Co-60, and Sr-90.

The average levels of Cs-137 were 0.51 pCi/g in downstream samples and 0.20 pCi/g upstream.

The Cs-137 concentrations at downstream stations has historically been higher than concentrations upstream.

This relationship is graphically represented in Figure H-13 which presents a plot of the Cs-137 concentrations in sediment since 1968.

Cobalt-60 concentrations in downstream samples averaged 0.15 pCi/g, while concentrations in 'upstream samples were below the lower limit of detection.

The maximum concentration downstream was 0.43 pCi/g.

Figure H-14 presents a

graph of the Co-60 concentrations measured in sediment since 1968.

The Sr-90 concentration in one upstream sample was 0.57 pCi/g.

Levels in three downstream 'samples averaged 0.67 pCi/g, with a maximum of 0.85 pCi'/g.

The remaining samples showed no Sr-90 activity.

A realistic assessment of the impact to the general public from these radioisotopes produces a'negligible dose equivalent.

Results from the analysis of sediment samples are shown in Table H-21.

Only naturally occurring radioisotopes were identified in clam flesh samples.

The results are presented in Table H-22.

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

These models were developed by TVA and are based on methodology provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living in the vicinity of a nuclear power plant.

The doses calculated are a representation of the dose to a "maximally exposed individual."

Some of the factors used in these calculations (such as ingestion rates) are maximum expected values which will

,tend to overestimate the dose to this "hypothetical" person.

In reality, the expected dose to actual individuals is lower.

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

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

drinking water 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.

For gaseous effluents, the public can be exposed to radiation from several sources:

direct r'adiation 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 I

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 maximally exposed individual due to radioactivity released from BFN in 1994 are presented in Table 2.

These estimates were made using the concentrations of the liquids and gases measured at the effluent monitoring points.

Also shown are the ODCH 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 0.03 mrem/year, or 1.0 percent of the limit.

The maximum organ dose equivalent from gaseous effluents is 0.028 mrem/year.

This represents 0.19 percent of the ODCM limit.

A more complete description of the effluents released from BFN and the corresponding doses projected from these effluents can be found in the BFN Radioactive Effluent Release Reports.

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

equivalent to the general public resulting from the operation of BFN is undetectably small'hen 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-137, and Sr-90 were seen in aquatic media.

The distribution of Cs-137 and Sr-90 in sediment is similar to fallout levels identified in samples both upstream and downstream from the plant during the preoperational phase of the monitoring program.

Co-60 was identified in sediment samples downstream from the plant in concentrations which would produce no measurable increase in the dose to the general public.

No increases of radioactivity have been seen in water samples.

Dose estimates were made from concentrations

'of radioactivity found in samples of environmental media.

Media evaluated

include, but are not limited to, air, milk, food products, drinking water, and fish.

Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons a't control stations.

Nore than 99 percent of those doses were contributed by the naturally occurring radionuclide K-40 and by Sr-90 and Cs-137, which are long-lived radioisotopes found in fallout from nuclear weapons testing.

Concentrations of Sr-90 and Cs-137 are consistent with levels measured in TVA's preoperational environmental radiological monitoring programs.

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

The radioactivity reported herein is primarily the 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

'xposure of members of the public.

34

REFERENCES 1.

Merril Eisenbud, Environmental Radioactivit; Academic Press, Inc.,

New York, NY, 1987.

2.

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

September 1987.

3.

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

4.

Electric Power Research Institute, Report No.

EPRI EA-2045, Project

1059, "Transuranium and Other Long-Lived Radionuclides in the Terrestrial Environs of Nuclear Power Plants,"

September 1981.

Table 1

A V

Effluent Reporting Lower Limit afJh.~uP Effluent Reporting Lower Limit H-3 Cr-51 Hn-54 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Nb-95 Zr-95 Ru-103 Ru-106 I-131 Cs-134 Cs-137 Ce-144 Ba-140 La-140 1,000 F 000 500,000 30,000 20,000 30,000 5,000 8,000 500 30,000 20,000 30,000 3,000 1,000 900 1,000 3,000 8,000 9,000 20,000 1,000 1,000 300 300 400 400 2

30 50 200 200 250 45 5

5 5

10 3

1.4 5

10 5

40 1

5 5

33 25 8

100,000 30,000 1,000 1,000 50 400 1,000 6

2,000 400 900 20 200 200 200 40 2,000 2,000 0.9 10 20 0.02 0.005 0.005 0.005 0.005 0.0006 0.0003 0.005 0.005 0.005 0.02

~ 0,02 0.005 0.005 0.01 0.01 0.005 Note:

1 pCi = 3.7 x 10

~ Bq.

Note:

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

1 Source:

Table 2 of Appendix B to 10 CFR 20. 1001-20.2401 2

Source:

BFN Offsite Dose Calculation Hanual, Table 2.3-3 3

Source:

Table E-1 of this report

0

Table 2

Maximum Dose due to Radioactive Effluent Releases Browns Ferry Nuclear Plant 1994 mrem/year Li uid Effluents

~Te 1994 Dose NRC Limit Percent of NRC Limit EPA Limit Percent of EPA Limit Total Body 0.03 Any Organ 0.04 10 7 1.0 0.4 25 25 0.1 0.2 Gaseous Effluents

~Te Noble Gas (Gamma)

Noble Gas (Beta)

Any Organ 1994 Dose 0.002 0.003 0.028 NRC Limit 10 20 15 Percent of NRC Limit 0.02 0.02 0.19 EPA Limit 25 25 Percent of EPA Limit 0.01 0.01 0.11

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'I

APPENDIX A ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM AND SAMPLING LOCATIONS 40

Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Honi toring Program'xposure Pathway Number of Samples and Sampling and 1

Type and Frequency AIRBORNE Parti cul ates Six samples from locations (in different sectors)

~ at or near boundary site (LH-1, LH-2 LH-3, LH-4, LH-6, and LH-7)

Two samples from control locations greater than 10 miles from the plant (RH-1 and RH-6)

Three samples from locations in communities approximately 10 miles from the plant PH-l, PH-2, and PH-3)

Continuous sampler operation with sample collection as required by dust loading but at least once per 7 days Particulate sampler.

Analyze for gross beta radioactivity greater than or equal to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.

Perform galena isotopic analysis on each sample when gross beta activity is greater than 10 times the average of control samples.

Perform gaama isotopic analysis on composite (by location) sample at least once per 31 days.

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

Table A-1 BROWNS FERRY.NUCLEAR PLANT Environmental Radiological Honitoring Program'xposure Pathway m

Soil Direct Number of Samples and Sampl es from same 1 ocati ons as air particulates Two or more dosimeters placed at locations (in different sectors) at or near the site boundary in each of the 16 sectors Two or more dosimeters placed at stations located approximately 5 miles from the plant in each of the 16 sectors Sampling and Once every year At least once per 92 days At least once per 92 days Type and Frequency Gamma scan, Sr-89, Sr-90 once per year Galena dose once per 92 days Gamma dose once per 92 days WATERBORNE Surface Water Drinking Mater Two or more dosimeters in at.

least 8 additional locations of special interest One sample upstream (TRH 305.0)

One sample immediately down-stream of discharge (TRH 293.5)

One sample downstream from plant (TRH 285.2)

One sample at the first potable'urface water supply downstream from the plant (TRH 282.6)

Collected by automatic sequential-type sampler with composite sample taken at least once per 7 days'ollected by automatic sequential-type sampler with composite sample taken at least once per 31 days Gross beta and ganea scan on 4-week composite.

Composite for Sr-89, Sr-90, and tritium at least once per 92 days Gross beta and ganma scan on 4-week composite.

Composite for Sr-89, Sr-90, and tritium at least once per 92 days

(I

Table A-l BROWNS FERRY NUCLEAR PLANT Environmental Radiological Honitoring Program'xposure Pathway n

r m

Orinking Water (Continued)

Ground Water I

Number of Samples and Three additional samples of potable surface water down-stream from the plant (TRH 274.9, TRH 259.5 and TRH 259.8)

One sample at a control location (TRH 306)

One additional sample at a control'location

~

(TRH 305)

One sample adjacent to the plant (Well No. 6)

One sample at a control location upgradient from the plant (Farm Sn)

Sampling and 1

Grab sample taken at least once per 31 days Collected by automatic sequential-type sampler with composite sample taken at least once per 7 days Collected by automatic sequential-type sampler with composite sample taken at least once per 31 days Grab sample taken at least once per 31 days Type and Frequency A

Gross beta and gamma scan on each sample.

Composite for Sr-89, Sr-90, and tritium at least once per 92 days Gamma scan on each composite.

Composite for Sr-89, Sr-90, and tritium at least once per 92 days Gamma scan on each sample.

Composite for Sr-89, Sr-90, and tritium at least once per 92 days AQUATIC Sediment Two samples upstream from discharge point (TRH 297.0 and 307.52)

One sample in immediate downstream area of discharge point (TRH 293.7)

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

At least once per 184 days At least once per 184 days Gamma scan',

Sr-89 and Sr-90 analyses Gamma scan, Sr-89 and Sr-90 analyses

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

Type and Frequency INGESTION Hilk Fish Clams At least 2 samples from dairy farms in the immediate vicinity of the plant (Farms 8 and Bn)

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

Three samples representing commercial and game species in Guntersville Reservoir above the plant Three samples representing commercial and game species in Wheeler Reservoir near the plant.

One sample downstream from the discharge One sample upstream from the plant (No permanent stations established; depends on location of clams)

At least once per 15 days when animals are on pasture; at least once per 31 days at other times At least once per 184 days At least once per 184 days Gamma scan and I-131 on each sample.

,Sr-89 and Sr-90 at least once per 31 days Gamma scan at least once per 184 days on edible portions Gamma scan on flesh only

Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program'xposure Pathway Fruits and Vegetables Vegetation Number of Samples and Samples of food crops such as

corn, green

beans, tomatoes, and potatoes grown at private gardens and/or farms in the immediate vicinity of the plant One sample of each of the same foods grown at greater than 10 miles distance from the plant Samples from farms producing milk but not providing a milk sample (Farm T)

Control samples from one control dairy (Farm GL)

Sampling and 1

At least once per year at time of harvest Once per 31 days Type and Frequency Gamma scan on edible portion I-131, gamma scan once per 31 days a.

b.

c-d.

The sampling program outlined in this table is that which was in effect at the end of 1993.

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.

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

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

Table A-2 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Map Location Number'tation Approximate Indicator (I)

Distance or Sector (miles)

Control (C)

Samples Collected'

. 2 3

4 5

6 7

8 9

10ll 12 13 18 22 23 24 25 26 27 28 29 30 31 32 33 34 36 37 70 PM-1 PM-2 PM-3 LM-7 RM-1 RM-6 LM-1 LM-2 LM-3 LM-4 LM-6 Farm B

Farm Bn Farm G1 Well No.

6'RM'82.6 TRM 306.0 TRM 259.6 TRM 274.9 TRM 285.2 TRM 293.5 TRM 305.0 TRM 307.52 TRM 293.7 TRM 288.78 TRM 277.98 Farm Be Farm T

TRM 297.0 TRM 259.8 NH NE SSE H

H E

N NNE ENE NNH SSH NNW N

WSH NW 13.8 10.9 8.2 2.1 31.3 24.2 1.0 0.9 0.9 1.7 3.0 6.8 5.0 35.0 0.02 11.4 12.0'4 4'9.1'.8'.54 11.0 13.52 0

3'.22'6.02'8.8 3.2.

3.0 34.2 Ce CI II AP,CF,R,S'P,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S AP,CF,R,S M,

M,H M,V W

PH PW PW PW SW SW SW SD SD SD SD M

V SD PW

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

Map Location Number'tation Approximate Indicator (I)

Distance or Samples Sector (miles)

Control (C)

Collected'heeler Reservoir'TRM 275-349)

Guntersvi lie Reservoir'RM (349-424)

F,CL a.

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

b.

Sample Codes:

AP = Air particulate filter CF =.Charcoal filter (Iodine)

CL = Clams F

= Fish M = Milk PW = Public drinking water c.

TRM = Tennessee River Mile d.

Miles from plant discharge (TRM 294).

e.

Also used as a control for public water.

R

= Rainwater S

= Soil SD = Sediment SW = Surface water V

= Vegetation W

= Well water Table A-3 BROWNS FERRY NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) Locations Map Location Number' 2

3 5

6 7

8 9

10 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 Station NH-3 NE-3 SSE-2 H-3 E-3 N-1 NNE-1 ENE-1 NNH-2 N-2 NNE-2 NNE-3 NE-1 NE-2 ENE-2 E-1 E-2 ESE-1 ESE-2 SE-1 SE-2 SSE-1 S-l S-2 SSW-1 SSW-2 SH-1 SH-2 SH-3 HSW-l.

WSW-2 HSH-3 W-1 H-2 H-4 HNW-1 WNH-2 NH-1 NW-2 Sector NW NE SSE W

E N

NNE ENE NNW N

NNE NNE NE NE ENE E

E ESE ESE SE SE SSE S

S SSW SSW SW SW SW HSW HSW HSW H

H H

HNW HNW NW NW Approximate Distance (miles) 13.8 10.9 8.2 31.3 24.2 0.97 0.88 0.92 1.7 5.0 0.7 5.2 0.8 5.0 6.2 0.8 5.2 0.9 3.0 0.5 5.4 5.1 3.1 4.8 3.0 4.4 1.9 4.7 6.0 2.7 5.1 10.5 1.9 4.7 32.1 3.3 4.4 2.2 5.3 Onsi te (On)'r Offsite (Off)

Off Off Off Off Off On On On On Off On Off On Off Off On Off On Off On Off Off Off Off Off Off On Off Off Off Off

'ff On Off Off Off Off Off Off

'48-

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

Map Location Number'8 69 Station NNH-1 NNH-3 Sector Approximate Distance (miles) 1.0 S.2 Onsite (On)'r Offsite (Off)

On Off a.

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

b.

TLDs designated onsi te are those located 2 miles or less from the plant.

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

Figure A-1 Environmental Radiological Sampling Locations Within 3 Mile of Plant

.NW 326.2 348.75 1 1.25 NNE 7

33.75 NE 303.75 39 56.25 WNW 258.7 5 WSW 28',o~

31m L

/i' gROWNS FERRY NUCLEAR PLANT IIIIIIIW 48 9

~44

~46 ENE 78.75 101.25 ESE 236.25 123.75 SW 213.75 SSW SSE S

168 75 Scale Mile 146.25 SE

Figure A-2 Environmental Radiological Sampling Locations From 1 to 5 Miles From the Plant NNW 348.75

~ 8 13 11.25 NNE 328.25 33,75 NW 42 303.75 58.25 WNW 65

~

6

~ 10 ENE 281.25 36, 64 78.75

~ 62 61 4

r.

SROWNS PER Y

NUCLEAR PLANT 258,75 WSW Ss 47 y 37 ~

+~

Bg

/1, a101.25 qb ESE 238.25 53 51 123.75 SW'13.75 SSW

~ 54 181.25 52 188.75 SSE 148.25 SCALE 0

0.5 1

0.5 2

MILES

Figure A-3 I

Environmental Racfiological Sampling Locations Greater Than 5 Miles From the Plant NNW 348.75 11.25 NE 328.25 33.75 NW AW ENCEBURO PULASKI NE 303.75 FAYETTEV LLE 56.25 WNW 34 ENE FLORENCE AT ENS 78.75 258.75 S EE 63 U

LO 2

CLE ICAL 6

LKE Lf 2

57 9

43 45 3

OECATUR SAN s

6

~ -

UNTSVILLE 101.25 WS RUSS VILLE 18 ESE OUH'IERSVK.LE AM 326.2 NALEYVI LE ARAB 123.75 SW CULLMAN SE 213.75 SSW 191.25 168.75 SSE 14B.25 SCALE

~

0 I

MILES 0

25

APPENDIX 8

~ 1 994 PROGRAM MODIFICATIONS APPENDIX B

Environmental Radiolo ical Monitorin Pro ram Modifications DUring 1994, no modifications were made to the BFN radiological environmental monitoring program.

APPENDIX C PROGRAM DEVIATIONS

Append) x C Pro ram Deviations During 1994, a small number of samples were not collected.

Those occurrences resulted in deviations from the scheduled program but not from the minimum program required in the Offsite Dose Calculation Manual.

Table C-1 lists these occurrences.

A general description follows.

Gross beta analysis of two public water samples could not be performed because of the presence of a large. volume of solids in the samples.

One air particulate and charcoal filter sample set was missed as a result of a t

malfunction in the switch on the sampler.

The switch was replaced and subsequent samples collected as scheduled.

Two air particulate composite sampl'es were lost during the strontium analysis as a result of bad ion exchange resin.

Table C-1 Environmental Radiolo ical Monitorin Pro ram Deviations Date Station Location Remarks 2/14/94

Florence, AL 34.2 miles downstream Gross Beta analysis of the public water sample could not be reliably performed because of a large volume of solids in the sample.

8/29/94 8/29/94 Champion Paper Co.

LM-1 BF 5 RM-6 BF 11.4 miles downstream 1.0 miles N

24.2 miles E

Gross Beta analysis of the public water sample could not be reliably performed because of a large volume of solids in the sample.

The composite air filter samples from these stations were lost during the strontium analysis as a

result of impurities in the ion exchange

resin, consequently concentrations of Sr-89 and Sr-90 were not determined.

The resin was replaced and subsequent strontium analyses completed.

11/21/94 LM-7 BF 2.1 mi les 0

Air particulate and charcoal filters were not collected as a result of a malfunction in the switch on the sampler.

The switch was replaced and subsequent samples collected.

APPENDIX D ANALYTICAL PROCEDURES

APPENDIX D Anal tical Procedures Analyses of environmental samples are performed by the radioanalytical laboratory located at the Hestern Area Radiological Laboratory facility in Muscle Shoals, Alabama.

All analysis procedures are based on accepted methods.

A summary of the analysis techniques and methodology follows.

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

Normal counting times are 50 minutes.

Hater samples are prepared by evaporating 500 ml of samples to near dryness, transferring to a stainless steel,planchet and completing the evaporation process.

For solid samples, a

specified amount of the sample is packed into a deep stainless steel planchet.

Air particulate filters are counted directly in a shallow planchet.

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

The normal count time is 100 minutes.

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

After a radiochemical separation, samples analyzed for Sr-89,90 are counted on a low background beta counting system.

The sample is counted a second time after a 7-day ingrowth period.

From the two counts the Sr-89 and Sr-90 concentrations can be determined.

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

A commercially available scintillation cocktail is used.

Gamma analyses are performed in various counting geometries depending on the sample type and volume.

All gamma counts are obtained with germanium type detectors interfaced with a computer based mutlichannel analyzer system.

Spectral data reduction is performed by the computer program HYPERMET.

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

All of the necessary efficiency values, weight-efficiency curves, and geometry tables are established and maintained on each detector and counting system.

A series of daily and periodic quality control checks are performed to monitor counting instrumentation.

System logbooks and control charts are used to document the results of the quality control checks.

The analysis of transuranic isotopes in soil and air filters is performed by leaching the sample with acid and then separating the isotopes of interest from the acid leach by an ion exchange technique.

The ion exchange technique separates the samples into two fractions, one containing plutonium and the other containing both americium and curium.

The Pu fraction and the Am/Cm fractions are electroplated onto separate stainless steel

discs, and counted for 1200 minutes on an alpha spectrometer employing a surface barrier detector'.

APPENDIX E

NOMINAL LONER LIMITS OF DETECTION (LLD)

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 gas, or from electronic noise.

Thus, there is always some sort of signal on these sensitive devices..

The signal registered when no activity is present in the sample is called the background.

The point at which the signal is determined to represent radioactivity in the sample is called the critical level.

This point is based on statistical analysis of the background readings from any particular device.

However, any sample measured over and over in the same device will give different readings, some higher than others.

The sample should have a 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.

Every time an activity is calculated from a sample, the background must be subtracted from the sample signal.

For the very low levels encountered in environmental monitoring, the sample signals are often very close to the background.

The measuring equipment is being used at the limit of its capability.

For a sample with no measurable activity, which often happens, about half the time its signal should fall below the average machine background and half the time it should be above the background.

If a signal above the background is present, the calculated activity is compared to the calculated LLD to determine if there is really activity present or if the number is an artifact of the way radioactivity is measured.

A number of factors influence the LLD, including sample size, count time, counting efficiency, chemical processes, radioactive decay factors, and interfering isotopes encountered in the sample.

The most likely values for these factors have been evaluated for the various analyses performed in the environmental monitoring program.

The nominal LLDs calculated from these

values, in accordance with the methodology prescribed in the ODCM, are presented in Table E-1:

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

The LLDs are also presented in the data tables.

For analyses for which LLDs have not been established, an LLD of zero is assumed in determining if a measured activity is reported as greater than the LLD.

Table E-1 Hominal LLD Values A.

Radiochemical Procedures Air Filters LaCiLm'1 Water

~ii~

Sediment Hilk Fish Wet Vegetation and Soil

&Mmlrzl ~LimN)

Q>Miler Gross Beta Tritium Iodine-131 Strontium-89 Strontium-90 0.002 0.0011 0.0004 1.9 300 0.4 5.0 2.0 0.4 2.0 2.0 0.09 0.03 6.0 31.0 12.0 1.6 0.4

Table E-1 Nominal LLD Values B.

Gamma Analyses (GeLi)

Air Particulates

~Xi/m3 Charcoal Filters Mater and Hilk

-a>XL23

Fish, Vegetation and Grain aQLi~in Wet Vegetation aQLl~at Soil and Foods Tomatoes Sediment Clam Flesh

Potatoes, etc.

QL hit Heat and Poultry

<~w Ce-141 Ce-144 Cr-51 I-131 Ru-103 Ru-106 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Hn-54 Zn-65 Co-60 K-40 Ba-140 La-140 Fe-59 Be-7 Pb-212 Pb-214 Bi-214 Bi-212 Tl-208 Ra-224 Ra-226 Ac-228 Pa-234m 0.005

.01

.02

.005

.02

.005

.04 0.015 0.01

.005

.02

.005

.02

.002

.01 0.50

.02

.07

.15

.03

.02

.12

.02

.03

.02

.03

.02

.30

.07

.04

.15

.03

.07

.05

.20

.02

.07 3.20 10 30 45 10 5

40 5

5 10 5

5 5

10 5

100 25 10 10 45 15 20 20 50 10 20 800

.07

.15

.30

.20

.03

.15

.03

.05

.25

.03

.05

.03

.40

.30

.20

.08

.25

,.04

.50

.10

.25

.03

.10 4.0 35 115 200 60 25 190 30 25 45 30 20 20 45 20 400 130 50 40 200 40 80 55 250 30 70

'4000

.10

.20

.35

.25

.03

.20

.03

.05

.035

.03

.05

.03

.75

.30

.20

.05

.25

.10

.15

.45

.06

.75

.15

.25 4.0

.35

.85 2.40

1. 70

.25 1.25

.14

.15

.45

.25

.20

.40

.20 3.50 2.40 1.40

.45 1.90

.30

.10

.50 2.00

.25 3.00

.50

.75 35.00 20 60 95 20 25 190 10 10 45 10 10 10 45 10 250 50 25 25 90 40 80 40 130 30 50 2500 15 50 75 25 15 60 10 10 20 10 10 10 20 10 200 50 30 20 70 20 40 25 90 30

" 30 2000

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

Specified by the BFN Offsite Dose Calculation Manual Hater

~Anal sls gCi/L Airborne Particulate or Gases Fish Milk

~Cl/m'Cl/K wet ~Cl/L Food Products Sediment

~ii

~ld Mn-54 Fe-59 Co-58,60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 15 30 15 30 30 15 1 l 15 18 60 15 gross beta 4

H-3 2000 x 10

'.A.

N.A.

7x10' x 10-z 6

x 10-'.A.

N.A.

130 260 130 260 N.A.

N.A.

130 150 N.A.

N.A.

15 18 60 15 N.A.

N.A.

60 60 80 N.A.

N.A.

150 180 N.A.

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

APPENDIX F

QUALITY ASSURANCE/QUALITY CONTROL PROGRAM

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 on all devices.

In the first type, the device is operated without a sample on the detector to determine the background count rate.

The background counts are usually low values and are due to machine noise, cosmic rays, or trace amounts of radioactivity in the materials used to construct the detector.

Charts of background counts are kept and monitored to ensure that no unusually high or low values are encountered.

In the second test, the device is operated with a known amount of radioactivity present.

The number of counts registered from such a

radioactive standard should be very reproducible.

These reproducibility checks are also monitored to ensure that they. are neither higher nor lower than expected.

Nhen counts from.either test.fall outside the expected

range, the device is inspected for malfunction or contamination.

It is not placed into service until it is operating properly.

In addition to these two general

checks, other quality control checks are performed on the variety of detectors used in the laboratory.

The exact nature of these checks depends on the type of 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 verify the performance of different portions of the analytical process.

These quality control samples may be blanks, replicate

samples, blind samples, or cross-checks.

Blanks are samples which contain no measurable radioactivity or no activity of the type being measured.

Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical

process, or interference from isotopes other than the one being measured.

Duplicate samples are generated at random by the same computer program which schedules the collection of the routine samples.

For example, if the routine program calls for four milk samples every week, on a random basis each farm might provide an additional sample several times a year.

These duplicate samples are analyzed along with the other routine samples.

They provide information about the variability of radioactive content in the various sample media.

If enough sample is available for a particular analysis, the laboratory analyst can split it into two portions.

Such a sample can provide information about the variability of the analytical process since two identical portions of material are analyzed side by side.

Analytical knowns are another category of quality control sample.

A known amount of radioactivity is added to a sample medium by the quality control staff or by the analysts themselves.

The analysts are told the radioactive content of the sample.

Hhenever possible, the analytical knowns contain the same amount of radioactivity each time they are run.

In this way, the analysts have immediate knowledge of the quality of the measurement process.

A portion of these samples are also blanks.

Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples.

The analyst, does not know they contain radioactivity.

Since the bulk of the ordinary workload of the environmental laboratory contains no measurable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the laboratory or they can be used to test the data review process.. If an analysis routinely generates numerous zeroes for a

t 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 (near the LLD) to determine whether or not the laboratory can find any unusual radioactivity whatsoever.

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

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

This means that the quality control staff knows the radioactive content or "right answer" but the analysts do not.

They are aware they are being tested.

Such samples test the best performance of the laboratory by determining if the analysts can find the "right answer."

These samples provide information about the accuracy of the measurement process.

Further information is available about the variability of the process if multiple analyses are requested on the same sample.

Internal cross-checks can also tell if there is a difference in performance between two analysts.

Like blind spikes or analytical

knowns, these samples can also be spiked with low levels of activity to test detection limits.

A series of cross-checks is produced by the EPA in Las Vegas.

These interlaboratory comparison samples or "EPA cross-checks" are considered to be the primary indicator of laboratory performance.

They provide'n 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 standa'rds produced by individuals outside TVA are used in the cross-checks.

The results of the analysis of these samples are reported back to EPA which then issues a report of all the results of all participants.

These reports are examined very closely by laboratory supervisory and quality control personnel.

They indicate how well the laboratory is doing compared to others across the nation.

Like internal cross-checks, the EPA cross-checks provide information to the laboratory about the'recision and accuracy of the radioanalytical work it does.

The results of TVA's participation in the EPA Interlaboratory Comparison Program are presented in Table F-1 and Figure F-1.

For 1994, all but one EPA cross-check sample concentrations measured by TVA's laboratory were within ~

3-sigma of the EPA reported values.

TVA splits certain environmental samples with laboratories operated by the States of Alabama and Tennessee and the EPA National Air and Radiation Environmental Laboratory in Montgomery, Alabama.

Nhen radioactivity has been present in the environment in measurable quantities, such as following atmospheric nuclear weapons testing, following the Chernobyl incident, or as naturally occurring radionuclides, the split samples have provided TYA with yet another level of information about laboratory performance.

These samples demonstrate performance on actual environmental sample matrices rath'er than on the constructed matrices used in cross-check programs.

A11 the quality control data are routinely collected,

examined, and reported to laboratory supervisory personnel.

They are ch'ecked for trends, problem

areas, or other indications that a portion of the analytical process needs correction or improvement.

The end result is a measurement process that provides reliable and verifiable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans.

Table F-1 RESULTS OBTAINED IN INTERLABORATORY COHPARISON PROGRAH A.

Air Filter (pCi/Filter)

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

~

~>L9mm

~v

~

~~m~ ~v.

~i~m

~v 8/94 35 46 31 56 17 58 20=9 18 15 9 15 B.

Radiochemical Analysis of Water (pCi/L) 1/94 2/94 3/94 EPA Value TVA mmaL hm.

62 17 66 EPA Value TVA XQ.mmes

/ha.

25 9 21 EPA Value TVA

~v 15 9 15 EPA Value TVA U~mal hm.

4936$ 856 4874 EPA Value TVA

&mal hm.

119 21 121 EPA Value TVA

~~(~mt)

~v.

28 5 27 4/94~

7/94 8/94 10/94'0/94 10 9

23 9

20 20 20 9

30 9

25 9 19 28 22 14 9 20 9 15 9

~ 14 18 9951 1723 9501 15 79 14 104 74

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

C.

Gamma-Spectral Analysis of Hater (pCi/L)

EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA

&mmes Wv tQ.mme hm

~Smal hm MmMm hm.

LQ.W<mal hm.

LQ.mmal hZ.

4/94~

6/94 10/94'1/94 98 17 89 73 12 73 20=9 50 9 40 9 59=9 20 50 134 23 39 58 100 17 134 252 43 227 100 34 9 40=9 20=9 24 9 33 29=9 30 36 49 9 52 20 39 9 41 22 '9 9 51 0.

Milk (pCi/L)

EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA A~v.

~~IIg~m

~. ~~~ ~.

~~iqmJL)

~v. ~~~

~v 9/94 25=9 26 15 9 17 75 14 80 59=9 63 1715 149 1713 a.

Performance Evaluation Intercomparison Study.

b.

The Grand Average of non-outlier participants indicates that the Performance Evaluation Standard had a postative bias for Gross Beta.

If the Grand Average of 14.91 pCi/liter were used for the known, TVA's results would be 1.65 sigma from the known.

c.

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

L ~

EPA Crosscheck Summary for 1994 gamma spectroscopy methods EPA Crosscheck Summary for 'l994 analytical chemistry methods

-2 (found - given) IEPA Sigma

-1 0

1

-2 (found - given) / EPA sigma 0

2 air filter milk milk milk Cs-137 Total K Cs-137 l-131 air filter air filter air filter milk Gross Alpha Gross ela Sr40 Sr 8

vrater water water water water water vrater water water water water water water water water water water I'a-133

- Cs-134

=

Ru-$06,:,

-Co40 os-134 Ba-133 Co40 Cs-134:.

Zn45 Cs;13? ~

Cs-137 Co40

-Cs-134 5-137 Co40 Cs-13?

milk water water water water water water water water water water water water water water water water Sr49 Sr40 Sr40 Gro s Beta l-13

. H4

)

= Pu-239 1

,Sr49 Sr40

< Sr49 -

, Sr40

'-H4 I!131:

=

'r48 Sr40 Gross Beta

.,- Gross B Laboratory objective: abs[(found - given)/EPA sigma ] < 3

APPENDIX G

LAND USE SURVEY

Appendix G

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

The land use survey also identifies the location of all milk animals and gardens of greater than 500 square feet producing fresh leafy vegetables within a distance of 3 miles from the plant.

The land use survey is conducted between April 1

and October 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.

In order to identify the locations around BFN which have the greatest relative potential for impact by the plant, radiation doses are projected for individuals living near BFN.

These projections use the data obtained in the survey and historical meteorological data.

They also assume that the plant is operating and that releases are equivalent to the design basis source terms.

The calculated doses are relative in nature and do not reflect actual exposures to individuals living near BFN.

Calculated doses to individuals based on measured effluents from the plant are well below applicable dose limits (see Assessment and Evaluation Section and Table 2).

Doses from breathing air (air submersion) are calculated for the nearest resident in each sector, while doses from drinking milk or eating foods produced near the plant are calculated for the areas with milk producing animals and gardens, respectively.

Air submersion doses were calculated for the same locations as in 1993, with the resulting values similar to those calculated in 1994.

Doses calculated for ingestion of home-grown foods changed in some sectors, reflecting shifts in the location of the nearest garden.

The changes were only very slight and did not significantly impact the doses caluclated in 1994.

For milk ingestion, projected annual doses were almost identical to those calculated in 1993.

The dose calculated for the consumption of milk from the farm in the NNH sector was slightly higher because of a decrease in the time the cows were fed stored feed.

Only two locations with milk producing animals were identified.

Samples are being taken from both of these farms.

Tables G-l, G-2, and G-3 show the comparative calculated doses for 1993 and 1994.

Table G-1 BROHNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident (Within 5 miles) mrem/year/reactor 1993 Surve 1994 Surve Sector N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW H

WNH NW NNH Approximate Distance (Miles) 2.08 1.61 2.56 1.42 2.56 1.33 5.03 4.26 2.82 2.60 3.15 2.56 1.52 2.84 2.27 0.95 Annual Dose 0.15 0.08 0.10 0.10 0.08 0.07 0.06 0.06 0.10 0.12 0.07 0.05 0.11 0.09 0.18 0.42 Approximate Distance (Miles) 1.23

1. 61 2.56 1.42 2.56 1.33 5.03 4.26 2.82 2.60 3.15 2.56 1.52 2.84 2.27 0.95 Annual Dose 0.22 0.08 0.10 0.10 0.08 0.07 0.06 0.06 0.10 0.12 0.07 0.05 0.11 0.09 0.18 0.42

Table G-2 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods (Nearest Garden Within 5 Miles) mrem/year/reactor 1993 Surve Approximate Sector Distance (Miles) Annual Dose 1994 Surve Approximate Distance (Miles) Annual Dose Number of Gardens Within 3 Miles

( 1994)

NNE NE ENE E

ESE SE SSE S

SSW SW WSW WNW NW NNW 2.56 3.41 2.75 1.70 2.60 2.46 a

4.36 2.82 2.84 3.88 2.70 1.70 a

2.72 1.14 3.08 1.01 1.23 2.44 1.84 2.19 0.97 2.25 2.35 0.69 0.60 1.26 3.41 9.96 1.23 3.41 2.75 1

~ 70 2.56 2.46 a

4.36 2.82 2.84 3,88 2.70 1.70 a

a 1.04 8.22 1.01 1.23 2.44 1.89 2.19 0.97 2.25 2.35 0.69 0.60 1

~ 26

10. 60 a.

Garden not identified in this sector.

e

Table G-3 BROHNS FERRY NUCLEAR PLANT Relative. Projected Annual Dose to Receptor Thyroid from Ingestion of Milk mrem/year/reactor Location Sector Approximate Distance (Miles)

Annual Dose 1993 1994 X/Q s/m'arm Bn' Farm B'NH 4.9 6.8 0.008 0.015 0.008 0.019 1.28 E -8 1.32 E -8 a.

Milk being sampled at these locations.

APPENDIX H

DATA TABLES Table H-1 DIRECT RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Brogans Ferry Nuclear Plant for Each Quarter 1994 mrem/Quarter' Di stance Mi 1 es 0-1 1-2 2-4 4-6 6

Avera e External Gamma Radiation Levels'st uarter 20.0 2 1.9 17.4 s 1.4 17.2 4 1.9 17.5 2 1.7 17.6 a 2.0 2nd uarter 16.7 a 1.1 15.4 x 1.1 14.1 a 1.3 14.3 s 1.2 14.1 2 0.8 3rd uarter 17.0 N 1.1 15.1 a 1.3 15.1 a 2.1 14.4 a 1.3 14.2 a 1.0 4th uarter 16.3 x 1.4 14.4 R 0.2 13.7 2 1.4 13.7 N 0.8 13.8 N 0.9

Average, 0-2 miles (onsite) 19.3 a 2.1 16.4 x 1.3 16.5 x 1.5 16.0 a 1.5

Average, 2 mi les (offsite) 17.5

1.9 14.2 a 1.1 14.5 a 1.4 13.7 a 1.0 a.

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

b.

Averages of the individual measurements in the set

~

1 standard deviation of the set.

-Table H-2 DIRECT RADIATION LEVELS Individual Stations Map Location Hemline 7

38 8

39 40 41 42 2

9 43 44 45 6

46 47 48 49 50 3

51 52 TLD Station Hwmber N-1 N-2 NNE-1 NNE-2 NNE-3 NE-1 NE-2 NE-3 ENE-1 ENE-2 E-1 E-2 E-3

, ESE-1 ESE-2 SE-1 SE-2 SSE-1 SSE-2 S-1 S-2 NRC Direction, S>fag go'ggregg 348 1

12 31 19 51 49 56 22 61 62 85 91 90 110 112 130 2

135 163 37 165 185 182 Approx.

Distance, hfilaa 1.0 5.0 0.9 0.7 5.2 0.8 5.0 10.9 0.9 6.2 0.8 5.2 24.2 0.9 3.0 0.5 5.4 5.1 7.5 3.1 4.8 rnrem/Quarter r 2nd Quarter3rd Quarter 4th Quarter October-P~c~g 1st Quarte January-

'EazlQSR4 21.7 16.6 20.2 20.8 16.9 21.2 20.8 18.8 20.8 18.9 21.5 18.1 18.5 18.5 20.0 20.2 18.5 18.3 19.2 18.4 16.3 April -

July-tun&9M9 mSu&9R4 18.6 13.2 16.6 16.8 13.2 17.7 16.0 14.7 16.2 14.1 16.6 14.0 14.1 13.8 14.5 14.6 13.0 13.1 14.0 14.1 12.5 18.6 13.1 16.0 18.0 13.8 17.6 16.1 14.8 17.4 15.7 18.0 15.1 15.2 14.9 15.5 15.8 13.4 14.0 14.4 14.6 12.3 18.1 13.0 16.2 17.0 13.3 18.1 16.3 14.7 16.3 15.0 17.1 16.9 14.6 14.5 15.4 15.5 13.2 13.4 14.3 14.6 12.5 NI8 Iih~

Annual

Exposure, mMmEear 77.0 55.9 69.0 72.6 57.2 74.6 69.2 63.0 70.7 63.7 73.2 64.1 62.4 61.7 65.4 66.1 58.1 58.8 61.9 61.7 53.6 '

Locations with TVAand NRC stations co-located.

Table H-2 DIRECT RADIATION LEVELS Individual Stations Map Location bLenbm 53 54 55 56 57 58 59 60 61 62 5

63 64 65 66 67 68 10 69 TLD Station Humber SSW-1 SSW-2 SW-1 SW-2 SW-3 WSW-1 WSW-2 WSW-3 W-1 W-2 W-3 W-4 WNW-1 WNW-2 NW-1 NW-2 NW-3 NNW-1 NNW-2 NNW-3 NRC QSatLo~o.*

15 13 12 10 Direction, Pmerees 203 199 228 219 224 244 251 257 275 268 275 265 291 293 326 321 310 331 331 339 Approx.

Distance, h5hs 3.0 4.4 1.9 4.7 6.0 2.7 5.1 10.5 1.9 4.7 31.3 32.1 3.3 4.4 2.2 5.3 13.8 1.0 1.7 5.2 EJEttoOLeJEaLE~d'ati~o~ee a

mrem/Quarter 1st Quarter 2nd Quarter3rd Quarter 4th Quarter January -

April -

July -

October-hLaLcM9%9J~ce 993 E~eJ~9 D~c199 16.1 12.3 12.2 11.4 18.2 14.3 14.7 13.3 18;2 14.6 14.2 14.1 18.7 14.2 13.9 13.7 16.5 13.0 13.0

'6.5 12.5 19.1 12.5 18.5 14.1 17.0 14.0 16.6' 13.0 13.1 12.8 18.5 14.5 14.1 14.6 17.7 14.4 12.7 13.4 17.2 13.2 12.8 12.9 19.6 15.2 14.8 15.3 18.2 14.5 13.9 14.3 18.6 14.4 14.4 13.7 13.9 15.4 15.3 15.5 14.1 15.1 15.0 14.8 12.7 14.3 13.8 13.3 15.2 17.6 17.1 16.4 15.3 16.9 17.0 14.2 15.0 15.5 14.3 Annual

Exposure, ILeen+e~t 52.0 60.5 61.1 60.5 56.7 60.6 63.6 55.5 61.7 58.2 56.1 64.9 60.9 61.1 60.1 59.0 54.1 66.3 65.6 59.0 Locations with TVAand NRC stations co-located.

Sum of available quarterly data normalized to 1 year for the annual exposure.

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENT'ATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN AIR FILTER PCI/M3 - 0.037 BQ/H3 NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMES'lONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)

NAME MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATION S MEAN (F)

RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED HEASUREMENTS GROSS ALPHA GROSS BETA 106 582 9.00E-04 9.76E-04(

2/

53) LM-1 BF 9.12E 1.04E-03 1.0 HILES N 2.00E-03 1.93E-02( 476/ 476)

LH1 BF NORTHWEST 6.56E 3 '3E-02 1.0 HILE N 9.76E.04(

2/

53) 53 VALUES < LLD 9.12E 1.04E-03 1.98E-02(

53/

53) 1.96E-02(

106/ 106) 9.15E 3.33E-02 7.25E 3.35E-02 GAMMA SCAN (GELI) 154 BE-7 Bl-212 Bl-214 K-40 PB-212 PB-214 TL-208 SR 89 2.00E-02 2.00E-02 5.00E-03 4.00E-02 5.00E-03 5.00E-03 2.00E-03 9.83E-02(

126/ 126) 6.00E 1.41E-01 4.25E-01(

8/ 126) 1.47E 8.52E-01 4.42E-02(

16/ 126) 5.00E 1.36E-01 4.60E-02(

1/ 126) 4.60E 4.60E-02 3.49E-01(

9/ 126) 8.97E 7.62E-01 4.08E-02(

15/ 126) 5.00E 1.40E-01 1.29E-01(

9/ 126) 2.70E-OZ-2.75E-01 PH-1 ROGERSVILLE AL 13.8 HILES NW LH2 BF NORTH 0.9 MILE NNE LM4 BF TRAILER P 1.7 HILES NNW LH-68F BAKER BOTTOH 3.0 MILES SSW LH2 BF NORTH 0.9 MILE NNE LH4 BF TRAILER P 1.7 HILES NNW LM2 BF NORTH 0.9 HILE NNE 1.02E-01(

14/

14) 7.31E 1.22E-01 8.52E-01(

1/

14) 8.52E 8.52E-01 1.25E-01(

1/

14) 1.25E 1.25E-01 4.60E-OZ(

1/

14) 4.60E 4.60E-02 7.62E-01(

1/

14) 7.62E.01-7.62E-01 7.27E-02(

2/

14) 5.00E.03-1.40E-01 2.75E-01(

1/

14) 2.75E 2.75E-01 9.79E-02(

28/

28) 7.05E 1.30E-01 1.28E-01(

2/

28) 1.00E 1.56E-01 3.40E-02(

2/

28) 1.37E 5.43E-02 28 VALUES < LLD 1 ~ 04E-01(

2/

28) 7.00E 1.37E-01 2.23E-OZ(

2/

28) 1.09E 3.37E-02 3.63E-02(

2/

28) 2.38E 4.88E-02 SR 90 AM 241 CH 244 1.10E-03 3 VALUES < LLD 4.00E-04 3 VALUES < LLD 2.50E-05 4 VALUES < LLD 2.50E-05 4 VALUES < LLD 3 VALUES < LLD 3 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD NOTE:

1.

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

2.

MEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY.

FRACTION OF DETECTABLE HEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATIOH WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN AIR FILTER PCI/M3 - 0.037 BQ/M3 NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD: 'l994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS

'LOCATION WITH HIGHEST ANHUAL MEAN DETECTION MEAN (F)

NAME MEAN (F)

(LLO)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAH (F)

RANGE SEE NOTE 2 NUHBER OF NONROUTINE REPORTED MEASUREMENTS PU 239,240 PU 238 CM 242 8

2.50E-05 4 VALUES < LLD 2.50E-05 4 VALUES < LLD 2.50E-05 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD NOTE:

1.

NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1 NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY.

FRACTION OF DETECTABLE MEASUREHEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENHESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CHARCOAL FILTER PCI/M3 - 0.037 BQ/M3 NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESI'ONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTIHG PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH NIGHEST ANNUAL MEAN DETECTIOH MEAN (F)

NAHE MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)

RANGE SEE NOTE 2 NUHBER OF NONROUTINE

REPORTED HEASUREMENTS GAMHA SCAN (GELI) 582 BI-214 K-40 5.00E-02 5.51E-02(

1/ 476)

LM1 BF NORTHWEST 5.51E 5.51E-02 1 ~ 0 MILE N 3.00E-01 3.19E-01(

3/ 476)

LM3 BF NORTHEAST 3.08E 3.39E-01 1.0 HILE ENE

5.51E-02(

1/

53) 106 VALUES < LLD 5.51E 5.51E-02 3.24E-OI (

2/

53) 3.17E.01(

1/ 106) 3.08E-O'I-3.39E-01 3.17E 3.17E-01 NOTE:

1.

NOMINAL LOWER 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).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION NESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN MILK PCI/L - 0.037 BQ/L NAME OF FACILITY: BRONNS FERRY NUCLEAR PLANI'OCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LSIER LIMIT ALL OF INDICATOR LOCATIONS LOCATION HITH HIGHEST AHNUAL MEAN DETECTION MEAN;(F)

HAME MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATION S MEAN (F)

RANGE SEE NOTE 2 NUMBER OF NOHROUTINE REPORTED HEASUREMENTS IODINE-131 104 4.00E-01 52 VALUES < LLD GAMMA SCAN (GELI) 104 CS-137 52 VALUES < LLD K-40 SR 89 52 5.DOE+00 5.70E+00(

1/

52) SMITH/BENNETT FARH 5.70E+00(

1/

26) 52 VALUES < LLD 5.70E+00-5.70E+00 5.0 MILES N 5.70E+00- 5.70E+00 1.DOE+02 1.34E+03(

52/

52)

BROOKS FARM 6.8 MILE 1.35E+03(

26/

26) 1.34E+03(

52/

52) 1.13E+03-1.56E+03 S

NNM 1 ~ 16E+03-1.51E+03 1.21E+03-1.53E+03 SR 90 2.DOE+00 26 VALUES < LLD 26 VALUES < LLD 52 2.DOE+00 2.48E+00(

3/

26)

BROOKS FARH 6.8 HILE 2.85E+00(

1/

13) 2.49E+00(

4/

26) 2.01E+00-2.85E+00 S

NNW 2.85E+00- 2.85E+00 2.08E+00-2.91E+00 NOTE:

1.

NOMIHAL LONER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE:

2.

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

0

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION MESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN VEGETATION PCI/KG - 0.037 BQ/KG (WET WEIGHT)

HAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAHA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE ANO TOTAL NUMBER OF ANALYSIS PERFORHED LOMER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN DETECI'ION HEAN (F)

NAHE HEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE HOl'E 2 SEE NO'IE 2 CONTROL LOCATIONS HEAN (F)

RANGE SEE NOTE 2 NUHBER OF NONROUTINE REPORTED HEASUREHENTS IODINE-131 26 6.DOE+00 13 VALUES < LLD 13 VALUES < LLD GAMMA SCAN (GELI) 26 BE-7 K-40 PB-212 SR 89 2.DOE+02 4.DOE+02 4.DOE+01 1.69E+03(

13/

13)

TERRY FARM 2.50E+02-5.56E+03 3.2 HILES MNW 4.82E+03(

13/

13)

TERRY FARH 2.55E+03-8.72E+03 3.2 HILES MNM 5.18E+01(

2/

13)

TERRY FARH 4.80E+01-5.56E+01 3.2 HILES WNM 1.69E+03(

'l3/

13) 2.50E+02-5.56E+03 4.82E+03(

13/

13) 2.55Ei03-8.72E+03 5.18E+01(

2/

13) 4.80E+01-5.56E+01 1.62E+03(

12/

13) 3.19E+02-5.61E+03 4.71E+03(

13/

13) 2.08E+03-7.85E+03 6.17E+01(

1/

13) 6.17E>01-6.17E+01 SR 90 3 '0E+01 4 VALUES < LLD 8

1.20E+01 2.51E+01(

3/

4)

TERRY FARH 1.84E+01-2.87E+01 3.2 HILES WNM 4 VALUES < LLD 2.51E+01(

3/

4) 1.40E+01(

1/

4) 1.84E+01-2.87E+01 1.40E+01-1.40E+01 NOTE:

1.

NOHINAL LOMER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:

2.

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

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

NAHE OF FACILITY: BROWHS FERRY HUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAHA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AHD TOTAL HUHBER OF ANALYSIS PERFORHED LOWER LIHIT ALL OF INDICATOR LOCATIONS 'OCATION WITH HIGHEST ANNUAL HEAH DETECTION HEAN (F)

HAHE MEAN (F)

(LLD)

RANGE DISTANCE AND DI RECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)

RAHGE SEE NOTE 2 NUMBER OF NOHROUTINE REPORTED MEASUREHENTS GROSS ALPHA NOT ESTAB 3.58E+00(

1/

1)

LH1 BF NORTHWEST 3.58E+00- 3.58E+00 1.0 MILE N 3.58E+00(

1/

1) 4.32E+00(

1/

1) 3.58E+00-3.58E+00 4.32E+00-4.32E+00 GAMHA SCAN (GELI) 1'I AC-228 BE-7 81-212 BI-214 CS-137 K-40 PB-212

, PB-214 RA-224 RA-226 TL-208 SR 89 2.50E-01 2.50E-01 4.50E-01 1 '0E-01 3.00E-02 7.50E-01 1.00E-01 1.50E-01 7.50E-01 1.50E-01 6.00E-02 1.07E+00(

5.57E 3.54E-01(

3.33E 1.08E+00(

5.62E 8.33E-01(

5.73E 3.41E-01(

1.41E 4.96E+00(

2.73E+00-1.00E+00(

5.57E 9.22E-01(

6.31E 1.11E+00(

9.37E 8.33E-01(

5.73E 3.38E-01(

1.80E 9/

9) 1.47E+00 2/

9) 3.75E-01 9/

9) 1.39E+00 9/

9) 1.12E+00 9/

9) 6.21E-01 9/

9) 7.86E+00 9/

9) 1.35E+00 9/

9) 1.27E+00 6/

9) 1.35E+00 9/

9) 1.12E+00 9/

9) 4.51E-01 LH4 BF TRAILER P 1.7 HILES NHW PH-2 BF ATHENS AL 10.9 HILES NE LH1 BF NORTHWEST

'1.0 HILE N LH4 BF TRAILER P 1.7 HILES NHW PH-2 BF ATHENS AL 10.9 HILES NE LH4 BF TRAILER P 1.7 MILES HHW LH1 BF NOR'THWEST 1.0 HILE N LM4 BF TRAILER P 1.7 MILES NNW LM4 BF TRAILER P

'l.7 MILES NHW LH4 BF TRAILER P 1 7 HILES HHW LH2 BF NORTH 0.9 HILE NNE 1.47E+00(

1/

1) 1.47E+00-1.47E+00 3.75E-01(

1/

1) 3.75E 3.75E-01 1.39E+00(

1/

1) 1.39E+00-1.39E+00 1.12E+00(

1/

1) 1.12E+00-1.12E+00 6.21E-01(

1/

1) 6.21E 6.21E-01 7.86E+00(

1/

1) 7.86E+00-7.86E+00 1.35E+00(

1/

1) 1.35E+00-1.35E+00 1.27E+00(

1/

1) 1.27E+00-'.27E+00 1.35E+00(

1/

1) 1.35E+00-1.35E+00 1.12E+00(

1/

1) 1.12E+00-1.12E+00 4.51E-01(

1/

1) 4.51E 4.51E-01 9.80E-01(

8.52E 5.35E-01(

5.35E 9.56E-01(

7.77E 9.80E-01(

7.35E 2.78E-01(

2.25E 01-5.36Et00(

4.70E+00-8.86E-01(

7.95E 1.08E+00(

7.93E 1 ~ 12E+00(

1.12E+00-9.80E-01(

7.35E 2.98E-01(

2.52E-01.

2/

2) 1.11E+00 1/

2) 5.35E-01 2/

2) 1.14E+00 2/

2) 1.22E+00 2/

2) 3.31E-01 2/

2) 6.02E+00 2/

2) 9.77E-01 2/

2) 1.36E+00 1/

2) 1.12E+00 2/

2) 1.22E+00 2/

2) 3.44E-01 SR 90 1.60E+00 9 VALUES < LLD 4.00E-01 9 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD NOTE:

1.

HOMINAL LOWER LIHIT OF DETEC'PION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:

2.

HEAH AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY.

FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORIHG AND INSTRUHENTATION MESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SOIL PCI/GM - 0.037 BQ/G'(DRY HEIGHT)

NAME OF FACILITY: BROMNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS

'ERFORMED LOMER LIMIT ALL OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)

NAME MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECT IOH RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)

RANGE SEE NOTE 2 NUMBER OF NONROUT INE REPORTED MEASUREMENTS PU 238 PU 239,240 AH 241 NOT ESTAB 1 VALUES < LLD LM1 BF NORTHWEST 1.0 HILE N NOT ESTAB 1.55E-02(

1/

1)

LM1 BF NORTHNEST 1.55E 1.55E-02

'1.0 MILE N 1 VALUES < LLD 1 VALUES < LLD 1.55E-02(

1/

1) 1 VALUES < LLD 1.55E 1.55E-02 CH 242 2

NOT ESTAB 7.73E-03(

1/

1)

LM1 BF NORTHNEST 7.73E.03(

1/

1) 1 VALUES < LLD 7.73E 7.73E-03 1.0 MILE N 7.73E 7.73E-03 CM 244 2

NOT ESTAB 1 VALUES < LLD LH1 BF NORTHNEST 1.0 MILE N NOT ESTAB 1 VALUES < LLD LM1 BF NORTKIIEST 1.0 MILE N 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD HOTE:

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 DETECI'ABLE HEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

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

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAHA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)

HAME MEAN (F)

(LLD)

RANGE DISTANCE AHD DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NO'IE 2 COHTROL LOCATIOHS MEAN (F)

RANGE SEE NOTE 2 NUMBER OF

'NONROUTINE REPORTED MEASUREHENTS GAMMA SCAN (GELI) 2 K;40 2.50E+02 9.15E+02(

1/

1) 7 MILES NNW 9.15E+02-9.15E+02 9.15E+02(

'I/

1) 5.85E+02(

1/

1) 9.15E+02-9.15E+02 5.85E+02-5.85E+02 NOTE:

1.

NOMINAL LOWER 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).

TENNESSEE VALLEY AUTHORITY EHVIRONMENTAL RADIOLOGICAL MONITORING AND IHSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN BEEF PCI/KG - 0.037 BQ/KG (WEI'T)

HAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50.259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)

NAME MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)

RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 2 Kr40 2.DOE+02 2.35E+03(

1/

1) SHITH/BEHNETT FARH 2.35E+03-2.35E+03 5.0 MILES N 2.35E+03(

1/

1). 2-57E+03(

1/

1) 2.35E+03-2.35E+03 2.57E+03-2.57E+03 NOTE:

1.

NOMINAL LOWER 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 IH PARENTHESES (F).

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

HAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)

NAME

, MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE HOTE 2 CONTROL LOCATION S MEAN (F)

RANGE SEE NOTE 2 NUHBER OF NDNROU'TINE REPORTED HEASUREHENTS GAMMA SCAN (GELI)

K-40 2.50E+02

'1.86E+03(

1/

I) 7 MILES NNW 1.86E+03-1.86E+03 1.86E+03(

1/

1) 8.66E+02(

1/

1) 1.86Ei03-1.86E+03 8.66E+02.

8.66E+02 NOTE:

1.

NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY.

FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

t I

tD

TENNESSEE VALLEY AUTHORITY ENVIROHNEHTAL RADIOLOGICAL NONITORIHG AND INSTRUNENTATION MESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CORN PCI/KG. 0.037 BQ/KG (MET MT)

NANE OF FACILITY: BROMNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTOHE ALABANA DOCKET HO.:

50-259,260,296 REPORTIHG PERIOD: 1994 TYPE AHD TOTAL NUNBER OF ANALYSIS PERFORNED LONER LIHIT ALL OF INDICATOR LOCATIONS LOCATION MITN NIGHEST ANNUAL'HEAH DETECTIOH NEAN (F)

HANE NEAH (F)

(LLD)

RANGE DISTANCE AHD DIRECTION RANGE SEE NOTE 1

SEE HOTE 2 SEE NOTE 2 CONTROL LOCATIONS NEAN (F)

RANGE SEE NOTE 2 HUHBER OF NOHROUTINE REPORTED NEASUREHEHTS GANNA SCAN (GELI) 2 K.-40 2.50E+02 1.92E+03(

1/

1) 7 MlLES NNM 1.92E+03-1.92E+03

'1.92E+03(

1/

1) 2.45E+03(

1/

1) 1.92E+03-1.92E+03 2.45E+03-2.45E+03 NOTE:

1 ~

NONIHAL LOMER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:

2.

NEAN AHD RANGE BASED UPON DETECTABLE HEASUREHEHTS ONLY.

FRACTION OF DETECTABLE HEASURENEHTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY

\\

RADIOACTIVITY IN PEAS PCI/KG - 0.037 BQ/KG (WET WT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLAHT LOCATION OF FACILITY: LIMESTONE ALABAHA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F:)

HAME MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN,.(F)

RANGE SEE NOTE 2 NUMBER OF NONROUT IHE REPORTED MEASUREMEHTS GAMMA SCAN (GELI) 2 K-40 2.50E+02 4.09E+03(

1/

1) 7 HILES NNW 4.09E+03-4.09E+03 4-09E+03(

1/

1) 2-59E+03(

1/

1) 4.09E+03-4.09Et03 2.59E+03-2.59E+03 NOTE:

1.

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

2.

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

I 00 I

TENNESSEE VALLEY AUTHORITY ENVIRONMEHTAL RADIOLOGICAL MONITORING AND IHSTRUMEHTATIOH WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN POTATOES PCI/KG - 0.037 BO/KG (WET WT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET HO.:

50-259,260,296 REPORTIHG PERIOD:

1994 TYPE AND TOl'AL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN'ETECTION MEAN (F)

NAME MEAN (F)

(LLD)

RANGE DISTANCE AHD DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONI'ROL LOCATIOHS MEAN (F)

RANGE SEE NOTE 2 HUMBER OF NONROUTIHE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 2 K-40 2.50E+02 2.94E+03(

1/

1) 7 MILES HHW 2.94E+03-2.94E+03 2.94E+03(

1/

1) 3.05E+03(

1/

1) 2.94E+03-2.94E+03 3.05E+03-3.05E+03 NOTE:

1.

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

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREMEHTS ONLY.

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY EHVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADiOLOGICAL LABORATORY RADIOACTIVITY IN TOMATOES PCI/KG - 0.037 BQ/KG (WET WT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAHA DOCKET NO.:

50-259,260,296 REPORTING PERIOD: 1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST AHNUAL MEAN DETECTION MEAN (F) i NAME MEAN (F)

(LLD)

RAHGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIOHS HEAN (F)

RANGE SEE NOTE 2 NUMBER OF NOHROUTINE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 2 K.-40 2.50E+02 2.17E+03(

1/

1) 7 MILES NNW 2.17E+03-2.17E+03 2.17E+03(

1/

1) 2.28E+03(

1/

1) 2.17E+03-2 ~ 17E+03 2.28E+03-2.28E+03 I

CD CD I

NOTE:

1.

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

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY.

FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PAREHTHESES (F).

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

PCI/L - 0.037 BQ/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS.

PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAH DETECTIOH MEAN (F)

NAME HEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)

RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS GROSS BETA 39 1.90E+00 2.73E+00(

22/

26)

TRH 293.5 1.92E+00- 4.23E+00 2.74E+00(

12/

'13) 2.44E+00(

13/

13) 1.92E+00- 4.23E+00 1.96E+00-2.95E+00 GAMMA SCAN (GELI) 39 SR 89 12 SR 90 12 TRITIUM 12 5.DOE+00 26 VALUES < LLD 5 O BOE+00 8 VALUES < LLD 2.DOE+00 8 VALUES < LLD 3.DOE+02 8 VALUES < LLD 13 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD NOTE:

1.

NOHIHAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1.

NOTE:

2.

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

TEHNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MOHITORING AND INSTRUMENTATIOH WESTERH AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH PUBLIC WATER(Total)

PCI/L - 0.037 BQ/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAHA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOtAL NUMBER OF ANALYSIS PERFORMED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH'IGHEST ANNUAL MEAN DETECTION MEAN.(F)

NAME MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)

RANGE SEE NOTE 2 NUHBER OF NONROUI'INE "

REPORTED, MEASUREMEHtS GROSS BEI'A 76 1.90E+00 2.40E+00(

35/

50)

CHAMPION PAPER 1.91E+00- 3.49E+00 TRM 282.6 2.50E+00(

9/

12) 2.43E+00(

21/

26) 2.13E+00- 3.49E+00 1.92E+00- 3.62E+00 GAMHA SCAN (GELI) 78 SR 89 24 5.DOE+00 52 VALUES < LLD 26 VALUES < LLD SR 90 TR IT IUH 5 ~ OOE<00 16 VALUES < LLD 24 2.DOE+00 16 VALUES < LLD 24 3.DOE+02 16 VALUES < LLD 8 VALUES < LLD 8 VALUES < LLD 8 VALUES < LLD NOTE:

1.

NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1 NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREHEHTS ONLY.

FRACTION OF DETECTABLE HEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORIHG AHD INSTRUMENTATION

'WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH WELL WATER(Total)

PCI/L - 0.037 BQ/L HAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET HO.:

50.259,260,296 REPORTIHG PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION 'WITH HIGHEST ANNUAL MEAN DETECTIOH MEAN (F)

NAME MEAN (F)

(LLD)

RANGE DISTANCE AHD DIRECTION RANGE SEE NOTE

'I SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIOHS MEAN (F)

RANGE SEE NOTE 2 NUMBER OF HOHROUTIHE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 26 81-214 PB-214 SR 89 2.00E+01 4.91E+01(

2/

13)

BFN WELL ¹6 2.90E+01-6.91E+01 0.02 MILES W 2.DOE+01 6.22E+Ol(

1/

13)

BFN WELL ¹6 6.22E+01-6.22E+01 0.02 MILES W 4.91E+01(

2/

13) 3.18E+02(

13/

13) 2.90E+01-6.91E+01 1.91E+02-5.95E+02 6.22E+01(

1/

13) 3.12E+02(

13/

13) 6.22E+01-6.22E+01 1.79E+02-5.75E+02 SR 90 TRITIUM 5.DOE+00 4 VALUES < LLD 8

2.DOE+00 4 VALUES < LLD 3 ~ OOE+02 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD NOTE:

1.

NOMINAL LOWER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IH TABLE E-1.

NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY-FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIOHS IS INDICATED IN PARENTHESES (F).

C)

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY I'ADIOACI'IVITY IN CRAPPIE FLESH PCI/GH - 0.037 BQ/G*(DRY WEIGHT)

NAME OF FACILITY: BRDWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUHBER

,OF ANALYSIS PERFORMED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST AHHUAL HEAN DETECTION MEAN (F)

,NAHE MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)

RANGE SEE NOTE 2 NUHBER OF NONROUTINE REPORTED MEASUREMEHTS GAMHA SCAN (GELI) 4 CS-137 K-40 3.00E-02 6.71E-02(

1/

2)

WHEELER RES 6.71E 6.71E-02 TRH 275-349 4.00E-01 1.50E+01(

2/

2) WHEELER RES 1.44E+01-1.56E+01 TRH 275-349 6.71E-02(

1/

2) 7.13E-02(

1/

2) 6.71E 6.71E-02 7.13E 7.13E-02 1.50E+01(

2/

2) 1 ~ 50E+01(

2/

2) 1.44E+01-1.56E+01 1.36E+01-1.63E+01 NOTE:

1.

NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1

~

NOTE:

2.

MEAH AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY-FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PAREHTHESES (F).

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION l!ESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SMALLMOUTH BUFFALO FLESH PCI/GM - 0.037 BQ/G (DRY NEIGHT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOMER LIHIT ALL OF INDICATOR LOCATIONS LOCATIOH NITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)

NAHE MEAN (F)

(LLD)

RANGE DISTANCE AND DI RECTION RANGE SEE NOTE I SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAR (F),

RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 4 K-40 4.00E-01 9.36E+00(

2/

2) MHEELER RES 8.93E+00- 9.79E+00 TRH 275-349 9.36E+00(

2/

2) 8.65E+00(

2/

2) 8.93E+00- 9.79E+00 7.83E+00- 9.47E+00 I

IC)

I NOTE:

1.

NOMINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-I NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY.

FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)-

TENNESSEE VALLEY AU'IHORITY ENVIRONMENTAL RADIOLOGICAL HONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SHALLMOUTH BUFFALO WHOLE PCI/GH - 0.037 BQ/G*(DRY WEIGHT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN DETECTION MEAN (F)

NAHE MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)

RANGE SEE NOTE 2 NUHBER OF NONROUTINE REPORTED HEASUREHENTS GAMHA SCAN (GELI) 4 K-40 4 'OE-01 5.DOE+00(

2/

2) WHEELER RES 4.94E+00-5.06E+00 TRH 275-349 5.DOE+00(

2/

2) 7.13E+00(

2/

2) 4.94Ei00- 5.06E+00 5.87E+00- 8.39E+00 I

C>

I NOTE:

1.

NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.

FRACTION OF DETECTABLE HEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

I CO

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SEDIHENT PCI/GH - 0.037 BQ/G (DRY WEIGHT)

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF 'FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F),.

NAHE MEAN (F)

(LLD)

RANGE-.

DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CON'IROL LOCATIONS MEAN (F)

RANGE SEE NOTE 2 NUMBER OF NONROUT I NE REPORTED MEASUREHENTS GAMHA SCAN (GELI) 10 AC-228 BE-7 81-212 81-214 C0.60 CS-137 K.40 PB-212 PB-214 RA-224 RA-226 TL-208 SR 89 2.50E-01 2.50E-01 4.50E-01 1.50E-01 3.00E-02 3.00E-02 7.50E-01 1.00E-01 1.50E-01 7.50E-01 1.50E-01 6.00E-02 1.33E+00(

6/

6)

TRH 293.7 9.78E 1.55E+00 BFN DISCHARGE 4.63E-01(

3/.

6)

TRM 293.7 3.35E 5.48E-01 BFN DISCHARGE 1.36E+00(

6/

6)

TRH 293.7 1.03E+00-1.69E+00 BFN DISCHARGE 1.06E+00(

6/

6)

TRM 293.7 6.82E 1.37E+00 BFN DISCHARGE 1.47E-01(

5/

6)

TRM 288.78 5.69E 4.33E-01 5.12E-01(

6/

6)

TRH 293.7 3.19E 7.10E-01 BFN DISCHARGE 1.13E+01(

6/

6) TRH 293.7 7.03E+00-1.31E+01 BFN DISCHARGE 1.23E+00(

6/

6)

TRM 293.7 8.50E 1.49E+00 BFN DISCHARGE 1.13E+00(

6/

6)

TRM 293.7 7.55E 1.48E+00 BFN DISCHARGE 1.33E+00(

6/

6)

TRH 293.7 7.74E-Ol-1.62E+00 BFN DISCHARGE 9.94E-01(

5/

6)

TRH 293.7 6.82E 1.15E+00 BFN DiSCHARGE 4.25E-01(

6/

6)

TRM 293.7 3.13E 4.99E-01 BFN DISCHARGE 1.52E+00(

1.49E+00-5.48E-01(

5.48E 1.46E+00(

1.46E+00-1.15E+00(

1.14E+00-2.49E-01(

6.55E 5.24E-01(

4.68E 1.31E+01(

1.31E<01-

'1.37E+00(

1.33Ei00-1 ~ 20E+00(

1.18E+00-1.48E+00(

1.45E+00-

1. 15E+00(

1.14Ei00-4.76E-01(

4.69E.01-2/

2) 1 ~ 55E+00 1/

2) 5.48E-01 2/

2) 1.47E+00 2/

2) 1.15E+00 2/

2) 4.33E-01 2/

2) 5.81E-01 2/

2) 1.31E+01 2/

2) 1.41E+00 2/

2) 1.21E+00 2/

2) 1.50E+00 2/

2) 1.15E+00 2/

2) 4.83E-01 1.16E+00(

9.68E 6.46E-01(

4.90E 1.15E+00(

8.25E 8.98E-01(

6.78E 4 VALUES 1.96E-01(

1.49E 1.24E+01(

1 ~ 13E+01-1.10E+00(

8.60E 9.88E-01(

7.26E 1.19E+00(

9.31E 8.98E-01(

6.78E 3.81E-01(

2.91E 4/

4) 1.35E+00 3/

4) 8.97E-01 4/

4) 1.41E+00 4/

4) 1.08E+00

< LLD 4/

4) 2.68E-01 4/

4) 1.35Ei01 4/

4) 1.29E+00 4/

4) 1.18E+00 4/

4) 1.40E+00 4/

4) 1.08E+00 4/

4) 4.54E-01 SR 90 10 1.60E+00 6 VALUES < LLD 4 VALUES < LLD 10 4.00E-01 6.73E-01(

3/

6)

TRH 277.98 4.43E 8.49E-01 8.49E-01(

1/

2) 5.66E-01(

1/

4) 8.49E 8.49E-01 5.66E 5.66E-Ol NOTE:

1.

NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY'RACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENI'HESES (F).

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

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1994 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)

NAHE MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)

RANGE SEE NOTE 2 NUHBER OF NONROUTINE REPORTED MEASUREHENTS GAMHA SCAN (GELI) 4 Bl-214 PB-212 PB-214 5.00E-01 3.00E-01 1 'OE-01 2.62E+00(

1/

2)

DOWNSTREAM LOCATION 2.62E+00-2.62E+00 DOWNSTREAM 4.32E-01(

1/

2)

DOWNSTREAM LOCATION 4.32E 4.32E-01 DOWNSTREAM 2.71E+00(

1/

2)

DOWNSTREAM LOCATION 2.71E+00-2.71E+00 DOWNSTREAM 2.62E+00(

1/

2) 2.62E+00-2.62E+00 4.32E-01(

1/

2) 4.32E 4.32E-01 2.71E+00(

1/

2) 2.71E+00- 2.71E+00 1.05E+00(

1/

2) 1.05E+00-1.05E+00 2 VALUES c LLD 8.43E-01(

1/

2) 8.43E 8.43E-01 NOTE:

1.

NOHINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:

2.

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

Direct Radiation Levels Browns Ferry Nuclear Plant 24 22 20 O

18 R

16 (0

E 14 12 10 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year/Quarter p On-Site + Off-Site

Direct Radiation Levels Four Quarter Moving Average 22 20 6)

(6

~

18 16 E

1 E

14 12 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year/Quarter On-Site +

Off-Site Browns Ferry Nuclear Plant

Direct Radiation Levels Watts Bar Nuclear Plant 24 g

20 18 (D

E 16 E

14 L+

12 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year/Quarter w On-Site k-Off-Site

Direct Radiation Levels Watts Bar Nuclear Plant - Four Quarter Moving Average 24 22 20

'a 18 (0

16 L

E 14 12 78 79 80 81 82 83 84 85 86 87 88 89 90

. 91 92 93 94 Year/Quarter

+ On-Site + Off-Site

Annual Average Gross Beta Activity AirFilters (pCi/Cubic Meter) 0.25 0.2 Initial plant operation in August 1973.

0.15 O

O 01 O

0.05 Preoperational Average 68 70 72 73o 75 77 79 81 83 85 87 89 91 93 69 71 73p 74 76 78 80 82 84 86 88 90 92 94 Year M Indicator II Control Browns Ferry Nuclear Plant

Annual Average:

Sr-90 in Milk 20 1'5 Initial plant operation in August 1973.

~

10 0

68 70 72 73o 75 77 79 81 83 85 87 89 91 93 69 71 73p 74 76 78 80 82 84 86 88 90 92 94 Year

~ Indicator

~ Control Preoperational Average Browns Ferry Nuclear Plant

Annual Average:

Cs-137 in Soil 2.5 Initial plant operation in August 1973.

E GJ U

1.5 O

0.5 68 70 72 73o 75 77 79 81 83 85 87 89 91 93 69 71 73p 74 76 78 80 82 84 86 88 90 92 94 Year

~ Indicator

+- Control Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to GeLi in 1977.

Annual Average Gross Beta Activity Surface Water, pCi/Liter Initial plant operation in August 1973.

Ql 4

U CL 68 69 70 71 7273p73o74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year

~ Indicator

-+ Control Preoperational Average Browns Ferry Nuclear Plant Note: No gross beta measurements were made in 1978.

Annual Average Gross Beta Activity Drinking Water, pCi/Liter Initial plant operation in August 1973.

k~g 68 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year w Indicator

-i-Control Preoperational Average Browns Ferry Nuclear Plant

Annual Average Cs-137 in Fish: Crappie 0.5 0.4 Initial plant operation in August 1973.

0.3 O~ 0.2 0.1 0

69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86-87 88 89 90 91 92 93 94 Year w Downstream

~ Upstream Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to GeLi in 1978.

Annual Average Cs-137 in Fish: Smallmouth Buffalo, Flesh 0.25 0.2 Initial plant operation in August 1973.

E 0.15 L

O 0.1 0.05 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year

~ Downstream

+- Upstream Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to GeLi in 1978.

Annual Average Cs-137 in Fish: Smallmouth Buffalo, Whole 0.14 0.12 Initial plant operation in August 1973.

0.1 E 008 1U)

~ 006 0.04 0.02 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year w Downstream

+- Upstream Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to GeLi in 1978.

Annual Average Cs-1 37 in Sediment Initial plant operation in August 1973.

3 O~ 2 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year

~ Downstream

~ Upstream Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to Geii in 1977.

Annual Average Co-60 in Sediment 0.8 0.6 Initial plant operation in August 1973.

E CJ cn 04 0

CL 0.2 0

69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year

~ Downstream

~ Upstream Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to GeLi in 1977.

0

ML18038B263

Text

SUMMARY

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